NUREG/CR-6490

ANL-96/13

Vol. 1

Nuclear Power Plant

Generic Aging

Lessons Learned (GALL)

Main Report and Appendix A

Prepared by

K. E. Kasza, D.R. Diercks, J. W Holland, S. U. Choi, J. L. Binder, ANL

W. J. Shack, 0. K. Chopra, D. C. Ma, A. Erdernir, ANL

J. L. Edson, L. C. Meyer, E. W Roberts, INEL

Argonne National Laboratory

Idaho National Engineering Laboratory

Lockheed Idaho Technologies Company

Prepared for

U.S. Nuclear Regulatory Commission
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NUREG/CR-6490

ANL-96/13

Vol. 1

Nuclear Power Plant

Generic Aging

Lessons Learned (GALL)

Main Report and Appendix A

Manuscript Completed: October 1996

Date Published: December 1996

Prepared by

K. E. Kasza, D. R. Diercks, J. W. Holland, S. U. Choi, J. L. Binder, ANL

W. J. Shack, 0. K. Chopra, D. C. Ma, A. Erdemir, ANL

J. L. Edson, L. C. Meyer, E. W. Roberts, INEL

Argonne National Laboratory

9700 South Cass Avenue

Argonne, IL 60439

Idaho National Engineering Laboratory

Lockheed Idaho Technologies Company

Idaho Falls, ID 83415

Prepared for

License Renewal Project Directorate

Office of Nuclear Reactor Regulation

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

NRC Job Codes J2076 and L1606

Nuclear Power Plant Generic Aging Lessons Learned:

- Mechanical, Structural, and Thermal-Hydraulic Components and Systems

- Electrical Components and Systems

by

K. E. Kasza, D. R. Diercks, J. W. Holland, S. U. Choi, J. L. Binder,

W. J. Shack, 0. K. Chopra, D. C. Ma, A. Erdemir,

J. L. Edson, L. C. Meyer, and E. W. Roberts

Abstract

The purpose of this generic aging lessons learned (GALL) review is to provide a systematic

review of plant aging information in order to assess materials and component aging issues

related to continued operation and license renewal of operating reactors. Literature on

mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of

97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information

Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and

Resources Council Industry Reports (NUMARC IRs) and literature on electrical components

and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information

Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed.

The results of these reviews were systematized using a standardized GALL tabular format and

standardized definitions of aging-related degradation mechanisms and effects. The tables are

included in volumes 1 and 2 of this report. A computerized data base has also been developed

for all review tables and can be used to expedite the search for desired information on

structures, components, and relevant aging effects. A survey of the GALL tables reveals that

all ongoing significant component aging issues are currently being addressed by the regulatory

process. However, the aging of what are termed passive components has been highlighted for

continued scrutiny.

... iii NUREG/CR-6490

Contents

Volume 1

Executive Summary ................................................................................................... vii

Acknowledgments ...................................................................................................... viii

List of Acronyms ........................................................................................................ ix

1 Introduction ........................................................................................................ 1

2 Description of Review Process .............................................................................. 2

3 Summary and Observations ................................................................................ 5

3.1 Mechanical, Structural, and Thermal-Hydraulic Components

and Systems ................................................................................................ 5

3.2 Electrical Components and Systems ............................................................. 8

References .................................................................................................................. 50

Appendix A: GALL Literature Review Tables - NPAR Reports, NRC Generic Letters,

Information Notices, Licensee Event Reports, and NRC Bulletins ........... 51

Volume 2

Appendix B: Gall Literature Review Tables - NUMARC Industry Reports

v NUREG/CR-6490
Tables

Tables 2-7 are separated into two parts depending on whether reviewed material pertains to

Mechanical, Structural, and Thermal-Hydraulic Components and Systems or to Electrical

Components and Systems.

Table 8 is a composite of all Age-Related Degradation mechanisms used in reviewing both

categories of material.

1 Selected Examples of Aging Issues Significant to Passive Components ...................... 6

2a NPAR Reports Reviewed: Mechanical, Structural, and Thermal-Hydraulic

Com ponents and System s ........................................................................................ 9

2b NPAR Reports Reviewed: Electrical Components and Systems ................................ 16

3a NRC Generic Letters Reviewed: Mechanical, Structural, and Thermal-Hydraulic

Com ponents and System s ........................................................................................ 20

3b NRC Generic Letters Reviewed: Electrical Components and Systems ...................... 22

4a NRC Information Notices Reviewed: Mechanical, Structural, and ThermalHydraulic Com ponents and System s ........................................................................ 23

4b NRC Information Notices Reviewed: Electrical Components and Systems ................ 30

5a NRC Licensee Event Reports Reviewed: Mechanical, Structural, and

Thermal-Hydraulic Components and Systems ........................................................ 36

5b NRC Licensee Event Reports Reviewed: Electrical Components and Systems ........... 38

6a NRC Bulletins Reviewed: Mechanical, Structural, and Thermal-Hydraulic

Com ponents and System s ........................................................................................ 41

6b NRC Bulletins Reviewed: Electrical Components and Systems ................................. 41

7a NUMARC Industry Reports Reviewed: Mechanical, Structural. and

Thermal-Hydraulic Components and Systems ........................................................ 42

7b NUMARC Industry Reports Reviewed: Electrical Components and Systems ............. 42

8 Listing of Standardized ARD Mechanisms, Definitions, and Associated Effects ......... 43

NUREG/CR-G490 vvi
Executive Summary

It is well established that many of the critical components in nuclear power plants are

subject to time-dependent degradation, or aging, as a result of normal plant operations. In a

joint effort by Argonne National Laboratory (ANL) and Idaho National Engineering Laboratory

(INEL) in support of the License Renewal Project Directorate (PDLR) of the U.S. Nuclear

Regulatory Commission (NRC), we have conducted a comprehensive review and assessment of

the results of the Nuclear Plant Aging Research Program (NPAR) and related information

pertaining to nuclear power plant aging effects and plant impact. The results of this review,

called the Generic Aging Lessons Learned (GALL) program, are presented in this report and

will be used by NRC as resource material to update nuclear power plant operation and license

renewal guidance and as background material for assisting NRC staff in license renewal

reviews and establishing positions.

More than 550 documents containing nuclear power plant aging information were

reviewed in this program. The PDLR staff performed searches for current operating experience

documents covering the 5-year period, 1989-1994, using the NRC's Nuclear Documents

Management System (NUDOCS). Searches used the following terms: aging, degradation, and

failures. All generic communications (Bulletins, Generic Letters, and Information Notices) and

Licensee Event Reports that were included in the searches were reviewed for aging information

by ANL/INEL.

The literature on mechanical, structural, and thermal-hydraulic components and systems

reviewed consisted of 97 NPAR reports, 23 NRC Generic Letters, 154 Information Notices, 29

LERs, 4 Bulletins, and 9 NUMARC IRs. The literature on electrical components and systems

reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53

LERs, 1 Bulletin, and 1 NUMARC IR

The results of these reviews were compiled by using a standardized tabular format and

standardized definitions of aging-related degradation effects. The GALL tables are presented in

volumes 1 and 2 of this report. A computerized data base has also been generated for all

GALL review tables. The data base/electronic library will provide the NRC staff, nuclear

industry, and public with a comprehensive source of information about aging mechanisms and

the resultant effects for nuclear systems, structures, and components and current information

on relevant programs. The data base can be readily expanded to include relevant information

from future NRC programs as they are completed. Copies of the data base are available in the

NRC's Public Document Room located in Washington, DC.

A preliminary assessment of the GALL tables reveals that all significant issues with

respect to component aging are currently being addressed by the regulatory process. However,

the aging of certain components and the resulting aging effects, particularly in the category of

what is termed passive components, have been highlighted for continued scrutiny and

evaluation.

vii vii NUREG/CR-6490
Acknowledgments

The authors are grateful to NRC program managers Deborah A. Jackson, Paul C.

Shemanski, P. T. Kuo, and Christopher M. Regan for their support in providing guidance and

reviewing information given in this report.

NUREG/CR-6490 vi VIII
List of Acronyms

ACI American Concrete Institute

ANL Argonne National Laboratory

ARD Age-Related Degradation

ASME American Society of Mechanical Engineers

BL Bulletin

ESFAS Engineered Safety Features Actuation System

GALL Generic Aging Lessons Learned

GC Generic Communications

GL Generic Letter

I&C Instrumentation and Control

INEL Idaho National Engineering Laboratory

IN Information Notice

IR Industry Report (submitted by NUMARC to address license renewal)

LER Licensee Event Report

NEI Nuclear Energy Institute

NPAR Nuclear Plant Aging Research

NRC Nuclear Regulatory Commission

NUDOCS Nuclear Documents (NRC's Document Management System)

NUMARC Nuclear Management and Resources Council

PDLR License Renewal Project Directorate

PS Plant-Specific

RG Regulatory Guide

RPS Reactor Protection System

S&T Req. Surveillance and Test Requirements

SR Safety Related

TS Req. Technical Specification Requirements

ix NUREG/CR-6490

1 Introduction

Approximately 110 nuclear electrical power generating plants operating in the United

States in 1993 generated 20% of the nation's electrical demand. 1 It is well established that

many of the critical components in nuclear power plants are subject to time-dependent

degradation, or aging, as a result of normal plant operations. In recognition of the potentially

adverse effects of the aging process on plant safety, the U.S. Nuclear Regulatory Commission's

(NRC's) Office of Nuclear Regulatory Research established the Nuclear Plant Aging Research

(NPAR) Program. The principal objective of this program was to develop a basic understanding

of age-related degradation (ARD) processes and their effect on nuclear power plant systems,

structures, and components. In addition, the Nuclear Energy Institute (NEI), formerly the

Nuclear Management and Resources Council (NUMARC), has developed a series of industry

reports describing their assessment of plant aging issues and management strategies.

The NRC's License Renewal Project Directorate (PDLR) has been charged with the

responsibility for developing appropriate technical criteria for addressing the aging issues

related to nuclear power plant license renewal. In order to carry out this responsibility, the

PDLR initiated an activity to assess and integrate the age-related information from all available

sources, including NPAR reports, generic communications, and Licensee Event Reports (LERs)

and to use the results of this assessment to supplement and update license renewal guidance

previously developed. This activity was called the Generic Aging Lessons Learned (GALL)

program.

This report presents the results of the GALL review program. This was a joint effort

involving 12 technical experts from Argonne National Laboratory (ANL) and Idaho National

Engineering Laboratory (INEL). ANL also had the responsibility for coordinating and

combining the results from the program into a single report. The ANL effort reviewed

information on mechanical, structural, and thermal-hydraulic components and systems. The

INEL effort reviewed information on electrical components and systems. The results of these

reviews were compiled by using a standardized tabular format and standardized definitions of

ARD effects. All tabulated review information is contained in Appendices A (Vol. 1) and B

(Vol. 2) of this report. This information is also available in a computerized data base format

based on the software program FoxPro, and this data base is available upon request from the

NRC's Public Document Room located in Washington, DC. This data base allows rapid queries

and sorts of the large amount of information generated in this review.

1 1 NUREG/CR-6490
2 Description of Review Process

More than 550 documents containing nuclear power plant information were reviewed for

GALL information. The PDLR staff performed searches for current operating experience

documents covering the 5-year period, 1989-1994, using the NRC's Nuclear Documents

Management System (NUDOCS). The searches used the following terms: aging, degradation,

and failures. All generic communications (Bulletins, Generic Letters, and Information Notices)

and Licensee Event Reports which were included in the searches were reviewed by ANL and

INEL for aging information.

The review process was a joint effort involving Argonne National Laboratory (ANL) and

Idaho National Engineering Laboratory (INEL), with ANL having the role of coordinating and

combining the results from the program into a single report. ANL reviewed literature on

mechanical, structural, and thermal-hydraulic components and systems, which consisted of

97 NPAR reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports

(LERs), 4 Bulletins, and 9 NUMARC IRs. INEL reviewed literature on electrical components

and systems, which consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information

Notices, 53 LERs, 1 Bulletin, and I NUMARC IR A total of 163 NPAR reports, 31 NRC Generic

Letters, 265 Information Notices, 82 LERs, 5 Bulletins, and 10 NUMARC Industry Reports

(IRs) were reviewed under the GALL program. The results of these reviews were compiled by

using a standardized tabular format and standardized definitions of ARD and effects.

Early in the review process, it was apparent that the terminology used in the various

documents describing aging mechanisms and the resulting effects was often inconsistent and

confusing. For example, an identified resulting effect was often used interchangeably with or

in place of the mechanism responsible for aging. This problem can lead to difficulty in

systematizing the literature and to technical misunderstandings between researchers.

Therefore, a standardized and consistent set of definitions and descriptors for all aging

mechanisms encountered during the review was developed based on the input of the 12

reviewers performing the review. Individual aging mechanisms and effects were identified and

defined, and these are listed and described in Table 8. This list should also help focus and

systematize future reactor aging studies.

The reports, notices, letters, and bulletins reviewed are listed in Tables 2-7. The results

from each reviewed document are summarized in the Generic Aging Lessons Learned (GALL)

tables contained in Appendices A (Vol. 1) and B (Vol. 2) of this two volume report. A separate

table was prepared for each of the NPAR reports and NUMARC IRs; findings from the Generic

Letters, Information Notices, Bulletins, and LERs are tabulated by year. All of the GALL table

information has also been entered into a FoxPro data base software program that can be used

on IBM PC-compatible systems to retrieve and categorize information on structures and

components and their related aging effects. A number of custom programs were developed to

automate entry of the data into the 19 data base fields containing up to 254 characters. The

final data base was carefully edited to ensure the accuracy of the data. Testing of the data

base involved searching for key words in one or more of the various data base fields (e.g.,

system, component, subcomponent or ARD mechanism). To facilitate searching on

structure/component and subcomponent names, a three-digit code was added to identify

similar items that appear with slightly different names throughout the data base. This code

will enable a searcher to quickly locate all of the relevant information on a particular

NUREG/CR-6490 2
structure/component. Hard copy of the entire data base contained in the Appendices was

produced with R&R ReportWriter software, which permits publication of tables that span two

pages. This software enhances the normal output capability of commercially available data

base programs. Electronic file copies of the data base are in xbase format, which is a generic

dbase file that can be read by most data base software packages.

The information contained in the GALL tables is a summary of that provided in the

reports. No attempt was made to supplement the contents of the reports with information

available from other sources or from the reviewer's personal knowledge or experience, except

for the contents of two table columns titled "Relevant Program" and "Report Recommendations"

as discussed below. Furthermore, we found that not all of the reports, notices, and bulletins

reviewed contained relevant information on Age-Related Degradation (ARD) processes. A

number of the NPAR reports described programs, methodologies, computer codes, etc., for

studying and analyzing aging processes in nuclear components, but did not provide detailed

information on the processes themselves. The tables for these reports contain a standard

statement indicating this fact. Almost all of the Generic Letters, Information Notices, LERs,

and Bulletins reviewed contained detailed information on the failure of specific components,

but the failures were sometimes judged not to be aging-related by the reviewer or by the

author of the reviewed document. For example, failures caused by improper heat treatment,

preexisting defects introduced during manufacturing, or overloads or other abuse during

operation were not considered aging-related by the reviewer, even though the failure might not

have occurred until the component had been in service for some time. GALL table entries are

not provided for Generic Letters, Information Notices, LERs, and Bulletins judged not to

contain detailed information on specific aging effects and impact on specific plant components.

Most of the information contained in the tables of the Appendices is self-explanatory, but

some of the columns require additional explanation. The entries in the "ARD Mechanism"

column are taken from the standard set of abbreviations listed and defined in Table 8 along

with their associated "ARD Effects" shown in the next column. The effect of the ARD process

is then explained more fully in the column headed "Effect of Aging on Component Function."

The "Relative Contribution to Component Failure" is a measure of the contribution of the ARD

mechanism listed to the failure of given component as compared to all causes of failure for

that component. Some of the reviewed reports provided numerical data on relative

contribution to failure, though most either gave qualitative assessments or said nothing. A

standard set of semiquantitative terms was used in this column where information was

available, namely "frequent," "moderate," "occasional," "infrequent," and "rare." These terms

relate only to the "Relative Contribution to Component Failure" and do not in any way quantify

the actual failure rate of a given component or its impact on plant safety.

The "Reported Programs" column lists existing programs, standards, or other guidance

referred to in the reviewed document that addresses the particular ARD process or aging issue

in question. The "Relevant Programs" column lists some programs currently in use by

licensees in addressing issues that affect the stated system, structure, or component. There

was no need to address the Relevant Programs column for the industry report tables, because

the information given in the IRs is current with respect to discussions between NEI and the

NRC staff. The "Report Recommendations" column summarizes any recommendations

contained in the reviewed report for remedial actions or follow-on work with respect to a

particular ARD process. These recommendations were not reviewed by the NRC staff for

adequacy or endorsement. Finally, the number in brackets assesses the current relevance of

3 3 NUREG/CR-6490
the recommendation based on the reviewer's judgment. One of four possible standard entries

is used: (1) obsolete or outdated, (2) safety enhancements, (3) may potentially need further

evaluation, or (4) issue is presently being addressed. This numerical code was not used for the

industry report tables, because the information given in these reports is current with respect

to discussions between NEI and the NRC staff. Several industry report table entries under the

Report Recommendations column heading have the word "More" appearing. This entry tells

the reader that more information can be found in NUREG-1557 (Summary of Technical

Information and Agreements from Nuclear Management and Resources Council Industry

Reports Addressing License Renewal). The Relevant Programs and Report Recommendations

columns for the industrial report tables contain details of the discussions between the NEI and

the NRC staff.

NUREG/CR-6490 4
3 Summary and Observations

More than 550 documents comprising 163 NPAR reports, 31 NRC Generic Letters, 265

Information Notices, 82 Licensee Event Reports, 5 Bulletins, and 10 NUMARC Industry

Reports were reviewed under the GALL program. The results of these reviews were

systematically summarized in a tabular format, using standardized definitions of ARD

mechanisms and effects developed for this study. The review reveals (1) no new issues with

respect to the components subject to ARD and the degradation mechanisms responsible and

(2) that all ongoing significant issues are currently being addressed by the regulatory process.

However, (3) the aging of passive components has been highlighted for continued scrutiny.

The information contained in the column headed "Report Recommendations" in the GALL

tables contained in the Appendices clearly reflects this position. Four possible aging issue

current relevance categorization indicators were possible in this column. The all-important

indicator "may potentially need further evaluation," which indicates the possibility of emerging

aging issues, appears only a few times.

A few general observations concerning specific aging issues and the components affected

are presented below.

3.1 Mechanical, Structural, and Thermal-Hydraulic Components and Systems

As expected, corrosion and corrosion-related processes were the dominant mechanisms of

ARD in coolant piping and steam generators. Where high-velocity fluids were present in

piping, erosion/corrosion was also a significant mechanism. Additionally for piping, feedwater

nozzles, and interfacing tanks and other components, nonuniform water temperature fields

aggravated by thermal buoyancy can cause large induced structural thermal stresses of either

quasi-steady, low-cycle, or thermal shock nature and can lead to cracking or significant

structural distortion. These thermal stresses are usually not accounted for in component

design and are highly plant- and mode-of-operation-dependent. They can occur under normal

or intermittent operation of plant systems and tend to be worse under low flow conditions. For

reactor internals, irradiation-assisted stress corrosion cracking was an important source of

degradation where high radiation fields were present. Other forms of corrosion, as well as

vibrational fatigue, also contributed to internals degradation.

Pump and valve casings were likewise found to be subject to corrosion and

erosion/corrosion related degradation. Thermal embrittlement was an important mechanism

in cast stainless steel pump and valve components. Moving parts in pumps and valves

suffered from ARD produced by wear, vibration, fatigue, and erosion/corrosion. Valve and

pump seals and other elastomer components were subject to degradation by physical and

chemical degradation at elevated temperature and/or prolonged exposure to the service

environment.

The principal degradation mechanisms affecting concrete structures were leaching and

breakdown of cement phases under the action of aggressive chemicals, degradation due to

freeze-thaw cycles, and corrosive attack of the embedded rebar. The responsible mechanism(s)

for some concrete wall cracking was found to be not well understood.

5 5 NUREG/CR-6490
Diesel generators, air compressors, and ventilating and air conditioning equipment

suffered principally from wear, vibration, and fatigue associated with reciprocating motion, as

well as corrosion and wear induced by contamination. Heat exchangers and steam generators

were subject to contamination and corrosion, as well as biofouling, thermal fatigue, and

vibrational fatigue. Vibrational fatigue, wear, and elevated temperature degradation of

damping fluids commonly caused degradation in snubbers.

Table 1 lists aging issues found to occur almost equally in BWR and PWR plants and tend

to center on various forms of corrosion and fatigue. Another important commonality of the

components listed in this table is that they are all what are termed passive components as

described in 10 CFR 54. This may be of considerable significance because the literature

reviewed seems to indicate that passive components are not as extensively or thoroughly

covered by current plant maintenance procedures. Furthermore, surveillance and monitoring

methods and instrumentation and procedures have not been as extensively developed or

employed for passive components subjected to the highlighted aging mechanisms, nor are

some of the passive component aging mechanisms as well understood. Thus, plant life

extension by employing component replacement and maintenance could be more tenuous for

the passive components. Furthermore, passive components tend to be some of the most costly

in a plant and are frequently not as easy to replace. For these reasons, the knowledge base for

predicting relevant aging effects behavior and significance, which is essential to the

development of robust plans for aging reduction, monitoring procedures, and maintenance, is

very important for passive components.

Table 1. Selected Examples of Aging Issues Significant to Passive Components

Reactor

Type Component Material Degradation Process References

PWR Instrumenta- Low-alloy steel Environmentally assisted NUREG/CRtion and CRD (A533B, A508) fatigue. Appropriate design 5490

housing with Type 308 or rules do not yet exist in the

nozzles 309 SS clad ASME Boiler & Pressure Vessel

Code.

BWR Closure studs A-540, B22, B2, or Environmentally assisted NUREG/CRand B24 fatigue, fretting, and boric acid 5490

PWR corrosion if leakage present .

PWR CRD system Various Dropped or stuck rod due to NUREG/CRcomponents failure by fatigue, mechanical 5555

wear, or stress corrosion

cracking

BWR Jet pump and inconel X-750 Cracking and possible failure NUREG/CRholddown from vibrational and/or 5754

beams environmentally assisted fatigue

and stress corrosion cracking

BWR Reactor Various Crack initiation, growth, and NUREG/CRinternals possible failure from irradiation- 5754

assisted stress corrosion

_ cracking (IASCC)

NUlREG/CR-6490 6
Table 1. Selected Examples of Aging Issues Significant to Passive Components (Cont'd)

Reactor

Type Component Material Degradation Process References

PWR Lower core Type 304 SS, A- Cracking and possible failure NUREG/CRsupport 286, Inconel X- from vibrational fatigue and 6048

structure 750, and others IASCC

components

BWR Pressure Low-alloy steel Cracking (possibly SCC) of weld IN 90-29

vessel upper (A533B, A508) clad, with cracks penetrating

head with Type 308 or into underlying base metal

309 SS clad

BWR Core shroud Type 304 SS SCC (or IASCC) leads to IN 93-79,

circumferential cracking of core IN 94-42

shroud and concerns about

possible structural failure in an

accident or seismic event

BWR Recirculating Cemented WC in Preferential corrosive

coolant pump Ni binder dissolution of Ni binder under

seals certain undefined conditions

leads to excessive seal leakage

and possible eventual pump

failure

BBWR All piping and Commonly used Large thermally induced NUREG/CRand feedwater materials, low- stresses, either quasi-steady or 4731 Vols. 1&2

[PWR nozzles and alloy steels low-cycle transient, thermal

interfacing fatigue, induced by nonuniform

tanks and coolant temperature fields

components aggravated by thermalbuoyancy-caused stratification

under no-flow or low-flow levels,

cause wall cracking or gross

abnormal component distortion,

usually not accounted for in

component design, highly plantand mode-of-operation

dependent

BWR Shielding wall Reinforced Actual process and mechanisms NUREG/CRand concrete and concrete unclear: shows up as large 4652

PWR other surface cracks not caused by

locations structural loading

7 7 NUREG/CR-6490
3.2 Electrical Components and Systems

Breakers and relays were usually covered together in the same report; the predominant

aging-related failure mechanisms were contact wear, sticking linkage, loss of lubrication, or

elevated temperature. Normally energized relay coils were frequently mentioned as highfailure-rate items because of the insulation breakdown caused by elevated temperature due to

self-heating from the continuous current. Breakers are routinely refurbished on periodic

schedules.

Degradation of cable insulation and jackets is the major effect of cable aging, due

primarily to radiation and elevated temperature. Despite sizable efforts to develop electrical

and mechanical methods of detecting cable insulation degradation, there are no reliable

methods of detecting degradation of electrical cable insulation in a reactor containment.

Electrical parameters, while relatively easy to measure, were found not to give a good

indication of mechanical degradation. The mechanical indentor method was successful only

for some insulation and jacket types.

Instrumentation and control (I&C) systems, including breakers and sensors, are made up

of many small components that are routinely replaced after a number of years of service, as

determined by qualification programs. Thus, aging is controlled by scheduled maintenance

and periodic replacement. Redundancy in the Reactor Protection System and Engineered

Safety Features Actuation Systems allows for taking a channel out of service for maintenance.

Motors and generators occasionally fail due to bearing wear caused by vibration and

winding insulation breakdown from elevated temperatures. Brushes also age due to wear.

Battery chargers and inverters are small electrical systems made up of many electronic

components that, like the I&C system, can be taken out of service for maintenance because of

redundancy. Many of the electrical I&C components are included in plant QA programs that

require periodic replacement. Inverter failures have caused numerous problems.

Many of the electrical I&C components are included in plant quality assurance programs

that require periodic replacement. A more detailed analysis may be carried out at a later date

to assess the significance of these mitigative practices and the aging processes.

NUREG/CR-6490 8
Table 2a. NPAR Reports Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

No report no. Tech. Integration Plan for Integration of Aging and Life-Extension

(May 1987) Review Group for Activities

Aging and Life

Extension

BNL Tech. Report Miller Scoping Test on Containment Purge and Vent Seal

A-3270-11-26-84 Material

BNL Tech. Report Silver, Vasudevan, Pilot Assessment: Impact of Aging on the Seismic

A-3270-12-85 and Subudhi Performance of Selected Equipment Types

BNL Tech. Report Fullwood, Higgins, Aging and Life Extension Assessment Program

A-3270-12-86 Subudhi, and Taylor (ALEAP) Systems Level Plan

BNL Tech. Report Fresco and Subudhi Interim Report-Aging Effects of Important

A-3270R-2-90 Balance of Plant Systems in Nuclear Power Plants

BNL Tech. Report Gunther Maintenance Team Inspection Results: Insights

TR-3270-6-90 Related to Plant Aging

BNL Tech. Report Grove and Gunther An Operational Assessment of the Babcock &

TR-3270-9-90 Wilcox and Combustion Engineering Control Rod

Drives

BNL Tech. Report Hsu, Vesely, Grove, Degradation Modeling: Extensions and

A-3270-6-21-91 Subudhi, and Applications

Samanta

EGG-SSRE-8972 Atwood Estimating Hazard Functions for Repairable

Components

EGG-SSRE-9017 Atwood User's Guide to PHAZE, a Computer Program for

Parametric Hazard Function Estimation

EGG-SSRE-9777 Watkins, Steele, and Isolation Valve Assessment (IVA) Software Version

DeWall 3.10, User's Manual

EGG-SSRE-9926 Steele, Watkins, and Evaluation of EPRI Draft Report NP-7065-Review

DeWall of NRC/INEL Gate Valve Test Program

EGG-SSRE- 10039 Hunt and Nitzel An Evaluation of the Effects of Valve Body Erosion

on Motor-Operated Valve Operability

Letter Report Subudhi Review of Aging-Seismic Studies on Nuclear Plant

Equipment

Letter Report Rib Summaries of Research Reports Submitted in

Connection with the Nuclear Plant Aging Research

(NPAR) Program

Nuclear Safety Hoopingarner and Safety Implications of Diesel Generator Aging

31:484-489 Zaloudek

9 9 NUREG/CR-6490
Table 2a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

NUREG/CP-0036 Bader and Hanchey Proceedings of the Workshop on Nuclear Plant

(SAND-82-2264C) Aging

NUREG- 1 144,V1 Morris and Vora Nuclear Plant Aging Research (NPAR) Program

Plan

NUREG- 1 144,V2 Vora Nuclear Plant Aging Research (NPAR) Program

Plan, Rev. I

NUREG- 1 144,V3 Nuclear Plant Aging Research (NPAR) Program

Plan, Status, and Accomplishments, Rev. 2

NUREG/CP-0100 Beranek Proceedings of the International Nuclear Power

Plant Aging Symposium

NUREG/CP-0105 Christensen Proceedings of the Seventeenth Water Reactor

Safety Information Meeting (aging session only)

NUREG/CR-2641 Drago, Borkowski, The In-Plant Reliability Data Base for Nuclear

(ORNL/TM 8271) Pike. and Goldberg, Power Plant Components: Data Collection and

Methodology Report

NUREG/CR-3154 Borkowski, Kahl, The In-Plant Reliability Data Base for Nuclear

(ORNL/TM 8647) Hebble, Frangola, and Plant Components: Interim Report-The Valve

Johnson Component

NUREG/CR-3543 Murphy, Gallaher, Survey of Operating Experiences from LERs to

(ORNL/TM 3543) Casada, and Hoy Identify Aging Trends

NUREG/CR-3818 Clark and Berry Report of Results of Nuclear Power Plant Aging

(SAND-84-0374) Workshop

NUREG/CR-3819 Rose, Steele, DeWall, Survey of Aged Power Plant Facilities

(EGG-2317) and Cornwell

NUREG/CR-4144 Davis, Shafaghi, Importance Ranking Based on Aging

(PNL-5389) Kurth, and Leverenz Consideration of Components Included in

Probabilistic Risk Assessments

NUREG/CR-4279 Bush, Heasler, and Aging and Service Wear of Hydraulic and

(PNL-5479, VI) Dodge Mechanical Snubbers used on Safety-Related

Piping and Components of Nuclear Power Plants

NUREG/CR-4302 Greenstreet, Murphy, Aging and Service Wear of Check Valves Used in

(ORNL-6193, VI) Gallaher, and Engineered Safety-Feature Systems of Nuclear

Eissenberg Power Plants, Vol. 1

NUREG/CR-4302 Haynes Aging and Service Wear of Check Valves Used in

(ORNL-6193, V2) Engineered Safety Feature Systems of Nuclear

Power Plants, Vol. 2

NUREG/CR-4380 Crowley and Evaluation of the Motor-Operated Valve Analysis

(ORNL-6226) Eissenberg and Test System (MOVATS) to Detect Degradation.

Incorrect Adjustments, and Other Abnormalities

in Motor-Operated Valves

NUREG/CR-6490 10
Table 2a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

NUREG/CR-4597 Adams and Makay Aging and Service Wear of Auxiliary Feedwater

(ORNL-6282, VI) Pumps for PWR Nuclear Power Plants, Vol. 1:

Operating Experience and Failure Identification

NUREG/CR-4597 Kitch, Schlonski, Aging and Service Wear of Auxiliary Feedwater

(ORNL-6282, V2) Sowatskey, and Pumps for PWR Nuclear Power Plants, Vol. 2:

Cesarski Aging Assessment and Monitoring Method

Evaluations

NUREG/CR-4652 Naus Concrete Component Aging and its Significance

(ORNL/TM- 10059) Relative to Life Extension of Nuclear Power Plants

NUREG/CR-4692 Murphy and Cletcher Operating Experience Review of Failures of Power

(ORNL/NOAC- Operated Relief Valves and Block Valves in

233) Nuclear Power Plants

NUREG/CR-4731 Shah and MacDonald Residual Life Assessment of Major Light Water

(EGG-2469), VI Reactor Components, Vol. 1

NUREG/CR-4731 Shah and MacDonald Residual Life Assessment of Major Light Water

(EGG-2469), V2 Reactor Components-Overview, Vol. 2

NUREG/CR-4747 Meale and Satterwhite An Aging Failure Survey of Light Water Reactor

(EGG-2473, Vol. Safety Systems and Components, Vol. 1

1)

NUREG/CR-4747 Meale and Satterwhite An Aging Failure Survey of Light Water Reactor

(EGG-2473, Vol. Safety Systems and Components, Vol. 2

2)

NUREG/CR-4769 Vesely Risk Evaluations of Aging Phenomena: The Linear

(EGG-2476) Aging Reliability Model and its Extensions

NUREG/CR-4967 Meyer Nuclear Plant Aging Research on High Pressure

(EGG-2514) Injection Systems

NUREG/CR-4977 Steele and Arendts SHAG Test Series: Seismic Research on an Aged

(EGG-2505, V1) United States Gate Valve and on a Piping System

in the Decommissioned Heissdampfreaktor (HDR):

Summary. Vol. 1

NUREG/CR-4977 Steele and Arendts SHAG Test Series: Seismic Research on an Aged

(EGG-2505, V2) United States Gate Valve and on a Piping System

in the Decommissioned Heissdampfreaktor (HDR):

Appendices, Vol. 2

NUREG/CR-4985 Subudhi, Taylor. Indian Point 2 Reactor Coolant Pump Seal

(BNL/NUREG- Clinton, Czajkowski, Evaluations

52095) and Weeks

NUREG/CR-5052 Higgins, Lofaro, Operating Experience and Aging Assessment of

(BNL-NUREG- Subudhi, Fullwood, Component Cooling Water Systems in Pressurized

52117) and Taylor Water Reactors

11 11 NUREG/CR-6490
Table 2o.. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

NUREG/CR-5057 Hoopingarner and Aging Mitigation and Improved Programs for

(PNL-6397) Zaloudek Nuclear Service Diesel Generators

NUREG/CR-5159 Kalsi, Horst, and Prediction of Check Valve Performance and

(KEI-1559) Wang Degradation in Nuclear Power Plant Systems

NUREG/CR-5248 Levy, Wreathall, Prioritization of TIRGALEX-Recommended

(PNL-6701) DeMoss, Wolford, Components for Further Aging Research

Collins, and Jarrell

NUREG/CR-5268 Lofaro, Subudhi, Aging Study of Boiling Water Reactor Residual

(BNL-NUREG- Gunther, Shier, Heat Removal System

52177) Fullwood, and Taylor

NUREG/CR-5314, Jaske and Shah Life Assessment Procedures for Major LWR

V3 Components; Cast Stainless Steel Components

NUREG/CR-5378 Wolford, Atwood, and Aging Data Analysis and Risk AssessmentRoesener Development and Demonstration Study

NUREG/CR-5379 Jarrell, Johnson, Nuclear Plant Service Water System Aging

(PNL-6560), V1 Zimmerman, and Degradation Assessment: Phase 1, Vol. 1

Gore

NUREG/CR-5379 Jar-ell, Larson, Nuclear Plant Service Water System Aging

(PNL-6560), V2 Stratton, Bohn, and Degradation Assessment, Vol. 2

Gore

NUREG/CR-5386 Brown, Palmer, Basis for Snubber Aging Research: Nuclear Plant

(PNL-691 1) Werry, and Blahnik Aging Research Program

NUREG/CR-5404 Casada Auxiliary Feedwater System Aging Study, Vol. 1

(ORNL-6566, VI)

NUREG/CR-5404 Kueck Auxiliary Feedwater System Aging, Phase I:

(ORNL-6566, V2) Follow-on Study

NUREG/CR-5406 DeWall and Steele BWR Reactor Water Cleanup System Flexible

(EGG-2569, Vi) Wedge Gate Isolation Valve Qualification and High

Energy Flow Interruption Test, Vol 1: Analysis and

Conclusions

NUREG/CR-5406 DeWall and Steele BWR Reactor Water Cleanup System Flexible

(EGG-2569, V2) Wedge Gate Isolation Valve Qualification and High

Energy Flow Interruption Test, Vol 2: Data Report

NUREG/CR-5406 DeWall and Steele BWR Reactor Water Cleanup System Flexible

(EGG-2569, V3) Wedge Gate Isolation Valve Qualification and High

Energy Flow Interruption Test, Vol 3: Review of

Issues Associated with the BWR Containment

Isolation Valve Closure

NUREG/CR-6490 12
Table 2a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

NUREG/CR-5419 Villaran, Fullwood, Aging Assessment of Instrument Air Systems in

(BNL-NUREG- and Subudhi Nuclear Power Plants

5221)

NUREG/CR-5479 Damiano and Kryter Current Applications of Vibration Monitoring and

(ORNL/CR/5479) Neutron Noise Analysis: Detection and Analysis of

Structural Degradation of Reactor Vessel Internals

from Operational Aging

NUREG/CR-5490 Werry Regulatory Instrument Review: Management of

Aging of LWR Major Safety Components

NUREG/CR-5491 Allen and Johnson Shippingport Station Aging Evaluation

(PNL-7191)

NUREG/CR-5507 Gunther and Taylor Results from the Nuclear Plant Aging Research

Program: Their Use in Inspection Activities

NUREG/CR-5510 Vesely, Kurth, and Evaluations of Core Melt Frequency Effects due to

Scalzo Component Aging and Maintenance

NUREG/CR-5515 Neely, Jeanmougin, Light Water Reactor Pressure Isolation Valve

and Corugedo Performance Testing

NUREG/CR-5519 Moyers Aging of Control and Service Air Compressors and

Dryers used in Nuclear Power Plants

NUREG/CR-5555 Gunther and Sullivan Aging Assessment of the Westinghouse PWR

Control Rod Drive System

NUREG/CR-5558 Steele, DeWall, and Generic Issue 87: Flexible Wedge Gate Valve Test

Watkins Program: Phase II Results and Analysis

NUREG/CR-5583 Kalsi, Horst, Wang, Prediction of Check Valve Performance and

and Sharma Degradation in Nuclear Power Plant Systems-Wear

and Impact Tests

NUREG/CR-5587 Vesely Approaches for Age-Dependent Probabilistic Safety

Assessments with Emphasis on Prioritization and

Sensitivity Studies

NUREG/CR-5612 Samanta, Vesely, Degradation Modeling with Applications to Aging

Hsu, and Subudhi and Maintenance Effectiveness Evaluation

NUREG/CR-5643 Blahnik, Casada, Insights Gained from Aging Research

Edson, Fineman

NUREG/CR-5646 Steele and Nitzel Piping System Response During High Level

Simulated Seismic Tests at the Heissdampfreaktor

Facility (SHAM Test Series)

NUREG/CR-5693 Lofaro, Gunther, Aging Assessment of Component Cooling Water

Subudhi and Lee Systems in Pressurized Water Reactors-Phase II

13 NUREG/CR-6490
Table 2a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

NUREG/CR-5699 Greene Aging and Service Wear of Control Rod Drive

Mechanisms for BWR Nuclear Plants-Vol. 1

NUREG/CR-5706 Casada NRC Bulletin 88-04: Potential Safety-Related

Pump Loss-An Assessment of Industry Data

NUREG/CR-5720 Steele, Watkins, Motor-Operated Valve Research Update

DeWall, and Russell

NUREG/CR-5754 Luk Boiling-Water Reactor Internals Aging Degradation

Study-Phase I

NUREG/CR-5779 Moyers Aging of Non-Power-Cycle Heat Exchangers Used

in Nuclear Power Plants

NUREG/CR-5783 Grove and Gunther Aging Assessment of the Combustion Engineering

and Babcock & Wilcox Control Rod Drives

NUREG/CR-5807 Wang and Kalsi Improvements in Motor Operated Gate Valve

Design and Prediction Models for Nuclear Power

Plant Systems

NUREG/CR-5848 Dukelow Recordkeeping Needs to Mitigate the Impact of

Aging Degradation

NUREG/CR-5870 Brown, Wer-y, and Results of LWR Snubber Aging Research

Blahnik

NUREG/CR-5944 Casada and Todd A Characterization of Check Valve Degradation

and Failure Experience in the Nuclear Power

Industry

NUREG/CR-6001 Buckley, Orton, Aging Assessment of BWR Standby Liquid Control

Johnson, and Larson Systems

NUREG/CR-6029 Winegardner Aging Assessment of Nuclear Air Treatment

System HEPA Filters and Adsorbers-Phase 1

NUREG/CR-6043 Blahnik and Klein Phase I Aging Assessment of Essential HVAC

Chillers Used in Nuclear Power Plants

NUREG/CR-6048 Luk Pressurized-Water Reactor Internals Aging

Degradation Study--A Phase I Report

ORNL/NRC/LTR- Casada Throttled Valve Cavitation and Erosion

91/25

PNL-5722 Blahnik and Operating Experience and Aging Assessment of

Goodman ECCS Pump Room Coolers

PNL-6287 Hoopingarner, Kirk- Study Group Review of Nuclear Service Diesel

wood, and Lounzecky Generator Testing and Aging Mitigation

NUREG/CR-6490 14
Table 2a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Author Title

PNL-7516 Hoopingarner Emergency Diesel Generator Technical

Specifications Study Results

PNL-7823 Chockie, Bjorkelo, Maintenance Practices to Manage Aging: A Review

Fleming, Scott, and of Several Technologies

Enderlin

PNL-SA- 18407 Johnson, Jarrell, Understanding and Managing Corrosion in

Sinha, and Shah Nuclear Power Plants

PNL-SA-20219 Brown and Blahnik ASME Subsection ISTD Recommendations Based

upon NPAR Snubber Aging Research Results

15 NUREG/CR-6490
Table 2b. NPAR Reports Reviewed

Electrical Components and Systems

Report No. Title

BNL A-3270-11-85 Seismic Endurance Tests Of Naturally Aged Small Electric Motors

BNL A-3270-3-86 Testing Program For The Monitoring Of Degradation In A

Continuous Duty 460 Volt Class "B", 10 Hp Electric Motor

CHAPTER 24 CABLES Aging And Life Extension Of Major Light Water Reactor

Components, Edited By V. N. Shah And P. E. Macdonald, Elsevier

Science Publishers B.V., 1993

NISTIR 4485 Annotated Bibliography: Diagnostic Methods And Measurement

Approaches To Detect Incipient Defects Due To Aging Of Cables

NISTIR 4487 Detection Of Incipient Defects In Cables By Partial Discharge

Signal Analysis

NISTIR 4787 The Use Of Time-Domain Dielectric Spectroscopy To Evaluate The

Lifetime Of Nuclear Power Station Cables

NUREG- 1377 R3 NRC Research Program On Plant Aging: Listing And Summaries Of

Reports Issued Through July 1992

NUREG/CP-0100 Proceedings Of The International Nuclear Aging Symposium,

Session 3 (Pgs 125-126 & 363-366)

NUREG/CP-0105 Seventeenth Water Reactor Safety Information Meeting (Electrical

Parts)

NUREG/CR-3956 In Situ Testing Of The Shippingport Atomic Power Station Electrical

Circuits

NUREG/CR-4156 Operating Experience And Aging-Seismic Assessment Of Electric

Motors

NUREG/CR-4234 V2 Aging And Service Wear Of Electric Motor-Operated Valves Used In

Engineered Safety-Feature Systems Of Nuclear Power Plants

NUREG/CR-4257 Inspection, Surveillance, And Monitoring Of Electrical Equipment

Inside Containment Of Nuclear Power Plants - With Applications To

Electrical Cables

NUREG/CR-4257 V2 Inspection, Surveillance, And Monitoring Of Electrical Equipment

In Nuclear Power Plants - Pressure Transmitters

NUREG/CR-4457 Aging Of Class le Batteries In Safety Systems Of Nuclear Power

Plants

NUREG/CR-4564 Operating Experience And Aging-Seismic Assessment Of Battery

Chargers And Inverters

NUREG/CR-4715 An Aging Assessment Of Relays And Circuit Breakers And System

Interactions

NUREG/CR-4740 Nuclear Plant-Aging Research On Reactor Protection Systems

NUREG/CR-4747 VI An Aging Failure Survey Of LWR Safety Systems And Components

NUREG/CR-6490 16
Table 2b. (Contd)

Electrical Components and Systems

Report No. Title

NUREG/CR-4747 V2 An Aging Failure Survey Of Light Water Reactor Safety Systems

And Components (Electrical)

NUREG/CR-4819 V1 Aging And Service Wear Of Solenoid-Operated Valves Used In

Safety Systems Of Nuclear Power Plants

NUREG/CR-4819 V2 Aging And Service Wear Of Solenoid-Operated Valves Used In

Safety Systems Of Nuclear Power Plants. Vol 2

NUREG/CR-4928 Degradation Of Nuclear Plant Temperature Sensors

NUREG/CR-4939 V1 Improving Motor Reliability In Nuclear Power Plants - Performance

Evaluation And Maintenance Practices

NUREG/CR-4939 V2 Improving Motor Reliability In Nuclear Power Plants

NUREG/CR-4939 V3 Failure Analysis And Diagnostic Tests On A Naturally Aged Large

Electric Motor

NUREG/CR-4967 Nuclear Plant Aging Research On High Pressure Injection Systems

NUREG/CR-4992 VI Aging And Service Wear Of Multistage Switches Used In Safety

Systems Of Nuclear Power Plants

NUREG/CR-5008 Development Of A Testing And Analysis Methodology To Determine

The Functional Condition Of Solenoid Operated Valves

NUREG/CR-5051 Detecting And Mitigating Battery Charger And Inverter Aging

NUREG/CR-5053 Operating Experience And Aging Assessment Of Motor Control

Centers

NUREG/CR-5141 Aging And Qualification Research On Solenoid Operated Valves

NUREG/CR-5181 Nuclear Plant Aging Research: The le Power System

NUREG/CR-5192 Testing Of A Naturally Aged Nuclear Power Plant Inverter And

Battery Charger

NUREG/CR-5280 V1 Age-Related Degradation Of Westinghouse 480-Volt Circuit

Breakers

NUREG/CR-5280 V2 Age-Related Degradation Of Westinghouse 480-Volt Circuit

Breakers (Mechanical Cycling)

NUREG/CR-5334 Severe Accident Testing Of Electrical Penetration Assemblies

NUREG/CR-5383 Effect Of Aging On Response Time Of Nuclear Plant Pressure

Sensors

NUREG/CR-5448 Aging Evaluation Of Class le Batteries: Seismic Testing

NUREG/CR-5461 Aging Of Cables, Connections, And Electrical Penetration

Assemblies Used In Nuclear Power Plants

NUREG/CR-5546 An Investigation Of The Effects Of Thermal Aging On The Fire

Damageability Of Electric Cables

NUREG/CR-5560 Aging Of Nuclear Plant Resistance Temperature Detectors

17 NUREG/CR-6490
Table 2b. (Cont'd)

Electrical Components and Systems

Report No. Title

NUREG/CR-5619 The Impact Of Thermal Aging On The Flammability Of Electric

Cables

NUREG/CR-5643 Insights Gained From Aging Research

NUREG/CR-5655 Submergence And High Temperature Steam Testing Of Class le

Electrical Cables

NUREG/CR-5700 Aging Assessment Of Reactor Instrumentation And Protection

System Components

NUREG/CR-5762 Comprehensive Aging Assessment Of Circuit Breakers And Relays

NUREG/CR-5772 VI Aging, Condition Monitoring, And Loss-Of-Coolant Accident (LOCA)

Tests Of Class le Electrical Cables

NUREG/CR-5772 V2 Aging, Condition Monitoring, And Loss-Of-Coolant Accident (LOCA)

'rests Of Class le Electrical Cables

NUREG/CR-5772 V3 Aging, Condition Monitoring, And Loss-Of-Coolant Accident (LOCA)

Tests Of Class le Electrical Cables

NUREG/CR-6095 Aging, Loss-Of-Coolant Accident (LOCA)L And High Potential Testing

Of Damaged Cables

NUREG/CR-9XXX Summaries Of Research Reports Submitted In Connection With The

Nuclear Aging Research (NPAR) Program

SAND--88-0754 Time-Temperature-Dose Rate Superpositions: A Methodology For

Predicting Cable Degradation Under Ambient Nuclear Power Plant

Aging Conditions

TIRGALEX Plan For Integration Of Aging And Life-Extension Activities

WYLE 60103-1 Test Plan Of Molded Case Circuit Breakers For The Comprehensive

Aging Assessment Of Circuit Breakers And Relays For Nuclear Plant

Aging Research (NPAR)

"VYLE 60103-2 Test Plan Of Metal Clad Circuit Breakers For The Comprehensive

Aging Assessment Of Circuit Breakers And Relays For ------ NPAR

Program, Phase li

WYLE 60103-3 Test Plan Of Auxiliary Relays For The Comprehensive Aging

Assessment Of Circuit Breakers And Relays For ---- (NPAR)

Program, Phase Ii

WYLE 60103-4 Test Plan Of Control Relays For The Comprehensive Aging

Assessment Of Circuit Breakers And Relays For ------ (NPAR)

Program, Phase Ii

WYLE 60103-5 Test Plan Of Protective Relays For The Comprehensive Aging

Assessment Of Circuit Breakers And Relays For Nuclear Plant Aging

Research (NPAR), Phase Ii

NUREG/CR-6490 118
Table 2b. (Cont'd)

Electrical Components and Systems

Report No. Title

WYLE 60103-6 Test Plan Of Timing Relays For The Comprehensive Aging

Assessment Of Circuit Breakers And Relays For Nuclear Plant Aging

Research (NPAR), Phase li

WYLE 60103-7 Test Plan Of Electronic Relays For The Comprehensive Aging

Assessment Of Circuit Breakers And Relays For Nuclear Plant Aging

Research (NPAR), Phase Ii

SAND93-7027 Aging Management Guideline for Commercial Nuclear Power PlantsElectrical Switchgear

SAND93-7046 Aging Management Guideline for Commercial Nuclear Power PlantsBattery Chargers, Inverters and Uninterruptible Power Supplies

SAND93-7068 Aging Management Guideline for Commercial Nuclear Power PlantsPower and Distribution Transformers

SAND93-7069 Aging Management Guideline for Commercial Nuclear Power PlantsMotor Control Centers

SAND93-7071 Aging Management Guideline for Commercial Nuclear Power PlantsStationary Batteries

19 19 NUREG/CR-6490
Table 3a. NRC Generic Letters Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Letter No. Title

GL 89-04 Guidance on Developing Acceptable Inservice Testing Programs

GL 89-08 Erosion/Corrosion-Induced Pipe Wall Thinning

GL 89-10 Safety-Related (1) Motor-Operated Valve Testing and Surveillance

GL 89-10b, Availability of Program Descriptions

Suppl. 2

GL 89- lOc, Consideration of the Results of NRC-Sponsored Tests of Motor-Operated

Suppl. 3 Valves

GL 89-10d, Consideration of Valve Mispositioning in Boiling Water Reactors

Suppl. 4

GL 89-10, Information on Schedule Grouping, and Staff Responses to Additional Public

Suppl. 6 Questions

GL 89-11 Resolution of Generic Issue 101, "Boiling Water Reactor Water Level

Redundancy"

GL 89-13 Service Water System Problems Affecting Safety-Related Equipment

GL 89-13, Service Water System Problems Affecting Safety-Related Equipment, Suppl. 1

Suppl. 1

GL 89-21, Request for Information Concerning Status of Implementation of Unresolved

Encl. 1 Safety Issue (USI) Requirements

GL 90-05 Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,

2, and 3 Piping

GL 90-06 Resolution of Generic Issue 70, "Power-Operated Relief Valve and Block Valve

Reliability," and Generic Issue 94, "Additional Low-Temperature Overpressure

Protection for Light-Water Reactors"

GL 90-09 Alternative Requirements for Snubber Visual Inspection Intervals and

Corrective Actions

GL 91-07 GI-23, "Reactor Coolant Pump Seal Failures" and its Possible Effect on

Station Blackout

GL 91-13 Request for Information Related to the Resolution of Generic Issue 130,

"Essential Service Water System Failures at Multi-Unit Sites," Pursuant to 10

CFR 50.54(f)

GL 91-17 Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power

Plants"

GL 91-18 Information to Licensees Regarding Two NRC Inspection Manual Sections on

Resolution of Degraded and Nonconforming Conditions and on Operability

GL 92-01, Reactor Vessel Structural Integrity, 10 CFR 50.54(f)

Rev. 1

NUREG/CR-6490 20
Table 3a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Letter No. Title

GL 92-02 Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal

Stress During Natural Convection Cooldown"

GL 92-04 Resolution of the Issues Related to Reactor Vessel Water Level

Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)

GL 93-04 Rod Control System Failure and Withdrawal of Rod Control Cluster

Assemblies, 10 CFR 50.54(f)

GL 94-01 Removal of Accelerated Testing and Special Reporting Requirements for

Emergency Diesel Generators

21 NUREG/CR-6490
Table 3b. NRC Generic Letters Reviewed

Electrical Components and Systems

Age

Letter No. Title Related

GL 89-19 Request For Action Related To Resolution Of Unresolved Safety No

Issue "Safety Implication Of Control Systems In LWR Nuclear

Power Plants," Pursuant To 10 CFR 50.54(F)

GL 91-06 Resolution Of Generic Issue A-30, "Adequacy Of Safety-Related No

DC Power Supplies," Pursuant To 10 CFR 50.54(F)

GL 91-11 Resolution Of Generic Issue 48, "LCOS For Class le Vital No

Instrument Buses," And 49, "Interlocks And LCOS For Class le

Tie Breakers," Pursuant To 10 CFR 50.54(F)

GL 91-15 Operating Experience Feedback Report, Solenoid-Operated Valve Yes

Problems At U.S. Reactors

GL 92-04 Resolution Of The Issues Related To Reactor Vessel Water Level No

Instrumentation In BWRs Pursuant To 10 CFR 50.54(F)

GL 92-08 Thermo-Lag 330-1 Fire Barriers No

GL 93-04 Rod Control System Failure And Withdrawal Of Rod Control No

Cluster Assemblies, 10 CFR 50.54(F)

GL 94-01 Removal Of Accelerated Testing And Special Reporting No

Requirements For Emergency Diesel Generators

NUREG/CR-6490 22
Table 4a. NRC Information Notices Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 89-01 Valve Body Erosion

IN 89-04 Potential Problems from the Use of Space Heaters

IN 89-06 Bent Anchor Bolts in Boiling Water Reactor Torus Supports

IN 89-08 Pump Damage Caused by Low-Flow Operation

IN 89-15 Second Reactor Coolant Pump Shaft Failure at Crystal River

IN 89-20 Weld Failures in a Pump of Byron-Jackson Design

IN 89-26 Instrument Air Supply to Safety-Related Equipment

IN 89-30 High-Temperature Environments at Nuclear Power Plants

IN 89-32 Surveillance Testing of Low-Temperature Overpressure-Protection Systems

IN 89-32, Surveillance Testing of Low-Temperature Overpressure-Protection Systems

Suppl. I

IN 89-33 Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs

IN 89-36 Excessive Temperatures in Emergency Core Cooling System Piping Located

Outside Containment

IN 89-38 Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3

IN 89-48 Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump Cooling

Water System

IN 89-49 Failure to Close Service Water Cross-Connect Isolation Valves

IN 89-53 Rupture of Extraction Steam Line on High Pressure Turbine

IN 89-55 Degradation of Containment Isolation Capability by a High-Energy Line Break

IN 89-58 Disablement of Turbine-Driven Auxiliary Feedwater Pump Due to Closure of

One of the Parallel Steam Supply Valves

IN 89-61 Failure of Borg-Warner Gate Valves to Close Against Differential Pressure

IN 89-62 Malfunction of Borg-Warner Pressure Seal Bonnet Check Valves Caused by

Vertical Misalignment of Disk

IN 89-65 Potential for Stress Corrosion Cracking in Steam Generator Tube Plugs

Supplied by Babcock and Wilcox

IN 89-67 Loss of Residual Heat Removal Caused by Accumulator Nitrogen Injection

IN 89-69 Loss of Thermal Margin Caused by Channel Box Bow

IN 89-71 Diversion of the Residual Heat Removal Pump Seal Cooling Water Flow

During Recirculation Operation Following a Loss-of-Coolant Accident

IN 89-73 Potential Overpressurization of Low Pressure Systems

IN 89-77 Debris in Containment Emergency Sumps and Incorrect Screen

Configurations

23 NUREG/CR-6490
Table 4a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 89-77, Debris in Containment Emergency Sumps and Incorrect Screen

Suppl. 1 Configurations

IN 89-79 Degraded Coatings and Corrosion of Steel Containment Vessels

IN 89-79, Degraded Coatings and Corrosion of Steel Containment Vessels

Suppl. 1

IN 89-80 Potential for Water Hammer. Thermal Stratification, and Steam Binding in

High-Pressure Coolant Injection Piping

IN 89-81 Inadequate Control of Temporary Modifications to Safety-Related Systems

IN 89-90 Pressurizer Safety Valve Lift Setpoint Shift

IN 89-90, Pressurizer Safety Valve Lift Setpoint Shift

Suppl. 1

IN 89-90, Pressurizer Safety Valve Lift Setpoint Shift

Suppl. 2

IN 90-02 Potential Degradation of Secondary Containment

IN 90-03 Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of

the Swing Arm

IN 90-04 Cracking of the Upper Shell-To-Transition Cone Girth Welds in Steam

Generators

IN 90-10 Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600

IN 90-17 Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves

IN 90-18 Potential Problems with Crosby Safety Relief Valves used on Diesel Generator

Air Start Receiver Tanks

IN 90-19 Potential Loss of Effective Volume for Containment Recirculation Spray at

PWR Facilities

IN 90-21 Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve

Seat Friction Was Underestimated

IN 90-29 Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a

Reactor Vessel Head

IN 90-30 Ultrasonic Inspection Techniques for Dissimilar Metal Welds

IN 90-32 Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel

Head

IN 90-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel

Suppl. 1 Head

IN 90-37 Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators

IN 90-39 Recent Problems with Service Water Systems

NUREG/CR-6490 24
Table 4a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 90-40 Results of NRC-Sponsored Testing of Motor-Operated Valves

IN 90-45 Overspeed of the Turbine-Driven Auxiliary Feedwater Pumps and

Overpressurization of the Associated Piping Systems

IN 90-49 Stress Corrosion Cracking in PWR Steam Generator Tubes

IN 90-53 Potential Failures of Auxiliary Steam Piping and the Possible Effects on the

Operability of Vital Equipment

IN 90-60 Availability of Failure Data in the Government-Industry Data Exchange

Program

IN 90-64 Potential for Common-Mode Failure of High Pressure Safety Injection Pumps

or Release of Reactor Coolant Outside Containment During a Loss-of-Coolant

Accident

IN 90-65 Recent Orifice Plate Problems

IN 90-68 Stress Corrosion Cracking of Reactor Coolant Pump Bolts

IN 90-68, Stress Corrosion Cracking of Reactor Coolant Pump Bolts

Suppl. I

IN 90-73 Corrosion of Valve-to-Torque Tube Keys in Spray Pond Cross Connect Valves

IN 90-74 Information on Precursors to Severe Accidents

IN 90-76 Failure of Turbine Overspeed Trip Mechanism Because of Inadequate Spring

Tension

IN 90-78 Previously Unidentified Release Path from Boiling Water Reactor Control Rod

Hydraulic Units

IN 90-79 Failures of Main Steam Isolation Check Valves Resulting in Disc Separation

IN-91-12 Potential Loss of Net Positive Suction Head (NPSH) of Standby Liquid Control

System Pumps

IN 91-18 High-Energy Piping Failures Caused by Wall Thinning

IN 91-18, High Energy Piping Failures Caused by Wall Thinning

Suppl. 1

IN 91-19 Steam Generator Feedwater Distribution Piping Damage

IN 91-27 Incorrect Rotation of Positive Displacement Pump

IN 91-28 Cracking in Feedwater System Piping

IN 91-32 Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and

Engineering

IN 91-38 Thermal Stratification in Feedwater System Piping

IN 91-41 Potential Problems with the Use of Freeze Seals

IN 91-43 Recent Incidents Involving Rapid Increases in Primary-to-Secondary Leak

Rate

25 NUREG/CR-6490
Table 4a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 91-50 A Review of Water Hammer Events After 1985

IN 91-56 Potential Radioactive Leakage to Tank Vented to Atmosphere

IN 91-58 Dependency of Offset Disc Butterfly Valve's Operation Orientation with

Respect to Flow

IN 91-61 Preliminary Results of Validation Testing of Motor-Operated Valve Diagnostic

Equipment

IN 91-67 Problems with the Reliable Detection of Intergranular Attack (IGA) of Steam

Generator Tubing

IN 91-69 Errors in Main Steam Line Break Analyses for Determining Containment

Parameters

IN 91-73 Loss of Shutdown Cooling During Disassembly of High-Pressure Safety

Injection System Check Valve

IN 91-80 Failure of Anchor Head Threads on Post-Tensioning System During

Surveillance Inspection

IN 91-82 Problems with Diaphragms in Safety-Related Tanks

IN 92-07 Rapid Flow-Induced Erosion/Corrosion of Feedwater Piping

IN 92-16 Loss of Flow from the Residual Heat Removal Pump during Refueling Cavity

Draindown

IN 92-16, Loss of Flow from the Residual Heat Removal Pump during Refueling Cavity

Suppl. 1 Draindown

IN 92-16, Loss of Flow from the Residual Heat Removal Pump during Refueling Cavity

Suppl. 2 Draindown

IN 92-19 Misapplication of Potter & Brumfield MDR Rotary Relays

IN 92-20 Inadequate Local Leak Rate Testing

IN 92-32 Problems Identified with Emergency Ventilation Systems for Near-Site (Within

10 miles) Emergency Operations Facilities and Technical Support Centers

IN 92-35 Higher Than Predicted Erosion/Corrosion in Unisolable Reactor Coolant

Pressure Boundary Piping Inside Containment at a Boiling Water Reactor

IN 92-36 Intersystem LOCA Outside Containment

IN 92-41 Consideration of the Stem Rejection Load in Calculation of Required Valve

Thrust

IN 92-50 Cracking of Valves in the Condensate Return Lines of a BWR Emergency

Condenser System

IN 92-57 Radial Cracking of Shroud Support Access Hole Cover Welds

IN 92-59 Horizontally-Installed Motor-Operated Gate Valves

NUREG/CR-6490 26
Table 4a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 92-60 Valve Stem Failure Caused by Embrittlement

IN 92-61 Loss of High Head Safety Injection

IN 92-63 Cracked Insulators in ASL Dry Type Transformers Manufactured by

Westinghouse Electric Corporation

IN 92-64 Nozzle Ring Settings on Low Pressure Water-Relief Valves

IN 92-65 Safety System Problems Caused by Modifications that Were Not Adequately

Reviewed and Tested

IN 92-70 Westinghouse Motor-Operated Valve Performance Data Supplied to Nuclear

Power Plant Licensees

IN 92-80 Operation with Steam Generator Tubes Seriously Degraded

IN 92-85 Potential Failures of Emergency Core Cooling Systems Caused by Foreign

Material Blockage

IN 92-86 Unexpected Restriction to Thermal Growth of Reactor Coolant Piping

IN 93-02 Malfunction of a Pressurizer Code Safety Valve

IN 93-06 Potential Bypass Leakage Paths Around Filters Installed in Ventilation

Systems

IN 93-08 Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading

IN 93-16 Failures of Nut-Locking Devices in Check Valves

IN 93-20 Thermal Fatigue Cracking of Feedwater Piping to Steam Generators

IN 93-21 Summary of NRC Staff Observations Compiled during Engineering Audits or

Inspections of Licensee Erosion/Corrosion Programs

IN 93-34 Potential for Loss of Emergency Cooling Function due to a Combination of

Operational and Post-LOCA Debris in Containment

IN 93-34, Potential for Loss of Emergency Cooling Function due to a Combination of

Suppl. 1 Operational and Post-LOCA Debris in Containment

IN 93-37 Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator

Housing Covers

IN 93-42 Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by

Velan

IN 93-43 Use of Inappropriate Lubrication Oils in Safety-Related Applications

IN 93-45 Degradation of Shutdown Cooling System Performance

IN 93-48 Failure of Turbine-Driven Main Feedwater Pump to Trip Because of

Contaminated Oil

IN 93-51 Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps

IN 93-54 Motor-Operated Valve Actuator Thrust Variations Measured with a Torque

Thrust Cell and a Strain Gage

27 NUREG/CR-6490
Table 4a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 93-55 Potential Problem with Main Steamline Break Analysis for Main Steam

Vaults/Tunnels

IN 93-59 Unexpected Opening of Both Doors in an Airlock

IN 93-61 Excessive Reactor Coolant Leakage Following a Seal Failure in a Reactor

Coolant Pump or Reactor Recirculation Pump

IN 93-62 Thermal Stratification of Water in BWR Reactor

IN 93-66 Switchover to Hot-Leg Injection Following a Loss-of-Coolant Accident in

Pressurized Water Reactors

IN 93-67 Bursting of High-Pressure Coolant Injection Steam Line Rupture Discs Injures

Plant Personnel

IN 93-68 Failure of Pump Shaft Coupling Caused by Temper Embrittlement during

Manufacture

IN 93-70 Degradation of Boraflex Neutron Absorber Coupons

IN 93-79 Core Shroud Cracking at Beltline Region Welds in Boiling-Water Reactors

IN 93-82 Recent Fuel and Core Performance Problems in Operating Reactors

IN 93-83 Potential Loss of Spent Fuel Pool Cooling Following a Loss of Coolant Accident

(LOCA)

IN 93-87 Fuse Problems with Westinghouse 7300 Printed Circuit Cards

IN 93-92 Plant Improvements to Mitigate Common Dependencies in Component Cooling

Water

IN 93-97 Failures of Yokes Installed on Walworth Gate

IN 93-101 Jet Pump Hold-Down Beam Failure

IN 94-01 Turbine Blade Failures Caused by Torsional Excitation from Electrical System

Disturbance

IN 94-03 Deficiencies Identified During Service Water System Operational Performance

Inspections

IN 94-05 Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves

IN 94-06 Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic

Depressurization System Valves

IN 94-08 Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam

Isolation Valve

IN 94-11 Turbine Overspeed and Reactor Cooldown During Shutdown Evolution

IN 94-13 Assemblies and Other Components Due to Improper Operation of Refueling

_ Equipment

IN 94-18 Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to

I Supplement 5 to Generic Letter 89-10)

NUREG/CR-6490 28
Table 4a. (Cont'd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Notice No. Title

IN 94-25 Failure of Containment Spray Header Valve to Open Due to Excessive

Pressure from Inertial Effects of Water

IN 94-27 Facility Operating Concerns Resulting from Local Area Flooding

IN 94-29 Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction

Pressure

IN 94-30 Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station

IN 94-34 Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns

IN 94-36 Undetected Accumulation of Gas in Reactor Coolant System

IN 94-38 Results of a Special NRC Inspection at Dresden Nuclear Power Station Unit 1

Following a Rupture of Service Water Inside Containment

IN 94-42 Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors

IN 94-43 Determination of Primary-to-Secondary Steam Generator Leak Rate

IN 94-44 Main Steam Isolation Valve Failure to Close on Demand Because of

Inadequate Maintenance and Testing

IN 94-45 Potential Common-Mode Failure Mechanism for Large Vertical Pumps

IN 94-48 Snubber Lubricant Degradation in High-Temperature Environments

IN 94-49 Failure of Torque Switch Roll Pins

29 NUREG/CR-6490
Table 4b. NRC Information Notices Reviewed

Electrical Components and Systems

Age

Notice No. Title Related

IN 89-03 Potential Electrical Equipment Problems No

IN 89-07 Failures Of Small-Diameter Tubing In Control Air, Fuel Oil, And Yes

Lube Oil Systems Which Render Emergency Diesel Generators

Inoperable

IN 89-11 Failure Of DC Motor-Operated Valves To Develop Rated Torque No

Because Of Improper Cable Sizing

IN 89-16 Excessive Voltage Drop In DC Systems No

IN 89-17 Contamination And Degradation Of Safety-Related Battery Cells Yes

IN 89-20 Weld Failures In A Pump Of Byron-Jackson Design Yes

IN 89-21 Changes In Performance Characteristics Of Molded-Case No

Breakers

IN 89-23 Environmental Qualification Of Litton-Veam CIR Series Electrical No

Connectors

IN 89-30 High Temperature Environments At Nuclear Power Plants No

IN 89-30-01 High Temperature Environments At Nuclear Power Plants No

IN 89-42 Failure Of Rosemount Models 1153 And 1154 Transmitters Yes

IN 89-43 Permanent Deformation Of Torque Switch Helical Springs In Yes

Limitorque SMA-Type Motor Operators

IN 89-50 Inadequate Emergency Diesel Generator Fuel Supply No

IN 89-63 Possible Submergence Of Electrical Circuits Located Above The No

Flood Level Because Of Water Intrusion And Lack Of Drainage

IN 89-64 Electrical Bus Bar Failures Yes

IN 89-66 Qualification Life Of Solenoid Valves Yes

IN 89-68 Evaluation Of Instrument Setpoints During Modifications No

IN 89-79 Degraded Coatings And Corrosion Of Steel Containment Vessels Yes

IN 89-79-01 Sustained Degraded Voltage On The Offsite Electrical Grid And No

Loss Of Other Generating Stations As A Result Of A Plant Trip

IN 89-84 Failure Of Ingersoll Rand Air Start Motors As A Result Of Pinion Yes

Gear Assembly Fitting Problems

IN 89-87 Disabling Of Emergency Diesel Generators By Their Neutral No

Ground-Fault Protection Circuitry

IN 90-18 Potential Problems With Crosby Safety Relief Valves Used On No

Diesel Generator Air Start Receiver Tanks

IN 90-22 Unanticipated Equipment Actuations Following Restoration Of No

Power To Rosemount Transmitter Trip Units

NUREG/CR-6490 30
Table 4b. (Cont'd)

Electrical Components and Systems

Age

Notice No. Title Related

IN 90-23 Improper Installation Of Patel Conduit Seals No

IN 90-25 Loss Of Vital AC Power With Subsequent Reactor Coolant System No

Heat-Up

IN 90-41 Potential Failure Of General Electric Magne-Blast Circuit Yes

Breakers And AK Circuit Breakers

IN 90-42 Failure Of Electrical Power Equipment Due To Solar Magnetic No

Disturbances

IN 90-43 Mechanical Interference With Thermal Trip Function In GE No

Molded-Case Circuit Breakers

IN 90-51 Failures Of Voltage-Dropping Resistors In The Power Supply Yes

Circuitry Of Electric Governor Systems

IN 90-51-01 Failure Of Voltage-Dropping Resistors In The Power Supply Yes

Circuitry Of Electric Governor Systems

IN 90-60 Availability Of Failure Data In The Government-Industry Data No

Exchange Program

IN 90-74 Information On Precursors To Severe Accidents No

IN 90-80 Sand Intrusion Resulting In Two Diesel Generators Becoming Yes

Inoperable

IN 91-06 Lockup Of Emergency Diesel Generator And Load Sequencer No

Control Circuits Preventing Restart Of Tripped Emergency Diesel

Generator

IN 91-11 Inadequate Physical Separation And Electrical Isolation Of Non- No

Safety-Related Circuits From Reactor Protection System Circuits

IN 91-20 Electric Wire Insulation Degradation Caused Failure In A Safety- Yes

Related Motor Control Center

IN 91-29 Deficiencies Identified During Electrical Distribution System No

Functional Inspections

IN 91-29-02 Potential Deficiencies Found During Electrical Distribution No

System Functional Inspections

IN 91-34 Potential Problems In Identifying Causes Of Emergency Diesel No

Generator Malfunctions

IN 91-45 Possible Malfunction Of Westinghouse ARD, BFD, And NBFD Yes

Relays, And A 200 DC And DPC 250 Magnetic Contactors

IN 91-46 Degradation Of Emergency Diesel Generator Fuel Oil Delivery Yes

Systems

IN 91-47 Failure Of Thermo-Lag Fire Barrier Material To Pass Fire No

Endurance Test

31 NUREG/CR-6490
Table 4b. (Contd)

Electrical Components and Systems

Age

Notice No. Title Related

IN 91-53 Failure Of Remote Shutdown System Instrumentation Because No

Of Incorrectly Installed Components

IN 91-57 Operational Experience On Bus Transfers No

IN 91-62 Diesel Engine Damage Caused By Hydraulic Lockup Resulting Yes

From Fluid Leakage Into Cylinders

IN 91-74 Changes In Pressurizer Safety Valve Setpoints Before Installation No

IN 91-78 Status Indication Of Control Power For Circuit Breakers Used In Yes

Safety-Related Applications

IN 91-79 Deficiencies In The Procedures For Installing Thermo-Lag Fire No

Barrier Materials

IN 91-81 Switchyard Problems That Contribute To Loss Of Offsite Power Yes

IN 91-83 Solenoid-Operated Valve Failures Resulted In Turbine Overspeed Yes

IN 91-85 Potential Failures Of Thermostatic Control Valves For Diesel Yes

Generator Jacket Cooling Water

IN 91-87 Hydrogen Embrittlement Of Raychem Cryofit Couplings Yes

IN 92-03 Remote Functions In General Electric F-Frame Molded-Case No

Circuit Breakers

IN 92-04 Potter & Brumfield Model MDR Rotary Relay Failures Yes

IN 92-05 Potential Coil Insulation Breakdown In ABB RXMH2 Relays No

IN 92-06 Reliability Of ATWS Mitigation System And Other NRC Required No

Equipment Not Controlled By Plant Technical Specifications

IN 92-09 Overloading And Subsequent Lock Out Of Electrical Buses No

During Accident Conditions

IN 92-12 Effects Of Cable Leakage Currents On Instrument Settings And No

Indications

IN 92-23 Results Of Validation Testing Of Motor-Operated Valve No

Diagnostic Equipment

IN 92-27 Thermally Induce Accelerated Aging And Failure Of Ite/Gould Yes

A.C. Relays Used In Safety-Related Applications

IN 92-29 Potential Breaker Miscoordination Caused By Instantaneous Trip No

Circuitry

IN 92-31 Electrical Connection Problem In Johnson Yokogawa Corporation No

YS-80 Programmable Indicating Controllers

IN 92-33 Increased Instrument Response Time When Pressure Dampening No

Devices Are Installed

NUREG/CR-6490 32
Table 4b. (Contd)

Electrical Components and Systems

Age

Report Title Related

IN 92-40 Inadequate Testing Of Emergency Bus Undervoltage Logic No

Circuitry

IN 92-43 Defective Molded Phenolic Armature Carriers Found On No

Elmwood Contactors

IN 92-44 Problems With Westinghouse DS-206 Type Circuit Breakers Yes

IN 92-45 Incorrect Relay Used In Emergency Diesel Generator Output No

Breaker Control Circuitry

IN 92-46 Thermo-Lag Fire Barrier Material Special Review Team Final No

Report Findings, Current Fire Endurance Tests, And Ampacity

IN 92-47 Intentional Bypassing Of Automatic Actuation Of Plant Protective No

Features

IN 92-48 Failure Of Exide Batteries Yes

IN 92-51 Misapplication And Inadequate Testing Of Molded-Case Circuit No

Breakers

IN 92-53 Potential Failure Of Emergency Diesel Generators Due To No

Excessive Rate Of Loading

IN 92-54 Level Instrumentation Inaccuracies Caused By Rapid No

Depressurization

IN 92-55 Current Fire Endurance Test Results For Thermo-Lag Fire No

Barrier Material

IN 92-67 Deficiency Of Design Modifications To Address Failures Of Hiller No

Actuators Upon A Gradual Loss Of Air Pressure

IN 92-69 Water Leakage Yard Through Conduits Into Building No

IN 92-78 Piston To Cylinder Liner Tin Smearing On Cooper-Bessemer KSV Yes

Diesel Engines

IN 92-81 Potential Deficiency Of Electrical Cables With Bonded Hypalon No

Jackets

IN 92-82 Results Of Thermo-Lag 330-1 Combustibility Testing No

IN 92-83 Thrust Limits For Limitorque Actuators And Potential No

Overstressing Of Motor-Operated Valves

IN 93-05 Storm-Related Loss Of Offsite Power Events Due To Salt Buildup Yes

On Switchyard Insulators

IN 93-09 Failure Of Undervoltage Trip Attachment On Westinghouse No

Model DB-50 Reactor Trip Breaker

IN 93-11 Single Failure Vulnerability Of Engineered Safety Features No

Actuation Systems

33 NUREG/CR-6490
Table 4b. (Cont'd)

Electrical Components and Systems

Age

Report Title Related

IN 93-15 Failure To Verify The Continuity Of Shunt Trip Attachment No

Contacts In Manual Safety Injection And Reactor Trip Switches

IN 93-22 Tripping Of Klockner-Moeller Molded-Case Circuit Breakers Due Yes

To Support Lever Failure

IN 93-23 Weschler Instruments Model 252 Switchboard Meters Yes

IN 93-25 Electrical Penetration Assembly Degradation No

IN 93-26 Grease Solidification Causes Molded-Case Circuit Breaker Yes

Failure To Close

IN 93-27 Level Instrumentation Inaccuracies Observed During Normal No

Plant Depressurization

IN 93-33 Potential Deficiency Of Certain Class le Instrumentation And Yes

Control Cables

IN 93-37 Eyebolts With Indeterminate Properties Installed In Limitorque No

Valve Operator Housing Covers

IN 93-46 Potential Problem With Westinghouse Rod Control System And No

Inadvertent Withdrawal Of A Single Rod Control Cluster

Assembly

IN 93-47 Unrecognized Loss Of Control Room Annunciators No

IN 93-49 Improper Integration Of Software Into Operating Practices No

IN 93-64 Periodic Testing And Preventive Maintenance Of Molded Case Yes

Circuit Breakers

IN 93-65 Reactor Trips Caused By Breaker Testing With Fault Protection No

Bypassed

IN 93-74 High Temperatures Reduce Limitorque AC Motor Operator No

Torque

IN 93-75 Spurious Tripping Of Low-Voltage Power Circuit Breakers With No

GE RMS-9 Digital Trip Units

IN 93-87 Fire Problems With Westinghouse 7300 Printed Circuit Cards No

IN 93-89 Potential Problems With BWR Level Instrumentation Backfill No

Modifications

IN 93-91 Misadjustment Between General Electric 4.16-LV Circuit No

Breakers And Their Associated Cubicles

IN 93-99 Undervoltage Relay And Thermal Overload Setpoint Problems No

IN 94-02 Inoperability Of General Electric Magne-Blast Breaker Because No

Of Misalignment Of Close-Latch Spring

IN 94-04 Digital Integrated Circuit Sockets With Intermittent Contact Yes

NUREG/CR-6490 34
Table 4b. (Cont'd)

Electrical Components and Systems

Age

Report Title Related

IN 94-10 Failure Of Motor-Operated Valve Electric Power Train Due To No

Sheared Of Dislodged Motor Pinion Gear Key

IN 94-19 Emergency Diesel Generator Vulnerability To Failure From Cold No

Fuel Oil

IN 94-20 Common-Cause Failures Due To Inadequate Design Control And No

Dedication

IN 94-33 Capacitor Failures In Westinghouse Eagle 21 Plant Protection Yes

Systems

IN 94-34 Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns No

IN 94-40 Failure Of A Rod Control Cluster Assembly To Fully Insert No

Following A Reactor Trip At Braidwood Unit 2

IN 94-41 Problems With General Electric Type Cr124 Overload Relay No

Ambient Compensation I_ I

35 NUREG/CR-6490
Table 5a. NRC Licensee Event Reports Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Title

LER 86-008, Main Coolant Pump Suction Valve Stem Failure

Rev. 1

LER 86-017, Local Leak Rate Test Results of App. J Related Valves in Excess of Limits

Rev. 1

LER 88-014 Primary Containment Penetration Local Leak Rate Test Failures

Rev. 1

LER 89-001 Oxidation of Division 2 Fuel Oil Resulted in Division 2 Diesel Generator Being

Inoperable when Division 1 Generator was Out for Planned Maintenance

LER 89-001, Oxidation of Division 2 Fuel Oil Resulted in Division 2 Diesel Generator Being

Rev. 1 Inoperable when Division 1 Generator was Out for Planned Maintenance

LER 89-005 Containment Vent Valve Seal Degradation Discovered

LER 89-011 Turbine Stop Valve Closure Due to Auto Stop Oil Line Break

LER 89-016- Auxiliary Feedwater Pump FW-10 Outside Design Basis

Rev. 2

LER 90-021 Containment Spray Header Clogged Nozzles Due to Pipe Wall Coating Material

Aging

LER 90-022 Degraded Fire Penetration Seals as Result of Inadequate Construction

Technique

LER 91-011 Discussion of Additional Design Features & Required Functions of

Rev. 2 Containment Electrical Penetration Assembly Seals not Included in Revs. 0 &

1 of LER

LER 92-001 ESF Component Actuation: 12GB4 (Cont. Isol. Valve) Failed-Closed Twice Due

to Equipment Failure

LER 92-003 Manual Reactor and Main Turbine Trip Due to Failed Expansion Joint in 21

Main Condenser

LER 92-006 Reactor Shutdown to Modify and Test Emergency Core Cooling and

Containment Spray Minimum Flow Isolation Valves

LER 92-007 Reactor Trip Due to Failure of the Low Pressure Turbine Exhaust Boot Seal

LER 92-008 Spent Fuel Pool Exhaust Ventilation System Inoperable Due to Unacceptable

Leakage Around the Charcoal Absorber

LER 92-009 Analyzer Failed with the Redundant Monitor Having Its Emergency Power

Source Inoperable

LER 92-010 Reactor Trip Due to Low Pressure Turbine Exhaust Boot Seal Failure

LER 92-013 Local Leak Rate Test Results in Excess of Limits Due to Valve Degradation

Rev. I

LER 92-026 Breach of Containment Integrity Due to Failure of Personnel Airlock Door

NUREG/CR-6490 36
Table 5a. (Contd)

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Title

LER 93-001 Technical Specification 3.0 Implementation Due to Excessive PPS Leakage

LER 93-001 Manual Reactor Trip Following a Steam Generator Tube Rupture

Rev. 2

LER 93-005 Failure of the Drywell Vent Valve 3-1601-63 Due to a Degraded O-Ring on

the Two-Way Versa Valve

LER 93-003 Main Steam Isolation Valve Local Leak Rate Exceeded

Rev. 1

LER 93-003 Main Steam Isolation Valve Local Leak Rate Exceeded

Rev. 2

LER 93-007 Discovery That Certain Valves Should be Subject to ASME Section XI Testing

LER 93-0 10 Failure of an Essential Cooling Water Traveling Screen Coupling

LER 94-005 Failure of Control Rod to Scram Due to Degradation of Pilot Valve Elastomers

Caused by In-Service Aging

LER 94-005 Failure of Control Rod to Scram Due to Degradation of Pilot Valve Elastomers

Rev. 1 Caused by In-Service Aging

37 NUREG/CR-6490
Table 5b. NRC Licensee Event Reports Reviewed

Electrical Components and Systems

Report Title

LER 88-011-282 Auto-Start Of Train A Of Auxiliary Building Special Ventilation

System As A Result Of A Radiation Monitor Spike

LER 88-033-02-327 Unplanned Reactor Trip Signal Due To A Reactor Protection System

(RPS) Channel 1 Instrument Failure During RPS Channel 2

Calibration

LER 89-001-280 Unplanned Auto Start Of #3 EDG Due To Failed Diode

LER 89-002-331 Age-Related Failure Of A Governor Printed Circuit Board Results In

High Pressure Coolant Injection System Inoperability

LER 89-003-263 Isolation Of Reactor Water Cleanup System Due To Capacitor

Failure In Filter/Demineralizer Inlet Temperature Indication Switch

LER 89-006-261 Reactor Trip Due To Loss Of Turbine E-H Control Power Supplies

LER 89-010-362 Fuel Handling Isolation System Train "A" Actuation Due To Power

Supply Failure

LER 89-014-271 Reactor Core Isolation Cooling System Inoperable Due To Motor

Burn Out

LER 89-015-327 Control Room Isolation Resulting From A Worn Set Of Contacts In

The 480 V Motor Starter For A Main Control Room Ventilation

Intake Radiation Monitor

LER 89-019-01-325 Failure Of Service Water System To Meet Design Requirements

LER 89-020-01-528 Apparent Ground Causes Control Element Assembly Slip

LER 89-031-01-302 Failure Of "A" 480 V Engineered Safeguards Transformer Causes

Temporary Interruption Of Decay Heat Cooling And A Plant

Operational Mode Change

LER 90-007-01-388 ESF Actuations Due To RPS EPA Breaker Spurious Trip

LER 90-018-244 Dropped Control Rod During Rod Control Exercise Causes

Automatic Actuation Of RPS

LER 90-022-01-344 Degraded Fire Penetration Seals As A Result Of Inadequate

Construction Technique

LER 90-023-325 Partial Group 6 Isolation Resulting From Failure Of Relay I-Cac-3a

LER 90-023-424 Transformer Failure Results In Loss Of Steam Generator Level And

Manual Reactor Trip

LER 90-029-01-325 Cbeaf System Actuation Resulting From The Failure Of The 1-D22aK2 Relay Coil.

LER 91-001-293 Automatic Closing Of The Primary Containment System Group 5

Isolation Valves During Surveillance Testing

LER 91-002-01-327 EGTS Inoperable Because Of A Train EGTS Being Out Of Service

For Filter Testing And B Train Diesel Generator Being Declared

Inoperable Resulting ---

NUREG/CR-6490 38
Table 5b. (Contd)

Electrical Components and Systems

Report Title

LER 91-006-530 ESF Actuation Due To Loss Of Power To 4.16 kV Bus

LER 91-007-456 Rod Control System Failure Causes Shutdown Bank Control Rods

To Be In A Condition Prohibited By Technical Specifications

LER 91-008-260 Unplanned Engineered Safety Features Actuation Due To A Failed

PCIS Relay

LER 91-010-01-155 Reactor Protection System Pressure Switches Experiencing Setpoint

Drift; Revision 1

LER 91-014-01-498 Erratic Containment Extended Range Pressure Channel Output

LER 91-016-260 Unplanned Engineered Safety Features Actuation Due To A Blown

Fuse Caused By A Failed Relay

LER 91-016-424 Failure To Complete Technical Specification Required Action For

Battery Cell Low Voltage

LER 91-020-237 Reactor Building Ventilation Isolation And Automatic Standby Gas

Treatment Initiation Due To Radiation Monitor Power Supply

Failure

LER 91-021-254 RCIC Declared Inoperable Due To High Pump Flow In ISI Required

Action Range

LER 91-028-325 Component Failure Of A Reactor Water Cleanup System Isolation

Logic Relay Resulted In An Unplanned Engineered Safety Feature

Actuation

LER 91-028-254 Loss Of Power To la RPS Bus Caused By EPA la-1 Tripping On

Undervoltage Due To Low M-G Set Output

LER 91-030-423 Motor Control Center Auxiliary Control Relay Failure Due To

Thermal Aging

LER 92-001-263 Shutdown Required By Technical Specification Due To Inoperable

Bellows Leak Detection System For Safety Relief Valves

LER 92-001-155 Brittle Motor Lead Wires Discovered In Vop-7050 (Main Steam

Isolation Valve-MSIV)

LER 92-001-296 Engineered Safety Feature Actuation Caused By A Failed Relay Coil

LER 92-001-339 Reactor Trip Caused By MFRV Closure Upon Failure Of Driver Card

LER 92-002-247 Reactor Trip Due To Main Feedwater Regulating Valve Going Closed

LER 92-004-389 Manual Reactor Trip Due To Low Steam Generator Water Level

Caused By A Failed Circuit In The 2a Feedwater Regulating Control

System.

LER 92-006-331 Emergency Safety Feature Actuation During Modification

Acceptance Testing Due To Damaged Switchyard Cable

39 NUREG/CR-6490
Table 5b. (Contdd)

Electrical Components and Systems

Report Title

LER 92-006-354 Reactor Shutdown To Comply With Technical Specification 3.6.1.1,

Due To Failure Of Suppression Chamber To Drywell Vacuum

Breakers

LER 92-007-01-333 Failure Of Analog Transmitter Trip System (ATTS) Trip Relays Due

To Thermal Aging

LER 92-009-01-499 Missed Technical Specification Required Surveillance Due To A

Faulty Toxic Gas Monitoring System Modem

LER 92-011-325 Primary Containment Monitoring System Inoperability Due To Relay

Failure

LER 92-021-237 Automatic Isolation Of Reactor Building Ventilation Due To

Radiation Monitor Trip Relay Failure

LER 92-034-01-333 Engineered Safety Feature Actuations Due To Transformer Failure

LER 92-038-255 Reactor Trip Caused By A Loss Of The Preferred AC Bus Y-20

Coincident With A Blown Fuse In A Second Channel Of The Reactor

Protective System

LER 93-002-249 Control Valve Fast Closure Half-Scram Pressure Switches Out-Of

Calibration Due To Setpoint Drift

LER 93-003-530 Emergency Diesel Generator Unable To Start And Run In Manual

Test Mode

LER 93-005-01-305 Annual Transmitter Calibration Finds A Shift In The Pressurizer

High Pressure Reactor Trip Signal Initiation Due To Instrument

Drift.

LER 93-005-01-275 Medium Voltage Cable Failures Due To Chemical Degradation And

Unknown Causes

LER 93-009-498 Technical Specification 3.0.3 Entry Due To Potentially Undersized

Fuses In The Solid State Protection System

LER 93-007-249 Yarway Reactor Water Level Switch Failure

LER 93-008-237 Yarway Reactor Water Level Switch Failure

NUREG/CR-6490 40
Table 6a. NRC Bulletins Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Bulletin No. Title

BL 89-01 Failure of Westinghouse Steam Generator Tube Mechanical Plugs

BL 89-01. Failure of Westinghouse Steam Generator Tube Mechanical Plugs

Suppl. 1

BL 89-01. Failure of Westinghouse Steam Generator Tube Mechanical Plugs

Suppl. 2

BL 89-02 Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal

Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves of

Similar Design

Table 6b. NRC Bulletins Reviewed

Electrical Components and Systems

Bulletin No. Title

"BL 90-01 Loss of Fill-Oil in Transmitters Manufactured By Rosemount

41 NUREG/CR-6490
Table 7a. NUMARC Industry Reports Reviewed

Mechanical, Structural, and Thermal-Hydraulic Components and Systems

Report No. Title

IR 90-01 PWR Containment Structures License Renewal Industry Report

IR 90-02 BWR Pressure Vessel License Renewal Industry Report

IR 90-03 BWR Vessel Internals License Renewal Industry Report

IR 90-04 PWR Vessel License Renewal Industry Report

IR 90-05 PWR Reactor Pressure Vessel Internals License Renewal Industry Report

IR 90-06 Class 1 Structures License Renewal Industry Report

IR 90-07 PWR Reactor Coolant System License Renewal Industry Report

IR 90-09 BWR Primary Coolant Pressure Boundary License Renewal Industry Report

IR 90-10 BWR Containments License Renewal Industry Report

Table 7b. NUMARC Industry Reports Reviewed

Electrical Components and Systems

Report No. Title

IR 90-08 Low Voltage Environmentally-Qualified Cable License Renewal Industry

Report

NUREG/CR-6490 42
Table 8. Standardized ARD Mechanisms, Definitions, and Associated Effects

Abbrevi- ARD ARD

ation Mechanism Definition Effect

ADH Adhesion Undesired adherence of intermittently Loss of movement

contacting surfaces of moving parts, as in

valves

AGR- Aggressive Breakdown of cement phases in concrete Loss of integrity;

CHEM chemicals caused by contact with aggressive chemical Increase of porosity

(e.g., acidic groundwaters) & permeability,

cracking, & spalling

AGREAC Reaction Chemical reactions between aggregates & Expansion &

with alkalies that are introduced by cement or cracking

Aggregates may come from admixtures, saltcontaminated aggregates, or penetration by

seawater or deicing salt solution

BIO Biofouling Buildup of micro- or macro-organisms on Buildup of deposits

component surfaces, resulting in flow

constriction, reduced heat transfer, etc. See

also CORR/MIC.

CATH Cathodic Softening of concrete at the reinforcing bar Loss of bond strength

protection surface when exposed to direct current for

effects on extended period of time

bond

strength

CLOG Clogging Buildup of foreign particles or contaminants Blockage of flow

leading to restricted flow of air or coolant passages

CONCAL Concrete Concrete strength can be reduced when it is Reduction of concrete

interaction pumped through aluminum piping during strength

with placement

aluminum

CONTAM Contamin- Undesirable introduction of foreign materials Buildup of deposits;

ation such as dust, wear debris. etc. onto critical loss of desired

surfaces or into lubricant surface properties;

loss of lubricant

properties

CORR Corrosion Chemical interaction with environment Loss of material;

resulting in loss of material or buildup of corrosion product

corrosion products buildup

CORR/ Corrosion of Corrosion of embedded or reinforcing steel Cracking, spalling,

RE embedded or caused by a decrease in concrete's alkalinity loss of bond, loss of

reinforcing (pH < 11.5) due to leaching of alkaline material

steel products, entry of acidic materials, or

carbonation

43 NUREG/CR-6490
Table 8. (Cont'd)

Abbrevi- ARD ARD

ation Mechanism Definition Effect

CORR/ Oxidation Corrosive reaction resulting in the Loss of material:

OX production of a surface oxide layer or corrosion product

internal oxidation of the material buildup; internal

damage

CORR/ Pitting Localized corrosion resulting in surface pits Local loss of material

PIT corrosion or holes

CORR/ Uniform Uniform corrosive loss of material over a Loss of material:

UA corrosion finite area corrosion product

(wastage) buildup

CORR/ Intergranu- Corrosive attack and penetration of the Crack initiation and

IN lar corrosive material along the grain boundaries with growth

attack negligible attack of the remainingmaterial

CORR/ Stress Cracking produced by the simultaneous Crack initiation and

SCC corrosion presence of a susceptible material, tensile growth

cracking stress, and a corrosive environment

CORR/ Primary A form of stress corrosion cracking observed Crack initiation and

PWSCC water stress on the primary water side of PWR steam growth

corrosion generators and related components

cracking

CORR/ Irradiation A form of stress corrosion cracking enhanced Crack initiation and

IASCC assisted by the presence of a significant neutron growth

stress irradiation field (fluence >= 1020 n/cm2 )

corrosion

cracking

CORR/ Transgranu- The transgranular form of SCC Crack initiation and

TGSCC lar stress growth

corrosion

cracking

CORR/ Intergranu- The intergranular form of SCC Crack initiation and

IGSCC lar stress growth

corrosion

cracking

CORR/ Crevice Localized corrosion produced by the Local loss of

CREV corrosion concentration of corrosive chemical species material; crack

in crevices initiation and growth

CORR/ Leaching Selective dissolution of a specific phase or Loss of material

LEACH corrosion chemical species by service environment soundness

NUREG/CR-6490 44
Table 8. (Cont'd)

Abbrevi- ARD ARD

ation Mechanism Definition Effect

CORR/ Microbio- Corrosion produced by micro- or macro- Loss of material;

MIC logically biological organisms, caused by the corrosion product

influenced production of corrosive substances, buildup

corrosion deposition, etc.

CORR/ Saline water Corrosion of reinforced concrete by salt Loss of strength

SA attack water attack of reinforcing bars

CORR/ Boric acid Corrosion of carbon and low-alloy steel Loss of material

BA corrosion produced by leakage of BWR primary coolant

containing boric acid

CREEP Creep Progressive plastic deformation produced by Change in dimension

exposure to elevated temperatures and/or

irradiation under stress

CURSTR Current Abnormal current exceeding limits or short Equipment

stress circuit temperature rise,

equipment

degradation,

dielectric loss,

insulation

breakdown

DRIFT Signal drift Various stressors can cause electrical Loss of calibration or

instrumentation or equipment set points or function

signals to drift

ELE- Elevated- Progressive physical or chemical degradation Chemical or physical

TEMP temperature induced by prolonged exposures to elevated degradation, thermal

degradation temperatures distortion; loss of

strength & modulus

EMBR Embrittle- Loss of material ductility resulting from Loss of fracture

ment chemical or microstructural changes toughness

induced by the operating environment

EMBR/ Irradiation Embrittlement induced by exposure to Loss of fracture

IR embrittle- neutron irradiation toughness; loss of

ment strength & modulus

(of concrete)

EMBR/ Thermal Embrittlement induced by microstructural Loss of fracture

TE embrittle- changes induced by prolonged exposures to toughness

ment elevated temperatures

EMBR/ Hydrogen Embrittlement induced by absorption of Loss of fracture

HY embrittle- hydrogen toughness

ment

45 NUREG/CR-6490
Table 8. (Cont'd)

Abbrevi- ARD ARD

ation Mechanism Definition Effect

EMBR/ Strain aging Embrittlement caused by strain aging Loss of fracture

SA embrittle- associated with the redistribution of carbon toughness

ment and nitrogen atoms in cold-worked carbon

steel

ENVIR Environ- Progressive physical or chemical degradation Chemical or physical

mental induced by prolonged exposures to the degradation

degradation service environment. See also ELETEMP.

ERO Erosion Loss of surface material at locations Wall thinning; loss of

impinged by high-velocity gas or liquid material

streams, sometimes containing solid

particles

ERO/ Erosion/ Accelerated form of corrosion caused by Wall thinning; loss of

CORR corrosion removal of surface oxide layer due to material

impingement of high-velocity stream

ERO/ Cavitation Erosive attack associated with the alternate Wall thinning; loss of

CAV erosion formation and collapse of bubbles, as in material

pumps, etc.

EXFORCE Excessive Greater than expected force Causes distortion or

force bending

FAT Fatigue Progressive loss of structural integrity Cumulative fatigue

associated with the initiation and growth of damage

cracks under cyclic loading conditions

FAT/ENV Environmen- Decreased fatigue life due to environment of Cumulative fatigue

tally assisted LWR reactor coolants damage

fatigue

FAT/FIV Flow- Fatigue resulting from flow-induced Cumulative fatigue

induced vibrations damage

vibrational

fatigue .

FAT/ Thermal Fatigue resulting from cyclic thermal Cumulative fatigue

THERM fatigue stresses damage

FRZ/ Freeze-thaw Breakdown of concrete caused by expansion Loss of integrity;

THAW cycles associated with repeated freeze-thaw cycles, Scaling, cracking, &

especially when wet spalling

GAS Gassing, loss Battery outgassing and material plating out Loss of battery

of material to capacity, won't hold

battery charge

plates

NUREG/CR-6490 46
Table 8. (Cont'd)

Abbrevi- ARD ARD

ation Mechanism Definition Effect

LEACH Leaching Degradation of concrete caused by Loss of integrity;

contacting water leaching out the Ca(OH)2 Increase of porosity

phase, resulting in disintegration & permeability

LOSLUB Loss of Loss of lubricity due to evaporation or Viscosity change,

lubricant contamination loss of lubricity,

allows rapid metal

wear

LOTEMP Low Lower than normal range Deterioration of

temperature normal function

MECHSTR Mechanical Exceeding normal stress range Deterioration of

stress mechanical function,

cracks, distortion,

creep

MASON- Restraint, Cracking of masonry block walls due to Cracking of masonry

BLOC shrinkage, restraint against expansion or contraction block walls

creep, & caused by changes in temperature, moisture,

aggressive or carbonation; or from shrinkage, creep, or

environment aggressive environment

MOIST Moisture Accumulation of moisture in filter media Increased pressure

retention drop; reduced

strength

MOIST- High Moisture in dielectric material Loss of dielectric

EL humidity, or properties, increase

moisture in conductivity,

present reduces life, &

molecular breakdown

PART Particle Accumulation of foreign particles in filter Increased pressure

retention media drop

PRESS- Pressure Repeated pressure changes through normal Deterioration of

CY cycles pressure range spring function

(spring becomes set)

RAD Nuclear Gamma or neutron radiation causing Both mechanical and

radiation degradation effects. electrical properties

degrade resulting in

embrittlement,

cracking,

discoloration, and

disintegration

47 NUREG/CR-6490
Table 8. (Cont'c)

Abbrevi- ARD ARD

ation Mechanism Definition Effect

RATCH Ratchetting Progressive plastic deformation caused by Change in dimension

cyclic loading with a superimposed tensile

mean stress

RELAX Stress Progressive reduction of intentional Loss of preload;

relaxation secondary stress produced by exposure to reduction of design

elevated temperatures and/or irradiation margin

under stress

RESID Residual Internal stresses introduced during Crack initiation

stresses fabrication or prior deformation

SETTLE Settlement Settlement of foundations & structures as Cracking, distortion,

they are constructed and during their early increase in

life component stress

level

SHRINK Shrinkage Reduction in one or more physical Change in dimension

dimensions

THERM- Thermal Repeated temperature changes through Deterioration of

CY cycles normal temperature range insulation, forms

cracks.

VIBR Vibration Moderate-to-high-frequency periodic motion Loosening; crack

resulting in loosening of component and initiation and growth

fittings, crack initiation, etc.

VOLSTR Voltage Over voltage (in excess of tolerance or design Corona or ionization

stress limit) may include freq., rate, duration, or discharge causing

magnitude burnout or degradation of insulation and

electronics

VOLSTR- Chemical Chemical effects related to corona, forms Reddish or white

CH effects nitrous oxide in presence of water molecules deposits in

related to insulation. degrades

voltage insulation

stress

WEAR Wear Loss of surface material caused by relative Attrition, lockup

motion between contacting surfaces

WEAR/ Fretting wear Form of wear produced by vibrational Attrition

FRET rubbing of adjacent surfaces, as from flowinduced vibration of steam generator tubes

WEAR/ Denting Constriction of steam generator tubes Constriction

DENT produced by formation of corrosion products

between tubes and adjacent surfaces

NUREG/CR-6490 48
Table 8. (Cont'dJ

Abbrevi- ARD ARD

ation Mechanism Definition Effect

WEAR/ Galling Form of rubbing wear characterized by Attrition

GALL excessive friction and localized welding at

high spots, followed by tearing and surface

roughening

WEATH Weathering Saturation of adsorber medium by adsorbed Loss of capacity

species

49 NUREG/CR-6490
References

1. "World Nuclear Industry Handbook," Nuclear Engineering International, Surrey, U.K.

(1994).

NUREG/CR-6490 50
Appendix A: GALL Literature Review Tables - NPAR Reports, NRC

Generic Letters, Information Notices, Licensee Event

ReDorts. and NRC Bulletins

51 51 NUREG/CR-6490

A.1 Mechanical, Structural, and Thermal-Hydraulic Components and Systems

53 53 NUREG/CR-6490
Table A.1 Gall Report for NPAR Reports Page 1A

Document: BNL A-3270, 11-26-84, Soaping Tests on Containment Purge and Vent Valve Seal Material

Reviewed by: Jeffrey L. Binder, ANL

Item Svstem StructureJComo Subcomoonent Materials Manufact•urer ARD mechanism ARD effects

butterfly valves Company degradation lCon 1 tanm ent JPurge and vent e IValve se a] material Ethy lene pr opylene Pa o rker pn Sea ] JE VRuryvl Chemical to or physc7erd 

Document: BNL A-3270, 12-85, Pilot Assessment: Impact of Aging on the Seismic Performance of Selected Equipment Types

Reviewed by: Jeffrey L. Binder, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Electric motors Bearings Not stated Allis-Chalmers VIBR Loosening

(<100 hp),

Fairbanks-Morse

and General Electric

(>= 100 hp)

2 Various Motor-operated Motor operators Not stated Limitorque Not stated Not stated

valves

3 Various Relays Not stated Not stated General Electric Co. Not stated Not stated

4 Various Circuit breakers Not stated Not stated General Electric Co. Not stated Not stated

5 Various Motor control Not stated Not stated Square D, General Not stated Not stated

centers Electric Co.

Document: BNL A-3270, 6-21-91, Degradation Modeling: Extensions and Applications

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various reactor Various, including This report does not

systems, including residual heat provide specific

the ECCS, service removal (RHR) detailed information

air, and service pumps, air on age-ralated

water. compressors, and degradation

service water pumps processes for

specific nuclear

components or

I_ I systems.

Document- BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Regulating valves Operator Not stated Not stated VIBR; CONTAM Loosening; loss of

(feedwater) desired surface

properties

2 Cooling system Motor-driven pumps Bearings and seals Not stated Not stated VIBR; CONTAM Loosening; loss of

(feedwater) desired surface

I_ properties 3Cooling system Motor-driven pumps Shaft or impeller Not stated Not stated FAT Cumulative fatigue

(feedwater) damage

4 Cooling system Motor-driven pumps Casing Not stated Not stated ERO/CORR Wall thinning; loss o

(feedwater) s proprtIematerial

Cooling system

(feedwater)

Turbine-driven

pumps

Seals Non stated Not stated CONTAM Loss of desired

surface properties
Table A.1 Gall Report for NPAR Reports Page 1B

Document: BNL A-3270, 11-26-84, Scoping Tests on Containment Purge and Vent Valve Seal Material

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Comoonent Function Contrib to Failure Reoorted nroas Rel.proqs Report Recommendations Paqe No. Item

Exposure to a containment environment Not stated Not discussed in ASME Sec Xl Not stated 3

characteristic of a severe accident report 1 or PS S&T

situation causes accelerated degradation I Req.

and cracking of the valve seat material _

Document: BNL A-3270, 12-85, Pilot Assessment: Impact of Aging on the Seismic Performance of Selected Equipment Types

Reviewed by: Jeffrey L Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rei.progs Report Recommendations Page No. Item

Misalignment induced by vibration causes Frequent Not discussed in PS S&T Req. Aging was not found to affect the 2-7 1

burnout of bearings, report seismic capacity of the components

considered as long as routine

preventative maintenance is __________________________ ____________ ____________ _________performed. [2]

Not stated Not stated Not discussed in ASME Sec XI Aging was not found to affect the 2-14 2

report & GL 89-10 & seismic capacity of the components

Suppl. considered as long as routine

preventative maintenance is

performed. (2]

Not stated Not stated Not discussed in If Class 1 E Aging was not found to affect the 2-18 3

report 1OCFR 50.49 seismic capacity of the components

otherwise PS considered as long as routine

S&T Req.. preventative maintenance is

performed. [2]

Not stated Not stated Not discussed in If Class 1 E Aging was not found to affect the 2-16 4

report 10CFR 50.49 seismic capacity of the components

otherwise PS considered as long as routine

S&T Req. preventative maintenance is

performed. [2]

Not stated Not stated Not discussed in If Class 1 E Aging was not found to affect the 2-18 5

report IOCFR 50.49 seismic capacity of the components

otherwise PS considered as long as routine

S&T Req. preventative maintenance is

performed. [2)

Document: BNL A-3270, 6-21-91, Degradation Modeling: Extensions and Applications

Reviewed by: Jeffrey L Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

S 1

Document: BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure caused by valve-induced vibration Frequent Not discussed in ASME Sec Xl Not stated 19 1

and contamination of the instrument air report & PS TS Req.

system by oil, moisture and/or rust, or

other foreign particles.

Loss of pump-to-motor alignment and Frequent Not discussed in ASME Sec Xl- Not stated 19 2

consequent pump instability, report IWP & PS TS

Req.

Not stated Occasional Not discussed in ASME Sec XI- Not stated 19 3

report IWP & PS TS

Req. & ASME

Sec III a

Not stated Rare Not discussed in ASME Sec XI Not stated 20 4

1 report IWB_

Failure of seals from contamination

results in subsequent lubricant

contamination from by steam leaking past

seals.

Infrequent Not discussed in

report

ASME Sec XlIWP & PS TS

Req.

Not stated 20 S
Table A.1 Gall Report for NPAR Reports Page 2A

Document: BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mech.anism ARD effects

61 Cooling system Turbine-driven Govemor Not stated Not stated CONTAM Loss of desired

(feedwater) pumps surface properties

7 Main turbine Electrohydraulic The report does not

control discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

8 Main generator The report does not

discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

9 Condensate system The report does not

discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

10 Electrical distribution The report does not

system discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

11 Circulating water

system

The report does not

discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.
Table A.1 Gall Report for NPAR Reports Page 213

Document: BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Mechanical failure of governor results Occasional Not discussed in ASME Sec Xl- Not stated 20 6

from contamination of control oil. report IWP & PS TS

Req.

No input for 7

current

programs

column

No input for 8

current

programs

column

Not discussed in No input for Not stated 9

report current

programs

column

Not discussed in No input for Not stated 10

report current

programs

column

No input for

current

programs

column

11
Table A.1 Gall Report for NPAR Reports Page 3A

Document: BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comi, Subcomponent Materials Manufacturer ARD mechanism ARD effects

12 Service/instrument The report does not

air system discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

13 Fire protection The report does not

system discuss specific

components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

14 Heating, ventilating, The report does not

and air conditioning discuss specific

system components and

aging mechanisms

for these systems.

However, they are

identified as

important for

considering aging

degradation, since

their failure can

cause unplanned

reactor scrams.

Document: BNL A3270, 12-86, Aging and Life Extension Assessment Program (ALEAP) Systems Level Plan

Reviewed by, Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various reactor Various, including This report does not

systems, including residual heat provide specific

the ECCS and removal (RHR) detailed information

service water pumps and service on age-related

water pumps degradation

processes for

specific nuclear

components or

systems.

Document: BNL TR-3270-6-90, Maintenance Team Inspection Results: Insights Related to Plant Aging

Reviewed by: Jeffrey L. Binder, ANL

Item System SkucturelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Broad spectrum This report does not

provide specific

detailed information

on age-ralated

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 3B

Document: BNL A-3270R, 2-90, Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reoorted oroas ReI.Droas Reoort Recommendations Paae No. Item - - - -

No input for

current

programs

column

12

No input for 13

current

programs

column

No input for 14

current

programs

column

Document: BNL A3270, 12-86, Aging and Life Extension Assessment Program (ALEAP) Systems Level Plan

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document- BNL TR-3270-6-90, Maintenance Team Inspection Results: Insights Related to Plant Aging

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

, 1I
Table A.1 Gall Report for NPAR Reports Page 4A

Document: EGG-SSRE-10039, An Evaluation of the Effects of Valve Body Erosion on Motor-Operated Valve Operability

Reviewed by: John W. Holland, ANL

Item System StructurelComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

1 Emergency Cooling Motor Operated Valve Body A216, Grade WCB, Anchor-Darling ERO Wall thinning; Loss

Valve (16 in. Globe Cast Carbon Steel Industries of Material

Valve)

2 Emergency Cooling Motor Operated Valve Body A216, Grade WCB, Anchor-Darling ERO/CAV Wall thinning; Loss

Valve (16 in. Globe Cast Carbon Steel Industries of Material

Valve)

Document: EGG-SSRE-8972, Estimating Hazard Functions for Repairable Components

Reviewed by: Jeffrey L. Binder, ANL

Iterm System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Feedwater system Motor-operated This report does not

valves provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

L . I systems.

Document: EGG-SSRE-9017, User's Guide to PHAZE, a Computer Code for Parametric Hazard Function Estimation

Reviewed by: Jeffrey L. Binder, ANL

Iterm System StructuretComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Feedwater system Motor-operated This report does not

valves provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

I __I _ IIsystems.

Document: EGG-SSRE-9777, Isolation Valve Assessment (IVA) User's Manual Version 3.10

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR feedwater Motor-operated This report does not

cleanup system flexible wedge gate provide specific

isolation valve detailed information

on age-related

degradation

processes for

specific nuclear

components or ___systems.

Document: EGG-SSRE-9926, Evaluation of EPRI Draft Report NP-7065 Review of NRC/INEL Gate Valve Test Program

Reviewed by: Jeffrey L Binder, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR water cleanup Motor operated This report does not

system flexible wedge gate provide specific

isolation valve detailed information

on age-related

degradation

processes for

specific nuclear

components or systems.
Table A.1 Gall Report for NPAR Reports Page 4B

Document: EGG-SSRE-10039, An Evaluation of the Effects of Valve Body Erosion on Motor-Operated Valve Operability

Reviewed by: John W. Holland, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

The wall thinning could create undue Infrequent Not stated ASME Sec XI Not stated 1-2, Cl- 1

stresses and deformations in the valve IST & GL 89- 10

body, which could lead to relative 10 & Suppl.

displacements and induce disc or stem

binding. Binding could prevent the valve

from performing its safety function.

The wall thinning could create undue Infrequent Not stated ASME Sec XI Not stated 1-2, Cl- 2

stresses and deformations in the valve IST & GL 89- 10

body, which could lead to relative 10 & Suppl.

displacements and induce disc or stem

binding. Binding could prevent the valve

from performing its safety function.

Document: EGG-SSRE-8972, Estimating Hazard Functions for Repairable Components

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: EGG-SSRE-9017, User's Guide to PHAZE, a Computer Code for Parametric Hazard Function Estimation

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: EGG-SSRE-9777, Isolation Valve Assessment (IVA) User's Manual Version 3.10

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: EGG-SSRE-9926, Evaluation of EPRI Draft Report NP-7065 Review of NRC/INEL Gate Valve Test Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1
Table A.1 Gall Report for NPAR Reports -

Document: Letter Report (auth. Subudhi), Review of Aging-Seismic Studies on Nuclear Plant Equipment

Reviewed by: Jeffrey L. Binder, ANL

Item System StructureJComp .SubcomDonent Materials Manufacturer

Page 5A

ARD mechanism ARD effects

1 Various Various This report does not

provide specific

detailed information on age-related

degradation

processes for

specific nuclear

components or systems.

Document: Letter ReportIANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various.including Electric Motors Stator/ Rotor Not stated Not stated ENVIR; VIBR Physical

RC Windings Degradation;

CVW, and others Loosening

I/ -

2 Various including Electric Motors Bearings and Not stated Not stated ENVIR; VIBR Physical

RCS, ECCS, SW, Lubrication Degradation;

CCW, and others Loosening

3 Various including Electric Motors Electrical Leads Not stated Not stated CONTAM; CORR Buildup of deposits

RCS, ECCS, SW,

CCW, and others

4 Various including Electric Motors Bolts and Fasteners Not stated Not stated VIBR Loosening

RCS, ECCS, SW,

CCW, and others

5 Various including Electric Motors Commutator Not stated Not stated WEAR Attrition

RCS, ECCS, SW, Brushes

CCW, and others

6 Electrical Power Battery Chargers Referred to INEL for

Distribution and Inverters review.

7 Electrical Power Electrical Cable Referred to INEL for

Distribution review.

8 Electrical Power Pressure Referred to INEL for

1 Distribution Transmitters review.

9 Electrical Power Emergency Diesel Governor Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

10 Electrical Power Emergency Diesel Sensors Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington,

11 Electrical Power

Distribution

Emergency Diesel

Generator

Relays Not stated ALCO, Allis

Chalmers,

Caterpillar, Cooper

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

VIBR, ENVIR, and

WEAR

Loosening, Physical

Degradation and

Attrition
Table A.1 Gall Report for NPAR Reports Page 6B

Document: Letter Report (auth. Subudhi), Review of Aging-Seismic Studies on Nuclear Plant Equipment

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported proas Rel.progs FleDort Recommendations Paae No. Item

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Winding degradation and loosening Frequent IEEE-323, 344, 334; If Class 1 E Update codes and standards noted 4-5 1

causes electrical shorts resulting in failure Reg. Guide 1.89; 10CFR 50.49 in previous column. [2]

of the motor. ASME-OM8 otherwise PS

S&T Req.

Steam and water environments cause Frequent IEEE-323, 344, 334; If Class 1 E Update codes and standards noted 4-6 2

corrosion. Vibration induced loosening Reg. Guide 1.89; 10CFR 50.49 in previous column. (2]

will lead to sea] leakage. Both ASME-OM8 otherwise PS

mechanisms will lead to cracking and S&T Req.

splitting of the bearings, loss of alignment,

and potential jamming or freezing of the

motor.

Improper electrical contacts. Occasional IEEE-323, 344, 334; If Class 1 E Update codes and standards noted 4-7 3

Reg. Guide 1.89; 10CFR 50.49 in previous column. [2]

ASME-OM8 otherwise PS

S&T Req.

Bending and distortion of bolts and Occasional IEEE-323, 344, 334; If Class 1 E Update codes and standards noted 4-7 4

fasteners leading to loss of motor Reg. Guide 1.89; 10CFR 50.49 in previous column. (21

balance. ASME-OM8 otherwise PS

S&T Req.

Poor connections of brushes leads to Occasional IEEE-323, 344, 334; If Class 1 E Update codes and standards noted 4-7 5

motor failure. Reg. Guide 1.89; 10CFR 50.49 in previous column. [2]

ASME-OM8 otherwise PS

S&T Req.

6

71

8'

Not stated. Occasional None stated PS TS Req., None given 4-46 9

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 10

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req.,

RG 1.9, RG

1.108

None given 4-46
Table A.1 Gall Report for NPAR Reports Page 6A

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

12 Electrical Power Emergency Diesel Startup components Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

13 Electrical Power Emergency Diesel Engine Piping Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

14 Electrical Power Emergency Diesel Injector Pumps Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

15 Electrical Power Emergency Diesel Controls Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

16 Electrical Power Emergency Diesel Starting Air Valve Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

17 Electrical Power Emergency Diesel Starting Motors Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington_

18 Electrical Power

Distribution

Emergency Diesel

Generator

Air Compressor Not stated ALCO, Allis

Chalmers,

Caterpillar, Cooper

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

VIBR, ENVIR, and

WEAR

Loosening, Physical

Degradation and

Attrition
Table A.1 Gall Report for NPAR Reports Page 6B

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated. Rare None stated PS TS Req., None given 4-46 12

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 13

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 14

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 15

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 16

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 17

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req.,

RG 1.9, RG

1.108

None given 4-46 18
Table A.1 Gall Report for NPAR Reports Page 7A

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 Electrical Power Emergency Diesel Breakers Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica Delaval, Worthington

20 Electrical Power Emergency Diesel Cooling/Lubrication Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Pumps Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg, Transamerica

Delaval, Worthington

21 Electrical Power Emergency Diesel Heat Exchangers Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

22 Electrical Power Emergency Diesel Cooling Piping Not stated ALCO, Allis VIBR, ENVIF, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

23 Electrical Power Emergency Diesel Lube Oil Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

24 Electrical Power Emergency Diesel Other Systems Not stated ALCO, Allis VIBR, ENVIR, and Loosening, Physical

Distribution Generator Chalmers, WEAR Degradation and

Caterpillar, Cooper Attrition

Bessemer,

Fairbanks Morse,

Electro-Motive

Division, Nordberg,

Transamerica

Delaval, Worthington

25 Various Motor Operated Not stated Not stated Not stated Not stated Not stated

Valves

26 Various Check Valves Bonnet Stainless steel Not stated WEAR; ERO/CORR Attrition, Loss of

material, Wall

thinning

27 Various Check Valves Fasteners Stainless steel Not stated VIBR; CORR Loosening; Loss of

material and

corrosion product

buildup
Table A.1 Gall Report for NPAR Reports Page 7B

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Page No. Item

Not stated. Rare None stated PS TS Req., None given 4-46 lG

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 2C

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 21

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 22

RG 1.9, RG

1.108

Not stated. Rare None stated PS TS Req., None given 4-46 23

RG 1.9, RG

1.108

Not stated. Not stated None stated PS TS Req., None given 4-46 24

RG 1.9, RG

1.108

Not stated. Not stated Reg Guides: ASME ASME Sec XI None given 4-54 25

XI, Div 1; Generic OM-GL89-10

Issues: Task & Suppl.

II.E.6.1, Item B-58,

Item C-11, Issue 54,

Issue 105

Change in bonnet dimensions and Not stated Reg Guides: 1.147, 4f SR ASME None given 4-60 26

cracking. 1.148; Generic Sec Xl IWB,

Issues: Task IWC, or IWD

II.E.6.1, Item B-58,

Item C-1 1

Vibration induced fracture of the

fasteners. Corrosion will accelerate the

process.

Not stated Reg Guides: 1.147,

1.148; Generic

Issues: Task

II.E.6.1, Item B-58,

Item C-1I

If SR ASME

Sec Xl IWB,

IWC, or IWD

None given 4-60 27
Table A.1 Gall Report for NPAR Reports Page 8A

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System StructurelComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

28 Various Check Valves Seat Stainless steel Not stated WEAR; ERO/CORR Attrition, Loss of

hardened alloy, material, Wall

resilient material thinning

29 Various Check Valves Obturator Stainless steel with Not stated WEAR; ERO/CORR Attrition, Loss of

hardened alloy material, Wall

seating thinning

30 Various Check Valves Obturator Hanger Stainless steel Not stated WEAR; FAT; Attrition, Loss of

ERO/CORR fracture toughness;

Loss of material,

Wall thinning

31 Various Check Valves Hanger Pin Stainless steel Not stated WEAR; FAT; Attrition, Loss of

ERO/CORR fracture toughness;

Loss of material,

Wall thinning

32 Various Check Valves Hanger Pin Bearing Hardened alloy Not stated WEAR; EMBR; Attrition, Loss of

ERO/CORR fracture toughness;

Loss of material,

Wall thinning

33 Various Check Valves Seal, Gaskets Asbestos type, Not stated EMBR/TE, WEAR, Loss of fracture

Stainless steel, CORR toughness; Attrition;

Resilient material Loss of material

34 RCS and ECCS Auxiliary Feedwater Thrust Bearings Rolling contact Not stated WEAR Attrition

Pumps elements (Specialty

steels)

35 RCS and ECCS Auxiliary Feedwater Thrust runners 400-series S.S. Not stated WEAR Attrition

Pumps

36 RCS and ECCS Auxiliary Feedwater Shaft seals Stuffing-box or Not stated WEAR Attrition

Pumps mechanical type

37 RCS and ECCS Auxiliary Feedwater Stationary vanes 400-series S.S. Not stated VIBR Loosening

Pumps

38 RCS and ECCS Auxiliary Feedwater Wear rings 400-series S.S. Not stated WEAR; VIBR Attrition, Loosening

Pumps

39 RCS and ECCS Auxiliary Feedwater Thrust balancers 400-series S.S. Not stated WEAR Attrition

Pumps

40 RCS and ECCS Auxiliary Feedwater Radial bearings Bearing white metal Not stated WEAR; ELE-TEMP Attrition, thermal

Pumps (typically tin-base distortion

babbitt)

41 RCS and ECcS Auxiliary Feedwater

Pumps

Shaft and Fasteners I 400-series S.S. Not stated WEAR; VIBR Attrition, Loosening
Table A.1 Gall Report for NPAR Reports Page 8B

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Seat damage leads to valve leakage. Not stated Reg Guides: 1.147, If SR ASME None given 4-60 28

1.148; Generic Sec XI IWB,

Issues: Task IWC, or IWD

Il.E.6.1, Item B-58,

Item C- 11

Change in obturator dimensions causes Not stated Reg Guides: 1.147, If SR ASME None given 4-60 29

valve leakage due to improper seating of 1.148; Generic Sec XI IWB,

the valve. Issues: Task IWC, or IWD

I1.E.6.1, Item B-58,

Item C-_11

Change in dimensions. Not stated Reg Guides: 1.147, If SR ASME None given 4-60 30

1.148; Generic Sec XI IWB,

Issues: Task IWC, or IWD

II.E.6.1, Item B-58,

Item C- 11

Fracture of the pin. Not stated Reg Guides: 1.147, If SR ASME None given 4-60 31

1.148; Generic Sec XI IWB,

Issues: Task IWC, or IWD

II.E.6.1, Item B-58,

Item 0- 11 1

Change in dimensions. Not stated Reg Guides: 1.147, If SR ASME None given 4-60 32

1.148; Generic Sec Xl IWB,

Issues: Task IWC, or IWD

I1.E.6.1, Item B-58,

Item C-1 1

Valve leakage, excessive force needed to Not stated Reg Guides: 1.147, If SR ASME None given 4-60 33

seat valve. 1.148; Generic Sec XI IWB,

Issues: Task IWC, or IWD

II.E.6.1, Item B-58,

Item C- 1I

Change in rotor axial position. Loss of Not stated Reg Guides: 1.147; ASME Sec Xl None given 4-68 34

transmitted torque. Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

Xi, OM-2, OM-6,

OM-14, OM-15

Loss of transmitted torque. Not stated Reg Guides: 1.147; ASME Sec XI None given 4-68 35

Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM-15

Seal leakage. Rotor vibration. Not stated Reg Guides: 1.147; ASME Sec XI None given 4-68 36

Generic Issues: Item IST & PS TS

C-1i1; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM-15

Pump vibration. Loss of delivered flow. Not stated Reg Guides: 1.147; ASME Sec XI None given 4-68 37

Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM- 15

Pump vibration. Loss of transmitted Not stated Reg Guides: 1.147; ASME Sec XA None given 4-68 38

torque. Loss of delivered flow. Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

Xl, OM-2, OM-6,

OM-14, OM-15 I

Loss of transmitted torque. Not stated Reg Guides: 1.147; ASME Sec Xl None given 4-68 39

Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM-15

Rotor vibration. Bearng heatup. Not stated Reg Guides: 1.147; ASME Sec XI None given 4-68 40

Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM-15

Pump vibration. Not stated Reg Guides: 1.147;

Generic Issues: Item

,-11; ASME Section

ASME Sec XI

IST & PS TS

Req.

None given 4-68 41

X1, OM-2, OM-6,

OM-14, OM-15
Table A.1 Gall Report for NPAR Reports Page 9A

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System StruCtUrelCoMD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

42 RCS and ECCS Auxiliary Feedwater Impellers CrNi alloy steels, 17- Not stated WEAR; VIBR Attrition, Loosening

Pumps 4Ph

43 RCS and ECCS Auxiliary Feedwater Couplings Gear type Not stated WEAR; VIBR Attrition, Loosening

Pumps

44 RCS Hydraulic Snubbers EP Seals Not stated Bergen-Patterson; WEAR Attrition

Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

45 RCS Hydraulic Snubbers Piston Seals Polyurethane Bergen-Patterson; WEAR Attrition

Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

Intemational Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

46 RCS Hydraulic Snubbers Poppet Not stated Bergen-Patterson; Not stated Not stated

Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

47 RCS Hydraulic Snubbers Activation Not stated Bergen-Patterson; Not stated Not stated

adjustment screw Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

48 RCS Hydraulic Snubbers Piston/ cylinder Not stated Bergen-Patterson; WEAR Attrition, scoring

Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co. I

HCS Hydraulic Snubbers I Not given Not stated Bergen- Patterson;

Blaw Knox; ITTGrinnell Corp.;

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

CLOG Blockage of flow
Table A.1 Gall Report for NPAR Reports Page 9B

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aqina on Component Function Contrib to Failure Reported proas Rel.proas Report Recommendations Page No. Item

Rotor unbalance and vibration. Loss of Not stated Reg Guides: 1.147; ASME Sec Xl None given 4-68 42

delivered flow. Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

XI, OM-2, OM-6,

OM-14, OM-15

Rotor vibration. Not stated Reg Guides: 1.147; ASME Sec XI None given 4-68 43

Generic Issues: Item IST & PS TS

C-11; ASME Section Req.

X), OM-2, OM-6,

OM-14, OM-15

Not stated. Not stated Reg Guides: NRC ASME Sec XI Re-assess existing requirements 4-82 44

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME XI, PVP-45

Not stated. Not stated Reg Guides: NRC ASME Sec XI Re-assess existing requirements 4-82 45

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME XI, PVP-45

Not stated. Not stated Reg Guides: NRC ASME Sec XI Re-assess existing requirements 4-82 46

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME Xl, PVP-45

Not stated. Not stated Reg Guides: NRC ASME Sec Xl Re-assess existing requirements 4-82 47

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME XI, PVP-45

Not stated. Not stated Reg Guides: NRC ASME Sec XI Re-assess existing requirements 4-82 48

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME XI, PVP-45

Not stated. Not stated Reg Guides: NRC

SRP 3.9.3, Draft RG

SC 708-4; Generic

Issues GL 84-13;

ASME Xl, PVP-45

ASME Sec XI

ISTD & PS TS

Req.

He-assess existing requirements

regarding visual examination. This

may not be adequate [2]

4-82 49
Table A.1 Gall Report for NPAR Reports Page 10A

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

50 RCS Mechanical Not given Not stated Bergen-Patterson; CORR Loss of material;

Snubbers Blaw Knox; ITT- buildup of corrosion

Grinnell Corp.; products

Pacific Scientific;

Anchor-Holth;

International Nuclear

Safeguards Corp.;

ITT Barton;

McDowell Welmon;

Power Piping Co.

Document: No report # (May 1987), Plan for Integration of Aging and Ufe-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Reactors Pressure Vessel Not applicable Pressure vessel Not stated EMBR/IR Loss of fracture

steels toughness

2 Reactors Pressure Vessel Not applicable Pressure vessel Not stated ELE-TEMP, Physical

steels EMBR/TE Degradation, Loss ol

fracture toughness

3 Reactors Pressure Vessel Not applicable Pressure vessel Not stated FAT/TE, FAT/ Initiation and growth

steels PRESS of cracks

4 PWR Containment Post-tensioning- Steel Not stated EMBR/HY Loss of fracture

systems toughness

5 PWR Containment Post-tensioning- Steel Not stated CORR Loss of material

systems

6 PWR Containment Post-tensioning- Steel Not stated RELAX Loss of preload

systems

7 PWR Containment Reinforced Concrete Concrete; Steel Not stated ELE-TEMP; Cracking and

AGRCHEM spalling of concrete;

AGCREAC; Corrosion and

I _LEACH; FRZTHAW fatigue of steel

8 PWR Containment Metal Containment Steel Not stated CORR; FAT Loss of material;

Uners Cumulative fatigue

damage

9 Reactor Coolant Piping and Safe Welds Ferritic Steel Not stated FAT Cumulative fatigue

System Ends damage

10 Reactor Coolant Piping and Safe Cast Components - Cast Austanitic Not stated EMBR/TE Loss of fracture

System Ends Hot Leg Stainless Steel toughness

11 Reactor Coolant Piping and Safe Wrought Wrought Austenitic Not stated CORR/IGSCC; FAT Crack initiation and

System Ends Components Stainless Steel growth, Cumulative

fatigue damage

12 -ESF and RPS Cables Not applicable Not stated Not stated ELE-TEMP; ENVIR; Physical degradation

IR/GAM

13 ESF and RPS Connectors Not applicable Not stated Not stated ELE-TEMP; ENVIR; Physical

IR/GAM; CORR degradation;

corrosion product

buildup

14ESF and RPS Penetrations Not applicable Not stated Not stated Not stated Not stated
Table A.1 Gall Report for NPAR Reports Page 10B

Document: Letter Report/ANL, Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Droas ReI.Droqs Report Recommendations Paqe No. Item

Not stated. Not stated Reg Guides: NRC ASME Sec Xl Re-assess existing requirements 4-82 50

SRP 3.9.3, Draft RG ISTD & PS TS regarding visual examination. This

SC 708-4; Generic Req. may not be adequate [2]

Issues GL 84-13;

ASME XI, PVP-45

Document: No report # (May 1987), Plan for Integration of Aging and Ufe-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reportedprogs Rel.progs Report Recommendations Page No. Item

Propagation of flaws and cracks leading Not stated Yes, too numerous 10CFR App. G, Extend the irradiation damage curve A.2 1

to loss of pressure retaining capability of to list RG 1.99 & to higher fluences, improve the

the component. ASME Sec Xl- accuracy of fracture toughness data,

IWB demonstrate engineering feasibility

of annealing, evaluate feasibility of

replacement.. (More) (4]

Propagation of flaws and cracks leading Not stated Yes, too numerous ASME Sec Xl- Extend the irradiation damage curve A.4 2

to loss of pressure retaining capability of to list IWB,10CFR to higher fluences, improve the

the component. App. G & RG accuracy of fracture toughness data,

1.99 demonstrate engineering feasibility

of annealing, evaluate feasibility of

replacement.. (More) [4]

Propagation of flaws and cracks leading Not stated Yes, too numerous. ASME Sec III & Extend the irradiation damage curve A.4 3

to loss of pressure retaining capability of to list XI-IWB,10CFR to higher fluences, improve the

the component. App. G & RG accuracy of fracture toughness data,

1.99 demonstrate engineering feasibility

of annealing, evaluate feasibility of

replacement.. (More) (4]

Loss of tension in tendon wire. Not stated None ASME Sec Xl- Develop methods of monitoring [2] A.15 4

IWL

Loss of tension in tendon wire. Not stated None ASME Sec Xl- Develop methods of monitoring [2] A.15 5

IWL

Loss of tension in tendon wire. Not stated None ASME Sec Xl- Develop methods of monitoring [2] A. 15 6

IWE

Deterioration of concrete shielding Not stated None ASME Sec XI- Develop inspection program; A.16 7

properties; decrease in containment IWE investigate potential chemical and

function capability. irradiation interactions (4-ORNL]

Increased leakage rates. Not stated None ASME Sec Xl- Evaluate research results related to A.18 8

IWE concrete-liner interactions; specify

requirements for visual inspection 4-

ASME 1[1]

Not stated. Not stated None ASME Sec III & Synthesize available data on fatigue A.25 9

Sec Xl design life; Expand ASME III to

expand design analysis to cover

fatigue for plant life extension [4-

ANL]

Not stated. Not stated None ASME Sec Xl- Develop methods to determine A.25 10

IWB damage due to thermal aging and

synthesize information [4-ANL]

Not stated. Not stated None ASME Sec Xl- Define better UT for overlay clad [4] A.26 11

IWB

Signal drift. Not stated None 10CFR 50.49 & Improve methods for detection and A.31 12

PS, S&T Req. mitigation; determine degradation

rates, failure rates, and residual life

predictions [2]

Signal drift. Not stated None 10CFR 50.49 & Improve methods for detection and A.31 13

PS, S&T Req. mitigation; determine degradation

rates, failure rates, and residual life

predictions [2] I

Not stated. Not stated None 10CFR 50.49 &

PS, S&T Req.

Not stated A32
Table A.1 Gall Report for NPAR Reports Page 11A

Document: No report # (May 1987), Plan for Integration of Aging and Life-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

15 Emergency Diesel Governor and Not stated Not stated Not stated VIBR, ENVIR, Loosening; Physical

Generator Controls CORR Degradation; Buildup

of corrosion

products

16 Emergency Diesel Fuel System Not stated Not stated Not stated VIBR; ENVIR Loosening; Physical

Generator Degradation

17 Emergency Diesel Cooling System Not stated Not stated Not stated ENVIR Physical

Generator Degradation

18 Emergency Diesel Starting System Not stated Not stated Not stated ENVIR; CORR Physical

Generator Degradation; Buildup

of corrosion

products

19 Emergency Diesel Lube System Not stated Not stated Not stated VIBR; CORR Loosening; Buildup

Generator of corrosion

products

20 Emergency Diesel Intake and Exhaust Not stated Not stated Not stated VIBR Loosening

Generator System

21 Emergency Diesel Engine Body Not stated Not stated Not stated VIBR; ELE-TEMP; Loosening; Physical

Generator CORR degradation; Loss of

material

22 Emergency Diesel Drivetrain Not stated Not stated Not stated VIBR Loosening

Generator

23 Emergency Diesel Switchgear Not stated Not stated Not stated ENVIR Physical

Generator Degradation

24 ESF, RPS, EDG, Switchgear and Circuit Breakers Not stated Not stated WEAR Attrition

and AC and DC Relays

Electrical Systems

25 ESF, RPS, EDG, Switchgear and Relays Not stated Not stated DRIFT; CORR Loss of instrument

and AC and DC Relays calibration; Buildup

Electrical Systems of corrosion

I_ products

26 ESF Electric Motor- Valve seal and seat Not stated Not stated WEAR; ERO/ Attrition; Loss of

operated Valves CORR material

271 SF Electric Motoroperated Valves

Fasteners Not stated Not stated VIBR Loosening
Table A.1 Gall Report for NPAR Reports Page 11B

Document: No report # (May 1987), Plan for Integration of Aging and Life-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.prc gs Report Recommendations Page No. Item

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.40 1i

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.40 16

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.41 17

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.41 18

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.41 19

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.41 20

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A42 21

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.42 22

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated

authority over maintenance [4]

Not stated. Not stated None PS TS Req., Reexamine regulatory policy A.42 23

RG 1.9,RG requiring frequent testing. Consider

1.108 benefit of qualified diesel

operator/technician having regulated authority over maintenance [4]

Failure of trip latch mechanism function. Not stated None If Class 1 E Determine if aging mechanism foun A.51 24

10CFR5O.49 in reactor trip breakers extends to

otherwise PS other breakers. Complete operating

S&T Req. experience assessment. [2]

Coil burnout in logic relays. Set point drift Not stated None PS S&T Req. Establish/develop a cost effective A.52 25

in protective and timing relays. methodology for detecting relay coil

degradation and a preventive

maintenance program [2] 1

Failure to seal completely. Not stated None ASME Sec Xl Identify and evaluate monitoring A.57 26

& GL 89-10 & methods. Review, evaluate and

Suppl. develop methods for operational

readiness determinations. Develop

criteria for acceptance. Reexamine

maintenance needs and practices.

_(More) [4-EPRI-MOVI

Breakage of fasteners. Not stated None ASME Sec Xl

& GL 89-10 &

Suppl.

Identify and evaluate monitoring

methods. Review, evaluate and

develop methods for operational

readiness determinations. Develop

rriteria for acceptance. Reexamine

maintenance needs and practices.

(More) [4-EPRI-MOVI

A.58 27
Table A.1 Gall Report for NPAR Reports Page 12A

Document: No report # (May 1987), Plan for Integration of Aging and Life-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Item SvhtmuctuuhrnfCnmn Subrcomn~onnt Mnteri~lk Mnnufnr~turAr ARfl m~h2ni~m AAfl 0ffai~t~ ..... .. . Com ... rvte ........ ruco ....... ....................................... mo. effects 28 ESF Electric Motor- Stem Not stated Not stated DIST Dimensional

operated Valves distortion of part

29 ESF Electric Motor- Motor Operators Not stated Not stated WEAR; CORR; Attrition; Buildup of

operated Valves DIST; VIBR Corrosion Products;

Dimensional

distortion of part;

Loosening

30 ESF Electric Motor- Contacts Not stated Not stated CORR Buildup of corrosion

operated Valves products

31 ESF Electro-hydraulic Not stated Not stated Not stated Not stated Not stated

Valves

32 ESF Electro-pneumatic Not stated Not stated Not stated Not stated Not stated

Valves

33 ESF Check Valves Not stated Not stated Not stated Not stated Not stated

34 ESF Explosively-actuated Not stated Not stated Not stated Not stated Not stated

Valves III

Document: Nuclear Safety 31:484-489, Safety Implications of Diesel Generator Aging

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Emergency Diesel Instruments and Governor, control air Not stated Not stated VIBR Loosening

Generator control subsystem, wiring

and terminations,

sensors

2 Emergency Diesel Fuel system Engine piping, Not stated Not stated VIBR Loosening

Generator injector pumps,

injectors and nozzles_

3 Emergency Diesel Starting system Air admittance Not stated Not stated CORR/CONTAM Corrosion product

Generator valves, controls, buildup/loss of

starting motors desired surface

properties

Document: NUREG-1 144, Nuclear Plant Aging Research (NPAR) Program Plan

Reviewed by: Dwight R. Diercks, ANL

Item System Structure(Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Multiple Multiple This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 12B

Document: No report # (May 1987), Plan for Integration of Aging and Life-Extension Activities

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported Droqs Rel.proqs Report Recommendations Paqe No. Item

Increase in stroke time. Not stated None ASME Sec XI Identify and evaluate monitoring A.58 28

& GL 89-10 & methods. Review, evaluate and

Suppl. develop methods for operational

readiness determinations. Develop

criteria for acceptance. Reexamine

maintenance needs and practices.

(More) [4-EPRI-MOV]

Decrease in transmitted torque. Increase Not stated None ASME Sec XI Identify and evaluate monitoring A.59 29

in stroke time. & GL 89-10 & methods. Review, evaluate and

Suppl. develop methods for operational

readiness determinations. Develop

criteria for acceptance. Reexamine

maintenance needs and practices.

(More) [4-EPRI-MOV]

Increase in contact resistance. Not stated None ASME Sec XI Identify and evaluate monitoring A.59 30

& GL 89-10 & methods. Review, evaluate and

Suppl. develop methods for operational

readiness determinations. Develop

criteria for acceptance. Reexamine

maintenance needs and practices.

(More) [4-EPRI-MOV]

Not stated. Not stated None ASME Sec Xl Not stated A.63 31

IWV

Not stated. Not stated None ASME Sec XI Not stated A.63 32

IWV

Not stated. Not stated None ASME Sec XI Not stated A.63 33

IWV

Not stated. Not stated None ASME Sec XI Not stated A.63 34

I _ _IWV

Document: Nuclear Safety 31:484-489, Safety Implications of Diesel Generator Aging

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Vibration and vibration-induced loosening Frequent PNL NPAR Diesel PS TS Req., Relaxation of fast-starting and fast- 485 1

of subcomponents were the most frequent Generator Study RG 1.9, RG loading test requirement [4]

causes of all failures. 1.108

Loosening of subcomponents by vibration Frequent PNL NPAR Diesel PS TS Req., Relaxation of fast-starting and fast- 485 2

has been observed to cause component Generator Study RG 1.9, RG loading test requirement [4]

failure. 1.108 1 1

Corrosion product buildup and Occasional PNL NPAR Diesel PS TS Req., Not stated 485, 486 3

contamination of subcomponents can lead Generator Study RG 1.9, RG

to failure-to-start problems. 1.108

Document: NUREG-1 144, Nuclear Plant Aging Research (NPAR) Program Plan

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.pregs Report Recommendations Page No. Item

1
Table A.1 Gall Report for NPAR Reports Page 13A

Document: NUREG-1144, Rev. 1, Nuclear Plant Aging Research (NPAR) Program Plan, Rev. 1

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Multiple Multiple This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG-1 144, Rev. 2, Nuclear Plant Aging Research: (NPAR) Program Plan, Status, and Accomplishments, Rev. 2

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Emergency Power Emergency Diesel Subsystems: I/C, Not stated Not stated VIBR Loosening

Generators Lube Oil, Exhaust,

Exciter and Voltage

Regulator, Starting,

Intake/Combustion,

Cooling, Fuel Oil

2 Cooling and Power Motors Stator Insulating Not stated Not stated FAT/THERM, Cumulative fatigue

Systems System, Bearing ENVIR damage,

Assemblies physical/chemical

degradation

3 Emergency Power Battery Chargers Electrolytic Not stated Not stated FAT/THERM Cumulative Fatigue

and Inverters Capacitors, Damage

Transformer, Semi

Conductors, Cable

Connectors, Wiring,

Structural Fasteners

4 Emergency Power Batteries Grids, Top Lead Alloy Not stated CORR Physical

Conductor Degradation

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR cooling Steam generator Tubing (primary Inconel 600 Westinghouse, CORR/PWSCC Crack initiation and

system side) Combustion growth

Engineering

2 PWR cooling Steam generator Tubing (primary Inconel 600 Westinghouse, CORR/IN Crack initiation and

system side) Combustion growth

Engineering

3 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, CORR/CREV Loss of material;

system side) Combustion corrosion product

Engineering buildup

4 PWR cooling

system

Steam generator Tubing (secondary

side)

Inconel 600 Westinghouse,

Combustion

Engineering

CORR/SCC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 13B

Document: NUREG-1 144, Rev. 1, Nuclear Plant Aging Research (NPAR) Program Plan, Rev. 1

Reviewed by: Dwight R. Diercks, ANL Effect of Aaina on Comnonent Function Contrib to Failure Reported nroas Rel.oroas Reeoot Recommendations Paae No. Item

1

Document: NUREG-1 144, Rev. 2, Nuclear Plant Aging Research: (NPAR) Program Plan, Status, and Accomplishments, Rev. 2

Reviewed by: David C. Ma, ANIL

Effect of Aging on Cam ponent Function Contrib to Failure Reported progs Re~rg Report Recommendations Page No. Item

The highest failure rate is 12% of the Frequent Not stated PS TS Req., Replace fast start testing by engine 6.151

governor in the I/C system due to RG 1.9, RIG health check; permit slower starts

vibration, vibration loosening, thermal and 1.108 and longer run times; monitor and

physical shock. Fuel oil, starting and trend engine condition monitor;

cooling also have a high failure rate. Fast conduct major engine overhaul

start testing contributes to aging. based on need rather than elapsed ________________________ _____________________time. [4]

The stator insulating system and bearing Frequent Not stated If Class 1 E Perform tests for stator/rotor wind 6.156.16 2

assemblies of small motors (<200 Ibs) 100FR 50.49 ings on windings temperature,

failed most frequently (>70%). Heating otherwise PS vibration signature, current

cycles of winding in starting and overload S&T Req. signature, voltage gradient, corone,

conditions cause degradation of insulating insulation resist ance, power

material. (More) factorfloss factor, polarization index; ____________ _________(More) [2]

Overheating, electrical transfers, and Frequent Not stated If Class 1 E Improve the vital bus reliability by 6.20 3

personnel errors are the most 10CFR 50.49 using an auto matic transfer switch;

documented stressors. Electrolytic otherwise PS use of equipment for detecting and

capacitors are thermal sensitive. Failure S&T Req. suppressing electrical bus

of electrolytic capacitors in a short circuit disturbances; use of higher voltage

mode result in direct loss of the and temperature related compo

equipment availability _______________nents and forced air cooling [2]

The dominant aging problem is the Not stated Not stated If Class 1 E Maintain and operate in accordance 6.21 4

thermal induced oxidation of the grids and 10CFR 50.49 with IEEEE Standard 450, Reg.

top conductors. The swelling of the lead otherwise PS Guide 1.129, and manufacturer's

alloy material causes poor contact and S&T Req. recommendations [2]

decreased battery capacity. Brittle lead

due to oxidation also leads to decreased

Iruggedness. I________ I__I__I__I__I

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

PWSCC generally occurs at points of~ Occasional EPRI Steam ASME Sec Xl In-situ stress relief of tubes near 96

high residual stress or in-service Generator Owners IWB & TS Req. tube-sheets; heat treat Inconel to

deformation (denting). PWSCC Group reduce susceptibility in new plants.

commonly leads to tube leakage and [4]

creates the potential for tube failure. ________ ____________________

lntergranular attack can occur during Rare Not discussed in ASME Sec Xl Control environment during layup to 98 2

layup, particularly in the presence of report IWB & TS Req. reduce oxygen and thiosulfates. [4]

impurities such as oxygen and

thiosulfates, and can lead to tube leakage

and possible tube failure. ________ ____________________

Typically caused by the presence or Occasional NRC Draft Branch ASME Sec XI Not stated. 98 3

formation of caustics, acid phosphates, Tech Position 5- IWB & TS Req.

chloride ions, or acid sulfates. Effects are 3;EPRI Steam

same as above. Generator Owner's Grp. _I

Caused by formation of NaOH by

hydrolysis reactions between phosphate

water treatmnent and corrosion product

oxides at tube sheet. Effects are same as

above.

Not stated NRC Draft Branch

Tech Position 5-

3;EPRI Steam

Generator Owner's

Grp.

ASME Sec Xl

IWB & TS Req.

Control water chemistry to eliminate

free caustic buildup; heat treat

tubing [4]

98-1 00 4
Table A.1 Gall Report for NPAR Reports Page 14A

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

5 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, CORR/IN Crack initiation and

system side) Combustion growth

Engineering

6 PWR cooling Steam generator Tubing (secondary CORR/UA Loss of material

system side)

7 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, CORR/PIT Local loss of materia

system side) Combustion

Engineering

8 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, WEAR/FRET Attrition

system side) Combustion

Engineering

9 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, WEAR Attrition

system side) Combustion

Engineering

10 PWR cooling Steam generator Tubing (secondary Inconel 600 Westinghouse, WEAR Attrition

system side) Combustion

Engineering

11 PWR cooling Steam generator Tube support plates Carbon steel; ferritic Westinghouse, WEAR/DENT Constriction

system stainless steel Combustion

Engineering

12 PWR cooling Steam generator Feedwater lines Not stated Westinghouse, FAT/THERM Cumulative fatigue

system Combustion damage

Engineering

13 PWR cooling Condensers Not stated Not stated CORR/UA Loss of material

system

14 BWR cooling Coolant piping Condenser tubes Type 304 stainless General Electric Co. CORR/IGSCC Crack initiation and

system steel growth

15 PWR pressure Pressure vessels, Bolts Ferritic stainless Not stated CORR Loss of material and

boundary pumps, etc. steel crack initiation

16 PWR pressure Pressure vessels, Bolts Ferritic stainless Not stated CORR/SCC Crack initiation and

boundary pumps, etc. steel growth

17 PWR pressure Pressure vessels, Bolts Austenitic stainless Not stated CORR/TGSCC Crack initiation and

boundary pumps, etc. steel growth

ElcrclislainNtsae

18Electrical and control

systems

Electrical

components

Electrical insulation Various organic

polymers

Not stated EMBR/IR;

EMBR/TH

Loss of fracture

toughness
Table A.1 Gall Report for NPAR Reports Page 14B

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.proqs Report Recommendations Page No. Item

Caused by the formation of a caustic Occasional NRC Draft Branch ASME Sec XI Thermally treat tubing, sleeve 100 5

environment at the tube sheet crevice. Tech Position 5- IWB & TS Req. affected area with more resistant

Effects are same as above 3;EPRI Steam material, eliminate crevice in design.

Generator Owner's [4]

Grp.

Occurs in creviced areas because of the Rare NRC Draft Branch ASME Sec Xl Eliminate phosphate water 100 6

formation of acid phosphates. Effects are Tech Position 5- IWB & TS Req. treatment; control sodium/phosphate

same as above. 3;EPRI Steam ratio. [4]

Generator Owner's

Group

Produced by chloride and air or oxygen Not stated NRC Draft Branch ASME Sec Xl Improve condenser performance to 101 7

inleakage plus Cu ions, resulting in local Tech Position 5- IWB & TS Req. eliminate chlorides and oxygen in

corrosion cells. Pits can lead to tube 3;EPRI Steam system [4]

leakage, though rupture is considered Generator Owner's

unlikely. Grp.

Produced by rubbing of tubes against Occasional Not discussed in ASME Sec Xl Change material and design of anti- 101 8

supports and anti-vibration bars because report IWB & TS Req. vibration bars. [4]

of flow-induced vibration. Can lead to

tube leakage and possible failure

Observed near uppermost tube support Not stated Not discussed in ASME Sec Xl Not stated. 101 9

plates in once-through SG, and is thought report IWB & TS Req.

to be caused by the erosive action of

corrosion product oxides carried in the

high-velocity stream.

Caused by foreign objects inadvertently Occasional Not discussed in ASME Sec Xl Avoid introduction of foreign objects 101-103 10

left in steam generators, which vibrate report IWB & TS Req. [4]

against tubes and can cause leakage and

possible failure.

Caused by buildup of oxides (primarily Moderate NRC Draft Branch ASME Sec XI Oxygen control or deaeration in 103-104 11

magnetite) in the gap between the tubes Tech Position 5- IWB & TS Req. condenser, feed-water lines, and

and the support plates, resulting in 3;EPRI Steam steam generator plus monitoring of

deformation, constriction, and possible Generator Owner's condenser leakage. [4]

tube failure. Grp.

Thermal fatigue associated with Occasional Not discussed in ASME Sec Xl Proper mixing of auxiliary and main 104 12

introduction of ambient temperature water report IWB & TS Req. feedwater. [4]

during startup and shutdown, possibly

accelerated by environmental effects, can

cause cracking at the I.D. of feedwater

lines, leading to leakage.

Corrosion produced by chlorides in salt- Not stated Not discussed in PS S&T Req. Monitor condenser leakage, protect 245-255 13

water-cooled PWRs can lead to leakage report damaged tubes with Ti sleeves, plug

in condenser tubes and service water and replace leaking tubes, use Ti

system components, allowing ingress of tubes in new units. [4]

chlorides into the secondary water system

Sensitized austenitic stainless steel under Moderate Not discussed in ASME Sec XI Deaeration, hydrogen water 107-120 14

residual or applied tensile stresses report IWC chemistry, material replacement, and

(typically near welds) is subject to IGSCC inspection [4]

in contact with oxygenated cooling water,

resulting in pipe cracking and leakage.

The nature of the corrosive attack Not stated Not discussed in ASME Sec Xl Not stated 230 15

(general, intergranular, etc.) is not report IWB

identified, but boric acid corrosion can

lead to failure of bolting materials in

service.

SCC of ferritic stainless steel bolting Not stated Not discussed in ASME Sec XI Not stated 230 16

materials can be caused by the report

nonjudicious use of lubricants, resulting in

failure in service

Chloride contamination can produce Not stated Not discussed in ASME Sec XI Not stated 230 17

TGSCC of austenitic stainless steel report

bolting materials, resulting in failure in

service.

Long-term exposure to irradiation at

elevated temperatures can produce

embrittlement and loss of strength in

organic insulation; the extent of the effect

varies with the material.

Not stated IEEE Std. 323-1974;

ASTM Std. D2953-

71

If Class 1E

1OCFR 50.49

otherwise PS

S&T Req.

Not stated 121-1 30 1lE
Table A.1 Gall Report for NPAR Reports Page 15A

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

19 Electrical and control Electrical Electrical insulation Polyimide, polyester, Not stated EMBR/IR; Loss of fracture

systems components silicone, polyvinyl, EMBR/TH toughness

teflon

20 Electrical and control Various control and Misc. sub- Various Various ELE-TEMP; Chemical and

systems switching devices component parts EMBR/IR; FAT; physical breakdown

VIBR

Document: NUREG/CP-0100, Proceedings of the International Nuclear Power Plant Aging Symposium

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Concrete structures Concrete (typically Not stated AGRCHEM Loss of integrity

steel reinforced)

2 Concrete structures Concrete (typically Not stated LEACH Loss of integrity

steel reinforced)

3 Concrete structures Concrete (typically Not stated CORR Loss of material

steel reinforced)

4 Concrete structures Concrete (typically Not stated FRZ/THAW Loss of integrity

steel reinforced)

5 Pressure boundary Pressure vessel and Austenitic stainless Not stated FAT Cumulative fatigue

coolant piping steels and ferritic damage

steels

6 Pressure boundary Pressure vessel SA533, Gr. B, Class Not stated EMBR/TE Loss of fracture

1 steel toughness

7 Pressure boundary Pressure vessel Not stated Not stated EMBR/TE Loss of fracture

toughness

8 Cooling system Feedwater lines Typically carbon or Not stated ERO/CORR Wall thinning

low-alloy steel

9 Cooling system Coolant pumps Pump impellers and 13Cr-4Ni-Mo cast Not stated EMBR Loss of fracture

blades martensitic stainless toughness

steel

10 Cooling system Coolant pumps Pump body CF8, CF8M, and Byron-Jackson; EMBRITE Loss of fracture

CF8A cast duplex Westinghouse; toughness

SS Bingham-Willamette;

CE/Klein, Schanzlin,

and Becker

11 Cooling system Coolant pumps Pump body CF8, CF8M, and

CF8A cast duplex

Ss

Byron-Jackson;

Westinghouse;

Bingham-Willamette;

CE/Klein, Schanzlin,

and Becker

FAT; FAT/THERM Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 15B

Document: NUREG/CP-0036, Proceedings of the Workshop on Nuclear Power Plant Aging

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Long-term exposure to irradiation at Not stated Not discussed in If Class 1 E Not stated 256-262 19

elevated temperatures is observed to report 1OCFR 50.49

dramatically decrease the life of teflon otherwise PS

compared to thermal aging alone, but the S&T Req.

life is significantly increased for the other

materials tested.

Various electrical control and switching Not stated IEEE Stds. 323- If Class 1 E Not stated 155-164 20

devices were subjected to pre- 1974 & 344-1975, 1OCFR 50.49

conditioning (thermal aging, irradiation, EPRI NP-2129, and otherwise PS

and mechanical cycling) prior to seismic NRC Reg. Guide S&T Req.

loading tests. The equipment showed 1.89, Rev. 1 (Feb.

little or no adverse effects from the 1982)

preconditioning.

Document: NUREG/CP-0100, Proceedings of the International Nuclear Power Plant Aging Symposium

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Acids, sulfates, and chlorides dissolved in Not stated Not discussed in ASME Sec XI Not stated 84-88

groundwater react with and breakdown report IWL

the cement phases in the concrete,

resulting in loss of strength.

Water in contact with concrete with Not stated Not discussed in ASME Sec XI Not stated 84-88 2

cracks or improper construction joints can report IWL

leach out the Ca(OH)2 phase, resulting in

disintegration. I

Water, typically containing dissolved Not stated Not discussed in ASME Sec XI Repair of cracks [4] 84-88 3

chlorides, seeps into cracks, reduces the report IWL

pH, and causes corrosive attack of the

embedded rebar, resulting in loss of

strength.

Expansion associated with freezing of Not stated Not discussed in ASME Sec XI Not stated 84-88 4

concrete while wet can cause spalling. report IWL

Repeated freeze/thaw cycles can cause

severe degradation.

Temperature and load cycles from Not stated Not discussed in ASME Sec XI Improved design rules under 100-113 5

operating transients, in combination with report IWB development. [4]

environmental effects, can cause crack

initiation, growth, and component failure.

Specimens of A533, Gr. B, Cl. 1 steel are Not stated Not discussed in 10CFR App. G Not stated 207-211 6

being subjected to accelerated thermal report & RG 1.99

aging treatments to determine possible

deleterious effects on fracture toughness

and other mechanical properties.

Long-term exposure to neutron irradiation Not stated USNRC RG 1.99, 1OCFR App. G Multifaceted approach for managing 338-341 7

causes a progressive decrease in fracture Rev. 2 and 1.154; 10 & RG 1.99 embrittlement is described. [4]

toughness of the RPV materials near the CFR 50

core, increasing their susceptibility to subsequent failure under severe transients.

Wall thinning through the combined Not stated Chexal-Horowitz- ASME Sec XI Change water chemistry; improve . 95-99 8

effects of corrosion and the erosion of the Erosion-Corrosion flow geometries of piping; use more

resulting poorly adherent magnetite layer (CHEC) computer resistant materials (e.g., higher Cr

under high-velocity flow result in possible code alloys) [4]

component failure.

Extended service at LWR operating Not stated Not discussed in ASME Sec XI Embrittlement can be reduced by 89-94 9

temperatures can lead to significant loss report proper heat treatment and chemistry

of fracture toughness, thereby increasing [2]

susceptibility to failure under impact

loading.

Prolonged service at operating Not stated ASME Code Section ASME Sec Xl Perform periodic volumetric and 212-219; 10

temperatures can produce microstructural Xl surface in-service inspection to 353-362

changes in the ferrite phase of the duplex characterize flaws. Second ref.

SSs that causes a progressive loss of describes three-phase monitoring

fracture toughness. _ _I I I program. [4-AN LI I

System operating transients and pump

vibrations can cause cyclic loadings and

possible growth of pre-existing flaws.

Not stated ASME Code Section ASME Sec III &

XI 1Xl

Perform periodic volumetric and

surface in-service inspection to

characterize flaws. [4]

212-2 19 11
Table A.1 Gall Report for NPAR Reports Page 16A

Document: NUREG/CP-0100, Proceedings of the Intemational Nuclear Power Plant Aging Symposium

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

12 Cooling system Coolant pumps Pump body CF8, CF8M, and Byron-Jackson; CORR/SCC Crack initiation and

CF8A cast duplex Westinghouse; growth

SS Bingham-Willamette;

CE/Klein, Schanzlin,

and Becker

13 Cooling system Coolant pumps Pump shaft Cr-plated; underlying Byron-Jackson; FAT; FAT/THERM Cumulative fatigue

alloy not stated Westinghouse; damage

Bingham-Willamette;

CE/Klein, Schanzlin,

and Becker

14 Cooling system Coolant pumps Closure studs SA193, Gr. B7 or Byron-Jackson; CORR/BA Loss of material

SA540, Gr. B23 Westinghouse;

Bingham-Willamette;

CE/Klein, Schanzlin,

and Becker

15 Not stated Not stated Elastomers for Natural or synthetic Not stated ENVIR Loss of desired

seals, diaphragms, rubber or related properties

hoses, belts, valve polymers

seats

16 Multiple Multiple Multiple Various Various Various Various

Document: NUREG/CP-0105, Proceedings of the U.S. Nuclear Regulatory Commission, 17th Water Reactor Safety Information Meeting

Reviewed by: Ali Erdemir, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Pressure boundary Pressure vessel Upper-shelf welds High-copper weld Combustion EMBR/IR Loss of fracture

material, LINDE-124 Engineering Inc. toughness

2 Pressure boundary Pressure vessel Upper head Austenitic stainless Combustion EMBR/IR Loss of fracture

stainless-steel weld steels, Types: 308, Engineering Inc. toughness

cladding 309,304

3 Cooling system Coolant piping Not stated 304 and 316 Not stated CORR/ IGSCC Crack initiation and

Stainless Steel growth

4 Pressure boundary Pressure vessel Not stated SA533, Gr. B, Class Not stated CORR/SCC Crack initiation and

1 steel growth

5 Pressure boundary Recirculating cover Not stated CF-3, CF-8, and CF- Georg Fischer Co., EMBR Loss of fracture

plate 8M, cast duplex SS Switzerland; and toughness

Gundremmingen

Reactor, Germany

6 Pressure bounaary Heactor internals Core support plate, core shroud and top

guide

Not stated Not stated CORR/SCC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 16B

Document: NUREG/CP-0100, Proceedings of the International Nuclear Power Plant Aging Symposium

Reviewed by: Dwight R. Diercks, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Very low levels of ferrite at repair and Not stated ASME Code Section ASME Sec XI Perform periodic volumetric and 212-219 12

fabrication welds plus sensitization from XI surface in-service inspection to

welding procedure can leave these characterize flaws. [4]

regions susceptible to crack initiation by SCC.

Alternate bending stresses from Not stated ASME Code Section ASME Sec Ill & Perform periodic volumetric and 212-219 13

asymmetric distribution of static pressure Xl XI surface in-service inspection to

and cyclic thermal stresses from turbulent characterize flaws. Use monitors to

mixing of hot and cold reactor coolant can detect vibrations caused by cracks in

cause fatigue crack initiation and growth. shaft. [4-EPRI]

Leakage of borated PWR primary coolant Not stated Not discussed in ASME Sec XI Perform periodic visual and 212-219 14

across pump casing-to-cover gasket can report or PS S&T volumetric in-service inspection to

cause significant corrosion of closure Req. detect corrosion. [4]

studs, leading to possible breakage.

Elastomers break down during storage by Not stated MIL-STD-1523A; PS S&T Req. Shelf life may be greater than that 118-124 15

breaking or crosslinking molecular bonds MIL-HDBK-695C given in MIL standards; more

and evaporation, migration, or mutation of research is needed. [2]

compound ingredients, causing loss of

strength, ductility, and'resilience.

Paper presents an overview of common 28-38 16

aging processes for PWR pressure

vessels, PWR reactor cooling system

piping and nozzles, BWR Mark I

containments, diesel generators, motoroperated valves, and cables, connections,

and penetrations. No aging.

Document: NUREG/CP-0105, Proceedings of the U.S. Nuclear Regulatory Commission, 17th Water Reactor Safety Information Meeting

Reviewed by: AJi Erdemir, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Irradiation reduces fracture toughness, Not stated NRC-HSSI, ASME- 10 CFR App. G Not stated 31-39 1

tearing modulus, and ductility of upper- 185

shelf welds, thus increasing their

susceptibility to crack initiation and

growth.

Irradiation reduces fracture toughness Not stated Not discussed in 10 CFR App. G Not stated 44-47 2

and tearing modulus of the weld cladding, report

During an overcooling transient, this can

lead to the growth of small surface flaws

thus increasing the probability of pressure

vessel failure.

High concentration of ionic impurities, Not stated EPRI-HWC ASME Sec XI Inject hydrogen into feedwater [4] 301-310 3

such as sulfates and chlorides, and

oxidizing radiolysis products in BWR

water together with high tensile stresses

resulted in IGSCC of 304 and 316 pipes.

Susceptibility to SCC increases with Not stated Not discussed in 10 CFR App. G Control sulfur content [4] 310-311 4

increasing sulfur content and/or number report

of sulfide inclusions. A533B steel

contains far fewer sulfide inclusions than

other ferrtic steels and is found to be less

susceptible to SCC.

Thermal aging decreases the fracture Not stated ASTM E813-85, ASME Sec XI Not stated. 332-342 5

toughness and tearing modulus of cast El 152

stainless steels. Precipitation and/or

growth of phase-boundary carbides or

nitrides leads to brittle fracture and/or

cleavage of ferrite phase due to particle

cracking.

Soluble corrosion products in reactor

coolant systems undergo cathodic

reduction, contributing to crack growth. At

289 C and 10 -6/s -1 strain rate, chromate

(at 0.1 ppm level) is found to be more

deleterious than nitrate, borate, carbonate,

& chlorides.

Not discussed in

report

ASME Sec Xi

& PS TS

Not stated 369-371 6
Table A.1 Gall Report for NPAR Reports Page 17A

Document: NUREG/CP-0105, Proceedings of the U.S. Nuclear Regulatory Commission, 17th Water Reactor Safety Information Meeting

Reviewed by: Ali Erdemir, ANL

Item SytmStructure/Comb Subcomnonent Materials Manufacturer ARD mechanism ARD effects

7 Cooling system Piping Not stated Stainless steel, Type Not stated CORR/SCC Crack initiation and

304 growth

8 Power plant Various Various Class 1E Not stated ELE-TEMP Chemical or physical

cables degradation, thermal

distortion

9; Cooling system Steam Generator Tubes Inconel 600 Not stated CORR/PWSCC Crack initiation and

growth

10 Not stated Not stated Circuit breakers and Relays (protective, Not stated WEAR Attrition

relays auxiliary, control,

timing, electronic);

breakers (moldedcase and metal-clad)

11 Auxiliary Feed Water Not stated Pump drivers, valve Not stated Not stated WEAR Loss of desired

System operators, valves, property or function,

pumps attrition

12 Compressed air Not stated Compressors, Not stated Not stated WEAR Loss of desired

system valves, filters, dryers, property or function.

pipes, silencers, Attrition

moisture separators

13 Power operation and Inverters Filter capacitors, Not stated Not stated ELE-TEMP Chemical or physical

safety system thyristors, fuses degradation; thermal

distortion

Document: NUREG/CR-2641, The In-Plant Reliability Data Base for Nuclear Power Plant Components: Data Collection and Methodology Report

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Safety-related Safety-related This report does not

provide specific

detailed information on age-related

degradation

processes for

specific nuclear

components or

I_ I_ I Isystems.

Document: NUREG/CR-3154, The In Plant Reliability Data Base for Nuclear Plant Components: Interim Report - The Valve Component

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Nuclear power

generating station

Valve Seat Not stated Not stated ERO/CORR,

ERO/CAV

Loss of material
Table A.1 Gall Report for NPAR Reports Page 17B

Document: NUREG/CP-0105, Proceedings of the U.S. Nuclear Regulatory Commission, 17th Water Reactor Safety Information Meeting

Reviewed by: All Erdemir, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Droas Rel.Droas Report Recommendations Page No. Item

Service-induced cracking of BWR reactor Not stated Not discussed in ASME Sec Xl Control hydrogen water chemistry [4] 372 7

internal components were mainly report or PS S&T

attributed to SCC. BWR water Req.

environments contain ionic impurities and

radiolysis products that can lead to SCC.

After artificial aging at 100 C to a nominal Not stated NRC/Long-Term PS S&T Req. Not stated 397 8

lifetime of 60 years using an aging Cable Aging

acceleration factor of -80, many cables Program

passed the loss of coolant accident steam

exposure test indicating a good life

extension potential for a number of cable

prod.

High-residual tensile stresses and low Not stated NRC/NPAR ASME Sec XI Eliminate high tensile stresses, 415-420 9

mill-annealing temp. contribute to IWB & PS S&T reduce hot leg temperature. [4]

PWSCC. Small increases in operating Req.

temp. can accelerate damage. Roll

transitions, irregular transitions at Ubends, and dented tubes are susceptible

sites for PWSCC.

Aging, contact oxidation, and service- Not stated NRC/NPAR PS S&T Req. Develop effective inspection, 434-435 10

related wear of circuit breakers and relays surveillance, and condition

can lead to loss of capacity and monitoring methods. [2]

inadvertent actuation of safety related

systems; and can cause significant

damage to associated equipment,

increase the chance of fires.

Aging and service related degradation is Not stated NRC/NPAR ASME Sec XI Optimize surveillance and monitoring 445-446 11

responsible for a significant fraction of the programs [4]

AFW failures. The degradation of

instrumentation and control devices, such

as electrical contacts, relays, switches,

circuits, etc. can result in component

failure.

Aging-related degradation plays a Not stated NRC/NPAR, PS S&T Req. Optimize preventive maintenance 458-463 12

significant role in compressed air system 10CFR50.73 procedure. [4]

failures. In particular, wear, corrosion,

fatigue, blocking/clogging, calibration

setpoint drift are the dominant

mechanisms for component failure.

Overheating, electrical transients, and Not stated IEEE-650-1989 PS S&T Req. Comprehensive inspection, testing 501-505 13

personnel errors are the leading causes of and preventive/ corrective

inverter failures. These failures can result maintenance [2]

in reactor trip, containment isolation,

safety injection system actuation, and loss

of feedwater.

Document: NUREG/CR-2641, The In-Plant Reliability Data Base for Nuclear Power Plant Components: Data Collection and Methodology Report

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported prols Rel.progs Report Recommendations Page No. Item

1

Document: NUREG/CR-3154, The In Plant Reliability Data Base for Nuclear Plant Components: Interim Report - The Valve Component

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Corrosion, erosion/cavitation (aggravated

when valve is operated nearly closed)

cause improper seating and fluid leakage

past a 'closed' valve.

Moderate ANSI FIRR

Committee

ASME Sec Xl

IST & PS S&T

Req.

Not stated 7-11,39,

45

1
Table A.1 Gall Report for NPAR Reports Page 18A

Document: NUREG/CR-3154, The In Plant Reliability Data Base for Nuclear Plant Components: Interim Report- The Valve Component

Reviewed by: Ken E. Kasza, ANL Item S~tmStructure/Come Subcomeonent Materials Manufacturer ARD mechanism ARD effects

2 Nuclear power Valve Stem Not stated Not stated WEAR Attrition

generating station

3 Nuclear power Valve Bonnet Not stated Not stated WEAR Attrition

generating station

4 Nuclear power Valve Packing Not stated Not stated ELE-TEMP Chemical or physical

generating station degradation

5 Nuclear power Valve Seals Not stated Not stated ELE-TEMP Chemical or physical

generating station degradation

6 Nuclear power Valve Fasteners Not stated Not stated FAT Cumulative fatigue

generating station damage

7 Nuclear power Valve Gate Not stated Not stated FAT Cumulative fatigue

generating station damage

8 Nuclear power Valve Flange Not stated Not stated CORR Loss of material

generating station

9 Nuclear power Valve Bushing Not stated Not stated WEAR Attrition

generating station

10 Nuclear power Valve Linkages Not stated Not stated WEAR Attrition"

generating station

Document: NUREG/CR-3543, Survey of Operating Experience from LERs to Identify Aging Trends

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 All safety-related Pipe Pipe welds Not stated Not stated FAT (Vibration- Cumulative fatigue

systems induced and damage

thermal)

2 All safety-related Pipe Pipe welds Not stated Not stated CORR/SCC Crack initiation and

systems growth

3 All safety-related Pipe Pipe threads and Not stated Not stated VIBR; FAT Loosening;

systems tube fittings Cumulative fatigue

damage

4 All safety-related

systems

iPipe Pipe wafls Not stated Notstated ERO/CORR Wall thinning
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-3154, The In Plant Reliability Data Base for Nuclear Plant Components: Interim Report- The Valve Component

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Droas Rel.proqs Report Recommendations

Page 18B

Page No. Item

Worn stem can cause misalignment of Occasional ANSI FIRR ASME Sec XI Not stated 7-11, 39, 2

stem travel, worn bushings, and faulty Committee IST & PS S&T 45

valve seating, leading to seat distortion Req.

and leaking.

Not stated Not stated ANSI FIRR ASME Sec XI Not stated 7-11,39, 3

Committee IST & PS S&T 45

Req.

Elevated temperature distortion and Moderate ANSI FIRR ASME Sec XI Not stated 7-11, 39, 4

chemical attack of packing can cause Committee IST & PS S&T 45

packing to deteriorate and loose sealing Req.

effectiveness, resulting in persistent fluid

leakage.

Elevated temperature distortion and Occasional ANSI FIRR ASME Sec Xl Not stated 7-11, 39, 5

chemical attack of seals can cause seals Committee IST & PS S&T 45

to deteriorate and loose sealing Req.

effectiveness, resulting in persistent fluid

leakage.

Fatigue resulting from vibration can cause Rare ANSI FIRR ASME Sec XI Not stated 7-11, 39, 6

loosening or breaking of fasteners, Committee IST & PS S&T 45

resulting in misalignment of parts and Req.

leakage.

Fatigue resulting from vibration can cause Rare ANSI FIRR ASME Sec XI Not stated 7-11, 39, 7

cracking or distortion of gate, leading to Committee IST & PS S&T 45

faulty seating and leakage or valve Req.

lamming.

Corrosion of flange faces can cause Rare ANSI FIRR ASME Sec Xl Not stated 7-11, 39, 8

failure to seal and leakage. Committee IST & PS S&T 45

Req.

Wear of bushing can cause improper Occasional ANSI FIRR ASME Sec XI Not stated 7-11, 39, 9

stem travel and damage to seat, resulting Committee IST & PS S&T 45

in leakage. Reg_.

Wear can cause linkages to improperly Rare ANSI FIRR ASME Sec Xl Not stated 7-11,39, 10

control valve positioning, resulting in valve Committee IST & PS S&T 45

not being closed completely or jamming Req.

into the seat Result is seat distortion and

leakage.

Document: NUREG/CR-3543, Survey of Operating Experience from LERs to Identify Aging Trends

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.prols Report Recommendations Page No. Item

Pipe welds are subject to loss of fatigue Frequent Not discussed in ASME Sec XI Most failure studies have 11,12,17, 1

resistance, resulting in leakage, report IWB, IWC or concentrated on a generic corn- 18

IWD ponent. Future work should include

the environment for each

component' subcomponenttype of

component, and material of

construction. (More) [4]

Wall thinning due to corrosion or stress Occasional Not discussed in ASME Sec XI Most failure studies have 8,14 2

corrosion cracking can lead to pipe report IWB, IWC or concentrated on a generic comleakage. IWD ponent. Future work should include

the environment for each

component/ subcomponent~type of

component, and material of

construction. (More) [4]

Subcomponents are subject to loosening Moderate Not discussed in ASME Sec XI Most failure studies have 11,12,13, 3

and cracking, resulting in pipe leakage. report IWB, IWC or concentrated on a generic corn- 17,18

IWD ponent. Future work should include

the environment for each

component/ subcomponenttype of

component, and material of

_construction. (More) [4] 1

Pipe wall thinning resulting in pipe failure

and tube crack or rupture, placing the

steam generator in a degraded failure

condition.

Occasional Not discussed in

report

ASME Sec Xl

IWB, IWC or

IWD

Most failure studies have

concentrated on a generic component. Future work should include

the environment for each

component' subcomponenttype of

component, and material of

construction. (More) [4]

8,9,17,18 4
Table A.1 Gall Report for NPAR Reports Page 19A

Document: NUREG/CR-3543, Survey of Operating Experience from LERs to Identify Aging Trends

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

5 All safety-related Valve Valve seats, Not stated Not stated WEAR or CONTAM Loss of material OR

systems housing, operators, improper valve

and shafts seating

6 All safety-related Pump Impellers, bearings, Not stated Not stated WEAR Attrition

systems seals or packing

7 All safety-related Pump Strainers, housings, Not stated Not stated CONTAM Blockage of flow

systems impellers passages

8 All safety-related Heat exchangers Coil Not stated Not stated CONTAM Coil blockage

systems

9 Building atmosphere Vane type air pumps Not stated Not stated Not stated WEAR caused by Attrition

radiation monitors CONTAM

Document: NUREG/CR-3818, Report of Results of Nuclear Power Plant Aging Workshops

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Pressure and Not stated Not stated ELE-TEMP Chemical or physical

temperature sensors degradation

2 Various Pressure and Not stated Not stated VIBR Loosening

temperature sensors

3 Various Pressure and Not stated Not stated WEAR Attrition

temperature sensors

4 Various Electrical connectors Not stated Not stated CONTAM Buildup of deposits

51 Various Electrical connectors Not stated Not stated CORR Corrosion product

buildup

6 Various Valve (solenoid) Not stated Not stated CONTAM Buildup of deposits

7 Various Valve (solenoid) Not stated Not stated WEAR Attrition

8 Various Valve operators Not stated Not stated VIBR Loosening

E Various Valve operators Not stated Not stated ELE-TEMP Chemical or physical

degradation
Table A.1 Gall Report for NPAR Reports Page 19B

Document: NUREG/CR-3543, Survey of Operating Experience from LERs to Identify Aging Trends

Reviewed by: Steve U. Choi, ANL Effect of Aaina on Comoonent Function Contrib to Failure Reported nroas Rel.Droas Renort Recommendations Pac e No. Item

Wear and foreign materials cause loss of Frequent Not discussed in ASME Sec Xl Most failure studies have 9,10,17,1 5

material and improper seating, resulting in report IST and GL 89- concentrated on a generic com- 8

internal leakage and packing leakage. 10 & suppl. ponent. Future work should include

the environment for each

component/ subcomponent type of

component, and material of

construction. (More) [4]

Wear of impellers, bearings, seals, or Frequent Not discussed in ASME Sec Xl Most failure studies have 8,17,18 6

packing can lead to pump failures. report IST concentrated on a generic component. Future work should include

the environment for each

component/ subcomponenttype of

component, and material of

construction. (More) [4]

Blockage of passages, resulting in Occasional Not discussed in ASME Sec XI Most failure studies have 10 7

inadequate water flow. report IST concentrated on a generic component. Future work should include

the environment for each

component/ subcomponent"type of

component, and material of

construction. (More) [4]

Coil blockage due to silt and marine Occasional Not discussed in ASME Sec Xl Most failure studies have 10 8

growth can lead to degraded heat report or PS S&T concentrated on a generic comexchanger performance. Req. ponent. Future work should include

the environment for each

component/ subcomponenttype of

component, and material of

construction. (More) [4]

Wear caused by foreign material in the Frequent Not discussed in PS S&T Req. Most failure studies have 10,18 9

sampled air stream apparently can lead to report concentrated on a generic corn- air pump failure. ponent. Future work should include

the environment for each

component/ subcomponenttype of

component, and material of

_construction. (More) [4]

Document: NUREG/CR-3818, Report of Results of Nuclear Power Plant Aging Workshops

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Causes decalibration, set point drift, or Not stated Not discussed in If Class 1 E Additional research and developmeni 10 1

failure of sensor, report 1 0CFR 50.49 [2]

otherwise PS

S&T Req.

Causes breakage of sensor. Not stated Not discussed in If Class 1 E Additional research and developmeni 10 2

report 10CFR 50.49 [2]

otherwise PS

S&T Req. I

Causes decajibration and set point drift. Not stated Not discussed in If Class 1E Additional research and developmeni 10 3

report 1 OCFR 50.49 [2]

otherwise PS

S&T Req.

Causes spurious response and open Not stated Not discussed in PS S&T Req. Additional research and developmeni 10 4

circuits, resulting from dirt and dust. report [2]

Causes spurious response and open Not stated Not discussed in PS S&T Req. Additional research and developmenl 10 5

circuits, report [2]

Contamination of fluids results in deposits Not stated Not discussed in ASME Sec Xl- Additional research and developmeni 10 6

on valve seats and failure to seat, report IWP [2]

resulting in leakage.

Wear of movable internals can cause Not stated Not discussed in ASME Sec Xl- Additional research and developmen 10 7

hindered operation in the form of leakage report IWP [2]

or failure to open or close.

Loosening of fasteners can cause failure Not stated Not discussed in ASME Sec XI- Additional research and development 11 8

to operate or leakage. report IWV &GL 89- [2]

1 1_ 10 & Suppl.

Elevated temperatures can cause degradation of lubricants and packing,

causing excessive torque.

Not stated Not discussed in

report

ASME Sec XlIWV &GL 89-

10 & Suppl.

Additional research and developmenl

[2]

11 9
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-3818, Report of Results of Nuclear Power Plant Aging Workshops

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Como Subcomoonent Materials

Page 20A

Manufacturer ARD mechanism ARD effects

10 Various Switch/relay/circuit Not stated Not stated VIBR Crack initiation and

breaker growth

11 Various Switch/relay/circuit Not stated Not stated CONTAM Buildup of deposits

breaker

121 Various Switch/relay/circuit Not stated Not stated CORR Corrosion product

breaker buildup

31 Various Diesel Generator Not stated Not stated WEAR Attrition

14 Various Motors/pump motors Not stated Not stated ELE-TEMP Chemical or physical

degradation

15 Various Motors/pump motors Not stated Not stated WEAR Attrition

16 Various Transformers Not stated Not stated ELE-TEMP Chemical or physical

degradation

17 Various Cables Not stated Not stated ELE-TEMP Chemical or physical

degradation

18 Various Cables Not stated Not stated VIBR Crack initiation and

growth

19 Various Snubbers Not stated Not stated ELE-TEMP Thermal distortion

20 Various Piping Not stated Not stated ERO Wall thinning

21 Various Steam generators Not stated Not stated CORR Loss of material

22 Various Relief valves Not stated Not stated ERO Wall thinning

23 Various Concrete/ anchors Not stated Not stated VIBR Crack initiation and

growth

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

I All BWR and PWR Valves Not stated Not stated Not stated CONTAM; ERO Loss of desired

fluid-mechanical surface properties;

systems loss of material

All BWR and PWR

fluid-mechanical

systems

Valves Not stated Not stated Not stated CORR Loss of material
Table A.1 Gall Report for NPAR Reports Page 20B

Document: NUREG/CR-3818, Report of Results of Nuclear Power Plant Aging Workshops

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fatigue of springs. Not stated Not discussed in If Class 1 E Additional research and development 11 10

report 10CFR 50.49 [2]

otherwise PS

S&T Req.

Causes improper electrical contact and Not stated Not discussed in If Class 1 E Additional research and developmen 11 11

spurious response. report 1OCFR 50.49 [2]

otherwise PS

S&T Req. I

Pitting/thinning of contacts, causing Not stated Not discussed in If Class 1 E Additional research and development 12

spurious response. report 1OCFR 50.49 [2]

otherwise PS

S&T Req.

Causes structure failure or reduced Not stated Not discussed in PS TS Req., Additional research and developmen 11 13

output. report RG 1.9, RG [2]

1.108

Elevated temperature can cause bearing Not stated Not discussed in If Class 1 E Additional research and developmen 11 14

or motor winding insulation failures, report 1OCFR 50.49 [2]

resulting in pump stoppage. otherwise PS

S&T Req.

Wear of bearings can cause motor Not stated Not discussed in If Class 1 E Additional research and developmeni 11 15

seizure and failure to pump. report 1OCFR 50.49 [2]

otherwise PS

S&T Req. I

Elevated temperatures can cause Not stated Not discussed in If Class 1 E Additional research and developmeni 12 16

insulation failure and turn-to-turn short report 1OCFR 50.49 [2]

circuits, resulting in failure of transformer. otherwise PS

S&T Req.

Elevated temperature can cause Not stated Not discussed in PS S&T Req. Additional research and developmeni 12 17

insulation failure and short to ground. report. [2]

Vibration can cause wire breakage. Not stated Not discussed in PS S&T Req. Additional research and developmeni 12 18

report. [2]

Elevated temperature causes excessive Not stated Not discussed in ASME Sec Xl- Additional research and developmeni 12 19

thermal distortion and overstress of report. ISTD [2]

snubbers.

Erosion can cause through-wall holes and Not stated Not discussed in SR ASME Sec Additional research and development 12 20

leaks. report. Xl IWB & PS [2]

S&T

Corrosion can cause through-wall holes, Not stated Not discussed in ASME Sec X1 Additional research and developmeni 12 21

cross contamination of fluids, and report. IWB & TS Req. [2]

reduced heat transfer

Erosion can cause through-wall holes and Not stated Not discussed in ASME Sec Xl Additional research and developmeni 12 22

leaks. report. IWB & IWV & [2]

TS Req.

Vibration causes loosening of fasteners Not stated. Not discussed in ACI 224R, 318, Additional research and 12 23

from concrete and loss of anchor report. 349 & Reg development. [2]

pretension. Guide1.127

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec XI The stressors that affect the 5, 17 1

FRMA buildup and erosion due to report component availability are due to

corrosion products can eventually lead to system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2] 1

Not stated Moderate Not discussed in

report

ASME Sec Xl The stressors that affect the

component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

5 2
Table A.1 Gall Report for NPAR Reports Page 21A

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 All BWR and PWR Valves Not stated Not stated Not stated ERO Wall thinning

fluid-mechanical

systems

4 All BWR and PWR Valves Not stated Not stated Not stated VIBR Loosening; crack

fluid-mechanical initiation and growth

systems

5 All BWR and PWR Valves Not stated Not stated Not stated ELE-TEMP Not stated

fluid-mechanical

systems

6 All BWR and PWR Pumps Not stated Not stated Not stated CONTAM; ERO Loss of desired

fluid-mechanical surface properties;

systems loss of material

7 All BWR and PWR Pumps Not stated Not stated Not stated VIBR Loosening; crack

fluid-mechanical initiation and growth

systems

8 All BWR and PWR Pumps Not stated Not stated Not stated CORR Loss of material

fluid-mechanical

systems

9 All BWR and PWR Pumps Not stated Not stated Not stated FAT Cumulative fatigue

fluid-mechanical damage

systems

'C All BWR and PWR

fluid-mechanical

systems

Pumps Not stated Not stated Not stated ERO Wall thinning
Table A.1 Gall Report for NPAR Reports Page 21 B

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Aaina on Comoonent Functiorn Contrib to Failure Rer~i orted -roas Rel.nroas Renort Recommendations Paae No. Item

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 5 3

report component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

_causes. [2]

Vibrations may ultimately lead to Occasional Not discussed in ASME Sec Xl The stressors that affect the 5,17 4

component damage. report component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 5

report component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec Xl- The stressors that affect the 5,17

FRMA buildup and erosion due to report IST component availability are due to

corrosion products can eventually lead to system operation. Improve operating

component failure. environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

Vibrations may ultimately lead to Frequent Not discussed in ASME Sec Xl- The stressors that affect the 5,17

component damage. report IST component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

Not stated Moderate Not discussed in ASME Sec Xl- The stressors that affect the 5

report IST component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

Not stated Moderate Not discussed in ASME Sec Xl- The stressors that affect the 5

report IST component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

-causes. (2]

Not stated Occasional Not discussed in ASMF Sec XIreport IST

The stressors mat affect me component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes [2]

5 IV
Table A.1 Gall Report for NPAR Reports Page 22A

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

11 All BWR and PWR Pumps Not stated Not stated Not stated ELE-TEMP Not stated

fluid-mechanical

systems

12 All BWR and PWR Pipes Not stated Not stated Not stated CORR Not stated

fluid-mechanical

systems

13 All BWR and PWR Pipes Not stated Not stated Not stated CONTAM; ERO Loss of desired

fluid-mechanical surface properties;

systems loss of material

14 All BWR and PWR Pipes Not stated Not stated Not stated ERO Wall thinning

fluid-mechanical

systems

15 All BWR and PWR Pipes Not stated Not stated Not stated FAT Cumulative fatigue

fluid-mechanical damage

systems

16 All BWR and PWR Pipes Not stated Not stated Not stated ELE-TEMP Not stated

fluid-mechanical

systems

17 All BWR and PWR Pipes Not stated Not stated Not stated VIBR Loosening; crack

fluid-mechanical initiation and growth

systems

All IWVVH ana i-'vW

fluid-mechanical

systems

All components

(valves, pumps and

pipes)

NOt stated Not stated Not stated CONTAM; ERO Loss of desired

surface properties;

loss of material
Table A.1 Gall Report for NPAR Reports Page 22B

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Aaina on Comnonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Paqe No. Item

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 5 11

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

Not stated Frequent Not discussed in ASME Sec Xl The stressors that affect the 5 12

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [2]

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec XA The stressors that affect the 5,17 13

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec Xl The stressors that affect the 5 14

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec XI The stressors that affect the 5 15

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to Occasional Not discussed in ASME Sec X1 The stressors that affect the 5 16

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Vibrations may ultimately lead to Occasional Not discussed in ASME Sec XI The stressors that affect the 5,17 17

component damage. report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to

FRMA buildup and erosion due to

corrosion products can eventually lead to

component failure.

Frequent Not discussed in

report

ASME Sec Xl

& PS S&T

Req.

The stressors that affect the

component availability are due to

system operation. Improve operatinc

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

6,17 18
Table A.1 Gall Report for NPAR Reports Page 23A

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 All BWR and PWR All components Not stated Not stated Not stated VIBR Loosening; crack

fluid-mechanical (valves, pumps and initiation and growth

systems pipes)

20 All BWR and PWR All components Not stated Not stated Not stated CORR Loss of material

fluid-mechanical (valves, pumps and

systems pipes)

21 All BWR and PWR All components Not stated Not stated Not stated ERO Wall thinning

fluid-mechanical (valves, pumps and

systems pipes)

22 All PWR fluid- Valves, pumps and Not stated Not stated Not stated VIBR Loosening; crack

mechanical systems pipes initiation and growth

23 All PWR fluid- Valves, pumps and Not stated Not stated Not stated CONTAM; ERO Loss of desired

mechanical systems pipes surface properties;

loss of material

24 All PWR fluid- Valves, pumps and Not stated Not stated Not stated CORR Loss of material

mechanical systems pipes

25 All PWR fluid- Valves, pumps and Not stated Not stated Not stated ERO Wall thinning

mechanical systems pipes

All BWR fluidmechanical systems

Valves, pumps and

pipes

Not stated Not stated Not stated CONTAM; ERO Loss of desired

surface properties;

loss of material
Table A.1 Gall Report for NPAR Reports Page 23B

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Aaina an Compnennnt Function Contrib to Failure Rn wted oroas Rel.oroas Reeort Recommendations Paae No. Item

Vibrations may ultimately lead to Moderate Not discussed in ASME Sec XI The stressors that affect the 6,17 19

component damage. report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec X1 The stressors that affect the 6 20

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec XI The stressors that affect the 6 21

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Frequent Not discussed in ASME Sec XA The stressors that affect the 6,17 22

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to Moderate Not discussed in ASME Sec Xl The stressors that affect the 6, 17 23

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]1

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 6 24

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 6 25

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4] 1 1 1

The cumulative effects of corrosion due to

FRMA buildup and erosion due to

corrosion products can eventually lead to

component failure.

Frequent Not discussed in

report

ASME Sec XI

& PS S&T

Req.

The stressors that affect the

component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

6,17 26
Table A.1 Gall Report for NPAR Reports Page 24A

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System StucturelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

27 All BWR fluid- Valves, pumps and Not stated Not stated Not stated CORR Loss of material

mechanical systems pipes

28 All BWR fluid- Valves, pumps and Not stated Not stated Not stated ERO Wall thinning

mechanical systems pipes

29 All BWR fluid- Valves, pumps and Not stated Not stated Not stated VIBR Loosening; crack

mechanical systems pipes initiation and growth

30 Residual heat Valves, pumps and Not stated Not stated Not stated VIBR Loosening; crack

removal systems for pipes initiation and growth

BWRs

31 Residual heat Valves, pumps and Not stated Not stated Not stated CONTAM; ERO Loss of desired

removal systems for pipes surface properties;

BWRs loss of material

32 Residual heat Valves, pumps and Not stated Not stated Not stated CORR Loss of material

removal systems for pipes

BWRs

33 Residual heat Valves, pumps and Not stated Not stated Not stated ERO Wall thinning

removal systems for pipes

BWRs

34 Safety injection

system for PWRs

Valves, pumps and

pipes

Not stated INot stated Not stated VIBR Loosening; crack

initiation and growth
Table A.1 Gall Report for NPAR Reports Page 24B

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Not stated Moderate Not discussed in ASME Sec XI The stressors that affect the 6 27

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec Xl The stressors that affect the 6 28

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Vibrations may ultimately lead to Occasional Not discussed in ASME Sec Xl The stressors that affect the 6,17 29

component damage. report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Vibrations may ultimately lead to Frequent Not discussed in ASME Sec Xl The stressors that affect the 7,11,17 30

component damage. report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec XI The stressors that affect the 7,11,17 31

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to Occasional Not discussed in ASME Sec Xl The stressors that affect the 7,11 32

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 7,11 33

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Vibrations may ultimately lead to

component damage.

Frequent Not discussed in

report

ASME Sec XI

& PS S&T

Req.

The stressors that affect the

component availability are due to

system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

7, 11,17 1 34
Table A.1 Gall Report for NPAR Reports Page 25A

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

35 Safety injection Valves, pumps and Not stated Not stated Not stated CONTAM; ERO Loss of desired

system for PWRs pipes surface properties;

loss of material

36 Safety injection Valves, pumps and Not stated Not stated Not stated FAT Cumulative fatigue

system for PWRs pipes damage

37 Safety injection Valves, pumps and Not stated Not stated Not stated ELE-TEMP Not stated

system for PWRs pipes

38 Cooling water Valves, pumps and Not stated Not stated Not stated CONTAM; ERO Loss of desired

system for PWRs pipes surface properties;

loss of material

39 Cooling water Valves, pumps and Not stated Not stated Not stated VIBR Loosening; crack

system for PWRs pipes initiation and growth

40 Cooling water Valves, pumps and Not stated Not stated Not stated ERO Wall thinning

system for PWRs pipes

41 Cooling water Valves, pumps and Not stated Not stated Not stated CORR Loss of material

system for PWRs pipes

Document: NUREG/CR-4144, Importance Ranking Based on Aging Considerations of Components Included in Probabilistic Risk Assessments

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Entire plant Broad spectrum This report does not

provide specific

detailed information

on aging

mechanisms for

specific

____________________________components. ___________________________________
Table A.1 Gall Report for NPAR Reports Page 25B

Document: NUREG/CR-3819, Survey of Aged Power Plant Facilities

Reviewed by: Steve U. Choi, ANL

Effect of Acina on Component Function Contrib to Failure ReDorted vroas Rel.proas Report Recommendations Pace No. Item

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec XI The stressors that affect the 7,11,17 35

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure. environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [41 "

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 7,11 36

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

_causes. [4]

Not stated Occasional Not discussed in ASME Sec XI The stressors that affect the 7,11 37

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

The cumulative effects of corrosion due to Frequent Not discussed in ASME Sec Xl The stressors that affect the 7,11,17 38

FRMA buildup and erosion due to report & PS S&T component availability are due to

corrosion products can eventually lead to Req. system operation. Improve operating

component failure, environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Vibrations may ultimately lead to Frequent Not discussed in ASME Sec XI The stressors that affect the 7, 11,17 39

component damage. report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec Xt The stressors that affect the 7,11 40

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4]

Not stated Moderate Not discussed in ASME Sec XI The stressors that affect the 7, 11 41

report & PS S&T component availability are due to

Req. system operation. Improve operating

environments first and include such

information as (a) vibration, (b)

contamination, (c) corrosion, and (d)

erosion to gain insight into root

causes. [4] 1 1

Document: NUREG/CR-4144, Importance Ranking Based on Aging Considerations of Components Included in Probabilistic Risk Assessments

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

_________________ ________ ______ _____

____.=i
Table A.1 Gall Report for NPAR Reports Page 26A

Document: NUREG/CR-4279, Aging and Service Wear of Hydraulic and Mechanical Snubbers Used on Safety-Related Piping and Components of Nuclear Power

Reviewed by: John W. Holland, ANL

Item System Sltucture/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Hydraulic Snubber Control Valve Not stated Not stated VIBR Loosening

2 Various Hydraulic Snubber Reservoir Not stated Not stated VIBR Loosening

3 Various Hydraulic Snubber Reservoir Not stated Not stated ELE-TEMP Thermal Distortion

4 Various Hydraulic Snubber Cylinder Not stated Not stated VIBR Loosening

51 Various Hydraulic Snubber Cylinder Not stated Not stated ELE-TEMP Thermal Distortion

6 Various Hydraulic Snubber Seal Polyurethane, Nitrile Not stated ELE-TEMP Thermal Distortion

Rubber, Viton,

Ethylene Propylene,

Tefzel, and Metal 0-

rings

7 Various Hydraulic Snubber Seal Polyurethane, Nitrile Not stated EMBR/IR Loss of Fracture

Rubber, Viton, Toughness

Ethylene Propylene,

Tefzel, and Metal 0-

rings

8 Various Hydraulic Snubber Seal Polyurethane, Nitrile Not stated WEAR Attrition

Rubber, Viton,

Ethylene Propylene,

Tefzel, and Metal 0-

rings

9 Various Hydraulic Snubber Hydraulic Fluid Not stated Not stated CONTAM Change in Viscosity

10 Various Mechanical Snubber Motion Sensor Not stated Not stated VIBR Loosening

11 Various Mechanical Snubber Motion Sensor Not stated Not stated CORR/OX Corrosion Product

Buildup, Internal

Damage

12 Various Mechanical Snubber Activation Rod Not stated Not stated VIBR Loosening

13 Various Mechanical Snubber Activation Rod Not stated Not stated CORR/OX Corrosion Product

Buildup, Internal

Damage

14 Various Mechanical Snubber Brake Mechanism Not stated Not stated VIBR Loosening

15 Various Mechanical Snubber Brake Mechanism Not stated Not stated CORR/OX Corrosion Product

Buildup, Internal

Damage
Table A.1 Gall Report for NPAR Reports Page 26B

Document: NUREG/CR-4279, Aging and Service Wear of Hydraulic and Mechanical Snubbers Used on Safety-Related Piping and Components of Nuclear Power

Reviewed by: John W. Holland, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Loosening of the Control Valve can cause Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4,3.16, 1

the component to become inoperative. ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 5.5, 8.1

Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Loosening of the Reservoir can lead to Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 3.16, 2

loss of hydraulic fluid and cause the ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 5.5, 8.1

component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule] I

Thermal distortion of the Reservoir can Rare ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 3

lead to loss of hydraulic fluid and cause ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

the component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Loosening of the Cylinder can lead to loss Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 4

of hydraulic fluid and cause the ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. (4-Maint rule]

Thermal distortion of the Cylinder can Rare ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 5

lead to loss of hydraulic fluid and cause ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

the component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Thermal distortion of the Seal can lead to Occasional ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 6

loss of hydraulic fluid and cause the ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Embrittiement of the Seal can lead to loss Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 7

of hydraulic fluid and cause the ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

component to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Wear of the Seal can lead to loss of Moderate ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 8

hydraulic fluid and cause the component ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

to become inoperative. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Viscosity change of the hydraulic fluid can Moderate ASME XI Std. ASME Sec XI Determine if in-service testing can 2.4, 5.5, 9

cause the component to operate ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

improperly. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Loosening of the Motion Sensor can lead Infrequent ASME XI Std. ASME Sec Xl Determine if in-service testing can 2.6-2.8, 10

to component failure and system lockup. ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Corrosion product buildup and internal Moderate ASME XI Std. ASME Sec XI Determine if in-service testing can 2.6-2.8, 11

damage of the Motion Sensor can lead to ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

lockup. Std. periodic inspection, surveillance, and

_maintenance. [4-Maint rule]

Loosening of the Activation Rod can lead Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.6-2.8, 12

to component failure and system lockup. ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule] I

Corrosion product buildup and internal Moderate ASME XI Std. ASME Sec XI Determine if in-service testing can 2.6-2.8, 13

damage of the Activation Rod can lead to ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16,8.1

lockup. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule]

Loosening of the Brake Mechanism can Infrequent ASME XI Std. ASME Sec XI Determine if in-service testing can 2.6-2.8, 14

lead to component failure and system ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

lockup. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule] I

Corrosion product buildup and internal Moderate ASME XI Std. ASME Sac XI Determine if in-service testing can 2.6-2.8, 15

damage of the Brake Mechanism can lead ANSI/ASME OM4 OM Code ISTD detect aging mechanisms. Perform 3.16, 8.1

to lookup. Std. periodic inspection, surveillance, and

maintenance. [4-Maint rule] I
Table A.1 Gall Report for NPAR Reports Page 27A

Document: NUREG/CR-4302, Vol. 1, Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item Svstem StructureJComD Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR and BWR Swing check valve Body assembly Types 304 and 316 Not stated WEAR Attrition

safety systems SS

2 PWR and BWR Swing check valve Body assembly Types 304 and 316 Not stated CORR Loss of material

safety systems SS

3 PWR and BWR Swing check valve Body assembly Types 304 and 316 Not stated ERO Wall thinning

safety systems SS

4 PWR and BWR Swing check valve Internals Stainless steel, Not stated WEAR Attrition

safety systems Stellite and Hastelloy

slots

5 PWR and BWR Swing check valve Internals Stainless steel, Not stated CORR Loss of material

safety systems Stellite and Hastelloy

slots

6 PWR and BWR Swing check valve Internals Stainless steel, Not stated ERO Loss of material

safety systems Stellite and Hastelloy

slots

7 PWR and BWR Swing check valve Internals Stainless steel, Not stated FAT Cumulative fatigue

safety systems Stellite and Hastelloy damage

slots

8 PWR and BWR Swing check valve Internals Stainless steel, Not stated CONTAM Loss of desired

safety systems Stellite and Hastelloy surface properties

slots

9 PWR and BWR Swing check valve Seals Welded seal, steel Not stated ELE-TEMP Chemical

safety systems sealing ring, degradation and

asbestos thermal distortion

10 PWR and BWR Horizontal piston-lift, Body assembly Types 304 and 316 Not stated WEAR Attrition

safety systems vertical-lift, and ball SS

check valves

11 PWR and BWR Horizontal piston-lift, Body assembly Types 304 and 316 Not stated CORR Loss of material

safety systems vertical-lift, and ball SS

check valves

12 PWR and BWR Horizontal piston-lift, Body assembly Types 304 and 316 Not stated ERO Wall thinning

safety systems vertical-lift, and ball SS

check valves

13 PWR and BWR Horizontal piston-lift, Internals Stainless steel, Not stated WEAR Attrition

safety systems vertical-lift, and ball Stellite and Hastelloy

check valves slots

14 PWR and BWR Horizontal piston-lift, Internals Stainless steel, Not stated CORR Loss of material

safety systems vertical-lift, and ball Stellite and Hastelloy

check valves slots

15 PWR and BWR Horizontal piston-lift, Internals Stainless steel, Not stated ERO Loss of material

safety systems vertical-lift, and ball Stellite and Hastelloy

check valves slots

1 E PWR and BWR

safety systems

Horizontal piston-lift,

vertical-lift, and ball

check valves

Internals Stainless steel,

Stellite and Hastelloy

slots

Not stated FAT Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 27B

Document: NUREG/CR-4302, Vol. 1, Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of A ina on Component Function Contrib to Failure Reported Droas Rel.Droas Report Recommendations Page No. Item

Causes obturator guide/holder to lose Infrequent Not discussed in ASME Sec X1 Improve inspection techniques and 4, 5, 8, 9, 1

tolerance and obturator to fall to seat report IST and IWB surveillance at plants [2] 10,14-18,

resulting in reverse leakage. 19,21,

26, 37, 38

Causes wall thinning and through-wall Infrequent Not discussed in ASME Sec Xl Not stated 4, 5, 8, 9, 2

external leakage. report IST and IWB 10,14-18,

19,21,

26, 37, 38

Causes wall thinning and through-wall Infrequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 3

external leakage. report IST and IWB 10,14-18,

19,21,

26, 37, 38

Causes hanger pin and bearing, obturator Frequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 4

hanger, and obturator to lose tolerance report IST and IWB 10,14-18,

resulting in valve failure to open or close 19, 21,

or reverse leakage. 49-52

Causes seat to lose tolerance and reverse Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 5

leakage. report IST and IWB 10,14-18,

19,21,

49-52

Causes seat to lose tolerance and reverse Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 6

leakage. report IST and IWB 10,14-18,

19,21,

49-52

Repetitive opening and closing of valve or Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 7

vibration can cause breakage of obturator report IST and IWB & 10, 14-18,

pin, arm, or obturator. Sec III 19,21,

I_ 49-52

Foreign material accumulation on seat or Moderate Not discussed in ASME Sec Xl Not stated 4, 5, 8, 9, 8

obturator surfaces can cause failure to report IST and IWB 10,14-18,

seat and reverse leakage. 19,21,

49-52

rSeal degradation can cause external Infrequent Not discussed in ASME Sec Xl Not stated 4, 5, 8, 9, 9

leakage. report IST and IWB 10, 14-18,

19,21,

49-52

Causes obturator guide/holder to lose Infrequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 10

tolerance and obturator to fall to seat report IST and IWB 10, 14-18,

resulting in reverse leakage. 19,21,

25, 37,

38, 49-52

Causes wall thinning and through wall Infrequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 11

external leakage. report IST and IWB 10,14-18,

19,21,

25, 37,

38, 49-52

Causes wall thinning and through wall Infrequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 12

external leakage. report IST and IWB 10, 14-18,

19,21,

25, 37,

38, 49-52

Causes obturator to lose tolerance Frequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 13

resulting in valve failure to open, close, or report IST and IWB 10,14-18,

reverse leakage. 19,21,

49-52

Causes seat to lose tolerance and reverse Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 14

leakage. report IST and IWB 10, 14-18,

19,21,

49-52

Causes seat to lose tolerance and reverse Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 15

leakage. report IST and IWB 10, 14-18,

19,21,

49-52

Repetitive opening and closing of valve or fluid induced vibration can cause cracking

of obturator or slot.

Moderate Not discussed in

report

ASME Sec Xl

IST and IWB &

Sec Ill

Not stated 4,5,8,9,

10,14-18,

19,21,

49-52

16
Table A.1 Gall Report for NPAR Reports Page 28A

Document: NUREG/CR-4302, Vol. 1, Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

17 PWR and BWR Horizontal piston-lift, Internals Stainless steel, Not stated CONTAM Loss of desired

safety systems vertical-lift, and ball Stellite and Hastelloy surface properties

check valves slots

18 PWR and BWR Horizontal piston-lift, Seals Welded seal, steel Not stated ELE-TEMP Chemical

safety systems vertical-lift, and ball sealing ring, degradation and

check valves asbestos thermal distortion

Document: NUREG/CR-4302, Vol. 2, Aging and Service Wear of Check Valves Used in Engineered Safety Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Engineered safety- Check valve (swing Body assembly Not stated Not stated WEAR Attrition

feature systems type)

2 Engineered safety- Check valve (swing Body assembly Not stated Not stated FAT Cumulative fatigue

feature systems type) damage

3 Engineered safety- Check valve (swing Body assembly Not stated Not stated ERO Wall thinning

feature systems type)

4 Engineered safety- Check valve (swing Body assembly Not stated Not stated CORR Loss of material

feature systems type)

5 Engineered safety- Check valve (swing Hinge pin Not stated Not stated WEAR Attrition

feature systems type)

6 Engineered safety- Check valve (swing Hinge pin Not stated Not stated CORR Corrosion product

feature systems type) buildup

7 Engineered safety- Check valve (swing Hinge pin Not stated Not stated FAT Cumulative fatigue

feature systems type) damage

8 Engineered safety- Check valve (swing Hinge arm Not stated Not stated WEAR Attrition

feature systems type)

9 Engineered safety- Check valve (swing Hinge arm Not stated Not stated FAT Cumulative fatigue

feature systems type) damage

10 Engineered safety- Check valve (swing Disc nut Not stated Not stated VIBR Loosening

feature systems type)

11 Engineered safety- Check valve (swing Disc Not stated Not stated WEAR Attrition

feature systems type)

12 Engineered safety- Check valve (swing Disc Not stated Not stated ERO/CORR Wall thinning

feature systems type)

13 Engineered safety- Check valve (swing Seat Not stated Not stated WEAR Attrition

feature systems type)

14 Engineered safety- Check valve (swing Seat Not stated* Not stated ERO/CORR Wall thinning

feature systems type)

15 Engineered safety- Check valve (swing Cap gasket Not stated Not stated Not stated Gasket deterioration

feature systems type) I I I II

Document: NUREG/CR-4380, Evaluation of the Motor Operated Valve Analysis and Test System (MOVATS) to Detect Degradation, Incorrect Adjustments, and Otl

Reviewed by: David C. Ma, ANL

Item Svstem StructureJComn Subcomnonent Materials Manufanturer ARI mpnhnnicm ARD affant_
Table A.1 Gall Report for NPAR Reports Page 28B

Document: NUREG/CR-4302, Vol. 1, Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Foreign material accumulating on seat or Moderate Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 17

obturator surfaces can cause failure to report IST and IWB 10, 14-18,

seat and reverse leakage. 19,21,

49-52

Seal degradation can cause extemal Infrequent Not discussed in ASME Sec XI Not stated 4, 5, 8, 9, 18

leakage. report IST and IWB 10, 14-18,

19,21,

49-52

Document: NUREG/CR-4302, Vol. 2, Aging and Service Wear of Check Valves Used in Engineered Safety Feature Systems of Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Movement of hinge pin in body mounting Moderate Not stated ASME Sec XI Improve surveillance requirements 81

holes causes holes to enlarge, leading to IWB or IST and techniques [4]

improper tracking of valve hinge arm and

potential impacting of swing valve with

valve body, thereby weakening valve body.

Repetitive swinging of arm and impacting Infrequent Not stated ASME Sec XI Improve surveillance requirements 8 2

of valve disc on body can cause cracking IWB or IST and techniques [4]

of body and external leakage.

Leakage past an improperly seated valve Moderate Not stated ASME Sec XI Improve surveillance requirements 8 3

can cause erosion of valve body and wall IWB or IST and techniques [4]

thinning.

Corrosion can lead to valve body leakage. Infrequent Not stated ASME Sec Xl Improve surveillance requirements 8 4

IWB or IST and techniques [4]

Flutter of valve causes wear of hinge pin, Frequent Not stated ASME Sec XI Improve surveillance requirements 2, 3, 4, 8 5

loss of hinge function, improper valve arm IWB or IST and techniques [4]

motion, and valve seating or sticking. I

Corrosion of hinge pin causes resistance Occasional Not stated ASME Sec XI Improve surveillance requirements 8 6

to motion of hinge arm and retarding of IWB or IST and techniques [4]

valve opening or closing.

Rattling of hinge pin in enlarged valve Occasional Not stated ASME Sec XI Improve surveillance requirements 2, 3, 8 7

body holes resulting from disc flutter can IWB or IST and techniques [4]

cause fatigue breakage of pin.

Flutter of the arm caused by fluid/arm Frequent Not stated ASME Sec XI Improve surveillance requirements 2, 3, 8 8

instabilities, prevalently occurring at low IWB or IST and techniques [4]

flows or caused by upstream flow

disturbances, causes wear between arm

and hinge pin, leading to impaired valve

motion and flow control. I

Long term flutter of arm and cyclic loading Infrequent Not stated ASME Sec XI Improve surveillance requirements 2, 8 9

or impacting of arm with other valve parts IWB or IST and techniques [4]

can cause arm breakage and complete

loss of function.

Flutter of hinge arm or impacting of arm Occasional Not stated ASME Sec XI Improve surveillance requirements 8 10

can cause nut to loosen. IWB or IST and techniques [4]

Excessive wear of the hinge assembly Infrequent Not stated ASME Sec XI Improve surveillance requirements 8 11

can cause the disc to contact with other IWB or IST and techniques [4]

valve parts and wear, resulting in improper

seating and leakage.

Erosion/corrosion carn cause sealing Occasional Not stated ASME Sec XI Improve surveillance requirements 8 12

surface irregularities and valve leakage. IWB or IST and techniques [4]

Disc/arm flutter instabilities can cause Occasional Not stated ASME Sec XI Improve surveillance requirements 7, 8 13

disc to rub or impact seat, producing seat IWB or IST and techniques [4]

wear and leakage.

Erosion/corrosion can cause sealing Frequent Not stated ASME Sec XI Improve surveillance requirements 8 14

surface irregularities and valve leakage. IWB or IST and techniques [4]

Cap gasket deterioration can cause valve Not stated Not stated ASME Sec XI Improve surveillance requirements 8 15

external leakage. IWB or IST and techniques [4]

Document: NUREG/CR-4380, Evaluation of the Motor Operated Valve Analysis and Test System (MOVATS) to Detect Degradation, Incorrect Adjustments, and Oti

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Wear and possible gear teeth breakage Occasional Not discussed in ASME Sec Xl Not stated 14,32

leads to failure of the valve to operate. I I report I& GL 89-10 1 1

Stem bent results in failure of the valve to Occasional

complete its stroke because of premature

torque switch grip.

Not discussed in ASME Sec Xl INot stated

report I&GL89-10 I 114,32 1
Table A.1 Gall Report for NPAR Reports Page 29A

Document: NUREG/CR-4380, Evaluation of the Motor Operated Valve Analysis and Test System (MOVATS) to Detect Degradation, Incorrect Adjustments, and Ot

Reviewed by: David C. Ma, ANL

Item System Structure/ComD Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 Not stated Motor operated Motor Pinion Not stated Limitorque Corp. ADH Loss of movement

valves

4 Not stated Motor operated Stem Not stated Limitorque Corp. WEAR Attrition

valves

5 Not stated Motor operated Stem/Spring Not stated Limitorque Corp. ENVIR Physical or chemical

valves degradation

6 Not stated Motor operated Motor Not stated Limitorque Corp. WEAR Attrition

valves

Document: NUREG/CR-4597, Vol. 1, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Auxiliary feedwater Rotor 400-series SS Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

centrifugal)

2 Cooling system Auxiliary feedwater Rotor 400-series SS Not stated WEAR Attrition

multistage pumps

(high-head

_centrifugal)

3 Cooling system Auxiliary feedwater Shaft Type 410, 414, or Not stated FAT Cumulative fatigue

multistage pumps 416SS damage

(high-head

centrifugal)

4 Cooling system Auxiliary feedwater Shaft Type 410, 414, or Not stated WEAR Attrition

multistage pumps 416SS

(high-head

centrifugal)

5 Cooling system Auxiliary feedwater Impeller Cast high-chromium Not stated FAT Cumulative fatigue

multistage pumps alloy steels: 13-5, damage

(high-head 15-5, and 17-4 PH

I_ centrifugal)

6 Cooling system Auxiliary feedwater Impeller Cast high-chromium Not stated WEAR Attrition

multistage pumps alloy steels: 13-5,

(high-head 15-5, and 17-4 PH

centrifuglal)

7 Cooling system Auxiliary feedwater Impeller Cast high-chromium Not stated ERO/CAV Wall thinning: loss o

multistage pumps alloy steels: 13-5, material

(high-head 15-5, and 17-4 PH

centrifugal)

8 Cooling system Auxiliary feedwater Thrust runner Type 416, 420, or Not stated FAT Cumulative fatigue

multistage pumps 420F SS damage

(high-head

_centrifugal)

9 Cooling system Auxiliary feedwater Thrust runner Type 416, 420, or Not stated WEAR Attrition

multistage pumps 420F SS

(high-head

.. _ centrifugal) I I

101 Cooling system Nonrotating internals Stationary vanes (diffuser or volute)Types 440A and

440B cast SS; 17-4

PH SS

Not stated FAT Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 29B

Document: NUREG/CR-4380, Evaluation of the Motor Operated Valve Analysis and test System (MOVATS) to Detect Degradation, Incorrect Acgustments, and Oti

Reviewed by: David C. Ma, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported Droas Rel.proqs Report Recommendations Paqe No. Item

Motor pinion binding can cause failure of Occasional Not discussed in ASME Sec Xl Not stated 14,'32 3

the motor operator to operate because of report & GL 89-10

motor burnout or actuation of the thermal

overload switch.

Stem wear in the form of worn threads or Occasional Not discussed in ASME Sec XI Not stated 14, 32 4

burrs can lead to failure to operate report & GL 89-10

because of gear breakage or premature

torque switch trip. I

Grease hardening results from extended Occasional Not discussed in ASME Sec Xl Not stated 15, 32 5

exposure of the grease to elevated report & GL 89-10

temperatures or radiation. The grease

hardening between the motor and the

worm gear can lead to a broken obturator

or seat on a bent stem, resulting from the

excess torque...

Motor bearing wear and changes in the Infrequent Not discussed in ASME Sec XI Not stated 15, 32 6

electrical resistance characteristics of report & GL 89-10

either the conductor or insulation can lead

to motor failure or actuation of the motor

thermal overload switch.

Document: NUREG/CR-4597, Vol. 1, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Hydraulically induced transient loading Moderate Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 14, 19, 1

and vibration of rotor at off normal report IST of AUXFP. Improve the pump 29, 45,

conditions associated with low flow can design to meet conditions [4] 64, 65

cause component fatigue fracture and

consequent reduced pump efficiency and

possible seizure.

Wear of various rotor surfaces due to off- Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 14, 19, 2

normal operation can cause progressive report IST of AUXFP. Improve the pump 29, 45,84

loss of efficiency, design to meet conditions [41

Hydraulic induced transient loading of Moderate Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 29, 45, 3

shaft at far off-design flows can cause report IST of AUXFP. Improve the pump 50, 64,65

progressive loss of shaft integrity and design to meet conditions [4]

possible pump seizure. I

Rubbing of shaft at wear surfaces due to Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 29, 45, 4

hydraulic caused transient forces causes report IST of AUXFP. Improve the pump 50, 64,65

shaft play and possible seizure. design to meet conditions [4]

Hydraulic induced transient loading of Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 29, 45, 5

impeller at off-design power operation report IST of AUXFP. Improve the pump 50, 64

causes progressive loss of integrity, design to meet conditions [4]

Rubbing at wear surfaces results in loss Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 29, 45, 6

of pump capacity to satisfy load report IST of AUXFP. Improve the pump 50, 64

requirements. design to meet conditions [4]

Insufficient NPSH and operating far from Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 9,29, 45, 7

design point can cause wall thinning and report IST of AUXFP. Improve the pump 50

structural failure of impeller, design to meet conditions [4]

Hydraulic instabilities at low flow causes Occasional Not discussed in ASME Sec XI Improve surveillance and monitoring 19, 47, 8

cyclic loading of component and cracking report IST of AUXFP. Improve the pump 49, 50, 64

leading to failure of pump to operate. design to meet conditions [4]

Transient loading of runners during Moderate Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 47, 49, 9

startup and running at low flow causes report IST of AUXFP. Improve the pump 50, 64

excessive wear and reduced pump design to meet conditions [4]

efficiency. I I

Hydraulic instabilities at low flow can

cause excessive vane vibration, leading to

vane breakage and pump stoppage.

Occasional Not discussed in

report

ASME Sec Xl

IST

Improve surveillance and monitoring

of AUXFP. Improve the pump

design to meet conditions [4]

9,15, 34,

42, 64
Table A.1 Gall Report for NPAR Reports Page 30A

Document: NUREG/CR-4597, Vol. 1, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item Svstem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

11 Cooling system Nonrotating internals Wear-surface 400-series SS Not stated WEAR Attrition

12 Cooling system Auxiliary feedwater Fasteners Cr-Mo steels Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

centrifugal)

13 Cooling system Auxiliary feedwater Pressure Cast 416 SS Not stated FAT Cumulative fatigue

multistage pumps containment casing (CA6NM) damage

(high-head

centrifugal)

14 Cooling system Auxiliary feedwater Suction nozzle Cast 416 SS Not stated FAT Cumulative fatigue

multistage pumps (CA6NM) damage

(high-head

centrifugal)

15 Cooling system Auxiliary feedwater Discharge nozzle Cast 416 SS Not stated FAT Cumulative fatigue

multistage pumps (CA6NM) damage

(high-head

centrifugal)

16 Cooling system Auxiliary feedwater Bearing Specialty steels Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

centrifugal)

17 Cooling system Auxiliary feedwater Bearing Specialty steels Not stated CONTAM Loss of lubricant

multistage pumps properties and

(high-head desired surface

centrifugal) _ properties

18 Cooling system Auxiliary feedwater Shaft seal Not stated Not stated WEAR Attrition

multistage pumps

(high-head

centrifugal)

19 Cooling system Auxiliary feedwater Thrust balancer 400-series SS Not stated WEAR Attrition

multistage pumps

(high-head

centrifugal)

20 Cooling system Auxiliary feedwater Thrust balancer 400-series SS Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

centrifugal)

21 Cooling system Auxiliary feedwater Coupling (gear type) Not stated Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

centrifugal)

22 Cooling system Auxiliary feedwater Coupling (gear type) Not stated Not stated WEAR Attrition

multistage pumps

(high-head

centrifugal)

23 Cooling system Auxiliary feedwater Fastener 400-series SS Not stated FAT Cumulative fatigue

multistage pumps damage

(high-head

1 _ 1 centrifugal) I
Table A.1 Gall Report for NPAR Reports Page 30B

Document: NUREG/CR-4597, Vol. 1, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.progs Report Recommendations Paae No. Item

Excessive wear of the impeller wear Frequent Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 29, 41, 11

surface rings is a result of excessive shaft report IST of AUXFP. Improve the pump 45, 50,

flexibility and operation at hydraulically design to meet conditions [4] 64, 87

unstable conditions, resulting in reduced

pump efficiency and capacity to deliver

flow.

Vibration can cause loosening or fatigue Occasional Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 20, 21, 12

fracture of fasteners ,resulting in report IST of AUXFP. Improve the pump 45, 49, 64

loosening of parts and possible design to meet conditions [4]

misalignment and pump seizure. I

Operation of pump at low flows produces Occasional Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 20, 34, 13

hydraulic instabilities that cause large report IST of AUXFP. Improve the pump 47, 49,

pressure oscillations and the potential for design to meet conditions [4] 50, 64

fatigue cracking of casing, resulting in

leakage.

Operation of pump at low flows produces Occasional Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 20, 34, 14

hydraulic instabilities that cause large report IST of AUXFP. Improve the pump 47, 49,

pressure oscillations and the potential for design to meet conditions [4] 50,64

fatigue cracking of casing, resulting in

leakage. I

Operation of pump at low flows produces Occasional Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 20, 34, 15

hydraulic instabilities that cause large report IST of AUXFP. Improve the pump 47, 49,

cyclic pressure fluctuations, possible design to meet conditions [4] 50, 64

fatigue cracking of discharge nozzles,

failure of pump to operate at design flows,

and leakage.

Operation of pump at low flows far from Moderate Not discussed in ASME Sec Xl Improve surveillance and monitoring 9,17, 29, 16

design point produces hydraulic report IST of AUXFP. Improve the pump 22, 34,

instabilities, causing large cyclic bearing design to meet conditions [4] 45, 64

loads and possible bearing fracture and

pump seizure.

Foreign material in lubricant and operation Frequent Not discussed in ASME Sec XI Improve surveillance and monitoring 9,17,19, 17

at excessive temperature can cause report IST of AUXFP. Improve the pump 22,29,

lubricant breakdown, resulting in bearing design to meet conditions [4] 34, 45,

seizure and failure to operate. 50, 64

Rotational rubbing between shaft and Frequent Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 29, 45, 18

seal, often aggravated by inadequate report IST of AUXFP. Improve the pump 50, 83

injection water, causes wear and rapidly design to meet conditions [4]

increasing leakage, decreasing pump

delivered capacity.

Wear between close tolerance moving Moderate Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 29, 45, 19

surfaces aggravated by unsteady thrust report IST of AUXFP. Improve the pump 80, 81,

forces at part load causes loss of force design to meet conditions (4] 82, 83

balancing and reduced flow.

Operation of pump at low flow and Occasional Not discussed in ASME Sec Xl Improve surveillance and monitoring 9, 29, 50, 20

frequent startup cause wear surface wear report IST of AUXFP. Improve the pump 80-83

and increased unbalance loads and design to meet conditions [4]

vibrations, causing cracking of balancer

and pump seizure.

Frequent starting/stopping of pump Occasional Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 47, 50, 21

produces large loads on gearing and report IST of AUXFP. Improve the pump 64

fatigue cracking of gear, resulting in design to meet conditions [4]

failure of pump to operate.

Frequent starting and stopping of pump Occasional Not discussed in ASME Sec Xl Improve surveillance and monitoring 47, 50, 22

and poor lubrication causes gear wear report 1ST of AUXFP. Improve the pump 64, 66

and reduced pump efficiency, design to meet conditions [4]

Vibration can cause breakage of fasteners Occasional Not discussed in ASME Sec XI Improve surveillance and monitoring 9, 20,21, 23

or loosening, resulting in leakage at a report IST of AUXFP. Improve the pump 45, 49,

pressure containment boundary such as design to meet conditions [4] 64, 65

the casing. I I I I I
Table A.1 Gall Report for NPAR Reports Page 31A

Document: NUREG/CR-4597, Vol. 2, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Plants

Reviewed by: Ken E. Kasza, ANL

Item System SkucturelComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary feedwater High head This report does not

system centrifugal pumps provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG/CR-4652, Concrete Component Aging and Its Significance Relative to Life Extension of Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Concrete structures Prestressed Tendon ducts and Not stated Not stated CORR Loss of material;

in LWR concrete wires corrosion product

containments buildup

2 Concrete structures Prestressed Tendons and wires Not stated Not stated CORR/SCC Crack initiation and

in LWR concrete reactor growth

vessels

3 Concrete structures Biological shield Various parts of Not stated Not stated Not stated Not stated

in LWR walls and buildings walls and buildings

Document: NUREG/CR-4692, Operating Experience Review of Failures of Power Operated Relief Valves and Block Valves in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Power operated Seat/plug interface Not stated Dresser, Garrett, ERO Wall thinning; loss ol

relief valves Target Rock, Crosby material

2 Various Power operated Packing Not stated Dresser, Garrett, ELE-TEMP Chemical or physical

relief valves Target Rock, Crosby degradation

3 Various Power operated Moving parts Not stated Dresser, Garrett, WEAR Attrition

relief valves Target Rock, Crosby

4 Various Power operated Controls Not stated Dresser, Garrett, Not stated Degradation

relief valves Target Rock, Crosby

5 Various Block valves Packing Not stated Dresser, Garrett, ELE-TEMP Chemical or physical

Target Rock, Crosby degradation

6 Various Block valves Torque and limit Not stated Dresser, Garrett, Not stated Not stated

switches Target Rock, Crosby

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J; Shack, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR primary

pressure boundary

Reactor pressure

vessel

Beltine region Low alloy steels

(SA302B, SA533B

1, SA508 2), Weld

deposited SS clad

(308, 309)

Combustion

Engineering, B&W,

Chicago Bridge and

Iron, Rotterdam

Dockyard Co.

EMBR/IR Loss of fracture

toughness
Table A.1 Gall Report for NPAR Reports Page 31B

Document: NUREG/CR-4597, Vol. 2, Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Comnonent Function Contrib to Failure Reported nroos Rel.proas Renort Recornmendations Paae No. Item

Document- NUREG/CR-4652, Concrete Component Aging and Its Significance Relative to Life Extension of Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The effects were so minor that component Not stated Not discussed in ASME Sec XI 1. Existing facilities that have been 33, 138, 1

replacement was not required. report IWL & RG 1.35 shut down after an extended period 139

of service should be used to obtain

aging-related data for concrete

materials.2. Accelerated aging

techniques should be investigated...

(More) [2]

Degraded tendons. However, the reactor Not stated Not discussed in ASME Sec XI 1. Existing facilities that have been 35, 138, 2

vessel was capable of withstanding the report IWL & RG 1.35 shut down after an extended period 139

operating pressures with the degraded of service should be used to obtain

tendons. aging-related data for concrete

materials.2. Accelerated aging

techniques should be investigated...

(More) [2]

Cracking of walls, which can be repaired Not stated Not discussed in ASME Sec Xl 1. Existing facilities that have been 36-37, 3

with a procedure such as epoxy injection, report IWL & RG 1.35 shut down after an extended period 138, 139

of service should be used to obtain

aging-related data for concrete

materials.2. Accelerated aging

techniques should be investigated...

_(More) [2] 1

Document: NUREG/CR-4692, Operating Experience Review of Failures of Power Operated Relief Valves and Block Valves in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

High pressure steam/water impinging on Frequent Not discussed in ASME Sec XI Improve design to withstand 1, 3, 24, 1

surfaces causes material removal and report IST & PS S&T conditions [4] 27, 67

leads to leakage. Req.

Elevated temperature of packing causes Occasional Not discussed in ASME Sec XI Improve design to withstand 1, 3, 24, 2

degradation and leakage. report IST & PS S&T conditions [4] 27, 67

Req.

Wear of various moving parts causes Occasional Not discussed in ASME Sec Xl Improve design to withstand 1, 3, 24, 3

failure of valves to seat or open as report IST & PS S&T conditions [4] 27, 67

designed. Req.

Degradation of the air or electrical Frequent Not discussed in ASME Sec XI Improve design to withstand 1, 3, 24, 4

actuation controls prevents valve report IST & PS S&T conditions [4] 27, 67

operation. Req.

Elevated temperature of packing causes Occasional Not discussed in ASME Sec Xl Improve design to withstand 1, 3,24, 5

degradation and leakage. report IST & PS S&T conditions [4] 27, 67

Req.

Causes valve to fail to close on demand. Not stated Not discussed in ASME Sec Xl Improve design to withstand 1,3, 24, 6

report IST & PS S&T conditions [4] 27, 67

Req.

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Loss of toughness could lead to brittle

fracture and failure of vessel especially

under severe loads (pressurized thermal

shock).

Frequent USNRC Reg. Guide

1.99 Rev. 2ASME

Sec. III Sect.

GUSNCR Heavy

Section Steel

Program

(HSST)EPRI (More)

10CFR App. G Further study of embrittlement

mechanisms and mitigation

techniques (flux reduction,

annealing, etc.) [4]

14-21 V1,

26-27 V1

1
Table A.1 Gall Report for NPAR Reports Page 32A

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructurefComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

PWR primary Reactor pressure Beltilne region Low alloy steels Combustion FAT/ENV Cumulative fatigue

pressure boundary vessel (SA302B, SA533B Engineering, B&W, damage

1, SA508 2), Weld Chicago Bridge and

deposited SS clad Iron, Rotterdam

(308, 309) Dockyard Co.

3 PWR primary Reactor pressure Beltiine region Low alloy steels Combustion FAT/THERM Cumulative fatigue

pressure boundary vessel (SA302B, SA533B Engineering, B&W, damage

1, SA508 2), Weld Chicago Bridge and

deposited SS clad Iron, Rotterdam

4 " (308, 309) Dockyard Co.

4 PWR primary Reactor pressure Outietiinlet nozzles Low alloy steels Combustion FAT/ENV Cumulative fatigue

pressure boundary vessel Engineering, B&W, damage

Chicago Bridge and

Iron, Rotterdam

Dockyard Co.

5 PWR primary Reactor pressure Outlet/inlet nozzles Low alloy steels Combustion FAT/THERM Cumulative fatigue

pressure boundary vessel Engineering, B&W, damage

Chicago Bridge and

Iron, Rotterdam

Dockyard Co.

6 PWR primary Reactor pressure In core Not identified Not stated FAT Cumulative fatigue

pressure boundary vessel instrumentation damage

penetrations

7 PWR primary Reactor pressure In core Not identified Not stated FAT/THERM Cumulative fatigue

pressure boundary vessel instirumentation damage

penetrations

8 PWR primary Reactor pressure Control rod drive SS304 and CF-8 W, CE, B&W FAT Cumulative fatigue

pressure boundary vessel housings (W) damage

9'PWR primary Reactor pressure Control rod drive SS304 and CF 8 W, CE, B&W FAT/THERM Cumulative fatigue

pressure boundary vessel housings (W) damage

10 PWR primary Reactor pressure Control rod drive SS304 and CF 8 W, CE, B&W EMBR/TE Loss of fracture

pressure boundary vessel housings (W) toughness

11 PWR primary Reactor pressure Closure studs Not identified Not stated FAT Cumulative fatigue

pressure boundary vessel damage

12 PWR primary Reactor coolant Piping SS304, CF8A, W, CE, B&W FAT Cumulative fatigue

pressure boundary piping CF8M, A516 Gr 70, damage

A106 Gr C, SS308L,

304L clad

13 PWR primary Reactor coolant Piping CF8A, CF8M W EMBR/TE Loss of fracture

pressure boundary piping toughness

14 PWR primary Reactor coolant Piping nozzles Not identified W, CE, B&W FAT Cumulative fatigue

pressure boundary piping damage

15 PWR primary Reactor coolant Fittings CF8A, A516 Gr 70, Not stated FAT Cumulative fatigue

pressure boundary piping SS308L, 309L clad damage

16 PWR primary Reactor coolant Dissimilar metal Low alloy steels W, CE, B&W FAT Cumulative fatigue

pressure boundary piping welds (SA302B, SA533B damage

1, SA50822),

SS304, CF8A,

CF8M, Alloy 600

17 PWR primary Pressurizer Vessel Low alloy steel (e.g., Not stated FAT Cumulative fatigue

pressure boundary A516 Gr 70, A 533B damage

1, A533A 1) with

308, 308L 309 SS or

I I_ Ni Cr Fe cladding

1 e PWR primary

pressure boundary

Pressurizer Vessel Low alloy steel (e.g.,

A516 Gr 70, A 533B

1, A533A 1) with

308, 308L 309 SS or

Ni Cr Fe cladding

Not stated FAT/ THERM Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 32B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported 1roqs Rel.proqs Report Recommendations Paqe No. Item

Crack initiation & propagation could result Moderate ASME Secs III & 10CFR App. G Better monitoring of transients. 21-24 VI 2

in leakage; possibility of brittle fracture Xllnternational Cyclic & ASME Sec III Additional studies required to

failure. Crack Growth Group improve predictions [4]

Crack initiation & propagation could result Moderate ASME Secs III & XI 10CFR App. G Better monitoring of transients. 21-24 V1 3

in leakage; possibility of brittie fracture & ASME Sec III Additional studies required to

failure. improve predictions [4]

Crack initiation & propagation could result Frequent ASME Secs III & ASME Sec III & Better monitoring of transients. 21-24 V1 4

in leakage. XIInternational Cyclic Sec XI IWB Additional studies required to

Crack Growth Group improve predictions [4]

Crack initiation & propagation could result Frequent ASME Secs Ill & Xl ASME Sec III & Better monitoring of transients. 21-24 VI 5

in leakage. Sec XI IWB Additional studies required to

improve predictions [4]

Crack initiation & propagation could result Frequent ASME Secs IIl & XI ASME Sec III & Better monitoring of transients. 21-24 V1 6

in leakage. Sec XI IWB Additional studies required to

improve predictions [4]

Crack initiation & propagation could result Frequent ASME Secs III & X1 ASME Sec IlII & Better monitoring of transients. 21-24 V1 7

in leakage. Sec Xl IWB Additional studies required to iprove

predictions [4]

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & Better monitoring of transients. 21-24 V1 8

in leakage. Sec XI IWB Additional studies required to

improve predictions [4]

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & Better monitoring of transients. 21-24 V1 9

in leakage. Sec XI IWB Additional studies required to

improve predictions [4]

Increases susceptibility to leakage. Moderate EPRI, WOG, ASME Sec XI Judged not important V1. Judged 13, 17 V1, 10

USNRC research IWB potentially important V2 [2] 108,130,

programs 131 V2

Crack initiation & propagation could result Frequent ASME Secs Ill & XI ASME Sec III & Should be replaced for life extension 13, 16, 11

in stud failure and subsequent leakage. _ _ Sec XI IWB [3] 25, 26 V1

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & Need in depth study of past 55, 60-63, 12

in leakage. Sec XI IWB operation to assess fraction of 64 V2

design life used [4]

Increases susceptibility to leakage. Moderate USNRC research ASME Sec Xl Need to monitor actual thermal 60-64 V2 13

Concludes brittle fracture not possible. program IWB embrittlement in plants [4]

Crack initiation & propagation could result Frequent ASME Secs III & Xl ASME Sec III & Identified as highest fatigue usage in 61, 63, 64 14

in leakage. Sec Xl IWB piping. Need in-depth study of past V2

operation to assess fraction of

design life used [4]

Crack initiation & propagation could result Frequent ASME Secs Ill & XI ASME Sec III & Need in-depth study of past 59, 63, 64 15

in leakage. Sec XI IWB operation to assess fraction of V2

design life used [4]

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & Identified as important site for 55, 64 V2 16

in leakage. Sec Xl IWB fatigue in primary piping system of

Westinghouse PWRs [4]

Crack initiation & propagation could result Frequent ASME Secs III & ASME Sec III & Reanalyze fatigue life with better 1924, 30, 17

in leakage. )IMIT Sec Xl IWB models of thermal history associated 3235, 37,

ResearchPressure with transientslmplement transient 40 42 V2

Vessel Research logging programs [4]

Committee

Crack initiation & propagation could result

in leakage.

Frequent ASME Secs III &

XIMIT Research

ASME Sec III &

Sec XI IWB

Reanalyze fatigue life with better

models of thermal history associated

with transients [4]

34,35,

42 V2

40 18
Table A.1 Gall Report for NPAR Reports Page 33A

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Ught Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 PWR primary Pressurizer Vessel Low alloy steel (e.g., Not stated FAT/ ENV Cumulative fatigue

pressure boundary A516 Gr 70, A 533B damage

1, A533A 1) with

308, 308L 309 SS or

Ni Cr Fe cladding

20 PWR primary Pressurizer Spray and surge Carbon or low alloy Not stated FAT/ THERM Cumulative fatigue

pressure boundary nozzles steel forgings, SS damage.

clad

21 PWR primary Pressurizer Spray and surge Carbon or low alloy Not stated FAT/ ENV Cumulative fatigue

pressure boundary nozzles steel forgings, SS damage

clad

22 PWR primary Pressurizer Spray and surge Carbon or low alloy Not stated FAT/ FIV Cumulative fatigue

pressure boundary nozzles steel forgings, SS damage

clad

23 PWR primary Pressurizer Spray and surge Alloy 600 (CE)Not Not stated FAT/ THERM Cumulative fatigue

pressure boundary nozzle thermal identified damage

sleeves Westinghouse and

B&W

24 PWR primary Pressurizer Spray and surge Alloy 600 (CE)Not Not stated FAT/ FIV Cumulative fatigue

pressure boundary nozzle thermal identified damage

sleeves Westinghouse and

B&W

25 PWR primary Pressurizer Spray and surge SS316, CF3M Not stated FAT/ THERM Cumulative fatigue

pressure boundary lines damage

26 PWR primary Pressurizer Spray and surge SS316, CF3M Not stated EMBR/ TE Loss of fracture

pressure boundary lines toughness

27 PWR primary Pressurizer Spray line head SS304, Alloy 600, Not stated FAT/ THERM Cumulative fatigue

pressure boundary Cast SS damage

28 PWR primary Pressurizer Spray line head SS304, Alloy 600, Not stated EMBR/ TE Loss of fracture

pressure boundary Cast SS toughness

29 PWR primary Pressurizer Spray line head SS304, Alloy 600, Not stated ERO Loss of material

pressure boundary Cast SS

30 PWR primary Pressurizer Heater sheaths and SS304, SS316, Alloy Not stated WEAR Attrition

pressure boundary sleeves 600

31 PWR primary Pressurizer Heater sheaths and SS304, SS316, Alloy Not stated CORR/SCC Crack initiation and

pressure boundary sleeves 600 growth

32 PWR primary Pressurizer Heater elements Not identified Not stated CORR Loss of material

pressure boundary

33 PWR primary Pressurizer Manway cover bolts Low alloy steel bolts Not stated CORR/ SCC Crack initiation and

pressure boundary A540 B24, A193 B7. growth

A320 L43

34 PWR primary Pressurizer Supports (keys, Not identified Not stated FAT Cumulative fatigue

__pressure boundary I_______ skirts, lugs) I_______ I_______ I_____ I__ damagea

35 PWR primary

pressure boundary

Pressurizer Supports (keys,

skirts, lugs)

Not identified Not stated FAT/ THERM Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 33B

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aaina on Component Function Contrib to Failure Reportedprocs Rel.proqs Report Recommendations Page No. Item

Crack initiation & propagation could result Frequent Intemational Cyclic ASME Sec III & Need to consider environment for 35,-41 V2 19

in leakage. Crack Growth Group Sec XI IWB both initiation & growth [4]

Crack initiation & propagation could result Frequent ASME Secs III & ASME Sec Ill, Reanalyze fatigue life with better 34,35, 40 20

in leakage. XIMIT Research Sec XI IWB & models of thermal history associated 42 V2

Assoc. NRC with transientslmplement transient

GC logging programs [4]

Horizontal configuration of piping and low Frequent International Cyclic ASME Sec III, Need to consider environment for 35, 41 V2 21

flow rates promote thermal stratification Crack Growth Group Sec XI IWB & both initiation & growth [4]

leading to high thermal loads. Assoc. NRC

GC

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec Ill, None 52, 55, 60 22

in leakage. Sec XI IWB & V2

Assoc. NRC

GC

Failure of sleeves could permit flow to Frequent ASME Secs III & ASME Sec Ill, Reanalyze fatigue life with better 34,35, 40 23

directiy impinge on nozzles and lead to XIMIT Research Sec XI IWB & models of thermal history associated 42 V2

higher fatigue loadings on nozzles. No Assoc. NRC with transients [4]

loose part problem (pg V2). Potential to GC

break loose (pg 57 V2).

Failure of sleeves could permit flow to Frequent Not discussed in ASME Sec III, None 52, 55, 60 24

directiy impinge on nozzles and lead to report Sec XI IWB & V2

higher fatigue loadings on nozzles. No Assoc. NRC

loose part problem (pg V2). Potential to GC

break loose (pg 57 V2).

Horizontal configuration of piping and low Frequent ASME Secs III & XI ASME Sec III, Analyze horizontal portions to 34,35, 40 25

flow rates promote thermal stratification Sec XI IWB & determine whether leak before break 42, 4960

leading to high thermal loads. Crack Assoc. NRC is expected. Include base metal in V2

initiation & propagation could result in GC inspections. Modify plant operating

leakage. Leak before break more difficult procedures to mimimize

to demonstrate for these relatively small stratification. Develop acoustic

diame emission monitoring for cracking. [4]

Horizontal configuration of piping and low Frequent Not discussed in ASME Sec Xl None 57 V2 26

flow rates promote thermal stratification report IWB

leading to high thermal loads. Leak

before break more difficult to demonstrate

for these relatively small diameter lines.

Change in spray pattern reduces Frequent ASME Secs Ill & ASME Sec III & Reanalyze fatigue life with better 34,35, 40 27

effectiveness in controlling pressure XIMIT Research Sec XI IWB models of thermal history associated 42 V2

surges and makes plant pressure control with transients [4]

more difficult. I

Not described. Frequent USNRC, EPRI, and ASME Sec XI High temperature may make more 37, 38, 28

WOG research IWB susceptible than most [4] 41, 42 V2

programs

Change in spray pattem could result in Infrequent Not discussed in ASME Sec XI High probability spray head will have 37, 41,42 29

higher vessel stresses, report IWB to be replaced [4] V2

Crack initiation & propagation could result Infrequent Not discussed in ASME Sec XI None 30, 32, 30

in unisolatable leakage. report IWB 33, 37,

38,40,42

V2

Crack initiation & propagation could result Infrequent Not discussed in ASME Sec Xl None 33, 36, 31

in unisolatable leakage. report IWB 38, 40 42

V2

Heaters have rated lifetimes of 5,000 Frequent Not discussed in ASME Sec XI None 37, 42 V2 32

cycles. Burnout is expected and report IWB

replacement part of normal maintenance.

Bolt failure would lead to leakage of Frequent Not discussed in ASME Sec Xl Plants need monitoring procedures 30, 36, 33

primary cooolant. Could lead to boric acid report IWB to detect boric acid leakage [4] 37, 38,40

corrosion of low alloy steel vessel. 42 V2

Cracking could lead to loss of support and Frequent ASME Secs IIl & Xl ASME Sec III & None 42 V2 34

overstress of piping. Sec XI IWB

Cracking could lead to loss of support and

overstress of piping.

Frequent ASME Sacs III & XI ASME Sec XI

IWB

None 42 V2 35
Table A.1 Gall Report for NPAR Reports Page 34A

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System Structur.elComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

36 PWR primary Chemical and Charging nozzle Low alloy steel W, CE, B&W FAT/ THERM Cumulative fatigue

pressure boundary volume control forging (CE, B&W), damage

system SS (W)

37 PWR primary Chemical and Charging nozzle Low alloy steel W, CE, B&W FAT/ FIV Cumulative fatigue

pressure boundary volume control forging (CE, B&W), damage

system SS (W)

38 PWR primary Chemical and Charging nozzle Alloy 600 (CE) W, CE, B&W FAT/ THERM Cumulative fatigue

pressure boundary volume control thermal sleeve damage

system

39 PWR primary Chemical and Charging nozzle Alloy 600 (CE) W, CE, B&W FAT/ FIV Cumulative fatigue

pressure boundary volume control thermal sleeve damage

system

40 PWR primary Safety Injection Safety injection Low alloy steel W, CE, B&W FAT/THERM Cumulative fatigue

pressure boundary System nozzle forging (CE, B&W), damage

SS (W)

41 PWR primary Safety Injection Safety injection Low alloy steel W, CE, B&W FAT/FIV Cumulative fatigue

pressure boundary System nozzle forging (CE, B&W), damage SS (W)

42 PWR primary Safety Injection Safety injection Alloy 600 (CE) W, CE, B&W FAT/THERM Cumulative fatigue

pressure boundary System nozzle thermal damage

sleeve

43 PWR primary Safety Injection Safety injection Alloy 600 (CE) W, CE, B&W FAT/FIV Cumulative fatigue

pressure boundary System nozzle thermal damage

sleeve

44 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/SCC Crack initiation and

pressure boundary generators growth

45 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/IN Crack initiation and

pressure boundary, generators growth

46 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/PIT Local loss of materia

pressure boundary generators

47 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/UA Loss of material

pressure boundary generators

48 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/OX Corrosion product

pressure boundary generators buildup

TuigAly60,60W4EWARFE trto

PWR primary

pressure boundary

Recirculating steam

generators

Tubing Alloy 600, 690 W, CE WEAR/FRET Attition
Table A.1 Gall Report for NPAR Reports Page 34B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Crack initiation & propagation could result Frequent ASME Secs III & Xl ASME Sec III & Horizontal portions of charging line 64 71 V2 36

in leakage. Sec XI IWB subject to stratified flows should be

checked to verify leak before break

behavior. Base metal should be

inspected. Acoustic emission

monitoring should be considered.

On line monitoring of transients. [4]

Crack initiation & propagation could result Frequent ASME Sacs III & XI ASME Sec III & None 65, 67,71 37

in leakage. Sec XI IWB V2

Failure of sleeves could permit flow to Frequent ASME Secs III & Xl ASME Sec III & None 64 71 V2 38

directiy impinge on nozzles and lead to Sec XI IWB

higher fatigue loadings on nozzles.

Potential to break loose.

Failure of sleeves could permit flow to Frequent ASME Secs III & XI ASME Sec Ill & None 65, 67,71 39

drectly impinge on nozzles and lead to Sec XI IWB V2

higher fatigue loadings on nozzles.

Potential to break loose.

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & Horizontal portions of injection line 67-71 V2 40

in leakage. Local stratified flow may Sec Xl IWB subject to stratified flows should be

develop in horizontal portion of line checked to verify leak before break

because there is normally no flow leading behavior. Base metal should be

to high thermal loads, inspected. Acoustic emission

monitoring should be considered.

_On-line monitoring of transients. [4]

Crack initiation & propagation could result Frequent ASME Secs III & XI ASME Sec III & None 68, 71 V2 41

in leakage. Sec XI IWB

Failure of sleeves could permit flow to Frequent ASME Secs III & XI ASME Sec IIl & None 67-71 V2 42

directly impinge on nozzles and lead to Sec XI IWB

higher fatigue loadings on nozzles.

Potential to break loose.

Failure of sleeves could permit flow to Frequent ASME Secs III & XI ASME Sec III & None 68, 71 V2 43

dlirectly impinge on nozzles and lead to Sec Xl IWB

higher fatigue loadings on nozzles.

Potential to break loose.

Crack initiation & propagation in tubesheet Frequent Vendor, EPRI, and ASME Sec XI Highest priority given to preventing 69, 72, 44

crevice region and tube support annuli. European work on IWB & PS TS faulted water chemistries. Follow 73, 76 V1i

mitigation Req. EPRI Secondary Water Chemistry 145,146,

techniques; repair Guidelines. Use boric acid and 149,151

techniques; morpholine. Use Alloy 690. [4] 160,163-

replacement 165 V2 I

Crack initiation & propagation in tubesheet Frequent Vendor, EPRI, and ASME Sec XI Highest priority given to preventing 69,72, 45

crevice region and tube support annuli. European work on IWB & PS TS faulted water chemistries. Follow 73,76 V1;

mitigation Req. EPRI Secondary Water Chemistry 145,146,

techniques; repair Guidelines. Use boric acid and 149,151

techniques; morpholine. Use Alloy 690. [4] 160,163-

replacement 165 V2

Local attack and tube thinning may Frequent Vendor, EPRI, and ASME Sec XI Highest priority given to preventing 69, 71, 46

eventually lead to leakage. European work on IWB & PS TS faulted water chemistries. Eliminate 75, 76 V1;

mitigation Req. copper alloys from feedwater 145,146,

techniques system. [4] 149,151,

163,164

V2

Wastage. Thinning of wall may eventually Frequent Vendor, EPRI, and ASME Sec XI None 69, 70, 47

lead to rupture of tube. European work on IWB & PS TS 75, 76 V1;

mitigation Req. 145,146,

techniques 155, 164

V2

Denting. Corrosion product buildup can Frequent Vendor and EPRI ASME Sec Xl Control secondary water chemistry. 69, 70, 48

cause excessive deformation of tubing mitigation IWB & PS TS Use ferritic SS support plates and 75, 76 V1;

and lead to cracking or blockage, techniques Req. designs which minimize crevices. 145,146,

No longer an important cause of 149,151

tube failure. [4] 153,162,

163,164

V2

Thinning of wall may eventually lead to

rupture of tube.

Moderate Vendor mitigation

techniques

ASME Sec Xl

IWB & PS TS

Req.

Redesign antivibration bars to

provide larger contact area. [4]

69, 73,76

V1; 145,

147, 149

V2

49
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Ught Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructurelComD Subcomponent Materials Manufacturer ARD mechanism

Page 35A

ARD effects

50 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE FAT/FIV Crack initiation and

pressure boundary generators growth

51 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE FAT/THERM Crack initiation and

pressure boundary generators growth

52 PWR primary Recirculating steam Tubing Alloy 600, 690 W, CE CORR/PWSCC Crack initiation and

pressure boundary generators growth

53 PWR primary Once-through steam Tubing Alloy 600 B&W ERO/CORR Wall thinning

pressure boundary generators

64 PWR primary Once-through steam Tubing Alloy 600 B&W FAT/ENV Cumulative fatigue

pressure boundary generators damage

55 PWR reactor Feedwater piping Piping Carbon steel (A106- W, CE, B&W EROICORR Wall thinning; loss o!

feedwater system B, A-155, KC-65) material

56 PWR reactor Feedwater piping Piping Carbon steel (A106- W, CE, B&W ERO/CAV Wall thinning; loss o'

feedwater system B, A-155, KC-65) material

57 PWR reactor Feedwater piping Piping Carbon steel (A106- W, CE, B&W FAT/THERM Cumulative fatigue

feedwater system B, A- 155, KC-65) damage

58 PWR reactor Feedwater piping Piping Carbon steel (A106- W, CE, B&W FAT Cumulative fatigue

feedwater system B, A-155, KC-65) damage

59 PWR reactor Feedwater piping Piping Carbon steel (A106- W, CE, B&W WAT HAM Cumulative fatigue

feedwater system B, A-155, KC-65) damage

60 PWR reactor Feedwater piping Elbows Carbon steel (A234- W, CE, B&W ERO/CORR Wall thinning; loss ol

feedwater system WPB) material

61 PWR reactor Feedwater piping Elbows Carbon steel (A234- W, CE, B&W ERO/CAV Wall thinning; loss ol

feedwater system WPB) material

62 PWR reactor Feedwater piping Elbows Carbon steel (A234- W, CE, B&W FAT/THERM Cumulative fatigue

feedwater system WPB) damage

63 PWR reactor Feedwater piping Elbows Carbon steel (A234- W, CE, B&W FAT Cumulative fatigue

feedwater system WPB) damage

64 PWR reactor Feedwater piping Elbows Carbon steel (A234- W, CE, B&W WAT HAM Cumulative fatigue

feedwater system WPB) damage

65 PWR reactor Feedwater piping Nozzles Not identified W, CE, B&W FAT/THERM Cumulative fatigue

feedwater system damage

66 PWR reactor

feedwater system

Feedwater piping Thermal sleeves Not identified W, CE, B&W FAT/THERM Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 35B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Ught Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aaina on Comaonent Function Contrib to Failure Reaorted aroas Rel.oroas Renort Recommendations Pace No. Item

Leakage or tube rupture. Moderate Vendor mitigation ASME Sec Xl Reduce local fluid forces with flow 145,147, 50

techniques IWB & PS TS resistance plates. [4] 150 V2

Req.

Can produce cracking or leakage Moderate Not discussed in ASME Sec Xl None 145,150 51

especially in tubes with denting. report IWB & PS TS V2

_Req.

Cracking and leakage in high stress areas Frequent Vendor, EPRI, and ASME Sec Xl Use Alloy 690. Shot and 69, 72, 52

such as U bends, rolled tubesheet joints, European work on IWB & PS TS rotopeening to induce favorable 75, 76 V1;

and dented regions. mitigation Req. residual stresses. Consider nickel 147,149,

techniques; repair plating as repair technique. [4] 154,160,

techniques 162,164,

165 V2

Fairly uniform wall thinning which could Frequent Not discussed in ASME Sec Xl None 73, 76, 77 53

lead to leakage or rupture. report IWB & PS TS V1; 148,

Req. 150,164

V2

In upper portion of generator in free lane Moderate Not discussed in ASME Sec Xl Need to control chemistry and 73, 76,77 54

water droplets impinge and dry out. report IWB & PS TS modify to preclude dryout [4] V1; 148,

Chemical buildup combined with thermal Req. 150,164

cycling or vibration can cause cracking. V2

Leads to localized wall thinning especially Frequent EPRI, Brtish, and ASME Sec Xl Water chemistry changes to mitigate 77, 82-86, 55

near flow discontinuities or anywhere French programs IWC erosion corrosion can have other 89-93, 97-

where high turbulence occurs (fittings, deleterious effects. Inside surfaces 103 V2

tees, elbows). If thinning is severe, even need to be kept as smooth as

modest pressure pulse can produce possible. Consider use of SS

rupture. _coatings. [4] 1

Feedwater system oeprates near Infrequent Not discussed in ASME Sec Xl None 88, 89 V2 56

saturation. Cavitiation can produce sever report IWC

local damage in regions with velocity

changes.

Most common in horizontal portions of Frequent Vendor programs ASME Sec Xl Acoustic monitoring should be 77-80, 85- 57

system where thermal stratifications can IWC & PS S&T considered [2] 88, 91,

occur. Crack initiation and propagation. Req. 93, 95,

99-101 V__

Crack initiation and propagation. Infrequent Not discussed in ASME Sec Xl None 82, 88, 58

report IWC & PS S&T 100 V2

Reg].I

Crack initiation and propagation. Can Moderate Vendor programs ASME Sec Xl None 81, 82, 59

produce final failure in structures IWC 94, 95,

weakened by other mechanisms. 100 V2

Leads to localized wall thinning especially Frequent EPRI, British, and ASME Sec XI Water chemistry changes to mitigate 77, 82-86, 60

near flow discontinuities or anywhere French programs IWC erosion corrosion can have other 89-93, 97-

where high turbulence occurs (fittings, deleterious effects. Inside surfaces 103 V2

tees, elbows). If thinning is severe, even need to be kept as smooth as

modest pressure pulse can produce possible. Consider use of SS

rupture. coatings. [4]

Feedwater system oeprates near Infrequent Not discussed in ASME Sec Xl None 82, 88, 89 61

saturation. Cavitiation can produce sever report IWC V2

local damage in regions with velcotiy

changes.

Most common in horizontal portions of Frequent Vendor programs ASME Sec Xl Acoustic monitoring should be 77-80, 85- 62

system where thermal stratifications can IWC & PS S&T considered [2] 88,91,

occur. Crack initiation and propagation. Req. 93, 95,

99-101 V2

Crack initiation and propagation. Infrequent Not discussed in ASME Sec Xl None 88, 100 63

report IWC & PS S&T V2

Reg.

Crack initiation and propagation. Can Moderate Vendor programs ASME Sec Xl None 81, 82, 64

produce final failure in structures IWC 94, 95,

weakened by other mechanisms. 100 V2

Most common in horizontal portions of Frequent Vendor programs ASME Sec XI None 77-80, 85- 65

system where thermal stratifications can IWC & PS S&T 88,91,

occur. Crack initiation and propagation. Req. 93, 95,

1_ 1_99-101 V, _

Most common in horizontal portions of

system where thermal stratifications can

occur. Crack initiation and propagation.

Frequent Vendor programs ASME Sec Xl

IWC & PS S&T

Req.

Acoustic monitoring should be

considered [2]

77-80, 85-

88, 91,

93, 95,

99-101 V91

6E
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL Item SytmStructurelComD SuboomDonent Materials Manufacturer ARD

Page 36A

mechanism ARD effects

67 PWR reactor Feedwater piping Thermal sleeves Not identified W, CE, B&W WAT HAM Cumulative fatigue

feedwater system damage

68 PWR reactor Feedwater piping Thermal sleeves Not identified W, CE, B&W FAT/FIV Cumulative fatigue

feedwater system damage

6S PWR Primary Reactor coolant Body CF-8, CF-8M, CF- W, Byron Jackson, EMBR/TE Loss of fracture

coolant system pumps 8A, Carbon steel Bingham, CE, Klein toughness

with SS clad (1

plant)

70 PWR Primary Reactor coolant Body CF-8, CF-8M, CF- W, Byron Jackson, FAT Cumulative fatigue

coolant system pumps 8A, Carbon steel Bingham, CE, Klein damage

with SS clad (1

plant)

71 PWR Primary Reactor coolant Body CF-8, CF-8M, CF- W, Byron Jackson, FAT/THERM Cumulative fatigue

coolant system pumps 8A, Carbon steel Bingham, CE, Klein damage

with SS clad (1 plant)

72 PWR Primary Reactor coolant Body CF-8, CF-8M, CF- W, Byron Jackson, CORR/SCC Crack initiation and

coolant system pumps 8A, Carbon steel Bingham, CE, Klein growth

with SS clad (1

I _plant)

73 PWR Primary Reactor coolant Shaft SS 304, 316 W, Byron Jackson, FAT Cumulative fatigue

coolant system pumps Bingham, CE, Klein damage

74 PWR Primary Reactor coolant Shaft SS 304, 316 W, Byron Jackson, FAT/THERM Cumulative fatigue

coolant system pumps Bingham, CE, Klein damage

75 PWR Primary Reactor coolant Closure studs Low alloy steel W, Byron Jackson, CORR Loss of material

coolant system pumps (A540-B23 or A193- Bingham, CE, Klein

B7)

76 PWR CRDMs and CRDMs Pressure housing SS 304 and CF-8 W, CE, B&W EMBR/TE Loss of fracture

reactor internals (W) Not identified toughness CE and B&W

77 PWR CRDMs and CR0Ms Pressure housing SS 304 and CF-8 W, CE, B&W FAT Cumulative fatigue

reactor internals (W) Not identified damage CE and B&W

78 PWR CRDMs and CRDMs Pressure housing SS 304 and CF-8 W, CE, B&W CORR/SCC Crack initiation and

reactor internals (W) Not identified growth

CE and B&W

79 PWR CRDMs and CRDMs Latch assembly SS 304 with Stellite W, CE, B&W WEAR Loss of material

reactor internals 6 and hard chrome

plate bearing and

wear surfaces (W)

Not identified CE

and B&W

80 PWR CRDMs and CRDMs Latch assembly SS 304 with Stellite W, CE, B&W WEAR/FRET Loss of material

reactor internals 6 and hard chrome

plate bearing and

wear surfaces (W)

Not identified CE

and B&W

81 PWR CRDMs and CRDMs Drive rod SS 410 (W) Not W, CE, B&W FAT Cumulative fatigue

reactor internals identified CE and damage

B&W

82 PWR CRDMs and CRDMs Drive rod SS 410 (W) Not W, CE, B&W WEAR Loss of material

reactor internals identified CE and

B&W

83 PWR CRIDMs and Reactor internals Instrument guide SS 304 (W) Not W, CE, B&W FAT/FIV Cumulative fatigue

reactor internals tubes (Thimble identified CE and damage

tubes) B&W

84 PWR CRDMs and Reactor internals Instrument guide SS 304 (W) Not W, CE, B&W WEAR/FRET Loss of material

reactor internals tubes (Thimble identified CE and

I tubes) B&W

85 PWR CRDMs and

reactor internals

Reactor internals Thermal shield SS304 W, CE, B&W FAT/FIV Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 36B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aoina on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Crack initiation and propagation. Can Moderate Vendor programs ASME Sec Xl None 81, 82, 67

produce final failure in structures IWC 94, 95,

weakened by other mechanisms. 100 V2

Crack initiation and propagation. Infrequent Not discussed in ASME Sec Xl None 82, 91, 68

report IWC & PS S&T 101 V2

_Req.

Loss of toughness would increase Moderate USNRC Research ASME Sec Xl Need model to predict embrittlement 10,11, 69

possibility of leakage, unstable ductile IWB & PS TS based on composition, 13-16 V2

tearing. Req. microstructure. Need information on

throughwall distribution of ferrite. [4]

Crack initiation and growth. Infrequent Not discussed in ASME Sec Xl None 11,12, 70

report IWB & PS TS 15, 16 V2

Req.

Crack initiation and growth. Infrequent Not discussed in ASME Sec Xl None 11,12, 71

report IWB & PS TS 15, 16 V2

Req.

Crack initiation and growth. Most likely to Infrequent Not discussed in ASME Sec Xl None 12 V2 72

affect low ferrite bodies and welds, report IWB & PS TS

Req.

Crack initiation and growth. Frequent Not discussed in ASME Sec Xl Need field demonstration of 11-16 V2 73

report IWB & PS TS improved NDE [4-EPRI]

Req.

Crack initiation and growth. Frequent Not discussed in ASME Sec XI Need field demonstration of 11-16 V2 74

report IWB & PS TS improved NDE [4-EPRI]

_ _ _Req.

Gasket leakage could lead to boric acid Moderate USNRC IN 80-27 ASME Sec Xl Improve gasket technology and 10,12, 75

attack of ferritic closure studs. IWB & PS TS inspection. Better inspection for 14-16 V2

Req. studs. [2]

Loss of toughness would increase Moderate EPRI, WOG, and ASME Sec Xl Evaluation of embrittlement is 121,130, 76

possibility of leakage. Affects only cast USNRC research IWB & PS TS needed [4] 131 V2

housings. programs Req.

Crack initiation and growth leading to Infrequent Not discussed in ASME Sec Xl Need to develop techniques to 133,137 77

leakage. Estimated usage factors are report IWB & PS TS assure integrity of inaccessible V2

very low. Req. welds [4]

Leakage in seal welds. Moderate Not discussed in ASME Sec Xl Need to develop techniques to 122,132 78

report IWB & PS TS assure integrity of inaccessible V2

Req. welds [4]

Binding and sticking of control rod drive. Moderate Not discussed in ASME Sec Xl Need life test to determine practical 129, 130, 79

report IWB & PS TS lifetimes [2] 137 V2

Req.

Binding and sticking of control rod drive. Moderate Not discussed in ASME Sec Xl Need life test to determine practical 129,130, 80

report IWB & PS TS lifetimes [2] 137 V2

Req.

Crack initiation and growth leading to Infrequent Not discussed in ASME Sec Xl None 137 V2 81

CRA uncoupling, report IWB & PS TS

Reg.

Loss of material leading to CRA Infrequent Not discussed in ASME Sec XI None 137 V2 82

uncoupling, report IWB & PS TS

Req.

Crack initiation and growth leading to Frequent USNRC IN 87 44, ASME Sec Xl Establish vibration monitoring 130,136- 83

leakage. Loose parts. USNRC Bulletin 88- IWB programs using neutron noise 138 V2

09 detectors [4]

Wall Thinning. Leakage, loose parts. Frequent USNRC IN 87 44, ASME Sec Xl None 130,136- 84

USNRC Bulletin 88- IWB 138 V2

09 1 1 1

Crack initiation and growth. Such

problems have lead to removal of thermal

shields in many CE plants.

Frequent Not discussed in

report

ASME Sec Xl

IWB

None 125,138

V2

85
Table A.1 Gall Report for NPAR Reports Page 37A

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

86 PWR CRDMs and Reactor internals Thermal shield bolts SS316, A-286, X- W, CE, B&W CORR/SCC Crack initiation and

reactor internals 750 growth

87 PWR CRDMs and Reactor internals Thermal shield bolts SS316, A-286, X- W, CE, B&W RELAX Stress relaxation

reactor internals 750

88 PWR CRDMs and Reactor internals Thermal shield bolts SS 316, A-286, X- W, CE, B&W FAT Cumulative fatigue

reactor internals 750 damage

89 PWR CRDMs and Reactor internals Core barrel SS 304 W, CE, B&W FAT/FIV Cumulative fatigue

reactor internals damage

90 PWR CRDMs and Reactor internals Core barrel SS 304 W, CE, B&W EMBR/IR Loss of fracture

reactor internals toughness

91 PWR CRDMs and Reactor internals Core barrel bolts SS 316, A 286, X W, CE, B&W CORR/SCC Crack initiation and

reactor internals 750 growth

92 PWR CRDMs and Reactor internals Core barrel bolts SS 316, A-286, X- W, CE, B&W RELAX Stress relaxation

reactor internals 750

93 PWR CRDMs and Reactor internals Core barrel bolts SS 316, A-286, X- W, CE, B&W FAT Cumulative fatigue

reactor internals. 750 damage

94 PWR CRDMs and Reactor internals Upper and lower SS 304, CF-8 AJloy W, CE, B&W FAT/FIV Cumulative fatigue

reactor internals core support X-750 and A-286 damage

structures

95 PWR CRDMs and Reactor internals Upper and lower SS 304, CF-8 Alloy W, CE, B&W CORR/SCC Crack initiation and

reactor internals core support X-750 and A-286 growth

structures

96 PWR CRDMs and Reactor internals Upper and lower SS 304, CF-8 Alloy W, CE, B&W EMBRITE Loss of fracture

reactor internals core support X-750 and A-286 toughness

structures

97 BWR primary Reactor pressure Beltiine region Low alloy steels Chicago Bridge and EMBR/IR Loss of fracture

pressure boundary vessel (SA302B, SA533B- Iron, Combustion toughness

1, SA508-2), Weld Engineering, B&W,

deposited SS clad Babcock/Hitachi,

(308, 309) Rotterdam Dockyard

Co.

98 BWR primary Reactor pressure Beltline region Low alloy steels Chicago Bridge and FAT/ENV Cumulative fatigue

pressure boundary vessel (SA302B, SA533B- Iron, Combustion damage

1, SA508-2), Weld Engineering, B&W,

deposited SS clad Babcock/Hitachi,

(308, 309) Rotterdam Dockyard

Co.

99 BWR primary Reactor pressure Beltline region Low alloy steels Chicago Bridge and FAT/THERM Cumulative fatigue

pressure boundary vessel (SA302B, SA533B- Iron, Combustion damage

1, SA508-2), Weld Engineering, B&W,

deposited SS clad Babcock/Hitachi,

(308, 309) Rotterdam Dockyard

Co.

100 BWR primary Reactor pressure Outlet/inlet nozzles Low alloy steels Chicago Bridge and FAT/ENV Cumulative fatigue

pressure boundary vessel A508-2, A105, Iron, Combustion damage

A508-3 Engineering, B&W,

Babcock/Hitachi,

Rotterdam Dockyard

Co.

101 BWR primary Reactor pressure Outletfinlet nozzles Low alloy steels Chicago Bridge and FAT/THERM Cumulative fatigue

pressure boundary vessel A508-2, A105, Iron, Combustion damage

A508-3 Engineering, B&W,

Babcock/Hitachi,

Rotterdam Dockyard

I_ I_ IGCO.

102 BWR primary Reactor pressure Closure studs Low alloy steels Not stated FAT Cumulative fatigue

pressure boundary vessel (A193-B7, SA540- damage

'I __ _ I __ I__ B22 or B23) I I I

103 BWR primary

pressure boundary

Reactor pressure

vessel

Bimetallic/trimetallic

weld nozzle to

safeend

Safeend 304 SS

Weld metal not

identified

Chicago Bridge and

Iron, Combustion

Engineering, B&W,

Babcock/Hitachi,

Rotterdam Dockyard

Co.

FAT Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 37B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.Droas Report Recomn iendations Paae No. Item

Bolt failure. Loose parts. Frequent EPRI UT program ASME Sec XI Need to study alternate 127-129. 86

for boltsVendor IWB materials/heat treatments to get 138 V2

programs longer lifetimes. [4]

Loss of bolt preload. Frequent Not discussed in ASME Sec Xl None 132,138 87

report IWB V2

Bolt failure. Loose parts. Frequent EPRI UT program ASME Sec Xl Develop high-cycle fatigue curves foi 123-125, 88

for boltsVendor IWB high-strength materials [3] 138 V2

programs I

Crack initiation and growth. Frequent Not discussed in ASME Sec Xl None 125,138 89

report IWB V2

Increased susceptibility to low ductility Frequent Not discussed in ASME Sec XI None 131,132, 90

failure. report IWB 138 V2

Bolt failure. Loose parts. Frequent EPRI UT program ASME Sec XI Need to study alternate 127-129. 91

for boltsVendor IWB materials/heat treatments to get 138 V2

programs longer lifetimes. [4]

Loss of bolt preload. Frequent Not discussed in ASME Sec X1 None 132,138 92

report IWB V2

Bolt failure. Loose parts. Frequent EPRI UT program ASME Sec XI Develop high cycle fatigue curves for 123 125, 93

for boltsVendor IWB high strength materials [3] 138 V2

programs

Crack initiation and growth. Frequent Not discussed in ASME Sec XI Develop high cycle fatigue curves for 123 125, 94

report IWB high strength materials [3] 138 V2

Guide pin failure. Loose parts. Frequent EPRI UT program ASME Sec XI Need to study alternate 127-129, 95

for boltsVendor IWB materials/heat treatments to get 138 V2

programs longer lifetimes. [4]

Increased susceptibility to low ductility Frequent EPRI, WOG, and ASME Sec Xl Need research program on 130,131, 96

failure. USNRC research IWB combined effect of radiation and 138 V2

programs temperature on embrittlement [3] _

Ductile high energy overload leading to a Frequent USNRC Reg. Guide 10 CFR App. G None 105,107 97

leak. Much less severe problem than in 1.99 Rev. 2 & ASME Sec V1

PWRs. Xl IWB

Crack initiation & propagation could result Moderate ASME Secs III & XI 10 CFR App. G Better monitoring of transients. 105 107 98

in leakage. & ASME Sec Additional studies required to Vl

Xl IWB improve predictions [2]

Crack initiation & propagation could result Moderate ASME Secs III & XI 10 CFR App. G Better monitoring of transients. 105-107 99

in leakage. & ASME Sec Additional studies required to V1

XI IWB improve predictions [2]

Crack initiation & propagation could result Moderate ASME Secs III & XI ASME Sec III & Better monitoring of transients. 105-107 100

in leakage. Sec XI IWB Additional studies required to V1

improve predictions [4]

Crack initiation & propagation could result Moderate ASME Secs III & XI ASME Sec III & Better monitoring of transients. 105-107 101

in leakage. Sec XI IWB Additional studies required to V1

improve predictions [4]

Crack initiation & propagation could result Moderate ASME Secs III & XI ASME Sec III & Should be closely inspected at 40 104,106, 102

in ductile overload failure and leakage. Sec Xl IWB year life [3] 107 V1

Crack initiation & propagation could result

in leakage.

Moderate Not discussed in

report

ASME Sec III & IShould be closely inspected at 40

Sec Xl IWB 1year life [4]

104,105,

107 VI

103
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Light Water Reactor Components Overview

Page 38A

Reviewed by: W. J. Shack, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

104 BWR primary Reactor pressure Bimetallic/bimetallic Safeend 304 SS Rotterdam Dockyard CORR/IGSCC Crack initiation and

pressure boundary vessel weld nozzle to Weld metal not Co. growth

safeend identified

105 BWR primary Reactor pressure Stub tube (attach SS, Alloy 600 Chicago Bridge and CORR/IGSCC Crack initiation and

pressure boundary vessel ments for CRDs) Iron, Combustion growth

Engineering, B&W,

Babcock/Hitachi,

Rotterdam Dockyard

Co.

106 BWR primary Recirculation piping Piping & safeends SS 304, 316, 304L, General Electric CORR/IGSCC Crack initiation and

pressure boundary system 316L, 304NG, growth

316NG

107 BWR primary Recirculation piping Piping & safeends SS 304, 316, 304L, General Electric CORR/SCC Crack initiation and

pressure boundary system 316L, 304NG, growth

316NG

108 BWR primary Recirculation piping Piping & safeends SS 304, 316, 304L, General Electric FAT/ENV Cumulative fatigue

pressure boundary system 316L, 304NG, damage

316NG

109 BWR primary Recircula tion piping Piping & safeends SS 304, 316, 304L, General Electric FAT/ THERM Cumulative fatigue

pressure boundary system 316L, 304NG, damage

316NG

110 BWR primary Recircula tion piping Welds Not identified General Electric EMBR/TE Loss of fracture

pressure boundary system toughness

111 BWR primary Recircula tion piping Fittings Not identified General Electric EMBR/ TE Loss of fracture

pressure boundary system toughness

112 BWR CRDMs and CRDMs Pressure housing, SS 304, Alloy 600 General Electric CORR/ IGSCC Crack initiation and

reactor internals stub tube growth

113 BWR CRDMs and CRDMs Pressure housing, SS 304, Alloy 600 General Electric FAT/ THERM Cumulative fatigue

reactor internals stub tube damage

114 BWR CRDMs and CRDMs Latching mechanism Alloy X 750 General Electric CORR/ IGSCC Crack initiation and

reactor internals growth

115 BWR CRDMs and CRDMs Latching mechanism Alloy X 750 General Electric FAT/ THERM Cumulative fatigue

reactor internals damage

116 BWR CRDMs and CRDMs Latching mechanism Alloy X 750 General Electric WEAR Loss of material

reactor internals

117 BWR CRDMs and CRDMs Piston seal C spring Alloy X 750 General Electric CORR/ IGSCC Crack initiation and

reactor internals growth

118 BWR CRDMs and CRDMs Diaphragms in air BUNA N rubber and General Electric EMBR/ TE Loss ot flexibility

reactor internals operated solenoid nylon

valves

119 BWR CRDMs and CRDMs Piston seals Graphitar 14 General Electric EMBR/ TE Loss of flexibility

reactor internals

120 BWR CRDMs and CRDMs Piston seals Graphitar 14 General Electric WEAR Loss of material

reactor internals

121 BWR CRDMs and Reactor internals Attachment welds to Alloy 182, 82 General Electric CORR/ IGSCC Crack initiation and

reactor internals vessel growth

122 BWR CRDMs and Reactor internals Attachment welds to Alloy 182, 82 General Electric FAT/ THERM Cumulative fatigue

reactor internals vessel damage

123 BWR CRDMs and Reactor internals Core shroud SS 304, 304L General Electric CORR/ IGSCC Crack initiation and

reactor internals growth

124 BWR CROMs and I Reactor internals Core plate SS 304L General Electric CORR/ IGSCC

reactor internals

Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 38B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Crack initiation & propagation could result Moderate Not discussed in ASME Sec XI Should be closely inspected at 40 107 VI 104

in leakage. report IWB year life [4]

SS tubes on early reactors (pre 1968) Frequent Not discussed in ASME Sec XI None 104 Vi 105

sensitized and susceptible to crack report IWB

initiation & propagation which could result

in leakage. Alloy 600 used 1968-1974.

Component eliminated in later reactors.

Crack initiation & propagation could result Frequent Industry & USNRC ASME Sec XI Long term field experience needed to 108, 110- 106

in leakage. programs IWB assess effectiveness of 112 Vi;

countermeasures [4] 275-295

V2

Crack initiation & propagation could result Infrequent Not discussed in ASME Sec Xl None 280, 281, 107

in leakage. report IWB 283 V2

Crack initiation & propagation could result Moderate Not discussed in ASME Sec III & None 110 112 108

in leakage. report Sec XI IWB Vi

Crack initiation & propagation could result Moderate Not discussed in ASME Sec III & None 108,110 109

in leakage, report Sec XI IWB 112 Vi

Increased susceptibility to low ductility Infrequent Not discussed in ASME Sec Xl Need additional work to determine 108,110, 110

failure, report IWB susceptibility [4] 112 V1

281 V2

Increased susceptibility to low ductility Infrequent Not discussed in ASME Sec Xl Need additionaJ work to better 108,110 111

failure. report IWB evaluate embrittiement under BWR 112 Vl

conditions and ferrite levels in cast 281 V2

compoments [4]

Crack initiation & propagation could result Moderate Vendor program ASME Sec Xl Hydrogen water chemistry effective 254, 256, 112

in leakage. IWB & PS TS mitigating action. [4] 257, 266,

Req. 269,270

V2

Crack initiation & propagation could result Moderate ASME Xl ASME Sec Xl None 251,252, 113

in leakage. IWB & PS TS 263, 264,

Req. 266, 270

V2

Drive may not lock properly. Separation of Moderate Not discussed in ASME Sec XI None 254, 264, 114

CRA and CRDM. report IWB & PS TS 270 V2

Reg.

Drive may not lock properly. Separation of Infrequent Not discussed in ASME Sec XI None 263,264, 115

ORA and CRDM. report IWB & PS TS 270 V2

Req.

Drive may not lock properly. Moderate Not discussed in ASME Sec XI Internals should be inspected 253,265, 116

report IWB & PS TS periodically for excessive wear 269,270

Req. damage [2] V2

Could cause control rod to stick. Moderate USNRC IE IN 86-88 ASME Sec XI Internals should be inspected 254, 259, 117

IWB & PS TS periodically for excessive wear 270 V2

Re_. damage [2]

May become brittle over time and break Frequent USNRC IE IN 86- ASME Sec XI Internals should be inspected 255, 269, 118

ap. Broken pieces may block vent ports 109 IWB & PS TS periodically for excessive wear 270 V2

n the scram pilot valves. Req. damage [2]

Could cause control rod to stick. Moderate USNRC IE IN 86-88 ASME Sec Xl Internals should be inspected 252,270 119

IWB & PS TS periodically for excessive wear V2

Req. damage [2]

Could cause control rod to stick. Moderate USNRC IE IN 86-88 ASME Sec Xl Internals should be inspected 269,270 120

IWB & PS TS periodically for excessive wear V2

Req. damage [2]

Crack could progress into vessel. Frequent ASME X1 Table IWB ASME Sec XI Need to develop remote inspection 260,263, 121

2500 1 IWB tools for these locations [3] 269,271

V2

Crack could progress into vessel. Moderate ASME Xl Table IWB ASME Sec XI Need to develop remote inspection 264, 269, 122

12500 1 IWB tools for these locations [2] 271 V2

Cracking could lead to loss of core Frequent ASME Xl Table IWB ASME Sec XI None 253,255, 123

geometry. 2500 1 IWB 270,271

1 1_ 1 V2

Cracking could lead to loss of core

geometry.

Frequent USNRC IE IN 84

89ASME Xl Table

IWB 2500 1

ASME Sec Xl

IWB

None 253, 255,

270, 271

V2

124
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item SytmStructureJComD Subcomoonent Materials Manufacturer ARD

Page 39A

miechanism ARD effects

125 BWR CRDMs and Reactor internals Jet pumps SS 304, 304L, 316L, General Electric CORR/ IGSCC Crack initiation and

reactor internals Alloy 600, SS CF 8, growth CF3

126 BWR CRDMs and Reactor internals Jet pumps SS 304, 304L, 316L, General Electric FAT/ Cumulative fatigue

reactor internals Alloy 600, SS CF 8, damage

CF 3

127 BWR CRDMs and Reactor internals Jet pumps SS 304, 304L, 316L, General Electric FAT! FIV Cumulative fatigue

reactor internals Alloy 600, SS CF 8, damage

CF 3

128 BWR CRDMs and Reactor internals Jet pumps SS 304, 304L, 316L, General Electric EMBR/TE Loss of fracture

reactor internals Alloy 600, SS CF 8, toughness

CF 3

129 BWR CRDMs and Reactor internals Jet pumps SS 304, 304L, 316L, General Electric ERO/CORR Loss of material

reactor internals Alloy 600, SS CF 8,

CF 3

130 BWR CRDMs and Reactor internals Top guide SS 304L General Electric CORR/ IGSCC Crack initiation and

reactor growth

131 Internals Reactor internals Top guide SS 304L General Electric CORR/ IASCC Crack initiation and

growth

132 Internals Reactor internals Core spray spargers SS 304 General Electric CORR/IGSCC Crack initiation and

and piping growth

133 BWR CRDMs and Reactor internals Core spray spargers SS 304 General Electric FAT/FIV Cumulative fatigue

reactor internals and piping damage

134 BWR CRDMs and Reactor internals Feedwater spargers 304 SS, Alloy 600 General Electric FAT/THERM Crack initiation and

reactor internals growth

135 BWR CRDMs and Reactor internals Feedwater spargers 304 SS, Alloy 600 General Electric CORR/IGSCC Crack initiation and

reactor internals growth

136 BWR CRDMs and Reactor internals Fuel assembly SS CF-8, 304, 304L General Electric CORR/IGSCC Crack initiation and

reactor internals supports growth

137 BWR CRDMs and Reactor internals Fuel assembly SS CF-8, 304, 304L General Electric CORR/IASCC Crack initiation and

reactor internals supports growth

138 BWR CRDMs and Reactor internals Fuel assembly SS CF-8, 304, 304L General Electric FAT/FIV Crack initiation and

reactor internals supports _growth

139 BWR CRDMs and Reactor internals Fuel assembly SS CF-8, 304, 304L General Electric EMBR/TE Loss of fracture

reactor internals supports toughness

140 BWR CRDMs and Reactor internals Baffle plate access Alloy 600 General Electric CORR/IGSCC Crack initiation and

reactor internals hole covers growth

141 BWR CRDMs and Reactor internals Steam separator SS 304, CF-8 General Electric CORR/IGSCC Crack initiation and

reactor internals assembly/dryer bolts growth

142 BWR CRDMs and Reactor internals Steam separator SS 304, CF-8 General Electric FAT/FIV Cumulative fatigue

reactor internals assembly/dryer bolts damage

143 BWR CRDMs and Reactor internals Steam separator SS 304, CF-8 General Electric EMBR/TE Loss of fracture

reactor internals assembly/dryer bolts toughness

144 BWR CRDMs and Reactor internals Steam separator A-286 General Electric CORR/IGSCC Crack initiation and

reactor internals dryer assembly growth

1____ _ 1____ beams I I I I

145 BWR CRDMs and

reactor internals

Reactor internals Steam separator

dryer assembly

beams

A 286 General Electric FAT/ FIV Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aging on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations

Page 39B

Page No. Item

Loss of adequate core flow. Frequent General Electric and ASME Sec Xl None 253, 257, 125

EPRI programs IWB 258,271

V2

Loss of adequate core flow. Frequent General Electric and ASME Sec Xl Need fatigue crack initiation and 253, 264, 126

EPRI programs IWB crack growth data in HWC 267, 271

environments [4] V2

Loss of adequate core flow. Infrequent General Electric and ASME Sec Xl None 264, 271 127

EPRI programs IWB V2

Concern is for cast SS components. Loss Infrequent WOG, EPRI, and ASME Sec Xl Continue research on embrittiement 265, 271 128

of toughness could enhance susceptibility NRC work at ANL IWB of cast SS [4] V2

to failure, if a crack develops due to

IGSCC or fatigue. Loss of adequate core

flow.

Could lead to wall thinning. Rare Not discussed in ASME Sec Xl None 265, 271 129

report IWB V2

Cracking could lead to loss of core Infrequent Not discussed in ASME Sec Xl None 253, 258, 130

geometry. report IWB 271 V2

Cracking could lead to loss of core Frequent General Electric ASME Sec Xl Current studies ignored swelling, 253,255, 131

geometry. program IWB multiple beam failures; only rough 263,270,

estimates for materials 271 V2

propertiesBetter understanding

needed to evaluate damage due to

IASCC [4-AN I]

Loss of effective ECCS. Frequent General Electric, ASME Sec Xl None 253, 257, 132

EPRI and USNRC IWB 271 V2

research

Loss of effective ECCS. Frequent Not discussed in ASME Sec XI None 253, 271 133

report IWB V2

Improper feedwater flow. Frequent Not discussed in ASME Sec XI None 253, 255, 134

report IWB 267, 271

V2

Improper feedwater flow. Frequent General Electric, ASME Sec Xl None 253, 271 135

EPRI and USNRC IWB V2

research

Loss of fuel geometry. Frequent General Electric, ASME Sec Xl None 243, 253, 136

EPRI and USNRC IWB 271 V2

research

Loss of fuel geometry. Frequent General Electric ASME Sec Xl Better understanding needed to 243,253, 137

program IWB evaluate damage due to IASCC [4- 255, 263,

ANL] 267,271

V2

Loss of fuel geometry. Infrequent Not discussed in ASME Sec XI None 243,253, 138

report IWB 271 V2

Loss of fuel geometry. Infrequent USNRC research ASME Sec Xl None 243, 253, 139

IWB 265,271

V2

Improper core flow. Frequent General Electric, ASME Sec Xl None 243,271 140

EPRI and USNRC IWB V2

research

Damage to steam lines and turbines. Frequent General Electric, ASME Sec Xl None 248, 255, 141

EPRI and USNRC IWB 253, 271

research V2

Damage to steam lines and turbines. Infrequent Not discussed in ASME Sec Xl None 248, 253, 142

report IWB 255, 271

V2

Damage to steam lines and turbines. Infrequent USNRC Research ASME Sec Xl None 248, 253, 143

IWB 255, 271

V2

Damage to steam lines and turbines. Frequent Not discussed in ASME Sec XI None 248, 253, 144

report IWB 255 V2

Damage to steam lines and turbines. Infrequent Not discussed in

report

ASME Sec XI

IWB

None 248, 253,

255 V2

14E
Table A.1 Gall Report for NPAR Reports Page 40A

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

146 BWR reactor Feedwater piping Piping SA 333 Gr 6. SA General Electric ERO/CORR Loss of material

feedwater system 106 Gr B

and main steam line

147 BWR reactor Feedwater piping Piping SA 333 Gr 6. SA General Electric FAT/THERM Cumulative fatigue

feedwater system 106 Gr B damage

and main steam line

148 BWR reactor Feedwater piping Piping SA 333 Gr 6. SA General Electric FAT/ ENV Cumulative fatigue

feedwater system 106 Gr B damage

and main steam line

149 BWR reactor Main steam piping Piping SA 106 Gr B, General Electric ERO/CORR Loss of material

feedwater system

and main steam line

150 BWR reactor Main steam piping Piping SA 106 Gr B, General Electric FAT Cumulative fatigue

feedwater system damage

and main steam line

151 BWR reactor Main steam piping Elbows SA 182 Gr B (forged General Electric ERO/CORR Loss of material

feedwater system elbows), SA 234 Grs

and main steam line WPC,, WPB, or

WPCW (welded

I _elbows)

152 BWR reactor Main steam piping Elbows SA 182 Gr B (forged General Electric FAT Cumulative fatigue

feedwater system elbows), SA 234 Grs damage

and main steam line WPC,, WPB, or

WPCW (welded

elbows)

153 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR Loss of material

Mark I drywell base 212 Gr B

near sand pocket

154 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR/CREV Local loss of materi

Mark I drywell base 212 Gr B

near sand pocket

155 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR/ MIC Loss of material Mark I drywell base 212 Gr B

near sand pocket

156 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR Loss of material

Mark I and II drywell 212 Gr B

157 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR/CREV Local loss of materia

Mark I and 11 drywell 212 Gr B

158 BWR Containments Metal containments Exterior surface of SA 516 Gr 70 SA Not stated CORR/ PIT Local loss of materia

Mark I and II drywell 212 Gr B

1591BWR Containments Metal containments Cylindrical spherical

shell transition

regon

SA 516 Gr 70 SA

212 Gr B

Not stated FAT Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 40B

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aging on Component Function Contrib to Failure Reported [roqs Rel.proqs Report Recommendations Page No. Item

Leakage or rupture. Moderate USNRC IE IN 87 01, ASME Sec Xl Need on line monitoring. Need to 208-210, 146

ASME XI IWB monitor dissolved oxygen levels. 212, 215,

Evaluate use of flame sprayed SS 216, 226,

coatings. [4] 227 V2

Crack initiation & propagation could result Frequent ASME Section III, ASME Sec III & Need on line monitoring [2] 208-210, 147

in leakage. ANSI B31.1, ASME Sec XI IWB 219,221-

Xl 224, 226,

2_27 V2

Crack initiation & propagation could result Frequent ASME Section III, ASME Sec III & Need on line monitoring. Need 208-210, 148

in leakage. ANSI B31.1, ASME Sec XI IWB evironmental fatigue data. Need to 220,221,

Xl monitor dissolved oxygen levels. [4] 226,227

V2

Leakage or rupture. Infrequent USNRC IE IN 87 01, ASME Sec XI Need on line monitoring [2] 208-210, 149

ASME Xl IWB 217-219,

226, 227

V2

Crack initiation & propagation could result Frequent ASME Section III, ASME Sec III & Need on line monitoring [2] 208-210, 150

in leakage. ANSI B31.1, ASME Sec Xl IWB 212, 226,

XI 227 V2

Leakage or rupture. Infrequent USNRC IE IN 87 01, ASME Sec Xl Need on line monitoring [2] 208-210, 151

ASME XI IWB 217-219,

226,227

V2

Crack initiation & propagation could result Frequent ASME Section III, ASME Sec III & Need on line monitoring [2] 208-210, 152

in leakage. ANSI B31.1, ASME Sec XI IWB 212,226,

Xl 227 V2

Leakage of radioactive gases. Frequent 11OCFR50 Appendix ASME Sec XI Mitigation methods need to be 169, 170, 153

J, USNRC GL 87-05 IWE developed. Use zinc rich or phenolic 172-178,

coatings instead of red lead or epoxy 188,190-

coatings [4] 192,195,

196,200,

201 V2

Leakage of radioactive gases. Moderate 10CFR50 Appendix ASME Sec XI Mitigation methods need to be 169,170, 154

J, USNRC GL 87-05 IWE developed. Use zinc rich or phenolic 172-178,

coatings instead of red lead or epoxy 188, 190-

coatings [4] 192,195,

196,200,

201 V2

Leakage of radioactive gases. Frequent 1OCFR50 Appendix ASME Sec XI Mitigation methods need to be 169, 170, 155

J, USNRC GL 87-05 IWE developed. Use zinc rich or phenolic 172-178,

coatings instead of red lead or epoxy 188, 190-

coatings [4] 192, 195,

196,200,

201 V2

Leakage of radioactive gases. Frequent 1OCFR50 Appendix ASME Sec XI Mitigation methods need to be 169, 170, 156

J, USNRC GL 87-05 IWE developed. Use zinc rich or phenolic 172-178,

coatings instead of red lead or epoxy 188,190-

coatings [4] 192,195,

196,200,

201 V2

Leakage of radioactive gases. Moderate 10CFR50 Appendix ASME Sec Xl Mitigation methods need to be 169, 170, 157

J, USNRC GL 87-05 IWE developed. Use zinc rich or phenolic 172-178,

coatings instead of red lead or epoxy 188,190-

coatings [4] 192,195,

196,200,

201 V2 I

Leakage of radioactive gases. Frequent IOCFR50 Appendix ASME Sec Xl Mitigation methods need to be 169,170, 158

J, USNRC GL 87-05 IWE & developed. Use zinc rich or phenolic 172-178,

1OCFR50 App. coatings instead of red lead or epoxy 188,190-

J coatings [4] 192,195,

196,200,

1 1_ 1_ 11201 V2

Leakage of radioactive gases. Occasional 10CFR50 Appendix

J

ASME Sec XI

IWE &

1OCFR50 App.

J

None 169,170,

193, 200,

201 V2

15S
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item SysemSructure/Como Subcomoonent Materials Manufacturer ARD mechanism

Page 41A

ARD effects

1601 BWR Containments Metal containments. Cylindrical spherical SA 516 Gr 70 SA Not stated EMBR/ IR Loss of fracture

shell transition 212 Gr B toughness

region

161 BWR Containments Metal containments Embedded shell SA 516 Gr 70 SA Not stated FAT/ THERM Cumulative fatigue

212 Gr B damage

162 BWR Containments Metal containments Embedded shell SA 516 Gr 70 SA Not stated CORR/ PIT Local loss of materia

212 Gr B

163 BWR Containments Metal containments High energy piping Not identified Not stated FAT Cumulative fatigue

penetrations damage

164 BWR Containments Metal containments SS bellows Type 304 SS Not stated CORR/ SCC Crack initiation and

growth

165 BWR Containments Metal containments Suppression SA 516 Gr 70 SA Not stated CORR Loss of material

pool/chamber Mark I 212 Gr B

and II

166 BWR Containments Metal containments Suppression SA 516 Gr 70 SA Not stated CORR/ PIT Local loss of materia

pool/chamber Mark I 212 Gr B

and II

167 BWR Containments Metal containments Suppression SA 516 Gr 70 SA Not stated CORR/MIC Loss of material

pool/chamber Mark I 212 Gr B

and II

168 BWR Containments Metal containments Dissimilar metal Ferritic to SS Not stated CORR Loss of material

welds

169 BWR Containments Metal containments Dissimilar metal Ferritic to SS Not stated FAT/ THERM Cumulative fatigue

welds damage

170 BWR Containments Reinforced concrete Reinforcing bars Not identified Not stated CORR Loss of material

containments

171 BWR Containments Reinforced concrete Reinforcing bars Not identified Not stated FAT Cumulative fatigue

containments damage

172 BWR Containments Reinforced concrete Mark I and II SA 516 Gr 60 Not stated CORR Loss of material

containments suppression pool

steel liner

1 BWH Containments Heintorced concrete

containments

Mark I and II

suppression pool

steel liner

SA 516 Gr 60 Not stated CORR/MIC Loss of material
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aqina on Component Function Contrib to Failure Reported proas Rel.proas Report Recommendations

Page 41B

Pace No. Item

Leakage of radioactive gases. Infrequent IOCFR50 Appendix ASME Sec XI None 169,170, 160

J IWE & 193,194,

10CFR50 App. 200,201

J V2

Loss of structural integrity. Occasional Not discussed in ASME Sec XI None 169,170, 161

report IWE & 172-178,

1OCFR50 App. 193,200,

J 201 V2

Loss of structural integrity. Frequent Not discussed in ASME Sec XI Develop electromagnetic acoustic 169,170, 162

report IWE & tranducers to detect corrosion [2] 172-178,

10CFR50 App. 200, 201

J V2

Leakage of radioactive gases. Occasional 10CFR5O Appendix ASME Sec XI None 177, 180, 163

J IWE & 200,201

10CFR50 App. V2 J I

Leakage of radioactive gases. Moderate 10CFR50 Appendix ASME Sec XI None 177,190, 164

J IWE & 196,200,

10CFR50 App. 201 V2

J

Leakage of radioactive gases. Frequent 10CFRSO Appendix ASME Sec XI None 169,170, 165

J, USNRC IN 88-82 IWE & 172-178,

1OCFR50 App. 188,190-

J 192, 195,

196,200,

201 V2

Leakage of radioactive gases. Frequent 10CFR50 Appendix ASME Sec XI None 169, 170, 166

J, USNRC IN 88-82 IWE & 172-178,

10CFR50 App. 188,190-

J 192,195,

196,200,

201 V2

Leakage of radioactive gases. Frequent 10CFR50 Appendix ASME Sec XI None 169, 170, 167

J, USNRC IN 88-82 IWE & 172-178,

10CFR50 App. 188,190-

J 192,195,

196, 200,

201 V2 I

Leakage of radioactive gases. Frequent ASME XI, 10CFR50 ASME Sec XI None 169,170, 168

Appendix J IWE & 172-178,

10CFR50 App. 200, 201

J V2

Leakage of radioactive gases. Occasional 10CFR50 Appendix ASME Sec XI None 169,170, 169

J IWE & 172-178,

10CFR50 App. 193, 200,

J 201 V2 I

Loss of structural integrity. Frequent USNRC Reg. Guide ASME Sec XI None 169,170, 170

1.136, Rev2 IWL & 182 185,

10CFR50 App. 189,194,

J 196,203

V2

Loss of structural integrity. Occasional USNRC Reg. Guide ASME Sec XI None 169,170, 171

1.136, Rev 2 IWL & 182 185,

10CFR50 App. 189,194,

J 196,203

V2

Leakage of radioactive gases. Frequent 10CFR5O Appendix ASME Sec XI None 169,170, 172

J IWL & 182 185,

10CFR5O App. 189,194,

J 196,203

V2

Leakage of radioactive gases. Frequent 10CFR50 Appendix

J

ASME Sec Xl

IWL &

10CFR5O App.

J

None 169,170,

182 185,

189,194,

196,203

V2

173
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Ught Water Reactor Components Overview

Page 42A

Reviewed by: W. J. Shack, ANL

Item System Structur e/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

174 BWR Containments Reinforced concrete Mark I and II SA 516 Gr 60 Not stated FAT Cumulative fatigue

containments suppression pool damage

steel liner

175 BWR Containments Reinforced concrete Drywall steel liner SA 516 Gr 60 Not stated CORR Loss of material

containments

176 BWR Containments Reinforced concrete Drywall steel liner SA 516 Gr 60 Not stated FAT Cumulative fatigue

containments damage

177 BWR Containments Reinforced concrete Concrete Not stated Not stated AGR-CHEM Chemical or physical

containments degradation

178 BWR Containments Reinforced concrete Concrete Not stated Not stated AGREAC Chemical or physical

containments degradation

179 BWR Containments Reinforced concrete Concrete Not stated Not stated ELE-TEMP Chemical or physical

containments degradation

180 BWR Containments Mark II Prestressed Postensioning Not identified Not stated CORR Loss of material

concrete anchors

181 BWR Containments Mark II Prestressed Postensioning Not identified Not stated CORR/ SCC Crack initiation and

concrete anchors growth

182 BWR Containments Mark II Prestressed Tendons Not identified Not stated CORR/ MIC Loss of material

concrete

183 BWR Containments Mark II Prestressed Suppression pool Not identified Not stated CORR Loss of material

concrete steel liner

184 BWR Containments Mark II Prestressed Suppression pool Not identified Not stated CORR/ MIC Loss of material

concrete steel liner

1851 BWR Containments Mark II Prestressed Suppression pool Not identified Not stated FAT Cumulative fatigue

concrete steel liner damage

186 BWR Containments Mark II Prestressed Drywall steel liner Not identified Not stated CORR Loss of material

concrete

187 BWR Containments Mark II Prestressed Drywell steel liner Not identified Not stated FAT Cumulative fatigue

concrete damage

188 BWR Containments Mark II Prestressed Reinforcing bars, Not identified Not stated CORR Loss of material

concrete

189 BWR Containments Mark II Prestressed Concrete Not identified Not stated AGREAC Chemical or physical

concrete degradation

190 BWR Containments Mark II Prestressed Concrete Not identified Not stated ELE-TEMP Chemical or physical

concrete _ _ _ degradation

1911 PWR Containments I Metal containments Shell welds & base

metal

Not identified Not stated CORR Loss of material
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations

Page 42B

Page No. Item

Leakage of radioactive gases. Occasional 10CFR50 Appendix ASME Sec Xl None 169,170, 174

J IWL 182 185,

189,193,

194,196,

203 V2

Leakage of radioactive gases. Frequent 10CFR50 Appendix ASME Sec Xl None 169,170, 175

J IWL & 182 185,

10CFR50 App. 189,194,

J 196,203

V2

Leakage of radioactive gases. Occasional 10CFR50 Appendix ASME Sec X1 None 169,170, 176

J IWL 182 185,

189,193,

194,196,

203 V2

Degradation of shielding properties. Moderate USNRC Reg. Guide ASME Sec X1 None 169,170, 177

1.136, Rev2 IWL 182 185,

189,194,

196,203

V2

Degradation of shielding properties. Occasional USNRC Reg. Guide ASME Sec XI None 169,170, 178

1.136, Rev 2 IWL 182 185,

189,194,

196, 203

V2

Degradation of shielding properties. Moderate USNRC Reg. Guide ASME Sec X1 None 169, 170, 179

1.136, Rev 2 IWL 182 185,

189,194,

196, 203

V2

Loss of prestress. Frequent Not discussed in ASME Sec Xl Improved methods of monitoring 185 187, 180

report IWL degradation needed. [4] 195,196,

204 V2

Loss of prestress. Frequent Not discussed in ASME Sec Xl None 185 187, 181

report IWL 195, 196,

204 V2

Loss of prestress. Frequent USNRC Reg. Guide ASME Sec Xl Improved methods of monitoring 185 187, 182

1.35 Rev 2, USNRC IWL decomposition of tendon grease 195,196,

Reg. Guide 1.90 needed. [4] 204 V2

_ Rev 1,

Leakage of radioactive gases. Frequent 10CFR50 Appendix ASME Sec Xl None 190 192, 183

J IWL & 204 V2

1OCFRSO App.

J

Leakage of radioactive gases. Frequent 10CFRSO Appendix ASME Sec Xl None 190 192, 184

J IWL & 204 V2

10CFR50 App.

J

Leakage of radioactive gases. Occasional 10CFR50 Appendix ASME Sec Xl None 193, 204 185

J IWL V2

Leakage of radioactive gases. Frequent 1OCFR50 Appendix ASME Sec Xl None 190 192, 186

J IWL & 204 V2

1OCFR50 App.

J

Leakage of radioactive gases. Occasional 10CFR5O Appendix ASME Sec Xl None 193,204 187

J IWL _V2

Loss of structural integrity. Frequent Not discussed in ASME Sec Xl None 194,204 188

report IWL V2

Degradation of shielding properties. Loss Occasional Not discussed in ASME Sec Xl None 194,204 189

of prestress. report IWL V2

Degradation of shielding properties. Moderate Not discussed in ASME Sec XI None 194,204 190

report IWL V2

Loss of structural integrity. Leakage of

radioactive gases.

Frequent 1 OCFR50 Appendix

J

ASME Sec Xl

IWE &

1OCFR50 App.

J

None 32, 39, 52

V1

191
Table A.1 Gall Report for NPAR Reports Page 43A

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Ught Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System Structurie/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

192 PWR Containments Metal containments Interface between Not identified Not stated CORR Loss of material

shell and concrete

slab at base

193 PWR Containments Metal containments Disconti nuities in Not identified Not stated CORR Loss of material

shell

194 PWR Containments Metal containments Embedded portion of Not identified Not stated CORR Loss of material

shell

195 PWR Containments Metal containments Base slab concrete Not identified Not stated AGREAC Chemical or physica

I _degradation

196 PWR Containments Metal containments Base slab concrete Not identified Not stated AGR-CHEM Chemical or physica

degradation

197 PWR Containments Reinforced concrete Reinforcing bars Not identified Not stated CORR Loss of material

containments

198 PWR Contalnments Reinforced concrete Steel liner Not identified Not stated CORR Loss of material

containments

199 PWR Containments Reinforced concrete Concrete Not identified Not stated AGREAC Chemical or physical

containments degradation

200 PWR Containments Reinforced concrete Concrete Not identified Not stated AGR-CHEM Chemical or physical

containments degradation

201 PWR Containments Pre-stressed Postensioning Not identified Not stated CORR Loss of material

concrete anchors

containments

202 PWR Containments Pre-stressed Tendons Not identified Not stated CORR/PIT Local loss of materia

concrete

containments

203 PWR Containments Pre-stressed Tendons Not identified Not stated CORR/MIC Loss of material

concrete

containments

204 PWR Containments Pre-stressed Steel liner Not identified Not stated CORR Loss of material

concrete

containments

205 PWR Containments Pre-stressed Reinforcing bars Not identified Not stated CORR Loss of material

concrete

containments

206 PWR Containments Pre-stressed Concrete Not identified Not stated AGREAC Chemical or physical

concrete degradation

containments

207 PWR Containments Pre-stressed Concrete Not identified Not stated AGR-CHEM Chemical or physical

concrete degradation

containments

208 BWR and PWR PWR support Neutron shield tank A516 Gr 60, A516 Not stated EMBR/IR Loss of fracture

reactor pressure systems Gr 70, A302 Gr B, toughness

vesssel supports SA533 Gr B1

209 BWR and PWR PWR support Column support A572, A36 Not stated EMBR/IR Loss of fracture

reactor pressure systems toughness

vesssel supports

210 BWR and PWR PWR support Cantilever support A572, A36 Not stated EMBR/IR Loss of fracture

reactor pressure systems toughness

vesssel supports

211* BWM ana PWR

reactor pressure

vesssel supports

PWH support

systems

Threaded parts in

sliding foot assembly

Not identified Not stated CORR/SCC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 43B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Auina on ComDonent Function Contrib to Failure Reported oroas ReI.Droas Report Recommendations Pace No. Item

Loss of structural integrity. Leakage of Frequent 10CFR50 Appendix ASME Sec Xl None 32, 39, 52 192

radioactive gases. J IWE & Vl

10CFR50 App.

J

Leakage of radioactive gases. Frequent 10CFR5O Appendix ASME Sec Xl None 32, 39, 52 192

J IWE & V1

10CFR5O App. J

Leakage of radioactive material. Frequent 10CFR50 Appendix ASME Sec Xl None 32, 39, 52 194

J IWE & V1

IOCFR50 App.

_J

Cracking and spalling. Moderate Not discussed in ASME Sec XI Additional information on long term 32, 37, 52 195

report IWE degradation needed. [2] Vl

Cracking and spalling. Frequent Not discussed in ASME Sec Xl Additional information on long term 32, 37, 52 196

report IWE degradation needed. [2] Vi

Loss of structural integrity. Frequent Not discussed in ASME Sec Xl None 32, 39, 197

report IWL 43, 45, 51

Vl

Leakage of radioactive material. Frequent IOCFR50 Appendix ASME Sec Xl None 32, 39, 51 198

J IWL & Vl

IOCFR50 App. J

Cracking and spalling. Exposure of Moderate Not discussed in ASME Sec Xl Additional information on long term 4245, 51 199

reinforcing steel to corrosion, report IWL degradation needed. [2] Vi

Cracking and spalling. Exposure of Frequent Not discussed in ASME Sec Xl Additional information on long-term 42-45, 51 200

reinforcing steel to corrosion, report IWL degradation needed. [2] V1

Loss of prestress. Frequent Not discussed in ASME Sec Xl Monitoring system needed to detect 45, 46, 50 201

report IWL degradation. [2] Vl

Loss of prestress. Frequent Not discussed in ASME Sec Xl Monitoring system needed to detect 45, 46, 50 202

report IWL degradation. [2] Vl

Loss of prestress. Frequent Not discussed in ASME Sec Xl Monitoring system needed to detect 45, 46,50 203

report IWL degradation. [2] Vi

Leakage of radioactive material. Frequent 1OCFR5O Appendix ASME Sec Xl None 32, 39, 50 204

J IWL & Vi

1OCFRSO App. J

Loss of structural integrity. Frequent Not discussed in ASME Sec Xl None 43, 45, 50 205

report IWL V1

Cracking and spalling. Exposure of Moderate Not discussed in ASME Sec XI Additional information on long-term 42-45, 50 206

reinforcing steel to corrosion. report IWL degradation needed. [2] V1

Cracking and spalling. Exposure of Frequent Not discussed in ASME Sec XI Additional information on long-term 42-45, 50 207

reinforcing steel to corrosion. report IWL degradation needed. [2) Vi

Low ductility fracture. Moderate Not discussed in ASME Sec X1 Need additional data on effects of 79-90,93 208

report IWB irradiation at temperatures less than V1

232 deg. C. Need additional data on

spectra and flux levels at supports

[4]

Low ductility fracture. Frequent Not discussed in ASME Sec Xl Need additional data on effects of 7990, 93 209

report IWB irradiation at temperatures less than V1

232 deg. C. Need additional data on

spectra and flux levels at supports

[4)

Low ductility fracture. Frequent Not discussed in ASME Sec XI Need additional data on effects of 79-90, 93 210

report IWB irradiation at temperatures less than V1

232 deg. C. Need additional data on

spectra and flux levels at supports

1[4]

Binding that may cause excessive

stresses in primary coolant system.

Frequent Not discussed in

report lWB

None 92,93 V1 211
Table A.1 Gall Report for NPAR Reports Page 44A

Document: NUREG/CR-4731 Vols. 1&2, Residual Ufe Assessment of Major Ught Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructuretComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

212 BWR and PWR PWR support Dry lubricant in Not identified Not stated EMBR/IR Degradation of

reactor pressure systems sliding foot assembly properties

vesssel supports

213 BWR and PWR PWR support Skirt support A516 Gr 60, A516 Babcock & Wilcox FAT Cumulative fatigue

reactor pressure systems Gr 70, A302 Gr B, damage

vesssel supports SA533 Gr B1

214 BWR and PWR BWR support Skirt support A516 Gr 60, A516 General Electric FAT Cumulative fatigue

reactor pressure system Gr 70, A302 Gr B, damage

vesssel supports SA533 Gr B1

215 Emergency diesel Fuel system Piping on engine Not identified Not stated FAT Cumulative fatigue

generators damage

216 Emergency diesel Fuel system Fuel injection pumps Not identified Not stated CONTAM Buildup of deposits

generators from corrosion and

wear

217 Emergency diesel Fuel system Fuel injectors Not identified Not stated CONTAM Buildup of deposits

generators from corrosion and

wear

218 Emergency diesel Fuel system Fuel nozzles Not identified Not stated CONTAM Buildup of deposits

generators from corrosion and

wear

219 Emergency diesel Fuel system Fuel supply pumps Not identified Not stated FAT Cumulative fatigue

generators damage

220 Emergency diesel Fuel system Filters & strainers Not identified Not stated CONTAM Buildup of deposits

generators from corrosion and

wear

221 Emergency diesel Starting system Starting air valve Not identified Not stated CONTAM Buildup of deposits

generators from corrosion and

wear

222 Emergency diesel Starting system Actuators, controls Not identified Not stated CORR Corrosion deposits

generators cause plugging and

binding

223 Emergency diesel Cooling system Pumps Not identified Not stated WEAR Failure of seals or

generators packing; wear of

impellers and

wearing rings

224 Emergency diesel Cooling system Pumps Not identified Not stated ERO/CAV Due to poor suction

generators conditions (blocked

filters, etc.)

225 Emergency diesel Cooling system Piping Not identified Not stated VIB Cumulative fatigue

generators damage

226 Emergency diesel

generators

Cooling system Pi'ping Not identified Not stated , ENVIR Deterioration of

gaskets and flex

joints
Table A.1 Gall Report for NPAR Reports Page 448

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Agina on ComDonent Function Contrib to Failure Reaorted Droas Rel.Droas ReOrt Recommendations Page No. Item

Degradation of the lubricant could cause Frequent Not discussed in ASME Sec Xl Investigate irradiation effects on 92, 93 V1 212

binding that may cause excessive report IWB lubricants [2]

stresses in primary coolant system.

Crack initiation and growth. Frequent Not discussed in ASME Sec XI None 92, 93 V1 213

report IWB

Crack initiation and growth. Frequent Not discussed in ASME Sec XI None 92, 93 V1 214

report IWB

Occurs during start or run modes. Failure Frequent NRC and EPRI PS TS Req., Based on experience in other 340, 342, 215

can lead to leakage and fire. Poor programs on diesel RG 1.9, RG industries diesel generator sets with 343, 344,

manufacturing or maintnenance errors, reliability 1.108 good maintenance have high 346, 347,

reliability. Nuclear fast start test 360 365

requirements degrade equipment V2

and need for such tests should be

analyzed and kept to a minimum [4]

Buildup causes binding of plunger. Frequent NRC and EPRI PS TS Req., None 336, 344, 216

Affects start and run modes. programs on diesel RG 1.9, RG 349, 350,

reliability 1.108 360 365

V2

Buildup causes binding of plunger. Frequent NRC and EPRI PS TS Req., None 336, 344, 217

Affects start and run modes. programs on diesel RG 1.9, RG 349, 350,

reliability 1.108 360 365

V2

Plugging of nozzle holes. Affects start Frequent NRC and EPRI PS TS Req., None 336, 344, 218

and run modes. programs on diesel RG 1.9, RG 349,350,

reliability 1.108 360-365

V2

Pump shaft or coupling fails. Fuel supply Moderate NRC and EPRI PS TS Req., None 336, 344, 219

is then lost or reduced. Affects run mode. programs on diesel RG 1.9, RG 349,350,

reliability 1.108 360-365

V2

Clogging. Fuel supply is then lost or Frequent NRC and EPRI PS TS Req., None 336, 344, 220

reduced. Affects run mode. programs on diesel RG 1.9, RG 349, 350,

reliability 1.108 360-365

V2

Dirt and corrosion products can plug or Frequent NRC and EPRI PS TS Req., Based on experience in other 336, 344, 221

bind valve. Affects start mode. programs on diesel RG 1.9, RG industries diesel generator sets with 349, 350,

reliability 1.108 good maintenance have high 360-365

reliability. Nuclear fast start test V2

requirements degrade equipment

and need for such tests should be

analyzed and kept to a minimum [4]

Plugging and binding from corrosion Frequent NRC and EPRI PS TS Req., None 336, 344, 222

products. Affects start mode. programs on diesel RG 1.9, RG 349, 350,

reliability 1.108 360-365

V2

Leakage at seals. Affects run mode. Frequent NRC and EPRI PS TS Req., Based on experience in other 337, 338, 223

programs on diesel RG 1.9, RG industries diesel generator sets with 342, 347,

reliability 1.108 good maintenance have high 348, 350,

reliability. Nuclear fast start test 360-365

requirements degrade equipment V2

and need for such tests should be

analyzed and kept to a minimum [4]

Loss of pressure and flow. Affects run Frequent NRC and EPRI PS TS Req., None 337, 338, 224

mode. programs on diesel RG 1.9, RG 342, 347,

reliability 1.108 348, 350,

360-365

V2

Leakage. Affects run mode. Frequent NRC and EPRI PS TS Req., None 337, 338, 225

programs on diesel RG 1.9, RG 342, 347,

reliability 1.108 348, 350,

360-365

V2

Leakage. Affects run mode. Frequent NRC and EPRI

programs on diesel

reliability

PSTS Req.,

RG 1.9, RG

1.108

None 337, 338,

342, 347,

348, 350,

360-365

V2

226
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism

Page 45A

ARD effects

227 Emergency diesel Cooling system Heat exchangers Not identified Not stated CORR Loss of material

generators

228 Emergency diesel Cooling system Heat exchangers Not identified Not stated ERO/CAV Loss of material

generators

229 Emergency diesel Cooling system Radiator Not identified Not stated CORR Loss of material

generators

230 Emergency diesel Engine structure Crankcase and Cast iron, welded Not stated FAT/THER Cumulative fatigue

generators cylinder block steel damage

231 Emergency diesel Engine structure Crankcase and Cast iron, welded Not stated FAT Cumulative fatigue

generators cylinder block steel damage

232 Emergency diesel Engine structure Liners and seals Cast iron Not stated WEAR Loss of material

generators

233 Emergency diesel Engine structure Main bearings Not identified Not stated FAT Cumulative fatigue

generators damage

234 Emergency diesel Engine structure Cylinder heads Nodular iron or cast Not stated FAT/THER Cumulative fatigue

generators steel damage

235 Emergency diesel Engine structure Bolting Not identified Not stated VIB Cumulative fatigue

generators damage

236 Emergency diesel Intake and exhaust Turbo charger Not identified Not stated VIB Cumulative fatigue

generators system damage

237 Emergency Diesel Lubrication system Pumps Not identified Not stated FAT Cumulative fatigue

Generators damage

238 Emergency Diesel Lubrication system Heat exchangers Not identified Not stated CORR Loss of material

Generators

239 Emergency Diesel Lubrication system Lube oil Not identified Not stated ENVIR Deterioration by heat

Generators

240 Emergency Diesel Lubrication system Lube oil Not identified Not stated CONTAM Leakage and wear

Generators particle contaminate

I I_ I_ I lubricant

241 Emergency Diesel

Generators

Lubrication system Piping Not identified Not stated VIB Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 45B

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Agina on Component Function Contrib to Failure Reported proas Rel.progs Report Recommendations Page No. Item

Leakage. Affects run mode. Frequent NRC and EPRI PS TS Req., None 337, 338, 227

programs on diesel RG 1.9, RG 342,'347,

reliability 1.108 348, 360-

365 V2

Leakage. Affects run mode. Frequent NRC and EPRI PS TS Req., None 337, 338, 228

programs on diesel RG 1.9, RG 342, 347,

reliability 1.108 348, 360-

365 V2

Leakge or plugging. Affects run mode. Frequent NRC and EPRI PS TS Req., None 337, 338, 229

programs on diesel RG 1.9, RG 342,347,

reliability 1.108 348,360

365 V2

Cracking of block or crankage produces Moderate NRC and EPRI PS TS Req., Based on experience in other 335, 342, 230

leakage into lube oil. Shaft and bearing programs on diesel RG 1.9, RG industries diesel generator sets with 347, 348,

failure. Affects run mode. reliability 1.108 good maintenance have high 350, 360-

reliability. Nuclear fast start test 365 V2

requirements degrade equipment

and need for such tests should be

analyzed and kept to a minimum [4]

Cracking of block or crankage produces Moderate NRC and EPRI PS TS Req., None 335, 342, 231

leakage into lube oil. Shaft and bearing programs on diesel RG 1.9, RG 347,348,

failure. Affects run mode. reliability 1.108 350, 360-

365 V2

Piston seizure. Leakage to lube oil. Moderate NRC and EPRI PS TS Req., None 335, 342, 232

Affects run mode. programs on diesel RG 1.9, RG 347, 348,

reliability 1.108 350, 360-

365 V2

Bearing failure. Damage to crankshaft. Moderate NRC and EPRI PS TS Req., None 335, 342, 233

Affects run mode. programs on diesel RG 1.9, RG 347,348,

reliability 1.108 350, 360-

365 V2

Cracking/fracture. Water leakage leads to Moderate NRC and EPRI PS TS Req., None 335, 342, 234

additional damage. Affects run mode. programs on diesel RG 1.9, RG 347, 348,

reliability 1.108 350, 360-

365 V2

Fracture leading to other consequences. Moderate NRC and EPRI PS TS Req., None 342, 347, 235

Affects run mode. programs on diesel RG 1.9, RG 348, 360-

reliability 1.108 365 V2

Fracture or bearing seizure; high speed Moderate NRC and EPRI PS TS Req., Based on experience in other 335, 336, 236

rotating part critically dependent on proper programs on diesel RG 1.9, RG industries diesel generator sets with 342, 348,

lubrication of bearings, reliability 1.108 good maintenance have high 349, 360-

reliability. Nuclear fast start test 365 V2

requirements degrade equipment

and need for such tests should be

analyzed and kept to a minimum [4]

Cracking, fracture of drive shaft. Affects Moderate NRC and EPRI PS TS Req., Based on experience in other 335, 336, 237

run mode. programs on diesel RG 1.9, RG industries diesel generator sets with 360-365

reliability 1.108 good maintenance have high V2

reliability. Nuclear fast start test

requirements degrade equipment

and need for such tests should be

analyzed and kept to a minimum [4]

Leakage. Affects run mode. Moderate NRC and EPRI PS TS Req., None 335, 336, 238

programs on diesel RG 1.9, RG 360-365

reliability 1.108 V2

Loss of lubrication effectiveness. Affects Frequent NRC and EPRI PS TS Req., None 335, 336, 239

run mode. programs on diesel RG 1.9 ,RG 360-365

reliability 1.108 V2

Loss of lubrication effectiveness. Affects Frequent NRC and EPRI PS TS Req., None 335, 336, 240

run mode. programs on diesel RG 1.9, RG 360-365

1 reliability 1.108 V2

Leakage. Loss of lubrication

9ffectiveness. Affects run mode.

Moderate NRC and EPRI

programs on diesel

reliability

PS TS Req.,

RG 1.9, RG

1.108

None 335, 336,

360-365

V2
Table A.1 Gall Report for NPAR Reports Page 46A

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

242 Emergency Diesel Drive train Pistons Cast iron or steel Not stated FAT Cumulative fatigue

Generators damage

243 Emergency diesel Drive train Piston rings Not identified Not stated WEAR Loss of material,

generators seizure

244 Emergency diesel Drive train Connecting rods Forged steel Not stated FAT Cumulative fatigue

generators damage

245 Emergency diesel Drive train Crankshaft Not identified Not stated FAT Cumulative fatigue

generators damage

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Service Water Check Valves Not stated Not stated Not stated WEAR Attrition

System

2 Service Water Check Valves Not stated Not stated Not stated ERO Wall Thinning

System

3 Service Water Check Valves Not stated Not stated Not stated WEAR Attrition

System

4 Service Water Check Valves Not stated Not stated Not stated CORR Loss of Material

System

5 Service Water Check Valves Not stated Not stated Not stated CONTAM Buildup of Deposits

System

6 Service Water Check Valves Not stated Not stated Not stated ERO Wall Thinning

System

7 Service Water Check Valves Not stated Not stated Not stated WEAR Attrition

System

8 Service Water Check Valves Not stated Not stated Not stated CORR Loss of Material

System

9 Service Water - Check Valves Not stated Not stated Not stated CLOG Row Blockage

System

10 Service Water Hand Control Valves Not stated Not stated Not stated WEAR Attrition

System

11 Nt sttedNot tatd COR Los o Matria

11 Service Water

System

Hand Control Valves I Not stated Not stated Not stated CORR Loss of Material
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4731 Vols. 1&2, Residual Life Assessment of Major Light Water Reactor Components Overview

Reviewed by: W. J. Shack, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.proas Report Recomm

Page 46B

endations Pacie No. Item

Piston seizure. Affects start and run Moderate NRC and EPRI PS TS Req., Based on experience in other 333, 335, 242

modes. programs on diesel RG 1.9, RG industries diesel generator sets with 346, 347,

reliability 1.108 good maintenance have high 360-365

reliability. Nuclear fast start test V2

requirements degrade equipment

and need for such tests should be

analyzed and kept to a minimum [4]

Piston seizure. Affects start and run Moderate NRC and EPRI PS TS Req., None 333,335, 243

modes. programs on diesel RG 1.9, RG 346,347,

reliability 1.108 360-365

V2

Piston seizure. Affects run mode. Moderate NRC and EPRI PS TS Req., None 333, 335, 244

programs on diesel RG 1.9, RG 346, 347,

reliability 1.108 360-365

V2

Failure of crankshaft Crankcase Moderate NRC and EPRI PS TS Req., None 333,335, 245

explosion. programs on diesel RG 1.9, RG 346, 347,

reliability 1.108 360-365

V2

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to.Failure Reported progs Rel.progs Report Recommendations Page No. Item

External Leakage - The most common Rare Not stated ASME Sec Xl Not stated F 8

case is flange leakage. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Open - Valve fails to open fully Rare Not stated ASME Sac Xl Not stated F 8 2

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-8

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-8 4

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Internal Leakage - (Reverse Leakage) - Rare Not stated ASME Sec Xl Not stated F-9

Reverse leakage is a failure mode to IWV & PS TS

describe internal leakage through a check Req. and/or PS

valve. S&T Re

Internal Leakage - (Reverse Leakage) - Occasional Not stated ASME Sec XI Not stated F-9 6

Reverse leakage is a failure mode to IWV & PS TS

describe internal leakage through a check Req. and/or PS

valve. S&T Re I

Internal Leakage - (Reverse Leakage) - Frequent Not stated ASME Sec XI Not stated F-9 7

Reverse leakage is a failure mode to IWV & PS TS

describe internal leakage through a check Req. and/or PS

valve. S&T Re

Internal Leakage - (Reverse Leakage) - Moderate Not stated ASME Sec Xl Not stated F-9 8

Reverse leakage is a failure mode to IWV & PS TS

describe internal leakage through a check Req. and/or PS

valve. S&T Re

Internal Leakage - (Reverse Leakage) - Rare Not stated ASME Sec XI Not stated F-9 9

Reverse leakage is a failure mode to IWV & PS TS

describe internal leakage through a check Req. and/or PS

valve. S&T Re

External Leakage - The most common Rare Not stated ASME Sec Xl Not stated F-10 10

case is a flange leakage. IWV & PS TS

Req. and/or PS

I__ I _ _ I_ S&T Re

External Leakage - The most common

case is a flange leakage.

Rare Not stated ASME Sec Xl

IWV & PS TS

Req. and/or PS

S&T Re

Not stated F-1 0 11
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 47A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

12 Service Water Hand Control Valves Not stated Not stated Not stated ERO Wail Thinning

System

13 Service Water Hand Control Valves Not stated Not stated Not stated WEAR Attrition

System

14 Service Water Hand Control Valves Not stated Not stated Not stated CORR Loss of Material

System

15 Service Water Hand Control Valves Not stated Not stated Not stated CLOG Flow Blockage

System

16 Service Water Hand Control Valves Not stated Not stated Not stated CORR Loss of Material

System

17 Service Water Hand Control Valves Not stated Not stated Not stated ADH Loss of Movement

System

18 Service Water Motor Operated Not stated Not stated Not stated ERO Wall Thinning

System Valves

19 Service Water Motor Operated Not stated Not stated Not stated WEAR Attrition

System Valves

20 Service Water Motor Operated Not stated Not stated Not stated CORR Loss of Material

System Valves

21 Service Water Motor Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

22 Service Water Motor Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

23 Service Water Motor-Operated Not stated Not stated Not stated FAT Cumulative Fatigue

System Valves Damage

24 Service Water Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

25 Service Water Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

26 Service Water Motor-Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

27 Service Water Motor-Operated Not stated Not stated Not stated DRIFT Signal Drift

System Valves

No stte No sttdNtsaeIR alTinn Service Water

System

Motor Operated

Valve

Not stated Not stated Not stated ERO Wall Thinning
Table A.1 Gall Report for NPAR Reports Page 47B

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-10 12

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec XI Not stated F-10 13

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Moderate Not stated ASME Sec X1 Not stated F-1 0 14

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-10 15

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Failure to Operate as Required - (a) A Rare Not stated ASME Sec Xl Not stated F-11 16

valve fails to meet specific requirements IWV & PS TS

such as a stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec Xl Not stated F-1 2 17

mode is used when the narrative lacks IWV & PS TS

specific information on whether the valve Req. and/or PS

failed to open or failed to close. S&T Re

Fails to Close - Valve fails to close fully Occasional Not stated GL 89-10 & Not stated F-13 18

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req I

Fails to Close - Valve fails to close fully Moderate Not stated GL 89-10 & Not stated F-1 3 19

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req I

Fails to Close - Valve fails to close fully Infrequent Not stated GL 89-10 & Not stated F-1 3 20

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Fails to Close - Valve fails to close fully Frequent Not stated GL 89-10 & Not stated F-1 3 21

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Falls to Close - Valve fails to close fully Frequent Not stated GL 89-10 & Not stated F-13 22

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Falls to Open - Valve fails to open fully Rare Not stated GL 89-10 & Not stated F-14 23

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Fails to Open - Valve fails to open fully Occasional Not stated GL 89-10 & Not stated F-1 4 24

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Fails to Open - Valve fails to open fully Infrequent Not stated GL 89-10 & Not stated F-1 4 25

when demanded. Suppl. ASME

Sec XI-IWV &

PS TS Req

Fails to Open. Rare Not stated GL 89-10 & Not stated F-14 26

Suppl. ASME

Sec XI-IWV &

PS TS Req I

Fails to Open. Rare Not stated GL 89-10 & Not stated F-1 4 27

Suppl. ASME

Sec XI-IWV &

I PS TS Req I

Failure to Operate as Required (a) a valve

fails to meet specific requirements such

as stroke time or (b) a valve loses the

ability to control system parameters.

Infrequent Not stated GL 89-10 &

Suppl. ASME

Sec XI-IWV &

PS TS Req

Not stated F-i15 28
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 48A

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Service Water Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valve

30 Service Water Motor-Operated Not stated Not stated Not stated CORR Loss of Materiai

System Valve

31 Service Water Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valve

32 Service Water Motor-Operated Not stated Not stated Not stated VIBR Loosening

System Valve

33 Service Water Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valve

34 Service Water Motor-Operated Not stated Not stated Not stated CORR Loss of Material

System Valve

35 Service Water Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valve

36 Service Water Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valve

37 Service Water Motor-Operated Not stated Not stated Not stated ELE-TEMP Physical

System Valve Degradation

38 Service Water Motor-Operated Not stated Not stated Not stated VIBR Loosening

System Valve

39 Service Water Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

40 Service Water Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

41 Service Water

System

Pneumatic-Operated

Valves

Not stated Not stated Not stated CORR Loss of Material

42 Service Water Pneumatic-Operated Not stated Not stated Not stated CLOG Row Blockage

System Valves

43 Service Water Pneumatic-Operated Not stated Not stated Not stated VIBR Loosening

System Valves

4 Service Water Pneumatic-Operated Not stated Not stated Not stated FAT Fatigue Cumulative

System Valves Damage

4E Service Water

System

Pneumatic-Operated

Valves

Not stated Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 48B

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure to Operate as Required (a) a valve Occasional Not stated GL 89-10 & Not stated F-15 29

fails to meet specific requirements such Suppl. ASME

as stroke time or (b) a valve loses the Sec XI-IWV &

ability to control system parameters. PS TS Req

Failure to Operate as Required (a) a valve Rare Not stated GL 89-10 & Not stated F-1i5 30

fails to meet specific requirements such Suppl. ASME

as stroke time or (b) a valve loses the Sec XI-IWV &

ability to control system parameters. PS TS Req

Failure to Operate as Required (a) a valve Infrequent Not stated GL 89-10 & Not stated F-15 31

fails to meet specific requirements such Suppl. ASME

as stroke time or (b) a valve loses the Sec XI-IWV &

ability to control system parameters. PS TS Req

Failure to Operate as Required (a) a valve Infrequent Not stated GL 89-10 & Not stated F-1 5 32

fails to meet specific requirements such Suppl. ASME

as stroke time or (b) a valve loses the Sec XI-IWV &

ability to control system parameters. PS TS Req

External leakage - The most common Frequent Not stated GL 89-10 & Not stated F-15 33

ase is a flange leak. Suppl. ASME

Sec XI-IWV &

PS TS Req

External leakage - The most common Infrequent Not stated GL 89-10 & Not stated F-15 34

:ase is a flange leak. Suppl. ASME

Sec XI-IWV &

PS TS Req

Fails to Open/Fails to Close - This failure Infrequent Not stated GL 89-10 & Not stated F-1 6 35

mode is used when the narrative lacks Suppl. ASME

specific information on whether the valve Sec Xl IWV &

failed to open or failed to close. PS TS Req

Fails to Open/Fails to Close - This failure Rare Not stated GL 89-10 & Not stated F-1 6 36

mode is used when the narrative lacks Suppl. ASME

specific information on whether the valve Sac XI-IWV &

railed to open or failed to close. PS TS Req

Fails to Open/Fails to Close - This failure Rare Not stated GL 89-10 & Not stated F-16 37

mode is used when the narrative lacks Suppl. ASME

specific information on whether the valve Sec XI-IWV &

failed to open or failed to close. PS TS Req

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec XI Not stated F-1 6 38

mode is used when the narrative lacks IWV & PS TS

specific information on whether the valve Req. and/or PS

railed to open or failed to close. S&T Re

External Leakage - The most common Frequent Not stated ASME Sec XI Not stated F-17 39

cases is a flange leak. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Frequent Not stated ASME Sec XI Not stated F-1 7 40

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-17 41

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Moderate Not stated ASME Sec Xl Not stated F-1 7 42

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec X1 Not stated F-17 43

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-1 8 44

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Fails to Open - Valve fails to open fully

when demanded.

Occasional Not stated ASME Sec Xl

IWV & PS TS

Req. and/or PS

S&T Re

Not stated F-i18 45
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 49A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

46 Service Water Pneumatic-Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

47 Service Water Pneumatic-Operated Not stated Not stated Not stated EMBR Loss of Fracture

System Valves Toughness

48 Service Water Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

49 Service Water Pneumatic-Operated Not stated Not stated Not stated CLOG Row Blockage

System Valves

50 Service Water Pneumatic-Operated Not stated Not stated Not stated DRIFT Set Point Drift

System Valves

51 Service Water Pneumatic-Operated Not stated Not stated Not stated VIBR Loosening

System Valves

52 Service Water Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

563 Service Water Pneumatic-Operated Not stated Not stated Not stated CORR Loss of Material

System Valves

54 Service Water Pneumatic-Operated Not stated Not stated Not stated VIBR Loosening

System Valves

55 Service Water Motor-Driven Pumps Not stated Not stated Not stated EMBR Loss of Fracture

System Toughness

56 Service Water Motor-Driven Pumps Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

57 Service Water Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

58 Service Water Motor-Driven Pumps Not stated Not stated Not stated CLOG Row Blockage

System

59 Service Water

System

Motor-Driven Pumps Not stated Not stated Not stated VIBR Loosening
Table A.1 Gall Report for NPAR Reports Page 49B

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL Effect of Aaina on Comaonent Funotion Contrib to Fnilure Renorted nrnas Relntroo• Renort Ret~nmn•nd•Hon• PeNn_ Item?

Fails to Open - Valve fails to open fully Infrequent Not stated ASME Sec Xl Not stated F-18 46

when demanded. IWV & PS TS

Req. and/or PS

S&T Re

Failure to Operate as Required - (a) a Rare Not stated ASME Sec Xl Not stated F-1i8 47

valve fails to meet specific requirements IWV & PS TS

such as stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re

Failure to Operate as Required - (a) a Frequent Not stated ASME Sec XI Not stated F-18 48

valve fails to meet specific requirements IWV & PS TS

such as stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re

Failure to Operate as Required - (a) a Rare Not stated ASME Sec XI Not stated F-18 49

valve fails to meet specific requirements IWV & PS TS

such as stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re

Failure to Operate as Required - (a) a Rare Not stated ASME Sec Xl Not stated F-18 50

valve fails to meet specific requirements IWV & PS TS

such as stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re

Failure to Operate as Required - (a) a Infrequent Not stated ASME Sec Xl Not stated F-18 51

valve fails to meet specific requirements IWV & PS TS

such as stroke time or (b) a valve loses Req. and/or PS

the ability to control system parameters. S&T Re I

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec Xl Not stated F-19 52

mode is used when the narrative lacks IWV & PS TS

specific information on whether the valve Req. and/or PS

failed to open or failed to close. S&T Re

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec Xl Not stated F-19 53

mode is used when the narrative lacks IWV & PS TS

specific information on whether the valve Req. and/or PS

failed to open or failed to close. S&T Re

Fails to Open/Fails to Close - This failure Infrequent Not stated ASME Sec Xl Not stated F-19 54

mode is used when the narrative lacks IWV & PS TS

specific information on whether the valve Req. and/or PS

failed to open or failed to close. S&T Re

External Leakage - The leakage failure Rare Not stated ASME Sec Xl Not stated F-19 55

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak.

External Leakage - The leakage failure Rare Not stated ASME Sec XI Not stated F-19 56

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak.

External Leakage - The leakage failure Frequent Not stated ASME Sec XI Not stated F-1 9 57

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak.

External Leakage - The leakage failure Moderate Not stated ASME Sec XI Not stated F-1 9 58

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak._

External Leakage -The leakage failure

mode describes a fault in which the pump

is operational, but is removed from service

because of excessive leakage of the

pumped medium. A common example of

this mode is a packing leak.

Infrequent Not stated ASME Sec Xl

IWP & PS TS

Req. and/or PS

S&T Re

Not stated IF-19 59
Table A.1 Gall Report for NPAR Reports Page 50A

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

60 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Inadequate

System Maintenance

Causes Accelerated

Aging

61 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Inadequate

System Operational

Procedures Causes

Accelerated Aging

62 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Construction Errors

System Cause Accelerated

Aging

63 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Construction

System Inadequacy Causes

Accelerated Aging

64 Service Water Motor-Driven Pumps Not stated Not stated Not stated BIO Buildup of

System Organisms

65 Service Water Motor-Driven Pumps Not stated Not stated Not stated ERO Wail Thinning

System

66 Service Water Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

67 Service Water Motor-Driven Pumps Not stated Not stated Not stated CORR Loss of Material

System

68 Service Water Motor-Driven Pumps Not stated Not stated Not stated ADH Movement Loss

System

69 Service Water Motor-Driven Pumps Not stated Not stated Not stated CLOG Row Blockage

System

70 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Improper Lubrication

System Causes Accelerated

Aging

71 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Insulation

System Breakdown Causes

Abnormal

Resistance

72 Service Water

System

Motor-Driven Pumps Not stated Not stated Not stated Not stated Open Circuit Causes

Abnormal

Resistance
Table A.1 Gall Report for NPAR Reports Page SOB

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL Effect of Aaina on Component Function Contrib to FailureReotdras elra eotRcmunendations Paae No. Item

ýExternal Leakage - The leakage failure Rare Not stated ASME Sec Xl Not stated F-19 60

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak.

External Leakage - The leakage failure Rare Not stated ASME Sec XI Not stated F-1 9 61

mode describes a fault in which the pump IWP & PS TS

is operational, but is removed from service Req. and/or PS

because of excessive leakage of the S&T Re

pumped medium. A common example of

this mode is a packing leak.

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-21 62

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fall to run to S&T Re

specifications.

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-21 63

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications. I

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-21 64

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Infrequent Not stated ASME Sec Xl Not stated F-21 65

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Frequent Not stated ASME Sec XI Not stated F-21 66

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Moderate Not stated ASME Sec XI Not stated F-21 67

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications. I

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-21 68

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Frequent Not stated ASME Sec XI Not stated F-21 69

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Occasional Not stated ASME Sec XI Not stated F-21 70

automatically or mznually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Infrequent Not stated ASME Sec XI Not stated F-21 71

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was automatically or manually tripped off-line

to prevent damage to the pump. It also

includes pumps that fail to run to

specifications.

Rare Not stated ASME Sec XI

IWP & PS TS

Req. and/or PS

S&T Re

Not stated F-21 72
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 51A

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

73 Service Water Motor-Driven Pumps Not stated Not stated Not stated VIBR Loosening

System

74 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Inadequate

System Maintenance

Causes Accelerated

Aging

75 Service Water Motor-Driven Pumps Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

76 Service Water Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

77 Service Water Motor-Driven Pumps Not stated Not stated Not stated CLOG Flow Blockage

System

78 Service Water Motor-Driven Pumps Not stated Not stated Not stated Not stated Current Over/Under

System Causes Degradation

of Equipment

79 Service Water Strainers Not stated Not stated Not stated WEAR Attrition

System

80 Service Water Strainers Not stated Not stated Not stated CORR Loss of Material

System

81 Service Water Strainers Not stated Not stated Not stated BIO Buildup or

System Organisms

82 Service Water Strainers Not stated Not stated Not stated CLOG Flow Blockage

System

83 Service Water Diesel Generator Not stated Not stated Not stated Not stated Design Inadequacy

System Causes Accelerated

Aging

84 Service Water Diesel Generator Not stated Not stated Not stated WEAR Attrition

System

85 Service Water Diesel Generator Not stated Not stated Not stated CONTAM Buildup of Deposits

System

86 Service Water Diesel Generator Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

87 Service Water

System

Diesel Generator Not stated Not stated Not stated EMBR Loss of Fracture

Toughness
Table A.1 Gall Report for NPAR Reports Page SIB

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aoina on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fails to Run - An operating pump was Occasional Not stated ASME Sec Xl Not stated F-21 73

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-21 74

automatically or manually tripped off-line IWP & PS TS

to prevent damage to the pump. It also Req. and/or PS

includes pumps that fail to run to S&T Re

specifications.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec Xl Not stated F-22 75

demand or which started and only IWP & PS TS

operated for a brief period of time before Req. and/or PS

tripping off-line. S&T Re

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-22 76

demand or which started and only IWP & PS TS

operated for a brief period of time before Req. and/or PS

tripping off-line. S&T Re I

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-22 77

demand or which started and only IWP & PS TS

operated for a brief period of time before Req. and/or PS

tripping off-line. S&T Re

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-22 78

demand or which started and only IWP & PS TS

operated for a brief period of time before Req. and/or PS

tripping off-line. S&T Re

Loss of Function - Inability to perform its Frequent Not stated PS TS Req & Not stated F-23 79

intended function. PS S&T Req.

Loss of Function - Inability to perform its Occasional Not stated PS TS Req., Not stated F-23 80

intended function. RG 1.9,& RG

1.108

Plugged - Plugging of Strainers Infrequent Not stated PS TS Req., Not stated F-23 81

RG 1.9,& RG

1.108

Plugged - Plugging of Strainers Moderate Not stated PS TS Req., Not stated F-23 82

RG 1.9,& RG

1.108

Fails to Start - Falls to start encompasses Infrequent Not stated PS TS Req., Not stated F-33 83

diesel generator failures that resulted from RG1.9,& RG

the diesel failing to start, failing to reach 1.108

rated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses Infrequent Not stated PS TS Req., Not stated F-33 84

diesel generator failures that resulted from RG 1.9,& RG

the diesel failing to start, failing to reach 1.108

rated speed and voltage once a start

sequence was initiated, and falling to

achieve expected loading (kW).

Fails to Start - Falls to start encompasses Infrequent Not stated PS TS Req., Not stated F-33 85

diesel generator failures that resulted from RG 1.9,& RG

the diesel failing to start, failing to reach 1.108

rated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses Rare Not stated PS TS Req., Not stated F-33 86

diesel generator failures that resulted from RG 1.9,& RG

the diesel failing to start, failing to reach 1.108

rated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Run - Failure to run is any failure

Df an operating diesel generator to supply

power to the emergency bus, given that

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Infrequent Not stated PS TS Req.,

RG 1.9,& RG

1.108

Not stated F-34 87
Table A.1 Gall Report for NPAR Reports Page 52A

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL Item SytmStructureJComD Subcombonent Materials Manufacturer ARD mechanism ARD effects

88 Service Water Diesel Generator Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

89 Service Water Diesel Generator Not stated Not stated Not stated WEAR Attrition

System

90 Service Water Diesel Generator Not stated Not stated Not stated ADH Loss of Movement

System

91 Service Water Diesel Generator Not stated Not stated Not stated CONTAM Buildup of Deposits

System

92 Service Water Diesel Generator Not stated Not stated Not stated Not stated Mechanical Overloac

System Causes Degradation

of Equipment

93 Service Water Diesel Generator Not stated Not stated Not stated DRIFT Set Point Drift

System

94 Service Water Diesel Generator Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

95 Service Water Diesel Generator Not stated Not stated Not stated Not stated Short Circuit Causes

System Abnormal

Resistance

96 Service Water Diesel Generator Not stated Not stated Not stated VIBR Loosening

System

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary Feedwater Check Valves Not stated Not stated Not stated ERO Wall Thinning

System

2 Au)dliaLy I-eedwater

System

Check Valves Not stated Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 52B

Document: NUREG/CR-4747, Vol. 1, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL Effect of Aaino on Combeonent Funntio~n COntrib tn Fniluirn RnnortL-d nvnn_• R~lInrnn_• g~nnrt R~enm, m•nd•finn• DJn N.n Item

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-34 88

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Frequent Not stated PS TS Req., Not stated F-34 89

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-34 90

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator. I

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-34 91

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-34 92

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Moderate Not stated PS TS Req., Not stated F-34 93

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-34 94

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-34 95

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-34 96

of an operating diesel generator to supply RG 1.9,& RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

External Leakage - The most common Rare Not stated ASME Sec Xl Not stated F-18

case is a flange leak. IWB or IWV,

PS TS Req. &

I_ _PS _ S&T R I

External Leakage -The most common case is a flange leak.

Frequent Not stated ASME Sec Xl

IWB or IWV,

PS TS Req. &

PS S&T R

Not stated F-18 2
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism

Page 53A

ARD effects

3 Auxiliary Feedwater Check Valves Not stated Not stated Not stated VIBR Loosening

System

4 Auxiliary Feedwater Check Valves Not stated Not stated Not stated Not stated Improper

System Maintenance

Causes Accelerated

___Aging

5 Auxiliary Feedwater Check Valves Not stated Not stated Not stated ADH Loss of Movement

System

6 Auxiliary Feedwater Check Valves Not stated Not stated Not stated CLOG Flow Blockage

System

7 Auxiliary Feeclwater Check Valves Not stated Not stated Not stated CONTAM Buildup of Deposits

System

8 Auxiliary Feedwater Check Valves Not stated Not stated Not stated VIBR Loosening

System

9 Auxiliary Feedwater Check Valves Not stated Not stated Not stated CONTAM Buildup of Deposits

System

10 Auxiliary Feedwater Check Valves Not stated Not stated Not stated ERO Wail Thinning

System

11 Auxiliary Feedwater Check Valves Not stated Not stated Not stated WEAR Attrition

System

12 Auxiliary Feedwater Check Valves Not stated Not stated Not stated CORR Loss of Material

System

13 Auxiliary Feedwater Check Valves Not stated Not stated Not stated CLOG Flow Blockage

System

14 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated CONTAM Buildup of Deposits

System

15 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated WEAR Attrition

System

16 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated VIBR Loosening

System

17 Auxiliary Feedwater Row Controllers Not stated Not stated Not stated CLOG Row Blockage

System

18 Auxiliary Feedwater Flow Controllers Not stated Not stated Not stated Not stated Out of Calibration

System Causes Loss of

Performance

19Auxiliary Feedwater

System

Flow Controllers Not stated Not stated Not stated Not stated Loss of Function

Due to Faulty

Electrical Module
Table A.1 Gall Report for NPAR Reports Page 53B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Renorted oroas Rel.oroas Report Recomrnendations Paae No. Item

External Leakage - The most common Rare Not stated ASME Sec Xl Not stated F-18 a

case is a flange leak. IWB or IWV,

PS TS Req. &

PS S&T R

External Leakage - The most common Rare Not stated ASME Sec XI Not stated F-18 4

case is a flange leak. IWB or IWV,

PS TS Req. &

PS S&T R

Fails to Open - Valve fails to open fully Infrequent Not stated ASME Sec XI Not stated F-18 5

when demanded. IWB or IWV,

PS TS Req. &

PS S&T R

Falls to Open - Valve fails to open fully Rare Not stated ASME Sec Xl Not stated F-18 6

when demanded. IWB or IWV,

PS TS Req. &

PS S&T R

Failure to Operate as Required - (a) a Moderate Not stated ASME Sec XI Not stated F-19 7

valve fails to meet specific requirements IWB or IWV,

such as stroke time or (b) a valve loses PS TS Req. &

the ability to control system parameters. PS S&T R

Failure to Operate as Required - (a) a Rare Not stated ASME Sec Xl Not stated F-19 8

valve fails to meet specific requirements IWB or IWV,

such as stroke time or (b) a valve loses PS TS Req. &

the ability to control system parameters. PS S&T R

Internal Leakage (Reverse Leakage) - Rare Not stated ASME Sec XI Not stated F-1 9 9

Reverse leakage is a failure mode used to IWB or IWV,

describe internal leakage through a check PS TS Req. &

valve. PS S&T R

Internal Leakage (Reverse Leakage) - Occasional Not stated ASME Sec XI Not stated F-19 10

Reverse leakage is a failure mode used to IWB or IWV,

describe internal leakage through a check PS TS Req. &

valve. PS S&T R

Internal Leakage (Reverse Leakage) - Frequent Not stated ASME Sec XI Not stated F-19 11

Reverse leakage is a failure mode used to IWB or IWV,

describe internal leakage through a check PS TS Req. &

valve. PS S&T R

Internal Leakage (Reverse Leakage) - Infrequent Not stated ASME Sec XI Not stated F-19 12

Reverse leakage is a failure mode used to IWB or IWV,

describe internal leakage through a check PS TS Req. &

valve. PS S&T R

Internal Leakage (Reverse Leakage) - Occasional Not stated ASME Sec Xl Not stated F-1 9 13

Reverse leakage is a failure mode used to IWB or IWV,

describe internal leakage through a check PS TS Req. &

valve. PS S&T R

Fails to Close. Rare Not stated If Class 1 E Not stated F-20 14

10CFR 50.49

otherwise PS

S&T Req.

Failure to Operate - The circuit breaker Occasional Not stated If Class 1 E Not stated F-20 15

does not function properly, either fails to IOCFR 50.49

open or fails to close on demand. otherwise PS

S&T Req.

Failure to Operate - The circuit breaker Rare Not stated If Class 1 E Not stated F-20 16

does not function properly, either fails to 1OCFR 50.49

open or fails to close on demand. otherwise PS

S&T Req.

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-21 17

erratic signals are produced by the 10CFR50.49

instrument. otherwise PS

"TS Req.

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-21 18

erratic signals are produced by the 10CFR50.49

instrument. otherwise PS

I_ _ ITS Req. II

Erroneous/Erratic Signals - Erroneous or

erratic signals are produced by the

instrument

Rare Not stated If Class 1E

10CFR50.49

otherwise PS

TS Req.

Not stated F-21 19
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 54A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

20 Auxdliary Feedwater Row Controllers Not stated Not stated Not stated Not stated Set Point Drift

System Causes Loss of

Function

21 Auxiliary Feedwater Row Controllers Not stated Not stated Not stated Not stated Electrical Failure

System Causes Loss of

Function

22 Auxiliary Feedwater Row Controllers Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

23 Auxiliary Feedwater Row Controllers Not stated Not stated Not stated Not stated Electrical Contact

System Failure Causes Loss

of Function

24 Auxiliary Feedwater Flow Control Not stated Not stated Not stated WEAR Attrition

System Recorders

25 Auxiliary Feedwater Row Control Not stated Not stated Not stated Not stated Out of Calibration

System Recorders Causes Loss of

Performance

26 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated CONTAM Buildup of Deposits

System

27 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated Not stated Set Point Drift

System Causes Loss of

Performance

28 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated Not stated Out of Calibration

System Causes Loss of

Performance

29 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

30 Auxiliary Feedwater Hand Control Valves Not stated Not stated Not stated WEAR Attrition

System

31 Auxiliary Feedwater Hand Control Valves Not stated Not stated Not stated WEAR Attrition

System

32 Auxiliary Feedwater Hand Control Valves Not stated Not stated Not stated CORR Loss of Material

System

33 Auxiliary Feedwater Hand Control Valves Not stated Not stated Not stated ERO Wall Thinning

System

34 Auxiliary Feedwater Hand Control Valves Not stated Not stated Not stated WEAR Attrition

System

35 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Out of Calibration

System Indicators Causes Loss of

Performance

36 Auxiliary Feedwater Level Control

System Indicators

Not stated Not stated Not stated Not stated Faulty Component

Causes Loss of

Performance
Table A.1 Gall Report for NPARReports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Acalin on Component Function Contrib to Failure Reeorted Droas Rel.proas Report Recommendations

Page 64B

Pane No. Item

Failure to Operate. Rare Not stated If Class 1 E Not stated F-21 20

10CFR50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-21 21

10CFR50.49

otherwise PS

TS Req. I

Failure to Operate. Infrequent Not stated If Class 1 E Not stated F-21 22

10CFR50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-21 23

10CFR50.49

otherwise PS

"TS Req.

Erroneous/Erratic Signals - Erroneous or. Infrequent Not stated If Class 1 E Not stated F-22 24

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

TS Req.

Erroneous/Erratic Signals - Erroneous or Occasional Not stated if Class 1 E Not stated F-22 25

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

_TS Req.

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-23 26

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

TS Req.

Erroneous/Erratic Signals - Erroneous or Infrequent Not stated If Class 1 E Not stated F-23 27

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

TS Req.

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-23 28

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

TS Req.

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-23 29

erratic signals are produced by the 10CFR50.49

instrument, otherwise PS

TS Req.

Failure to Operate. Frequent Not stated ASME Sec Xl Not stated F-23 30

IWB or IWV,

PS TS Req. &

PS S&T R I

External Leakage - The most common Occasional Not stated ASME Sec Xl Not stated F-24 31

case is a flange leak. IWB or IWV,

PS TS Req. &

PS S&T R

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-24 32

when demanded. IWB or IWV,

PS TS Req. &

PS S&T R

Failure to Operate as Required. Rare Not stated ASME Sec XI Not stated F-25 33

IWB or IWV,

PS TS Req. &

PS S&T R

Internal Leakage. Rare Not stated ASME Sec Xl Not stated F-25 34

IWB or IWV,

PS TS Req. &

PS S&T R

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-26 35

erratic signals are produced by the 1OCFR 50.49

instrument, otherwise PS

I__ I_ ITS Req. I

Erroneous/Erratic Signals - Erroneous or

Brratic signals are produced by the

instrument

Infrequent Not stated If Class 1E

1OCFR 50.49

otherwise PS

TS Req.

Not stated F-26
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD

Page 55A

mechanism ARD effects

37 Auxiliary Feedwater Level Control Not stated Not stated Not stated FAT Cumulative Fatigue

System Indicators Damage

38 Auxiliary Feedwater Level Control Not stated Not stated Not stated WEAR Attrition

System Indicators

39 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Faulty Component

System Indicators Causes Loss of

Performance

40 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated End of Life Electrical

System Indicators Failure

41 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Out of Caiibration

System Causes Loss of

Performance

42 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

43 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

44 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Faulty Component

System Causes Loss of

Performance

45 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

46 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated CONTAM Buildup of Deposits

System

47 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated Attrition Buildup of Deposits

System

48 Au)dliary Feedwater Motor Driven Pumps Not stated Not stated Not stated CLOG Flow Blockage

System

49 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated Not stated Poor Maintenance

System Causes Acceler atea

Aging

50 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

51 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

52 Auxiliary Feedwater

System

Motor Driven Pumps I Not stated Not stated Not stated CLOG Row Blockage
Table A.1 Gall Report for NPAR Reports Page 5513

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor'Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aqina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Failure to Operate. Rare Not stated If Class 1 E Not stated F-27 37

10CFR 50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-27 38

1OCFR 50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-27 39

1OCFR 50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-27 40

1OCFR 50.49

otherwise PS

TS Req. I

Erroneous/Erratic Signals - Erroneous or Rare Not stated If Class 1 E Not stated F-28 41

erratic signals are produced by the 10CFR 50.49

instrument. otherwise PS

TS Req.

Erroneous/Erratic Signals - Erroneous or Occasional Not stated If Class 1 E Not stated F-28 42

erratic signals are produced by the 1OCFR 50.49

instrument. otherwise PS

TS Reg.

Failure to Operate. Occasional Not stated If Class 1 E Not stated F-28 43

1OCFR 50.49

otherwise PS

TS Req.

Failure to Operate. Rare Not stated If Class 1 E Not stated F-28 44

1OCFR 50.49

otherwise PS

TS Req.

External Leakage - The leakage failure Occasional Not stated ASME Sec XI Not stated F-29 45

mode describes a fault in which the pump IWP, PS TS

is operational, but is removed from service Req & PS S&T

because of excessive leakage of the Req.

pumped medium. A common example of

this mode is a packing leak.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-29 46

demand or which started and only IWP, PS TS

operated for a brief period of time before Req & PS S&T

tripping off-line. Req.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec Xl Not stated F-29 47

demand or which started and only IWP, PS TS

operated for a brief period of time before Req & PS S&T

tripping off-line. Req.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec Xl Not stated F-29 48

demand or which started and only IWP, PS TS

operated for a brief period of time before Req & PS S&T

tripping off-line. Reg. I

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec Xl Not stated F-29 49

demand or which started and only IWP, PS TS

operated for a brief period of time before Req & PS S&T tripping off-line. Req.

Fails to Run - An operating pump was Infrequent Not stated ASME Sec Xl Not stated F-30 50

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Run - An operating pump was Frequent Not stated ASME Sec Xl Not stated F-30 51

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Run - An operating pump was automatically or manually tripped off-line

to prevent damage to the pump. It also

includes pumps that fail to run to

specifications.

Rare Not stated ASME Sec XI

IWP, PS TS

Req & PS S&T

Req.

Not stated F-30
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 56A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

53 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated Not stated Set Point Drift Loss

System of Function

54 Auxiliary Feedwater Motor Driven Pumps Not stated Not stated Not stated Not stated Improper Lubrication

System Causes Accelerated

Aging

55 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

56 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated ERO Wall Thinning

System Valves

57 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

58 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated CORR Loss of Material

System Valves

59 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

60 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated CLOG Row Blockage

System Valves

61 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated Not stated Improper Lubrication

System Valves Causes Accelerated

Aging

62 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

63 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated ERO Wall Thinning

System Valves

64 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

65 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

66 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

67 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

68 Auxiliary Fedwater

System

Motor-Operated

Valves

Not stated Not stated Not stated CONTAM Buildup of Deposits
Table A.1 Gall Report for NPAR Reports Page 56B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fails to Run - An operating pump was Infrequent Not stated ASME Sec XI Not stated F-30 53

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Run -An operating pump was Rare Not stated ASME Sec XI Not stated F-30 54

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Extemal Leakage -The most common Rare Not stated ASME Sec Xl Not stated F-30 55 cause is flange leak. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Close - Valve fails to close fully Frequent Not stated ASME Sec XI Not stated F-31 56

when demanded. IWV, PS TS

Req, GL 89-10

_& Suppl.

Fails to Close -Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-31 57

when demanded. IWV, PS TS

Req, GL 89-10

& suppl.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec XI Not stated F-31 58

when demanded. IWV, PS TS

Req, G L 89-10

& Suppl.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec Xl Not stated F-31 59

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec Xl Not stated F-31 60

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec X1 Not stated F-31 61

when demanded. IWV, PS TS

Req, G L 89-10

& Suppl.

Fails to Open - Valve Fails to open fully Moderate Not stated ASME Sec XI Not stated F-32 62

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Failure to Operate as required - (a) valve Rare Not stated ASME Sec XlI Not stated F-32 63

fails to meet specific requirements such IWV, PS TS as stroke time or (b) a valve loses the Req, GL 89-10

ability to control system parameters. & Suppl.

Failure to Operate as required - (a) valve Rare Not stated ASME Sec XI Not stated F-32 64

fails to meet specific requirements such IWV, PS TS as stroke time or (b) a valve loses the Req, GL 89-10

ability to control system parameters. & Supp l.

Fails to Open/Fails to Close -This failure Infrequent Not stated ASME Sec XI Not stated F-33 65

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, G L 89-10

failed to open or failed to close. & Suppl.

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec XI Not stated F-33 66

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, GL 89-10

failed to open or failed to close. & Suppl.

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec Xl Not stated F-33 67

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, GL 89-10

failed to open or failed to close. & Suppl.

Erroneous/Erratic Signals. Rare Not stated ASME Sec Xl

IWV, PS TS

Req, GL 89-10

& Suppl.

Not stated F-33 68
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 57A

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

69 Auxiliary Fedwater Motor-Operated Not stated Not stated Not stated Not stated Out of Calibration

System Valves Causes Loss of

Performance

70 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

71 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated ERO Wall Thinning

System Valves

72 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated FAT Cumulative Fatigue

System Valves Damage

73 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

74 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

75 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated CLOG Flow Blockage

System Valves

76 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated Not stated Human Error

System Valves Causes Accelerated

Aging

77 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated FAT Cumulative Fatigue

System Valves Damage

78 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

79 Auxiliary Fedwater Pneumatic-Operated Not stated Not stated Not stated ADH Loss of Movement

System Valves

80 Auxiliary Feedwater Pneumatic-Operated Not stated Not stated Not stated CLOG Row Blockage

System Valves

81 Auxiliary Feedwater Pneumatic-Operated Not stated Not stated Not stated Not stated Water Intrusion

System Valves Causes Accelerated

Aging

82 Auxiliary Feedwater Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

83 Auxiliary Feedwater Pneumatic-Operated Not stated Not stated Not stated Not stated Improper Lubrication

System Valves Causes Accelerated

Aging

84 Auxiliary Feedwater Pneumatic-Operated Not stated Not stated Not stated FAT Cumulative Fatigue

System Valves Damage

No stte WEA AttrIto BEAuxiliary Feedwater Pneumatic-Operated

System Valves

Not stated Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 57B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.progs Report Recommendations Page No. Item

Erroneous/Erratic Signals. Infrequent Not stated ASME Sec XI Not stated F-33 69

IWV, PS TS

Req, G L 89-10

& Suppl.

External Leakage. Frequent Not stated ASME Sec Xl Not stated F-35 70

IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Moderate Not stated ASME Sec XI Not stated F-35 71

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec Xl Not stated F-35 72

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Frequent Not stated ASME Sec Xl Not stated F-35 73

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Moderate Not stated ASME Sec Xl Not stated F-35 74

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec Xl Not stated F-35 75

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec XI Not stated F-35 76

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Occasional Not stated ASME Sec XI Not stated F-36 77

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Frequent Not stated ASME Sec XI Not stated F-36 78

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Infrequent Not stated ASME Sec Xl Not stated F-36 79

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-36 80

when demanded. IWV, PS TS

Req, & PS

S&T Req. I

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec Xl Not stated F-36 81

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Failure to Operate as Required - (a) A Frequent Not stated ASME Sec Xl Not stated F-36 82

valve fails to meet specific requirements IWV, PS TS

such as a stroke time or (b) a valve loses Req, & PS

the ability to control system parameters. S&T Req.

Failure to Operate as Required - (a) A Infrequent Not stated ASME Sec Xl Not stated F-36 83

valve fails to meet specific requirements IWV, PS TS

such as a stroke time or (b) a valve loses Req, & PS

the ability to control system parameters. _S&T Req.

Fails to Open/Fails to Close - This failure Rare Not stated ASME Sec Xl Not stated F-36 84

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, & PS

failed to open or failed to close. I I S&T Req. _ _

Fails to Open/Fails to Close - This failure

mode is used when the narrative lacks

specific information on whether the valve

failed to open or failed to close.

Infrequent Not stated ASME Sec Xl

IWV, PS TS

Req, & PS

S&T Req.

Not stated F-36 8!;
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 58A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

86 Au)dliary Feedwater Pressure Switches Not stated Not stated Not stated CONTAM Buildup of Deposits

System

87 Auxiliary Feedwater Pressure Switches Not stated Not stated Not stated Not stated Out of Calibration

System Causes Loss of

Performance

88 Auxiliary Feedwater Pressure Switches Not stated Not stated Not stated WEAR Attrition

System

89 Auxiliary Feedwater Pressure Switches Not stated Not stated Not stated CORR Loss of Material

System

90 Auxiliary Feedwater Pressure Switches Not stated Not stated Not stated Not stated Electrical Arcing

System Causes Loss of

I I_ Function

91 Auxiliary Feedwater Pressure Not stated Not stated Not stated Not stated Out of Calibration

System Transmitter Causes Loss of

Performance

92 Auxiliary Feedwater Pressure Not stated Not stated Not stated WEAR Attrition

System Transmitter

93 Auxiliary Feedwater Pressure Not stated Not stated Not stated Not stated Electrical Open

System Transmitter Circuit Causes

Abnormal

Resistance

94 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition

System

95 Auxiliary Feedwater Relays Not stated Not stated Not stated Not stated Set Point Drift

System Causes Loss of

Function

96 Auxiliary Feedwater Relays Not stated Not stated Not stated Not stated End of Life Electrical

System Failure Causes

Accelerated Aging

97 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition

System

98 Auxiliary Feedwater Relief Valves Not stated Not stated Not stated WEAR Attrition

System

99 Auxiliary Feedwater Relief Valves Not stated Not stated Not stated CONTAM Buildup of Deposits

System

100 Auxiliary Feedwater Relief Valves Not stated Not stated Not stated Not stated Set Point Drift

System Causes Loss of

Function

101 Auxiliary Feedwater Snubbers Not stated Not stated Not stated WEAR Attrition

System

102 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated WEAR Attrition

System Pump

103 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated FAT Cumulative Fatigue

System Pump Damage

104 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated WEAR Attrition

System Pump

105~Auiliary F-eedwater

System

T urDine-nriven

Pump

Not stated Not stated Not stated CLOG Flow Blockage
Table A.1 Gall Report for NPAR Reports Page 58B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recomnnendabons Page No. Item

Erroneous/Erratic Signals - Erroneous or Rare Not stated PS TS Req, & Not stated F-38 86

erratic signals are produced by the PS S&T Req.

instrument.

Erroneous/Erratic Signals - Erroneous or Moderate Not stated PS TS Req, & Not stated F-38 87

erratic signals are produced by the PS S&T Req.

instrument.

Failure to Operate. Rare Not stated PS TS Req, & Not stated F-38 88

PS S&T Req.

Failure to Operate. Infrequent Not stated PS TS Req, & Not stated F-38 89

PS S&T Req.

Failure to Operate. Rare Not stated PS TS Req, & Not stated F-38 90

PS S&T Req.

Erroneous/Erratic Signals - Erroneous or Occasional Not stated PS TS Req, & Not stated F-39 91

erratic signals are produced by the PS S&T Req.

instrument.

Failure to Operate. Rare Not stated PS TS Req, & Not stated F-39 92

PS S&T Req.

Failure to Operate. Rare Not stated PS TS Req, & Not stated F-39 93

PS S&T Req.

Fails to Open - Failure of a normally Rare Not stated PS TS Req, & Not stated F-40 94

closed relay to open upon demand. PS S&T Req.

Fails to Open - Failure of a normally Rare Not stated PS TS Req, & Not stated F-40 95

closed relay to open upon demand. PS S&T Req.

Failure to Operate. Rare Not stated PS TS Req, & Not stated F-40 96

PS S&T Req.

Failure to Operate. Infrequent Not stated PS TS Req, & Not stated F-40 97

PS S&T Req.

Fails to Open - Failure of the relay to Rare Not stated ASME Sec Xl Not stated F-40 98

operate due to lack of an input signal. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Failure of the relay to Rare Not stated ASME Sec Xl Not stated F-42 99

operate due to lack of an input signal. IWV, PS TS

Req, & PS

S&T Req.

Premature Open - A typical example is the Rare Not stated ASME Sec Xl Not stated F-42 100

relief valve opening prior to its pressure IWV, PS TS

setting. Req, & PS

S&T Req.

External Leakage - The leakage failure Frequent Not stated ASME Sec XI Not stated F-45 101

mode describes a fault in which the pump ISTD

is operational, but is removed from service

because of excessive leakage of the

pumped medium. A common example of

this mode is a packing leak.

External Leakage - The leakage failure Infrequent Not stated ASME Sec Xl Not stated F-45 102

mode describes a fault in which the pump IWP, PS TS

is operational, but is removed from service Req & PS S&T

because of excessive leakage of the Req.

pumped medium. A common example of

this mode is a packing leak.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-45 103

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. Re__

Fails to Start - Pumps did not start upon Infrequent Not stated ASME Sec XI Not stated F-45 104

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. 1 Req. I

Fails to Start - Pumps did not start upon

demand or which started and only opened

for a brief period of time before tripping

off-line.

Infrequent Not stated ASME Sec XI

IWP, PS TS

Req & PS S&T

Req.

Not stated F-45 105
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 59A

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

106 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated CORR Loss of Material

System Pump

107 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated ADH Loss of Movement

System Pump

108 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated CLOG Flow Blockage

System Pump

109 Auxiliary Feedwater Turbine-Driven Not stated Not stated Not stated VIBR Loosening

System Pump

110 Auxiliary Feedwater Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

111 Auxiliary Feedwater Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

System

112 Auxiliary Feedwater Motor-Driven Pumps Not stated Not stated Not stated CLOG Row Blockage

System

113 Auxiliary Feedwater Motor-Driven Pumps Not stated Not stated Not stated VIBR Loosening

System

114 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated WEAR Attrition

System Valves

115 Auxiliary Feedwater Motor-Operated Not stated Not stated Not stated CORR Loss of Material

System Valves

116 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated Design Error

System Causes Accelerated

Aging

117 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated WEAR Attrition

System

118 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated CONTAM Buildup of Deposits

System

11s Auxiliary l-eeclwater

System

Diesel Generator Not stated Not stated Not stated DRIFT Set Point Drift

Causes Loss of

Performance
Table A.1 Gall Report for NPAR Reports Page 59B

Document. NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported Droas Rel.proqs Report Recommendations Page No. Item

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec XI Not stated F-45 106

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. Req.

Fails to Start - Pumps did not start upon Rare Not stated ASME Sec Xl Not stated F-45 107

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. Req.

Fails to Start - Pumps did not start upon Infrequent Not stated ASME Sec XI Not stated F-45 108

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. Req.

Fails to Start - Pumps did not start upon Occasional Not stated ASME Sec Xl Not stated F-45 109

demand or which started and only opened IWP, PS TS

for a brief period of time before tripping Req & PS S&T

off-line. Req.

External Leakage - The leakage failure Frequent Not stated ASME Sec Xl Not stated F-51 110

mode describes a fault in which the pump IWP, PS TS

is operational, but is removed from service Req & PS S&T

because of excessive leakage of the Req.

pumped medium. A common example of

this mode is a packing leak.

Fails to Run - An operating pump was Frequent Not stated ASME Sec Xl Not stated F-51 111

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-51 112

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Run - An operating pump was Rare Not stated ASME Sec Xl Not stated F-51 113

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications. I

External Leakage - The most common Frequent Not stated ASME Sec Xl Not stated F-53 114

case is a flange leak. IWV, PS TS

Req, GL 89-10

& suppl.

External Leakage - The most common Frequent Not stated ASME Sec Xl Not stated F-53 115

case is a flange leak. IWV, PS TS

Req, G L 89-10

& Suppl.

Fails to Start - Fails to start encompasses Infrequent Not stated PS TS Req., Not stated F-59 116

diesel generator failures that resulted from RG 1.9, RG

the diesel failing to start, failing to reach 1.108

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses Infrequent Not stated PS TS Req., Not stated F-59 117

diesel generator failures that resulted from RG 1.9, RG

the diesel failing to start, failing to reach 1.108

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses Infrequent Not stated PS TS Req., Not stated F-59 118

diesel generator failures that resulted from RG 1.9, RG

the diesel failing to start, failing to reach 1.108

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses

diesel generator failures that resulted from

the diesel failing to start, failing to reach

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Rare Not stated PS TS Req.,

RG 1.9, RG

1.108

Not stated F-59 1 is
Table A.1 Gall Report for NPAR Reports Page 60A

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/Como Subcomoonent Materials Manufacturer ARD mechanism ARD effects

Item120 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated Loss of Performance

System due to Faulty

Electrical Module

121 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated Electrical Short

System Circuit Causes

Abnormal

Resistance

122 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated EMBR Loss of Fracture

System Toughness

123 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated FAT Cumulative Fatigue

System Damage

124 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated WEAR Attrition

System

125 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated ADH Loss of Movement

System

126 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated CONTAM Buildup of Deposits

System

127 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated Improper Lubrication

System Causes Acceleration

of Aging

128 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated DRIFT Set Point Drift

System Causes Loss of

Performance

129 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated Loss of Performance

System due to Faulty

Electrical Module

130 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated VIBR Loosening

System

131 High Pressure

Safety Injection

System

Check Valves Not stated Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 60B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aqinl on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Fails to Start - Fails to start encompasses Rare Not stated PS TS Req., Not stated F-59 120

diesel generator failures that resulted from RG 1.9, RG

the diesel failing to start, failing to reach 1.108

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Start - Fails to start encompasses Infrequent Not stated PS TS Req., Not stated F-59 121

diesel generator failures that resulted from RG 1.9, RG

the diesel failing to start, failing to reach 1.108

stated speed and voltage once a start

sequence was initiated, and failing to

achieve expected loading (kW).

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-60 122

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-60 123

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Frequent Not stated PS TS Req., Not stated F-60 124

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-60 125

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-60 126

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-60 127

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Occasional Not stated PS TS Req., Not stated F-60 128

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Infrequent Not stated PS TS Req., Not stated F-60 129

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

Fails to Run - Failure to run is any failure Rare Not stated PS TS Req., Not stated F-60 130

of an operating diesel generator to supply RG 1.9, RG

power to the emergency bus, given that 1.108

the diesel generator had undergone a

successful start. It also includes the

spurious stopping of the diesel generator.

External Leakage - The most common case is a flange leak.Infrequent Not stated ASME Sec X!

IWV, PS TS

Req, & PS

S&T Req.

Not stated F-63 131
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Page 61A

Reviewed by: David C. Ma, ANL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

132 High Pressure Check Valves Not stated Not stated Not stated CONTAM Buildup of Deposits

Safety Injection

System

133 High Pressure Check Valves Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

134 High Pressure Check Valves Not stated Not stated Not stated ADH Loss of Movement

Safety Injection

System

135 High Pressure Check Valves Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection

System

136 High Pressure Flow Transmitters Not stated Not stated Not stated Not stated Materials Defect

Safety Injection Causes Accelerated

System Aging

137 High Pressure Flow Transmitters Not stated Not stated Not stated Not stated Out of Calibration

Safety Injection Causes Loss of

System Performance

138 High Pressure Flow Transmitters Not stated Not stated Not stated FAT Cumulative Fatigue

Safety Injection Damage

System

139 High Pressure Flow Transmitters Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

140 High Pressure Hand Control Valves Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

141 High Pressure Hand Control Valves Not stated Not stated Not stated CORR Loss of Material

Safety Injection

System

142 High Pressure Hand Control Valves Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection

System

143 High Pressure Hand Control Valves Not stated Not stated Not stated Not stated Improper Lubrication

Safety Injection Causes Accelerated

System Aging

144 High Pressure Hand Control Valves Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection

System

145 High Pressure Hand Control Valves Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

146 High Pressure Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

147 High Pressure Motor-Driven Pumps Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

148 High Pressure

Safety Injection

System

Motor-Unven Pumps, Not stated Not stated Not stated CLOG Flow Blockage
Table A.1 Gall Report for NPAR Reports Page 61B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Internal Leakage - (reverse leakage) - Rare Not stated ASME Sec X1 Not stated F-62 132

Reverse leakage is a failure mode used to IWV, PS TS

describe internal leakage though a check Req, & PS

valve. S&T Req.

Internal Leakage - (reverse leakage) - Frequent Not stated ASME Sec Xl Not stated F-62 133

Reverse leakage is a failure mode used to IWV, PS TS

describe internal leakage though a check Req, & PS

valve. S&T Req. I

Internal Leakage - (reverse leakage) - Rare Not stated ASME Sec XI Not stated F-62 134

Reverse leakage is a failure mode used to IWV, PS TS

describe internal leakage though a check Req, & PS

valve. S&T Req.

Internal Leakage - (reverse leakage) - Infrequent Not stated ASME Sec Xl Not stated F-62 135

Reverse leakage is a failure mode used to IWV, PS TS

describe internal leakage though a check Req, & PS

valve. S&T Req. I

Erroneous/Erratic Signals - Erroneous or Rare Not stated PS S&T Req. Not stated F-67 136

erratic signals are produced by the

instrument.

Erroneous/Erratic Signals - Erroneous or Occasional Not stated PS S&T Req. Not stated F-67 137

erratic signals are produced by the

instrument.

Failure to Operate. Rare Not stated PS S&T Req. Not stated F-67 138

Failure to Operate. Infrequent Not stated PS S&T Req. Not stated F-67 139

External Leakage - The most common Infrequent Not stated ASME Sec XI Not stated F-68 140

rase is a flange leak. IWV, PS TS

Req, & PS

S&T Req.

External Leakage - The most common Rare Not stated ASME Sec XI Not stated F-68 141

rase is a flange leak. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec Xl Not stated F-69 142

Nhen demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-69 143

Nhen demanded. IWV, PS TS

Req, & PS

S&T Req. I

Failure to Operate as Required. Rare Not stated ASME Sec XI Not stated F-69 144

IWV, PS TS

Req, & PS

S&T Req.

Failure to Operate as Required. Rare Not stated ASME Sec XI Not stated F-69 145

IWV, PS TS

Req, & PS

S&T Req.

External Leakage - The leakage failure Infrequent Not stated ASME Sec Xl Not stated F-74 146

mode describes a fault in which the pump IWP, PS TS

is operational, but is removed from service Req & PS S&T

because of excessive leakage of the Req.

pumped medium. A common example of

this mode is a packing leak.

Fails to Run - An operating pump was Occasional Not stated ASME Sec XI Not stated F-75 147

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications.

Fails to Hun - An operating pump was automatically or manually tripped off-line

to prevent damage to the pump. It also

includes pumps that fail to run to

specifications.

Rare Not stated ASME Sec XI

IWP, PS TS

Req & PS S&T

Req.

Not stated F-75 148
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Page 62A

Item System Structure/Como Subcomponent Materials Manufacturer ARD mechanism ARD effects

149 High Pressure Motor-Driven Pumps Not stated Not stated Not stated Not stated Poor Maintenance

Safety Injection Causes Accelerated

System Aging

150 High Pressure Motor-Driven Pumps Not stated Not stated Not stated Not stated Failure to Follow

Safety Injection Procedures Causes

System Accelerated Aging

151 High Pressure Motor-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

152 High Pressure Motor-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

153 High Pressure Motor-Operated Not stated Not stated Not stated ADH Loss of Movement

Safety Injection Valves

System

154 High Pressure Motor-Operated Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection Valves

System

155 High Pressure Motor-Operated Not stated Not stated Not stated FAT Cumulative Fracture

Safety Injection Valves Damage

System

156 High Pressure Motor-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

157 High Pressure Motor-Operated Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection Valves

System

158 High Pressure Motor-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

159 High Pressure Motor-Operated Not stated Not stated Not stated VIBR Loosening

Safety Injection Valves

System

160 High Pressure Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

161 High Pressure Pneumatic-Operated Not stated Not stated Not stated CORR Loss of Material

Safety Injection Valves

System

162 High Pressure Pneumatic-Operated Not stated Not stated Not stated ADH Loss of Movement

Safety Injection Valves

System

163 High Pressure Pneumatic-Operated Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection Valves

System

1014

Safety Injection

System

Valves INIoL MLiWUM Not;) S!.M[• INO' staawu VVC/r-l. - ,urirlon
Table A.1 Gall Report for NPAR Reports Page 62B

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Droas Rel.proqs Report Recommendations Page No. Item

Fails to Run - An operating pump was Rare Not stated ASME Sec Xl Not stated F-75 149

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fall to run to Req.

specifications.

Fails to Run - An operating pump was Rare Not stated ASME Sec XI Not stated F-75 150

automatically or manually tripped off-line IWP, PS TS

to prevent damage to the pump. It also Req & PS S&T

includes pumps that fail to run to Req.

specifications. I

External Leakage - The most common Frequent Not stated ASME Sec XI Not stated F-76 151

case if a flange leak. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Close - Valve fails to close fully Occasional Not stated ASME Sec XI Not stated F-76 152

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec XI Not stated F-76 153

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl. 

Falls to Close -Valve fails to close fully Infrequent Not stated ASME Sec XI Not I stated F-76 154

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec X1 Not stated F-77 155

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Falls to Open - Valve fails to open fully Infrequent Not stated ASME Sec Xl Not stated F-77 156

when demanded. IWV, PS TS

Req, G L 89-10

& Suppl.

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec XI Not stated F-77 157

when demanded. IWV, PS TS

Req, GL 89-10

& Suppl.

Fails to Operate as Required - (a) a valve Occasional Not stated ASME Sec XI Not stated F-77 158

falls to meet specific requirements such IWV, PS TS as a stroke time or (b) a valve loses the Req, GL 89-10

ability to control system parameters. & Suppl.

Falls to Operate as Required - (a) a valve Rare Not stated ASME Sec XI Not stated F-77 159

fails to meet specific requirements such IWV, PS TS as a stroke time or (b) a valve loses the Req, GL 89-10

ability to control system parameters. & Suppl.

Fails to Open/Falls to Close - This failure Frequent Not stated ASME Sec XI Not stated F-78 160

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, & PS

failed to open or failed to close. S&T Req.

Fails to Open/Falls to Close - This failure Rare Not stated ASME Sec Xl Not stated F-78 161

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, & PS

failed to open or failed to close. S&T Req.

Fails to Open/Falls to Close - This failure Rare Not stated ASME Sec XI Not stated F-78 162

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, & PS

failed to open or failed to close. I S&T Req. I

Fails to Open/Falls to Close - This failure Occasional Not stated ASME Sec XI Not stated F-78 163

mode is used when the narrative lacks IWV, PS TS

specific Information on whether the valve Req, & PS

failed to open or failed to close. S&T Req.

External Leakage - The most common case is a flange leak.

Rare Not stated ASME Sec XI

IWV, PS TS

Req, & PS

S&T Req.

Not stated F-79 164
Table A.1 Gall Report for NPAR Reports Page 63A

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

165 High Pressure Pneumatic-Operated Not stated Not stated Not stated WEAR Attrition

Safety Injection Valves

System

166 High Pressure Pneumatic-Operated Not stated Not stated Not stated Not stated Coil Burnout Failure

Safety Injection Valves

System

167 High Pressure Pneumatic-Operated Not stated Not stated Not stated ERO Wall Thinning

Safety Injection Valves

System

168 High Pressure Pneumatic-Operated Not stated Not stated Not stated FAT Cumulative Fatigue

Safety Injection Valves Damage

System

169 High Pressure Relief Valve Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

170 High Pressure Relief Valve Not stated Not stated Not stated CORR Loss of Material

Safety Injection

System

171 High Pressure Relief Valve Not stated Not stated Not stated CLOG Flow Blockage

Safety Injection

System

172 High Pressure Relief Valve Not stated Not stated Not stated CLOG Row Blockage

Safety Injection

System

173 High Pressure Relief Valve Not stated Not stated Not stated Not stated Set Point Drift

Safety Injection Causes Loss of

System Performance

174 High Pressure Relief Valve Not stated Not stated Not stated Not stated Set Point Drift

Safety Injection Causes Loss of

System Performance

175 High Pressure Relief Valve Not stated Not stated Not stated Not stated Poor Maintenance

Safety Injection Causes Accelerated

System Aging

176 High Pressure Snubbers Not stated Not stated Not stated WEAR Attrition

Safety Injection

System

177 High Pressure Snubbers Not stated Not stated Not stated ELE-TEMP Material Degradation

Safety Injection

System

178 High Pressure Snubbers Not stated Not stated Not stated Not stated Poor Maintenance

Safety Injection Causes Accelerated

System Aging

Document: NUREG/CR-4769, Risk Evaluations of Aging Phenomena in Linear Aging Reliability Model and Its Extensions

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Various reactor

safety systems,

including trip and

safety features

actuation systems,

Class 1 E electrical

power distribution

systems, service

water system, and

coolant injection

systems.

Various, including

piping, pipe

supports,

bistables/switches,

indicators,

recorders,

conductors, relays,

valves, controllers,

circuit breakers,

motors, pumps,

valve operators, and

heat exchangers.

This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-4747, Vol. 2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components

Reviewed by: David C. Ma, ANL

Effect of Acina on ComDonent Function Contrib to Failure Reported proas Rel.proas Report Recomr

Page 63B

nendations Paae No. Item

Fails to Close - Valve fails to close fully Occasional Not stated AsME Sec Xl Not stated F-79 165

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Rare Not stated ASME Sec Xl Not stated F-80 166

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Internal Leakage. Rare Not stated ASME Sec Xl Not stated F-80 167

IWV, PS TS

Req, & PS

S&T Req.

Fails to Open/Fails to Close -this failure Infrequent Not stated ASME Sec Xl Not stated F-81 168

mode is used when the narrative lacks IWV, PS TS

specific information on whether the valve Req, & PS

failed to open or failed to close. S&T Req.

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec Xl Not stated F-83 169

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Rare Not stated ASME Sec Xl Not stated F-83 170

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Close - Valve fails to close fully Infrequent Not stated ASME Sec Xl Not stated F-83 171

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open -Valve fails to open fully Infrequent Not stated ASME Sec XI Not stated F-83 172

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Fails to Open - Valve fails to open fully Frequent Not stated ASME Sec XI Not stated F-83 173

when demanded. IWV, PS TS

Req, & PS

S&T Req.

Premature Open - A typical example is the Infrequent Not stated ASME Sec XI Not stated F-84 174

relief valve opening prior to its pressure IWV, PS TS

setting. Req, & PS

__S&T Req.

Premature Open - A typical example is the Rare Not stated ASME Sec XI Not stated F-84 175

relief valve opening prior to its pressure IWV, PS TS

setting. Req, & PS

_S&T Req.

Loss of Function. Infrequent Not stated ASME Sec XI Not stated F-85 176

ISTD

Loss of Function. Frequent Not stated ASME Sec XI Not stated F-85 177

ISTD

Loss of Function. Infrequent Not stated ASME Sec XI Not stated F-85 178

ISTD

Document: NUREG/CR-4769, Risk Evaluations of Aging Phenomena in Linear Aging Reliability Model and Its Extensions

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1
Table A.1 Gall Report for NPAR Reports Page 64A

Document: NUREG/CR-4769, Risk Evaluations of Aging Phenomena in Linear Aging Reliability Model and Its Extensions

Reviewed by: Jeffrey L. Binder, ANL

Item System StructureaComp Subcomponent Materials Manufacturer ARD mechanism

Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems

Reviewed by: Steve U. Choi, ANL

Item System Structure[Como Suboomoonent Materials Manufacturer ARD mechanism

ARD effects

ARD effects

PWR high pressure Piping Thermal sleeves and Not stated Not stated FAT/THERM Cumulative fatigue

injection system nozzles damage

2 PWR high pressure Piping Elbows Not stated Not stated FAT/THERM Cumulative fatigue

injection system damage

3 PWR high pressure Piping Pipe Stainless steel Not stated FAT Cumulative fatigue

injection system damage

4 PWR high pressure Piping Pipe Stainless steel Not stated CORR/SCC Crack initiation and

injection system growth

5 PWR high pressure Piping Pipe welds and Not stated Not stated VIBR Crack initiation and

injection system flanges growth, loosening

6 PWR high pressure Piping Pipe welds Type 304 SS Not stated CORR/SCC Crack initiation and

injection system growth

7 PWR high pressure Piping Nozzles, safe ends, Ferritic (carbon) Not stated CORR Crack initiation and

injection system and threaded steel growth

fasteners

8 PWR high pressure Valves Stem, packing, and Not stated Not stated CLOG Blockage of flow

injection system body passages

9 PWR high pressure Valves Packing, seat, and Not stated Not stated WEAR Attrition

injection system disk

10 PWR high pressure Valves Packing, seat, and Not stated Not stated CONTAM Buildup of deposits

. injection system disk

11 PWR high pressure Pumps Impeller blades Types 304 and 316 Not stated CORR/MIC Loss of material;

injection system SS corrosion product

I_ buildup

12 PWR high pressure Instrumentation and Switches and relays Not stated Not stated WEAR Attrition

injection system controls

13 PWR high pressure Instrumentation and Contacts Not stated Not stated CORR Corrosion product

injection system controls buildup

14 PWR high pressure Instrumentation and Insulation Not stated Not stated FAT/THERM Cumulative fatigue

injection system controls damage

Document: NUREG/CR-4977, Vol. 1, SHAG Test Series: Seismic Research on an Aged United States Gate Valve and on a Piping System in the Decommissionec

Reviewed by: David C. Ma, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Motor Operated Torque Switch Not stated Umitorque Corp. RATCH Change in

Gate Valve Helical Spring (SMA dimension

Type)
Table A.1 Gall Report for NPAR Reports Page 64B

Document: NUREG/CR-4769, Risk Evaluations of Aging Phenomena in Linear Aging Reliability Model and Its Extensions

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Paae No. Item

Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems

Reviewed by: Steve U. Choi, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.Iroas Reoort Recommendations

High-pressure injection/makeup nozzles Not stated Not discussed in ASME Sec Ill & Not stated 29, 30, 1

have developed through-wall cracks due report Sec XI IWB 33, 36, 53

to thermal fatigue. All cracks were

associated with loose thermal sleeves. 33

Elbows in the safety injection piping Not stated Not discussed in ASME Sec XI Not stated 332

between the cold leg and the first check report IWB

valve have developed through-wall cracks.

Cracks or through-wall leakage. Not stated Not discussed in ASME Sec Xl Not stated 30, 36 3

report IWB

Cracking was discovered in some safety Not stated Not discussed in ASME Sec XI Not stated 30 4

system pipes containing borated water, report IWB

but no losses due to this problem were

reported.

Cracks have occurred due to vibration and Not stated Not discussed in ASME Sec XI Not stated 30 5

dynamic loading (water hammer). report IWB

Cracks occur in the weld heat affected Not stated Not discussed in ASME Sec XI Not stated 30, 53, H- 6

zone. report IWB 3

Not stated. Not stated Not discussed in ASME Sec XI Not stated 53, H-3 7

report IWB

MOVs and check valves have failed to Not stated Not discussed in ASME Sec XI Not stated 30,33, 8

operate due to boron crystallization on the report IWV 53, H-3

valve stems and in the valve packing and

body. Boric acid crystals have caused

blockage, resulting in malfunction of an

HPI pump in one instance.

Leakage, fail to operate, and blockage. Not stated Not discussed in ASME Sec XI Not stated 30, 36 9

report IWV

Leakage, fail to operate, and blockage. Not stated Not discussed in ASME Sec XI Not stated 30, 36 10

report IWV

Not stated. Not stated Not discussed in ASME Sec XI Not stated 30, 33 11

report IWP

Not stated. Not stated Not discussed in If Class 1 E Not stated 33 12

report 1OCFR 50.49

otherwise PS

TS Req.

Not stated. Not stated Not discussed in If Class 1 E Not stated 33 13

report 1OCFR 50.49

otherwise PS

TS Req.

Not stated. Not stated Not discussed in If Class 1 E Not stated 33 14

report 1OCFR 50.49

otherwise PS

TS Req.

Document: NUREG/CR-4977, Vol. 1, SHAG Test Series: Seismic Researchon an Aged United States Gate Valve and on a Piping System in the Decommissione(

Reviewed by: David C. Ma, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Motor operator torque switch spring had a Moderate Not discussed in ASME Sec XI Not s d 34-37, 41 1

permanent deformation after 25 years of report IWV, Req, GL

service (0.47 in. shorter than original 89-10 & Suppl.,

length of 4.46 in.) due to yielding and & PS

ratcheting effects so that the motor

operator was unable to properly close

(More) I I I I
Table A.1 Gall Report for NPAR Reports Page 65A

Document: NUREG/CR-4977, Vol. 2, SHAG Test Series: Seismic Research on an Aged United States Gate Valve and on a Piping System in the Decommissionec

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Piping Motor-Operated Torque Switch Not Stated Lmitorque Corp. RATCH Changein

Gate Valve Helical Spring of Dimension

SMA Type

Limitorque Motor

Operator

Document: NUREG/CR-4985, Indian Point 2 Reactor Coolant Pump Seal Evaluations

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Reactor coolant First stage seal Aluminum-oxide face Westinghouse WEAR Attrition

pump (hydrostatic filmridng plates, O-ring

face seal) polymers

2 Cooling system Reactor coolant Second stage seal Carbon graphite- Westinghouse WEAR Attrition

pump (rubbing face seal) stator and chrome

carbide coatedrunner, O-ring

polymers

3 Cooling system Reactor coolant Third stage seal Carbon graphite Westinghouse WEAR Attrition

pump (rubbing face seal) stator and chrome

carbide coatedrunner, O-ring

polymers

Document: NUREG/CR-5052, Operating Experience and Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Component cooling Valves (motor and Operator Not stated Not stated Not stated Not stated

water systems in air operated, manual,

PWRs check and relief)

2 Component cooling Valves (motor and Seat Not stated Not stated WEAR Attrition

water systems in air operated, manual,

PWRs check and relief)

3 Component cooling Valves (motor and Seat Not stated Not stated VIBR Crack initiation and

water systems in air operated, manual, growth

PWRs check and relief)

4 Component cooling Valves (motor and Seat Not stated Not stated CONTAM Buildup of deposits

water systems in air operated, manual,

PWRs check and relief)

5 Component cooling Pumps (centrifugal) Seals Not stated Not stated WEAR Attrition

water systems in

PWRs

6 Component cooling

water systems in

PWRs

Pumps (centrifugal) I Seals Not stated Not stated VIBR Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 65B

Document: NUREG/CR-4977, Vol. 2, SHAG Test Series: Seismic Research on an Aged United States Gate Valve and on a Piping System in the Decommissioned

Reviewed by: David C. Ma, ANL

Effect of Aoina on ComDonent Function Contrib to Failure ReDorted Droas Rel.proqs Report Recommendations Page No. Item

The permanent deformation of the torque Moderate Not stated ASME Sec XI Simple torque wrench handwheel A.25- 1

spring is caused by two effects: 1. The IWV, Req, GL may detect the permanent A.27,

new spring had significant yielding 2. 89-10 & Suppl., deformation of the torque spring. [4 A.32

Full time compression may cause & PS MOV Program]

accelerated aging. (More)

Document: NUREG/CR-4985, Indian Point 2 Reactor Coolant Pump Seal Evaluations

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Wear due to relative motion between Frequent Not discussed in 10CFR50 App. Not stated S-1, 1-1, 1

rotating seal surfaces, which can be report B & PS S&T 1-6, 2-2,

hastened or aggravated by crud in water, Req. 2-4, 4-2,3,

causes leakage. If wear becomes 4-23

excessive, it can cause loss of significant

quantities of primary coolant and

difficulties on pump startup.

Wear due to relative motion between Frequent Not discussed in 10CFRSO App, Not stated S-1, 1-1, 2

rotating seal surfaces, which can be report B & PS S&T 1-6, 2-2,

hastened or aggravated by crud in water, Req. 2-4, 4-4,

causes leakage. Newer seal designs and 4-23

improved seal materials have reduced

some of the problems.

Wear due to relative motion between Frequent Not discussed in 10CFR50 App. Not stated S-1, 1-1, 3

rotating seal surfaces, which can be report B & PS S&T 1-6, 2-2,

hastened or aggravated by crud in water, Req. 2-4, 4-5,

causes leakage. Newer seal designs and 4-23

improved sea] materials have reduced

some of the problems.

Document: NUREG/CR-5052, Operating Experience and Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Loss of valve operator causes failure of Moderate Not discussed in ASME Sec XI Not stated 1-2, 1-3, 1

valve to open or close, report IWB or IWC & 1-4, 1-5,

IWV, Req, GL 2-1, 4-15,

89-10 & 4-18,4-

20, 4-34,

8-3, 8-5

Wear of seat causes valve leakage. Frequent Not discussed in ASME Sec Xl Not stated 1-2, 1-3, 2

report IWB or IWC & 1-4, 1-5,

IWV, Req, & 2-1, 4-15,

PS S&T R 4-18,4-

20, 4-34,

8-3, 8-5

Cracking of seat causes valve leakage. Moderate Not discussed in ASME Sec XI Not stated 1-2, 1-3, 3

report IWB or IWC & 1-4, 1-5,

IWV, Req, & 2-1, 4-15,

PS S&T R 4-18,4-

20, 4-34,

8-3, 8-5

Foreign contaminants in cooling water and Occasional Not discussed in ASME Sec XI Not stated 1-2, 1-3, 4

failure to seat and leakage. report IWB or IWC & 1-4, 1-5,

IWV, Req, & 2-1, 4-15,

PS S&T R 4-18,4-

20, 4-34,

8-3, 8-5

Wear of seals causes coolant leakage. Frequent Not discussed in 10CFR5O App. Not stated 1-2, 1-3, 5

report B & PS S&T 1-4, 1-5,

Req. 2-1, 4-15,

4-18, 4-

20, 4-34,

18-3, 8-7

Cracking of seals causes leakage. Occasional Not discussed in

report

10CFR50 App.

B & PS S&T

Req.

Not stated 1-2, 1-3,

1-4, 1-5,

2-1, 4-15,

4-18, 4-

20, 4-34,

8-3, 8-7

6
Table A.1 Gall Report for NPAR Reports Page 66A

Document: NUREG/CR-5052, Operating Experience and Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Item SvtmStructurelComo Subcomoonent Materials Manufacturer ARD mechanism ARD effects

.. ... System..... . .. . ... r ....... ................ er.a s.M a ctur.r..RID .... .echani ... ..... ......

7 Component cooling Pumps (centrifugal) Bearings Not stated Not stated WEAR Attrition

water systems in

PWRs

8 Component cooling Pumps (centrifugal) Bearings Not stated Not stated VIBR Crack initiation and

water systems in growth

PWRs

9 Component cooling Heat exchangers Tube Not stated Not stated CORR Loss of material

water systems in (Shell-U-tube)

PWRs

10 Component cooling Heat exchangers Tube Not stated Not stated ERO Loss of material

water systems in • (Shell-U-tube)

PWRs

II Component cooling Heat exchangers Shell Not stated Not stated CORR Loss of material

water systems in (Shell-U-tube)

PWRs

12 Component cooling Heat exchangers Shell Not stated Not stated ERO Loss of material

water systems in (Shell-U-tube)

PWRs

13 Component cooling Heat exchangers Tubesheet Not stated Not stated CORR Loss of material

water systems in (Shell-U-tube)

PWRs

14 Component cooling Heat exchangers Tubesheet Not stated Not stated ERO Loss of material

water systems in (Shell-U-tube)

PWRs

15 Component cooling Piping components Not delineated Not stated Not stated CORR Loss of material

water systems in

PWRs

16 Component cooling Piping components Not delineated Not stated Not stated ERO Loss of material

water systems in

PWRs

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Diesel generator Instruments and

controls

Governor Not stated ALCO, Allis

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Falrbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

VIBR Loosening
Table A.1 Gall Report for NPAR Reports Page 66B

Document: NUREG/CR-5052, Operating Experience and Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Comeonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Paae No. Item

Bearing wear can cause excessive rotor Moderate Not discussed in ASME Sec Xl Not stated 1-2, 1-3, 7

vibration and vane damage, resulting in report IWB or IWC & 1-4, 1-5,

complete failure of pump. IWP, PS TS 2-1, 4-15,

Req & PS 4-18,4-

20, 4-34,

8-3, 8-7

Hydraulic induced dynamic forces can Occasional Not discussed in ASME Sec Xl Not stated 1-2, 1-3, 8

cause bearing vibration and cracking, report IWB or IWC & 1-4, 1-5,

resulting in seizure of shaft. IWP, PS TS 2-1, 4-15,

Req & PS 4-18,4-

20, 4-34,

8-3, 8-7

Corrosion causes holes in tubes and Frequent Not discussed in PS TS Req. & Heat exchanger aging can increase 1-2, 1-3, 9

contamination of coolants and reduced report PS S&T Req. dramatically in the out years [4] 1-4, 1-5,

heat transfer. 2-1,4-18,

4-20, 4-

34, 8-6, 8-

3

Corrosion causes holes in tubes and Occasional Not discussed in PS TS Req. & Heat exchanger aging can increase 1-2, 1-3, 10

contamination of coolants and reduced report PS S&T Req. dramatically in the out years [4] 1-4, 1-5,

heat transfer. 2-1, 4-18,

4-20, 4-

34, 8-6, 8-

3

Loss of material causes holes in shell and Occasional Not discussed in PS TS Req. & Heat exchanger aging can increase 1-2, 1-3, 11

leakage to ambient report PS S&T Req. dramatically in the out years [4] 1-4, 1-5,

2-1, 4-18,

4-20, 4-

34, 8-6, 8-

3

Loss of material causes holes in shell and Occasional Not discussed in PS TS Req. & Heat exchanger aging can increase 1-2, 1-3, 12

leakage to ambient report PS S&T Req. dramatically in the out years [4] 1-4, 1-5,

2-1, 4-18,

4-20, 4-

34, 8-6, 8-

3

Loss of material in tubesheet causes Occasional Not discussed in PS TS Req. & Heat exchanger aging can increase 1-2, 1-3, 13

cross contamination between coolant, report PS S&T Req. dramatically in the out years [4] 1-4, 1-5,

2-1, 4-18,

4-20, 4-

34, 8-6, 8-

3

Loss of material in tubesheet causes Occasional Not discussed in PS TS Req. & Heat exchanger aging can increase 14

cross contamination between coolant. report PS S&T Req. dramatically in the out years [4]

Poor water quality causes corrosion and Moderate Not discussed in ASME Sec Sec Piping aging can increase 1-2, 1-3, 15

leakage holes or cracks in piping. In report Xl IWB or IWC dramatically in the out years [4] 1-4, 1-5,

addition, external corrosion is caused by 3-1, 4-18,

auxiliary building environment. 8-3

High flow velocity can cause material Occasional Not discussed in Piping aging can increase 1-2, 1-3, 16

removal and leakage holes. report dramatically in the out years [4] 1-4, 1-5,

3-1, 4-18,

8-3

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReLprogs Report Recommendations Page No. Item

Subcomponent becomes sufficiently

loosened that it no longer functions and

the component fails.

Frequent Not discussed in

report

PS TS Req.,

RG 1.9, RG

1.108

Reduce fast starts imposed by

present regulation; implement new

testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

2.4 I
Table A.1 Gall Report for NPAR Reports Page 67A

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomlonent Materials Manufacturer ARD mechanism ARD effects

2 Diesel generator Instruments and Control air systems Not stated ALCO, Allis VIBR Loosening

controls Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

3 Diesel generator Instruments and Wiring and Not stated ALCO, Allis VIBR Loosening

controls terminations Chaimers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

4 Diesel generator Instruments and Sensors Not stated ALCO, Allis VIBR Loosening

controls Chaimers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delavai, and

Worthington

5 Diesel generator Fuel system Engine piping Not stated ALCO, Allis VIBR Loosening

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

6 Diesel generator Fuel system Injector pumps Not stated ALCO, Allis VIBR Loosening

Chaimers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delavai, and

Worthington

7 Diesel generator Fuel system Injectors and Not stated ALCO, Allis VIBR Loosening

nozzles Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

8 Diesel generator Starting system Starting air valve Not stated ALCO, Allis

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

CONTAM Loss of desired

surface properties
Table A.1 Gall Report for NPAR Reports Page 67B

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Comnonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Page No. Item

Subcomponent becomes sufficiently Occasional Not discussed in PS TS Req., Reduce fast starts imposed by 2.4 2

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Infrequent Not discussed in PS TS Req., Reduce fast starts imposed by 2.4 3

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Infrequent Not discussed in PS TS Req., Reduce fast starts imposed by 2.4 4

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Infrequent Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 5

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Occasional Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 6

oosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Infrequent Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 7

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Environmental dust and corrosion product

buildup from environmental moisture

cause fouling of the subcomponents.

Moderate Not discussed in

report

PS TS Req.,

RG 1.9, RG

1.108

Reduce fast starts imposed by

present regulation; implement new

testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

2.4, 2.5 8
Table A.1 Gall Report for NPAR Reports Page 68A

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by; Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

9 Diesel generator Starting system Controls Not stated ALCO, Allis CONTAM Loss of desired

Chalmers, surface properties

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

10 Diesel generator Starting system Starting motor Not stated ALCO, Allis CONTAM Loss of desired

Chalmers, surface properties

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

11 Diesel generator Cooling system Piping Not stated ALCO, Allis VIBR Loosening

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

12 Diesel generator Cooling system Pumps Not stated ALCO, Allis VIBR Loosening

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

13 Diesel generator Cooling system Heat exchangers Not stated ALCO, Allis VIBR Loosening

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

14 Diesel generator Engine structure Crankcase Not stated ALCO, Allis VIBR Loosening

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

15 Diesel generator Engine structure I Cylinder lines Not stated ALCO, Allis

Chalmers,

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

Worthington

FAT Cumulative fatigue

damage
Table A.1 Gall Report for NPAR Reports Page 68B

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Environmental dust and corrosion product Occasional Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 S

buildup from environmental moisture report RG 1.9, RG present regulation; implement new

cause fouling of the subcomponents. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Environmental dust and corrosion product Occasional Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 10

buildup from environmental moisture report RG 1.9, RG present regulation; implement new

cause fouling of the subcomponents. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Moderate Not discussed in PS TS Req., Reduce fast starts imposed by 2.4, 2.5 11

loosened that it no longer functions and report RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Occasional PNL NPAR Diesel PS TS Req., Reduce fast starts imposed by 2.4, 2.5 12

loosened that it no longer functions and Generator Study RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Internal components become sufficiently Occasional PNL NPAR Diesel PS TS Req., Reduce fast starts imposed by 2.4, 2.5 13

loosened that it no longer functions and Generator Study RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Subcomponent becomes sufficiently Moderate PNL NPAR Diesel PS TS Req., Reduce fast starts imposed by 2.4, 2.5 14

loosened that it no longer functions and Generator Study RG 1.9, RG present regulation; implement new

the component fails. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Repeated thermal loadings lead to fatigue

crack initiation and growth and eventual

mechanical failure

Occasional PNL NPAR Diesel

Generator Study

PS TS Req.,

RG 1.9, RG

1.108

Reduce fast starts imposed by

present regulation; implement new

testing and trending procedures as

recommended in the report; improve

maintenance practices. 14]

2.4, 2.5 15
Table A.1 Gall Report for NPAR Reports Page 69A

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

16 Diesel generator Engine structure Main bearings Not stated ALCO, Allis CONTAM Loss of lubricant

Chalmers, properties

Caterpillar, Cooper,

Bessemer,

Electromotive

Division, Fairbanks

Morse, Nordberg,

Transamerica

Delaval, and

I _Worthington

Document: NUREG/CR-5159, Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Reactor Check valve This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

I I_ systems.

Document: NUREG/CR-5248, Prioritization of TIRGALEX-Recommended Components for Further Aging Research

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 All major systems All major This report does not

structures/compone provide specific

nts detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems. I

Document: NUREG/CR-5268, Aging Study of Boiling Water Reactor Residual Heat Removal System

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR residual heat Motor operated Not stated Not stated Not stated WEAR Attrition

removal system valves

2 BWR residual heat Motor operated Not stated Not stated Not stated ELE-TEMP Chemical or physical

removal system valves degradation

3 BWR residual heat Instrumentation Not stated Not stated Not stated Calibration drift Change in set points

removal system

4 BWR residual heat Supports for piping Not stated Not stated Not stated Not stated Not stated

removal system

5 BWR residual heat Breakers Not stated Not stated Not stated Not stated Not stated

removal system

6 BWR residual heat

removal system

Heat exchangers Not stated INot stated INot stated CORR lloss of material
Table A.1 Gall Report for NPAR Reports Page 69B

Document: NUREG/CR-5057, Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators

Reviewed by: Jeffrey L. Binder, ANL

Effect of A inn on Com onent Function Contrib to Failure Renorted proas Rel.Drogs ReDor t Recommendations Paae No. Item

Oil contamination leads to loss of Occasional PNL NPAR Diesel PS TS Req., Reduce fast starts imposed by 2.4, 2.5 16

lubrication in the bearing assemblies, Generator Study RG 1.9, RG present regulation; implement new

resulting in loss of function. 1.108 testing and trending procedures as

recommended in the report; improve

maintenance practices. [4]

Document: NUREG/CR-5159, Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Document: NUREG/CR-5248, Prioritization of TIRGALEX-Recommended Components for Further Aging Research

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item~1

Document: NUREG/CR-5268, Aging Study of Boiling Water Reactor Residual Heat Removal System

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Wear of packing and drive can cause Frequent Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 1

leakage and failure to operate due to improvement studies IWB & IWV, between frequent performance 35, 10-1

binding, are ongoing Req, GL 89-10 testing of RHR components and

& Suppl. aging detection and mitigation [4)

High temperatures in motor windings can Frequent Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 2

cause insulation deterioration and motor improvement studies IWB & IWV, between frequent performance 35,10-1

failure. Highest failure component in are ongoing Req, GL 89-10 testing of RHR components and

RHR systems. & Suppl. aging detection and mitigation [4]

Change in set points with time can cause Moderate Reliability If Class 1 E Perform study of the relationship 5-1 to 5- 3

system components to shut down or fail to improvement studies 10CFR 50.49 between frequent performance 35, 10-1

shut down when critical thresholds are are ongoing otherwise PS testing of R HR components and

exceeded. Second highest failure S&T Req aging detection and mitigation [4]

component in RHR system.

Not stated. Occasional Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 4

improvement studies between frequent performance 35, 10-1

are ongoing testing of RHR components and

aging detection and mitigation [4]

Not stated. Occasional Reliability If Class 1 E Perform study of the relationship 5-1 to 5- 5

improvement studies 10CFR 50.49 between frequent performance 35,10-1

are ongoing otherwise PS testing of RHR components and

S&T Req aging detection and mitigation [4]

Tube wall thinning can cause leakage

across tubes, reduced heat transfer, and

possible radioactive contamination.

Infrequent Reliability

improvement studies

are ongoing

PS S&T Req. Perform study of the relationship

between frequent performance

testing of RHR components and

aging detection and mitigation [4]

5-1ito 5-

35,10-1

6
Table A.1 Gall Report for NPAR Reports Page 70A

Document: NUREG/CR-5268, Aging Study of Boiling Water Reactor Residual Heat Removal System

Reviewed by: Ken E. Kasza, ANL

Item Svstem StruudtlrelComn Suibtamnn~nat Mnt•_rinl_• Mnn~f~nt4 rmr ARI'l m~enh~nk_•r A n fl ff•nt_•

7 BWR residual heat Heat exchangers Not stated Not stated Not stated CLOG Blockage of flow

removal system passages

8 BWR residual heat Pumps/motors Not stated Not stated Not stated WEAR Attrition

removal system

9 BWR residual heat Pumps/ motors Not stated Not stated Not stated ELE-TEMP Chemical or physical

removal system degradation

10 BWR residual heat Pumps/ motors Not stated Not stated Not stated FAT Cumulative fatigue

removal system damage

11 BWR residual heat Pipes Not stated Not stated Not stated CORR/IGSCC Loss of material

removal system

12 BWR residual heat Pipes Not stated Not stated Not stated FAT/ THERM Cumulative fatigue

removal system damage

Document: NUREG/CR-5314, Vol.3, Life Assessment Procedures for Major LWR Components, Cast Stainless Steel Components

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR cooling water Coolant pump Types C, E, and F CF-8, CF-8A, or CF- Borg-Warner, EMBR/TE Loss of fracture

system pump bodies 8M cast SS Westinghouse toughness

2 PWR cooling water Piping Pipes CF-8A or CF-8M Westinghouse EMBR/TE Loss of fracture

system cast SS toughness

3 PWR cooling water Piping Fittings CF-8A cast SS Westinghouse EMBR/TE Loss of fracture

system toughness

4 PWR cooling water Piping Surge line Cast duplex SS Westinghouse EMBR/TE Loss of fracture

system toughness

5 PWR cooling water

system

Piping Surge line CF-8M cast SS Combustion

Engineering

EMBRfTE Loss of fracture

toughness
Table A.1 Gall Report for NPAR Reports Page 70B

Document: NUREG/CR-5268, Aging Study of Boiling Water Reactor Residual Heat Removal System

Reviewed by: Ken E. Kasza, ANL

Effect of Aqina on Component Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Page No. Item

Foreign contaminants can cause tube Infrequent Reliability PS S&T Req. Perform study of the relationship 5-1 to 5- 7

blockage and reduced heat btansfer. improvement studies between frequent performance 35, 10-1

are ongoing testing of RHR components and

aging detection and mitigation [4]

Wear causes increased internal leakage Infrequent Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 8

flows and loss of capacity to pump at improvement studies IWP between frequent performance 35,10-1

design values as well as external leakage. are ongoing testing of RHR components and

aging detection and mitigation [4]

Inadequate cooling of seals results in Infrequent Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 9

pump inoperability and winding failure in improvement studies IWP between frequent performance 35, 10-1

motors. are ongoing testing of RHR components and

aging detection and mitigation [4]

Operation of pumps at very low flows Infrequent Reliability ASME Sec Xl Perform study of the relationship 5-1 to 5- 10

causes hydraulic flow instabilities and improvement studies IWP between frequent performance 35, 10-1

vibration of impeller and rotor and are ongoing testing of RHR components and

breakage of these subcomponents. aging detection and mitigation [4]

Wall thinning can cause leakage through Occasional Reliability ASME Sec Xl Perform study of the relationship 5-1 to 5- 11

pipe walls and cracking in welds, improvement studies IWB & PS S&T between frequent performance 35, 10-1

are ongoing Req testing of RHR components and

aging detection and mitigation [4]

Large time dependent temperature Occasional Reliability ASME Sec XI Perform study of the relationship 5-1 to 5- 12

gradients in piping can cause cracking improvement studies IWB & PS S&T between frequent performance 35,10-1

and leakage. are ongoing Req testing of RHR components and

I I_ I_ aging detection and mitigation [4]

Document: NUREG/CR-5314, Vol. 3, Ufe Assessment Procedures for Major LWR Components, Cast Stainless Steel Components

Reviewed by: Jeffrey L Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Component becomes less flaw tolerant Not stated AN L aging studies, ASME Sec XI Estimate the extent of thermal 1-3, 11,

(critical flaw size decreases), resulting in NRC and EPRI UT IWP & IWB or embrittlement by a combination of 26-44

diminished structural integrity, studies IWC (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepalr procedures as an option

_for license extension. (More) [4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 3, 11, 26- 2

(critical flaw size decreases), resulting in NRC and EPRI UT IWB or IWC embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) [4]

Component becomes less flaw tolerant Not stated AN L aging studies, ASME Sec Xl Estimate the extent of thermal 3,11,26- 3

(critical flaw size decreases), resulting in NRC and EPRI UT IWB or IWC embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepalr procedures as an option

for license extension. (More) [4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4,11, 26- 4

(critical flaw size decreases), resulting in NRC and EPRI UT IWB or IWC embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) [4]

Component becomes less flaw tolerant

(critical flaw size decreases), resulting in

diminished structural integrity.

Not stated AN L aging studies,

NRC and EPRI UT

studies

ASME Sec XI

IWB or IWC

Estimate the extent of thermal

embrittlement by a combination of

(a) analytical modelng of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) [4]

4,11,26-

44
Table A.1 Gall Report for NPAR Reports Page 71A

Document: NUREG/CR-5314, Vol. 3, Ufe Assessment Procedures for Major LWR Components, Cast Stainless Steel Components

Reviewed by: Jeffrey L Binder, ANL

Item System StructureJComD Subcomoonent Materials Manufacturer ARD mechanism ARD effects

6 PWR cooling water Pressurizer Spray head Cast SS Westinghouse EMBR/TE Loss of fracture

system toughness

7 PWR cooling water Check valves Valve body Cast SS Not stated EMBR/TE Loss of fracture

system toughness

8 PWR cooling water Recirculation piping Fittings and valves Cast SS Not stated EMBR/TE Loss of fracture

system toughness

9 Control rod system Control rod drive Drive mechanism CF-8 cast SS Westinghouse, EMBRITE Loss of fracture

housing (Westinghouse); not Combustion toughness

stated (CE and GE) Engineering, and

General Electric

10 Reactor core Core internals Control rod CF-8 cast SS Combustion EMBRITE Loss of fracture

assembly shrouds Engineering toughness

11 Reactor core Core internals Lower support Cast SS Westinghouse EMBR/TE Loss of fracture

structures and toughness

instruments

12 Reactor core Core internals Orificed fuel CF-8 cast SS General Electric EMBR/TE Loss of fracture

supports toughness

13 Reactor core Core internals Unspecified jet CF-8 and CF-3 cast General Electric EMBR/TE Loss of fracture

pump assembly SS toughness

Document: NUREG/CR-5378, Aging Data Analysis and Risk Assessment-Development and Demonstration Study

Reviewed by: Jeffrey L. Binder, ANL

item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary feedwater Various, including This report does not

system. steam-driven pumps, provide specific

motor- and air- detailed information

operated valves, on age-related

check valves, stop degradation

valves, piping, and processes for

instruments, specific nuclear

components or systems.
Table A.1 Gall Report for NPAR Reports Page 71 B

Document: NUREG/CR-5314, Vol. 3, Life Assessment Procedures for Major LWR Components, Cast Stainless Steel Components

Reviewed by: Jeffrey L. Binder, ANL Effect of Aninn on Comnonent Functlion Crrntrih to Failure Ren~orted nron• ReI.oroa]s Renort Recommendations PaeN.Item

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec Xl Estimate the extent of thermal 4, 11, 26- 6

(critical flaw size decreases), resulting in NRC and EPRI UT IWB & Assoc embrittlement by a combination of 44

diminished structural integrity. studies NRC GC (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE: Consider

weldrepair procedures as an option

for license extension. [4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4, 11,26- 7

(critical flaw size decreases), resulting in NRC and EPRI UT IWB or IWC embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modelng of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option for license extension. (More) (4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4,11,26- 8

(critical flaw size decreases), resulting in NRC and EPRI UT IWB or IWC embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) (4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4,11,26- 9

(critical flaw size decreases), resulting in NRC and EPRI UT IWB & PS TS embrittlement by a combination of 44

diminished structural integrity, studies Req. (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option for license extension. (More) (4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4, 11,26- 10

(critical flaw size decreases), resulting in NRC and EPRI UT IWB embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) (4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4, 11,26- 11

(critical flaw size decreases), resulting in NRC and EPRI UT IWB embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) [4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec XI Estimate the extent of thermal 4,11,26- 12

(critical flaw size decreases), resulting in NRC and EPRI UT IWB embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) (4]

Component becomes less flaw tolerant Not stated ANL aging studies, ASME Sec Xl Estimate the extent of thermal 4, 11, 26- 13

(critical flaw size decreases), resulting in NRC and EPRI UT IWB embrittlement by a combination of 44

diminished structural integrity, studies (a) analytical modeling of in-service

degradation, (b) metallurgical

evaluation, and (c) NDE. Consider

weldrepair procedures as an option

for license extension. (More) [4]

Document: NUREG/CR-5378, Aging Data Analysis and Risk Assessment-Development and Demonstration Study

Reviewed by: Jeffrey L Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5379, Vol. 1, Nuclear Plant Service Water System Aging Degradation Assessment, Phase I

Reviewed by: Dwight R. Diercks, ANL

Item Svtem uetrnJ~mn Suhe~nmnnnent Mzaterial Manuficturer ARD medhanism

Page 72A

ARD effedt•

I Open and closed Piping Not stated Carbon steel Not stated CORR/PIT Local loss of materia

service water

systems

2 Open and closed Piping Not stated Carbon steel Not stated CORR Loss of material and

service water corrosion product

systems buildup

3 Open and closed Check valve Check valve swing Carbon steel Not stated CORR/UA Loss of material

service water arm

systems

4 Open and closed Gage valve Gage valve disk Carbon steel Not stated CORR/UA Loss of material

service water

systems

5 Open and closed Heat exchanger Tubing 90Cu-lONi Not stated CORR/PIT Local loss of materia

service water

systems

6 Open and closed. Heat exchanger Tubing 90Cu-10Ni Not stated CORR/PIT Local loss of materia

service water

systems

7 Open and closed Heat exchanger Tubing 90Cu-10Ni Not stated CORR/ leaching Loss of material

service water

systems

Document: NUREG/CR-5379, Vol. 2, Nuclear Plant Service Water System Aging Degradation Assessment, Phase II

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Open service water Valves Valve stems Type 410 stainless Not stated CORR Loss of material

systems steel

2 Open service water Heat exchanger Tubing 90/10 copper-nickel Not stated* CORR/leaching Loss of material

systems

3 Open service water Piping, coolers, and Piping, cooler U- Carbon steel Not stated CORR Loss of material

systems valves joints, and valve

internals

4 Open service water Motor-operated Valve disk Not stated Not stated CORR Loss of material

systems valves

5 Open service water Heat exchangers Tubing and Not stated Not stated CORR Loss of material and

systems instrument lines corrosion product

buildup

6 Open service water Pumps Impellers and Brass Not stated ERO Wall thinning

systems screens

7 Open service water Heat exchangers Tubing Not stated Not stated BIO Buildup of deposits

systems

E Open service water

systems

Various Not stated Not stated Not stated BIO Buildup of deposits
Table A.1 Gall Report for NPAR Reports Page 72B

Document: NUREG/CR-5379, Vol. 1, Nuclear Plant Service Water System Aging Degradation Assessment, Phase I

Reviewed by: Dwight R. Diercks, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported proes Rel.progs Report Reciommendations Page No. Item

Tuberculation or concentration cell Frequent Not discussed in ASME Sec XI Some benefit obtained from B.2, B.7, 1

corrosion from deposits on the I.D. piping report & PS S&T replacing carbon steel piping with B.8

surface results in localized pitting Req. stainless steel. [2]

corrosion and penetration of the piping

wail.

Rust deposits from general corrosion and Moderate Not discussed in ASME Sec XI Some benefit obtained from B.2, B.6, 2

biological and/or inorganic deposition report & PS S&T replacing carbon steel piping with B.7

results in pipe plugging. Req. stainless steel. [2]

Rust produced by general corrosion is Occasional Not discussed in ASME Sec XI Not stated B.2 3

removed by chaffing as the swing arm report & PS S&T

rotates, producing failure by an Req.

unspecified process.

General corrosion results in loss of net Occasional Not discussed in ASME Sec XI Not stated B.2 4

section and eventual separation of disk report & PS S&T

from valve stem. Req.

Pitting corrosion, commonly associated Occasional Not discussed in PS S&T Req. Not stated B.2 5

with concentration cells set up at I.D. report

surface deposits, leads to localized pitting

and penetration of the tube wall

Tuberculation deposits from localized Occasional Not discussed in PS S&T Req. Not stated B.2 6

corrosion can break off, and the resulting report

fragments can result in tube plugging.

Preferential dissolution of Ni Occasional Not discussed in PS S&T Req. Not stated B.2 7

(denickelification) from the tubing alloy report

can lead to loss of tube integrity and

leakage. L

Document: NUREG/CR-5379, Vol. 2, Nuclear Plant Service Water System Aging Degradation Assessment, Phase II

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Stainless steel components operating in Frequent Not discussed in ASME Sec IX Maintain a minimum water flow to 3.3 1

stagnant loops of open service water report IWV or PS prevent oxygen depletion. [4]

systems are subject to corrosive attack S&T Req.

due to depletion of the dissolved oxygen in

the water needed to maintain a protective

oxide surface layer. I

Copper-nickel tubing in open service Not stated Not discussed in PS S&T Req. Maintain a minimum water flow to 3.3 2

water systems is subject to nickel report prevent oxygen depletion. [4]

leaching, particularly under stagnant

conditions where oxygen depletion

occurs.

Corrosion of carbon steel components is Frequent Not discussed in ASME Sec XI Not stated 3.3 3

accelerated by the flowing water report or PS S&T

conditions used to counter the problems Req.

caused by oxygen depletion.

The majority of electrical failures Frequent Not discussed in ASME Sec Xl Not stated 3.3 4

experiences with the motors on motor- report & GL 89-10 &

operated valves were found to be Suppl. or PS

corrosion related S&T Re

Corrosion products, primarily from carbon Occasional Not discussed in PS S&T Req. Not stated 3.3 5

steel, can cause flow blockage in small report

tubed heat exchangers and instrument

lines.

Erosion of brass pump impellers has Occasional Not discussed in ASME Sec Xl Not stated 3.3 6

required replacement of these report IWP or PS

components every two years; similar S&T Req.

erosion has been observed in pump

impellers and coarse screens in fire water

systems

Biofouling from microorganism growth Not stated Not discussed in PS S&T Req. Not stated 3.4 7

can cause decreased efficiency, report

component corrosion, and reduced

system flow. - _ _

Biofouling from large organisms can cause corrosion, local erosion and pitting,

and plugging and fouling.

Not stated Not discussed in

report

PS S&T Req. Not stated 3.4
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5379, Vol. 2, Nuclear Plant Service Water System Aging Degradation Assessment, Phase I1

Reviewed by: Dwight R. Diercks, ANL

Item System StructurelComp Subcomponent Materials Manufacturer A

Page 73A

RD mechanism ARD effects

9 Recirculating service Piping Not stated Carbon steel Not stated CORR Loss of material

water systems

10 Open service water Ring headers Ring header Carbon steel Not stated CORR/PIT Local loss of materia

systems supports

11 Open service water Discharge butterfly Not stated Not stated ERO/CAV Loss of material

systems valves

12 Open service water Valve actuators Not stated Not stated FAT/ vibration Cumulative fatigue

systems damage

13 Open service water Multiple Not stated Not stated Water hammer Excessive pressure

systems loading

14 Closed service water Air intake structure Concrete with Not stated CORR/SA Crack initiation and

systems carbon steel rebar growth

and aluminum

embedment

15 Closed service water Air intake structure Concrete Not stated CORR; AGGR- Loss of integrity

systems CHEM

16 Closed service water Pump Pump shaft sleeves Not stated Not stated CORR Loss of material

systems

17 Closed service water Piping components Carbon steel Not stated CORR Loss of material

systems (non-safety-related)

18 Closed service water Packing followers Ductile iron and Not stated CORR/SCC Crack initiation and

systems and other valve parts other materials growth

19 Closed service water Butterfly valves Misc, sub- Monel and carbon Not stated CORR Loss of material and

systems components steel corrosion product

buildup

20 Closed service water Check valves Unspecified Not stated WEAR Attrition

systems elastomer and other

materials

21 Closed service water Valves Not stated Not stated ADH Component failure

systems

22 Closed service water Heat exchanger Tubing Copper-nickel Not stated CORR/UA Loss of material

systems

23 Closed service water Heat exchanger Tubing Copper-nickel Not stated BIO Buildup of deposits

systems
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5379, Vol. 2, Nuclear Plant Service Water System Aging Degradation Assessment, Phase II

Page 73B

Paae No. Item

Reviewed by: Dwight R. Diercks, ANL

Effect of Aaina on Comoonent Function Contrib to Failure Reported proas ReI.Droas Reeort Recommendations

Small bore carbon steel piping had been Formerly frequent; Not discussed in ASME Sec XI Change make-up water sources and 3.4 9

subject to significant corrosion problems, now rare report or PS S&T introduce corrosion control. [4]

but the problem has been largely Req.

eliminated proper water treatment.

Ring header supports for pond spray Occasional Not discussed in PS S&T Req. Not stated 3.4 10

rings have suffered some pitting attacks, report

resulting in areas of slight metal removal.

Some cavitation erosion has been Once occasional; Not discussed in ASME Sec Xl Replace affected components with 3.5 11

observed on discharge butterfly valves, now rare report IWV steel. [2]

but the use of hardened steel components

is expected to mitigate this problem.

Vibration, usually from motor operation, Occasional Not discussed in ASME Sec XI Not stated 3.5 12

has caused air leaks in air-operated valve report IWV

actuators.

Water hammer results in excessive Once occasional; Not disucssed in ASME Sec XI Add a keep-full or jockey pump and 3.5 13

pressure loading of unspecified eliminated report or PS S&T req. motor-operated valve sequencing. [1]

recirculation system components.

Concrete pedestal cracking at the intake Not stated Not discussed in PS S&T Req. Not stated 3.5 14

structure can occur because of rebar report

corrosion and aluminum embedment

failure.

Intake structure degradation can occur Occasional Not discussed in PS S&T Req. Not stated 3.5 15

through attack from marine and report

groundwater chemicals on concrete

binders and cements.

Corrosion of pump shaft sleeves has Rare Not discussed in ASME Sec XI Not stated 3.5 16

been observed under shaft sleeves, report IWP or PS

necessitating replacement of the shaft. S&T Req.

Drains and intake wash screens in non- Occasional; rare with Not discussed in PS S&T Req. Replace with lined or stainless steel 3.6 17

safety-related piping has suffered uniform SS re report pipe. [2]

corrosion and biofouling.

Non-wetted valve parts have failed under Occasional Not discussed in ASME Sec XI Not stated 3.6 18

stress-induced corrosion. In addition, a report IWV or PS

series of corrosion failures of ductile iron S&T Req.

packing followers, caused by dampness,

leakage, and other possibly factors, has

occurred. I

Corrosion in butterfly valves between the Occasional Not discussed in ASME Sec Xl Not stated 3.6 19

carbon steel packing follower and the report IWV or PS

monel shaft has caused binding of the S&T Req.

shaft.

Check valves were suffering premature Occasional; new Not discussed in ASME Sec Xl New elastomer seals and protective 3.6 20

wear in valve seat area and check disk, valve elim. report IWV or PS painting reduced problem until AlNew elastomer seals and protectant paint S&T Req. bronze replacements can be

on check disk has reduced rate of installed. [1]

degradation; existing valves are to be

replaced with aluminum bronze. I

Valve body to valve liner adhesion can Occasional Not discussed in ASME Sec XI Not stated 3.6 21

cause loss of liner integrity, leading to report IWV or PS

rapid corrosion and failure. S&T Req.

Copper-nickel heat exchanger tubes Occasional; Not discussed in PS S&T Req. Replace with Ti alloy tubes (4] 3.6 22

previously used were subject to salt-water eliminated with report

corrosion and are being replaced with

titanium alloy tubes.________

Accumulation of vegetation, Common Not discussed in PS S&T Req. Removed by heat treatment, chlorine 3.6 23

micoorganisms, and larger organisms can report injection, and backflushing. [4]

result in plugging of heat exchanger.
Table A.1 Gall Report for NPAR Reports Page 74A

Document: NUREG/CR-5386, Basis for Snubber Aging Research: Nuclear Plant Aging Research Program

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomconent Materials Manufacturer ARD mechanism ARD effects

1 Various Snubber This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or systems.

Document: NUREG/CR-5404, Vol. 1, Auxiliary Feedwater System Aging Study

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary feedwater All major This report does not

system components provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or systems. I

Document: NUREG/CR-5404, Vol. 2, Auxiliary Feedwater System Aging Study: Phase I Follow-On Study

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary feedwater Various This report does not

provide specific

detailed information on age-related

degradation

processes for

specific nuclear

components or systems.

Document: NUREG/CR-5406, Vol. 1, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption T

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR water cleanup Motor operated This report does not

system flexible wedge gate provide specific

isolation valve detailed information

on age-related

degradation

processes for

specific nuclear

components or systems.

Document: NUREG/CR-5406, Vol. 2, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption T

Reviewed by: Jeffrey L Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR water cleanup Motor operated This report does not

system flexible wedge gate provide specific

isolation valve detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 748

Document: NUREG/CR-5386, Basis for Snubber Aging Research: Nuclear Plant Aging Research Program

Reviewed by: Steve U. Choi, ANL Effect of Aoino on Component Function Contrib to Failure Resorted nroas Rel.1oroas Ren~ort Recommendations Paae No. Item

i 1

Document: NUREG/CR-5404, Vol. 1, Auxiliary Feedwater System Aging Study

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Document: NUREG/CR-5404, Vol. 2, Auxiliary Feedwater System Aging Study: Phase I Follow-On Study

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Document: NUREG/CR-5406, Vol. 1, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption T

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Document: NUREG/CR-5406, Vol. 2, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption " Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item
Table A.1 Gall Report for NPAR Reports Page 75A

Document: NUREG/CR-5406, Vol. 3, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption 1

Reviewed by: Jeffrey L. Binder, ANL

Item Sv~qtem Structure/Comn Subcomn}onent Mnterial• Mnnufscturer ARD mechanism ARD effects

1 BWR water cleanup Motor operated This report does not

system flexible wedge gate provide specific

isolation valve detailed information on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG/CR-5419, Aging Assessment of Instrument Air Systems in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Instrument Compressor and Compressors Not stated Not stated WEAR Attrition

air/service air receiver

systems

2 Instrument Compressor and Compressors Not stated Not stated VIBR Loosening; crack

air/service air receiver initiation and growth

systems

3 Instrument Compressor and Aftercoolers/moistur Not stated Not stated CORR Loss of material;

air/service air receiver e separators corrosion product

systems buildup

4 Instrument Compressor and Aftercoolers/moistur Not stated Not stated ENVIR Deterioration

air/service air receiver e separators

systems

5 Instrument Compressor and Aftercoolers/moistur Not stated Not stated CLOG Blockage of flow

air/service air receiver e separators passages

systems

6 Instrument Compressor and Air receivers Not stated Not stated CORR Loss of material;

air/service air receiver corrosion product

systems buildup

7 Instrument Compressor and Air receivers Not stated Not stated CONTAM Loss of desired

air/service air receiver surface properties

systems

8 Instrument Filter/dryer train Air dryers Not stated Not stated CLOG Blockage of flow

air/service air passages

systems

9 Instrument Filter/dryer train Air dryers Not stated Not stated CORR Loss of material;

air/service air corrosion product

systems buildup

10 Instrument Filter/dryer train Air dryers Not stated Not stated ENVIR Deterioration

air/service air

systems

11 Instrument Filter/dryer train Air dryers Not stated Not stated CONTAM Loss of desired

air/service air surface properties

systems

12 Instrument Filter/dryer train Pre-filters Not stated Not stated CORR Loss of material;

air/service air corrosion product

systems buildup

13 Instrument Filter/dryer train Pre-filters Not stated Not stated MOIST Increased pressure

air/service air drop; reduced

systems strength

14 Instrument Filter/dryer train After-filters Not stated Not stated PART Increased pressure

air/service air drop

systems

15 Instrument Filter/dryer train After-filters Not stated Not stated WEAR Attrition

air/service air

systems

16 Instrument Air distribution Valves Not stated Not stated WEAR Attrition

air/service air system

systems

17 Instrument Air distribution Valves Not stated Not stated CORR Loss of material;

air/service air system corrosion product

systems _ _ _ buildup

Instrument

air/service air

systems

Air distribution

system

Valves Not stated Not stated CONTAM Loss of desired

surface properties
Table A.1 Gall Report for NPAR Reports Page 75B

Document: NUREG/CR-5406, Vol. 3, BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption T

Reviewed by: Jeffrey L Binder, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported Droas Rel.oroas Report Recommendations. Paae No. Item

Document: NUREG/CR-5419, Aging Assessment of Instrument Air Systems in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs. Report Recommendations Page No. Item

Failure to load/unload properly and Frequent Not discussed in PS S&T Req. Not stated 4-12, 13, 1

air/lubricating oil leaks would cause the report 17

immediate loss of a compressor.

Excess vibration would cause the Moderate Not discussed in PS S&T Req. Not stated 4-12, 13, 2

compressor to automatically trip or lead to report 18

required shutdown.

Air/water leaks and loss of function. Frequent Not discussed in PS S&T Req. Not stated 4-13, 18 3

report

Air/water leaks and loss of function. Moderate Not discussed in PS S&T Req. Not stated 4-13,18 4

report

Air/water leaks and loss of function. Occasional Not discussed in PS S&T Req. Not stated 4-13,18 5

report

Leaking air, drain valve stuck or clogged, Frequent Not discussed in PS S&T Req. Not stated 4-13, 18, 6

and excessive water buildup. report 19

Leaking air, drain valve stuck or clogged, Infrequent Not discussed in PS S&T Req. Not stated 4-13, 18, 7

and excessive water buildup. report 19

Degraded function of the dryers, air leaks, Occasional Not discussed in PS S&T Req. Not stated 4-13, 15, 8

and desiccant/moisture carry-over to report 19

contaminate the instrument air system.

Degraded function of the dryers, air leaks, Infrequent Not discussed in PS S&T Req. Not stated 4-13,15, 9

and desicoant/moisture carry-over to report 19

contaminate the instrument air system.

Degraded function of the dryers, air leaks, Infrequent Not discussed in PS S&T Req. Not stated 4-13,15, 10

and desiccant/moisture carry-over to report 19

contaminate the instrument air system.

Degraded function of the dryers, air leaks, Infrequent Not discussed in PS S&T Req. Not stated 4-13, 15, 11

and desiccant/moisture carry-over to report 19

contaminate the instrument air system.

Diminished or loss of air flow and leaking. Frequent Not discussed in PS S&T Req. Not stated 4-15,19 12

report

Diminished or loss of air flow and leaking. Infrequent Not discussed in PS S&T Req. Not stated 4-15,19 13

report

Diminished or loss of air flow and leaking. Moderate Not discussed in PS S&T Req. Not stated 4-16,20 14

report

Diminished or loss of air flow and leaking. Rare Not discussed in PS S&T Req. Not stated 4-16,20 15

report

Failure to open/close, seat leaking, and Occasional Not discussed in PS S&T Req. Not stated 4-16, 17, 16

leakage from packing, gaskets, or valve report 20

body cracks.

Failure to open/close, seat leaking, and Occasional Not discussed in PS S&T Req. Not stated 4-16, 17, 17

leakage from packing, gaskets, or valve report 20

body cracks. I _I

Failure to open/close, seat leaking, and

eakage from packing, gaskets, or valve

body cracks.

Hare Not discussed in

report

PS S&T Req. Not stated 4-16, 17,

20
Table A.1 Gall Report for NPAR Reports Page 76A

Document: NUREG/CR-5419, Aging Assessment of Instrument Air Systems in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Item System StructureJComp Subcomponent Materials Manufac

Document: NUREG/CR-5479, Current Applications of Vibration Monitoring and Neutron Noise Analysis

Reviewed by: Steve U. Choi, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Various This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG/CR-5490, Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components

Reviewed by: AJi Erdemir, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR-pressure Beltine region Not stated 5331-1, SA-508-2, Not stated EMBR/IR Loss of fracture

vessel SA-302 B toughness

2 PWR-pressure BelWine region Not stated 533B-1, SA-508-2, Not stated ENVIR, FAT Chemical or physical

vessel SA-302 B degradation,

cumulative fatigue

damage

3 PWR-pressure Outlet/inlet nozzles Weldments Linde 80, 91,124, Not stated ENVIR, FAT Chemical or physical

vessel and 1092 degradation,

cumulative fatigue

damage

4 PWR-pressure Instrumentation Weldments Unde 80, 91,124, Not stated ENVIR, FAT Chemical or physica

vessel nozzles, CRDM and 1092 degradation,

housing nozzles cumulative fatigue

I_ damage

5 PWR-pressure Closure studs Not stated SA-540 Gr. B24 Not stated ENVIR, FAT Chemical or physical

vessel Class 3 degradation,

cumulative fatigue

damage

6 BWR-pressure Feedwater nozzles Welds SA-508-2, SA-193 Not stated FAT Cumulative fatigue

vessel and safe ends Gr. B7 damage

7 BWR-pressure Recirculation system Inlet/outlet nozzles SA-508-2, SA-193 Not stated CORR/ IGSCC Crack initiation and

vessel and dissimilar metal Gr. B7 growth

welds

8 BWR-pressure Recirculation system Other welds SA-193 Gr. B7 Not stated CORR/IGSCC Crack initiation and

vessel growth

9 BWR pressure Beltline region Not stated Various low carbon Not stated EMBR/IR Loss of fracture

vessel steel toughness

10 BWR pressure Closure studs Not stated SA-540 Gr. B22 or Not stated FAT, WEAR/ FRET Cumulative fatigue

vessel B23 damage, Attrition

11 BWR pressure External attachment Not stated SA-193 Gr. B7 Not stated FAT Cumulative fatigue

vessel welds _damage

12 PWR steam

generator

Tubes Recirculat ng inside

surface

Inconel 600 or 690 Westinghouse,

Combustion

Engineering,

Babcock & Wilcox

CORR/PWSSC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 76B

Document: NUREG/CR-5419, Aging Assessment of Instrument Air Systems in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Effect of Aginq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Cracked piping, leaking joints and Moderate Not discussed in PS S&T Req. Not stated 4-17,20 19

plugged lines cause a diminished or report

complete loss of compressed air.

Incorrect signal. Infrequent Not discussed in PS S&T Req. Not stated 4-17,21 20

report

Document: NUREG/CR-5479, Current Applications of Vibration Monitoring and Neutron Noise Analysis

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Document: NUREG/CR-5490, Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components

Reviewed by: Aii Erdemir, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Irradiation causes a drop in upper-shelf Not stated 10 CFR 50 App. H, 1OCFR50 App. Reduce neutron flux, develop I1-1 1

energy and a shift in nil-ductility transition Reg. Guide 1.99, G & RG 1.99 techniques for in-situ testing [4]

temperature. Rev. 2

Not stated. Not stated 10 CFR 50, App. G, 10CFR50 App. Use state-of-the-art ultrasonic I1-1 2

10 CFR 50.55a, G & RG 1.99 inspection techniques to monitor

IWB-2500, IWB- defect size and location [4]

3000, IWB-5000

Not stated. Not stated 10 CFR 50, IWB- ASME Sec III & Use on-line fatigue monitoring, 11-1 3

2500 Sec Xl IWB evaluate irradiation embrittement

damage [4]

Not stated. Not stated 10 CFR 50, IWB- ASME Sec Ill.& Not stated I1-1 4

2500 Sec Xl IWB

Preload cycles during head replacement Not stated 10 CFR 50, IWB- ASME Sec III & Not stated I1-1 5

and boric acid corrosion can cause 2500 Sec Xl IWB

damage.

High-cycle thermal fatigue caused by Not stated 10 CFR 50, IWB- ASME Sec IIl & Use on-line fatigue monitoring, 11-2 6

feedwater leakage led to the development 2500 Sec XI IWB modify design, revise operating

of cracks in nozzles. procedures [4]

IGSCC initiated in HAZ may propagate Not stated 10 CFR 50, IWB- ASME Sec XI Control hydrogen water chemistry to 11-2 7

into base metal. 2500 IWB reduce IGSCC damage [4]

IGSCC initiated in HAZ may propagate Not stated 10 CFR 50, IWB- ASME Sec X1 Control hydrogen water chemistry to 11-2 8

into base metal by corrosion and/or 2500 IWB reduce IGSCC damage [4]

environmental fatigue.

Irradiation caused a drop in upper shelf Not stated 10 CFR 50 App. H 10CFRSO App. Adopt in-service annealing, 11-2 9

energy and a shift in nil-ductility-transition and G, Reg. guide G & RG 1.99 implement neutron flux reduction

temperature. Welds were more 1.99, Rev.2; 10 CFR program, develop acoustic emission

susceptible to embrittlement than base 50.55a IWB-2500, monitoring to detect crack growth [4]

metal. 3000, 5000

Fatigue and fretting are major aging Not stated 10 CFR 50.55a 1 OCFR50 App. Not stated 11-2 10

concerns for studs. IWB-2500 G, RG 1.99 &

ASME Sec Xl

IWB I

Low-cycle thermal and mechanical fatigue Not stated 10 CFR 50.55a ASME Sec III & Not stated 11-2 11

can cause damage in welds. I IWB-2500 Sec Xl IWB

U-bends, roll transition, and dented tube

regions are susceptible to PWSCC.

Tubes with low mill-annealing temperature

are more susceptible.

Not stated 10 CFR 50.55a

IWB-2500

ASME Sec Xl

IWB & PS TS

req.

Control water chemistry, install filtersi Ill-1 12

[4]
Table A.1 Gall Report for NPAR Reports Page 77A

Document: NUREG/CR-5490, Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components

Reviewed by: All Erdemir, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

13 PWR steam Tubes Recirulating outside Inconel 600 or 690 Westinghouse, CORR/ IGSCC Crack initiation and

generator surface Combustion growth

Engineering,

Babcock & Wilcox

14 PWR steam Tubes Once-through Inconel 600 or 690 Babcock & Wilcox ERO, FAT Wall thinning, loss o

generator outside surface material; cumulative

fatigue damage

15 PWR steam Multiple Various Various inconel and Westing-house, CORR/PIT, FAT, Local loss of

generator ferritic SS Combustion WEAR/ FRET material, cumulative

Engineering, fatigue damage, wall

Babcock & Wilcox thinning, loss of

Piping__material

16 PWR reactor coolan Piping Nozzles and thermal SA 105 Gr. 2, 304N Westinghouse, FAT/THERM Cumulative fatigue

system sleeves SS, Inconel SB-166 Combustion damage

and 168 Engineering,

Babcock & Wilcox

17 PWR reactor coolani Piping Terminal ends Not stated Not stated FAT/THERM Cumulative fatigue

system dissimilar metal damage

I _welds

18 PWR reactor coolant Piping Surge and spray 316 SS, CF8M Combustion FAT/ THERM Cumulative fatigue

system lines Engineering damage

19 PWR reactor coolant Piping Hot and cold legs, Various cast SS or Westinghouse, EMBR/TE Loss of fracture

system cross-over leg, Austenitic SS Combustion toughness

fittings, surge line Engineering,

Babcock & Wilcox

20 Pressure vessel Pressurizer, surge Nozzles and thermal SA-105 Gr. 2, 304N Westinghouse, FAT/THERM, ERO Cumulative fatigue

and spray lines sleeves SS, Inconel SB-168 Combustion damage; wall

Engineering thinning, loss of

I _material

21 Pressure vessel Pressurizer, surge Terminal end Not stated Not stated FAT/THERM Cumulative fatigue

and spray lines dissimilar metal damage

welds

22 Pressure vessel Cast SS piping Surge line, spray CF8A, CF8M, SA Westinghouse, FAT/THERM, Cumulative fatigue

line, valves, fittings 516 Gr. 70, 308L Combustion EMBR/TE, ERO, damage; loss of

and 309L SS Engineering, CORR/BA fracture toughness;

Babcock & Wilcox wall thinning, loss of

material

23 Pressure vessel Vessel wall Not stated A-533, GL B, Class Not stated FAT/THERM Cumulative fatigue

1 damage

24 Emergency diesel Various Multiple Various alloy steels, ALCO, Allis Various Various

generator cast iron, aluminum, Chalmers,

Stellite seats, Caterpillar, and

gaskets, hoses others

Document: NUREG/CR-5491, Shippingport Station Aging Evaluation

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Various This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 77B

Document: NUREG/CR-5490, Regulatory Instrument Review: Management of Aging of LWR Major Safety-Related Components

Reviewed by: Ali Erdemir, ANL Effect of Aaina on Component Function Contrib to Failure Reported oroas ReI.Droas Re~ort Recommendations Paae No. Item

Hot-leg tubes in tube-to-tubesheet crevice Not stated 10 CFR 50.55a ASME Sec Xl Introduce compressive residual Il1-1 13

region are susceptible to IGSCC. IWB-2500 IWB & PS TS stresses [4]

req.

Not stated. Not stated Not stated ASME Sec Xl Control chemistry to prevent II1-1 14

IWB & PS TS concentration of impurities leading to

req. fatigue cracks [4]

Does not provide detailed information on Not stated Not stated ASME Sec Xl Not stated I1-11 15

age-related degradation processes. IWB & PS TS

req.

Low and high-cycle thermal and Not stated 10 CFR 50.55a, ASME Sec III & Maintain full flow in spray line, IV-1 16

mechanical fatigue can cause damage on IWB-2500 Sec XI IWB prevent thermal shock conditions,

various nozzles and thermal sleeve examine welds more frequently [4]

components.

Low- and high-cycle thermal and Not stated 10 CFR 50.55a, ASME Sec III & Use acoustic emission method to IV-1 17

mechanical fatigue can cause cumulative IWB-2500 Sec XI IWB detect crack growth in welded

fatigue damage in dissimilar metal welds. regions [2]

Low- and high-cycle thermal and Not stated 10 CFR 50.55a, ASME Sec III & Use acoustic emission method to IV-1 18

mechanical fatigue can cause cumulative IWB-2500 Sec XI IWB detect crack growth in welded

fatigue damage in surge and spray lines, regions (2]

Large fluctuations in coolant temperature Not stated 10 CFR 50.55a, ASME Sec Xl Develop ultrasonic techniques to IV-1 19

can cause thermal embrittlement in cast IWB-3000 and 5000 IWB detect flaws in cast SS piping [4]

SS piping.

Not discussed. Not stated 10 CFR 50.55a, ASME Sec I1l, Maintain full flow in spray lines, V-1 20

IWB-2500 Sec XI IWB & prevent thermal shock conditions [4]

Assoc. NRC

GC

Not discussed. Not stated 10 CFR 50.55a, ASME Sec Ill, Develop and use improved NDE V-1 21

IWB-2500 Sec XI IWB & methods to monitor the degree of

Assoc. NRC embrittlement [2]

GC

Not discussed. Not stated 10 CFR 50.55a, ASME Sec Ill, Develop and use improved NDE V-1 22

IWB-2500 Sec XI IWB & methods to monitor the degree of

Assoc. NRC embrittiement and to detect flaws;

GC monitor valve leakage [2]

Not discussed. Not stated 10 CFR 50.55a, 10CFR50 App. Not stated V-1 23

IWB-2500 G, ASME Sec

IIII

Does not provide specific detailed Not stated Not stated PS TS Req., Not stated VI-1 24

information on age-related degradation RG 1.9, RG

processes. 1.108

Document: NUREG/CR-5491, Shippingport Station Aging Evaluation

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1
Table A.1 Gall Report for NPAR Reports Page 78A

Document: NUREG/CR-5507, Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities

Reviewed by: David C. Ma, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Not stated Inverters Filter Capacitors Not stated Not stated Electrical Transient Not stated

2 Not stated Inverters Thyristors Not stated Not stated Over heating Not stated

3 Not stated Inverters Fuses Not stated Not stated FAT Not stated

4 Not stated Motors (for pump Stator Insulating, Not stated Not stated FAT/THERM Cumulative Fatigue

and valve operation) Bearing Assemblies, Damage

Rotor

5 Not stated Motors (for pump Stator Insulating, Not stated Not stated ENVIR Chemical, Physical

and valve operation) Bearing Assemblies, Degradation

Rotor

6 Not stated Motors (for pump Stator Insulating, Not stated Not stated VIBR Loosening

and valve operation) Bearing Assemblies,

Rotor

7 Not stated Battery Chargers Capacitors, Not stated Not stated FAT/THERM Overheating

Transformers,

Inductors, Diodes

and Thyristors

8 Not stated Battery Chargers Capacitors, Trans Not stated Not stated Not stated Loss of Connection

formers, Inductors,

Diodes and

Thyristors

9 Not stated Motor Control Circuit Breaker, Not stated Not stated CONTAM Contact surface

Centers Contactor, degradation, set

Transformer, Relays point drift

and Thermal

Overload Devices

10 Component Cooling

Water Systems

(PWRs)

Valves Valve Operator and

Valve Seat

Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 78B

Document: NUREG/CR-5507, Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities

Reviewed by: David C. Ma, ANL

Effect of Anino on Comnonent Function Contrib to Failure Reported proas Rel.proas Report Recomme ndations Paqie No. Item

Failure of filter capacitors directly related Moderate Not stated PS S&T Req. Use of an automatic transfer switch; A 2, A3, 1

to ambient temperatures, applied voltage installation of higher voltage and A 4

and ripple current; failure of thyristors due temperature rated components;

to over heating of thyristor/heat sink forced air cooling and adding

connection caused by improper torque additional temperature monitoring

and thermal fatigue. (More) capabilities [2]

Failure of filter capacitors directly related Moderate Not stated PS S&T Req. Use of an automatic transfer switch; A 2, A3, 2

to ambient temperatures, applied voltage installation of higher voltage and A 4

and ripple current; failure of thyristors due temperature rated components;

to over heating of thyristor/heat sink forced air cooling and adding

connection caused by improper torque additional temperature monitoring

and thermal fatigue. (More) capabilities [2]

Failure of filter capacitors directly related Moderate Not stated PS S&T Req. Use of an automatic transfer switch; A 2, A 3, 3

to ambient temperatures, applied voltage installation of higher voltage and A 4

and ripple current; failure of thyristors due temperature rated components;

to over heating of thyristor/heat sink forced air cooling and adding

connection caused by improper torque additional temperature monitoring

and thermal fatigue. (More) capabilities [2]

The stator insulating system and bearing Moderate Not stated ASME Sec Xl Perform periodic insulation A-7, A-11 4

assemblies are most friequently failed by IWB or IWC, resistance test, partical discharge

aging effects for smaller motors (<200 GL 89-10 & test and power factor test. Perform

lbs.). Large motor failures are primarily Suppl. & P AC/DC leakage test, voltage impulse

due to voltage surges and mechanical test and chemical analysis of lube

stress from centrifugal and magnetic oil. (More) [2]

forces. (More)

The stator insulating system and bearing Moderate Not stated ASME Sec Xl Perform periodic insulation A-7, A-11 5

assemblies are most frequently failed by IWB or IWC, resistance test, partical discharge

aging effects for smaller motors (<200 GL 89-10 & test and power factor test Perform

lbs.). Large motor failures are primarily Suppl. & P AC/DC leakage test, voltage impulse

due to voltage surges and mechanical test and chemical analysis of lube

stress from centrifugal and magnetic oil. (More) [2]

forces. (More)

The stator insulating system and bearing Moderate Not stated ASME Sec XI Perform periodic insulation A-7, A-11 6

assemblies are most frequently failed by IWB or IWC, resistance test, partical discharge

aging effects for smaller motors (<200 GL 89-10 & test and power factor test Perform

lbs.). Large motor failures are primarily Suppl. & P AC/DC leakage test, voltage impulse

due to voltage surges and mechanical test and chemical analysis of lube

stress from centrifugal and magnetic oil. (More) [2]

forces. (More)

Aging impact on battery chrager is Moderate Not stated PS S&T Req. Periodic checking of connection A-1 4, A- 7

minimal. High voltage, current, humidity, between SCR and heat sink; 18

and temperature decrease the life of the monitoring insulation resistance and

battery charger. Failure of the battery winding temperature; periodic

charger could result in depletion of its manual operation and calibration of

associated battery and a potential loss of the circuit breakers and protective

dc power. relays; periodically replace the filter

capacitors. [2]

Aging impact on battery chrager is Moderate Not stated PS S&T Req. Periodic checking of connection A-14, A- 8

minimal. High voltage, current, humidity, between SCR and heat sink; 18

and temperature decrease the life of the monitoring insulation resistance and

battery charger. Failure of the battery winding temperature; periodic

charger could result in depletion of its manual operation and calibration of

associated battery and a potential loss of the circuit breakers and protective

dc power. relays; periodically replace the filter

capacitors. [2]

Significant component failure of the motor Frequent Not stated PS S&T Req. Perform periodic maintenance A-19, A- 9

control center. The failure mode includes inciuding: checking for moisture, oil 22

failure to close, failure to open, failure to and foreign material in cabinet;

operate, open circuit, short circuit, tripped. example for pitting, corrosion, and

Age related degradation of overheating for bus bar; check for

subcomponents has impacted safety arcing or overheating for fuses;

system. inspect contacts for starter; (More)

I 1_ 1 1[2]

Aging is a significant factor in failure of

the CCW system (over 70%). The

failures are dominated by the wear

induced leakage in the valve operator and

valve seat (37% of total failures).

Frequent Not stated ASME Sec Xl

IWB, GL 89-10

& Suppl., & PS

TS

Perform periodic visual inspection,

leakage tests, stem torque check,

torque/limit switch setting and

rurrenttvoltage monitoring. [4]

A-24, A25110
Table A.1 Gall Report for NPAR Reports Page 79A

Document: NUREG/CR-5507, Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities

Reviewed by: David C. Ma, ANL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

II Component Cooling Valves Valve Operator and Not stated Not stated CONTAM Buildup deposits

Water Systems Valve Seat

(PWRs)

12 Component Cooling Valves Valve Operator and Not stated Not stated ERO/CORR Wall thinning, loss ol

Water Systems Valve Seat material

(PWRs)

13 Component Cooling Valves Valve Operator and Not stated Not stated Setpoint Drift Loss of performance

Water Systems Valve Seat

(PWRs)

14 Component Cooling Pumps Seals, Bearings Not stated Not stated WEAR Attrition

Water Systems

(PWRs)

15 Component Cooling Heat Exchangers Tubes, Tube Sheet Not stated Not stated WEAR/DENT Denting

Water Systems

(PWRs)

16 Component Cooling Heat Exchangers Tubes, Tube Sheet Not stated Not stated ERO/CORR Wall thinning, loss o

Water Systems material

(PWRs)

17 Component Cooling Heat Exchangers Tubes, Tube Sheet Not stated Not stated CLOG Blockage of flow

Water Systems passages

(PWRs)

18 Residual Heat Valves, Pumps, Hea Not stated Not stated Not stated WEAR Attrition

Removal Systems Exchangers

(BWRs)

19 Residual Heat Valves, Pumps, Heal Not stated Not stated Not stated CORR Loss of Material

Removal Systems Exchangers

(BWRs)

20 Residual Heat Valves, Pumps, Heal Not stated Not stated Not stated Setpoint Drift (EDS) Loss of function

Removal Systems Exchangers

(BWRs)

21 Residual Heat Valves, Pumps, Heal Not stated Not stated Not stated EMBR Loss of fracture

Removal Systems Exchangers toughness

(BWRs)
Table A.1 Gall Report for NPAR Reports Page 798

Document: NUREG/CR-5507, Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities

Reviewed by: David C. Ma, ANL

Effect of Aaina on Component Function Contrib to Failure Reportedgprogs ReI.progs Report Recommendations Page No. Item

Aging is a significant factor in failure of Moderate Not stated ASME Sec Xl Perform periodic visual inspection, A-24, A- 11

the CCW system (over 70%). The IWB, GL 89-10 leakage tests, stem torque check, 25

failures are dominated by the wear & Suppl., & PS torque/limit switch setting and

induced leakage in the valve operator and TS current/voltage monitoring. [4]

valve seat (37% of total failures).

Aging is a significant factor in failure of Moderate Not stated ASME Sec Xl Perform periodic visual inspection, A-24, A- 12

the CCW system (over 70%). The IWB, GL 89-10 leakage tests, stem torque check, 25

failures are dominated by the wear & Suppl., & PS torque/limit switch setting and

induced leakage in the valve operator and TS current/voltage monitoring. [4]

valve seat (37% of total failures).

Aging is a significant factor in failure of Moderate Not stated ASME Sec XI Perform periodic visual inspection, A-24, A- 13

the CCW system (over 70%). The IWB, GL 89-10 leakage tests, stem torque check, 25

failures are dominated by the wear & Suppl., & PS torque/limit switch setting and

induced leakage in the valve operator and TS current/voltage monitoring. [4]

valve seat (37% of total failures).

Pump failure is dominated by wear Frequent Not stated ASME Sec XI Perform periodic visual inspection A-26, A- 14

induced leakage in the seal in the bearing. IWP & PS TS for leakage; vibration recordings; 27

Req. temperature, quality and level

checking for lube oil, bearing

_temperature check. [4]

The stressors are high pressure, high Frequent Not stated ASME Sec Xl, Perform periodic visual inspections, A-25 15

flow and service water exposure. PS S&T Req., temperature monitoring,

& PS TS Req. acoustic/eddy current test, and bolt

torque check. [2]

The stressors are high pressure, high Moderate Not stated ASME Sec Xl, Perform periodic visual inspections, A-25 16

flow and service water exposure. PS S&T Req., temperature monitoring,

& PS TS Req. acoustic/eddy current test, and bolt

torque check. [2]

The stressors are high pressure, high Moderate Not stated ASME Sec Xl, Perform periodic visual inspections, A-25 17

flow and service water exposure. PS S&T Req., temperature monitoring,

& PS TS Req. acoustic/eddy current test, and bolt

torque check. [2]

More than 50% of the failure in RHR Frequent Not stated ASME Sec XI For valves: Perform periodic valve A-29, A- 18

systems are attributed to aging. Wear is IWB, IWP, stroke tests for valve stroke time and 34

the aging mechanism in the shutdown or IWV, & PS TS valve seat leakage. Periodically

testing mode. Corrosion, set point drift Req. check valve correct position.

and embrittiement are aging mechanisms Monitoring valve degradation by relie

in the standby mode. (More) valve set point verification (5 years),

(More) [2]

More than 50% of the failure in RHR Occasional Not stated ASME Sec Xl For valves: Perform periodic valve A-29, A- 19

systems are attributed to aging. Wear is IWB, IWP, stroke tests for valve stroke time and 34

the aging mechanism in the shutdown or IWV, & PS TS valve seat leakage. Periodically

testing mode. Corrosion, set point drift Req. check valve correct position.

and embrittdement are aging mechanisms Monitoring valve degradation by relie

in the standby mode. (More) valve set point verification (5 years),

(More) [2]

More than 50% of the failure in RHR Frequent Not stated ASME Sec Xl For valves: Perform periodic valve A-29, A- 20

systems are attributed to aging. Wear is IWB, IWP, stroke tests for valve stroke time and 34

the aging mechanism in the shutdown or IWV, & PS TS valve seat leakage. Periodically

testing mode. Corrosion, set point drift Req. check valve correct position.

and embrittiement are aging mechanisms Monitoring valve degradation by reliel

in the standby mode. (More) valve set point verification (5 years),

(More) [2]

More than 50% of the failure in RHR Occasional Not stated ASME Sec Xl For valves: Perform periodic valve A-29, A- 21

systems are attributed to aging. Wear is IWB, IWP, stroke tests for valve stroke time and 34

the aging mechanism in the shutdown or IWV, & PS TS valve seat leakage. Periodically

testing mode. Corrosion, set point drift Req. check valve correct position.

and embrittlement are aging mechanisms Monitoring valve degradation by reliel

in the standby mode. (More) valve set point verification (5 years),

_(More) [2]
Table A.1 Gall Report for NPAR Reports Page 80A

Document: NUREG/CR-5510, Evaluations of Core Melt Frequency Effects Due to Component Aging and Maintenance

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Come Subcomconent Materials Manufacturer ARID mechanism ARD effects

1 Various Various This report does not

provide specific detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG/CR-5515, Light Water Reactor Pressure Isolation Valve Performance Testing

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

I Light water reactor Check and gate This report does not

pressure isolation valves provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or systems. I II

Document: NUREG/CR-5519, Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Control and service Air compressors Running gear Full-floating: Al; Ingersoll-Rand, Joy, WEAR Attrition

air system bearings spherical roller: steel Worthington

or steel-backed CuPb; double roller:

steel or babbitt-lined

steel

2 Control and service Air compressors Seals/packing Elastomer/TFE or Ingersoll-Rand, Joy, WEAR Attrition

air system including piston rod carbon rings Worthington

packing

3 Control and service Air compressors Crosshead Al, tin-faced cast Ingersoll-Rand, Joy, WEAR Attrition

air system iron, babbitted cast Worthington

iron

4 Control and service Air compressors Belts Not stated Not stated WEAR Attrition

air system

5 Control and service Air compressors Piston rod Hardened steel, Ingersoll-Rand, Joy, CORR Loss of material;

air system chrome-plated Worthington corrosion product

hardened steel buildup

Control and service

air system

Air compressors Piston

rider/compression

rings

TFE (teflon) Ingersoll-Rand, Joy,

Worthington

WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 80B

Document: NUREG/CR-5510, Evaluations of Core Melt Frequency Effects Due to Component Aging and Maintenance

Reviewed by: Jeffrey L. Binder, ANL

Effect of Acina on ComDonent Function Contrib to Failure Renorted Droas Rel.Droas Ret~ort Recommendations Paqe No. Item

Document: NUREG/CR-5515, Light Water Reactor Pressure Isolation Valve Performance Testing

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

1

Document: NUREG/CR-5519, Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated. Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,20 1

report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Seals and packing undergo gradual Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,20,21, 2

deterioration due to aging and wear, report compressor or dryer failure is rare. 29

resulting in leaks and reduced An effective surveillance and

compressor output However, sudden monitoring program, can provide

failure of the compressor does not reliable service from the

normally occur, compressors and dryers should no

longer consider in NPAR prog. [2]

Not stated. Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,21 3

report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Belt failures (either breaking or being Not stated Not discussed in PS S&T Req. Loss of the air supply due to 21,26 4

thrown off). report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Not stated. Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,23 5

report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Wear of piston rings would result in

reduced compressor outputs.

Not stated Not discussed in

report

PS S&T Req. Loss of the air supply due to

compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

13,21,22 6
Table A.1 Gall Report for NPAR Reports Page 81A

Document: NUREG/CR-5519, Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

7 Control and service Air compressors Cylinder bore Cast iron, cast semi- Ingersoll-Rand, Joy, CORR Loss of material;

air system steel Worthington corrosion product

buildup

8 Control and service Air compressors Intake/exhaust Stainless steel, Ingersoll-Rand, Joy, FAT Cumulative fatigue

air system valves nodular iron Worthington damage

9 Control and service Air compressors Intake/exhaust Stainless steel, Ingersoll-Rand, Joy, ERO Wall thinning; loss o

air system valves nodular iron Worthington material

10 Control and service Air compressors Cooling water Not stated Not stated CLOG Blockage of flow

air system passages passages

11 Control and service Air dryers Valves Stainless steel Not stated WEAR Attrition

air system

12 Control and service Air dryers Desiccant Silica gel or activatec Not stated ERO Loss of material

air system alumina

13 Control and service Air dryers Filter elements Not stated Not stated CLOG Blockage of flow

air system passages

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Reactor Protection Control Rod Drive Absorber Rods Ag-In-Cd in 304SS Not stated WEAR Attrition

System Tubes

2 Reactor Protection Control Rod Drive Absorber Rods Ag-In-Cd in 304SS Not stated FAT Cumulative fatigue

System Tubes damage

3 Reactor Protection Control Rod Drive

System

Absorber Rods Ag-In-Cd in 304SS

Tubes

Not stated CORR/ IGSCC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 81B

Document: NUREG/CR-5519, Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants

Reviewed by: Steve U. Choi, ANL

Effect of Aginq on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,22;23 7

report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Leaking, broken, or loose valves would Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,22,43 8

result in reduced compressor outputs. report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Leaking, broken, or loose valves would Not stated Not discussed in PS S&T Req. Loss of the air supply due to 13,22,43 9

result in reduced compressor outputs. report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Sediment and dissolved minerals in well Not stated Not discussed in PS S&T Req. Loss of the air supply due to 27 10

water result in scale buildup and blockage report compressor or dryer failure is rare.

in the cooling water passages. An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Valves stuck, leaking, or inoperative. Not stated Not discussed in PS S&T Req. Loss of the air supply due to 24,31 11

report compressor or dryer failure is rare.

An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Not stated. Not stated Not discussed in PS S&T Req. Loss of the air supply due to 17,30,31 12

report compressor or dryer failure is rare. An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

longer consider in NPAR prog. [2]

Failure of the afterfilter resulted in Not stated Not discussed in PS S&T Req. Loss of the air supply due to 30,31 13

desiccant carryover into the instrument air report compressor or dryer failure is rare.

system. An effective surveillance and

monitoring program, can provide

reliable service from the

compressors and dryers should no

_longer consider in NPAR prog. [2]

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Rupture of control rod cladding. Frequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 1

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

Rupture of control rod cladding. Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 2

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

I 1_ 1[2]

Rupture or control rod cladding. Infrequent ASME Sect. III Div.

1

PS S&T Req.

& PS TS Req.

System redesign and selection of

alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

3-12, 3-13 3
Table A.1 Gall Report for NPAR Reports Page 82A

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Reactor Protection Control Rod Drive Split Pin Inconel X-750 Not stated CORR/SCC Crack initiation and

System growth

5 Reactor Protection Control Rod Drive Spider Assembly 304SS Not stated WEAR Attrition

System

6 Reactor Protection Control Rod Drive Spider Assembly 304SS Not stated FAT Cumulative fatigue

System damage

7 Reactor Protection Control Rod Drive Spider Assembly 304SS Not stated CORR/SCC Crack initiation and

System growth

8 Reactor Protection Control Rod Drive Control Rod Guide Inconel X-750 Not stated WEAR Attrition

System Tube

9 Reactor Protection Control Rod Drive Guide Thimble Inconel X-750 Not stated WEAR Attrition

System

10 Reactor Protection Control Rod Drive Pressure Housing 304SS Not stated EMBR/TE Loss of fracture

System toughness

11 Reactor Protection Control Rod Drive Pressure Housing 304SS Not stated CORR Loss of material

System

12 Reactor Protection Control Rod Drive Pressure Housing 304SS Not stated FAT Cumulative fatigue

System damage

13 Reactor Protection Control Rod Drive Latch Assembly Stellite 6, Haynes Not stated WEAR Attrition

System 25, and 304SS

14 Reactor Protection Control Rod Drive Latch Assembly Stellite 6, Haynes Not stated FAT Cumulative fatigue

System 25, and 304SS damage

15 Reactor Protection Control Rod Drive Drive Rod 41OSS Not stated WEAR Attrition

System

16 Reactor Protection Control Rod Drive Drive Rod 410SS Not stated FAT Cumulative fatigue

System damage

17 Reactor Protection Control Rod Drive I Coil Stack Assembly! Electrical insulation Not stated CORR Loss of material

System
Table A.1 Gall Report for NPAR Reports Page 82B

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Loose parts in reactor coolant system and Moderate ASME Sect. IIl Div. PS S&T Req. System redesign and selection of 3-12, 3-13 A

stuck control rod. 1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 E

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 6

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 7

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Stuck control rod. Frequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 a

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2] 3-12_3-1

Stuck control rod and fuel assembly Moderate ASME Sect. Ill Div. PS S&T Req. System redesign and selection of 3-12,3-13 9

mechanical degration. 1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Rod control system leakage and rupture Infrequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 10

of the primary pressure boundary. 1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Rod control system leakage and rupture Infrequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 11

of the primary pressure boundary. 1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance [2]

Rod control system leakage and rupture Infrequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 12

of the primary pressure boundary. 1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 13

1 & PS TS Req. altemate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Infrequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 14

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

_[21

Dropped and/or stuck control rod. Moderate ASME Sect. II Div. PS S&T Req. System redesign and selection of 3-12, 3-13 16

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

:[2]

Dropped and/or stuck control rod. Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 16

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Uropped and/or stuck control rod. Occasional ASME Sect. III Div.

1 PS S&T Req.

& PS TS Req.

System redesign and selection of

alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

3-12,3-13 17
Table A.1 Gall Report for NPAR Reports Page 83A

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Item Sse Structure/Comb Subcomoonent Materials Manufacturer ARD mechanism ARD effects

18 Reactor Protection Control Rod Drive Coil Stack Assembly Electrical insulation Not stated EMBR/TE Breakdown

System

19 Reactor Protection Control Rod Drive Coil Stack Assembly Electrical Connector Not stated CORR Loss of Material

System

20 Reactor Protection Control Rod Drive Coil Stack Assembly Electrical Connector Not stated WEAR Attrition

System

21 Reactor Protection Control Rod Drive Coil Stack Assembly Electrical Connector Not stated FAT Cumulative fatigue

System damage

22 Reactor Protection Control Rod Drive Rod Control System Semi-conductor Not stated CORR Loss of Material

System & Logic Cabinets devices, electronic

components, and

connectors

23 Reactor Protection Control Rod Drive Rod Control System Semi-conductor Not stated FAT Cumulative fatigue

System & Logic Cabinets devices, electronic damage

components, and

connectors

24 Reactor Protection Control Rod Drive Rod Control System Semi-conductor Not stated WEAR Attrition

System & Logic Cabinets devices, electronic

components, and

connectors

25 Reactor Protection Control Rod Drive Rod Position Electrical wiring, Not stated CORR Loss of Material

System Indication Systems insulation,

connectors, semiconductor devices,

and electromechanical

components

26 Reactor Protection Control Rod Drive Rod Position Electrical wiring, Not stated WEAR Attrition

System Indication Systems insulation,

connectors, semiconductor devices,

and electromechanical

components

27 Reactor Protection Control Rod Drive Rod Position Electrical wiring, Not stated FAT Cumulative fatigue

System Indication Systems insulation, damage

connectors, semiconductor devices,

and electromechanical

components

Document: NUREG/CR-5558, Generic Issue 87: Flexible Wedge Gate Valve Test Program, Phase 11 Results and Analysis

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 BWR water cleanup Motor-operated This report does not

system and the high- flexible wedge gate provide specific

pressure coolant valve detailed information

injection (HPCI) on age-related

steam line degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 83B

Document: NUREG/CR-5555, Aging Assessment of the Westinghouse PWR Control Rod Drive System

Reviewed by: John W. Holland, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported Droas Rel.proqs Report Recommendations Pacie No. Item

Rupture of control rod cladding. Frequent ASME Sect. Ill Div. PS S&T Req. System redesign and selection of 3-12, 3-13 18

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 19

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2_

Dropped and/or stuck control rod. Frequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 20

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Dropped and/or stuck control rod. Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 21

1 & PS TS Req. alternate materials, improve

ventilation to electronics, and

improve monitoring and maintenance

[2]

Single/multiple rod drop, inability to move Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12,. 3-13 22

rods on demand, erroneous rod 1 & PS TS Req. alternate materials, improve

movement, incorrect or spurious rod ventilation to electronics, and

control system failure alarms, and improve monitoring and maintenance

incorrect rod position indication. [2]

Single/multiple rod drop, inability to move Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 23

rods on demand, erroneous rod 1 & PS TS Req. alternate materials, improve

movement, incorrect or spurious rod ventilation to electronics, and

control system failure alarms, and improve monitoring and maintenance

incorrect rod position indication. [2]

Single/multiple rod drop, inability to move Frequent ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 24

rods on demand, erroneous rod1 & PS TS Req. alternate materials, improve

movement, incorrect or spurious rod ventilation to electronics, and

control system failure alarms, and improve monitoring and maintenance

incorrect rod position indication. [2]

Incorrectfinaccurate rod position Occasional ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 25

information and possibly a false dropped 1 & PS TS Req. alternate materials, improve

rod indication, ventilation to electronics, and

improve monitoring and maintenance

[2]

IncorrectAnaccurate rod position Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 26

information and possibly a false dropped 1 & PS TS Req. alternate materials, improve

rod indication, ventilation to electronics, and

improve monitoring and maintenance

[2]

Incorrect/inaccurate rod position Moderate ASME Sect. III Div. PS S&T Req. System redesign and selection of 3-12, 3-13 27

information and possibly a false dropped 1 & PS TS Req. alternate materials, improve

rod indication. ventilation to electronics, and

improve monitoring and maintenance

[2]

Document: NUREG/CR-5558, Generic Issue 87: Rexible Wedge Gate Valve Test Program, Phase II Results and Analysis

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

i 1
Table A.1 Gall Report for NPAR Reports Page 84A

Document: NUREG/CR-5583, Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems - Wear and Impact Tests

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR core discharge Swing check valves Hinge pin The hinge pin and Not stated WEAR Attrition

system the bushing are

made of cobaltbased alloys

(Haynes Stellite #25

and Stoody #6

respectively)

2 Auxiliary feedwater Tilting disc check Hinge pin 410 stainless steel Not stated WEAR Attrition

turbine steam supply valves hinge pin and

system Stellite-6 bushing

3 PWR feedwater Swing check valves Disc stud A217 MCC Pacific Valve FAT Cumulative fatigue

system Company damage

Document: NUREG/CR-5587, Approaches for Age-Dependent Probabilistic Safety Assessments with Emphasis on Prioritization and Sensitivity Studies

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Accumulators, Actuator, check This report does not

auxiliary feedwater, valve, diesel provide specific

high/low pressure generator, motor detailed information

injection, safety driven pump, motor on age-related

injection system, low operated valve, degradation

pressure safety relief valve, processes for

recirculation, primary turbine driven pump specific nuclear

pressure relief, components or

onsite emergency systems.

power, main steam

system I I I II

Document: NUREG/CR-5612, Degradation Modeling with Applications to Aging and Maintenance Effectiveness Evaluations

Reviewed by: Steve U. Choi, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Various This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Auxiliary feedwater Pump parts Not stated Not stated WEAR Attrition

pumps

2 Various Auxiliary feedwater Turbine steam Not stated Not stated CORR Loss of material and

pumps supply valve stems corrosion product

buildup

3 Various Auxiliary feedwater Diesel fuel oil line Not stated Not stated FAT Cumulative fatigue

pumps damage

No stte WA AttrItio

4 various Auxiliary reeawater

pumps

Bearings Not statea Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 84B

Document: NUREG/CR-5583, Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems - Wear and Impact Tests

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Excessive wear of the hinge pin bushings Frequent Not discussed in ASME Sec XI Not stated 41, 42 1

had caused some of the bushings to report IWB & IWV

completely wear through, and the debris

of the worn-through bushings for some

valves were found downstream, resulting

in massive change-out of components.

The 410 SS hinge pins had almost Frequent Not discussed in ASME Sec XI Not stated 44, 45 2

completely wom through due to the disc report IWB, IWV &

oscillation caused by the low rate of steam PS TS Req.

flow, resulting in material modifications to

Stellite-6 vs. Stellite-6.

The disc stud/nut connection had Frequent Not discussed in ASME Sec XI Not stated 45,46, 3

fractured due to repeated impact against report IWB & IWV C.1

the open stop, which had allowed the disc

to separate from the hinge and

subsequently, a water hammer event

occurred in the horizontal feedwater line

caused by failed check valves. I

Document: NUREG/CR-5587, Approaches for Age-Dependent Probabilistic Safety Assessments with Emphasis on Prioritization and Sensitivity Studies

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

I

Document: NUREG/CR-5612, Degradation Modeling with Applications to Aging and Maintenance Effectiveness Evaluations

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: NUREG!CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1 2

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 3

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in

report

ASME Sec Xl

IWB, IWP, &

PS TS Req.

Recommendations for research,

inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

2 4
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Page 85A

Item Sse StructureJComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

5 Various Auxiliary feedwater Bearings Not stated Not stated CORR Loss of material

pumps

6 Various Auxiliary feedwater Impellers Not stated Not stated WEAR Attrition

pumps

7 Various Auxiliary feedwater Thrust balancer Not stated Not stated WEAR Attrition

pumps

8 Various Auxiliary feedwater Thrust balancer Not stated Not stated WEAR/GALL Attrition

pumps

9 Various Check valves Body assembly, Not stated Not stated WEAR Attrition

hinge pins, discs

and seats

10 Various Check valves Body assembly, Not stated Not stated ERO Wall thinning; loss o

hinge pins, discs material

and seats

11 Various Check valves Body assembly, Not stated Not stated CORR Loss of material

hinge pins, discs

and seats

12 Various Check valves Hinge arms Not stated Not stated WEAR Attrition

13 Various Motor-operated Gear, shaft, stem Not stated Not stated WEAR Attrition

valves nut, drive sleeve,

seal, clutch

mechanism, motor

operator switch

gear/cam, yoke

bushing, valve stem,

and stem packing

14 Various Motor-operated Bearings, valve Not stated Not stated WEAR Attrition

valves obturator, obturator

guide, and valve seat

15 Various Motor-operated Bearings, valve Not stated Not stated CORR Loss of material

valves obturator, obturator

guide, and valve seal

16 Various PORVs and block Valve disks and Not stated Not stated WEAR Attrition

valves seats

17 Various PORVs and block Valve disks and Not stated Not stated WEAR/GALL Attrition

valves seats

18 Various Snubbers "Blank" Not stated Not stated WEAR/FRET Attrition

19 Various Snubbers "Blank" Not stated Not stated CORR Loss of material

201 Various Solenoid-operated

valves

Insulating material Polymer Not stated EMBR/IR Loss of fracture

toughness
Table A.1 Gall Report for NPAR Reports Page 85B

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Effect of Aaina on Comnonent Function Cont~rib to Failure Reno rted Droas Rela.roas Reoort Recommendations Paae No. Item .......... of • ........ nun - - r ... - - - - to-- - -. - .------ . . r ..... r- - -- Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 5

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 6

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 2 7

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 8

report IWB, IWP, & inspection, maintenance, operations,

PS TS Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 9

report IWB, IWV or inspection, maintenance, operations,

PS S&T Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1 10

report IWB, IWV or inspection, maintenance, operations,

PS S&T Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 11

report IWB, IWV or inspection, maintenance, operations,

PS S&T Req. and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 12

report IWB, IWV or inspection, maintenance, operations,

PS S&T Req. and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 13

report IWB, IWV, & inspection, maintenance, operations,

GL 89-10 & and design/test are listed on p. 2-6.

Suppl. [4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 14

report IWB, IWV, & inspection, maintenance, operations,

GL 89-10 & and design/test are listed on p. 2-6.

Suppl. [4]

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1 15

report IWB, IWV, & inspection, maintenance, operations,

GL 89-10 & and design/test are listed on p. 2-6.

Supp_. [4]_

PORVs stuck-open or with leakage. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1 16

report IWB & IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6. [4) PORVs stuck-open or with leakage. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1 17

report IWB & IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Loosening of fasteners and an increase in Not stated Not discussed in ASME Sec Xl Recommendations for research, 1,2 18

clearances between mating parts. report ISTD inspection, maintenance, operations,

and design/test are listed on p. 2-6.

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1,2 19

report ISTD inspection, maintenance, operations,

and design/test are listed on p. 2-6.

_ _ _ _ _ _ _ _ .. . . . ... . .. .. ..... . ... [41.. ...

NOi stated. Not stated Not discussed in

report

ASME Sec XI

IWB, IWV

Recommendations for research,

nspection, maintenance, operations,

and design/test are listed on p. 2-6.

'4]

1 20
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Page 86A

Item System StructureJComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

21 Various Solenoid-operated Insulating material Polymer Not stated ELE-TEMP Chemical and

valves physical degradation

221 Various Solenoid-operated O-rings, Not stated Not stated AGRCHEM Chemical

valves diaphragms, degradation

gaskets, seals, core

seats

23 Various Solenoid-operated O-rings, Not stated Not stated EMBR/IR Loss of fracture

valves diaphragms, toughness

gaskets, seals, core

seats

24 Various Solenoid-operated O-rings, Not stated Not stated ELE-TEMP Chemical and

valves diaphragms, physical degradation

gaskets, seals, core

seats

25 Various Solenoid-operated Metallic parts Not stated Not stated WEAR Attrition

valves

26 Various Solenoid-operated Metallic parts Not stated Not stated FAT Cumulative fatigue

valves damage

27 Various Solenoid-operated Valve orifice Not stated Not stated FAT Cumulative fatigue

valves damage

28 Component cooling Valves Valve seats and Not stated Not stated WEAR Attrition

water system (PWR) operators

29 Component cooling Pumps Seals and bearings Not stated Not stated WEAR Attrition

water system (PWR)

30 CRD system RCAA Cladding, RCAA to Not stated Westinghouse WEAR Attrition

(Westinghouse) CRDM coupling

31 CRD system RCAA Spider assembly Not stated Westinghouse FAT Cumulative fatigue

(Westinghouse) vane weld damage

32 CRD system RCAA Reactor internal Not stated Westinghouse CORR/SCC Crack initiation and

(Westinghouse) components growth

33 CRD system CRDM Operating coil Not stated Not stated ELE-TEMP Chemical and

physical degradation

34 CRD system CRDM Cast housings Not stated Not stated EMBR Loss of fracture

toughness

35 CRD system CRDM Latch assembly Not stated Not stated CONTAM Buildup of deposits

36 CRD system Power and logic Temperature Not stated Not stated CONTAM Buildup of deposits

cabinets sensitive

components and

heat sinks

CRD system Power and logic

cabinets

Temperature

sensitive

components and

heat sinks

Not stated Not stated ELE-TEMP Chemical and

physical degradation
Table A.1 Gall Report for NPAR Reports Page 86B

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 21

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 22

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 23

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6. [4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 24

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 25

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 26

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 27

report IWB, IWV inspection, maintenance, operations,

and design/test are listed on p. 2-6.

Leakage. Not stated Not discussed in ASME Sec XI Recommendations for research, 1 28

report IWV, PS TS inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6. [4]

Leakage. Not stated Not discussed in ASME Sec X1 Recommendations for research, 1 29

report IWP, PS TS inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 30

report IWB, PS TS inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 2 31

report IWB, PS TS inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6.

_[4]

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 2 32

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 33

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[3]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 234

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 35

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 236

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

1(2]

Not stated. Not stated Not discussed in

report

PS TS Req. Recommendations for research,

inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

2 37
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Page 87A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

38 CRD system RPI Detector coil Not stated Not stated ELE-TEMP Chemical and

physical degradation

39 CRD system Cable and Connectors Not stated Not stated CORR Corrosion product

connectors buildup

40 CRD system Cable and In-containment Not stated Not stated ELE-TEMP Chemical and

connectors cables physical degradation

41 CRD system Cable and Connector mating Not stated Not stated WEAR Attrition

connectors pins

42 BWR high pressure Valves and valve Not stated Not stated Not stated WEAR Attrition

injection systems operators

(HPCI and HPCS)

43 BWR high pressure Turbines Not stated Not stated Not stated WEAR Attrition

injection systems

(HPCI and HPCS)

44 BWR high pressure Turbines Not stated Not stated Not stated CONTAM Buildup of deposits

injection systems

(HPCI and HPCS)

45 BWR high pressure Turbines Not stated Not stated Not stated FAT Cumulative fatigue

injection systems damage

(HPCI and HPCS)

46 BWR high pressure Instrumentation and Not stated Not stated Not stated CORR Loss of material and

injection systems controls corrosion product

(HPCI and HPCS) buildup

47 BWR high pressure Instrumentation and Not stated Not stated Not stated CONTAM Buildup of deposits

injection systems controls

(HPCI and HPCS)

48 BWR high pressure Pumps Not stated Not stated Not stated WEAR Attrition

injection systems

(HPCI and HPCS)

49 BWR high pressure Pipe Not stated Not stated Not stated CORR Loss of material

injection systems

(HPCI and HPCS)

50 BWR high pressure Pipe Not stated Not stated Not stated ENVIR Degradation

injection systems

(HPCI and HPCS)

51 BWR high pressure Pipe Not stated Not stated Not stated FAT Cumulative fatigue

injection systems damage

(HPCI and HPCS)

52 BWR high pressure Pipe Not stated Not stated Not stated CONTAM Buildup of deposits

injection systems

(HPCI and HPCS)

53 BWR high pressure Pipe supports Not stated Not stated Not stated ENVIR Degradation

injection systems

(HPCI and HPCS)

54 High pressure

injection system

(PWR)

HPIS components Not stated Not stated Not stated CORR Loss of

mateial;corrosion

product buildup
Table A.1 Gall Report for NPAR Reports Page 87B

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL Effect of Aaina on Component Function Contrib to Failure Remoorted nroas Rel.oroas Renort Recommendations Paae No. Item Effect of Auin---an....... C- nt Func - n - - - tre .. -- ..... -r--. Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 38

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 39

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 40

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Not stated. Not stated Not discussed in PS TS Req. Recommendations for research, 2 41

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Degraded operation. Frequent Not discussed in ASME Sec. XI Recommendations for research, 1, 2 42

report IWB, IWV, GL inspection, maintenance, operations,

89-10 & Suppl. and design/test are listed on p. 2-6.

[4]

Degraded operation. Infrequent Not discussed in PS S&T Req. Recommendations for research, 1,2 43

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Degraded operation. Rare Not discussed in PS S&T Req. Recommendations for research, 1,2 44

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Degraded operation. Rare Not discussed in PS S&T Req. Recommendations for research, 1,2 45

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Loss of function. Occasional Not discussed in PS S&T Req. Recommendations for research, 1,2 46

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Loss of function. Infrequent Not discussed in PS S&T Req. Recommendations for research, 1, 2 47

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Low injection flow, Frequent Not discussed in ASME Sec XI Recommendations for research, 1, 2 48

report IWB & IWP inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Leakage. Frequent Not discussed in ASME Sec XI Recommendations for research, 1,2 49

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Leakage. Infrequent Not discussed in ASME Sec XI Recommendations for research, 1,2 50

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Leakage. Infrequent Not discussed in ASME Sec XI Recommendations for research, 1,2 51

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Leakage. Infrequent Not discussed in ASME Sec X1 Recommendations for research, 1,2 52

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Failure to operate. Infrequent Not discussed in ASME Sec XI Recommendations for research, 1,2 53

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

1[4]

Not stated. Not stated Not discussed in

report

ASME Sec XI

IWB

Recommendations for research,

inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

1,2 54
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Page 88A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

55 High pressure Thermal sleeves and Not stated Not stated Not stated FAT Cumulative fatigue

injection system nozzles damage

(PWR)

56 High pressure Elbows Not stated Not stated Not stated FAT/THERM Cumulative fatigue

injection system damage

(PWR)

57 Instrument air Compressors Not stated Not stated Not stated WEAR Attrition

system

58 Instrument air Compressors Not stated Not stated Not stated FAT Cumulative fatigue

system damage

59 Instrument air Air dryers Not stated Not stated Not stated CLOG Blockage of flow

system passages

60 Instrument air Air dryers Not stated Not stated Not stated CORR Loss of material and

system corrosion product

buildup

61 Instrument air Air dryers Not stated Not stated Not stated CONTAM Buildup of deposits

system

62 Instrument air Filters Not stated Not stated Not stated CLOG Blockage of flow

system passages

63 Instrument air Filters Not stated Not stated Not stated WEAR Attrition

system

64 Instrument air Valves Not stated Not stated Not stated WEAR Attrition

system

65 Instrument air Valves Not stated Not stated Not stated CORR Loss of material and

system corrosion product

buildup

66 Instrument air Piping Not stated Not stated Not stated ERO/CORR Wall thinning;loss of

system material

67 Service water Piping Not stated Not stated Not stated CORR Loss of material and

system (open) corrosion product

buildup

68 Service water Piping Not stated Not stated Not stated BIO Buildup of deposits

system (open)

69 Service water Heat exchangers Not stated Not stated Not stated BIO Buildup of deposits

system (closed)

70 Service water Heat exchangers Not stated Not stated Not stated CORR Loss of material and

system (closed) corrosion product

buildup

71 Service water

system (closed)

Valves Not stated Not stated Not stated CORR Loss of material and

corrosion product

buildup
Table A.1 Gall Report for NPAR Reports Page 88B

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Effect nf Anin on nmnnnnt FuInction Contrih to Failure Reno rtL:d nrofl5 Rel.nroczs Report Recommendations PaeN.Item

Not stated. Not stated Not discussed in ASME Sec Xl Recommendations for research, 1,2 55

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated. Not stated Not discussed in ASME Sec XI Recommendations for research, 1, 2 56

report IWB inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

D)egraded operation, failure to Moderate Not discussed in PS S&T Req. Recommendations for research, 1,2 57

load/unload, leaks (air and oil). report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

_ _. [2]

Degraded operation, failure to Infrequent Not discussed in PS S&T Req. Recommendations for research, 1, 2 58

load/unload, leaks (air and oil). report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Delivery of compressed air with a higher Occasional Not discussed in PS S&T Req. Recommendations for research, 1,2 59

dew point than specified, desiccant and report inspection, maintenance, operations,

moisture carry-over, and design/test are listed on p. 2-6.

[4]

Delivery of compressed air with a higher Infrequent Not discussed in PS S&T Req. Recommendations for research, 1, 2 60

dew point than specified, desiccant and report inspection, maintenance, operations,

moisture carry-over, and design/test are listed on p. 2-6.

[4]

Delivery of compressed air with -a higher Infrequent Not discussed in PS S&T Req. Recommendations for research, 1,2 61

dew point than specified, desiccant and report inspection, maintenance, operations,

moisture carry-over, and design/test are listed on p. 2-6.

(4]

Reduced air flow. Frequent Not discussed in PS S&T Req. Recommendations for research, 1,2 62

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Reduced air flow. Rare Not discussed in PS S&T Req. Recommendations for research, 1, 2 63

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Fail to open/close valves. Occasional Not discussed in PS S&T Req. Recommendations for research, 1,2 64

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Fail to open/close valves Occasional Not discussed in PS S&T Req. Recommendations for research, 1, 2 65

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Plugged piping, leaks Not stated Not discussed in PS S&T Req. Recommendations for research, 1, 2 66

report inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[2]

Not stated Not stated Not discussed in PS S&T Req., Recommendations for research, 1, 2 67

report PS TS Req. inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4]

Not stated Not stated Not discussed in PS S&T Req., Recommendations for research, 1, 2 68

report PS TS Req. inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4] I1 2

Not stated Not stated Not discussed in ASME Sec Xl Recommendations for research, 1,2 69

report or PS S&T inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6.

[4]

Not stated Not stated Not discussed in ASME Sec XI Recommendations for research, 1, 2 70

report or PS S&T inspection, maintenance, operations,

Req. and design/test are listed on p. 2-6. 1[4]

Not stated Not stated Not discussed in

report

ASME Sec XI

or PS S&T

Req.

Recommendations for research,

inspection, maintenance, operations,

and design/test are listed on p. 2-6.

[4)

1,2 71
Table A.1 Gall Report for NPAR Reports Page 89A

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

721 Recirculating SWS Valves and sensors Not stated Not stated 1Not stated CORR Loss of material and

I I corrosion product

Document: NUREG/CR-5646, Piping System Response During High Level Simulated Seismic Tests at the Heissdampfreaktor Facility (SHAM Test Facility)

Reviewed by: David C. Ma, ANL

Item System Structure/Coml Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Piping System Motor Operated Not stated Not stated Mov-Umitorque; Not stated Not stated

Gate Valve, snubbers-Pacific

Snubbers, Rigid Scientific; Rigid

Struts, Piping struts & pipingITT'Grinnell

Document: NUREG/CR-5693, Vol. 2, Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Component cooling Heat exchanger Tubes Admiralty metals, Not stated CORR Loss of material

water systems in brass, bronze or

pressurized water copper-nickel

reactors

2 Component cooling Heat exchanger Tubes Admiralty metals, Not stated ERO Loss of material

water systems in brass, bronze or

pressurized water copper-nickel

reactors

3 Component cooling Heat exchanger Tubes Admiralty metals, Not stated WEAR Loss of material

water systems in brass, bronze or

pressurized water copper-nickel

reactors

4 Component cooling Heat exchanger Tubes Admiralty metals, Not stated CLOG Flow blockage

water systems in brass, bronze or

pressurized water copper-nickel

reactors

51 Component cooling Heat exchanger Tubesheets Admiralty metals, Not stated CORR Loss of material

water systems in brass, bronze or

pressurized water copper-nickel

reactors

6 Component cooling Heat exchanger Tubesheets Admiralty metals, Not stated ERO Loss of material

water systems in brass, bronze or

pressurized water copper-nickel

reactors

71 Component cooling Heat exchanger Channel/bonnet Carbon steels Not stated CORR Loss of material

water systems in heads

pressurized water

reactors

8 Component cooling Heat exchanger Channel/bonnet Carbon steels Not stated ERO Loss of material

water systems in heads

pressurized water

reactors

9 Component cooling Valves Seats Bronze, SS316, Not stated CORR Loss of material

water systems in SS410, stellite,

pressurized water elastomers

reactors

10 Component cooling Valves Seats Bronze, SS316, Not stated ERO Loss of material

water systems in SS410, stellite,

pressurized water elastomers

reactors

11 Component cooling Valves Seats Bronze, SS316, Not stated CONTAM Loss of desired

water systems in SS410, stellite, surface properties

pressurized water elastomers

reactors

Component cooling

water systems in

pressurized water

reactors

Valves Plugs Bronze, SS316,

SS410, stellite

Not stated CORR Loss of material
Table A.1 Gall Report for NPAR Reports

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Steve U. Choi, ANL

Page 89B

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in PS S&T Req. Recommendations for research, 11,2 72

report Iand inspection, maintenance, operations,

design/test are listed on p. 2-6. ([4]II I

Document: NUREG/CR-5646, Piping System Response During High Level Simulated Seismic Tests at the Heissdampfreaktor Facility (SHAM Test Facility)

Reviewed by: David C. Ma, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported oroos Rel.proas Report Recommendations Page No. Item

This report discusses the effects of Not stated Not stated ASME Sec XI Not stated 1

increasing levels of seismic excitation on IWB, IWV, ja full scale, in situ piping system ISTD, GL 89-

containing a naturally aged motor 10 & Suppl. [operated valve. (More)

Document: NUREG/CR-5693, Vol. 2, Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Causes tube leakage and possible Moderate Not discussed in ASME Sec Xl, More study of preventative measures 3-5, 3-6 1

radiation release. report PS TS Req. [4]

Causes tube leakage and possible Moderate Not discussed in ASME Sec Xl, More study of preventive measures 3-5, 3-6, 2

radation release, report PS TS Req. [3] 7-7

Causes tube leakage and possible Moderate Not discussed in ASME Sec Xl, More study of preventive measures 3-5, 3-6, 3

radiation release, report PS TS Req. [3] 7-7

Cause reduced flow and heat transfer. Frequent Not discussed in ASME Sec Xl, More study of preventive measures 3-5, 3-6, 4

report PS TS Req. [3] 7-7

Loss of material can cause wall thinning Occasional Not discussed in ASME Sec X1, More study of preventive measures 3-5, 3-6, 5

and with time leakage or corrosion report PS TS Req. [3] 7-7

products fouling tubes.

Loss of material can cause wall thinning Occasional Not discussed in ASME Sec XI, More study of preventive measures 3-5, 3-6, 6

and leakage, report PS TS Req. [3] 7-7

Corrosion products an cause tube fouling Occasional Not discussed in ASME Sec XI, More study of preventive measures 3-5, 3-6, 7

and reduced heat transfer or wall thinning report PS TS Req. [3] 7-7

leading to leakage.

Loss of material causes wall thinning and Occasional Not discussed in ASME Sec X1, More study of preventive measures 3-5, 3-6, 8

possible leakage. report PS TS Req. [3] 7-7

Causes valve leakage due to change in Moderate Not discussed in ASME Sec XI More study of preventive measures 1-7, 3-12, 9

seat geometry. report IWV & PS TS [3] 7-6

Req.

Causes valve leakage due to change in Moderate Not discussed in ASME Sec XI More study of preventive measures 1-7, 3-12, 10

seat geometry. report IWV & PS TS [3] 7-6

Req.

Foreign contaminants accumulate on seat Moderate Not discussed in ASME Sec XI More study of preventive measures 1-9, 3-12, 11

causing valve to stick or failure to seat report IWV & PS TS [3] 7-6

producing leakage. Req.

Lauses tailure ot valve to seat and

leakage.

Occasional Not discussed in

report

ASME Sec Xl

IWV & PS TS

Req.

More study of preventive measures

[3]

1-7, 3-10,

7-6

12
Table A.1 Gall Report for NPAR Reports Page 90A

Document: NUREG/CR-5693, Vol. 2, Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Item System Structure/ComD Subcomponent Materials Manufacturer ARD mechanism ARD effects

13 Component cooling Valves Plugs Bronze, SS316, Not stated ERO Loss of material

water systems in SS410, stellite

pressurized water

reactors

14 Component cooling Valves Packing Asbestos, PTFE, Not stated WEAR Loss of material

water systems in aramid, graphite

pressurized water

reactors

15 Component cooling Valves Body Carbon steel or Not stated CORR Loss of material

water systems in stainless steel

pressurized water

reactors

16 Component cooling Pneumatic valve Diaphragms Neoprene or other Not stated EMBR Loss of fracture

water systems in operator actuators natural and synthetic toughness

pressurized water rubbers reinforced

reactors with fibers

17 Component cooling Pneumatic valve Diaphragms Neoprene or other Not stated FAT Cumulative fatigue

water systems in operator actuators natural and synthetic damage

pressurized water rubbers reinforced

reactors with fibers

18 Component cooling Pneumatic valve O-rings Neoprene or other Not stated EMBR Loss of fracture

water systems in operator actuators natural or synthetic toughness

pressurized water rubbers reinforced

reactors with fibers

19 Component cooling Pneumatic valve O-rings Neoprene or other Not stated WEAR Causes structural

water systems in operator actuators natural or synthetic deterioration

pressurized water rubbers reinforced

reactors with fibers

20 Component cooling Centrifugal pumps Mechanical seals Stainless steel, Not stated WEAR Causes loss of seal

water systems in tungsten carbide, material

pressurized water lead bronze, carbon

reactors and many others

including rubber in

secondary seals

21 Component cooling Centrifugal pumps Mechanical seals Stainless steel, Not stated ELE-TEMP Causes seal

water systems in tungsten carbide, distortion or cracking

pressurized water lead bronze, carbon

reactors and many others

including rubber in

secondary seals

22 Component cooling Centrifugal pumps Bearings Tin bronze, steel, Not stated WEAR Causes loss of

water systems in lead-bronze, or bearing material

pressurized water aluminum alloy

reactors

23 Component cooling Centrifugal pumps Bearings Tin bronze, steel, Not stated FAT Cumulative fatigue

water systems in lead-bronze, or damage

pressurized water aluminum alloy

reactors

24 Component cooling Centrifugal pumps Bearings Tn bronze, steel, Not stated ELE-TEMP Causes distortion

water systems in lead-bronze, or

pressurized water aluminum alloy

reactors

25 Component cooling Centrifugal pumps Packings Asbestos, PTFE, Not stated WEAR Causes loss of

water systems in aramid/PTFE, material

pressurized water graphite

reactors

26 Component cooling Centrifugal pumps Gaskets Non-asbestos in Not stated Not stated Causes leakage

water systems in newer pumps

pressurized water

reactors

Document: NUREG/CR-5699, ORNL-6666/V1,

Reviewed by: Jeffrey L. Binder, ANL .

Item System Structure/Comp

Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Subcomponent Materials

1 BWR Control Rod Control Rod Drive Flange and plugs Gauge F304

Drive System Mechanism Stainless
Table A.1 Gall Report for NPAR Reports Page 90B

Document: NUREG/CR-5693, Vol. 2, Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors

Reviewed by: Ken E. Kasza, ANL

Effect of Aoina on ComDonent Function Contrib to Failure ReDorted Drous Rel.proqs Report Recommendations Paae No. Item

Causes failure of valve to seat and Occasional Not discussed in ASME Sec Xl More study of preventive measures 1-7, 3-10, 13

leakage, report IWV & PS TS [3] 7-6

Req.

Relative motion between stem and Moderate Not discussed in ASME Sec XI More study of preventative measures 1-7, 1-8, 14

packing causes loss of material and report IWV & PS TS [2] 1-9, 3-9,

leaking which can result in a radiation Req. 3-10, 7-6

release.

Corrosion can cause wall thinning through Not stated Not discussed in ASME Sec Xl Need for improved monitoring to 3-11,8-4, 15

loss of material in body resulting in report IWB or IWC, detect aging and preventive 7-6

leakage. IWV & PS TS measures [2]

Req.

Contamination of air supply with dirt or Frequent Not discussed in ASME Sec Xl Improved surveillance and better 1-7, 1-10, 16

moisture and elevated temperatures report IWV & PS TS choice of materials to reduce aging 3-15, 3-17

cause diaphragm to deteriorate and Req. [2]

actuator to malfunction.

Repeated cycling of actuator causes Frequent Not discussed in ASME Sec Xl Improved surveillance and better 1-7, 1-10, 17

fatigue of diaphragm and failure resulting report IWV & PS TS choice of materials to reduce aging 3-15, 3-17

in loss of actuator control of valves. Req. [2]

Contamination of air supply or elevated Moderate Not discussed in ASME Sec Xl Improved surveillance and better 1-7, 1-10, 18

temperatures cause loss of O-ring report IWV & PS TS choice of materials to reduce aging 3-15, 3-17

integrity and air leakage resulting in erratic Req. [2]

actuator control or loss of control.

Wear of O-ring causes air leakage and Moderate Not discussed in ASME Sec Xl Improved surveillance and better 1-7, 1-10, 19

actuator sluggishness to respond or lack report IWV & PS TS choice of materials to reduce aging 3-15, 3-17

of response. Req. [2]

Wear of seals causes leakage of water Frequent Not discussed in ASME Sec Xl Improved surveillance and better 1-6, 1-9, 20

and excessive shaft play. report IWP & PS TS choice of materials [4] 3-23, 3-

Req. 24, 3-25,

3-26

Seal distortion or cracking causes water Frequent Not discussed in ASME Sec Xl Improved surveillance and better 21

leakage, report IWP & PS TS choice of materials [4]

Req.

Excessive bearing wear resulting from Moderate Not discussed in ASME Sec XI Improved surveillance and better 1-6, 1-9, 22

shaft alignment problems, loss of report IWP & PS TS materials [4] 3-23, 3-

lubricant or dirt can cause pump seizure. Req. 27, 3-24

Cyclic stressing or operating for long Moderate Not discussed in ASME Sec Xl Improved surveillance [2] 1-6, 1-9, 23

periods outside optimum design flow report IWP & PS TS 3-23, 3-

limits can cause bearing breakage. Req. 27, 3-24

Loss of bearing coolant or lubricant can Occasional Not discussed in ASME Sec XI Not stated 24

cause thermal distortion of bearing and report IWP & PS TS

possible seizure. Req.

Wear of packing by rotating shaft can Moderate Not discussed in ASME Sec Xl Use improved packing materials and 1-6, 1-9, 25

lead to pump leakage and possible report IWP & PS TS monitor for leaks [2] 3-23

release of radioactive water. Req.

Faulty gasket can lead to leakage of water Infrequent Not discussed in ASME Sec XI Not stated 1-6, 1-9, 26

which may be radioactive, report IWP & PS TS 3-23

Req.

Document: NUREG/CR-5699, ORNL-6666N1, Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Reviewed by: Jeffrey L Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

None stated. Rare None stated PS TS Req. & None given

PS S&T Req.

5
Table A.1 Gall Report for NPAR Reports Page 91A

Document: NUREG/CR-5699, ORNL-6666/V1, Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Como SubcomDonent Materials Manufacturer ARD mechanism ARD effects

2 BWR Control Rod Control Rod Drive Cylinder, tube, and Wrought 304 GE CORR/IGSCC Crack initiation and

Drive System Mechanism flange assembly stainless in earlier growth

designs; Cast 304L

collet retainer tube;

stainless steel in

replacements and

newer designs

3 BWR Control Rod Control Rod Drive Piston tube Type 304 stainless GE Not stated Not stated

Drive System Mechanism in earlier designs;

ASME SA-249 or

SA-479 Grade XM19 stainless in late

designs

4 BWR Control Rod Control Rod Drive Index tube Type 304 stainless GE Not stated Not stated

Drive System Mechanism in earlier designs;

ASME SA-249 or

SA-479 Grade XM19 stainless in late

designs

5 BWR Control Rod Control Rod Drive Collet piston Type 304 stainless GE Not stated Not stated

Drive System Mechanism

6 BWR Control Rod Control Rod Drive Collet fingers, Inconel alloy X-750 GE Not stated Not stated

Drive System Mechanism coupling spud, collet

spring

7 BWR Control Rod Control Rod Drive Drive and stop Graphitar GE WEAR; EMBR/TE Attrition; Loss of

Drive System Mechanism piston seals and fracture toughness

bushings

8 BWR Control Rod Control Rod Drive Piston seal C- Inconel alloy X-750 GE Not stated Not stated

Drive Mechanism Mechanism springs

9 BWR Control Rod Control Rod Drive Piston rings Haynes 25 GE Not stated Not stated

Drive Mechanism Mechanism

10 BWR Control Rod Control Rod Drive Ball check valve Haynes stellite or GE Not stated Not stated

Drive Mechanism Mechanism tungsten carbide

base alloy

11 BWR Control Rod Control Rod Drive Elastomeric O-ring Ethylene propylene Not stated Not stated Not stated

Drive Mechanism Mechanism seals

12 BWR Control Rod Control Rod Drive Drive piston head 17-4PH GE Not stated Not stated

Drive Mechanism Mechanism (precipitation

hardened) stainless

steel

13 BWR Control Rod Control Rod Drive O-rings Teflon-coated, type Not stated Not stated Not stated

Drive Mechanism Mechanism 304 stainless steel

14 BWR Control Rod Control Rod Drive Inner Filter Not stated GE Not stated Not stated

Drive Mechanism Mechanism

15 BWR Control Rod Hydraulic Control Accumulator Not stated GE WEAR Attrition

Drive Mechanism Unit (HCU) nitrogen charging

valve packing

16 BWR Control Rod Hydraulic Control Accumulator Not stated GE WEAR Attrition

Drive Mechanism Unit (HCU) nitrogen charging

valve stem

17 BWR Control Rod Hydraulic Control Scram discharge Not stated Dresser and Vogt CORR/IGSCC Crack initiation and

Drive Mechanism Unit (HCU) rise isolation valve growth

stem and disks

18 BWR Control Rod Hydraulic Control Scram water Carbon Steel w/ GE CORR Loss of inner plating

Drive Mechanism Unit (HCU) accumulator tank chromium inner material

plating

19 BWR Control Rod Hydraulic Control Scram water Teflon GE ERO Loss of material

Drive System Unit (HCU) accumulator tank

inlet and outlet valve

seats

20 BWR Control Rod

Drive System

Hydraulic Control

Unit (HCU)

Scram water

accumulator tank

inlet and outlet valve

diaphragms

Buna-N rubber

reinforced with nylon

GE WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 91B

Document: NUREG/CR-5699, ORNL-6666N1, Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Component Function Contrib to Failure Reported nrogs Rel.proas Report Recommendations Page No. Item

IGSCC leads to cracks in the collet Rare None stated PS TS Req. & Weekly surveillance testing. 55 2

housing region of flow holes, near the PS S&T Req. Successful response of a CRD to a

internal section change, and in the vicinity normal withdrawal signal at normal

of the attachment weld. Circumferential drive operating pressures is a

separation of the tube is possible but not conclusive test of collet retainer tube

likely. integrity at all reactor operating

_conditions. [4]

Not stated. Not stated None stated PS TS Req. & None stated 5 3

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 4

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 5

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 6

PS S&T Req.

Seal degradation leads to increase in Moderate None stated PS TS Req. & GE has improved graphitar seals 28 7

pressure required to move the drive. PS S&T Req. available as of 1992 [1]

Not stated. Not stated None stated PS TS Req. & None stated 5 8

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 9

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 10

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 11

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 12

PS S&T Req.

Not stated. Not stated None stated PS TS Req. & None stated 5 13

PS S&T Reg,

Not stated. Not stated None stated PS TS Req. & None stated 31 14

PS S&T Req.

Wear of the valve packing can cause Infrequent None stated PS TS Req. & Use GE supplied packing tool when 27 15

leakage of the nitrogen accumulator and PS S&T Req. installing. (4]

loss of driving pressure for CRD.

Wear of the valve stem can cause Rare None stated PS TS Req. & Correct practice of operating valve 27 16

leakage of the nitrogen accumulator and PS S&T Req. with foot instead of hand [4]

loss of driving pressure for CRD.

IGSCC can cause separation of the disk Rare None stated PS TS Req. & None stated 27 17

from the stem and loss of valve function. PS S&T Req.

This can cause failure for the CRD to

scram.

Corrosion of the chromium plating by Infrequent None stated PS TS Req. None stated 27 18

high-chloride, low-PH water conditions

can lead to water seepage and corrosion

of the tank. Loss of function of this

subcomponent can lead to control rod

insertion. I

Erosion by flakes of plating from a Rare None stated PS TS Req. None stated 27 19

corroded accumulator can collect and

erode the seat. This will cause leakage

and control rod insertion.

Increased wear caused by improper

installation and will cause eventual

leakage. This will cause control rod

insertion.

Infrequent None stated PS TS Req. None stated 27 20
Table A.1 Gall Report for NPAR Reports Page 92A

Document: NUREG/CR-5699, ORNL-6666N1, Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Reviewed by: Jeffrey L. Binder, ANL

Item Svstem Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

21 BWR Control Rod Hydraulic Control Scram pilot valve Buna-N rubber GE ELE-TEMP; WEAR Physical

Drive System Unit (HCU) seats degradation; Attrition

22 BWR Control Rod Hydraulic Control Scram pilot valve Not stated GE ELE-TEMP Physical

Drive System Unit (HCU) solenoid coils degradation;

Thermal distortion

23 BWR Control Rod Balance of control Pump bearings Not stated Not stated VIBR Loosening

Drive System rod drive system

24 BWR Control Rod Balance of control Electrical Not stated Not stated WEAR Attrition

Drive System rod drive system Components

25 BWR Control Rod Balance of control Pump gaskets and Not stated Not stated WEAR Attrition

Drive System rod drive system seals

Document: NUREG/CR-5706, Potential Safety-Related Pump Loss: An Assessment of Industry Data

Reviewed by: Ken E. Kasza, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Safety Pump This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

I_ _ _ I_ I _ _ _ I systems. I I I _I

Document: NUREG/CR-5720, Motor-Operated Valve Research Update

Reviewed by: Ken E. Kasza, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Various Motor-operated This report does not

valves provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems. I I _I _I

Document: NUREG/CR-5754, Boiling Water Reactor Internals Aging Degradation Study, Phase 1

Reviewed by: All Erdemir, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Reactor internals Jet pump assembly Pump holddown Inconel X-750 Not stated CORR/IGSCC Crack initiation and

beams growth

2 Reactor internals Core spray system Spray sparger Type 304 SS Not stated CORR/IGSCC Crack initiation and

growth

3 Reactor internals Shroud support Access hole cover Inconel 600 Not stated CORR/IGSCC Crack initiation and

growth

4 Reactor internals Feedwater sparger Not stated Types 304 and Not stated VIBR; FAT/THERM Crack initiation and

316NG SS growth; Cumulative

fatigue damage

5 Reactor internals Jet pump assembly Jet pump Inconel X-750 Not stated VIBR Crack initiation and

growth

Pressure vessel Control rod drive

(CRD) housing

Stub tube Type 304 SS Not stated CORR/IGSCC Crack initiation and

growth
Table A.1 Gall Report for NPAR Reports Page 92B

Document: NUREG/CR-5699, ORNL-6666N1, Vol. 1, Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aaina on Comnonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Paue No. Item

Prolonged exposure to service Infrequent None stated PS TS Req. None stated 28 21

temperature causes degradation and

increases in CRD scram times.

Prolonged exposure to service Infrequent None stated PS TS Req. Periodic monitoring of surface 28 22

temperature causes degradation and temperatures with industrial

increases in CRD scram times, pyrometers. [2]

Not stated. Occasional None stated PS TS Req. None stated 31 23

Loss of device setpoint and calibration. Occasional None stated PS TS Req. None stated 36 24

Loss of seal capability and pump head. Infrequent None stated PS TS Req. None stated 31 25

Document: NUREG/CR-5706, Potential Safety-Related Pump Loss: An Assessment of Industry Data

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Document: NUREG/CR-5720, Motor-Operated Valve Research Update

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: NUREG/CR-5754, Boiling Water Reactor Intemals Aging Degradation Study, Phase 1

Reviewed by: Ali Erdemir, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

A combination of low heat treatment Not stated ASME B&PV Code, ASME Sec Xl- Solution heat-treat at higher 30 1

temperature (which led to the sensitization Section XI IWB temperature, reduce preloads in the

of the beam material) and high preloads beam bolts [4]

on the beam bolt led to IGSCC of jet

pump holddown beams.

Cold working and sensitization during Not stated ASME B&PV Code, ASME Sec Xl- Not stated 30 2

fabrication of the spargers and stresses Section II & XI IWB

incurred during installation were the major

factors leading to the IGSCC of core

spray spargers.

Welding induced residual stresses and Not stated ASME B&PV Code, ASME Sec Xl- Not stated 30 3

crevice conditions on the welded area led Section XI IWB

to the formation of through-the-wall cracks

in the welds through IGSCC. I

Flow induced vibration and rapid thermal Not stated ASME B&PV Code, ASME Sec Xl- Use new sparger with a thigh slip-fit 31 4

cycling led to the development of fatigue Section III IWB oint [4]

cracks in the vicinity of the feedwater

nozzle comer and sparger.

Flow induced vibration led to the Not stated ASME B&PV Code, ASME Sec Xl- Redesign and use a stronger 32 5

development of fatigue cracks in the Section III IWB holddown beam [4]

pump support system. I I

Welding induced residual stresses led to

the development of through-the-wall

cracks in the HAZ of the J-welds that join

the CRD housing to the top of the stub

tube.

Not stated ASME B&PV Code,

Section Ill & Xl

PS TS Req. Not stated 31
Table A.1 Gall Report for NPAR Reports Page 93A

Document: NUREG/CR-5754, Boiling Water Reactor Internals Aging Degradation Study, Phase 1

Reviewed by: Ail Erdemir, ANL

Item Svatem Sf'utcturAICnmn Subnomnonnnt Mntprizla Man ufntcturer ARfl mechanism ARfl effects

7 Pressure vessel In-core neutron flux Guide tube Type 304 SS Not stated CORR/IASCC Crack initiation and

monitor growth

8 Pressure vessel In-core neutron flux Local power range Type 304 SS Not stated VIBR Loosening, crack

monitor monitor dry tube initiation and growth

9 Reactor internals Multiple Various Typically Type 304 Not stated CORR/SCC Crack initiation and

SS growth

10 Reactor internals Multiple Various Typically Type 304 Not stated FAT Cumulative fatigue

SS damage

11 Reactor internals Multiple Various Typically Type 304 Not stated CORR/SCC; FAT; Crack initiation and

SS EMBR; ERO; growth, cumulative

CREEP fatigue damage, loss

of fracture

toughness, (More)

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Non-Power-Cycle Emergency diesel Shell Not stated Not stated ERO/CORR Wall thinning

heat exchangers generator heat

exchanger (mainly

shell-and tube type)

2 Non-Power-Cycle Emergency diesel Tubes Not stated Not stated ERO/CORR Wall thinning

heat exchangers generator heat

exchanger (mainly

shell-and tube type)

3 Non-Power-Cycle Emergency diesel Tubes Not stated Not stated CONTAM Buildup of deposits

heat exchangers generator heat

exchanger (mainly

shell-and tube type)

4 Non-Power-Cycle Emergency diesel Tubes Not stated Not stated FAT Cumulative fatigue

heat exchangers generator heat damage

exchanger (mainly

I shell-and tube type)

5 Non-Power-Cycle Emergency diesel Tubesheet Not stated Not stated CORR Loss of material

heat exchangers generator heat

exchanger (mainly

shell-and tube type)

6 Non-Power-Cycle Emergency diesel Heads/nozzles Not stated Not stated ERO/CORR Wall thinning

heat exchangers generator heat

exchanger (mainly

shell-and tube type)

7 Non-Power-Cycle Containment cooling Shell Carbon steel Not stated ERO/CORR Wall thinning

heat exchangers heat exchanger

(mainly shell- and

tube type)

E Non-Power-Cycle

heat exchangers

Containment cooling

heat exchanger

(mainly shell- and

tube type)

Shell Carbon steel Not stated ' CONTAM Buildup of deposits
Table A.1 Gall Report for NPAR Reports Page 93B

Document: NUREG/CR-5754, Boiling Water Reactor Internals Aging Degradation Study, Phase 1

Reviewed by: Ali Erdemir, ANL

Effect of Aaina on Comaonent Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Combination of a high level of neutron Not stated ASME B&PV Code, PS TS Req. Not stated 31 7

irradiation and the presence of high Section III & XI

tensile stresses due to crud and oxides

that accumulated in crevices between the

guide plug and the thin tube segment are

considered as the major causes of the

IASCC of tubes.

Row induced vibration generated by the Not stated ASME B&PV Code, PS TS Req. Install a flow deflector [4] 32-33 8

low-pressure coolant flow resulted in Section III

fatigue failures in dry tubes.

This report lists several other BWR Not stated ASME B&PV Code, ASME Sec Ill & Install a flow deflector [4] 32 9

internal components (e.g., shroud head Section III XI IWB

bolts, access hole cover, core spray line

internal piping, steam dryer support ring,

jet pump assembly riser pipe, control

plates, IRM/SRM dry tubes, neutron

source holder) (More)

This report lists several other BWR ASME Sec III & 33 10

internal components (e.g., steam dryer, XI IWB

steam dryer sensing line, jet pump

restrainer gate, in-core neutron flux

monitor dry tube, feedwater sparger) with

reported fatigue failures.

This report lists several BWR internal ASME Sec III & 27 11

components by name as being XI IWB

susceptible to SCC, creep, fatigue,

embrittiement, and erosion, however, it

does not provide an in-depth discussion

of these aging processes for any of the

components listed.

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Leakage in shell wail could jeopardize Occasional Not stated PS S&T Req. Not stated 18, 21 1

cooling of emergency diesel generators.

Leakage across tubes can produce con- Occasional Not stated PS S&T Req. Not stated 19, 23 2

lamination of shell and tube side fluids.

Buildup of foreign contaminants in tubes Occasional Not stated PS S&T Req. Not stated 18,21 3

such as scale, silt, debris, and biological

organisms can cause partial or complete

blockage of flow and reduced heat

transfer.

Ructuating loads caused by flow induced Infrequent Not stated PS S&T Req. Not stated 19, 23 4

vibration or thermal cycling can crack

tubes and produce contamination of shell

and tube side fluids.

Corrosion of the tube-to-tubesheet welds Infrequent Not stated PS S&T Req. Not stated 19, 23 5

can cause leakage between the primary

and secondary fluids.

Wall thinning caused by erosion/corrosion Occasional Not stated PS S&T Req. Not stated 18, 23 6

can lead to external leakage.

Leakage in shell wall could jeopardize Not stated Not stated ASME Sec XI, Not stated 4, 6,18 7

post-accident containment cooling PS S&T Req.,

through degrading of spray headers water PS TS Req.

supply. I I

Buildup of foreign contaminants in shell

such as scale, silt, debris, and biological

organisms can cause partial or complete

blockage of flow

Occasional Not stated ASME Sec Xl,

PS S&T Req.,

PS TS Req.

Not stated 18
Table A.1 Gall Report for NPAR Reports Page 94A

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

9 Non-Power-Cycle Containment cooling Tubes Austenitic stainless Not stated ERO/CORR Wall thinning

heat exchangers heat exchanger steel

(mainly shell- and

tube type)

10 Non-Power-Cycle Containment cooling Tubes Austenitic stainless Not stated CONTAM Buildup of deposits

heat exchangers heat exchanger steel

(mainly shell- and

tube type)

11 Non-Power-Cycle Containment cooling Tubes Austenitic stainless Not stated FAT Cumulative fatigue

heat exchangers heat exchanger steel damage

(mainly shell- and

tube type)

12 Non-Power-Cycle Containment cooling Tubesheet Not stated Not stated CORR Loss of material

heat exchangers heat exchanger

(mainly shell- and

tube type)

13 Non-Power-Cycle Containment cooling Heads/nozzles Not stated Not stated ERO/CORR Wall thinning

heat exchangers heat exchanger

(mainly shell- and

tube type)

14 Non-Power-Cycle Residual heat Shell Carbon steel Not stated ERO/CORR Wall thinning

heat exchangers removal heat

exchanger (mainly

shell- and tube type)

15 Non-Power-Cycle Residual heat Gasket Not stated Not stated ELE-TEMP Chemical or physica.

heat exchangers removal heat degradation

exchanger (mainly

shell- and tube type)

16 Non-Power-Cycle Residual heat Tubes Austenitic stainless Not stated ERO/CORR Wail thinning

heat exchangers removal heat steel

exchanger (mainly

shell- and tube type)

17 Non-Power-Cycle Residual heat Tubes Austenitic stainless Not stated CONTAM Buildup of deposits

heat exchangers removal heat steel

exchanger (mainly

shell- and tube type)

18 Non-Power-Cycle Residual heat Tubes Austenitic stainless Not stated FAT Cumulative fatigue

heat exchangers removal heat, steel damage

exchanger (mainly

shell- and tube type)

19 Non-Power-Cycle Residual heat Tubesheet Carbon steel Not stated CORR Loss of material

heat exchangers removal heat

exchanger (mainly

shell- and tube type)

20 Non-Power-Cycle Residual heat Heads/nozzles Not stated Not stated ERO/CORR Wall thinning

heat exchangers removal heat

exchanger (mainly

shell- and tube type)

21 Non-Power-Cycle Component cooling Shell Carbon steel Not stated ERO/CORR Wail thinning

heat exchangers water heat

exchanger (mainly

shell-and tube type)

22 Non-Power-Cycle Component cooling Gasket Not stated Not stated ELE-TEMP Chemical or physical

heat exchangers water heat degradation

exchanger (mainly

shell-and tube type)

23 Non-Power-Cycle Component cooling Tubes Admiralty, 90-10 Cu- Not stated ERO/CORR Wall thinning

heat exchangers water heat Ni, aluminum-brass,

exchanger (mainly or titanium

shell-and tube type)

24 Non-P-'ower-L;ycle

heat exchangers Component cooling

water heat

exchanger (mainly

shell-and tube type)

Tubes Admiralty, 90-10 CuNi, aluminum-brass,

or titanium

Not stated CONTAM Buildup of deposits
Table A.1 Gall Report for NPAR Reports Page 94B

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Proqs Rel.proqs Report Recommendations Page No. Item

Leakage across tubes can cause reduced Moderate Not stated ASME Sec Xl, Not stated 18, 23 9

flow for emergency cooling PS S&T Req.,

PS TS Req.

Buildup of foreign contaminants in tubes Occasional Not stated ASME Sec X1, Not stated 18, 21 10

such as scale, silt, debris, and biological PS S&T Req.,

organisms can cause partial or complete PS TS Req.

blockage of flow and reduced heat

transfer

Ructuating loads caused by flow induced Occasional Not stated ASME Sec X1, Not stated 18 11

vibration or thermal cycling can crack PS S&T Req.,

tubes and produce contamination of shell PS TS Req.

and tube side fluids

Corrosion of the tube-to-tubesheet welds Infrequent Not stated ASME Sec XI, Not stated 19 12

can cause leakage between the primary PS S&T Req.,

and secondary fluids PS TS Req.

Erosion/corrosion caused wall thinning Infrequent Not stated PS S&T Req., Not stated 18,19 13

=an cause leakage external to the heat PS TS Req.

oxchanger

Leakage in shell wall could reduce Infrequent Not stated PS S&T Req., Not stated 4,18 14

shutdown coolant effectiveness PS TS Req.

Gasket failure from elevated temperature Moderate Not stated PS S&T Req., Not stated 18, 22 15

zauses leakage. PS TS Req.

Leakage across tubes can cause reduced Moderate Not stated ASME Sec XI, Not stated 19,21,23 16

low for emergency cooling PS S&T Req.,

PS TS Req.

Buildup of foreign contaminants in tubes Occasional Not stated ASME Sec XI, Not stated 18, 21 17

such as scale, silt, debris, and biological PS S&T Req.,

Drganisms can cause partial or complete PS TS Req.

blockage of flow and reduced heat

transfer

Fluctuating loads caused by flow induced Infrequent Not stated ASME Sec XI, Not stated 18,19 18

vibration or thermal cycling can crack PS S&T Req.,

tubes and produce contamination of shell PS TS Req.

and tube side fluids

Corrosion of the tube-to-tubesheet welds Infrequent Not stated ASME Sec XI, Not stated 19 19

an cause leakage between the primary PS S&T Req.,

and secondary fluids PS TS Req.

Erosion/corrosion caused wall thinning Infrequent Not stated ASME Sec XI, Not stated 18, 19 20

can cause leakage external to the heat PS S&T Req.,

exchanger PS TS Req.

Leakage in shell wall could cause Infrequent Not stated PS S&T Req., Not stated 4, 18 21

contamination PS TS Req.

Gasket failure from elevated temperature Frequent Not stated PS S&T Req., Not stated 18,22 22

:auses leakage and possible PS TS Req.

Dontamination

Leakage across tubes can cause reduced Frequent Not stated ASME Sec XI, Not stated 19, 21,23 23

Hlow for emergency cooling and possible PS S&T Req.,

contamination PS TS Req.

Buildup of foreign contaminants in tubes

such as scale, silt, debris, and biological

organisms can cause partial or complete

blockage of flow and reduced heat

transfer

Frequent Not stated ASME Sec XI,

PS S&T Req.,

PS TS Req.

Not stated 18,21 24
Table A.1 Gall Report for NPAR Reports Page 95A

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp SubcomDonent Materials Manufacturer ARD mechanism ARD effects

25 Non-Power-Cycle Component cooling Tubes Admiralty, 90-10 Cu- Not stated FAT Cumulative fatigue

heat exchangers water heat Ni, aluminum-brass, damage

exchanger (mainly or titanium

shell-and tube type)

26 Non-Power-Cycle Component cooling Tubesheet Carbon steel Not stated CORR Loss of material

heat exchangers water heat

exchanger (mainly

shell-and tube type)

27 Non-Power-Cycle Component cooling Heads/nozzles Not stated Not stated ERO/CORR Wall thinning

heat exchangers water heat

exchanger (mainly

shell-and tube type)

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Combustion Control Element Control Elements Clad-Inconel 625 CE WEAR; CORR/ Attrition; Crack

Engineering (CE) Assemblies SCC initiation and growth

Control Rod Drive

System

2 Combustion Control Element Fuel Assembly Zircaloy-4 CE WEAR Attrition

Engineering (CE) Assemblies Guide Tubes

Control Rod Drive

System

3 Combustion Control Element Upper Guide Stainless Steel CE WEAR; EMBR/IR; Attrition; Loss of

Engineering (CE) Assemblies Structure-Spider FAT fracture toughness;

Control Rod Drive Cumulative fatigue

System damage

4 Combustion Control Element Motor Housing 403 Stainless Steel CE EMBR; CORR; FAT Loss of fracture

Engineering (CE) Drive Mechanisms Assembly Ni-Cr-Fe alloy toughness; Loss of

Control Rod Drive (CEDM) material; Cumulative

System fatigue damage

5 Combustion Control Element Motor Assembly- High Cobalt Alloy CE WEAR; FAT; Attrition; Cumulative

Engineering (CE) Drive Mechanisms Latches, Links and CONTAM fatigue damage;

Control Rod Drive (CEDM) Pins Buildup of deposits

System

6 Combustion Control Element Upper Pressure Type 316 Stainless CE EMBR; CORR; FAT Loss of fracture

Engineering (CE) Drive Mechanisms Housing Assembly toughness; Loss of

Control Rod Drive (CEDM) material; Loss of

System fracture toughness

7 Combustion Control Element Extension Shaft Type 304 Stainless, CE WEAR; FAT; Attrition; Loss of

Engineering (CE) Drive Mechanisms Chromium plated CORR/SCC fracture toughness;

Control Rod Drive (CEDM) Crack initiation and

System growth

8 Combustion Control Element Vent Valves Type 440 Stainless CE CORR; FAT; Corrosion product

Engineering (CE) Drive Mechanisms Steel, Type 316 WEAR; EMBR/TE buildup; Cumulative

Control Rod Drive (CEDM) Stainless Steel Seat fatigue damage;

System Attrition; Loss of

I _fracture toughness

9 Combustion Control Element Coil Stack Assembly Copper wire CE CORR; WEAR Loss of material;

Engineering (CE) Drive Mechanisms - Coils insulated with high Attrition

Control Rod Drive (CEDM) temperature enamel

System vacuum impregnated

with high

temperature varnish

10 Combustion CEDM Control Control Element Not stated CE These components

Engineering (CE) Systems Drive Control are referred to INEL

Control Rod Drive System and Control for review.

System Power Programmer

11 Combustion CEDM Control Rack and Pinion Not stated CE These components

Engineering (CE) Systems Control System are referred to INEL

Control Rod Drive for review.

System I _

12 uombusuton

Engineering (CE)

Control Rod Drive

System

UEA Hod Position

Indication

Heed Switch

Position Transmitter

Assembly

Not stated CE These components

are referred to INEL

for review.
Table A.1 Gall Report for NPAR Reports Page 95B

Document: NUREG/CR-5779, Aging of Non Power Cycle Heat Exchangers Used in Nuclear Power Plants

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Fluctuating loads caused by flow induced Occasional Not stated ASME Sec XI, Not stated 18,19 25

vibration or thermal cycling can crack PS S&T Req.,

tubes and produce contamination of shell PS TS Req.

and tube side fluids

Corrosion of the tube-to-tubesheet welds Infrequent Not stated ASME Sec XI, Not stated 19 26

can cause leakage between the primary PS S&T Req.,

and secondary fluids and contamination PS TS Req.

Erosion/corrosion caused wall thinning Moderate Not stated ASME Sec Xl, Not stated 18, 19 27

can cause leakage external to the heat PS S&T Req.,

exchanger and contamination PS TS Req.

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Clad cracking and wash out of the poison. Occasional None stated PS S&T Req., Rod exposure tracking; Increased 5-13 1

PS TS Req. visual inspection [2]

Cracking of the tube wall. Frequent None stated PS S&T Req., Add guide tube sleeving; Increase 5-13 2

PS TS Req. inspection [21

Cracking of the guide causing rod drops. Rare None stated PS S&T Req., None given 5-13 3

PS TS Req.

Housing cracking leads to primary coolant Frequent None stated PS S&T Req., Improve leakage monitoring [2] 5-13 4

leakage (SBLOCA) and jamming of the PS TS Req.

drive mechanism.

Failure of these sub-components will lead Rare None stated PS S&T Req., Increase inservice inspection [2] 5-13 5

to dropping or locking of the control PS TS Req.

element

Housing cracking leads to primary coolant Frequent None stated PS S&T Req., Improve leakage monitoring [2] 5-13 6

leakage (SBLOCA) and jamming of the PS TS Req.

drive mechanism.

Shaft cracking will lead to locking of the Occasional None stated PS S&T Req., Increase inservice inspection [2] 5-13 7

mechanical operation. PS TS Req.

Loss of valve function and primary coolant Rare None stated PS S&T Req., Increase inservice inspection [2] 5-13 8

leakage. PS TS Req.

Loss of coil function will lead to dropped, Rare None stated PS S&T Req., Increase inservice inspection [2] 5-13 9

slipped or immovable control elements. PS TS Req.

PS S&T Req., 10

PS TS Req.

PS S&T Req., 11

PS TS Req.

PS S&T Req.,

PS TS Req.

12
Table A.1 Gall Report for NPAR Reports Page 96A

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Item System StructureIComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

13 Combustion CEA Rod Position Pulse Count Position Not stated CE These components

Engineering (CE) Indication Indication System are referred to INEL

Control Rod Drive for review.

System

14 Combustion CEDM Cooling Fans Not stated CE Not stated Not stated

Engineering (CE) System

Control Rod Drive

System

15 Combustion CEDM Cooling Cooling Shroud Sheet metal CE CORR/BA Loss of material

Engineering (CE) System

Control Rod Drive

System

16 Combustion CEDM Cooling Instrumentation Not stated CE Not stated Not stated

Engineering (CE) System

Control Rod Drive

System 1

17 Babcock & Wilcox Control Rod Control Rod Type 304 Stainless B&W CORR/SCC; WEAR Crack initiation and

(B&W) Control Rod Assemblies Cladding growth; Attrition

Drive System

.18 Babcock & Wilcox Control Rod Fuel Assembly Zircaloy-4 B&W WEAR Attrition

(B&W) Control Rod Assemblies Guide Tubes

Drive System

19 Babcock & Wilcox Control Rod Upper Internal Grade CF3M B&W CORR/SCC; Crack initiation and

(B&W) Control Rod Assemblies Brazement Stainless WEAR; EMBR/IR; growth; Attrition;

Drive System Assemblies-Spider FAT Loss of fracture

toughness;

Cumulative fatigue

I _damage

20 Babcock & Wilcox Control Rod Drive Motor Tube Low alloy steel clad B&W EMBR/TE; CORR; Loss of fracture

(B&W) Control Rod Mechanisms with Inconel or Type FAT toughness; Loss of

Drive System (CRDM) 403 stainless material; Cumulative

fatigue damage

21 Babcock & Wilcox Control Rod Drive Stator Coils Copper Wire, Dow B&W Referred to INEL for

(B&W) Control Rod Mechanisms Corning 997 review.

Drive System (CRDM) Varnish, Kapton,

Nomex, Silicone

I Rubber

22 Babcock & Wilcox Control Rod Drive Vent Valve O-rings Stainless Steel B&W CORR; WEAR; Corrosion product

(B&W) Control Rod Mechanisms FAT; EMBR/TE buildup; Attrition;

Drive System (CRDM) Cumulative fatigue

damage; Loss of

fracture toughness

23 Babcock & Wilcox Control Rod Drive Rotor Assembly- Stellite Ni-Cr-Fe B&W WEAR; FAT; Attrition; Cumulative

(B&W) Control Rod Mechanisms roller nuts, segment Alloy, Type 403 CONTAM fatigue damage;

Drive System (CRDM) arms, springs Stainless Steel Buildup of deposits

24 Babcock & Wilcox Control Rod Drive Leadscrew 17-4 PH Stainless B&W WEAR; FAT; Attrition; Cumulative

(B&W) Control Rod Mechanisms Steel CORR/SCC fatigue damage;

Drive System (CR DM) Crack initiation and

growth;

25 Babcock & Wilcox CRDM Power and Power Supplies Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems review.

Drive System

26 Babcock & Wilcox CRDM Power and Programmers Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems review.

Drive System

27 Babcock & Wilcox CRDM Power and Trip Breakers Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems review.

Drive System

28 Babcock & Wilcox CRDM Power and Programmer Drive Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems Motors review.

Drive System

29 Babcock & Wilcox CRA Rod Position Absolute Position Not stated B&W Referred to I NEL for

(B&W) Control Rod Indication Indication System review.

Drive System I

30 Babcock & Wilcox

(B&W) Control Rod

Drive System

CRA Rod Position

Indication

Relative Rod

Position Indication

Not stated B&W Referred to INEL for

review.
Table A.1 Gall Report for NPAR Reports Page 96B

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aqina on Component Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Paqe No. Item

PS S&T Req., 1:

PS TS Req.

Loss of rod drive mechanism cooling Not stated None stated PS S&T Req., Improve leakage monitoring [2) 5-13 14

capacity leading to inoperable CRDM or PS TS Req.

rod drops.

Loss of rod drive mechanism cooling Not stated None stated PS S&T Req., Improve leakage monitoring [2] 5-13 15

capacity leading to inoperable CRDM or PS TS Req.

rod drops.

Loss of rod drive mechanism cooling Not stated None stated PS S&T Req., Improve leakage monitoring [2] 5-13 1E

capacity leading to inoperable CRDM or PS TS Req.

rod drops.

Clad cracking and wash out of the poison. Occasional None stated PS S&T Req., Rod exposure tracking; Increased 5-14 17

PS TS Req. visual inspection [2]

Cracking of the tube wall. Rare None stated PS S&T Req., Component design modification [2] 5-14 1E

PS TS Req.

Cracking of the guide causing rod drops. Rare None stated PS S&T Req., None given 5-14 iS

PS TS Req.

Housing cracks causing primary coolant Rare None stated PS S&T Req., Improved leakage monitoring; 5-14 2C

leakage (SBLOCA) and jamming of the PS TS Req. Improved visual inspection [2]

drive mechanism.

PS S&T Req., 21

PS TS Req.

Loss of valve function and primary coolant Occasional None stated PS S&T Req., Improved leakage monitoring; 5-14 22

leakage. PS TS Req. Improved visual inspection [2]

Failure of these sub-components will lead Rare None stated PS S&T Req., None stated 5-14 22

to dropping or locking of the control rod PS TS Req.

assembly.

Cracking of the leadscrew will cause a Rare None stated PS S&T Req., Periodic wear measurements [2] 5-14 24

dropped or immovable control rod. PS TS Req.

PS S&T Req., 2E

PS TS Req.

PS S&T Req., 2i

PS TS Req.

PS S&T Req., 27

PS TS Req.

PS S&T Req., 2E

PS TS Req.

PS S&T Req., 2E

PS TS Req.

PS S&T Req.,

PS TS Req.
Table A.1 Gall Report for NPAR Reports Page 97A

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effe

Document: NUREG/CR-5807, Improvements in Motor Operated Gate Valve Designs and Prediction Models for Nuclear Power Plant Systems

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomoonent Materials Manufacturer ARD mechanism ARD effects

1 Various Motor operated gate This report does not

valves provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or systems.

Document: NUREG/CR-5848, Recordkeeping Needs to Mitigate the Impact of Aging Degradation

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Multiple Multiple This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

I I_ I I systems.

Document: NUREG/CR-5870, Results of LWR Snubber Aging Research

Reviewed by: Steve U. Choi, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 PWR and BWR Mechanical Lead screw, thrust Not stated Not stated VIBR (high- Loosening, wear

cooling and snubbers bearing, capstan amplitude)

emergency cooling spring, pins, and

systems attachment lugs

2 PWR and BWR Mechanical Fasteners, clevis Not stated Not stated VIBR (low- Loosening, wear

cooling and snubbers pins, and amplitude)

emergency cooling attachments

systems

3 PWR and BWR Mechanical Lubricants Not stated Not stated ELE-TEMP Chemical or physical

cooling and snubbers degradation

emergency cooling

systems

4 PWR and BWR

cooling and

emergency cooling

systems

Mechanical

snubbers

Capstan and

capstan spring

Not stated Not stated CORR Loss of material;

corrosion product

buildup
Table A.1 Gall Report for NPAR Reports Page 97B

Document: NUREG/CR-5783, BNL-NUREG-52299, Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL F~ff~t nf Aninn •nr rnmnnn•_nt FIunetinn (='nntrib tn Fahilure RennrtL=d nrnn•; ReI.nroa]s Reoort Recommendations Paa e No. Item

Loss of cooling leading to inoperable Rare None stated PS S&T Req., None stated 31 CROM. PS TS Req.

Loss of cooling leading to inoperable Rare None stated PS S&T Req., None stated 32

CRDM. PS TS Req.

Loss of cooling leading to inoperable Rare None stated PS S&T Req., None stated 33

CRDM. PS TS Req.

Document: NUREG/CR-5807, Improvements in Motor Operated Gate Valve Designs and Prediction Models for Nuclear Power Plant Systems

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.prosgs Report Recommendations Page No. Item~1

Document: NUREG/CR-5848, Recordkeeping Needs to Mitigate the Impact of Aging Degradation

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Document: NUREG/CR-5870, Results of LWR Snubber Aging Research

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

High-amplitude vibration can result in Not stated Not discussed in ASME Sec XI Monitor service-life to include 17,19 1

localized fretting and wear of mating report ISTD determination of snubber failure or

parts. It can also result in an increase in degradation causes, operating

drag force, an increase in mechanical environment, managing snubbers in

clearances, jamming, and/or an increase severe environments, augmented

in the acceleration threshold, surveillance, trending degradation

parameters & testing. [2]

Low-amplitude vibration can lead to Not stated Not discussed in ASME Sec Xl Monitor service-life to include 17,19 2

loosening of fasteners and, in combination report ISTD determination of snubber failure or

with the weight of the snubber, can cause degradation causes, operating

wear of clevis pins and attachments, environment, managing snubbers in

resulting in elongated attachment holes, severe environments, augmented

and can cause internal wear. surveillance, trending degradation

parameters & testing. [2]

Solidification of lubricants increases Not stated Not discussed in ASME Sec XI Monitor service-life to include 17,19 3

friction and results in an increase in drag report ISTD determination of snubber failure or

force. degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

_parameters & testing. [2] 1

Internal corrosion can lead to increasing

drag force, jamming, and/or a decrease in

the snubber's acceleration threshold as a

result of a buildup of rust.

Not stated Not discussed in

report

ASME Sec Xl

ISTD

Monitor service-life to include

determination of snubber failure or

degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

17,19 4
Table A.1 Gall Report for NPAR Reports Page 98A

Document: NUREG/CR-5870, Results of LWR Snubber Aging Research

Reviewed by: Steve U. Choi, ANL Item SysemStucturelComn• Subcomn~onent Mazternias Manufacturer ARD mechanism ARD effects .. . .. S v te . . . . . . . . . . .... ....... .... ............. .. . . .. . ... ... . .... ... ........ . ... . ... . . .. 5 PWR and BWR Hydraulic snubbers Seals Not stated Not stated ELE-TEMP Chemical or physical

cooling and degradation

emergency cooling

systems

6 PWR and BWR Hydraulic snubbers Plastic hydraulic Not stated Not stated ELE-TEMP Chemical or physical

cooling and reservoirs degradation

emergency cooling

systems

7 PWR and BWR Hydraulic snubbers Control valve Not stated Not stated CORR Loss of material;

cooling and corrosion product

emergency cooling buildup

systems

8 PWR and BWR Hydraulic snubbers Control valve Not stated Not stated VIBR Loosening, wear

cooling and

emergency cooling

systems

9 PWR and BWR Hydraulic snubbers Threaded fasteners, Not stated Not stated VIBR Loosening, wear

cooling and clevis pins,

emergency cooling attachment holes

systems

10 PWR and BWR Hydraulic snubbers Hydraulic fluid Not stated Not stated VIBR Gelation

cooling and

emergency cooling

systems

Document: NUREG/CR-5944, A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry

Reviewed by: Ken E. Kasza, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Reactor flow control Check valves Hinge pin/bushings Not stated Not stated CORR; WEAR Loss of material,

attrition

2 Reactor flow control Check valves Disk stud Not stated Not stated FAT; VIBR Cumulative fatigue

damage

3 Reactor flow control Check valves Hinge arm Not stated Not stated FAT; VIBR Cumulative fatigue

damage

4 Reactor flow control Check valves Seat Not stated Not stated CORR; ERO Loss of material

5 Reactor flow control Check valves Valve body Not stated Not stated WEAR Attrition
Table A.1 Gall Report for NPAR Reports Page 98B

Document: NUREG/CR-5870, Results of LWR Snubber Aging Research

Reviewed by: Steve U. Choi, ANL Effect of Aaina on Comoonent Function Contrib to Failure Reeorted:I orooas ReI.Droas Report Recommendations Pacie No. Item

Seal leaks would result in loss of fluid Not stated Not discussed in ASME Sec XI Monitor service-life to include 3,11 5

from the snubber, report ISTD determination of snubber failure or

degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

Elevated temperature can lead to Not stated Not discussed in ASME Sec XI Monitor service-life to include 3,11 6

deformation of plastic hydraulic reservoirs. report ISTD determination of snubber failure or

degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

Internal corrosion resulting in the Not stated Not discussed in ASME Sec Xl Monitor service-fife to include 3,11 7

generation of corrosion products can report ISTD determination of snubber failure or

cause a malfunction of the snubber degradation causes, operating

control valve. environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

Wear due to high-amplitude vibration can Not stated Not discussed in ASME Sec Xl Monitor service-life to include 3,12 8

result in particle generation, potentially report ISTD dletermination of snubber failure or

affecting control valve performance. degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

High- or low-amplitude vibration can result Not stated Not discussed in ASME Sec XI Monitor service-life to include 3,12,J.6 9

in loosening of threaded fasteners and/or report ISTD determination of snubber failure or

wear or deformation of clevis pins and degradation causes, operating

attachment holes. environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

parameters & testing. [2]

Extreme high-amplitude vibration can Not stated Not discussed in ASME Sec XI Monitor service-life to include 3,12,J.2 10

result in gelated, blackened hydraulic report ISTD determination of snubber failure or

fluid. degradation causes, operating

environment, managing snubbers in

severe environments, augmented

surveillance, trending degradation

1parameters & testing. [2] 1 1

Document: NUREG/CR-5944, A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.proEs Report Recommendations Pa e No. Item

Corrosion and wear of hinge pins and Rare ASME Working ASME Sec XI Not stated 10,'21 1

bushings can cause valve to open or Group on Check IWV

close sluggishly or not move, resulting in Valves (OM 22)

leakage or reduced flow.

Fatigue due to flow impact and vibration Occasional ASME Working ASME Sec XI Not stated 7,17 2

can cause misalignment of valve disk and Group on Check IWV

seat, resulting in leakage. Valves (OM 22)

Fatigue due to flow impact and vibration Occasional ASME Working ASME Sec XI Not stated 7,17 3

can cause misalignment of valve disk and Group on Check IWV

seat, resulting in leakage. Valves (OM 22)

Erosion and/or corrosion causes valve to Moderate ASME Working ASME Sac XI Not stated 7, 21, 32 4

seat improperly, resulting in minor or Group on Check IWV

major fluid leakage. The impact depends Valves (OM 22)

on where valve is located in plant, and can

lead to important safety related events.

This degradation is prevalent in large

values.

Degradation of a body penetration, such Moderate ASME Working ASME Sec XI Not stated 10 5

as packing or a valve stem, due to wear Group on Check IWB, IWV

interferes with proper valve functioning Valves (OM 22)

and causes possible leakage.
Table A.1 Gall Report for NPAR Reports Page 99A

Document: NUREG/CR-6001, Aging Assessment of BWR Standby Liquid Control Systems

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComo SubcomDonent Materials Manufacturer ARD mechanism ARD effects

1 Standby liquid Relief valves Not delineated Not stated Not stated WEAR Attrition

control in BWR

2 Standby liquid Relief valves Not delineated Not stated Not stated CQRR Loss of material;

control in BWR corrosion product

buildup

3 Standby liquid Relief valves Not delineated Not stated Not stated CONTAM Buildup of deposits

control in BWR

4 Standby liquid Accumulators Not delineated Not stated Not stated Not stated Nitrogen blanket

control in BWR pressure reduction

5 Standby liquid Pumps Not delineated Not stated Not stated Not stated Aging degradation of

control in BWR packing, seals and

internal valves

6 Standby liquid Instrumentation Not delineated Not stated Not stated Not stated Impaired ability to

control in BWR monitor system

Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Air-treatment system HEPA filters Filtering media Glass fiber filter Not stated PART Increased pressure .paper," possibly drop

with organic

additions

2 Air-treatment system HEPA filters Filtering media Glass fiber filter Not stated MOIST Increased pressure .paper," possibly drop and reduced

with organic strength

additions

3 Air-treatment system HEPA filters Filtering media Glass fiber filter Not stated ENVIR Physical degradation 'paper," possibly

with organic

additions

4 Air-treatment system HEPA filters Frames and Aluminum and other Not stated CORR Loss of material

separators metals

5 Air-treatment system HEPA filters Sealants, gaskets, Unidentified organic Not stated ELE-TEMP; ENVIR Chemical and

and water repellents materials physical degradation

6 Air-treatment system Air treatment system Adsorber medium Activated charcoal Not stated WEATH Loss of capacity

adsorbers (carbon)

7 Air-treatment system Air treatment system

adsorbers

Adsorber medium Activated charcoal

(carbon)

Not stated ENVIR Chemical and

physical degradation
Table A.1 Gall Report for NPAR Reports Page 99B

Document: NUREG/CR-6001, Aging Assessment of BWR Standby Uquid Control Systems

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.p'roqs Report Recommendations Page No. Item

Wear can cause valve setpoint to drift. Moderate Not discussed in ASME Sec Xl Not stated 6,13,14, 1

Higher value results in a loss of system report IWV 23

overpressure protection; a decrease could

reduce the rate of boron injection effecting

reactivity control.

Improper concentrations of boric acid Occasional Not discussed in ASME Sec XZ Not stated 6,13,14, 2

causes corrosion of valve internals and report IWV 23

reduced valve function.

Buildup of sodium pentaborate Occasional Not discussed in ASME Sec XI Not stated 13,14 3

precipitates on valve internals causes report IWV

changes in valve opening characteristics

and injection of borate.

Loss of nitrogen pressure is caused by Not stated Not discussed in ASME Sec XI Not stated 13,14 4

valve wear and failure of gas bladder. report IWV

However the accumulators would stay

intact and still would pass flow in times of

critical need.

Degradation could prevent pumps from Occasional Not discussed in ASME Sec XI Not stated 13,14,23 5

operating within technical specifications report IWP

and change borate injection

characteristics.

Instrumentation required to monitor the Occasional Not discussed in 10CFR50.49 Not stated 13,14 6

system, such as component status lights, report

tank level sensors, temperature, pressure

and flow gauges, are subject to aging but

are not stated to be necessary for system

operation during critical need.

Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Dust pickup increase the pressure drop Frequent ASME N509-1989; PS S&T Req., Monitor pressure drop across filter 4.1, 5.1,

across the filter. Dust pickup can also ASME N510- RG 1.140, RG and change filter as required. [2] 6.1

reduce the effectiveness of organic 1989;NRC RG 1.52 1.52

materials added for strengthening and and RG 1.140

water repellency.

Moisture incorporation into the filter Frequent ASME N509-1989; PS S&T Req., Not stated 4.1,7.4 2

medium causes increased pressure drop ASME N510- RG 1.140, RG

and reduced filter strength, and structural 1989;NRC RG 1.52 1.52

failure of the filter can occur even under and RG 1.140

design flow rates.

Prolonged exposure to air containing Occasional ASME N509-1989; PS S&T Req., Not stated 4.1 3

normal concentrations of oxygen and ASME N51 0- RG 1.140, RG

oxides of nitrogen can cause 1989;NRC RG 1.52 1.52

embrittiement of the filter media material, and RG 1.140

resulting in possible leakage and loss of

filtration.

Corrosive attack of metallic components Occasional ASME N509-1989; PS S&T Req., Not stated 4.1, 5.2 4

in H EPA filters exposed to aggressive ASME N510- RG 1.140, RG

environments can cause structural failure 1989;NRC RG 1.52 1.52

and consequent leakage and loss of and RG 1.140

filtration.

Heat and radiation are reported to cause Occasional ASME N509-1989; PS S&T Req., Not stated 4.1, 5.2 5

aging and deterioration of face gaskets, ASM E N51 0- RG 1.140, RG

adhesives, sealants, and water repellents. 1989;NRC RG 1.52 1.52

resulting in filter leakage and loss of and RG 1.140

effective filtration. I

Airborne moisture, contaminants, and Frequent ASME N510-1989; PS S&T Req., Not stated 4.2, 5.2 6

pollutants are readily absorbed by carbon NRC RG 1.52 and RG 1.140, RG

bed adsorbers, thereby depleting RG 1.140 1.52

adsorbent capacity and reducing

efficiency.

Oxidation of the carbon adsorbent

medium has been found to deplete

adsorbent capacity and reduce efficiency.

Occasional ASME N510-1989;

NRC RG 1.52 and

RG 1.140

PS S&T Req.,

RG 1.140, RG

1.52

Not stated 4.2 7
Table A.1 Gall Report for NPAR Reports Page 100A

Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

8 Air-treatment system Air treatment system Unidentified Stainless steel Not stated CORR; CORR/PIT Loss of material

adsorbers stainless steel

components

Document: NUREG/CR-6043, Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Heating, ventilating Centrifugal chiller Compressor seals Non-ferrous metals Not stated WEAR Attrition

and air conditioning or carbon and

(HVAC) elastomers

2 Heating, ventilating, Centrifugal chiller Compressor motor Not stated Not stated WEAR Attrition

and air conditioning bearings

(HVAC)

3 Heating, ventilating, Centrifugal chiller Compressor motor Not stated Not stated ELE-TEMP Chemical and

and air conditioning physical degradation (HVAC)

4 Heating, ventilating, Centrifugal chiller Condenser and Carbon steel plate; Carrier, Trane, and CORR; CORR/PIT; Loss of material and

and air conditioning evaporator/cooler Cu or Cu- 10% Ni York CORR/MIC corrosion product

(HVAC) heat exchangers tubing buildup

5 Heating, ventilating, Centrifugal chiller Condenser and Carbon steel plate; Carrier, Trane, and VIBR Loosening

and air conditioning evaporator/cooler Cu or Cu-i10% Ni York

(HVAC) heat exchangers tubing

6 Heating, ventilating, Centrifugal chiller Refrigerant lines Cu or Cu-i10% Ni Not stated FAT; VIBR Cumulative fatigue

and air conditioning tubing damage; loosening

(HVAC)

7 Heating, ventilating, Condenser cooling Piping and tubing Not stated Carner, Trane, and CORR Loss of material and

and air conditioning water system York corrosion product

(HVAC) buildup

8 Heating, ventilating, Condenser cooling Piping and tubing Not stated Carrier, Trane, and FAT Cumulative fatigue

and air conditioning water system York damage

(HVAC)

9 Heating, ventilating, Lubrication system Tubing and other Not stated Carrier, Trane, and FAT Cumulative fatigue

and air conditioning components York damage

(HVAC)

10 Heating, ventilating, Lubrication system Lubricant Hydrocarbon Not stated CORR; WEAR Loss of material;

and air conditioning attrition

(HVAC)

11i Heating, ventilating, Control system Misc. small Not stated Carrier, Trane, and FAT Cumulative fatigue

and air conditioning components York damage

(HVAC)

12 Heating, ventilating, Control system Float valve bearings Not stated Carrier, Trane, and CORR; Loss of material;

and air conditioning and pivots York CORR/IGSCC crack initiation and

(HVAC) growth
Table A.1 Gall Report for NPAR Reports Page 100B

Document: NUREG/CR-6029, Vol. 1, Aging Assessment of Nuclear Air-Treatment System HEPA Filters and Adsorbers, Phase I

Reviewed by: Dwight R. Diercks, ANL

Effect of Acina on Comaonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Paoe No. Item Pag " NoItn Relatively rapid galvanic corrosion and Occasional ASME N510-1989; PS S&T Req., Notstated 43 8

severe pitting can occur in stainless steel NRC RG 1.52 and FRG 1.140, RG

adsorber components in contact with wet RG 1.140 1.52

carbon, resulting in loss of integrity and

effectiveness by the adsorber assembly.

Document: NUREG/CR-6043, Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reportedprogs Rel.progs Report Recommendations Page No. Item

Components are subject to time- Occasional Not discussed in PS S&T Req. Periodically (3 to 10 years) overhaul 31,'33,

dependent wear and ultimate failure, report and inspect all wearing parts, with C.3

resulting in loss of refrigerant through interval based on shortest material

leakage. life. [4]

Components are subject to time- Occasional Not discussed in PS S&T Req. Periodically (3 to 10 years) overhaul 26, 31, 2

dependent wear, resulting in loss of report and inspect all wearing parts, with 32, C.3

bearing function and motor failure, interval based on shortest material

life. [4]

Motor insulation and internal electrical Occasional Not discussed in PS S&T Req., Heat scan with infrared temperature- 31, 33, 3

components are subject to thermal report RG 1.32, RG. sensing instruments. [4] D.2, D.3

breakdown, resulting in motor failure. 1.140

Corrosion failures associated with Frequent Not discussed in PS S&T Req. Control water quality supplied to the 26, 27, 4

moisture ingress into the refrigerant in report condenser and evaporator; 28, 30,

refrigerant systems can lead to leakage periodically examine tubes and clean 31, 32,

and loss of refrigerant. Others include of necessary. [4] 33, 39,

heat exchanger tube fouling and plugging, C.2, D.5,

crevice corrosion at tube sheets, and bio- E.2, E.4

fouling.

Loosening of bolts by vibration has been Occasional Not discussed in PS S&T Req. Periodically perform vibration 31, D.3 5

observed to cause component failure, report analysis. [4]

Leakage of refrigerant lines apparently Occasional Not discussed in PS S&T Req. Periodically perform vibration 31, 33, 6

caused by vibrational fatigue or loosening report analysis. [4] C.2, C.3,

can lead to loss of refrigerant and system C.4, D.7,

failure. E.2

System components are subject to Frequent Not discussed in PS S&T Req. Control water quality supplied to the 31, 33, 7

corrosion, fouling, and plugging if good report condenser and evaporator; C.2, C.3,

water chemistry is not maintained, periodically examine tubes and clean C.4, D.7,

resulting in system failure. _of necessary. [4] E.2

Vibrational fatigue failure of cooling Occasional Not discussed in PS S&T Req. Periodically perform vibration 29, 31, 8

system piping has been reported, report analysis. [4] D.2

resulting in cooling water leakage and

possible system failure.

Lubrication system leaks apparently Occasional Not discussed in PS S&T Req. Periodically perform vibration 31, 31, 9

caused by vibrational fatigue have been report analysis; routinely analyze lubrication C.2, D.2,

reported, and such leaks can lead to loss oil to ensure correct chemistry. [4] D.4, E.2,

of lubricant and compressor and pump E.3

bearing failure.

Leakage from corrosion can cause Moderate Not discussed in PS S&T Req. Routinely analyze lubrication oil to 30, 32, 10

contamination of lubrication system by report ensure correct chemistry. [4] E.2, E.5

acids, leading to accelerated wear and

ultimate failure of compressor and pump

bearings.

Small control system components such Frequent Not discussed in PS S&T Req. Periodically perform vibration 29, 30, 11

as timers, cam switches, relays, terminal report analysis; annually service and test 31, 33,

and wire connectors, and lamp bulbs are components to ensure reliability. [4] D.6, E.2,

subject to mechanical fatigue-related E.3, E.6

failures due to vibration.

Corrosive attack of bearings and pivots in Rare Not discussed in PS S&T Req. Routinely analyze refrigerant to 31, 33, 12

float valves due to water ingress into the report ensure correct chemistry. [4] C.2, C.3,

refrigerant can lead to failure. IGSCC of a C.4, D.3

valve ball float in Waterford Unit 3 has

also been observed.
Table A.1 Gall Report for NPAR Reports Page 101A

Document: NUREG/CR-6048, Pressurized-Water Reactor Internals Aging Degradation Study, Phase 1

Reviewed by: All Erdemir, ANL

Item S~e Structure/Comn Subc~omnonent Materials M3nufn~turer ARD mechnni~m ARD effects

1 Reactor internals Lower core support Thermal shield Type 304 SS Westinghouse. VIBR Crack initiation and

structure growth

2 Reactor internals Lower core support Thermal shield radial Type 304 SS Westinghouse. VIBR Crack initiation and

structure limiter pin growth

3 Reactor internals Lower core support Thermal shield Type 304 SS Westinghouse VIBR Crack initiation and

structure flexure support growth

system

4 Reactor internals Lower core support Thermal shield Type 304 SS Combustion VIBR; WEAR Crack initiation and

structure Engineering growth; attrition

5 Reactor internals Lower core support Hold-down ring Type 304 SS Combustion VIBR; WEAR Crack initiation and

structure Engineering growth; attrition

6 Reactor internals Lower core support Fuel rods Type 304 SS Westinghouse VIBR Crack initiation and

structure growth

7 Reactor internals Lower core support Thermal shield Alloy A-286 Babcock & Wilcox CORR/IGSCC Crack initiation and

structure support bolts growth

8 Reactor internals Lower core support Barrel-to-core Alloy A-286 Babcock & Wilcox CORR/IGSCC Crack initiation and

structure support shield bolts growth

9 Reactor internals Core barrel Baffle bolts Inconel X-750 Westinghouse CORR/IGSCC Crack initiation and

growth

10 Reactor internals Upper core support Control rod guide Inconel X-750 Westinghouse CORR/IGSCC Crack initiation and

structure tube support pins growth

11 Reactor internals In-core. Flux thimbles and Types 304 and 316 Westinghouse VIBR, WEAR Crack initiation and

instrumentation guide tube SS growth, attrition

support structure

12 Reactor internals In-core Surveillance Type 304 SS Babcock & Wilcox VIBR, WEAR Crack initiation and

instrumentation specimen holder growth, attrition

I _ _ Isupport structure tube

Document: ORNL/NRC/LTR-91/25, Throttled Valve Cavitation and Erosion

Reviewed by: Ken E. Kasza, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

316 SS, stellite over Not stated

SS, cast iron, carboni

steel
Table A.1 Gall Report for NPAR Reports Page 101B

Document: NUREG/CR-6048, Pressurized-Water Reactor Internals Aging Degradation Study, Phase

Reviewed by: Ali Erdemir, ANL Effect of Aainn on Comrnonent Function (Zontrib to Failure Renarted oroas Relneroas

1

Re~ort Recommendations PaeN.Item

Vibration of thermal shield in a shell mode Not stated ASME B&PV Code, ASME Sec XI Not stated 38

caused some of the shell segments to Section XI IWB & Assoc.

come into contact with the core barrel. NRC GC

The repeated impact loadings caused

failures in the core barrel support bolts

and also damaged the thermal shield.

RFow-induced vibration caused radial Not stated ASME B&PV Code, ASME Sec XI Not stated 38 2

limiter pins to come into contact with the Section XI IWB & Assoc.

sides of the keyway in the core barrel, NRC GC

eventually leading to cracking of the fillet

welds between pins and thermal shield. "rThe top mounted flexure support system Not stated ASME B&PV Code, ASME Sec Xl Not stated 38

failed due to high-cycle fatigue caused by Section Xl IWB & Assoc.

small-amplitude flow-induced vibration of NRC GC

the thermal shield.

Pump-generated pressure pulsations Not stated ASME B&PV Code, ASME Sec XI Not stated 38 4

caused excessive wear damage and loss Section Xl IWB & Assoc.

of some support and positioning pins. NRC GC

Lugs welded to the core barrel were also

damaged. In one unit the damaged lugs

caused a through-the-wall crack in the

core barrel. I

Row-induced vibration caused excessive Not stated ASME B&PV Code, ASME Sec XI Use 403 SS, increase hold-down 38 5

mechanical wear in the hold-down ring of Section XI IWB & Assoc. spring force. [4]

a CE unit due to the insufficient levels of NRC GC

hold-down sprinn force.

Baffle plate water-jetting due to pressure Not stated ASME B&PV Code, ASME Sec XI Change design, modify downward 38-39 6

differential set fuel rods into whirling Section XI IWB & Assoc. bypass flow to an upward bypass

motions and excessive vibrations, which NRC GC flow scheme [4]

eventually led to cladding degradation and

failures.

High tensile stresses due to preloads and Not stated Not discussed in ASME Sec XI Change design, reduce tensile 40 7

poor design in the shank region of bolts report IWB & Assoc. stress level, change material to Xled to the development of IGSCC at the NRC GC 750 [1]

bolt-head-to-bolt shank transition area.

As a result, some bolts were lost and

others became loose.

Overtorquing on bolts and hot-head Not stated Not discussed in ASME Sec XI Reduce torque to bolts, change fab- 41 8

manufacturing process were the most report IWB & Assoc. ncation practice, use bolts made by

probable cause of IGSCC in a number of NRC GC machining [1]

bolts that join core barrel to core support

shield.

Routine inspections detected signs of Not stated Not discussed in ASME Sec XI Use austenitic stainless steel bolts 42 9

cracks in core baffle bolts, and the report IWB & Assoc. [4]

failures were attributed to IGSCC possibly NRC GC

due to sensitization of the Inconel X-750

bolts.

Crevice conditions, improper heat Not stated NRC Information ASME Sec XI Solution heat treat at a higher 41 10

treatment, and overtorquing of nuts during Notice 82-29 IWB & Assoc. temper-ature, increase pin size,

installation of the support pins may have NRC GC reduce preloads during installation.

contributed to IGSCC. [4]

Fretting and mechanical wear resulted in Not stated NRC Information ASME Sec XI Move thinned segments away from 43 11

thinning and eventual leakage of the Notice 87-44 IWB & Assoc. the vibrating region. Use thickerthimble and guide tubes. Flow-induced NRC GC walled tubes [4]

vibration was identified as the leading

contributor to fretting and wear.

Flow induced vibration due to pump- Not stated Not discussed in ASME Sec XI Change stiffness of tubes [4) 43 12

generated pressure pulsations caused report IWB & Assoc.

excessive wear on tubes. NRC GC

Document: ORNL/NRC/LTR-91/25, Throttled Valve Cavitation and Erosion

Reviewed by: Ken E. Kasza, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Valves used under throttled service can Occasional

experience cavitation, which can remove

material. For butterfly type valves, wall

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8,

report IWV, GL 89-10 and materials appropriate for 10, 18

& Suppl. operating conditions [4]
Table A.1 Gall Report for NPAR Reports Page 102A

Document: ORNL/NRC/LTR-91/25, Throttled Valve Cavitation and Erosion

Reviewed by: Ken E. Kasza, ANL Item System Structure/Como Subeomoonent Matierials Manufacturer ARD mechanism ARD effects

2 Condensate/feedwat Valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

er body/seat/plug SS, cast iron, carbon

steel

3 Chemical volume Valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

and control body/seat/plug SS, cast iron, carbor

steel

4 Service water Valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

body/seat/plug SS, cast iron, carbon

steel

5 Main steam Valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

body/seat/plug SS, cast iron, carbon

steel

6 Residual heat Globe valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

removal body/seat/plug SS, cast iron, carbon

steel

7 Residual heat Butterfly valve Internals: 316 SS, stellite over Not stated ERO/CAV Loss of material

removal body/seat/plug SS, cast iron, carbon

steel

Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 All systems in ECCS pump room Fan V- Cord (cotton, rayon, Not stated VIBR Loosening; crack

general and RHR coolers Belts/Sheaves synthetic, steel) initiation and growth

system in particular fiber, rubber/steel

2 All systems in ECCS pump room Fan V- Cord (cotton, rayon, Not stated WEAR Attrition

general and RHR coolers Belts/Sheaves synthetic, steel)

system in particular fiber, rubber/steel

3 All systems in ECCS pump room Motor- and fan- Steel, brass, bronze, Not stated WEAR Attrition

general and RHR coolers bearings grease, lube oil

system in particular

4 All systems in

general and RHR

system in particular

ECCS pump room

coolers

Motor- and tanbearings

Steel, brass, bronze,

grease, lube oil

Not stated CORR Loss of

material;corrosion

product buildup
Table A.1 Gall Report for NPAR Reports Page 1028

Document: ORNINRC/LTR-91/25, Throttled Valve Cavitation and Erosion

Reviewed by: Ken E. Kasza, ANL Effect of Aaina on Comoonent Function Contrib to Failure Renorted Droas Re~I.roas Renort Recommendations Paae No. Item

Valves used under throttled service can Moderate Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 2

experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18

material. For butterfly type valves, wall & Suppl. operating conditions [4]

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Valves used under throttled service can Occasional Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 3

experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18

material. For butterfly type valves, wall & Suppl. operating conditions [4]

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Valves used under throttled service can Moderate Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 4

experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18

material. For butterfly type valves, wall & Suppl. operating conditions [4]

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Valves used under throttled service can Occasional Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 5

experience cavitation, which can remove report IWV, GL 89-10 and materials appropriate for 10,18

material. For butterfly type valves, wall & Suppi. operating conditions [4]

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Valves used under throttled service can Occasional Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 6

experience cavitation, which can remove report IWB, IWV, GL and materials appropriate for 10,12,

material. For butterfly type valves, wall 89-10 & Suppl. operating conditions [4] 13,18

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Valves used under throttled service can Moderate Not discussed in ASME Sec Xl More carefully select valve type, trim 3, 4, 8, 7

experience cavitation, which can remove report IWB, IWV, GL and materials appropriate for 10,12,

material. For butterfly type valves, wall 89-10 & Suppl. operating conditions [4] 13,18

thinning can occur in adjacent

downstream pipe. Cavitation can cause

vibration damage.

Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated. Frequent Not discussed in PS S&T Req. Follow mfg. recommendations for 2.4, 5.3 1

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use strip heaters to

control humidity. [4]

Not stated. Not stated Not discussed in PS S&T Follow mfg. recommendations for 5.4 2

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use [4]

Not stated. Frequent Not discussed in PS S&T Req., Follow mfg. recommendations for 2.4,5.4 3

report RG 1.32 installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

_frequencies, use [4] 1 1

Not stated. Not stated Not discussed in

report

PS S&T Req.,

RG 1.32

Follow mfg. recommendations for

installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use [4]

6.5
Table A.1 Gall Report for NPAR Reports Page 103A

Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers

Reviewed by: Steve U. Choi, ANL Item~vfm Sfru~tureIComn Subcom~onent Materials Manuf•acturer ARD mechanism ARD effects

5 All systems in ECCS pump room Couplings/fans Not Not stated VIBR Loosening; crack

general and RHR coolers stated/Galvanized, initiation and growth

system in particular carbon and stainless

steel, aluminum

6 All systems in ECCS pump room Cooling coils Copper, copper- Not stated VIBR Loosening; crack

general and RHR coolers nickel, aluminum initiation and growth

system in particular

7 All systems in ECCS pump room Cooling coils Copper, copper- Not stated CORR Loss of

general and RHR coolers nickel, aluminum material;corrosion

system in particular product buildup

8 All systems in ECCS pump room Fan motors Copper, steel, silicon Not stated VIBR Loosening; crack

general and RHR coolers steel, aluminum, initiation and growth

system in particular insulating materials,

cast iron, brass,

mica, plastics,

graphite, cable,

seals and gaskets

9 All systems in ECCS pump room Fan motors Copper, steel, silicon Not stated ELE-TEMP Degradation

general and RHR coolers steel, aluminum,

system in particular insulating materials,

cast iron, brass,

mica, plastics,

graphite, cable,

I_ I seals and gaskets

10 All systems in ECCS pump room Fan motor mounting Not stated Not stated CORR Loss of

general and RHR coolers bolts, lead material;corrosion

system in particular connection, conduit product buildup

boxes, housing

enclosures

Document: PNL-6287, Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation

Reviewed by: Steve U. Choi, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Diesel Generator Various This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: PNL-7516, Emergency Diesel Generator Technical Specifications Study Results

Reviewed by: Steve U. Choi, ANL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Diesel Generator Various This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.
Table A.1 Gall Report for NPAR Reports Page 103B

Document: PNL-5722, Operating Experience and Aging Assessment of ECCS Pump Room Coolers

Reviewed by: Steve U. Choi, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Not stated. Not stated Not discussed in PS S&T Req. Follow mfg. recommendations for 2.4, 6.1- 5

report installation, surveillance, and 6.3

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use.[4]

Not stated. Not stated Not discussed in PS S&T Req. Follow mfg. recommendations for 2.4, 6.3 6

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly.

check vibration amplitudes and

frequencies, use [4]

Not stated. Not stated Not discussed in PS S&T Req. Follow mfg. recommendations for 6.6 7

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use [4]

Not stated. Not stated Not discussed in PS S&T Req., Follow mfg. recommendations for 2.4, 6.1 8

report RG 1.32 installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

_frequencies, use [4]

Not stated. Not stated Not discussed in PS S&T Req. Follow mfg. recommendations for 6.4 9

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

frequencies, use [4]

Not stated. Not stated Not discussed in PS S&T Req. Follow mfg. recommendations for 6.5 10

report installation, surveillance, and

maintenance, add vibration isolation

mounts, use acoustic and temp.

monitoring techniques, regularly

check vibration amplitudes and

_frequencies, use [4] 1

Document: PNL-6287, Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

1

Document: PNL-7516, Emergency Diesel Generator Technical Specifications Study Results

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item
Table A.1 Gall Report for NPAR Reports

Document: PNL-7823, Maintenance Practices to Manage Aging: A Review of Several Technologies

Reviewed by: Ken E. Kasza, ANL

Item System StructureJComp Subcomponent Materials Manufacturer

Page 104A

ARD mechanism ARD effects

1 Reactor All major This report does not

components provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Containment Metal containment Drywell base Not stated Not stated CORR Loss of material

2 Containment Metal containment Drywall base Not stated Not stated CORR/CREV Loss of material

3 Containment Metal containment Drywall base Not stated Not stated CORR/MIC Loss of material

4 Containment Metal containment Embedded shell Not stated Not stated CORR/CREV Loss of material

5 Containment Metal containment Embedded shell Not stated Not stated CORR/PIT Loss of material

6 Containment Metal containment Embedded shell Not stated Not stated CORR Loss of material

7 Containment Metal containment Bellows Stainless steel Not stated CORR/IGSCC Crack initiation and

growth

8 Containment Metal containment Bellows Stainless steel Not stated CORR/TGSCC Crack initiation and

growth

9 Containment Metal containment Suppression pool Not stated Not stated CORR Loss of material

10 Containment Metal containment Suppression pool Not stated Not stated CORR/MIC Loss of material

11 Containment Metal containment Suppression pool Not stated Not stated CORR/PIT Loss of material

12 Containment Metal containment Dissimilar metal Not stated Not stated CORR Loss of material

welds

13 Containment Reinforced concrete Reinforcing bars Not stated Not stated CORR Loss of material

containment

14 Containment Reinforced concrete Suppression pool

containment liner

Steel Not stated CORR Loss of material
Table A.1 Gall Report for NPAR Reports

Document: PNL-7823, Maintenance Practices to Manage Aging: A Review of Several Technologies

Reviewed by: Ken E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure Reported proas ReI.proas

Page 104B

Reoort Recommendations Paae No. Item .. .. .. • . -- . . .. . . .. .. . .. .. .. .. . . . .- -. ..- - -• . . .i - - 1

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Leakage of radioactive gases. Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 17

Sect. III and XI IWE & refurbishent, and replacement on a

10CFRSO App. timely basis. [4]

J

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec XI Effective application of mainteance, 17 2

Sect. III and XI IWE & refurbishent, and replacement on a

10CFR50 App. timely basis. [4]

J I

Leakage of radioactive gases. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17 3

Sect. III and Xl IWE & refurbishent, and replacement on a 10CFR50 App. timely basis. [4]

J

Loss of structural integrity. Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 17

Sect. III and XI IWE & refurbishent, and replacement on a

1OCFR50 App. timely basis. [4]

J I

Loss of structural integrity. Occasional ASME B&PV Code ASME Sec Xl Effective application of malnteance, 17 5

Sect. Ill and XI IWE & refurbishent, and replacement on a

1OCFRS0 App. timely basis. [4]

J

Loss of structural integrity. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17

Sect. III and XI IWE & refurbishent, and replacement on a 10CFR50 App. timely basis. [4]

Leakage of radioactive gases. Frequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17 7

Sect. III and XI IWE & refurbishent, and replacement on a

10CFR50 App. timely basis. [4]

Leakage of radioactive gases. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17 8

Sect. III and Xl IWE & refurbishent, and replacement on a 1 OCFR50 App. timely basis. [4]

SIJ

Leakage of radioactive gases. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17 9

Sect. III and XI IWE & refurbishent, and replacement on a 10CFR50 App. timely basis. [4]

J

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 17 10

Sect. Ill and XI IWE & refurbishent, and replacement on a 1OCFR50 App. timely basis. [4]

SIJ

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec XI Effective application of mainteance, 17 11

Sect. III and XI IWE & refurbishent, and replacement on a 1 OCFR50 App. timely basis. [4]

J

Leakage of radioactive gases. Frequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 18 12

Sect. III and XI IWE & refurbishent, and replacement on a 1OCFR50 App. timely basis. [4]

Loss of structural integrity. Infrequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 18 13

Sect. III and Xl IWL refurbishent, and replacement on a I_ I_ _timely basis. [4] _

Leakage of radioactive gases. Occasional ASME B&PV Code

Sect. III and XI

ASME Sec Xl

IWL &

10CFR5O App.

J

Effective application of mainteance,

refurbishent, and replacement on a timely basis. [4]

18 1A
Table A.1 Gall Report for NPAR Reports

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Item System Structure/Comp Subcomponent Materials

Page 105A

Manufacturer ARD mechanism ARD effects

15 Containment Reinforced concrete Suppression pool Steel Not stated CORR/MIC Loss of material

containment liner

16 Containment Prestressed Posttensioning Not stated Not stated CORR Loss of material

concrete system anchor

containment

17 Containment Prestressed Posttensioning wire Not stated Not stated CORR/PIT Loss of material

concrete or strand

containment

18 Containment Prestressed Posttensioning wire Not stated Not stated CORR/MIC Loss of material

concrete or strand

containment

19 Containment Prestressed Suppression pool Steel Not stated CORR Loss of material

concrete liner

containment

20 Containment Prestressed Suppression pool Steel Not stated CORR/MIC Loss of material

concrete liner

containment

21 Containment Prestressed Drywall liner Steel Not stated CORR Loss of material

concrete

containment

22 Containment Prestressed Reinforcing bar Not stated Not stated CORR Loss of material

concrete

containment

23 Containment Prestressed and Uner over wall dome Steel Not stated CORR Loss of material

reinforced concrete and base slab

24 BWR cooling Reactor pressure Nozzles Not stated Not stated CORR/IGSCC Crack initiation and

system vessel growth

25 BWR cooling Recirculation piping Weld heat-affected Not stated Not stated CORR/IGSCC Crack initiation and

system zones growth

26 BWR cooling Feedwater and main Near fittings and Not stated Not stated CORR Loss of material

system steam lines discontinuities

27 BWR cooling Feedwater and main Near fittings and Not stated Not stated ERO/CORR Loss of material

system steam lines discontinuities

28 BWR cooling Control rod drive Pressure housing & Not stated Not stated CORR/IGSCC Crack initiation and

system mechanisms stub tube growth

29 BWR cooling Reactor internals Attachment welds Not stated Not stated CORR/IGSCC Crack initiation and

system growth

30 BWR cooling Reactor internals Jet pumps Not stated Not stated CORR/IGSCC Crack initiation and

system growth

31 PWR cooling Reactor pressure Vessel flange and Not stated Not stated FAT Cumulative fatigue

system vessel studs damage

32 PWR cooling Recirculation steam Hot-leg tubes and U- Not stated Not stated CORR/IGSCC Crack initiation and

system generator tubes bends growth

33 PWR cooling Recirculation steam Cold-leg side in Not stated Not stated CORR/PIT Loss of material

system generator tubes sludge pile

34 PWR cooling Recirculation steam Tubing O.D. above Not stated Not stated CORR/UA Loss of material

system generator tubes tube sheet

runce -i:--- u-_ rou...n stea ... •tea genera.. or I- =l= statea _aco.. ...... ........ Loss. . . .. 3"VV COOling Onoe-through steam , Steam generator Not stated B5abcock & Wilcox E-RO/CORR Loss of material

system generators tubes
Table A.1 Gall Report for NPAR Reports Page 105B

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Effect of Aaina on ComDonent Function Contrib to Failure Reported Droas Rel.proas Report Recommendations Page No. Item

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 18 15

Sect. III and XI IWL & refurbishent, and replacement on a 10CFR50 App. timely basis. [4]

Reduction of load-carrying capacity. Moderate ASME B&PV Code ASME Sec XA Effective application of mainteance, 18 16

Sect. III and Xl IWL refurbishent, and replacement on a

timely basis. [4]

Reduction of load-carrying capacity. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 18 17

Sect. III and Xl IWL & refurbishent, and replacement on a

10CFR50 App. timely basis. [4]

Reduction of load-carrying capacity. Infrequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 18 18

Sect. III and Xl IWL refurbishent, and replacement on a

timely basis. [4]

Leakage of radioactive gases. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 19 19

Sect. III and Xl IWL & refurbishent, and replacement on a

10CFR50 App. timely basis. [4]

J

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 19 2C

Sect. III and Xl IWL & refurbishent, and replacement on a

1 OCFR50 App. timely basis. [4]

SIJ

Leakage of radioactive gases. Occasional ASME B&PV Code ASME Sec Xl Effective application of malnteance, 19 21

Sect. III and Xl IWL & refurbishent, and replacement on a

10CFR50 App. timely basis. [4]

J

Loss of structural integrity. Infrequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 19 22

Sect. III and Xl IWL refurbishent, and replacement on a timely basis. [4]

Leakage of radioactive gases and Infrequent ASME B&PV Code ASME Sec Xl Effective application of mainteance, 19-20 23

interaction of liner and concrete. Sect. III and XI IWL & refurbishent, and replacement on a

1OCFR50 App. timely basis. [4]

J

Ductile overload leading to leakage. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 21 24

Sect III and Xl IWB refurbishent, and replacement on a timely basis. [4]

Cracking and leakage. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 21 25

Sect. III and Xl IWB refurbishent, and replacement on a

timely basis. [4]

Cracking, large deformations, rupture, Frequent ASME B&PV Code ASME Sec XA Effective application of mainteance, 21 26

and leakage. Sect III and Xl IWB refurbishent, and replacement on a

timely basis. [4]

Cracking, large deformations, rupture, Moderate ASME B&PV Code ASME Sec XA Effective application of malnteance, 21 27

and leakage. Sect. III and XA IWB refurbishent, and replacement on a

timely basis. [4]

Cracking leading to leakage. Occasional ASME B&PV Code ASME Sec Xl Effective application of malnteance, 21 28

Sect. IlI and XI IWB refurbishent, and replacement on a

timely basis. [4]

Crack growth progressing into reactor Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 21 29

vessel. Sect. III and XI IWB refurbishent, and replacement on a

timely basis. [4]

Loss of adequate core flow. Moderate ASME B&PV Code ASME Sec Xl Effective application of malnteance, 22 3C

Sect. III and Xl IWB refurbishent, and replacement on a

timely basis. [4]

Eventual ductile overload failure. Moderate ASME B&PV Code ASME Sec III & Effective application of mainteance, 23 31

Sect. III and Xl Xl IWB refurbishent, and replacement on a

timely basis. [4]

Possible eventual cracking. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 23 32

Sect. III and XI IWB & PS TS refurbishent, and replacement on a

Req. timely basis. [4]

Possible eventual perforation, resulting in Occasional ASME B&PV Code ASME Sec Xl Effective application of malnteance, 23 33

leakage. Sect. III and XI IWB & PS TS refurbishent, and replacement on a

___Req. timely basis. [4] 1

Tube thinning, possibly leading to Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 23 34

penetration and leakage. Sect III and Xl IWB & PS TS refurbishent, and replacement on a

I I I Req. timely basis. [4]

Tube thinning, possibly leading to

penetration and leakage.

Frequent ASME B&PV Code

Sect III and Xl

ASME Sec Xl

IWB & PS TS

Req.

Effective application of mainteance, 24

refurbishent, and replacement on a

timely basis. [4]
Table A.1 Gall Report for NPAR Reports Page 106A

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Item System StructurelComp SubcomDonent Materials Manufacturer ARD mechanism ARD effects

36 PWR cooling Pressurizer sleeve Heater sheaths Not stated Not stated CORR/SCC Crack initiation and

system growth

37 PWR cooling Pressurizer sleeve Heater sheaths Not stated Not stated WEAR Attrition

system

38 PWR cooling Pressurizer sleeve Manway bolts Not stated Not stated CORR/SCC Crack initiation and

system growth

39 PWR cooling Reactor internals Thermal shield, Not stated Not stated FAT Cumulative fatigue

system bolts, core barrel, damage

and core support

structure

40 PWR cooling Reactor internals Thermal shield, Not stated Not stated CORR/IGSCC Crack initiation and

system bolts, core barrel, growth

and core support

structure

41 PWR cooling Reactor internals Thermal shield, Not stated Not stated EMBR/IR Loss of fracture

system bolts, core barrel, toughness

and core support

structure

42 PWR cooling Reactor internals Thermal shield, Not stated Not stated EMBR/TE Loss of fracture

system bolts, core barrel, toughness

and core support

structure

43 PWR cooling Feedwater piping Piping and nozzle Not stated Not stated ERO/CORR Loss of material

system and nozzle inside containment

44 PWR cooling Feedwater piping Piping and nozzle Not stated Not stated FAT Cumulative fatigue

system and nozzle inside containment damage

Document: PNL-SA-20219, ASME Subsection ISTD Recommendations based upon NPAR Snubber Aging Research Results

Reviewed by: Steve U. Choi, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Piping Snubber This report does not

provide specific

detailed information

on age-related

degradation

processes for

specific nuclear

components or

systems.

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Item System skucture/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Combustion Control Element Control Elements Clad-Inconel 625 CE WEAR; CORR/SCC Attrition; Crack

Engineering (CE) Assemblies initiation and growth

Control Rod Drive

System

2 Combustion Control Element Fuel Assembly Zlrcaloy-4 CE WEAR Attrition

Engineering (CE) Assemblies Guide Tubes

Control Rod Drive

System

3 Combustion Control Element Upper Guide Stainless Steel CE WEAR; EMBR/IR; Attrition; Loss of

Engineering (CE) Assemblies Structure-Spider FAT fracture toughness;

Control Rod Drive Cumulative fatigue

System damage

4 Combustion Control Element Motor Housing 403 Stainless Steel CE EMBR; CORR; FAT Loss of fracture

Engineering (CE) Drive Mechanisms Assembly Ni-Cr-Fe alloy toughness; Loss of

Control Rod Drive (CEDM) material; Cumulative

I System 1 1 fatigue damage

E Combustion

Engineering (CE)

Control Rod Drive

System

Control Element

Drive Mechanisms

(CEDM)

Motor AssemblyLatches, Links and

Pins

High Cobalt Alloy CE WEAR; FAT;

CONTAM

Attrition; Cumulative

fatigue damage;

Buildup of deposits
Table A.1 Gall Report for NPAR Reports Page 1068

Document: PNL-SA-18407, Understanding and Managing Corrosion in Nuclear Power Plants

Reviewed by: John W. Holland, ANL

Effect of Aaina on Component Function Contrib to Failure Reported Droas ReI.proqs Report Recommendations Paqe No. Item

Cracking leading to leakage. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 24 36

Sect. III and XI IWB refurbishent, and replacement on a

timely basis. [4]

Metal loss leading to leakage. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 24 37

Sect. Ill and XI IWB refurbishent, and replacement on a

timely basis. [4]

Bolt breakage leading to leakage. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 24 38

Sect. III and XI IWB refurbishent, and replacement on a

timely basis. [4]

Broken bolts, cracks, and loose parts. Frequent ASME B&PV Code ASME Sec III & Effective application of mainteance, 24 39

Sect. IlI and XI XI IWB refurbishent, and replacement on a

timely basis. [4]

Broken bolts, cracks, and loose parts. Moderate ASME B&PV Code ASME Sec XI Effective application of mainteance, 24 40

Sect. III and XI IWB refurbishent, and replacement on a

timely basis. [4]

Broken bolts, cracks, and loose parts. Occasional ASME B&PV Code ASME Sec XI Effective application of mainteance, 24 41

Sect. III and XI IWB refurbishent, and replacement on a

timely basis. [4]

Broken bolts, cracks, and loose parts. Infrequent ASME B&PV Code ASME Sec XI Effective application of mainteance, 24 42

Sect, Ill and XI IWB refurbishent, and replacement on a

timely basis. [4]

Rupture caused by water pressure. Moderate ASME B&PV Code ASME Sec Xl Effective application of mainteance, 24 43

Sect. III and XI & PS S&T refurbishent, and replacement on a

] Req. timely basis. [4]

Leakage through fatigue cracks. Occasional ASME B&PV Code ASME Sec Xl Effective application of mainteance, 24 44

Sect. III and XI & PS S&T refurbishent, and replacement on a

I I I Req. timely basis. [4]

Document: PNL-SA-20219, ASME Subsection ISTD Recommendations based upon NPAR Snubber Aging Research Results

Reviewed by: Steve U. Choi, ANL

Effect of Aging on Component Function Contribto Failure Reported progs Rel.progs Report Recommendations Page No. Item ~1

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Clad cracking and wash out of the poison. Occasional None stated ASME Sec XI None given 1

IWB & PS

Tech Spec.

Req.

Cracking of the tube wall. Frequent None stated ASME Sec Xl None given 2

IWB & PS

Tech Spec.

Req.

Cracking of the guide causing rod drops. Rare None stated ASME Sec Xl None given 3

IWB & PS

Tech Spec.

Req.

Housing cracking leads to primary coolant Frequent None stated ASME Sec Xl None given 4

leakage (SBLOCA) and jamming of the IWB & PS

drive mechanism. Tech Spec.

__ 1__ Req. I

Failure of these sub-components will lead

to dropping or locking of the control

element

Rare None stated ASME Sec Xl

IWB & PS

Tech Spec.

Req.

None given
Table A.1 Gall Report for NPAR Reports Page 107A

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

6 Combustion Control Element Upper Pressure Type 316 Stainless CE EMBR; CORR; FAT Loss of fracture

Engineering (CE) Drive Mechanisms Housing Assembly toughness; Loss of

Control Rod Drive (CEDM) material; Loss of

System fracture toughness

7 Combustion Control Element Extension Shaft Type 304 Stainless, CE WEAR; FAT; Attrition; Loss of

Engineering (CE) Drive Mechanisms Chromium plated CORR/SCC fracture toughness;

Control Rod Drive (CEDM) Crack initiation and

System growth

8 Combustion Control Element Vent Valves Type 440 Stainless CE CORR; FAT; Corrosion product

Engineering (CE) Drive Mechanisms Steel, Type 316 WEAR; EMBRITE buildup; Cumulative

Control Rod Drive (CEDM) Stainless Steel Seat fatigue damage;

System Attrition; Loss of

fracture toughness

9 Combustion Control Element Coil Stack Assembly Copper wire CE CORR; WEAR Loss of material;

Engineering (CE) Drive Mechanisms - Coils insulated with high Attrition

Control Rod Drive (CEDM) temperature enamel

System vacuum impregnated

with high

_ temperature varnish

10 Combustion CEDM Control Control Element Not stated CE These components

Engineering (CE) Systems Drive Control are referred to INEL

Control Rod Drive System and Control for review.

System Power Programmer

11 Combustion CEDM Control Rack and Pinion Not stated CE These components

Engineering (CE) Systems Control System are referred to INEL

Control Rod Drive for review.

System

12 Combustion CEA Rod Position Reed Switch Not stated CE These components

Engineering (CE) Indication Position Transmitter are referred to INEL

Control Rod Drive Assembly for review.

System

13 Combustion CEA Rod Position Pulse Count Position Not stated CE These components

Engineering (CE) Indication Indication System are referred to INEL

Control Rod Drive for review.

System

14 Combustion CEDM Cooling Fans Not stated CE Not stated Not stated

Engineering (CE) System

Control Rod Drive

_ System

15 Combustion CEDM Cooling Cooling Shroud Sheet metal CE CORR/BA Loss of material

Engineering (CE) System

Control Rod Drive

System

16 Combustion CEDM Cooling Instrumentation Not stated CE Not stated Not stated

Engineering (CE) System

Control Rod Drive

System

17 Babcock & Wilcox Control Rod Control Rod Type 304 Stainless B&W CORR/SCC; WEAR Crack initiation and

(B&W) Control Rod Assemblies Cladding growth; Attrition

Drive System

18 Babcock & Wilcox Control Rod Fuel Assembly Zlrcaloy-4 B&W WEAR Attrition

(B&W) Control Rod Assemblies Guide Tubes

Drive System

19 Babcock & Wilcox Control Rod Upper Internal Grade CF3M B&W CORR/SCC; Crack initiation and

(B&W) Control Rod Assemblies Brazement Stainless WEAR; EMBR/IR; growth; Attrition;

Drive System Assemblies-Spider FAT Loss of fracture

toughness;

Cumulative fatigue

damage

20 Babcock & Wilcox

(B&W) Control Rod

Drive System

Control Rod Drive

Mechanisms

(CRDM)

Motor Tube Low alloy steel clad

with Inconel or Type

403 stainless

B&W EMBR/TE; CORR;

FAT

Loss of fracture

toughness; Loss of

material; Cumulative

fatigue damage
Table A.1 Gall Report for NPAR Reports Page 107B

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL F~ffLe.t nf Aninn nm (•nmn~n~nt Fuinctinn Cnntrih tn F~iluip Rennrt..d nrna• Rel~nroas Rebort Recommendations Pae No. Item ........ of "'i o Corn.. on ...... n ... .. ..... i .Failur .... . ro .... e pr-7 . ..... ora . ... R r Recommendation............e Housing cracking leads to primary coolant Frequent None stated ASME Sec Xl None given 6

leakage (SBLOCA) and jamming of the IWB & PS

drive mechanism. Tech Spec.

Req.

Shaft cracking will lead to locking of the Occasional None stated ASME Sec X1 None given 7

mechanical operation. IWB & PS

Tech Spec.

Req.

Loss of valve function and primary coolant Rare None stated ASME Sec Xl None given

leakage. IWB & PS

Tech Spec.

Req.

Loss of coil function will lead to dropped, Rare None stated ASME Sec XI None given

slipped or immovable control elements. IWB & PS

Tech Spec.

Req.

Referred to INEL for review. Rare 10

None given 11

Rare 12

13

Loss of rod drive mechanism cooling Not stated None stated ASME Sec XI None given 14

capacity leading to inoperable CRDM or and PS Tech

rod drops. Spec. Req.

Loss of rod drive mechanism cooling Not stated None stated ASME Sec XI None given 15

capacity leading to inoperable CRDM or and PS Tech

rod drops. Spec. Req.

Loss of rod drive mechanism cooling Not stated None stated If Class 1 E None given 16

capacity leading to inoperable CRDM or 10CFR 50.49

rod drops. otherwise PS

S&T Req. I

Clad cracking and wash out of the poison. Occasional None stated ASME Sec Xl None given 17

IWB and PS

Tech Spec.

Req.

Cracking of the tube wall. Rare None stated ASME Sec XI None given 18

IWB & PS

Tech Spec.

Req.

Cracking of the guide causing rod drops. Rare None stated ASME Sec Xl None given 19

IWB & PS

Tech Spec.

Req.

Housing cracks causing primary coolant

leakage (SBLOCA) and jamming of the

drive mechanism.

Rare None stated ASME Sec Xl

IWB & PS

Tech Spec.

Req.

None given 20
Table A.1 Gall Report for NPAR Reports Page 108A

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L Binder, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

21 Babcock & Wilcox Control Rod Drive Stator Coils Copper Wire, Dow B&W Referred to INEL for

(B&W) Control Rod Mechanisms Corning 997 review.

Drive System (CRDM) Varnish, Kapton,

Nomex, Silicone

Rubber

22 Babcock & Wilcox Control Rod Drive Vent Valve O-rings Stainless Steel B&W CORR; WEAR; Corrosion product

(B&W) Control Rod Mechanisms FAT; EMBRY'TE buildup; Attrition;

Drive System (CRDM) Cumulative fatigue

damage; Loss of

I __ fracture toughness

23 Babcock & Wilcox Control Rod Drive Rotor Assembly- Stellite Ni-Cr-Fe B&W WEAR; FAT; Attrition; Cumulative

(B&W) Control Rod Mechanisms roller nuts, segment Alloy, Type 403 CONTAM fatigue damage;

Drive System (CRDM) arms, springs Stainless Steel Buildup of deposits

24 Babcock & Wilcox Control Rod Drive Leadscrew 17-4 PH Stainless B&W WEAR; FAT; Attrition; Cumulative

(B&W) Control Rod Mechanisms Steel CORR/SCC fatigue damage;

Drive System (CRDM) Crack initiation and

I _growth;

25 Babcock & Wilcox CRDM Power and Power Supplies Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems review.

Drive System

26 Babcock & Wilcox CRDM Power and Programmers Not stated B&W Referred to I NEL for

(B&W) Control Rod Control Systems review.

Drive System

27 Babcock & Wilcox CRDM Power and Trip Breakers Not stated B&W Referred to INEL for

(B&W) Control Rod Control Systems review.

Drive System

28 Babcock & Wilcox CRDM Power and Programmer Drive Not stated B&W Referred to I NEL for

(B&W) Control Rod Control Systems Motors review.

Drive System

29 Babcock & Wilcox CRA Rod Position Absolute Position Not stated B&W Referred to INEL for

(B&W) Control Rod Indication Indication System review.

Drive System

30 Babcock & Wilcox CRA Rod Position Relative Rod Not stated B&W Referred to INEL for

(B&W) Control Rod Indication Position Indication review.

Drive System

31 Babcock & Wilcox CRDM Cooling Centrifugal Pumps Not stated B&W CORR/BA Loss of material

(B&W) Control Rod System

Drive System

32 Babcock & Wilcox CRDM Cooling Heat Exchangers Not stated B&W CORR/BA Loss of material

(B&W) Control Rod System

Drive System

33 Babcock & Wilcox CRDM Cooling Surge Tank Not stated B&W CORR/BA Loss of material

(B&W) Control Rod System

Drive System
Table A.1 Gall Report for NPAR Reports Page 108B

Document: TR-3270, 9-90, An Operational Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives

Reviewed by: Jeffrey L. Binder, ANL

Effect of Acina on Component Function Contrib to Failure Reported proas Rel.proqs Report Recommendations Page No. Item

21

Loss of valve function and primary coolant Occasional None stated ASME Sec Xl None given 22

leakage. IWB & PS

Tech Spec.

Req.

Failure of these sub-components -will lead Rare None stated ASME Sec XI None given 23

to dropping or locking of the control rod IWB & PS

assembly. Tech Spec.

Req.

Cracking of the leadscrew will cause a Rare None stated ASME Sec X1 None given 24

dropped or immovable control rod. IWB & PS

Tech Spec.

Req.

25=

26

27

28

29

30

Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 31

CRDM. IWB & PS

Tech Spec.

Reg.

Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 32

CRDM. IWB & PS

Tech Spec.

Req.

Loss of cooling leading to inoperable Rare None stated ASME Sec XI None given 33

CRDM. IWB & PS

Tech Spec.

Req.
Table A.1 Gall Report for NRC Generic Letters

Document: GL Letters, NRC Generic Letters, 1989-1994

Reviewed by: Dwight R. Diercks, ANL

Item Svstem StructurelComp Subcomponent

Page 1A

Materials. Manufacturer ARD mechanism ARD effects

1 Cooling System Feeclwater piping Not stated Carbon steel Not stated ERO/CORR Wall thinning

2 Cooling System Feedwater piping Nozzles Not stated General Electric Co. FAT/THERM Cumulative fatigue

damage

3 Cooling System Steam generator and Supports Not stated Not stated EMBR/IR Loss of fracture

coolant pump toughness

4 Cooling System BWR primary Not stated Type 304 stainless General Electric Co. CORR/IGSCC Crack initiation and

system piping steel growth

5 Cooling System Piping, heat Not stated Various Not stated BIO Buildup of deposits

exchangers, and

other components

6 Containment system Reactor pressure Not stated Not stated Not stated EMBR/IR Loss of fracture

vessel toughness
Table A.1 Gall Report for NRC Generic Letters

Document: GL Letters, NRC Generic Letters, 1989-1994

Reviewed by: Dwight R. Diercks, ANL

Effect of Aoina on Component Function Contrib to Failure Reported progs

Page 1B

Rel.progs Report Recommendations Page No. Item

Erosion/corrosion caused by high-velocity Moderate NUREG-1344 Implement long-term erosion- 89-08 1

flow of water through piping has caused corrosion monitoring programs. [4]

several incidents of piping failure or wall

thinning below ASME Code allowables.

Fluctuations in water temperature within Frequent NUREG-0619 Not stated 89-21, p. 2

BWR vessel in nozzle region produces 5

high-cycle fatigue and resulting crack

initiation and growth in nozzles. I

Fracture toughness of support materials Not stated NUREG-0577 Maintain minimum temperature 89-21, pp. 3

may be inadequate, creating the potential above fracture transition 6

for fracture or lamellar tearing in service, temperature; replace supports if

gradalu__ necessary (4]

The gradual buildup of macroscopic Frequent NUREG/CR-5210; Implement surveillance and control 89-13; 89- 4

biological fouling organisms (e.g., blue NUREG/CR-5234 program outlined in Generic Letter 13, Suppl.

mussels, American oysters, Zebra 89-13[4] 1

mussels, and Asiatic clams) inhibits

coolant flow, ultimately resulting in flow

rates below technical specifications. I

Combination of residual or service Formerly frequent NUREG-0313 Follow recommendations in 89-21, p. 5

stresses, sensitization from welding, and NUREG-0313. [4] 11

oxygenated cooling water can cause

IGSCC of piping, resulting in leakage.

Neutron irradiation over extended time Not stated NUREG- Follow NUREG-0744 methods for 89-21, pp. 6

periods can cause embrittlement of the 0744;ASTM E- evaluating Charpy upper shelf 5-6, 16;

reactor pressure vessel material, 185;Reg. Guide impact strength. [4] 92-01,

particularly near the beltline, resulting in 1.99, Rev. 2 Rev. 1

loss of impact resistance and possible

failure in a severe pressurized overcool

event
Table A.1 Gall Report for Information Notices Page 1A

Document: IN&B 1989, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL

Item Syse tuctureJComD Subcom~onent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Valves Carbon steel valve Carbon steel Not stated ERO/CAV Loss of material

bodies

2 Cooling system Coolant pump Pump shaft A-286 Byron Jackson FAT Cumulative fatigue

damage

3 Cooling system Coolant pump Ring surrounding Not stated Byron Jackson Not stated Not stated

bearing housing

4 Cooling system Steam generator Tubing mechanical Inconel 600 Westinghouse CORR/PWSCC Crack initiation and

plugs growth

5 Cooling system Steam generator Tubing mechanical Inconel 600 Babcock & Wilcox CORR/PWSCC Crack initiation and

plugs growth

6 Cooling system Steamlines Atmospheric dump Not stated Control CONTAM Loss of desired

valves Components, Inc. surface properties

7 (Various water Pumps Impeller, bushings, Brass bushings; Not stated ERO/CAV; VIBR Loss of material;

systems) and other internal other materials not physical damage

components stated.

8 Electrical control Electrical cable Neoprene Not stated ELE-TEMP Chemical and

system insulation chloroprene and physical degradation

other organic

polymers

9 Turbine High-press. steam 14-in. piping Carbon steel Not stated ERO/CORR Wall thinning

extraction line

10 Containment system Containment Steel shell (Carbon?) steel Not stated CORR/BA Loss of material

structure

Document: IN&B 1990, 1990 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Service water Check valve Swing arm 17-4 PH stain-less Borg-Warner CORR/SCC Crack initiation and

system steel, H1100 heat growth

treatment

2 Service water Motor-operated Valve seat Not stated BIF/General Signal ENVIR Physical degradation

system butterfly valve Corp.

3 Service water

system

Piping and heat Sexchangers

Valve seat Not stated Not stated CONTAM Buildup of deposits
Table A.1 Gall Report for Information Notices Page 1B

Document: IN&B 1989, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL

I~ffaent nf Aninn nn tCnmonnnnt Funrtion Contrib to Failure Ren(orted oroas Rel.D~roas Report Recommendations Pace No. Item ........ o inn "f ... ... ................................ ... ... .. '-•_ ._.....r- Report Recommendations

Significant localized wall thinning of 16- Not stated Not discussed in Not stated 89-01 1

and 24-in. valve bodes apparently caused report

by cavitation can lead to rupture.

Abrupt decoupling of pump shaft and Not stated Not discussed in Use improved vibration monitoring 89-15 2

impeller probably caused by shaft fracture report system to detect growing cracks in

or failure of cap screws and drive pins, shaft [2]

resulting in pump failure. Root cause is

undetermined, but possibly fatigue.

Failure of attachment weld was repaired Not stated Not discussed in Repair with full-penetration welds 89-20 3

by fillet welds that failed four years later, report and realignment of ring. [2]

resulting in pump failure and loose parts

in the recirculation loop.

lntergranular cracking, apparently Not stated Not discussed in Replace plugs from suspect heats of 89-33; 4

associated with improper heat treatment report material; discontinue use of Bull. 89-

and/or susceptible heats of material, can Westinghouse plugs. [4] 01,89-01,

cause mechanical tube plugs to loosen, Suppl. 1 &

leak, and sometimes be forcibly ejected, 2.

causing additional tube damage. I

Intergranular cracking, apparently Not stated NRC Bull. 89-01 Conduct eddy current inspections of 89-65 5

associated with intragranular carbides and installed plugs. [4]

relatively little intergranular precipitation

improper heat treatment and susceptible

heats of material, could lead to possible

plug failure.

Foreign particles from steamlines lodge in Not stated Not discussed in Design modifications have been 89-38 6

valve clearance areas and on sealing report implemented by the manufacturer [1]

surfaces, resulting in leakage past valve

plug piston ring and consequent valve

malfunctioning.

Repeated operation of the pumps at 60% Not stated Not discussed in Avoid sustained operation of pumps 89-087

or less of their design flow resulted in report at low flow rates [4]

slow deterioration of internal components,

causing eventual loss of pump function.

Prolonged exposure of electrical cable Not stated NRC Temporary Provide better containment cooling to 89-30 8

insulation to temperatures above their Instruction 2515/98 maintain temperatures below the EQ

environmental qualification (EQ) design temperature [4]

temperature, e.g., in reactor containment,

can lead to insulation breakdown and

failure.

Abrupt change in I.D. at nozzle-to-pipe Not stated NRC Bull. 87-01 Not stated 89-53 9

connection apparently causes flow

turbulence, leading to accelerated

erosion-corrosion of adjacent piping.

Boric acid leaking from instrument line Not stated 10CFR50, Appendix Containment in-service inspection 89-79; 89- 10

compression fittings condenses on the J for wail thinning by corrosion [4] 79, Suppl.

outer surface of the containment steel 1

shell, resulting in general and pitting

corrosion.

Document: IN&B 1990,1990 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.pr•gs Report Recommendations Page No. Item

Preexisting casting defects, including Not stated Aerospace Materials Replace with parts from another 90-03 1

porosity, hot cracks, and weld repairs, Spec. 5398A and vendor; inspect parts for flaws

plus improper heat treatment, resulted in Mil. Spec. MIL-H- before installation. [4]

propagating cracks in the high chloride 6875

service water that caused fracture and

loss of function.

Valve seat material hardens with time Not stated GL 89-10 Set open torque switch to maximum 90-21 2

under service conditions, causing value; test and inspect valves. [4]

increase in coefficient of friction and

,possible failure of valve to open.

Accumulation of silt and corrosion

products in piping reduced emergency

water flows to levels below design basis

conditions.

Not stated 10CFR50, Append.

A and B

Cleaning of contamination and

adjustments in flow distribution [4]

90-39
Table A.1 Gall Report for Information Notices

Document: IN&B 1990,1990 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item Syse fuc~tureIComn Suboc

Page 2A

)mbonent Materials Manufacturer ARD mechanism ARD effects

4 Service water Containment air Tubes Not stated Not stated CONTAM Buildup of deposits

system coolers

5 Service water Service water lines Check valves Not stated Not stated CONTAM Buildup of deposits

system

6 Service water Piping Not stated Not stated CORR; CORR/MIC Loss of material;

system corrosion product

buildup

7 Cooling system Steam generator Upper shell-to- Not stated Westinghouse and CORR; Loss of material;

transition cone girth Combustion FAT/THERM cumulative fatigue

welds Engineering damage

8 Cooling system Steam generator Tubes Not stated Westinghouse and CORR/SCC Crack initiation and

Combustion growth

Engineering

9 Cooling system Pressurizer Pressurizer heater Inconel 600 Not stated CORR/PWSCC Crack initiation and

thermal sleeves growth

10 Cooling system Coolant pumps Bolts fastening A453, Gr. 660 (Alloy Not stated, but CORR/IGSCC Crack initiation and

turning vanes A-286) similar to growth

Westinghouse

design

11 Pressure vessel Pressure vessel Weld cladding and Not stated Not stated CORR/SCC Crack initiation and

upper head base-metal heat- growth

affected zone

Document: IN&B 1991, 1991 NRC Information Notices

Reviewed by: Dwight R. Dieroks, ANL

Item System StuctureIComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Moisture separator 6-inch, schedule 40 Carbon steel Not stated ERO/CORR Wall thinning

drain piping

2 Cooling system Feedwater regulating 6-inch piping Carbon steel Not stated ERO/CORR Wall thinning

valve bypass line

3 Cooling system Low-pressure drain Piping Carbon steel Not stated ERO/CORR Wall thinning

system

4 Cooling system Row-measuring- Orifice flange Carbon steel Not stated ERO/CORR Wall thinning

orifice

5 Cooling system Moisture separator 8-inch elbow Carbon steel Not stated ERO/CORR Wall thinning

reheater

6 Cooling system Steam generators Feedwater

distribution feedring

piping

Carbon steel Combustion

Engineering

FAT/THERM;ERO/

CORR

Cumulative fatigue

damage; wall

thinning
Table A.1 Gall Report for Information Notices Page 2B

Document: IN&B 1990, 1990 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL Effet of Aainal on Comnonent Funotion Contrib to Failure Relnorted nroas Rel.nroas Rel~ort Reoommendations Pae No. Item

Buildup of silt and corrosion products in Not stated IOCFR50, Append. Remove deposits [4] 90-39 4

containment air cooler tubes reduced A and B

service water flow rates to unacceptable

levels.

Buildup of silt in emergency water service Not stated 1OCFR50, Append. Remove deposits [4] 90-39 5

line check valve could have prevented A and B

system from functioning.

Acidic well water and MIC have resulted Not stated 1OCFR50, Append. Chemically clean system and/or 90-39 6

in a corrosion pitting rate of 24 mils per A and B replace pipe [4]

year in the affected components.

Corrosion fatigue from thermal cycling, Not stated Not discussed in Perform more frequent inspections 90-04 7

dissolved oxygen in feedwater, and Cu report of affected region. [4]

alloys in feedwater system result in crack

initiation at surface corrosion pits and

subsequent crack growth into girth welds. I

Secondary side-initiated cracking of Not stated Not discussed in Plug leaking tubes; develop 90-49 8

steam generator tubes, typically in the report improved NDE techniques to detect

expansion transition near the tubesheet or cracks [4]

at the support plate, has resulted in

leaking cracks in several PWRs.

Residual stresses from reaming or roll Not stated Not discussed in Implement augmented inspection 90-10 9

joining plus a susceptible Inconel 600 report program. [4]

microstructure and the PWR coolant

environment lead to PWSCC and

leakage.

Alloy A-286 is subject to IGSCC at peak Not stated B&W Owner's Discontinue the use of Alloy A-286 90-68 10

stresses >100 ksi, depending upon Cr Group Report BAW- as a reactor structural material. [4]

content, fabrication practice, and 1842

environment The present failures

occurred in foreign reactors and

threatened coolant pump function.

Grinding residual stresses, low delta- Not stated General Electric Co. PT of back-clad region for surface 90-29 11

ferrite content, and high dissolved-oxygen RICSIL No. 050 cracks and enhanced UT for

in the coolant induce interdendritic SCC subsurface cracks. [4]

of weld cladding, and resulting cracks

propagate into underlying base metal,

possibly threatening structural integrity. __

Document: IN&B 1991, 1991 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

High-velocity turbulent flow of water Not stated Not discussed in System found to be susceptible by 91-18 1

through piping caused wall thinning by report EPRI CHEC code and should have

erosion/corrosion and resulted in pipe been inspected [4]

rupture and actuation of fire-protection

deluge system.

High-velocity turbulent flow of water Not stated Not discussed in Failed piping replaced [4] 91-18 2

through piping caused wall thinning by report

erosion/corrosion and resulted in steam

leak and repair outage.

High-velocity turbulent flow of water Not stated Not discussed in Failed piping temporarily replaced 91-18 3

through piping caused wall thinning by report with A106, Gr. B; permanent

erosion/corrosion and resulted in piping replacement to be A335-P22. [4]

rupture.

High-velocity turbulent flow of water Not stated Not discussed in Failed flanges temporarily replaced 91-18 4

through piping caused wall thinning by report with same material; more-resistant

erosion/corrosion and resulted in flange material being considered for

rupture. _permanent replacement [4]

High-velocity turbulent flow of water Not stated Not discussed in System found to be susceptible by 91-18, 5

through piping caused wall thinning by report CHECMATE code and should have Suppl. 1

erosionjcorrosion and resulted in elbow been inspected [4]

rupture and actuation of fire-protection

deluge system., I I

Cracking and wall thinning resulted in

component failure and introduction of

loose parts into secondary side of steam

generator.

Not stated Not discussed in

report

Component redesigned for

increased strength and erosion

resistance. [4]

91-19
Table A.1 Gall Report for Information Notices

Document: IN&B 1991, 1991 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Page 3A

Item System Structure[Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

7 Cooling system Steam generators Tubing Not stated Mitsubishi (based on FAT Cumulative fatigue

Westinghouse damage

design)

8 Cooling system Steam generators Tubing Not stated Combustion Not stated Not stated

Engineering

9 Cooling system Steam generators Tubing Not stated Babcock & Wilcox FAT Cumulative fatigue

damage

10 Cooling system 1-inch accumulator Nozzle-to-pipe weld Not stated Not stated FAT; VIBR Cumulative fatigue

fill line damage; crack

initiation and growth

11 Cooling system Condensate storage Diaphragm Not stated Goodyear Co.; Lorel ENVIR Chemical or physical

tanks Corp. degradation

Document: IN&B 1992,1992 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cooling system Steam generators 4-inch, schedule 80 A106B carbon steel Westinghouse ERO/CORR Wall thinning

feedwater piping

2 Cooling system Primary coolant loop Reducing tee riser Not stated Not stated ERO/CORR Wall thinning

3 Cooling system Pressurizer power- Valve stems SA 564, Type 630, Rockwell EMBR/TE Loss of fracture

operated relief valves H900-H 1150 (17-4 International (now toughness

PH) stainless steel Edward Valve Co.)

4 Emergency Manual gate valves Valve bodies CF8M cast stainless Not stated FAT Cumulative fatigue

condenser system steel damage

5 Reactor internal Core shroud support Welded access hole Inconel 600 with General Electric CORR/IGSCC Crack initiation and

support structure plate Inconel 82 or 182 growth

weld filler metal

Document: IN&B 1993,1993 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Emergency Core Residual heat Thrust bearing Not stated Ingersoll-Rand WEAR Attrition

Cooling system removal pump

2 Emergency Core Residual heat Discharge check Not stated Copes-Vulcan FAT Cumulative fatigue

Cooling system removal pump valve lock wire damage

3 Emergency Core

Cooling system

Residual heat

removal pump

Discharge check

valve disk and

hanger assembly

Stainless steel

locking device; other

parts not stated

Pacific Valve

Engineering

VIBR Loosening
Table A.1 Gall Report for Information Notices Page 3B

Document: IN&B 1991, 1991 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aqinl on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

High-cycle fatigue failure of steam Not stated Not discussed in Incorrect insertion of antivibration 91-43 7

generator tube at uppermost support plate report corrected [4]

resulted in excessive primary-tosecondary leak rate.

Cracking of steam generator tube at U- Not stated NRC Bull. 88-02, Not stated 91-43 8

bend at a location where flow conditions Fig. 1

permit contaminants to be deposited on

the tube surface resulted in excessive

primary-to-secondary leak rate.

Tube cracking at lower face of upper Not stated NRC Bull. 88-02, Not stated 91-43 9

tubesheet resulted in excessive primary- Fig. 1

to-secondary leak rate.

Two ruptures of the nozzle-to-pipe weld in Not stated Not discussed in Revise operation procedures [4] 91-50 10

the accumulator fill line during filling were report

caused by flow-induced vibration and

resulted in spillage of coolant.

Long-term deterioration of diaphragms in Not stated Not discussed in Replace diaphragms after 9 years or 91-82 11

contact with their service environment report more frequently if indicated by

results in the development of holes and inspections. [4]

tears, with consequent leaks and possible

clogging of equipment.

Document: IN&B 1992, 1992 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

High-velocity flow of water through piping Not stated Not discussed in Redesign piping to reduce flow 92-07 1

caused wall thinning by erosion/corrosion report velocity. [4]

and necessitated the replacement of 90

feet of piping for which the wall thickness

was at or near the minimum allowable.

High-velocity flow of water through Not stated NRC Bull. 87-01; Not stated 92-35 2

reducing tee riser caused wall thinning by NRC GL 89-08

erosion/corrosion and necessitated component replacement because wall thickness was near the minimum allowable. I

Valve stems are subject to secondary Not stated Not discussed in Not stated 92-60 3

aging after several thousand hours at 600 report

F, resulting in increased susceptibility to

fracture when subjected to excessive

torque from power actuator.

Fatigue (possibly thermal) resulted in Not stated Not discussed in Not stated 92-50 4

leaking cracks in at least one gate valve report

and partially through-wall cracks in

several other valves. I

Apparent IGSCC of welds joining access Not stated GE SIL No. 462, Perform periodic visual and UT 92-57 5

hole covers to shroud support plates Suppl. 3 examinations of region; repair

resulted in circumferential cracking in procedures being developed [4]

weld region, with some cracks possibly

propagating into the adjacent base metal.

Document: IN&B 1993, 1993 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Thrust load during normal operation Not stated Not discussed in Redesign pump to reduce bearing 93-08

exceeded design value, resulting in report load; replace periodically. [4]

abnormally high wear of bearing and

failure after approx. eight fuel cycles.

Inadequate disk nut torquing allowed nut Not stated Not discussed in Replace lock wire with 1/8-in. cotter 93-16 2

to rotate back and forth. Resulting cyclic report pin (4]

loading caused high-cycle fatigue failure

of lock wire, loss of disk nut and washer,

and check valve failure. I I I

Inadequate capscrew torquing, missing

capscrews, and improper reuse of locking

device results in capscrew loosening, loss

of disk and hanger assembly, and check

valve failure.

Not stated Not discussed in

report

Revise maintenance procedure to

ensure correct installation. [4]

93-16 3
Table A.1 Gall Report for Information Notices

Document: IN&B 1993, 1993 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Page 4A

Item S~e •tr.chJr•/Comn •iihr~mnnnent Mnteril_• Mln. i ~pifh irew A~r1 rnrkhniem AI~fl •ff•_t@

4 Emergency Core Residual heat Coolant pump Not stated Not stated CLOG Blockage of flow

Cooling system removal pump strainers and passages

containment sump

screens

5 Emergency Core High-pressure Steam exhaust Stainless steel Black Sivalls & Not stated Not stated

Cooling system coolant injection rupture disk Bryson, Inc.

pump

6 Cooling system Steam generators Feedwater piping Not stated Westinghouse and FAT/THERM Cumulative fatigue

Combustion damage

Engineering

7 Cooling system Piping Feedwater piping Carbon steel Not stated ERO/CORR Wall thinning

and other

components

8 Cooling system Turbine-driven Turbine stop valve Not stated Not stated CONTAM Loss of lubricant

feedwater pumps properties

9 Cooling system Motor-operated gate Valve yoke Case carbon steel Walworth FAT Cumulative fatigue

and globe valves damage

10 Cooling system Jet pump Hold-down beam Not stated General Electric Co. CORR/IGSCC; FAT Crack initiation and

growth; cumulative

fatigue damage

11 Spent fuel storage Spent fuel storage Boraflex neutron Polymer base with Brand Industrial ENVIR Physical degradation

system racks absorbing material silica filler and Services, Inc.

neutron absorber

(boron?)

12 Reactor internals Core shroud Beltline region welds Stainless steel General Electric Co. CORR/IGSCC Crack initiation and

growth

13 Reactor internals Fuel rods Fuel rod cladding Zircaloy Westinghouse, WEAR/FRET Attrition

Siemens, General

Electric Co.

Document: IN&B 1994, 1994 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electrical generating Turbines Turbine blades Not stated General Electric Co. FAT Cumulative fatigue

system damage

2 Electrical generating Turbine low auto Plunger rod, stainless steel and Not stated CORR Corrosion product

system stop oil pressure bushing, and case aluminum buildup

switch

Cooling system Steam generator Kinetically weldrepaired tubesIncone1600 Babcock & Wilcox CORR/PWSCC Crack initiation and

growth
Table A.1 Gall Report for Information Notices Page 4B

Document: IN&B 1993,1993 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aginq on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Foreign debris can block emergency core Not stated Not discussed in Remove debris [4] 93-34 and 4

cooling screens and sumps, resulting in report 93-34,

possible reduced emergency core cooling Suppl. 1

in and accident situation.

Rupture disk failed unexpectedly after 20 Not stated Not discussed in Replace 20-year-old rupture disks 93-67 5

years of service, resulting in personal report with new ones. [4]

injuries. Cause of failure is unclear, but

vendor speculated that an unspecified

aging process may have caused the

strength to degrade.

Thermal stratification in feedwater lines, Frequent NUREG/CR-0691 Reduce severity of thermal cycles. 93-20 6

particularly during cold, low-flow [4]

conditions, leads to rapid thermal fatigue

loading, resulting in cracking and leakage.

Erosion/corrosion has been observed to Frequent ASME Section Xl, Develop improved inspection and 93-21 7

cause excessive wall thinning and IWA 4100 and 4300 repair procedures in accordance

possible piping failure in numerous plants. with ASME Section Xl. [4]

Inspection and repair procedures are

often inadequate.

Gradual buildup of contaminants in the Not stated Not discussed in Flush oil system [4] 93-48 8

control oil for the stop valve on the report

turbine-driven feed water pump caused

the valve to stick open when the main

turbine tripped, resulting in overfill of the

pressure vessel.

Preexisting defects, component design, Not stated Not discussed in Weld repair cracks; torque bolts 93-97 9 and insufficient bolt torque can lead to the report sufficientiy when reinstalling yokes.

initiation and growth of fatigue cracks that [4]

could cause eventual component failure.

IGSCC that initiated at a machined radius Not stated Not discussed in Replace beams of similar design if in 93-101 10

propagated over -80% of the cross- report service for more than 8 years. [4]

sectional area. The resulting loss of

preload apparently led to fatigue crack

growth and eventual component failure.

Surveillance coupons of Boraflex tested Not stated EPRI TR-101986 Not stated 93-70 11

after five years had degraded

substantially. Similar degradation of the

Boraflex used in the high-density spent

fuel storage racks would result in loss of

subcriticality margin in the pool.

IGSCC in the HAZ of core shroud circum- Not stated GE RICSIL 054, Add stiffening braces to the top 93-79 12

ferential welds near the beltline resulted in Rev. 1 portion of the shroud. [4]

axial cracking that may compromise the

structural integrity of the shroud.

Debris-induced fretting and grid-to-rod Not stated Not discussed in Install vibration damping; redesign 93-82 13

flow-induced vibrational fretting can lead report core to reduce vibration. [4] to cladding perforation and fuel rod failure. I I I I I

Document: IN&B 1994, 1994 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs. Report Recommendations Page No. Item

Torsional excitation of the turbine- Not stated Not discussed in Not stated 94-01 1

generator shaft from an electrical system report

disturbance causes vibration, resulting in

separation of turbine blades by high-cycle fatigue.

Apparent galvanic corrosion between the Not stated Not discussed in Not stated 94-11 2

SS plunger rod and the remaining Al parts report

caused corrosion product buildup and

switch malfunction, resulting in an

erroneous signal to the control computer

and turbine overspeed.

Tubes repaired with kinetically welded

sleeves may be susceptible to PWSCC

adjacent to the sleeve because of residual

stresses introduced, despite the postweld heat treatment. Result is tube

leakage.

Not stated Not discussed in

report

Not stated; problem still under

investigation [4]

94-05 a
Table A.1 Gall Report for Information Notices

Document: IN&B 1994, 1994 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL

Item Syse tucture/ComD Subcc

Page 5A

)mnonent Materials Manufacturer ARD mechanism ARD effects

4 Cooling system Main steam isolation Guide ribs Not stated Atwood & Morrill WEAR Attrition

valve Co., Inc.

5 Cooling system Standby service Bolts and Carbon steel Not stated CORR Loss of material

water pump lockwashers in shaft

coupling assemblies

6 Cooling system Pipe snubbers Internal lubricant Hydrocarbon grease Pacific Scientific ELE-TEMP Chemical and

physical degradation

7 Emergency core Air dampers and Elastomer seals Buna-N Not stated ELE-TEMP Chemical and

cooling system solenoid valves physical degradation

8 Emergency core Shutdown cooling Sealing surfaces of Stellite Anchor-Darling RESID; Crack initiation;

cooling system suction isolation valve disk and slide FAT/THERM cumulative fatigue

valves seat ring damage

9 Emergency core High-pressure Torque switch drive AISI 1070 carbon Limitorque EMBR; ENVIR Loss of fracture

cooling system coolant injection pinion gear roll pin steel toughness; chemical

motor-operated valve and physical

degradation

10 Emergency core High head safety Pump casing Carbon steel clad Dresser Industries, Not stated; Crack initiation and

cooling system injection pump with stainless steel Pacific Pump CORR/BA growth; loss of

Division material

11 Reactor internals Core shroud Core plate support Stainless steel General Electric CORR/IGSCC Crack initiation and

ring weldment Company growth
Table A.1 Gall Report for Information Notices Page 5B

Document: IN&B 1994,1994 NRC Information Notices

Reviewed by: Dwight R. Diercks, ANL Effect of Aaina on Comnonent Function Contrib to Failure Reported aroas Rel.oroas Renort Recommendations Paae No. Item

Improper clearances between valve Not stated NRC Inspect. Rept Install anti-rotation modification from 94-08 4

poppet and body can cause excessive 50-458/93-18 manufacturer [4]

wear of guide ribs, resulting in failure of

valve to close properly.

Extensive general corrosion of the bolts Not stated Not discusses in Rebuild pumps; modify testing 94-45 5

and lockwashers in the pump shaft report procedure to detect internal changes

coupling assemblies caused shifting of before severe damage occurs. [4]

internal parts and damage to impellers

and bowls, resulting in degraded vibration

performance.

Prolonged exposure to temperatures of 38 Common Not discussed in Replace failed snubbers; develop 94-48 6

to 93 deg. C caused the internal lubricant report criteria for service life program. [4]

grease to bake and dry out, resulting in

insufficient drag resistance during testing.

Prolonged exposure to elevated temper- Not stated Not discussed in Replace affected components with 94-06 7

atures causes the Buna-N elastomer seal report qualified replacements. [4]

material to break down, resulting in leakage of the nitrogen supply for the automatic depressurization valves and

possible failure of these valves in a LOCA

situation.

High residual stresses from inadequate Not stated Not discussed in Not stated 94-30 8

stress relief or thermal fatigue led to the report

initiation and growth of cracks in the

sealing surfaces of the valves, resulting in

excessive valve leakage.

Brittleness of roll pin material, possibly Not stated Not discussed in Replace with larger diameter pin 94-49 9

combined with hardening of grease in report fabricated of Type 416 stainless

drive mechanism in one case, caused steel for better ductility and impact

shear fracture of pin under load, resulting resistance. [4]

in failure of valve.

Cracking of the stainless steel cladding Not stated Pacific Pump Perform field inspections described 94-63 10

from an unidentified cause leads to Bulletin 037-0-0104- in Pacific Pump Bulletin 037-0-0104-

exposure of the underlying carbon steel, 0 0. [4]

which corrodes relatively rapidly in contact

with boric acid in the coolant.

IQSCC in and near the HAZ of the Not stated GE RICSIL 054, Safety implications under 94-42 11

outside circumference of the core plate Rev. 1 investigation by NRC. [4]

support ring weldment resulted in a 360

circum-ferential crack with a max. depth

of -2.13 cm in two different reactors.
Table A.1 Gall Report for Licensee Event Reports Page 1A

Document: LER's, Licensee Event Reports (LERs)

Reviewed by: Ma and K. E. Kasza, ANL

Item System StructurelComp SubcomDonent Materials Manufacturer ARD mechanism ARD effects

1 Control Rod Drive Scram Solenoid Pilot Pressure and Rubber Automatic Switch ELE-TEMP Hardening, cracking

Valves Exhaust Diaphragms Company

2 Control rod drive Scram solenoid pilot Diaphragm Buna-N General Electric EMBR Loss of fracture

valves toughness

3 Containment Personal Airlock Door Shaft Seal Not stated Not stated WEAR Attrition

Range Bolts

4 Containment Main Steam Isolation Seat Surfaces, Not stated Not stated WEAR, RATCH Attrition, change in

Valves Actuator Spring dimension

5 Containment Vent Valve Seal Nitrile Elastomer Atwood and Morrill WEATH Loss of capacity

Co.

6 Containment H2/02 gas analyzer Analyzer pump Not stated Teledyne Not stated Not stated

diaphragm

7 Penetration Inboard Containment Boot Seal Not stated Not stated ENVIR Chemical or physical

Pressurization Purge Exhaust degradation

System Valves

8 Condenser System Low Pressure Exhaust Boot Seal Fabric Reinforced Uniroyal FAT Cumulative Fatigue

Turbines Rubber Damage

9 Feedwater Check Valve Seal Rubber (Parker Not stated ELE-TEMP/ERO Physical

E692) degradation, loss of

material

10 Hot Leg Loop Isolation Valve Valve Stem 17 4PH Stainless Not stated CORR/SCC Crack initiation and

Steel (ASTM A 56M growth

Type 630)

11 Auxiliary Feedwater Pump Pneumatic Different Pressure Not stated Not stated EDS (setpoint drift) Loss of function

Speed Control Loop Transmitter

12 Emergency diesel Fuel oil injector Injector screw Not stated Nordberg Not stated Not stated

generator pump

13 Spent fuel pool Charcoal absorber Seal on bypass Rubber Johnson Controls Not stated Not stated

exhaust ventilation damper blade edge

-14 Spent fuel pool Charcoal absorber Damper blades Not stated Johnson Controls Not stated Not stated

exhaust ventilation

15 Fail-safe 2 way solenoid valve Seal O-ring Not stated Versa Product Co. FAT Cumulative fatigue

accumulator damage

161 Power system Steam generator Tube Not stated Combustion

Engineering System80

CORR/IGSCC Crack initiation and

growth
Table A.1 Gall Report for Licensee Event Reports

Document: LER's, Licensee Event Reports (LERs)

Reviewed by: Ma and K. E. Kasza, ANL

Effect of Aaina on Component Function Contrib to Failure

Page 1B

Reported progs Rel.progs Report Recommendations Page No. Item

Control rod failed to scram due to Frequent Not discussed in PS TS Req. Use of new diaphragm material [2] 94-005-01

degradation of pilot valve elastomers report

(hardening, cracking and permanent set)

caused by high temperature produced by

the energized solenoid coils.

Control air leakage through degraded Not applicable Not discussed in PS TS Req. Not stated 94-005-00 2

solenoid diaphragms rendered valve report

inoperable and failure to scram a control

rod resulted.

Excessive force to support shaft bearing Moderate Not discussed in 10CFR5O App. Including inspection of the shaft seal 92-026-00 3

and increased use of the airlock caused report J & PS TS gasket bolts in plant maintenance

the shaft seal flange to loosen and move Req. and inspection [4]

away from its seating, resulting in test

pressure drop below criteria of

containment aidock leakage test.

During local leak rate testing, the leak rate, Frequent Not discussed in PS TS Req. Replace springs on regular basis [4] 92-013-01 4

limit was exceeded due to degraded valve report

seal seat surfaces (misalignment of the

poppet seat caused by wear of the guide

ribs.)

Leakage of rubber seal attributed to Not stated Not discussed in PS TS Req. The failed seal was replaced and the 89-005-00 5

weather checking on exposed surface and report leak rate met acceptance cri teria.

storage causing unacceptable leakage in To prevent recurrence, both shelf life

an Appendix J Type B leakrate test. and durometer testing requirements

shall be considered in the

procurement documents [4]

Incorrect readings of oxygen Not applicable Not discussed in PS TS Req. Not stated 92-009-00 6

concentration because of air leak into report

analyzer.

Environmental aging of seal material Not stated Not discussed in ASME Sec XI Not stated 93-001-00 7

caused leakage of PPS exceeding report & PS TS Req.

allowable rate. Seating area was cleaned

and the leakage stopped.

Loss of condenser vacuum due to fatigue Moderate Not discussed in PS TS Req. Replace entire boot seal rather than 92-010-00 8

failure of the north low pressure turbine report performing local repair [2)

exhaust boot seal (a fabric reinforced

rubber expansion joint), causing an

automatic turbine trip and reactor trip. Frequent

Leakage of rubber seal due to thermal Frequent Not discussed in ASME Sec XI Replace the soft seal material 86-017-01 9

aging and erosive wear, causing report IWV & PS TS (Parker E692) with a new material

excessive leak rate of the check valves. Req. more resistive to thermal aging and

erosive wear than the original [4]

Crack due to tensile stress on the stem Infrequent Not discussed in ASME Sec XI To minimize the in service stresses, 86-008-01 10

and entrapped water propagated through report IWV & PS TS the valves will be soft back seated

the valve stem diameter, resulting in the Req. during plant heatup and hard back

valve gate being in a partially closed seated only when operating

position. temperature is reached [4]

Inoperability of the pump pneumatic Not stated Not discussed in PS TS Req. Record turbine steam bowl 89-016-02 11

speed control loop due to leaking bellows, report pressures, including the speed

setpoint drift, limited pump speed and control loop. In the preventive

discharge pressure below that needed to maintenance/calibration program at

inject water into the steam generators initial plant startup, perform periodic

under some accident conditions. full flow test [4]

Emergency diesel generator not operable Not applicable Not discussed in PS TS Req. Not stated 92-009-00 12

to allow fixing of injector pump. report

Over time the rubber seals lose pliability Not applicable Not discussed in PS TS Req. Not stated 92-008-00 13

and allow leakage in the ventilation report

system.

Bent damper blades prevented sealing Not applicable Not discussed in PS TS Req. Not stated 92-008-0 14

and caused leakage in the ventilation report

system. I I II

Deterioration of O-ring caused control air Not applicable Not discussed in PS TS Req. Not stated 93-005-001 15

leakage and failure of solenoid to meet report

specs. I I II

Rupture of tube causes leakage leading to

low pressurizer level and pressure

causing reactor trip and radiation in

secondary system.

Not applicable Steam Generator

Task Force formed

ASME Sec XI

IWB & PS TS

Req.

Not stated 93-00 1 -ox 16
Table A.1 Gall Report for Licensee Event Reports

Document: LER's, Licensee Event Reports (LERs)

Reviewed by: Ma and K. Kasza, AN L

Page 2A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

17 Main steam line Isolation valve (globe Seat Not stated Atwood and Morrill CORR/PIT Local loss of materia

valve) Company Inc.

18 Main steam line Isolation valve (globe Seat Not stated Atwood and Morrill CREEP Change in

valve) Company Inc. dimension

19 Essential cooling Traveling screen Flexible coupling Elastomeric Rexnord ENVIR Chemical or physical

water filter degradation

20 Not stated High Pressure Auto Stop Oil Une Not stated Not stated RESID/FAT Crack initiation,

Turbine Stop Valve cumulative fatigue

damage

21 Penetration Inboard Containmeni Seal Seat Not stated Not stated ENVIR Chemical or Physica

Pressurization Purge Exhaust Degradation

System Valves

22 Emergency Power Diesel Generator Fuel Oil Not stated Not stated OX Buildup of Deposit

System

23 Emergency Power Diesel Generator Fuel Oil Not stated Not stated OX Buildup of Deposit

System

24 Containment Spray Heading Piping Spray Nozzle Piping: Carbon Steel Not stated CLOG Blockage of flow

System passages

25 Fire Protection 3-hour Fire-rated Penetration Fire Seal Silicone Foam Not stated Improper Loss of Function

Barriers installation/lack of

inspection rqmt.

26 Steam Generator Air-operated Valve Actuator Rubber Not stated ENVIR Physical

Blowdown Outlet Isolation Valve Rubber Diaphragm Degradation

27 Not stated Main Condenser Expansion Joint Rubber Not stated ENVIR Physical

Degradation

28 Not stated Turbine Low Pressure Rubber Uniroyal FAT Cumulative Fatigue

Exhaust Boot Seal Damage

29 Emergency Cooling Motor-operated Not stated Not stated Not stated Improper Switch Loss of Function

System and Valves Setting

Containment Spray

System

30 Primary Containmeni Isolation Valves, O-rings, Seat Rings, Ethylene-propylene, Various ENVIR/WEAR Physical

Isolation System Reactor Vessel Gaskets Rubber Degradation, Atthitior

Stabilizer Hatch

31 Containment Electric Penetration Seals Polyurethane Bunker Ramo Hydrolysis Physical

Penetration Assemblies Degradation, Attritior
Table A.1 Gall Report for Licensee Event Reports

Document: LER's, Ucensee Event Reports (LERs)

Reviewed by: Ma and K. Kasza, ANL

Effect of Aaina on ComDonent Function Contrib to Failure

Page 2B

Renorted oroas Rel.mroas Report Recommendations Paqe No. Item

Technical specifications for leakage limits Moderate Not discussed in ASiME Sec Xl Not stated 93-003- 17

on valves is exceeded, report & PS TS Req. 01; 003-

02

Technical specification for leakage limits Infrequent Not discussed in ASME Sec XI Not stated 93-003-01 18

on valves is exceeded, report & PS S&T

Req.

Aging of elastomeric couplings resulted in Not applicable Not discussed in PS S&T Req. Not stated 93-010-00 19

their cracking and failure of traveling report

screen filter to operate.

Turbine stop valve closure due to auto Rare Not stated PS S&T Req. Perform visual inspection of the 89-011-00 20

stop oil line weld leak resulted in a manual accessible welds, measure vibration

reactor trip and a manual safety injection, of the auto stop oil line during plant

The weld failure was due to inadequate startup [4)

field installation (overlapping welds) and

fatigue.

Environmental aging of seal material Not stated Not stated PS S&T Req. Not stated 93-013-01 21

caused leakage of PPS exceeding

allowable rate. Seating area was cleaned

and the leakage stopped. I

Oxidation of fuel oil due to a high Infrequent Not stated RG 1.9, RG Periodic replace ment of the fuel oil 89-001-00 22

concentration of insolubles clogging the 1.108 & PS TS and use of a higher grade diesel fuel

sample filter, causing inoperability of Req. oil which has a longer shelf life [4]

diesel generator.

Oxidation of fuel oil due to a high Infrequent Not stated RG 1.9, RG Periodic replacement of the fuel oil 89-001-01 23

concentration of insolubles clogging the 1.108 & PS TS and use of a higher grade diesel fuel

sample filter, causing inoperability of Req. oil which has a longer shelf life. Add

diesel generator. a biocide, a dispersant and a

stabilizer to extend the shelf life. [4]

Nozzle blockage due to accumulation of Frequent Not stated PS S&T Req. Replacement of the CSS nozzles 90-021-00 24

the deteriorated coating of the CSS piping & PS TS Req. with clog resistant nozzles [4]

inner surface could block the CSS flow.

Gaps, tears, or splits due to improper Frequent Not stated PS S&T Req. Use a different type of foam and 90-002-00 25

installation and lack of inspection different installation techniques [4]

requirements were found in the seals.

Propagation of a fire across boundary

would affect the plant safe shutdown.

Failure of rubber diaphragm resulting in Not stated Not stated ASME Sec Xl Not stated 92-001-00 26

air leakage and failure of the valve IWV & PS S&T

closure. Req. I

The air leakage through the torn Infrequent Not stated PS S&T Req. Periodic replacement of the 92-003-00 27

expansion joint rubber belt caused low & PS TS Req. expansion joints [2]

vacuum in the main condenser and

subsequent manual reactor and main

turbine trip.

Failure of the north low pressure turbine Not stated Not stated PS S&T Req. Not stated 92-007-00 28

boot seal due to fatigue caused

condenser low vacuum and subsequent

automatic reactor and turbine trip.

Isolation valves were not capable of full Frequent GL89-10 ASME Reconfigure and test the MOVs to 92-006-00 29

closure under design basis conditions due satisfy the GL89 10 criteria [4]

to improper drive gear sets and torque

switch settings.

Brittie and broken O-ring seals of the Frequent Not stated IOCFR50 App. Periodic replacement of the O-rings 88-014-00 30

reactor vessel stabilizer hatch indicated J [4]

that the ethylene propylene (EP) material

is generally unable to resist harsh

environments. O-rings made of silicone

rubber were in good condition.

Degradation of seal material, Frequent Not stated PS S&T Req Use a more durable material, 91-011-02 31

polyurethane, due to hydrolysis would ethylene propylene rubber; install a

allow moisture intrusion into the electrical silicone rubber O-ring as a backup

penetration assembly during a LOCA seal; upgrade the nitrogen supply

event, potentially resulting in discontinuity system to safety-grade system [4]

lof off-site power.
Table A.1 Gall Report for NRC Bulletins Page IA

Document: BL 89-01, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL

Itemn System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Cooling system Steam genertor Tubing mechanical Inconel 600 Westinghouse CORR/PWSCC Crack initiation and plugs growth

Document: BL 89-02, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL
Table A.1 Gall Report for NRC Bulletins Page lB

Document: BL 89-01, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs

Ilntergranular cracking, apparently Not stated Not discussed in

associated with improper heat treatment report

and/or susceptible heats of material, can

cause mechanical tube plugs to loosen,

leak, and sometimes be forcibly ejected,

causing additional tube damage.

Rel.progs Report Recommendations Page No. Item TReplace plugs from suspect heats ol 89-33; 1

material; discontinue use of Bull. 89-

Westinghouse plugs. [4] 01, 89-01,

2.

Document: BL 89-02, 1989 NRC Information Notices and Bulletins

Reviewed by: Dwight R. Diercks, ANL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Susceptibility to SO was apparently Not stated ASME SAl93-86 Inspect bolts for cracks; replace BL 89-02 1

enhanced by improper heat treatment defective bolts with bolts having Rc

(hardness too high), coupled with hardness <=26. [4]

presence of borated water. Resulting

cracking led to bolt fracture.

A.2 Electrical Components and Systems

NUREG/CR-6490
Table A.2 Gall Report for NPAR Reports Page 1A

Document: BNL A-3270-11-85, Seismic Endurance Tests of Naturally Aged Small Electric Motors

Reviewed by: Jerry Edson, INEL

Item Su•tem StructureJComn SubcomDonent Materials Manrufacturer ARD mechanism ARD effects

1 Electric Motors Terminal Boxes Not stated Not stated CORR Improper sealing of

the cover gaskets

2 Electric Motors Stator Winding Not stated Not stated Not stated Break down of

varnish and

insulation

Electric Motors All Other Not stated Not stated Not stated Not stated

I _ _ _ I Components I I I

Document: BNL A-3270-3-86, Testing Program For The Monitoring of Degradation in a Continuous Duty 460 volt Class "B", 10 hp Electric Motor

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electric Motor Dielectrics Organic insulation Not stated ELETEMP MOIST- Insultion degradation

(Insulation) materials EL RAD, VIBR, causes leakage

CURSTR, VOLSTR, through the

CONTAM insulation

2 Electric Motor Bearings Not stated Not stated Not stated Ball or roller surface

defects cause

vibration

Electric Motor Cage (Rotor) Not stated Not stated Not stated Damaged or

defective cage

4 Electric Motor Stator Steel, Copper, Not stated THERM-CY, FAT Stress caused by

Organic insulation differences in

thermal expansion

rates

Document: CHAPTER 24 CABLES, Aging and Ufe Extension of Major Ught Water Reactor Components

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Non-Shielded Single Polymers, Rubber, Not stated ELETEMP, MOIST- Jacket embrittlement

& Multi-Conductor Sicicon, Copper, EL, OXIDAT, & RAD & cracking,

Jacketed Kapton propagating thru

insulation

2 Shielded Pair Multi- Polymers, Rubber, Not stated ELETEMP, MOIST- Jacket & crackingConductor Jacketed Silicon & Copper EL, OXIDAT, & RAD moisture diffuses

through jacket and

cond.

Connections - Non- Not stated Not stated ELETEMP & Moisture diffuses

Sealed MOIST-EL into cables and

connection internals

4 Connections - Polymers Not stated ELETEMP, RAD, & Seals not hermetic

Compression Sealed VIBR

Cables, Halogination Polymers Not stated ELETEMP, RAD, & Electrolytes that

of Filled Polymers MOIST-EL increase leakage or

_1_ losses

6 Mineral Insulated Not stated Not stated THERMO-CY & Open hermetic seals

Cable VIBR

7 Terminal Strips Not stated Not stated CONTAM Increase leakage or

losses

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Battery Chargers Circuit Breakers Contacts, Coil, Not stated Not stated WEAR & LOSLUB Bearing wear &

and Inverters Unkages, & Case solidification of

lubrication

2 Battery Chargers Circuit Breakers Contacts, Coil, Not stated Not stated FAT, OXIDAT Metal fatigue,

and Inverters Unkages, & Case embrittlement &

cracking of

insulation

Battery Chargers

and Inverters

Circuit Breakers Contacts, Coil,

Unkages, & Case

Not stated Not stated OXIDAT & WEAR Oxidation and pitting

of contact surfaces
Table A.2 Gall Report for NPAR Reports Page 1 B

Document: BNL A-3270-11-85, Seismic Endurance Tests of Naturally Aged Small Electric Motors

Reviewed by: Jerry Edson, INEL E~ff~t of Anine, on (Combnonnt Funiofion Contrib to Fnilure Reported nroas Rel.eroas Renort Recommendations Paa=e No. Item Effec of A " ................................ lre ... ..... r '.--.ror . .. r . . R e Page No.. .. .. Leakage of moisture into the box could Not stated Not discussed in No specific Not stated 3, 4 1

lead to termination corrosion'and report program

overheating which could cause degraded

performance or failure to operate

Excessive leakage current and decreased Not stated Not discussed in No specific Not stated 4 2

performance or failure to operate report program

Not stated Not stated Not discussed in No specific Not stated A-6 3

1 report program I

Document: BNL A-3270-3-86, Testing Program For The Monitoring of Degradation in a Continuous Duty 460 volt Class "B", 10 hp Electric Motor

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Leakage through the insulation causes Not stated Not discussed in IEEE 334-1974 Not stated 1, 3,12 1

imbalances between phases, phases with report Section 14

below normal current, and overheating in

phases with above normal current.

Results in decreased output.--

Increased friction and reduced output Not stated Not discussed in IEEE 334-1974 Not stated 3,15 2

report Section 14

Decreased speed or torque Not stated Not discussed in IEEE 334-1974 Not stated 15 3

report Section 14

Additional aging stress to the windings Not stated Not discussed in IEEE 334-1974 Not stated 3 4

report Section 14

Document: CHAPTER 24 CABLES, Aging and Life Extension of Major Light Water Reactor Components

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Circuit ground or short Frequent Limited No specific Utilities (1) monitor temp/rad 845,848,8 1

program determine hot spots, (2) perform 54,863, &

periodic inspections, & (3) don't 865

disturb cables [4]

Circuit opens, grounds, total loss of Frequent Limited No specific Utilities adopt improved failure 845,848,8 2

function program analysis & recording [4] 54,863,

865

Circuit opens, grounds, total loss of Not stated Not discussed in No specific Not stated 845,848,8 3

function report program 63, 865

During DBE moisture enters through Not stated Not discussed in No specific Not stated 845,848,8 4

connection, contacts corride, circuit report program 50,863, &

grounds or shorts 865

Disable function during dbe Not stated Not discussed in No specific Not stated 845,848,8 5

report program 63, & 865

DBE-excessive leakage disables cable Not stated Not discussed in No specific Not stated 845,848,8 6

report program 51, &865

DBE-excessive leakage disables cable Not stated Not discussed in No specific Not stated 833,845,8 7

report program 1 48, & 865

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure to operate Occasional Not discussed in Vendor specific Not stated 4-18 1

report program, Tech.

Spec. surveil.

Falls to open - trip coil force becomes less Occasional Not discussed in Vendor specific Not stated 4-18 2

than spring force. report program, Tech.

Spec. surveil.

Fails to open - loss of continuity across contacts.

Rare Not discussed in

report

Vendor specific

program, Tech.

Spec. surveil.

Not stated 4-18 3
Table A.2 Gall Report for NPAR Reports Page 2A

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Item System StructurelComD Subcomoonent Materials Manufacturer ARD mechanism ARD effects

Item4 Battery Chargers Fuse Not stated Not stated FAT Metal fatigue

and Inverters

5 Battery Chargers Fuse Not stated Not stated ELE-TEMP Melting of link

and Inverters

6 Battery Chargers Relay Contacts Not stated Not stated OXIDAT & WEAR Oxidation & pitting ol

and Inverters contact surfaces

7 Battery Chargers Relay Coil Not stated Not stated CORR Electromechanical

and Inverters action causing

corrosion of fine

wires.

8 Battery Chargers Electrolytic Not stated Not stated ELETEMP Over heating by

and Inverters Capacitors internal stresses

causes loss of

electrolyte

9 Battery Chargers Electrolytic Not stated Not stated VIB Failure of leads

and Inverters Capacitors

10 Battery Chargers Oil Filled Capacitors Not stated Not stated ELETEMP Over heating forms

and Inverters gasses and

dielectric breakdown

11 Battery Chargers Oil Filled Capacitors Not stated Not stated VIB Failure of leads

and Inverters

12 Battery Chargers Transformer Wire Not stated Not stated THERM-CY & Cracking of

and Inverters _ ELETEMP insulation

13 Battery Chargers Transformer Wire Not stated Not stated LOTEMP Cracking of moisture

and Inverters seals

14 Battery Chargers Transformer Wire Not stated Not stated VOLSTR Insulaton material

and Inverters deterioration

15 Battery Chargers Transformer Wire Not stated Not stated VIB & ELETEMP Fracture of

and Inverters connecting wires

and changes in

shunting.

16 Battery Chargers Silicon Controlled Not stated Not stated VOLSTR & Transients resulting

and Inverters Rectifier CURSTR in over voltage &

current &

overheating

17 Battery Chargers Resistor Not stated Not stated VIB Lead fails

and Inverters

18 Battery Chargers Resistor Not stated Not stated ELETEMP Decrease in

and Inverters resistance values as

temperature

increases

19 Battery Chargers Printed Circuit Not stated Not stated THERM-CY Cracking of input

and Inverters Boards lines

20 Battery Chargers Printed Circuit Not stated Not stated CORR Loss of material

and Inverters Boards

21 Battery Chargers Printed Circuit Not stated Not stated VIB Loose or open

and Inverters Boards connection

22 Battery Chargers Surge Suppressor Not stated Not stated VOLSTR OR Semiconductor

and Inverters CURSTR barrier breakdown

I_ due to overheating.

23 Battery Chargers Connectors Not stated Not stated FAT & VI B Fatigue of wires at

and Inverters terminals -

24 Battery Chargers Meters Not stated Not stated CONTAM Dirt on movement

and Inverters and increase in

bearing friction

25 Battery Chargers Meters Coil Insulation Not stated Not stated ELETEMP Coil insulation

and Inverters degrades causing

shorting

26 Battery Chargers Meters Contacts Not stated Not stated WEAR & CORR Contacts pitting or

and Inverters IIII_ Icorrosion

27 Cable Insulation Not stated Not stated ELETEMP, RAD, &

MOIST-EL

Loss of dielectric

properties &

changes in structure
Table A.2 Gall Report for NPAR Reports Page

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

2B

Effect of Aaina on Cornoonent Function Contrib to Failure Reported Droas Rel.proas ReDort Recommendations Pace No. Item Item

Fails open due to equipment load cycling Occasional Not discussed in Vendor specific Not stated 4-18 4

report program, Tech.

Spec. surveil.

Fails open due to heat generated by Rare Not discussed in Vendor specific Not stated 4-18 5

surrounding components. report program, Tech.

Spec. surveil.

Contacts open - loss of continuity across Rare Not discussed in Tech. Spec. Not stated 4-18 6

contacts report surveillance

Open circuit of coil - loss of continuity Rare Not discussed in Vendor specific Not stated 4-18 7

through coil wires, report program

Loss of capacitance and degraded Occasional Not discussed in Vendor specific Not stated 4-18 8

system operation. report program

Open circuit Rare Not discussed in Vendor specific Not stated 4-18 9

report program

Loss of capacitance Occasional Not discussed in Vendor specific Not stated 4-18 10

report program

Open circuit Rare Not discussed in Vendor specific Not stated 4-18 11

report progam

Short circuit - turn to turn or to ground Occasional Not discussed in Vendor specific Not stated 4-19 12

report program

Short circuit - turn to turn or to ground Occasional Not discussed in Vendor specific Not stated 4-19 13

report program

Short circuit - turn to turn or to ground Occasional Not discussed in Vendor specific Not stated 4-19 14

report program

Change in inductance Rare Not discussed in Vendor specific Not stated 4-19 15

report program

Short or open circuit Occasional Not discussed in Vendor specific Not stated 4-19 16

report program

Open circuit Rare Not discussed in Vendor specific Not stated 4-19 17

report program

Change in resistance value and degraded Rare Not discussed in Vendor specific Not stated 4-19 18

circuit operation. report program

Change in output Rare Not discussed in Vendor specific Not stated 4-19 19

report program

Open circuit at terminals or within printed Rare Not discussed in Vendor specific Not stated 4-19 20

circuit board. report program

Change in output Occasional Not discussed in Vendor specific Not stated 4-19 21

report program

Short circuit Rare Not discussed in Vendor specific Not stated 4-19 22

report program

Open or short circuit Occasional Not discussed in Vendor specific Not stated 4-19 23

report program

No response (stuck) Occasional Not discussed in Vendor specific Not stated 4-19 24

report program

No response from meter Rare Not discussed in Vendor specific Not stated 4-19 25

report program

Fails to open or close Occasional Not discussed in Vendor specific Not stated 4-19 26

report program

Cracks when flexed & loss of flexibility,

loss of imperviousness, failure frequently

coupled with presence of moisture or

water.

Rare Not discussed in

report

No specific

program

Not stated 3-33 27
Table A.2 Gall Report for NPAR Reports Page 3A

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L C. Meyer, INEL

Item SytmStucture/Comn Subcomoonent Materials Manufacturer ARD mechanism ARD effects

28 Cable Insulation Not stated Not stated ELETEMP, RAD, & Loss of dielectric

MOIST-EL properties &

changes in structure

29 Cable Insulation Not stated Not stated ELETEMP, RAD, & Loss of dielectric

MOIST-EL properties &

changes in structure

30 (Pressure Force Balance Type Force Bar & Linkage Not stated Not stated WEAR & VIB Wear of pivot points

Transmitters)

31 (Pressure Force Balance Type Force Motor Not stated Not stated VOLSTR ELETEMP Insulation failure &

Transmitters) (Feedback Coil) coil burnout

32 (Pressure Force Balance Type Amplifier Not stated Not stated THER-CY & Shorting or opening

Transmitters) VOLSTR of electronic

components

33 (Pressure Force Balance Type Housing Seals Not stated Not stated ELETEMP, RAD, Compresive set or

Transmitters) OR EMBR cracking

34 (Pressure Force Balance Type Diaphragm Not stated Not stated CORR Perforation of

Transmitters) diaphragm from

corrosion

35 (Pressure Force Balance Type Diaphragm Seal Not stated Not stated Not stated Seal deterioration

Transmitters) from decomposition

36 (Pressure Capicitance Type Sensing Cell Not stated Not stated Not stated Perforation in cell

Transmitters) Transmitters allowing leakage of

fluid

37 (Pressure Capicitance Type Terminal Cover Plate Not stated Not stated EMBR, ELETEMP, Embrittiement and

Transmitters) Transmitters Seal & RAD seal cracking

38 (Pressure Capicitance Type Electronics Not stated Not stated OXIDAT & Circuit continuity lost

Transmitters) Transmitters CONTAM and bridging of

circuits

39 (Pressure Capicitance Type Electronics Not stated Not stated VOLSTR & Shorting or opening

Transmitters) Transmitters ELETEMP of component

40 (Pressure Capicitance Type Sensing Cell Not stated Not stated ELETEMP OR RAD Chemical changes in

Transmitters) Transmitters fill-oil

41(Pressure

Transmitters)

Capicitance Type

Transmitters

Electronics Not stated Not stated RAD, ELETEMP,

OR VOLSTR

Change in

component

parameters
Table A.2 Gall Report for NPAR Reports Page 3B

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Cracks when flexed & loss of flexibility, Rare Not discussed in No specific Not stated 3-34 28

loss of imperviousness, failure frequently report program

coupled with presence of moisture or

water. I

Cracks when flexed & loss of flexibility, Rare Not discussed in No specific Not stated 3-34 29

loss of imperviousness, failure frequently report program

coupled with presence of moisture or

water. Adverse changes in insulation

resistance may cause attenuation of

signals.

Failure to operate - decrased accuracy or Occasional Not discussed in RG 1.118, Not stated 4-43 30

complete failure. Zero shift may result report IEEE 338-

from bent components causing 1987, ISA

transmitter failure to operate as required. 67.06, Tech

SpecI

Failure to operate - loss of output Rare Not discussed in RG 1.118, Not stated 4-43 31

report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate - may fail high, low, lose Occasional Not discussed in RG 1.118, Not stated 4-43 32

accuracy, or fail with steady output. report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate - inability of seal to Occasional Not discussed in RG 1.118, Not stated 4-43 33

provide moisture and pressure barrier report IEEE 338-

results in failure of electronics due to 1987, ISA

shorting and corrosion from ingress of 67.06, Tech

environmental contaminants. Spec

Failure to operate as required - zero shift Occasional Not discussed in RG 1.118,1EEE Not stated 4-43 34

or leakage through diaphram causing report 338-1987,ISA

variable instrument drift as pressures 67.06,10 CFR across diapharam equalize 50.49

Failure to operate as required - leakage Occasional Not discussed in RG 1.118, Not stated 4-43 35

through diaphram causing variable report IEEE 338-

instrument drift as pressures across 1987, ISA

diapharam equalize 67.06, Tech

Spec

Failure to operate or loss of accuracy or Rare Not discussed in RG 1.118, Not stated 4-44 36

drift report IEEE 338-

1987, ISA

67.06, Bul 90-

01

Failure to operate - inability to provide Rare Not discussed in RG 1.118,1EEE Not stated 4-44 37

moisture and pressure boundary resulting report 338-1987,ISA

in loss of electronics due to ingress of 67.06,10 CFR

environmental contaminants 50.49

Failure to operate or loss of signal or Occasional Not discussed in RG 1.118, Not stated 4-44 38

sporadic operation report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate - loss of output, may fail Occasional Not discussed in RG 1.118, Not stated 4-44 39

high or low. report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate as required such as Rare Not discussed in RG 1.118, Not stated 4-45 4E

zero shift, reduced accuracy, or changes report IEEE 338-

in response time. 1987, ISA

67.06, IN 95-20

F-ailure to operate as required - loss of

accuracy, drift, or zero shift.

Occasional Not discussed in

report

RG 1.118,

IEEE 338-

1987, ISA

67.06, Tech

Spec

Not stated 4-45 41
Table A.2 Gall Report for NPAR Reports Page 4A

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

42 (Pressure Strain Gage Type Strain Gage Not stated Not stated Not stated Loss of continuity in

Transmitters) bridge circuit related

to aging

43 (Pressure Strain Gage Type Seals Not stated Not stated CONTAM, EM BR, Embrittlenent or

Transmitters) ELETEMP, OR cracking

RAD

44 (Pressure Strain Gage Type Potentiometer Not stated Not stated CORR & ELETEMP Corrodes open due

Transmitters) to thermal stress

45 (Pressure Strain Gage Type Electric Module Not stated Not stated Not stated Component

Transmitters) deterioration or

change in

parameters

46 (Pressure Strain Gage Type Bourdon Tube Not stated Not stated CORR Perforation of tube

Transmitters) allowing leaks to

transmitter housing

Document: NISTIR 4485, Annotated Bibliography - Diagnostic Methods and Measurement Approached to Detect Incipient Defects Due to Aging of Cables

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

[1 Cable Not stated Not stated Not stated Not stated Not stated

Document: NISTIR 4487, Detection of incipient Defects in Cables by Partial Discharge Signal Analysis

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1Cable Insulation Not stated Not stated MOIST-EL, Defects develop

IOXIDAT, from these

_________ ______________________ _________JELETEMP, & RAD mechanisms

Document: NISTIR 4787, The Use of Time-Domain Dielectric Spectroscopy to Evaluate the Lifetime.of Nuclear Power Station Cables

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electrical Cable Jacket Vinyl Not stated Not stated Not stated

2 Electrical Cable Insulation PE, XLPE, XLPO Not stated ELETEMP & RAD Chemical reactions,

crosslinking,

ionization

3 Electrical Cable Insulation PE, XLPE, XLPO Not stated ELETEMP Chemical reactions,

COMBINED WITH crosslinking,

RAD ionization

Document: NUREG-1377 R3, NRC Research Program on Plant Aging: Listing and Summaries of Reports Issued Through July 1992

Reviewed by: Jerry Edson, INEL

Itemr System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Listing and NOT

Summaries of 123 SPECIFICALLY

NPAR Reports ADDRESSED IN

_ _PAR__Rp__t_ _ THE REPORT
Table A.2 Gall Report for NPAR Reports Page 4B

Document: Letter Report/INEL, Summaries of Research Reports Submitted in Connection With the Nuclear Aging RESEARCH (NPAR) PROGRAM

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure to operate - loss of output. Rare Not discussed in RG 1.118, Not stated 4-45 42

report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate - inability to provide Occasional Not discussed in RG 1.118,1EEE Not stated 4-45 43

moisture and pressure barrier leading to report 338-1987,ISA

failure of electronics due to contamination. 67.06,10 CFR

50.49

Failure to operate - fails over range, wire- Occasional Not discussed in RG 1.118, Not stated 4-45 44

wound potentiometer corrosion of resistive report IEEE 338-

elements leads to failure 1987, ISA

67.06, Tech

Spec I

Failure to operate or loss of full output Occasional Not discussed in RG 1.118, Not stated 4-45 45

report IEEE 338-

1987, ISA

67.06, Tech

Spec

Failure to operate as required - drift, Rare Not discussed in RG 1.118, Not stated 4-45 46

contamination of transmitter intemals, and report IEEE 338-

failure to respond 1987, ISA

67.06, Tech

Spec

Document: NISTIR 4485, Annotated Bibliography - Diagnostic Methods and Measurement Approached to Detect Incipient Defects Due to Aging of Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations... Page No. Item

This is a collection of 156 reveiwed Not stated Not discussed in No specific Not stated NA 1

abstracts of reports and papers related to report program

cable aging and defect assessment

covering the 1970-1986 period. An

additional list of 850 citations was

compiled from references given in the

reveiwed papers.

Document: NISTIR 4487, Detection of Incipient Defects in Cables by Partial Discharge Signal Analysis

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

The defects will degrade insulating lOccasional Not discussed in No specific Ihardware Six recommendations 

development 

each 

Three for for 1 and 1201 1

Isoftware. [4]

Document: NISTIR 4787, The Use of Time-Domain Dielectric Spectroscopy to Evaluate the Lifetime of Nuclear Power Station Cables

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in No specific Not stated 15 I

report program I

Embrittlement, softening, loss of Not stated Not discussed in No specific Not stated 1, 2, 4, 7, 2

elongation and reduced dielectric strength report program 8, 15,17,

could cause failure to accurately transmit 22-38

voltage or current.

Embrittlement, softening, loss of Not stated Not discussed in No specific Not stated 1, 2, 4, 7, 3

elongation and reduced dielectric strength report program 8,15, 17,

could cause failure to accurately transmit 22-38

voltage or current.

Document: NUREG-1377 R3, NRC Research Program on Plant Aging: Usting and Summaries of Reports Issued Through July 1992

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The purpose of the report is to present a Not discussed in the No specific Not stated 1

listing and summaries of 123 NPAR I report program

reports. Specific aging effects and

recommendations are addressed by the

individual reports.
Table A.2 Gall Report for NPAR Reports Page SA

Document: NUREG/CP-0100, Proceedings of the Intemational Nuclear Aging Symposium, Session 3

Reviewed by: L. C. Meyer, INEL

Item Svstem StructurelComD SubCOmDonent Materials Manufacturer ARD mechanism ARD effects

17 Resistance Not stated Not stated THERM-CY Conductive

Temperature compounds become

Devices insulative

18 Electrical Wiring Insulation Kapton (Aeromatic Not stated MOIST-EL & ELE- Insulation cracking

polymide) TEMP and loss of

mechanical

properties

19 Pressure Force Balance Type Not stated Foxboro CONTAM & FRZ- Blockage of sensing

Transducers Sensors THAW lines

20 Pressure Not stated Not stated Rosemount CONTAM & FRZ- Blockage of sensing

Transducers THAW lines

21 Micro Processor & IC DIE Silicon, Silicon oxide Not stated CONTAM, Contamination

ICs & interfaces VOTSTR, CURSTR causes shorts, V & I

stresses cause

burnout

22 Micro Processor & IC DIE Metalization Not stated CORR Corrosion from

ICs adjacent materials

23 Micro Processor & IC Package Metalic leads & Not stated FAT, CORR, VIB, & Corr from adjacent

ICs container and glass CONTAM materials, vib causes

seals fat, contain shorts

24 Diesel Generator Not stated Not stated Not stated Not stated WEAR & LOSLUB Wear from lack of

lubrication during

fast starts

25 Cable Insulation EPR, CSPE, & Four vendors listed RAD, ELETEMP, & Insulation

XLPE MOIST-EL degradation from all

three mechanisms

Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

14 Auxiliary Feedwater Not stated Not stated Not stated Not stated

System

15 Auxiliary Feedwater Cable Various cable Seven vendors RAD AND Not stated

System materials Identified ELETEMP

16 Auxiliary Feedwater Steam Generator Tubes Not stated Westinghouse FAT, EROS, CORR Primary water stress

System corrosion cracking

(PWSCC)

17 Auxiliary Feedwater Circuit Breakers Not stated Not stated Not stated Not stated

System

18 Auxiliary Feedwater Turbine Driven Not stated Not stated Not stated Not stated

System Pump

19 Auxiliary Feedwater Compressors Not stated Not stated WEAR, CONTAM, Set point drift,

System & VIB degraded parts, &

__loose connections

20 Auxiliary Feedwater Dryers Not stated Not stated CORR & CONTAM Blockage, deteration

_ System of components

21 Auxiliary F-eeawater

System

Valve Not stated Not stated WEAR, CONTAM,

AND CORR

Set point drift,

fracture/cracking,

component

deterioration
Table A.2 Gall Report for NPAR Reports Page 5B

Document: NUREG/CP-0100, Proceedings of the International Nuclear Aging Symposium, Session 3

Reviewed by: L. C. Meyer, INEL

Effect of Aaina on Component Function Contrib to Failure Reported Droas ReI.proas Report Recommendations Paae No. Item

Never-seez usd in thermal wells lose Not stated Reg Guides 1.118 Reg Guides Not stated 363-366 17

conductivity with age and effects and 1.105 1.118 and

response time of RTD. 1.105

Cracking can result in contamination Occasional Not discussed in No specific Not stated 130-131 18 lintrusion and improper output, report program

Partial or full blockage of sensing lines Not stated IEEE-Std 338, Reg IEEE 338, Reg Not stated 137-139 19

effects the transducer response time. Guide 1.118, & ISA Guide 1.118,

Std 67.06 ISA 67.06

Partial or full blockage of sensing lines Not stated IEEE-Std 338, Reg IEEE 338, Reg Not stated 138-139 20

effects the transducer response time. Guide 1.118, & ISA Guide 1.118,

Std 67.06 ISA 67.06

Contamination enters by cracks or from Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 21

MFG process and if moved by handling program emerge, their aging sensitivity should

can short gate elements, voltage and be addressed. [2]

current spikes may overstress leads or

connections weakened by manufacturing

process or chemical reactions of materials

used in IC.

Metalization may fail because of corrosion Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 22

from adjacent materials program emerge, their aging sensitivity should

be addressed. [2]

Vibration may crack glass seals allowing Not stated IEEE-323-1983 No specific As new vendors & technologies 146-152 23

contamination to enter case, corr from program emerge, their aging sensitivity should

moisture entering cracked seals or be addressed. [2]

adjacent materials, contamination left from

mfg process or entering through seal

cracks may cause component shorting.

Decreases reliable life of diesels Not stated Not discussed in IEEE 387-1984 Not stated 153-157 24

report Section 7.5,

IEEE 749-1983

The report is not an aging evaluation, but Not stated IEEE Std-74 & IEEE No specific Not stated 158-166 25

only describes long term tests to STD-383-1974 program

determine the amount of insulation

degratation from radiation, elevated

temperature, pwr atmospheres, and

inerted BWR atmospheres.

Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

This report develops an aging risk Not stated Not discussed in No specific Not stated 377-398 14

assesment methodology using the aPWR report program

AFW system to demonstrate method

This report covered loca testing of aged Not stated Not discussed in No specific Not stated 399-410 15

cables. Aging information provided in report program

other Sandia reports on cable aging_

PWSCC damages steam tubes at three Rare Not discussed in No specific Not stated 411-431 16

locations; roll transition regions, U-bends, report program

and tube dents. Leaks at these locations

can lead to shuting down the reactor.

This report covers NPAR phase 2 tasks Not stated NPAR No specific Not stated 433-437 17

related to resolving technical safety issues program

This report only provides an overview and Not stated Not discussed in No specific Comprehensive testing of 439-451 18

identifies the turbine driven pump as report program components and i&c. [2]

historically having the most failures with

the turbine i&c/governor control system

having half of these failures. Does not

have specific aging data.

Degraded operation or failure Occasional Not discussed in No specific Not stated 453-471 19

report program

Fallure or degraded operation Occasional Not discussed in No specific Not stated 453-471 20

_ _ _ IIreport program II

Fallure to operate, failure to open or

close, or degraded operation

Occasional Not discussed in

report

No specific

program

Not stated 453-471 21
Table A.2 Gall Report for NPAR Reports Page 6A

Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)

Reviewed by: L. C. Meyer, INEL

Itemn Sv~tem StructurnIComn Subcomnonent Materials Mnnufac~turer ARD) m~hanikm ARD effects

22 Auxiliary Feedwater Diesel Generator Not stated Not stated Not stated Not stated

System

23 Auxiliary Feedwater Circuit Breakers Not stated Not stated Not stated Not stated Not stated

System

24 Auxiliary Feedwater Not stated Not stated Not stated Not stated Not stated Not stated

System

25 Auxiliary Feedwater Not stated Not stated Not stated Not stated Not stated Not stated

System

Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Pressurizer Heater Cable Conductor NO. 6 AWG, single Okonite CORR Increased loop

Feeder Circuit copper conductor resistance

2 Pressurizer Heater Cable Insulation 1/16 IN. thick oil Okonite Not stated Low insulation

Feeder Circuit base resistance

3 Pressurizer Heater Cable Jacket 1/32-IN. black Okonite Not stated Not stated

Feeder Circuit neoprene

4 Pressurizer Heater Cable Conductor NO. 10 AWG Not stated CORR Not stated

Main Feeder Circuit Copper

5 Pressurizer Heater Cable Insulation Silicon rubber with Not stated OXIDAT Degraded insulation

Main Feeder Circuit glass braid resistance

6 Pressurizer Heater Cable Jacket Silicon rubber Not stated Not stated Not stated

Main Feeder Circuit

7 Instrumentation and Heater, MOV, and Stop Joint, Splices, Not stated Not stated MOIST-EL AND Loss of material, and

Control RTD Circuits and Terminals CORR corrosion product

buildup

8 Rod Control Position Cable 33 Conductor, NO. Copper Okonite Not stated Not stated

Indicator Cables 16 AWG, Stranded

Wire

9 Rod Control Position Cable Insulation Oil base insulation Okonite Not stated Not stated

Indicator Cables

10 Rod Control Position Cable Jacket Neoprene Okonite Not stated Not stated

Indicator Cables

11 Resistance Cable Insulation NO. 18 AWG, tinned Not stated Not stated Not stated

Temperature copper stranded.

Detector Circuits spiral wrapped and

shielded with a

chrome vinyl jacket

12 Resistance RTDs Sensing Element Platinum Leeds and Northrup Not stated Not stated

Temperature

1 Detector Circuits

13 Resistance Terminals and Stop Not stated Not stated Not stated CORR AND Increase in

Temperature Joints MOIST-EL resistance, open

Detector Circuits circuit, and film on

terminals

14 Nuclear RG-149U Cables Insulation NO. 18 AWG Not stated Not stated Not stated

Instrumentation copper center

conductor and

polyethylene

insulation

15 Motor Operated Limit Switches Contacts Not stated Not stated CORR Material buildup on

Valves contacts

16 Motor Operated Cable Not stated Not stated Not stated Not stated Not stated

Valves

17 Motor Operated

Valves

Motor Not stated Not stated Not stated Not stated Not stated
Table A.2 Gall Report for NPAR Reports Page 6B

Document: NUREG/CP-0105, Seventeenth Water Reactor Safety Information Meeting (Electrical Parts)

Reviewed by: L. C. Meyer, INEL Effect of Aaina on Comoonent Function Contrib to Failure Reported nroas ReI.nroas Report Recommendations Paa e No. Item .......... of ... ..... to Failure -- r ..... r .e..r" a . ... r_ ..................... Pag... t Failure to start Occasional Not discussed in IEEE 387-1984 Not stated 473-495 22

report Section 7.5,

IEEE 749-1983

Failure to transfer Occasional Not discussed in IEEE 741-1986 Not stated 473-495 23

report Section 7

This report only covers the use of N PAR Not stated Not discussed in N/A Not stated 497-407 24

results in inspection activities. Aging report

summaries are covered in other npar

reports

This report covers a methodology for Not stated Not discussed in N/A Not stated 509-529 25

managing aging in nuclear power plants report I I I_ J

Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The effect was a small decrease in Rare Plant specific No specific Keep moisture out [2] 5, 6, & 7 1

available wattage to heaters maintenance program

Degraded heater oeration, one circuit Rare Plant specific No specific Keep moisture out of cables [2] 5, 6, 7, & 2

failed because of low insulation resistance maintenance program 21

Not stated Rare Not discussed in No specific Not stated 6 3

report program

Marginal operation Rare Not discussed in No specific Not stated 6 4

report program

Marginal operation of heaters Rare Not discussed in No specific Not stated 6 5

report program

Not stated Rare Not discussed in No specific Not stated 6 6

report program

Nonenvironmentaly sealed splices and Occasional Not discussed in No specific Periodic plant maintenance to clean 7 and 21 7

terminals presents vulnerable areas for report program terminals and check seals and to

oxidation, corrosion, dust, and moisture use ECCAD to check circuits before

contamination to set in. failure [2]

None Rare Not discussed in No specific Not stated 7, 8, and 8

report program 21

None Rare Not discussed in No specific Not stated 7, 8, and 9

report program 21

None Rare Not discussed in No specific Not stated 7, 8, and 10

report program 21

None Rare Not discussed in No specific Not stated 7, 8, and 11

report program 21

One circuit shorted to ground at the Rare Not discussed in ANSI/IEEE Not stated 8, 9, and 12

instrument end report 338-1987 21

Circuits had higher than expected loop Occasional Not discussed in No specific Not stated 9, 10, and 13

resistance, four circuits had a series report program 21

resistance occuring at the stop joints,

resistance problem also observed at

termination points in the control room, one

circuit was shorted to ground at the

instrument end

None Rare Not discussed in ANSI N42.4- Not stated 12. 13, 14

report 1971 and 21

Insulation resistance exceeded the Rare Not discussed in Vendor Not stated 12, 20, 15

standard recommended minimum, report specific, GL and 21

although not serious enough to alter the 89-10,

intended limit switch function NUREG-1352

None Rare Not discussed in No specific Not stated 12, 20, 16

report program _ and 21 1

None except two movs lOcated outside,

axposed to weather were inoperable.

Rare Not discussed in

report

Vendor

specific, GL

89-10,

NUREG-1352

Not stated 12,20,

and 21

17
Table A.2 Gall Report for NPAR Reports Page 7A

Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits

Reviewed by: L. C. Meyer, INEL

Item System Structure/ComD Subcomoonent Materials Manufacturer ARD mechanism ARD effects

1181 Valves1111 Motor Operated Not stated Not stated ttated Not stated WEATH Not stated

Document: NUREG/CR-4156, Operating Experience and Aging-Seismic Assessment of Electric Motors

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 3 Phase Induction & Stator - Conductors Copper Not stated VIB, THERM, AND Loosening of

Synchronous Motors and Structural SHRINK laminations and

Components locking devices

2 3 Phase Induction & Stator - Insulation Mica, glass, resins, Not stated THERM, OXIDAT, Degraded dielectric

Synchronous Motors enamels, mylars, MOIST-EL, AND properties & tensile

tiger, varnish, and RAD strength, brittle

nonhygroscopic

materials

3 3 Phase Induction & Rotor - Contuctors Copper Not stated VIB & THERM Rotor embalance,

Synchronous Motors and Structural loose parts, and

Components overheating

4 3 Phase Induction & Rotor - Insulating Mica, glass, resins, Not stated CURSTR, THERM, Insulation damage,

Synchronous Motors Materials enamels, mylars, RAD, AND MOIST- winding short,

fiber, varnish, and EL overheating of rotor

nonhygroscopic coils

marteials

5 3 Phase Induction & Rotor - Commutator Mica, copper, Not stated WEAR, FAT, DIRT, Brush wearout,

Synchronous Motors and Brushes carbon, and steel in CONTAM, AND relaxed spring, oil

spring mechanism OXIDAT deposits, & loose

contact

6 3 Phase Induction & Bearings Steel, brass, and Not stated VIB, THERM, Material attrition,

Synchronous Motors bronze WEAR, cracking of bearings

CONTAMIN, AND scoring of surface

LOSLUBE

7 3 Phase Induction & Bolts, Ranges, and Steel, cast iron, Not stated VIB, CORR, FAT, Sheared bolts,

Synchronous Motors Housing brass, and copper THERM, AND cracked flanges or

MECHSTR housing, overheated

frame

8 3 Phase Induction & Seals and Gaskets Polymers Not stated THERM, VIB, AND Cracking, shrinking,

Synchronous Motors RAD leaking of oil or

water, embrittlement

9 3 Phase Induction & MOV's Break Coils Copper Not stated THERM, CORR, Corrosion product

Synchronous Motors CURSTR buildup, current

overload, &

misoperation

10 3 Phase Induction & Conduit Box, Leads, Copper Not stated VIB AND CORR, Leak, poor electrical

Synchronous Motors and Connections CONTAM, MOIST- contact, loose leads,

EL improper seals

11 3 Phase Induction & Motor See sub- Not stated WEAR, THERM, Misaligned parts,

Synchronous Motors components VIB, CURSTR, burned out motor, &

RAD, FAT, AND disengaged motor

MOIST-EL I _I

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant,,

Reviewed by: Jerry Edson, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Not stated 

WEAR Not stated 

ElM, Umitorque, 1 Motor Operated

Valve

Gearbox- Gears Not stated ERM, Limitorque, Rotork

WEAR INot stated
Table A.2 Gall Report for NPAR Reports Page 7B

Document: NUREG/CR-3956, In Situ Testing of the Shippingport Atomic Power Station Electrical Circuits

Reviewed by: L. C. Meyer, INEL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Inoperable 11report 7Rare Not discussed in IIIand N/A Not stated 12,20, 21 181

Document: NUREG/CR-4156, Operating Experience and Aging-Seismic Assessment of Electric Motors

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs !. . Report Recommendations Page No. Item

Not stated Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, S-2, 2-15,

report Section 14 operational readiness acceptance and 4-23

criteria, in-situ testing and monitoring

_programs [2] 1

Degraded operation or failure to function Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, S-2, 2-15, 2

report Section 14 operational readiness acceptance & 4-23

criteria, in-situ testing and monitoring

programs [2]

Frame distortion, shift in rotor center of Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, S-2, 2-20, 3

gravity, insuficient cooling, winding short report Section 14 operational readiness acceptance 4-23

short or overheating of rotor coils leading criteria, in-situ testing and monitoring

to burnt motor and failure to function, programs [2]

Excess current due to aging from many Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15, S-2, 4

starts, cage winding failure due to jogging, report Section 14 operational readiness acceptance 4-24

over heating of rotor coils leading to burnt criteria, in-situ testing and monitoring

motor, winding shorts, insulation programs [2]

shrinkage results in decreased output or

failure to function.

Loose brush connection, dirt & foreign Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-22, S-2, 5

particles, wear out of carbon brushes, report Section 14 operational readiness acceptance 4-25

relaxed spring load in the brush holder criteria, in-situ testing and monitoring

mechanisms, dirt/moisture on programs [2]

commutator and oxidation effects results

in decreased output or failure to function.

Seized bearings, and overheating, Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15, 4- 6

excessive vibration could cause fracture report Section 14 operational readiness acceptance 22, 4-23,

and bearing scoring, corrosion due to criteria, in-situ testing and monitoring 4-25, 4-

exposure to air. programs [2] 26, and 4-

27

Failure to function or degraded operation OCCCASIONAL Not discussed in IEEE 334-1974 Preventive maintenance programms, 2-15, 4- 7

report Section 14 operational readiness acceptance 24, 4-25,

criteria, in-situ testing and monitoring 4-25, 4-

programs [2] 27, and 4-

28

Decreased output or failure to function. Occasional Not discussed in IEEE 334-1974 Preventive maintenance programms, 5-15 & 4- 8

report Section 14 operational readiness acceptance 28

criteria, in-situ testing and monitoring

programs [2]

Burning of motor windings, jamming of Rare Not discussed in Vendor Preventive maintenance programms, 5-15 & 4- 9

break coil, overload the motor drawing report specific, GL operational readiness acceptance 28

large currents into the windings results in 89-10, criteria, in-situ testing and monitoring

failure to operate. NUREG-1352 programs [2]

Degraded insulation, shorts, or open Occasional Not discussed in No specific Preventive maintenance programms, 4-28 10

circuits result in decreased output or report program operational readiness acceptance

failure to function. criteria, in-situ testing and monitoring

programs [2]

Burned or dead motor, disengaged motor, Rare Not discussed in IEEE 334-1974 Preventive maintenance programms, 4-29 11

& overcurrent results in decreased output report Section 14 operational readiness acceptance

or failure to function. criteria, in-situ testing and monitoring

I_ programs [2]

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant.

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure to open or close, failure to operate

as required

Not stated Not discussed in

report

Vendor

specific, GL

89-10,

NUREG-1352

Accurate and consistent mov testing

should be performed. Good records

should be maintained [4]

5-12,15,

72,167

1
Table A.2 Gall Report for NPAR Reports Page 8A

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant

Reviewed by: Jerry Edson, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

2 Motor Operated Gearbox -Fasteners Not stated ElM, Limitorque, Not stated Fastener loosening

Valve Rotork

Motor Operated Gearbox - Stem Nut Not stated ElM, Limitorque, WEAR Not stated

Valve Rotork

4 Motor Operated Gearbox - Drive Not stated ElM, Umitorque, WEAR Not stated

Valve Sleeve Rotork

5 Motor Operated Gearbox - Bearings Not stated ElM, Limitorque, WEAR Not stated

Valve Rotork

Motor Operated Gearbox - Lubencani Not stated ElM, Umitorque, Not stated Hardening

Valve Rotork

7 Motor Operated Gearbox - Shaft Not stated ElM, Limitorque, WEAR, MECHSTR Tapering of the shafl

Valve Rotork

8 Motor Operated Gearbox - Clutch Not stated ElM, Limitorque, WEAR Not stated

Valve Rotork

9 Motor Operated Gearbox - Spring Not stated ElM, Limitorque, Not stated Response change

Valve Pack and Torque Rotork

Switch

10 Motor Operated Gearbox - Stem Not stated ElM, Limitorque, Not stated Loosening

Valve Lock Nut Rotork

11 Motor Operated Gearbox - Seal Not stated ElM, Limitorque, WEAR Deterioration

Valve Rotork

12 Motor Operated Motor Not stated ElM, ULmitorque, CORR, WEAR Not stated

Valve Rotork

13 Motor Operated Motor Not stated ElM, Limitorque, ELETEMP Break down of

Valve Rotork insulation

14 Motor Operated Switches - Contacts Not stated ElM, Umitorque, CORR, CORR/PIT Not stated

Valve Rotork

15 Motor Operated Switches - Insulation Not stated ElM, LUmitorque, ELETEMP Insulation

Valve Rotork breakdown

16 Motor Operated Switches - Grease Not stated ElM, Umitorque, Not stated Hamening

Valve Rotork

17 Motor Operated Switches - Gear and Not stated ElM, Limitorque, WEAR Not stated

Valve Cam Rotork

18 Motor Operated

Valve

Switches - Fastener Not stated ElM, Umitorque,

Rotork

Not stated Loosening
Table A.2 Gall Report for NPAR Reports Page 8B

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant,

Reviewed by: Jerry Edson, INEL F~ff~t nf Aani~n ,n (•nmnnn~nt I,,~tinn tin nfrih trn FI=hir• RIwr-ld . nrnns . .. ReInronns L Report -- Recommendations -- Pae No. Item_______

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 2

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 3

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 4

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 5

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352 I

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 6

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 7

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 8

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352 I

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 9

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4] NUREG-1352

Failure to open or close, failure to operate Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 10

as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Leakage of lubricant out from gearbox or Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 11

leakage of contaminants into the gear box report specific, GL should be performed. Good records 72, 167

resulting in failure to open or close or 89-10, should be maintained [4]

failure to operate as required NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 12

operate as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 13

operate as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12,15, 14

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12,15, 15

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12,15, 16

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12,15, 17

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

INUREG-1352

Failure to open or close or aiure to

operate as required

Not stated Not discussed in

report

Vendor

specific, GL

89-10,

NUREG-1352

Accurate and consistent mov testing

should be performed. Good records

should be maintained [4]

5-12,15,

72, 167

18
Table A.2 Gall Report for NPAR Reports Page 9A

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plani

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 Motor Operated Valves - Operator Not stated Anchor Darling, WEAR, CORR Not stated

Valve Velan, ET

20 Motor Operated Valves - Yoke Not stated Anchor Darling, WEAR Not stated

Valve Bushing Velan, ET

21 Motor Operated Valves - Valve Stem Not stated Anchor Darling, WEAR, MECHSTR Tapering of the shaft

Valve Velan, ET

22 Motor Operated Valves - Fasteners Not stated Anchor Darling, Not stated Loosening

Valve Velan, ET

23 Motor Operated Valves - Valve Seat Not stated Anchor Darling, WEAR, CORR Not stated

Valve Velan, ET

24 Motor Operated Valves - Bonnet Seal Not stated Anchor Darling, Not stated Deterioration

Valve Velan, ET

25 Motor Operated Valves - Stem Not stated Anchor Darling, Not stated Deterioration

Valve Packing Velan, ET

Document: NUREG/CR-4257, Inspection, Surveillance, and Monitoring of Electrical Equipment Inside Containment of Nuclear Power Plants - With Applications to I

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Cable 600 V, 4 kV, and 13 Cross-linked Not stated THERM, RAD, Chemical changes,

kV Power Cable polyethylene (XLPE) CHEM, AND dielectric

Insulation MOIST-EL degradation, &

cracks

2 Cable 600 V, 4 kV, and 13 Ethylene propylene Not stated THERM, RAD, Chemical changes,

kV Power Cable CHEM, AND dielectric

Insulation MOIST-EL degradation, &

cracks

3 Cable 600 V, 4 kV, and 13 Polyvinyl chloride Not stated THERM, RAD, Radiation

kV Power Cable (PVC) CHEM, AND deterioration,

Insulation MOIST-EL dielectric

degradation, &

cracks

4 Cable Cable Sheathing and Chlorosulfonated Not stated THERM, RAD, & Radiation

Jacket polyethylene (CSP) CHEM. deterioration,

and Kapton dielectric

degradation, &

cracks

5 Cable Control Cable Cross-linked Not stated THERM, RAD, & Radiation

polyethylene (XLPE) CHEM. deterioration,

dielectric

degradation, &

cracks

6 Cable Coaxial Cable Cross-linked Not stated THERM, RAD, & Radiation

polyethylene (XLPE) CHEM. deterioration,

dielectric

degradation, &

cracks

7 Cable Mineral Insulation Not stated Not stated RAD & VI B Wear

Metal Jacket Cable I __
Table A.2 Gall Report for NPAR Reports Page 9B

Document: NUREG/CR-4234 V2, Aging and Service Wear of Electric Motor-Operated Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plant!

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12, 15, 19

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12,15, 20

operate as required report specific, GL should be performed. Good records 72, 167

89-10, should be maintained [4]

_NUREG-1352 I

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12,15, 21

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12, 15, 22

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Failure to open or close or failure to Not stated Not discussed in Vendor Accurate and consistent mov testing 5 - 12, 15, 23

operate as required report specific, GL should be performed. Good records 72,167

89-10, should be maintained (4]

NUREG-1352

Leakage Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12,15, 24

report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Leakage Not stated Not discussed in Vendor Accurate and consistent mov testing 5- 12,15, 25

report specific, GL should be performed. Good records 72,167

89-10, should be maintained [4]

NUREG-1352

Document: NUREG/CR-4257, Inspection, Surveillance, and Monitoring of Electrical Equipment Inside Containment of Nuclear Power Plants - With Applications to I

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Chemical changes in polymer resulting Rare Not discussed in No specific Testing to be based on safety 26,38, 40, 1

from aging, loss of dielectric generally report program importance, determine root cause of & 53

occurs after deterioration of mechanical failures, remove samples after 5 to

properties, treeing may cause rapid 10 years for tests [4]

breakdown of dielectric capabilities, loss

of flexibility, can't withstand voltage stress

Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26,38, 40, 2

deterioration of mechanical properties, report program importance, determine root cause of & 53

treeing may cause rapid breakdown of failures, remove samples after 5 to

dielectric capabilities. loss of flexibility, 10 years for tests [4]

can't with stand voltage stress

Subject to deterioration from radiation, Rare Not discussed in No specific Testing to be based on safety 26,38, 40, 3

loss of dielectric generally occurs after report program importance, determine root cause of & 53

deterioration of mechanical properties. failures, remove samples after 5 to

10 years for tests [4]

Major failure modes for sheathing are loss Rare Not discussed in No specific Testing to be based on safety 26,38, 40, 4

of flexibility and imperviousness, teflon report program importance, kapton not & 53

glue fails at low radiaton doses resulting recommended for applications

in inability to protect conductor insulation. subject to radiation doses > 0.01

mrad [4]

Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26, 39, 5

deterioration of mechanical properties, report program importance, determine root cause of 40, & 53

loss of flexibility, loss of imperviousness, failures, remove samples after 5 to

aging similar to power cable. Results in 10 years for tests [4]

failure to properly transmit voltage or

current.

Loss of dielectric generally occurs after Rare Not discussed in No specific Testing to be based on safety 26, 39, 6

deterioration of mechanical properties, report program importance, determine root cause of 40, & 53

loss of flexibility, loss of imperviousness, failures, remove samples after 5 to

aging similar to power cable. Results in 10 years for tests [4]

failure to properly transmit voltage or

current_

Conductor wear through insulation due to Rare Not discussed in No specific Testing to be based on safety 26, 30, 7

bending or vibration. Results in ffailure to report program importance, determine root cause of

ransmit voltage or current. _failures. I [4]
Table A.2 Gall Report for NPAR Reports Page 10OA

Document: NUREG/CR-4257 V2, Inspection, Surveillance, and Monitoring of Electrical Equipment in Nuclear Power Plants - Pressure Transmitters

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Force Balance Type Force Balance Bar & 316 stainless steel The Foxboro VIB AND WEAR Wear, failure to

Transmitter Unkage Company operate, bending

component, zero

shift

2 Force Balance Type Feedback Coil Copper The Foxboro THERM, Burnout

Transmitter Company

31 Force Balance Type Amplifier Carbon resistors, The Foxboro THERM, RAD, Degradation of

Transmitter transistors, OP Company VOLSTR insulation, insulation

amps, capacitors & breakdown, & cracks

diodes

4 Force Balance Type Housing Seals Viton The Foxboro THERM, RAD, & Embrittiement,

Transmitter Company CONTAM cracking, and

inability to seal

5 Force Balance Type Diaphragm Capsule 316 stainless steel The Foxboro CORR Leakage or

Transmitter Company perforation

6 Force Balance Type Diaphragm Seal 316 stainless steel The Foxboro THERM OR RAD Inability to maintain

Transmitter Company pressure barrier,

_ _variable instrument

7 Capacitance Type Sensing Cell 316 stainless steel Rosemount THERM AND RAD Leakage, rupture, oil

Transmitter breakdown, or

perforation

8 Capacitance Type Terminal Cover Seal Ethylene propylene Rosemount THERM AND RAD Embrittiement and

Transmitter cracking

9 Capacitance Type Electronics Cover Ethylene propylene Rosemount THERM AND RAD Embrittlement and

Transmitter Seal cracking

10 Capacitance Type Electronics Parts - Not stated Rosemount OXIDAT, THERM, Degradation of

Transmitter Misc Small AND VOLSTR insulation, arcing,

Components shorts and open

circuits

11 Strain Gage Type Strain Gage Resistive material ITT Barton VIB Loss of continuity or

Instruments open resistor

12 Strain Gage Type Housing Seal Ethylene propylene ITT Barton THERM AND RAD Embrittlement or

Instruments cracking

13 Strain Gage Type Potentiometer Phenolic body, nylon ITT Barton CORR AND Corrosion material

rotor, and slider Instruments THERM buildup lubricant

loss

14 Strain Gage Type Electric Module Carbon resistor, ITT Barton VIB, THERM, OR Component

transistors, Instruments RAD deterioration or

operational amplifier, change in

capacitors, and component

diodes parameters.

15 Strain Gage Type Bourdon Tube Haynes alloy NO 25 ITT Barton CORR Contamination build

Instruments up and material loss.
Table A.2 Gall Report for NPAR Reports Page 10B

Document: NUREG/CR-4257 V2, Inspection, Surveillance, and Monitoring of Electrical Equipment in Nuclear Power Plants - Pressure Transmitters

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.prosgs Report Recommendations Page No. Item

Wear of pivot points, decreased accuracy, Rare Not discussed in IEEE 338-1987 Not stated 9, 18 & 21 1

complete failure, zero shift, bending of report

components in level system,

Loss of output Rare Not discussed in IEEE 338-1987 Not stated 9, 18 & 21 2

report

Shorting or opening of electronic Occasional Not discussed in IEEE 338-1987 Not stated 9, 18 & 21 3

components, loss of accuracy, drift, zero report

shift, loss of signal, may fail high or low,

lose accuracy, or fail with steady output.

Inability of seal to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,18 & 21 4

pressure barrier, ingress of environmental report

contaminants, and loss of pressure

barrier results in transmitter drift or failure

to respond.

Perforation of diaphragm from corrosion Rare Not discussed in IEEE 338-1987 Not stated 9, 18 & 21 5

or flaw, variable instrument drift as report

pressures across diaphragm equalize,

and leakage through diaphragm,

permanent deformation of diaphragm, and

zero shift.

Variable instrument drift as pressures Rare Not discussed in IEEE 338-1987 Not stated 9, 18 & 21 6

across diaphragm equalize, and inablitity report

to maintain pressure barrier.

Leakage of cell fluid through diaphragm, Rare Not discussed in Enhanced Not stated 9,11, 19 7

loss of accuracy and drift, rupture allows report Surveillance - & 21

equalization of forces on diaphragm, GL 90-01

drastic change in sensing cell Suppl. 1

characteristics, oil breakdown due to

thermal or radiation stress.

Inability of sea] to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,11, 19 8

pressure boundary, cracking due to report & 21

thermal or radiation stresses, and loss of

electronics due to ingress of

environmental contaminants. Results in

transmitter drift or failure to respond.

Inability of seal to provide moisture and Occasional Not discussed in 10 CFR 50.49 Not stated 9,11,19 9

pressure boundary, cracking due to report & 21

thermal or radiation stresses, and loss of

electronics due to ingress of

environmental contaminants. Results in

transmitter drift or failure to respond.

Loss of signal, sporadic operation, Occasional Not discussed in IEEE 338-1987 Not stated 9,11,19 10

shorting or opening of components, report & 21

oxidation of contacts, bridging of circuits.

Loss of continuity in bridge circuit, loss of Occasional Not discussed in IEEE 338-1987 Not stated 6, 7, 20 & 11

output, loss of response to input pressure, report 22

and failure of instrument.

Inability to provide moisture and pressure Occasional Not discussed in 10 CFR 50.49 Not stated 6, 7,20 & 12

barrier, failure of electronics due to report 22

contamination. Results in instrument drift

or failure to respond.

Corrosion of resistive elements in Occasional Not discussed in IEEE 338-1987 Not stated 6, 7, 20 & 13

potentiometer, wirewound potentiometer report 22

corrodes open due to thermal stress and

corrosive lubricant, fails over range, and

loss of span adjustment.

Loss of full output, calibration shift, Occasional Not discussed in IEEE 338-1987 Not stated 6, 7,20 & 14

component parameters change. report 22

Permanent deformation of tube, zero shift, Occasional Not discussed in IEEE 338-1987 Not stated 6, 7, 20 & 15

leaks in bourdon tube to transmitter report 22

housing, perforatioon due to corrosion,

drift of transmitter, failure of transmitter to

respond.
Table A.2 Gall Report for NPAR Reports .Page 11A

Document: NUREG/CR-4457, Aging of Class 1E Batteries in Safety Systems of Nuclear Power Plants

Reviewed by: Jerry Edson, INEL

Item System Structure/Coml Subcomponent Materials Manufact turer ARD mechanism ARD effects

1 Batteries - General GNB/Gould, Exide,

C&D

Batteries Grids Lead-calcium alloy GNB/Gould, Exide, ELETEMP Plate growth, loss of

C&D contact with active

material

3 Batteries Active Material Lead, lead dioxide GNB/Gould, Exide, GAS, CONTAM Dislodging or

C&D shedding of active

material from the

grid

4 Batteries Separators Rubber/glass mat, GNB/Gould, Exide, ELETEMP Decreased electrical

polyethelene sheets C&D insulation

5 Batteries Electrolyte Sulfuric acid and GNB/Gould, Exide, CONTAM Chemical reactions,

water C&D hydolysis

6 Batteries Vents Fused Alumina GNB/Gould, Exide, MECHSTR Vent breaks allowing

C&D contamination to

enter

71 Batteries Top Conductors Lead-calcium alloy GNB/Gould, Exide, ELETEMP, CORR, Low electrolyte level

C&D EMBR causes corrosion

and embrittlement

8 Batteries Terminals Lead-calcium alloy, GNB/Gould, Exide, CORR/OX, CORR Poor electrical

lead-calcium with C&D contact with external

copper insert busses

9 Batteries Container and Cover Polycarbonate, GNB/Gould, Exide, MECHSTR, Oxidation of the lead

styrene acrylonitrile, C&D CORR/OX causes plate growth

acrylo butadiene

styrene

Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters

Reviewed by: Jerry Edson, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Chargers and General

Inverters

Chargers and Circuit Breakers Not stated PCP, Elgar CONTAM, WEAR, Increased friction,

Inverters EMBR, FAT, binding, loss of

CORR/PIT, continuity

LOSLUB

3 Chargers and Fuse Not stated PCP, Elgar FAT, ELETEMP Metal fatigue and

Inverters melting of the fuse

material

4 Chargers and Relay Not stated PCP, Eigar CORR/PIT, CORR Loss of continuity

Inverters across contacts and

thru coil

Chargers and Electrolytic Not stated PCP, Elgar ELETEMP, VIBR Loss of electrolyte,

Inverters Capacitors failure of leads

6 Chargers and Oil Filled Capacitors Not stated PCP, Elgar ELETEMP, VIBR Dielectric

Inverters breakdown, failure oi

leads

7 Chargers and Magnetics Copper, polyamide PCP, Elgar ELETEMP, Cracking/degr. of

Inverters (Transformer, polymer, mylar tape, THERM-CY, VIBR, insulation and seals,

Inductor) ferite steel LOTEMP, VOLSTR wire fracture

8 Chargers and

Inverters

Silicon Controlled

Rectifier

Not stated PCP, Elgar ELETEMP, Over heating due to

VOLSTR, CURSTR transients
Table A.2 Gall Report for NPAR Reports Page 11B

Document: NUREG/CR-4457, Aging of Class 1E Batteries in Safety Systems of Nuclear Power Plants

Reviewed by: Jerry Edson, INEL

Effect of Aaina on Comoonent Function Contrib to Failure Reeorted progs Rel.proas Report Recommendations Paqe No. Item

Not discussed in N/A A Phase 2 study of seismic 31 1

report vulnerability and advanced

surveillance methods for identying seismic vulnerability [1]

Increased temp. from overcharging, ac Frequent IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 2

ripple, and the environment accelerates 1.129 14,24-26,

oxidation. Poor electrical contact and 32, 33

breaking of the container with subsequent

loss of electrolyte results in reduced

capacity or failure

Gassing caused by overcharging or Occasional IEEE 450, RG 1.129 IEEE 450, RG Not stated 8, 12,13, 3

contamination introduced into the 1.129 14,24-26,

electrolyte deteriorates the active material 32, 33

resulting in reduced capacity

Decreased electrical insulation resulting in Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 4

internal shorts and failure of the battery 1.129 14, 24-26,

32, 33

Chemical reactions and hydrolysis causes Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 51

loss of electrolyte and loss of sulfuric acid 1.129 14,24-26,

resulting in reduced battery capacity 32, 33

Contaminates in the electrolyte result in Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12, 13, 6

reduced capacity 1.129 14,24-26,

32, 33

Embrittied top conductors are susceptible Occasional IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 7

to breaking and causes loss of capacity 1.129 14, 24-26,

32, 33

Poor electrical contact results in loss of Not stated IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12,13, 8

capacity and may result in total battery 1.129 14,24-26,

failure 32, 33

Plate growth and handling stresses Frequent IEEE 450, RG 1.129 IEEE 450, RG Not stated 8,12, 13, 9

results in cracked containers which allow 1.129 14, 24-26,

electrolyte to escape resulting in reduced 32, 33

capacity or total failure

Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not discussed in N/A A comprehensive PM and testing 6-7 1

report program supported by personnel

training should be implemented.

Procedures are needed [2]

Failure to operate, fails open Occasional IEEE-650, NEMA ANSI/IEEE Not stated 4-25, 4- 2

PE 5, IEC 146-2, 741-1986 27, 5-4

IEEE-944 Section 7.3 thru 5-9

Fuse fails open. Failure to operate Occasional IEEE-650, NEMA ANSI/IEEE Pursue fuse failures due to thermal 4-25, 4- 3

PE 5, IEC 146-2, 741-1986 fatigue [2] 27, 5-4

IEEE-944 Section 7.3 thru 5-9,

6-7

Contacts open, open ciruit of the coil, and Occasional IEEE-650, NEMA Vendor Not stated 4-25, 4- 4

relay fails to operate PE 5, IEC 146-2, specific, NEMA 27, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Loss of capacitance and open circuit Frequent IEEE-650, NEMA Vendor Not stated 4-25, 4- 5

resulting in improper output or failure to PE 5, IEC 146-2, specific, NEMA 27, 5-4

operate IEEE-944 PE 5, JEC 142- thru 5-9

2

Loss of capacitance and open circuit Frequent IEEE-650, NEMA Vendor Not stated 4-25, 4- 6

resulting in improper output or failure to PE 5, IEC 146-2, specific, NEMA 27, 5-4

operate IEEE-944 PE 5, IEC 142- thru 5-9

2

Short circuits (turn to turn or to ground)or Occasional IEEE-650, NEMA Vendor Not stated 2-19, 4- 7

change in inductuance resulting in PE 5, IEC 146-2, specific, NEMA 25, 4-28,

improper output. IEEE-944 PE 5, IEC 142-. 5-4 thru 5-

2 9

Short or open circuit resulting in improper

or no output

Occasional IEEE-650, NEMA

PE 5, IEC 146-2,

IEEE-944

Vendor

specific, NEMA

PE 5, IEC 142-

2

Not stated 4-25, 4-

28, 5-4

thru 5-9

a
Table A.2 Gall Report for NPAR Reports Page 12A

Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and Inverters

Reviewed by: Jerry Edson, INEL

Item System Structure/CoMD SubcomDonent Materials Manufacturer ARD) mechanism ARD effects

9 Chargers and Resistors Not stated PCP, Eigar ELETEMP, VIBR Lead fails, decrease

Inverters in resistance

10 Chargers and Printed Circuit Not stated PCP, Elgar THERM-CY, CORR, Cracking of circuit

Inverters Boards VIBR lines, open/loose at

terminals

Chargers and Surge Suppressors Not stated PCP, Elgar ELETEMP, Semiconductor

Inverters VOLSTR, CURSTR barrier breakdown

12 Chargers and Connectors Not stated PCP, Elgar FAT Wire breaks

Inverters

13 Chargers and Meters Not stated PCP, Elgar CONTAM, Increase in bearing

Inverters ELETEMP friction, coil

degrades

14 Chargers and Switches Not stated PCP, Elgar CORR, CORR/PIT Loss of continuity

Inverters across contacts

15 Chargers and Potentiometer Not stated PCP, Elgar ELETEMP Loss of continuity

Inverters across wiper arm

and coil

Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions

Reviewed by: L. C. Meyer, INEL

Item System Structure(Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Protective, Auxiliary, Relay Steel, aluminum, GE & Westinghouse THERM Shape changes for

and Control Relays lexan, and phenolic lexan, no effect for

steel, al., or phnol.

2 Protective, Auxiliary, Coil Wire, Spools, & polyamide-imide Not stated THERM & VOLSTR Thermally caused

and Control Relays Coatings insulated wire, failures, open

copper magnet wire, circuits, and shorts

and nylon bobbins

3 Protective, Auxiliary, Coil Spools Nylon, Zytel & lexan Not stated THERM Thermally caused

and Control Relays failures

Protective, Auxiliary, Coil Coating Polyester tape, fiber Not stated THERM Thermally caused

and Control Relays glass tape, & varnish failures

Protective, Auxiliary, Contact Carriers Phenolic, Zytel, Not stated THERM Nylon may change in

and Control Relays delrin, & nylon shape

Protective, Auxiliary, Contacts Silver alloy Not stated WEAR, CHEM Oxidation when

and Control Relays exosed to air &

material attrition

7 Protective, Auxiliary, Lead Wires Copper Not stated VIB Loose terminals

and Control Relays

8 Protective, Auxiliary, Coil Lead Wire

and Control Relays Insulation

Teflon, silicon

rubber, and Tefzel

Not stated THERM & RAD Slow aging effects,

degradation in

insulation
Table A.2 Gall Report for NPAR Reports Page 12B

Document: NUREG/CR-4564, Operating Experience and Aging-Seismic Assessment of Battery Chargers and. Inverters

Reviewed by: Jerry Edson, INEL

Effect of Aaina on Comnonent Function Contrib to Failure Reported proas Rel.proas ReDort Recomimendations Paqe No. Item

Open circuits, change in resistance Rare IEEE-650, NEMA Vendor Not stated 4-25, 4- 9

values resulting in improper or no output PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Change in output of the charger/inverter Occasional IEEE-650, NEMA Vendor Not stated 4-25, 4- 10

PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Short ciruit within the surge arrestor and Rare IEEE-650, NEMA Vendor Not stated 4-25, 4- 11

failure to operate PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Fatigue caused by installation stress Occasional IEEE-650, NEMA Vendor Not stated 4-25, 4- 12

causes wires to break resulting in open or PE 5, IEC 146-2, specific, NEMA 28, 5-4

short circuits and failure to operate IEEE-944 PE 5, IEC 142- thru 5-9

2

No or improper response from the meter Occasional IEEE-650, NEMA Vendor Not stated 4-25, 4- 13

PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Switch failes open or closed Occasional IEEE-650, NEMA Vendor Not stated 4-25, 4- 14

PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Thermal degradation results in open or Frequent IEEE-650, NEMA Vendor Not stated 4-25, 4- 15

short circuit and improper output PE 5, IEC 146-2, specific, NEMA 28, 5-4

IEEE-944 PE 5, IEC 142- thru 5-9

2

Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions

Reviewed by: L.C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported. progs Rel.progs Report Recommendations Page No. Item

Binding of control relays, have been noted Rare Not discussed in Protection: Perform root cause failure 28, 29, 1

for continuously energized compact relays report IEEE 741, evaluation, develop test method for 35, and

with plastic cases resulting in improper IEEE 338 thermally induced failure cause, see 160

operation or failure to operate report for more rec. [2]

The higher temperatures associated with Rare Not discussed in Protection: Perform root cause failure 28,29, 2

continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35, and

failures of relay coils and bobbins IEEE 338 thermally induced failure cause, see 160

resulting in improper operation or failure to report for more rec. [2]

operate.

The higher temperatures associated with Rare Not discussed in Protection: Perform root cause failure 28, 29, 3

continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35, and

failures of relay bobbins resulting in relay IEEE 338 thermally induced failure cause, see 160

having improper operation or failure to report for more rec. [2]

operate.

The higher temperatures associated with Rare Not discussed in Protection: Perform root cause failure 28,29, 4

continuously energized coils have caused report IEEE 741, evaluation, develop test method for 35, and

failures of relay coils (assumed it includes IEEE 338 thermally induced failure cause, see 160

coatings) resulting in improper operation report for more rec. [2]

or failure of relay. Change in shape due to thermal aging Rare Not discussed in Protection: Perform root cause failure 28, 29, 5

can cause binding or improper contact report IEEE 741, evaluation, develop test method for 35, and

mating resulting in improper operation or IEEE 338 thermally induced failure cause, see 160

failure of relay. report for more rec. [2]

Wear due to use and testing resulting in Rare Not discussed in Protection: Perform root cause failure 28, 29, 6

failure to make proper contact. report IEEE 741, evaluation, develop test method for 35, and

IEEE 338 thermally induced failure cause, see 160

report for more rec. [2]

Loose terminations can cause ohmic Rare Not discussed in Protection: Perform root cause failure 28, 29, 7

heating and burnout report IEEE 741, evaluation, develop test method for 35, and

IEEE 338 thermally induced failure cause, see 160

report for more rec. [2] 1 H

Improper operation or failure to operate. Rare Not discussed in

report

Protection:

IEEE 741,

IEEE 338

Perform root cause failure

evaluation, develop test method for

thermally induced failure cause, see

report for more rec. [2]

28, 29,

35, and

160
Table A.2 Gall Report for NPAR Reports Page 13A

Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

9 Protective, Auxiliary, Slip Motor Rotor Aluminum disc & Not stated CONTAM Metalic iron based

and Control Relays stainless steel shaft particles can prevent

operation

10 Time Delay Relays Case Steel, Lexan, and Not stated THERM Shape changes for

phenolic lexan & phenolic

11 Time Delay Relays timing Motor Magent wire with Not stated THERM Same as other

formal varnish insulation varnish

12 Time Delay Relays Relay Silver Not stated WEAR Wear with use

13 Time Delay Relays Relay Delrin, Zytel, Not stated THERM Oxidation of contact

phenolic, & nylon.

14 Time Delay Relays Cams Delrin & metal Not stated THERM & WEAR Delrin may change

shape, metal may wear

15 Time Delay Relays Timing Circuits Resistance and Not stated Not stated Not stated

capacitance

networks with solid

state components

16 Time Delay Relays Timing Diaphragm Silicon rubber Not stated THERM Material may take a

(Applies to set if not exercised

Pneumatic Relay periodically.

Only)

17 Solid State Relays Solid state Not stated Not stated THERM, RAD, Insulation

Components - SCRs VOLSTR, CURSTR, degradation from

& TRIAC & VIB. therm & rad, fatique

from vib.

18 Molded Case Circuit Contacts, Trip Not stated GE, Westinghouse, THERM, ELECT, Material vaporized,

Breakers Device, Spring, and & Gould MECH, & ENV. annealing bimetal,

Case wear, friction & fat

19 Metal-Clad Circuit Housing, Doors, Steel, electroplated GE, Westinghouse, CURSTR, VIB, FAT, Loose parts,

Breakers Frame & steel, & cast bronze & Gould & CORR. component failure,

Mechanisms stiffening of joints.

2T Metal-Clad Circuit Mechanisms Molybenium disulfide Not stated LOSLUB AND Dryout and

Breakers Lubricants & petroleum-based THERM hardening of

grease lubricants

21 Metal-Clad Circuit Contacts Silver Alloy on GE, Westinghouse, CURSTR, WEAR, Loss of material,

Breakers copper base & Gould THERM, AND wear, and

CONTAM contamination

22 Metal-Clad Circuit Insulating Materials Polyester, glass GE, Westinghouse, THERM, EMBR, Contamination, loss

Breakers for Power Path fiber-filled epoxy & Gould AND VOLSTR of dielectric

resin, & phenolic properties, & leakage

Relays path

23 Safety Injection Relays See relay See relay material GE & Agastat VOLSTR, THERM, Thermal stress, coil

Subcomponent descriptions VIB, AND WEAR burnout, set point

Descriptions drift, & con. wear

241 Safety Injection Circuit Breakers Molded Case and See CB detail GE, Westinghouse, ELECT, THERM, Loss of material,

Metal-Clad Circuit descriptions & Gould VIB, WEAR, & ENV corr, & arcing

Breakers evaporation of

I I I I contacts
Table A.2 Gall Report for NPAR Reports Page 13B

Document: NUREG/CR-4715, An Aging Assessment of Relays and Circuit Breakers and System Interactions

Reviewed by: L. C. Meyer, INEL

Effect of Aqing on Component Function Contrib to Failure Reported Droas Rel.Droas Report Recommendations Page No. Item

Metalic iron based particles can lodge Rare Not discussed in lEE 741-1986 Perform root cause failure 28,-29, 9

between the disc and magnet preventing report Section 7, evaluation, develop test method for 35, and

operation. IEEE 338-1987 thermally induced failure cause, see 160

report for more rec. (2]

Some rare instances of case shape Rare Not discussed in Safety related: Perform root cause failure 28, 30, 10

changes resulting in binding of contacts report IEEE 741, evaluation, develop test method for 35, & 36.

resulting in failure to operate. IEEE 338 thermally induced failure cause, see report for more rec. [2]

Insulaton failure may cause shorts and Rare Not discussed in Safety related: Not stated 30, 35, & 11

failure to provide timing delay function. report IEEE 741, 36.

IEEE 338

Contacts wear with cycling and making Rare Not discussed in Safety related: Not stated 30, & 35 12

and breaking load resulting in failure to report IEEE 741,

make proper contact. IEEE 338

Failure to make proper contact. Rare Not discussed in Safety related: Not stated 30, & 35 13

report IEEE 741,

IEEE 338

Cams may wear and high temperature Rare Not discussed in Safety related: Not stated 30, & 35 14

may deform delrin cams resulting in report IEEE 741,

degraded operation or relay failure. IEEE 338

Not stated Rare Not discussed in Safety related: Not stated 30 15

report IEEE 741,

IEEE 338

The first operation of relay after a long Rare Not discussed in Safety related: Not stated 30 & 36 16

period will have an improper time delay. report IEEE 741,

IEEE 338

Breakdown of insulation, ohmic heating Occasional Not discussed in Safety related: Not stated 26, 27, 17

lead to insulation and component failure, report IEEE 741, 28, & 30.

vib. may loosen sockets/pins causing IEEE 338

opens, shorts resulting relay failure.

Damage contacts & arc chute materials, Occasional Not discussed in Safety related: Replace after two nuisance trips, 78, 83, 18

annealed bimetal strips causes nuisance report IEEE 741. develop diagnostic techniques for 91, 97,99,

trips, vaporized material deposits on Others: No early detection of component 113, and

insulation, loose connections, leakage specific failures. [2] 163

paths, component failure, hardening of

lubricants, stiffening of joints, & loss of

operability.

Freezing of joints, increased friction, & Rare Not discussed in Safety related: Inspection and cleaning after each 85, 98, 19

loss of operability - report IEEE 741. interruption of a major fault. [2] 99, 100, &

Others: No 163

specific

Evaporation of petrolium based grease Occasional Not discussed in Vendor specific Inspection and cleaning after each 85, 98, 20

may leave a nonlubricating soap base & report programs interruption of a major fault. [2] 99, 100, &

high temperatures may cause harding of 163

lubricants resulting in loss of operability.

Failure to operate as required. Occasional Not discussed in Vendor specific Inspection and cleaning after each 85, 98, 21

report programs interruption of a major fault [2] 99,100,

101, &

163.

Failure to provide insulation results in Occasional Not discussed in Vendor specific Inspection and cleaning after each 85, 98, 22

circuit failure. report programs interruption of a major fault. [2] 99,100,

101, &

163.

Coil failures, binding, and electrical Occasional Not discussed in lEE 741-1986 Desirable to have incipient failure 142, 159, 23

component failures increase with age. report Section 7, detection technique to detect both & 160

Protection relays may also fail due to drift IEEE 338-1987 old and new failure modes [2]

Loss of operability. Occasional Plant maintenance IEEE 741-1986 Dagnostic techniques should be 142, 161, 24

Section 7 developed for use with physical 162, &

inspections to determine condition of 163.

_circuit breakers. [2] 1
Table A.2 Gall Report for NPAR Reports Page 14A

Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems

Reviewed by: L. C. Meyer, INEL

Item System StructurelComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

1 Reactor Protection Pressure Seals Ethylene propylene Not stated THERM, RAD, Leaks

System Transmitter MOIST-EL

2 Reactor Protection Pressure Fill-Oil Silicon Not stated THERM & RAD Oil degradation

System Transmitter

3 Reactor Protection Pressure Electronic Epoxy glass Not stated THERM, RAD, Drift and

System Transmitter Components laminate, seats, & MOIST-EL subcomponent

insulation materials degradation

4 Reactor Protection Pressure Piping & Valves Stainless steel Not stated CORR Blockage, leaks

System Transmitter

5 Reactor Protection Pressure Valve Packing Not stated Not stated WEAR Leaks

System Transmitter

6 Reactor Protection Strain Gage Bourdon Tube, EDPM, Nylon, Not stated RAD, THERM, Resistance change,

System Pressure Transduce Electronic copper, tefzel, & MOIST-EL, & tube blockage, and

Components, Seals steel CONTAM shunting

& Wire

7 Reactor Protection Pressure Switch Bellows, Switch Copper Not stated THERM, MOIST- Wear, tube

System Contacts, Seals & EL, CONTAM, blockage, and

Wire WEAR contact resistance

change

8 Reactor Protection Resistance Sensing Wire, Platinum, aluminum Not stated RAD, THERM, AND Resistance change

System Temperature Device Insulator & Sheath oxide powder, and MOIST-EL and shunting

inconel X750 or

stainless steel

sheath

9 Reactor Protection Nuclear Instrument Nuclear Sensitive Not stated Not stated THERMAL-CY AND Degrades sensor,

System Ion Chamber MOIST-EL low resistance, and

erratic output

10 Reactor Protection Electronic Modules Various Electronic Not stated Not stated FAT & VIB Loss of fatigue

System Components resistance

11 Reactor Protection Relays Coils and Contacts Not stated Not stated WEAR, CONTAM, Contacts wear,

System CORR, AND foreign material build

CURSTR up causes short ckt.

12 Reactor Protection Scram Breakers Contacts, Under Not stated Westinghouse WEAR Contact wear, pin

System Volatge & Shunt Trip binding in uv

Attachments attachent, lack of

lubricant

13 Reactor Protection Control Cable Conductor #16 AWG copper Not stated CORR, MOIST-EL, Mechanical damage

System except nuclear RAD, & WEAR & corrosion on instruments sue terminations

I _RG11/CU Coax

14 Reactor Protection

System

Control Cable Insulation Cross linked

polyethylene and

polyethylene

Not stated MOIST-EL, RAD, &

WEAR

Mechanical damage,

insulaton

degradation, and low

ir
Table A.2 Gall Report for NPAR Reports Page 14B

Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems

Reviewed by: L. C. Meyer, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported progs Rel.proqs Report Recommendations Page No. Item

Seal failure allows leaks leading to Occasional Not discussed in IEEE 338- Not stated 15,18,

transmitter drift and moisture intrusion, report 1987, RG 61, 65, &

1.118, ISA 69

67.06, Tech

Spec

Degradation or loss of fill-oil causes Rare Not discussed in IEEE 338- Not stated 18, & 62 2

transmitter drift and signal variance from report 1987, RG

other channels. 1.118, ISA

67.06, Tech

Spec

Components are subject to drift of zero & Occasional Not discussed in IEEE 338- Not stated 18, 65, & 3

span set points, and ultimate failure, report 1987, RG 70

resulting in loss of data channel. 1.118, ISA

67.06, Tech

_____________Spec

Blockage causes degraded channel Occasional Not discussed in IEEE 338- Not stated 17, 19,28, 4

operation, components are subject to report 1987, RG 42, & 69

loss of calibration, resulting in loss of data 1.118, ISA

channel. 67.06, Tech

Spec

Components are subject to loss of Occasional Not discussed in IEEE 338- Not stated 65 5

calibration, resulting in loss of data report 1987, RG

channel. 1.118, ISA

67.06, Tech

Spec

Sensing element resistance change due Occasional Not discussed in IEEE 338- Not stated 15, 17, 6

to radiation, seal failure allows moisture to report 1987, RG 48, & 69

get into connectors that lead to shunting 1.118, ISA

signal, foreign material blocks sensing 67.06, Tech

tube. Spec

Wear leads to switch failure, seal failure Occasional Not discussed in IEEE 338- Not stated 17, 34, 7

allows moisture to get into connectors that report 1987, RG 37, 49, &

lead to shunting signal, foreign material 1.118, ISA 65

blocks sensing tube. 67.06, Tech

Spec

Sensing element resistance change due Rare Not discussed in IEEE 338- Not stated 17. 19, 8

to radiation, seal failure allows moisture to report 1987, RG 27, 32, &

get into sensor and moisture causes 1.118, ISA 70

shunting of signal. 67.06, Tech

Spec

Transmitter becomes noisy or erratic, also Rare Not discussed in IEEE 338- Not stated 19,20, 9

low insulation resistance (few problems report 1987, RG 27, 33,

reported). 1.118, ISA 65, & 66

67.06, Tech

Spec

Small system components such as Occasional Not discussed in IEEE 338- Not stated 27, 29-33, 10

transistors, capacitors, logic elements, report 1987, RG 35-37, 42-

terminals and wire connectors are subject 1.118, ISA 45, 47-49,

to mechanical fatigue-related failures due 67.06, Tech 65, & 70

to vibration, most failures are catastropic Spec

with unknown cause.

Sticking armature, open or short circuits Occasional Not discussed in IEEE 338- Not stated 11, 13, B- 11

in the coil of the electromagnet, and report 1987, RG 7, & C-3

contact degradation causes failure to 1.118, ISA

function. 67.06, Tech

Spec

Increased friction, nicking of latch Occasional Not discussed in IEEE 338- Not stated 66, 70, 12

surfaces caused by repeated opeations, report 1987, RG and

binding and friction causes degraded 1.118, ISA Appendix

operation or failure to operate. 67.06, Tech B

Spec I

Increase in series resistance and loose Rare Not discussed in No specific Further research is needed to 20, 21, 13

connections cause failure to accurately report program determine if improved maintenance 23, 48, &

conduct current. and new predictive techniques are 70

needed. [4]

Decreasea insula on resistance damage

due to handling will accelerate aging and

result in cable falling to accurately

bransmit voltage and current.

Hare Not discussed in

report

No specific

program

Further research is needed to

determine if improved maintenance

and new predictive techniques are

needed. [4]

20,21,

23, 48, &

70

14
Table A.2 Gall Report for NPAR Reports Page 15A

Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems

Reviewed by: L. C. Meyer, INEL Item System StructurelComo SubcomDonent Materials lanufacturer ARC) mechanism ARC) effects

15 Reactor Protection Control Cable Jacket Neoprene and Not stated CORR, MOIST-EL, Loss of material,

System galvanized steel RAD, EMBR, & attrition, and

except nuclear cable WEAR insulation

had PVC and degradation

galvanized steel

16 Reactor Protection Cable Penetrations Assembly, Seals, SS, brass, Not stated CORR, MOIST-EL, Loss of material,

System Cable, Connectors, elastomer, insul. & RAD insulation

& Inert Gas Mali, polysulfone, degradation, loss of

polyolefin, gold fill gass

plated copper

17 Reactor Protection Transmitters, See components B & W CORR, RAD, VIB, See components

System Electronic Modules, CURSTR, THERM,

Cables, Breakers & CONTAM

Document: NUREG/CR-4747 V1, An Aging Failure Survey of LWR Safety Systems and Components

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1~Four Systems J Not stated Not stated Ntstated

Covered (Same as N

Vol ume 2) J________1_______1 ______________ __ ____

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Item System StructuretComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated CONTAM Buildup of deposits

System

2 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated WEAR Attrition

System

3 Auxiliary Feedwater AC Circuit Breakers Not stated Not stated Not stated VIBR Loosening

System

4 Auxiliary Feedwater Flow Controllers Not stated Not stated Not stated CLOG Row blockage

System

5 Auxiliary Feedwater Flow Controllers Not stated Not stated Not stated Not stated Loss of performance

System

6 Auxiliary Feedwater 'Flow Controllers Not stated Not stated Not stated Not stated Drift, contact failure,

System module failure, or

elect, failure

7 Auxiliary Feedwater Row Control Not stated Not stated Not stated WEAR Attrition

System Recorders

8 Auxiliary Feedwater Flow Control Not stated Not stated Not stated Not stated Loss of performance

System Recorders

9 Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated CONTAM Buildup of deposites

System causing

erroneous/erratic

signals

1 C Auxiliary Feedwater

System

Flow Transmitters Not stated Not stated Not stated Not stated Out of calibration,

drift, or module taultý
Table A.2 Gall Report for NPAR Reports Page 1513

Document: NUREG/CR-4740, Nuclear Plant-Aging Research on Reactor Protection Systems

Reviewed by: L. C. Meyer, INEL [=ff•,•t nf Aninn nn r~nmnnn~nt FuunP~finn C3nntrih tn F~ilu~re Rennrted nrna• Relnlrons Renort Recommendations Pacae No. Item

Failure to protect cable insulation and Occasional Not discussed in No specific Further research is needed to 20, 21, & 15

conductors. report program determine if improved maintenance 48

and new predictive techniques are

needed. [4]

Radiation causes embrittlement and Rare Not discussed in No specific Further research is needed to 20 & 23 16

insulation degradation, corrosion causes report program determine if improved maintenance

material degradation and material build and new predictive techniques are

up, leaking seal allow loss of fill gas and needed. (2]

then moisture intrusion resulting in failure

to accurately transmit voltage and current.

See components Rare Not discussed in lEE 338-1987, Further research is needed to IV, 69, & 17

report RG 1.118, ISA determine if improved maintenance A-16

67.06, Tech. and new predictive techniques are

Spec needed. [2]

Document: NUREG/CR-4747 V1, An Aging Failure Survey of LWR Safety Systems and Components

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The aging information in Volume 1 is the Not stated Not discussed in N/A stated 1

same asthat covered in the Volume 2 reportI

reveiw. I 1 I 1 _1

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fails to close Rare Not discussed in lEE 741-1986 Not stated F-20 1

report Section 7

Failure to operate - the circuit breaker Occasional Not discussed in lEE 741-1986 Not stated F-20 2

does not function properly, either fails to report Section 7

open or fails to close on demand.

Failure to operate - the circuit breaker Rare Not discussed in lEE 741-1986 Not stated F-20 3

does not function properly, either fails to report Section 7

open or fails to close on demand.

Erroneous or erraric signals - erroneous Rare Not discussed in IEEE 338- Not stated F-21 4

or erratic signals are produced by the report 1987, Tech.

instrument because of foreign material Spec.

intrusion, requirements

Erroneous or erratic signals - erroneous Rare Not discussed in IEEE 338- Not stated F-21 5

or erratic signals are produced by the report 1987, Tech.

instrument due to faulty module or loss of Spec.

calibration. requirements

Failure to operate Rare Not discussed in IEEE 338- Not stated F-21 6

report 1987, Tech.

Spec.

requirements

Erroneous/erratic signals - erroneous Rare Not discussed in IEEE 338- Not stated F-22 7

erratic signals are produced by the report 1987, Tech.

instrument. Spec.

requirements

Erroneous/erratic signals - erroneous Rare Not discussed in IEEE 338- Not stated F-22 8

erratic signals are produced by the report 1987, Tech.

instrument being out of calibration. Spec.

requirements

Eroneous or erratic signals are produced Rare Not discussed in IEEE 338- Not stated F-23 9

by the instrument report 1987, RG

1.118, ISA

67.06, Tech

ISpec

Loss of performance Occasional Not discussed in

report

IEEE 338-

1987, RG

1.118, ISA

67.06, Tech

Spec

Not stated F-23 10
Table A.2 Gall Report for NPAR Reports Page 16A

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1I Auxiliary Feedwater Flow Transmitters Not stated Not stated Not stated WEAR Attrition

System

12 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Erroneous/erratic

System Indicators signals

13 Auxiliary Feedwater Level Control Not stated Not stated Not stated FAT Cumulative fatigue

System Indicators damage

14 Auxiliary Feedwater Level Control Not stated Not stated Not stated WEAR Attrition

System Indicators

15 Auxiliary Feedwater Level Control Not stated Not stated Not stated Not stated Loss of performance

System Indicators or end of life

16 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Erroneous/erratic

System signals

17 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated FAT Cumulative fatigue

System damage

18 Auxiliary Feedwater Level Controllers Not stated Not stated Not stated Not stated Loss of performance

System

19 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CONTAM Buildup of deposits

System

20 Auxiliary Feedwater Pressure Switch Not stated Not stated. Not stated Not stated Loss of performance

System

21 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated WEAR Attrition

System

22 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CORR Loss of material

System

23 Auxiliary Feedwater Pressure Switch Not stated Not stated Not stated CURSTR Arcing, material

System attrltion, and carbon

deposits

Auxiiary Feedwater Pressure

System Transmitter

Not stated Not stated Not stated Not stated Loss of performance
Table A,2 Gall Report for NPAR Reports Page 16B

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Failure to operate Rare Not discussed in IEEE 338- Not stated F-23 11

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Out of calibration or faulty module related Rare Not discussed in IEEE 338- Not stated F-27 12

to aging, report 1987, RG

1.118, ISA

67.06, Tech

Spec I

Failure to operate Rare Not discussed in IEEE 338- Not stated F-27 13

report 1987, RG

1.118, ISA

67.06, Tech

Failure to operate Rare Not discussed in IEEE 338- Not stated F-27 14

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate because of end of life or Rare Not discussed in IEEE 338- Not stated F-27 15

faulty module related to aging. report 1987, RG

.1.118, ISA

67.06, Tech

Spec

Loss of performance due to out of Rare Not discussed in IEEE 338- Not stated F-28 16

calibration or faulty module report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate Rare Not discussed in IEEE 338- Not stated F-28 17

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate due to faulty module Rare Not discussed in IEEE 338- Not stated F-28 18

related to aging. report 1987, RG

1.118, ISA

67.06, Tech

Spec

Erroneous or erratic signals are produced Rare Not discussed in IEEE 338- Not stated F-38 19

by the instrument, report 1987, RG

1.118, ISA

67.06, Tech

Erroneous signals are produced by the Occasional Not discussed in IEEE 338- Not stated F-38 20

instrument because of out of calibration report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate Rare Not discussed in IEEE 338- Not stated F-38 21

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate Rare Not discussed in IEEE 338- Not stated F-38 22

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate Rare Not discussed in IEEE 338- Not stated F-38 23

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Erroneous signals are produced by the

instrument due to out of calibration or

faulty module.

Rare Not discussed in

report

IEEE 338-

1987, RG

1.118, ISA

67.06, Tech

Soec

Not stated F-39 24l
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Item System StructureJComD SubcomDonent Materials Manufacturer ARD mechanism

Page 17A

ARD effects

25 Auxiliary Feedwater Pressure Not stated Not stated Not stated WEAR Attrition

System Transmitter

26 Auxiliary Feedwater Pressure Not stated Not stated Not stated Not stated Open circuit

System Transmitter

27 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition

System

28 Auxiliary Feedwater Relays Not stated Not stated Not stated Not stated Loss of function

System

29 Auxiliary Feedwater Relays Not stated Not stated Not stated WEAR Attrition

System

30 Chemical and AC Circuit Breakers Not stated Not stated Not stated FAT Cumulative fatigue

Volume Control damage

System _

31 Chemical and Heat Tracing Not stated Not stated Not stated CORR Loss of material

Volume Control Heaters

System

32 Chemical and Heat Tracing Not stated Not stated Not stated Not stated Abnormal resistance

Volume Control Heaters or aging related set

System point drift.

33 Chemical and Level Controllers Not stated Not stated Not stated FAT Cumulative fatigue

Volume Control damage

System

34 Chemical and Level Controllers Not stated Not stated Not stated Not stated Loss of performance

Volume Control

System

35 Chemical and Level Transmitters Not stated Not stated Not stated Not stated Loss of performance

Volume Control

System

36 Class 1 E DC Power Batteries Not stated Not stated Not stated Not stated Cause accelerated

Supply System aging, not hold

charge, or end of life

37 Class 1 E DO Power Battery Not stated Not stated Not stated WEAR Attrition

Supply System

38 Class 1 E DC Power Battery Not stated Not stated Not stated CONTAM Buildup of deposits

Supply System

39 Class 1E DC Power Battery Not stated Not stated Not stated Not stated Loss of performance

Supply System

FJ40 Class 1 E DC Power AC Circuit Breaker Not stated Not stated Not stated WEAR Attrition

Supply System

41 Emergency On-Site

Power Supply

System

Diesel Generator Not stated Not stated Not stated Not stated Loss of performancel
Table A.2 Gall Report for NPAR Reports Page 17B

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL Effect of Aaina on Combonent Funtction Contrib to Failure Renorted nrnnn ReI.nroas Report Reoommendzation• PaenItem

Effect an f onC m Io ........ o e tF c ... i n .... tibt . ..... R . pr .... te r' . e....r---s . ... or .............................. t Failure to open - failure to operate Rare Not discussed in IEEE 338- Not stated F-39 25

report 1987, RG

1.118, ISA

67.06, Tech

Spec

Failure to operate Rare Not discussed in IEEE 338- Not stated F-39 26

report 1987, RG

1.118, ISA

67.06, Tech

Spec I

Fails to open - failure of a rnormally closed Rare Not discussed in Vendor Not stated F-40 27

relay to open upon demand because of report specific, NEMA

binding, or wear PE 5, IEC 146-

2

Failure to operate because of drift or Rare Not discussed in Vendor Not stated F-40 28

insulation breakdown related to aging, report specific, NEMA

PE 5, IEC 146-

2

Failure to operate Rare Not discussed in Vendor Not stated F-41 29

report specific, NEMA

PE 5, IEC 146-

2

Failure to operate - the circuit breaker Rare Not discussed in ANSI/IEEE Not stated F-47 30

does not function properly, either fails to report 741-1986

open or fails to close on demand. Section 7

Loss of function Rare Not discussed in No specific Not stated F-48 31

report program

Loss of function Rare Not discussed in No specific Not stated F-48 32

report program

Erroneous or erratic signals are produced Rare Not discussed in IEEE 338- Not stated F-49 33

by the instrument, report 1987, RG

1.118, ISA

67.06

Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338- Not stated F-49 34

by the instrument because of being out of report 1987, RG

calibration. 1.118, ISA

67.06

Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338- Not stated F-50 35

by the instrument because of being out of report 1987, RG

calibration or faulty module. 1.118, ISA

67.06

Loss of function - lack of specified output Occasional Not discussed in IEEE 450- Not stated F-56 36

from batteries report 1987, RG

1.129, Tech

Spec Surveil.

Loss of function - inability of the charging Rare Not discussed in Vendor Not stated F-57 37

unit to perform its function to report specific, NEMA

specifications. PE 5, IEC 146-

2

Loss of function - inability of the charging Rare Not discussed in Vendor Not stated F-57 38

unit to perform its function to report specific, NEMA

specifications. PE 5, IEC 146-

2

Loss of function - inability of the charging Frequent Not discussed in Vendor Not stated F-57 39

unit to perform its function to report specific, NEMA

specifications because of set point drift or PE 5, IEC 146-

faulty module, 2

Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-58 40

does not function properly, either fails to report Section 7

open or fails to close on demand.

-ailure to perform as expected because o0

aging related component drift or out of

calibration.

Hare Not discussed in

report

Vendor

specific, RG

1.108, Tech.

Specs.

Not stated F-61 41
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism

Page 18A

ARD effects

42 Emergency On-Site Diesel Generator Not stated Not stated Not stated Not stated Loss of function

Power Supply

System

43 CLASS 1 E AC Circuit Breaker Not stated Not stated Not stated WEAR Attrition

Instrumentation,

Uninterruptable

Power Supply

System

44 CLASS 1 E Inverter Not stated Not stated Not stated WEAR Attrition

Instrumentation,

Uninterruptable

Power Supply

System

45 CLASS 1 E Inverter Not stated Not stated Not stated Not stated Loss of function

Instrumentation,

Uninterruptable

Power Supply

System

46 CLASS 1 E Inverter Not stated Not stated Not stated Not stated Loss of performance

Instrumentation,

Uninterruptable

Power Supply

System

47 High Pressure AC Circuit Breakers Not stated Not stated Not stated FAT Cumulative fatigue

Injection System damage

48 High Pressure AC Circuit Breakers Not stated Not stated Not stated WEAR Attrition

Injection System

49 High Pressure AC Circuit Breakers Not stated Not stated Not stated Not stated Los of performance

Injection System

50 High Pressure Flow Transmitter Not stated Not stated Not stated Not stated Cause accelerated

Injection System aging

51 High Pressure Row Transmitter Not stated Not stated Not stated Not stated Loss of performance

Injection System

52 High Pressure Row Transmitter Not stated Not stated Not stated FAT Cumulative fatigue

Injection System damage

53 High Pressure Flow Transmitter Not stated Not stated Not stated WEAR Attrition

Injection System

54 High Pressure Heat Tracing Not stated Not stated Not stated CORR Loss of material

Injection System Heaters

55 High Pressure Heat Tracing Not stated Not stated Not stated Not stated Winding failure,

Injection System Heaters open, short, or high

resistance

56 High Pressure Load Sequence Not stated Not stated Not stated Not stated End of life

Injection System Controllers

57 High Pressure Load Sequence Not stated Not stated Not stated CONTAM Builup of deposits

Injection System Controllers

58 High Pressure Load Sequence Not stated Not stated Not stated Not stated Loss of performance

Injection System Controllers

59 High Pressure Level Transmitters Not stated Not stated Not stated Not stated Loss of performance

Injection System

60 High Pressure Pressure Not stated Not stated Not stated Not stated Loss of performance

Injection System Transmitter

61 Service Water

System

AC Breakers Not stated Not stated Not stated FAT Fatigue

accumulative

damaces
Table A.2 Gall Report for NPAR Reports Page 18B

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Ught Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L.C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Failure due to open circuit. Rare Not discussed in Vendor Not stated F-61 42

report specific, RG

1.108, Tech.

Specs.

Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-63 43

does not function properly, either fails to report Section 7

open or fails to close on demand.

Loss of function - the inverter fails to Occasional Not discussed in Vendor specific Not stated F-64 44

perform its intended function to specified report programs.

requirements. Tech. Specs.

The inverter fails to perform its intended Occasional Not discussed in Vendor specific Not stated F-64 45

function to specified requirements due to report programs.

electrical failure, insulation breakdown, Tech. Specs.

open or short circuit related to aging.

The inverter has degraded operation Occasional Not discussed in Vendor specific Not stated F-64 46

because of aging related drift or faulty report programs.

modules. Tech. Specs.

Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-66 47

does not function properly, either fails to report Section 7

open or fails to close on demand.

Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-66 48

does not function properly, either fails to report Section 7

open or fails to close on demand.

Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-66 49

does not function properly, either fails to report Section 7

open or fails to close on demand because

of a faulty module.

Erroneous or erratic signals are produced Rare Not discussed in IEEE 338- Not stated F-67 50

by the instrument report 1987, RG

1.118

Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338- Not stated F-67 51

by the instrument because out of report 1987, RG

calibration. 1.118

Failure to operate Rare Not discussed in IEEE 338- Not stated F-67 52

report 1987, RG

1.118

Failure to operate Rare Not discussed in IEEE 338- Not stated F-67 53

report 1987, RG

1.118

Loss of function Rare Not discussed in No specific Not stated F-71 54

report program

Loss of function Occasional Not discussed in No specific Not stated F-71 55

report program

Erroneous or erratic signals Rare Not discussed in IEEE 338- Not stated F-72 56

report 1987, RG

1.118

Failure to operate Occasional Not discussed in IEEE 338- Not stated F-72 57

report 1987, RG

1.118

Failure to operate because of faulty Occasional Not discussed in IEEE 338- Not stated F-72 58

module report 1987, RG

1.118

Erroneous or erratic signals because unit Occasional Not discussed in IEEE 338- Not stated F-73 59

out of calibration, report 1987, RG

1.118

Erroneous or erratic signals are produced Occasional Not discussed in IEEE 338- Not stated F-82 60

by the instrument because of set point report 1987, RG

drift due to aging. 1 11.118 1

Failure to operate - the circuit breaker

does not function properly, either fails to

open or fails to close on demand.

Rare Not discussed in

report

IEEE 741-1986

Section 7

Not stated F-88 61
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism

Page 19A

ARD effects

62 Service Water AC Breakers Not stated Not stated Not stated WEAR Attrition

System

63 Service Water AC Breakers Not stated Not stated Not stated Not stated Binding or out of

System adjustment

64 Service Water AC Breakers Not stated Not stated Not stated CONTAM Buildup of deposits

System

65 Service Water AC Breakers Not stated Not stated Not stated Not stated Coil failure

System

66 Service Water Flow Indicators Not stated Not stated Not stated Not stated Loss of performance

System

67 Service Water Flow Swicthes Not stated Not stated Not stated CONTAM Buildup of deposits

System

68 Service Water Row Swicthes Not stated Not stated Not stated Not stated Loss of performance

System

69 Service Water Pressure Indicators Not stated Not stated Not stated CLOG Buildup

System

70 Service Water Pressure Indicators Not stated Not stated Not stated Not stated Loss of performance

System

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 SOV ASCO 3-Way Coil Class H insulation ASCO ELETEMP, Loss of dielebtic

Direct Acting CURSTR, & strength and

VOLSTR conductor

I_ short/open

2 SOV Core Stainless steel ASCO CONTAM Friction between

core and guide

3 SOV Disk Holder Assy EPDRM OR Vitron ASCO ELETEMP Degradation of

Seat elastomers

4 SOV Disc Holder Spring Steel ASCO CORR Spring relaxation or

failure

5 SOV Core Spring Stainless steel ASCO CORR Spring failure

6 SOV Disc Holder EPDM OR Viton ASCO CONTAM & Seat degradation

Assembly Seat ELETEMP

7 SOV 3-Way Pilot Coil Not stated ASCO ELETEMP, Insulation failure and

Operated CURSTR, & conductor

VOLSTR open/short

8 SOV Core Not stated ASCO CONTAM Binding between

core and guide

SOV Disc Holder Assy

Seat

Elastomers ASCO CORR ELETEMP Valve disc adheres

to oriface
Table A.2 Gall Report for NPAR Reports Page 19B

Document: NUREG/CR-4747 V2, An Aging Failure Survey of Light Water Reactor Safety Systems and Components (Electrical)

Reviewed by: L. C. Meyer, INEL Effect of Aaina on Comr, nnent Funtction Contrib to Failure Renorted nroas Rel~oroas Reoort Recommendations Paae No. Item .. -; . . . . . .• .. r .. . . . . . .. . . .. . ... . . . r.. ..-- - .- r'- - . .;.;.. --7 . .. r . . . . ... . . . .

Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-88 62

does not function properly, either fails to report Section 7

open or fails to close on demand. I

Failure to operate - the circuit breaker Rare Not discussed in IEEE 741-1986 Not stated F-88 63

does not function properly, either fails to report Section 7

open or fails to close on demand. I

Failure to operate - the circuit breaker Occasional Not discussed in IEEE 741-1986 Not stated F-88 64

does not function properly, either fails to report Section 7

open or fails to close on demand.

Premature open - the opening of the Rare Not discussed in IEEE 741-1986 Not stated F-88 65

circuit breaker prior to demand, report Section 7

Failure to operate due to being out of Occasional Not discussed in IEEE 338- Not stated F-89 66

calibration (aging related). report 1987, RG

1.118

Erroneous or erratic signals Rare Not discussed in IEEE 338- Not stated F-89 67

report 1987, RG

1.118

Erroneous or erratic signals due to set Frequent Not discussed in IEEE 338- Not stated F-90 68

point drift, insulation breakdown or out of report 1987, RG

calibration. 1.118

Erroneous or erratic signals Rare Not discussed in IEEE 338- Not stated F-104 69

report 1987, RG

1.118

Erroneous or erratic signals because of Rare Not discussed in IEEE 338- Not stated F-104 70

being out of calibraton. report 1987, RG

1.118

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Valve does not operate Occasional Not discussed in Vendor specific R&D to develope test methods. 25-26. 34- 1

report programs Testing of proposed monitoring 35.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Partial/full failure of valve to change Occasional Not discussed in Vendor specific R&D to develops test methods. 25-26. 34- 2

position report programs Testing of proposed monitoring 35.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34- 3

report programs Testing of proposed monitoring 35.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34- 4

report programs Testing of proposed monitoring 35. 41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Seat leakage Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34- 5

report programs Testing of proposed monitoring 35. 41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Seat leakage Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34- 6

report programs Testing of proposed monitoring 35.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 7

report programs Testing of proposed monitoring 36. 41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 8

report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 64

_Evaluation of failures [4]

Valve tails to operate as required Not stated Not discussed in

report

Vendor specific

programs

R&D to develope test methods.

Testing of proposed monitoring

techniques. Develope baseline data.

Evaluation of failures [4]

25-26. 34.

36. 41-43.

54

S
Table A.2 Gall Report for NPAR Reports Page 20A

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Item System StructurefComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

10 SOV Disc Holder Spring Steel ASCO CORR Spring relaxation or

failure

11 SOV Pressure Diaphragm ASCO CONTAM Blocked bleeder hole

Bleed Hole

12 SOV Exhaust Diaphragm ASCO CONTAM Blocked bleeder hole

Bleed Hold

13 SOV Core Spring Stainless steel ASCO CORR Spring failure

14 SOV Disc Holder Assy EPDM ASCO CONTAM Seat degradation

Seat ELETEMP

15 SOV Pressure Diaphragm EPDM OR Nomex ASCO CONTAM Continuous exhaust

fabric ELETEMP

16 SOV Exhaust Diaphragm EPDM OR Nomex ASCO CONTAM Leakage through

fabric ELETEMP exhaust port

17 SOV 2-Way Direct Coil Class H insulation Vaicore ELETEMP Insulation failure

Operating CURSTR VOLSTR short/open

conductors

18 SOV 2-Way Direct Coil Not stated Valcore ELETEMP Insulation failure

Operating CURSTR VOLSTR short/open

conductors

19 SOV 2-Way Direct Plunger Spring Stainless steel Valcore CONTAM CORR Binding in guide.

Operating spring breakage

20 SOV 2-Way Direct Plunger Spring Stainless steel Valcore CONTAM CORR Binding in guide.

Operating spring breakage

21 SOV 2-Way Direct Pilot Spring Not stated Valcore CORR Spring failure

Operating

22 SOV 2-Way Direct Plunger Stainless steel Valcore CONTAM Binding in guide tube

Operating

23 SOV 2-Way Direct Plunger Stainless steel Valcore CONTAM Binding in guide tube

Operating

24 SOV 2-Way Direct Pilot Spring Stainless steel Valcore CORR Spring failure

Operating

25 SOV 2-Way Direct Position Reed Not stated Valcore Not stated Contact failure

Operating

2E SOV 2-Way Direct

Operating

Poppet Seat Elastomers Valcore ELETEMP

CONTAM

Eroded seat
Table A.2 Gall Report for NPAR Reports Page 20B

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Effect of Aqina on Component Function Contrib to Failure Reported Proqs Rel.progs Report Recommendations Page No. Item

Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 10

report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve slow to respond Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 11

report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate as required Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 12

report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 13

report programs Testing of proposed monitoring 36. 41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26.34. 14

report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve leakage - valve failure to operate as Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26.34. 15

required report programs Testing of proposed monitoring 36. 41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve leakage - valve failure to operate as Not stated Not discussed in Vendor specific R&D to develope test methods. 25-26. 34. 16

required report programs Testing of proposed monitoring 36.41-43.

techniques. Develope baseline data. 54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 16.25-28. 17

report programs Testing of proposed monitoring 34. 37.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 18

report programs Testing of proposed monitoring 34.38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 16.25-28. 19

report programs Testing of proposed monitoring 34.37.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 20

report programs Testing of proposed monitoring 34.38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 21

report programs Testing of proposed monitoring 34.38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve sluggish or not operational Not stated Not discussed in Vendor specific R&D to develope test methods. 16.25-28. 22

report programs Testing of proposed monitoring 34.37.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve sluggish or no operation Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 23

report programs Testing of proposed monitoring 34. 38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Slow valve closure Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 24

report programs Testing of proposed monitoring 34.38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

No or constant position indication Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 25

report programs Testing of proposed monitoring 34.38.

techniques. Develope baseline data. 41-43.54

_Evaluation of failures [4]

Valve leakage Not stated Not discussed in

report

Vendor specific

programs

R&D to develope test methods.

Testing of proposed monitoring

techniques. Develope baseline data.

Evaluation of failures [4]

16.25-28.

34. 37.

41-43. 54

2E
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Page 21A

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

27 SOV 2-Way Direct Poppet Seat EPDM Valcore ELETEMP Eroded seat

Operating CONTAM

28 SOV 2-Way Direct Pilot Seat Seal EPDM Valcore ELETEMP Eroded seat

Operating CONTAM

29 SOV 2-Way Direct Coil Class H insulation TRC ELETEMP Insulation failure and

Operating CURSTR VOLSTR short/open

conductor

30 SOV Coil Diode Not stated TRC Not stated Open diode

31 SOV Core Not stated TRC CONTAM Binding in core tube

32 SOV Pilot Disc Seat Stainless steel TRC ELETEMP Degradation of

CONTAM elastomers

33 SOV Main Disc Stainless steel TRC CONTAM Jammed disc

34 SOV Position Switch Not stated TRC WEAR Contact failure

35 SOV Position Relay Not stated TRC Not stated Coil conductor

short/open

36 SOV Return Spring Stainless steel TRC CORR Spring breakage

37 SOV Main Disc Seat Stainless steel TRC WEAR Seat degradation

Document: NUREG/CR-4819 V2, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants, Vol. 2

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Solenoid-Operated Core Seat & Seals Not stated ASCO AND Skinner THERM & AGR- Prolonged

Valves (Elastomeric CHEM temperatures

Components) degrades seals,

chem attack by oils

2 Solenoid-Operated Solenoid Coil Not stated Not stated THERM Degraded insulation

Valves Insulation

3 Solenoid-Operated Core Spring Not stated Not stated WEAR & CORR Changes in

Valves mechanical

propeties. binding, oi

corrsion contain

Solenoid-Operated Sliding Surfaces Not stated Not stated WEAR & CORR Loss of material and

Valves crud buidup
Table A.2 Gall Report for NPAR Reports Page 21B

Document: NUREG/CR-4819 V1, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported Proas Rel.Droqs Report Recommendations Paqe No. Item

Valve leakage Not stated Not discussed in Vendor specific R&D to develops test methods. 19.'25-28. 27

report programs Testing of proposed monitoring 34. 38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve leakage Not stated Not discussed in Vendor specific R&D to develope test methods. 19.25-28. 28

report programs Testing of proposed monitoring 34. 38.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 29

report programs Testing of proposed monitoring 34.39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails closed Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 30

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 31

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 32

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve fails to operate Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 33

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43. 54

Evaluation of failures [4]

Loss of position indication Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 34

report programs Testing of proposed monitoring 34.39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Position indication does not change Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 35

report programs Testing of proposed monitoring 34.39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve remains open Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 36

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Valve does not have a tight shutoff Not stated Not discussed in Vendor specific R&D to develope test methods. 21.25-28. 37

report programs Testing of proposed monitoring 34. 39.

techniques. Develope baseline data. 41-43.54

Evaluation of failures [4]

Document: NUREG/CR-4819 V2, Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants, Vol. 2

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Pa e No. Item

Chemical attack of elastomers by oil and Rare Not discussed in Vendor specific Determine the sensitivity with which 5, 7, 8, 1

degradation of elastomers resulting from report programs degraded elestomenc valve seats 11, & 44

prolonged operation at excessively high can be determined from electrical

temperatures resulting in failure to measurements [2]

operate.

Electrical failure of solenoid coil, caused Occasional Not discussed in Vendor specific Visual inspections and electrical 5, 7, 8, 2

by high-voltage turn-off transients in report programs resistance tests [2] 11, & 44

combination with insulation weakened by

prolonged operation at high temperatures,

electrical failure due to short circuit,

conductor burnout.

Changes in mechanical properties of Rare Not discussed in Vendor specific Visual inspections and electrical 5, 7, 8, 3

materials, binding in operation, hum or report programs characterization of inrush currents 11, & 44

chatter, worn spring, & wear, change in [2]

valve operating time or in rush current.

Mechanical binding and sluggish shifting Occasional Not discussed in Vendor specific Visual inspections and electrical 5, 7, 8, 4

caused by worn or improper parts or the report programs characterization of inrush currents 11, & 44

presence of foreign materials inside the and valve actuation times. [2]

valve, increase in frictional force
Table A.2 Gall Report for NPAR Reports Page 22A

Document: NUREG/CR-4928, Degradation of Nuclear Plant Temperature Sensors

Reviewed by: L C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Temperature RTD Sensing Wire Platinum Not stated OXIDAT, VIB, Platininum oxide

Sensors or Film CONTAM, & ELE- build up, fat, ion

TEMP migration, & strain

2 Temperature RTD Insulation Powder or cement Not stated MOIST-EL Moisture decreases

Sensors (material not resistance

identified in report)

Temperature RTD Sheath Stainless steel Not stated VIB Cold working in

Sensors metals

Document: NUREG/CR-4939 V1, Improving Motor Reliability in Nuclear Power Plants - Performance Evaluation and Maintenance Practices

Reviewed by: Jerry Edson, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 ElectricoMtrs Dielectric, Not stated Not stated Not stated Insulation is most IRotational, affected by aging

Mechanical mechanisms

Document: NUREG/CR-4939 V2, Improving Motor Reliability in Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Motor Insulation Glass, mylar, dacron Westinghouse ELETEMP Slot wedge

w/poly binder, epoxy, developed hole(s),

poly fibers & poly arcing to ground

varnish

2 Motor Bearing Not stated Westinghouse ELETEMP WEAR Bearing failure

Document: NUREG/CR-4939 V3, Failure Analysis and Diagnostic Tests on A Naturally Aged Large Electric Motor

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

400HP, 2400 V Not stated Not stated IVOLSTR IInsulation

L _ _ _ _ _ _ _ _ _ _ _ _ M otor IfIIbreakdow n

Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

15 PWR high pressure Air Operated Valves Not stated Not stated CONTAM Parts degrade from

injection system oil in air supply

16 PWR high pressure HPI Nozzles and Stainless steel Not stated THERM FAT Crack initiation and

injection system Thermal Sleeve propagation

17 PWR high pressure I & C Electronics Small Electronic Not stated Not stated CORR Opens, shorts, and

injection system Components loose connections

18 PWR high pressure PIPING Stainless steel Not stated THERM FAT, Cracking & abrasive

injection system WEAR, VIB, & wear MECHSTR

19 PWR high pressure Valve Stainless steel Not stated WEAR & CONTAM Leakage, blockage,

injection system & mechanical

linkage faults

201 PWR high pressure Pump Stainless steel Not stated THERM-CY, Wear on parts and

injection system WEAR, VIB, & FAT seal leaks

21 PWR high pressure Pipe Supports Not stated Not stated VIB AND FAT Loosening of

injection system connections or breaking loose

22 PWR high pressure Motor Operated Stainless steel Not stated WEAR AND Loose connections,

injection system Valve VOLSTR wear on moving

parts, motor failure
Table A.2 Gall Report for NPAR Reports Page 22B

Document: NUREG/CR-4928, Degradation of Nuclear Plant Temperature Sensors

Reviewed by: L C. Meyer, INEL Effect of Aoina on Comnonent Function Contrib to Failure Reported Dross Rel.Droas Report Recommendations Paae No. Item Effect of Acino ........ r Function . to .. Frt I- pf Changes in resistance causes calibration Not stated Not discussed in RG 1.118, Burn-in program for new sensors, A-9, and 1

changes report IEEE 338-1987 develop a data base for degradation A-31 to Amechanisms, and simple tests to 36

check sensor prob. [2]

Shunting of sensing element occurs when Not stated Not discussed in No specific Burn-in program for new sensors, A-9, and 2

insulating powder gets wet. moisture report program develop a data base for degradation A-31 to Aintrusion occurs when the seals dry out, mechanisms, and simple tests to 36

shrink, crack, or leak resulting in check sensor prob. [2]

calibration shift or failure to function.

Mechanical shock and vibration can Not stated Not discussed in No specific Burn-in program for new sensors, A-9, and 3

cause cold working in metal that leads to report program develop a data base for degradation A-31 to Afailure of the sheath and moisture mechanisms, and simple tests to 36

intrusion. check sensor prob. [2]

Document: NUREG/CR-4939 V1, Improving Motor Reliability in Nuclear Power Plants - Performance Evaluation and Maintenance Practices

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

This report references a phase I study Not stated EPRI; IEEE EPRI; IEEE 4, Motors important to safety should 1-6; 2-7; 1

that report investigated only addresses aging motor effects. evaluation This 4,43,85,95,112,117, 28,43,85,95,112,1117,28,49[] 43, 85, 95, 112, undergo cost-effective PM programs 4-1; 1015-

and maintenance practices 1 I 112; 7-1

Document: NUREG/CR-4939 V2, Improving Motor Reliability in Nuclear Power Plants

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure. Reported progs Rel.progs Report Recommendations Page No. Item

Motor failure Not stated Not discussed in IEEE 334-1974 The 'plug reversal life test" is 2-1, 6-1 1

report Section 14.2.3 recommended for motor

qualification. [2]

Motor failure Not stated Not discussed in IEEE 334-1974 Not stated 4-1,5-1, 2

report Section 14.2.3 6-1

Document: NUREG/CR-4939 V3, Failure Analysis and Diagnostic Tests on A Naturally Aged Large Electric Motor

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item IMtrfiure IFrequent IDC insulation &/or IEEE 334-1974 lInsfall effective grnd or grnd 13-4 11

polarization tests Section 14.2.3 fdetectors on 3 Ph "capacitanceI

_grnded (delta) PWR syst [2]

Document: NUREG/CR-4967, Nuclear Plant Aging Research on High Pressure Injection Systems

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fail to operate Rare Not discussed in Vendor specific Not stated 36 15

report program. Tech

Spec surveill.

Nozzle leaks and loose parts resulting in Rare Not discussed in Dye penetrant, Not stated 36 & 53 16

degraded HPI system report ultrasonic,

radiography

Failure to operate Occasional Not discussed in IEEE 338-1987 Not stated 36 17

report

Through the pipe wall leakage resulting in Rare Not discussed in Dye penentant, Not stated 36 & 53 18

HPIS degraded operation or failure to report ultrasonic,

function. radiography

Failure to operate resulting in HPIS Rare Not discussed in Vendor specific Not stated 36 & 53 19

failure. Valve failure allowes cold water to report programs

flow back into primary system resulting

piping cracks.

Fail to start or run Rare Not discussed in Vendor specific Not stated 36 20

report programs

Lose of pipe supports stresses piping Rare Not discussed in Plant specific Not stated 36 21

leading to potential pipe failure and HPIS report program

failure. I

Valve failure to operate results in HPIS Rare Not discussed in Vendor specific Not stated 36 22

failure. report programs
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-4992 V1, Aging and Servcie Wear of Multistage Switches Used in Safety Systems of Nuclear Power Plants

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism

Page 23A

ARD effects

1 Multistage Switches General GE, Westinghouse,

Electro., Micro

2 Multistage Switches Cam Shaft Steel, Al, brass GE, Westinghouse, EXFORCE, WEAR Bent or twisted shaft

Electro., Micro

3 Multistage Switches Cam Shaft Steel, Al, brass GE, Westinghouse, MECHSTR, WEAR Broken camshaft

Electro., Micro

4 Multistage Switches Contacts Silver or silver alloy GE, Westinghouse, CORR, FAT, Broken or distorted

Electro., Micro FAT/THERM, VIBR, contact, sticking,

CONTAM, loose contact

ELETEMP, WEAR

5 Multistage Switches Contacts Silver or silver alloy GE, Westinghouse, ELETEMP, Pitted, worn, or

Electro., Micro CURSTR, VOLSTR, welded contact

6 Multistage Switches Contact Block Phenolic GE, Westinghouse, VIBR Loose contact bank

Electro., Micro

7 Multistage Switches Moving Contact Steel, Al, brass GE, Westinghouse, FAT Spring breaks

Spring Electro., Micro

8 Multistage Switches Moving contact Not stated GE, Westinghouse, FAT Gear breaks

Assembly Electro., Micro

Multistage Switches Moving Contact Pin Not stated GE, Westinghouse, ELETEMP, FAT, Pin breaks

Electro., Micro THERM-CY

10 Multistage Switches Cams Polyphenylene oxide, GE, Westinghouse, ELETEMP, RAD, Closing or opening

acetal, phenolic Electro., Micro THERM-CY, WEAR cam failure

11 Multistage Switches Cam Follower Polycarbonate GE, Westinghouse, ELETEMP, RAD, Broken or warped

Electro., Micro VIBR follower

12 Multistage Switches Cam Follower Polycarbonate GE, Westinghouse, WEAR Slipping of cam

Electro., Micro follower

13 Multistage Switches Switch Handle Polycarbonate GE, Westinghouse, VIBR Broken or loose set

Electro., Micro screws

14 Multistage Switches Shaft Bearings Not stated GE, Westinghouse, LOSLUB, WEAR, Bearing freezes up

Electro., Micro CONTAM

15 Multistage Switches Gear Not stated GE, Westinghouse, FAT, WEAR Gear failure

Electro., Micro

16 Multistage Switches Detent Mechanism Steel, Al, brass, GE, Westinghouse, FAT, WEAR Wom detent

vulcanized fiber Electro., Micro mechanism, loose

detent roller pin

17 Multistage Switches Detent Stop Arm Steel, Al, brass GE, Westinghouse, EXFORCE Bent stop arm

Electro., Micro
Table A.2 Gall Report for NPAR Reports Page 23B

Document: NUREG/CR-4992 V1, Aging and Servcie Wear of Multistage Switches Used in Safety Systems of Nuclear Power Plants

Reviewed by: Jerry Edson, INEL

Effect of Aaina on Comeonent Function Contrib to Failure Reported progs Rel.proas Report Recommendations Paqe No. Item

Not stated Not discussed in No Operators provide feedback on 2,10, 52 1

report specific/vendor problems, failures should be

specific analyzed,no further consideraton by

programs NPAR [2]

Bent or twisted shaft causes incorrect Not stated General - none No Not stated 2,10,, 31- 2

contact alignment and failure to operate specifically for specific/vendor 37, 41-44,

as required switches specific 52

programs

Switch will not change state resulting in Not stated General - none No Not stated 2,10, 31- 3

failure to operate specifically for specifictvendor 37, 41-44,

switches specific 52

programs

Contacts do not close or change state, Frequent General - none No Not stated 2,10, 31- 4

open or short circuit, high electrical specifically for specific/vendor 37, 41-44,

resistnace resulting in failure to operate switches specific 52

programs

High contact resistance resulting in failure Frequent General - none No Not stated 2,10, 31- 5

to operate as required specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Contacts do not mate properly resulting in Not stated General - none No Not stated 2, 10, 31- 6

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

No positive return of cam followers, Not stated General - none No Not stated 2, 10, 31- 7

contacts may open or close randomly specifically for specifictvendor 37, 41-44,

resulting in failure to operate switches specific 52

programs

Contacts to not change state resulting in Not stated General - none No Not stated 2, 10, 31- 8

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Contacts will tend to remain closed during Not stated General - none No Not stated 2,10, 31- 9

opening cam action resulting in failure to specifically for specific/vendor 37,41-44,

operate switches specific 52

programs

Contacts to not change state resulting in Not stated General - none No Not stated 2,10, 31- 10

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Contacts do not change state resulting in Not stated General - none No Not stated 2,10, 31- 11

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Incomplete contact closure resulting in Not stated General - none No Not stated 2,10, 31- 12

failure to operate as required specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Switch will not change state resulting in Not stated General - none No Not stated 2, 10, 31- 13

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Switch will not change state resulting in Not stated General - none No Not stated 2, 10, 31- 14

failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

Switch will not maintain position resulting Not stated General - none No Not stated 2,10, 31- 15

in failure to operate specifically for specific/vendor 37, 41-44,

switches specific 52

programs

False indication of position change, Frequent General - none No Not stated 2,10, 31- 16

contacts do no properly line up resulting in specifically for specific/vendor 37, 41-44,

failure to operate as required switches specific 52

programs

Overtravel of cams at end stop resulting in Not stated General - none No Not stated 2,10, 31- 17

failure to operate as required specifically for specific/vendor 37, 41-44,

switches specific 52

programs
Table A.2 Gall Report for NPAR Reports Page 24A

Document: NUREG/CR-5008, Development of A Testing and Analysis Methodology to Determine the Functional Condition of Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomoonent Materials Manufacturer ARD mechanism ARD effects

Solenoid Valves General Not stated

2 Solenoid Valves Spring Not stated Not stated Not stated Weakened spring

3 Solenoid Valves Valve Seat Not stated Not stated CONTAM Not stated

4 Solenoid Valves Plunger Not stated Not stated Not stated Sticking plunger

Document: NUREG/CR-5051, Detecting and Mitigating Battery Charger and Inverter Aging

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Inverter Automatic Transfer Not stated Not stated ELETEMP & Degraded

Switch (Two Pairs of CURSTR component or burn

SCR's) out

2 Battery Electrolytic Not stated Not stated ELETEMP Reduced capacitor

Capacitors life

3 Battery Semi-Conductors Not stated VIB, THERM, & Vibration loosens

CURSTR connections & heat

degrades operation

4 Battery Magnetics - High permeability Not stated ELETEMP AND Aging degradation

Transformers alloys, copper CURSTR resulting from over

windings, & heating & elec.

insulation stress

5 Battery Complete Assembly Enclosures and Seven listed ELETEMP & Overheating &

electrical CURSTR, electrical transients

components from stresses

Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Canters

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Motor Control Center General

Motor Control Center Molded Case Circuit Lubr., adhes., Not stated FAT, WEAR, Mech. stress,

Breakers neoprene, silicone, CONTAM, CORR, sticking, surface

polyester, phenolic, CORR/PIT, deterioration, low

rubber, silver alloy, torque

copper, stainless

steel

3 Motor Control Center Molded Case Circuit Lubr., adhes., Not stated WEAR, Out of adjustment,

Breakers neoprene, silicone, defective latch,

polyester, phenolic, short/ground,

rubber, silver alloy, stresses

copper, stainless

steel

4 Motor Control Center Relay Phenolic, vulcanized Not stated ELETEMP, CORR, Breakdown of

rubber, silver alloy, CORR/PIT insulation, contact

copper, steel surface degradation

5 Motor Control Center Relay Phenolic, vulcanized Not stated CONTAM, CORR, Foreign matl

rubber, silver alloy, CORR/PIT, VIBR, accumulation,

copper, steel FAT surface degradation,

misalign.

6 Motor Control Center Relay Phenolic, vulcanized Not stated WEAR Out of calibration

rubber, silver alloy,

copper, steel

7 Motor Control Contel Transformer Phenolic, fiberglass,

copper wire, teflon

Not stated ELETEMP,

CURSTR, VOLSTR

Overheating,

deterioration and

breakdown of

insulation
Table A.2 Gall Report for NPAR Reports Page 24B

Document: NUREG/CR-5008, Development of A Testing and Analysis Methodology to Determine the Functional Condition of Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

This report is not an aging assessment of Not stated Not discussed in Vendor specific Explore alternative analytical 23 1

sovs. The report investigates testing and report programs techniques. Further develop and

analysis methodologies, validate coherency model [2]

Not stated Not stated Not discussed in Vendor specific Not stated 13 2

report programs

Not stated Not stated Not discussed in Vendor specific Not stated 13 3

report programs

Not stated Not stated Not discussed in Vendor specific Not stated 13 4

report programs

Document: NUREG/CR-5051, Detecting and Mitigating Battery Charger and Inverter Aging

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Inverter fails and vital bus loads are Not stated Not discussed in Vendor specific Not stated 3-15 TO 1

automatically transferred to alternate report programs 3-22

source if failure occurs.

Aging due to high temperature leads to Frequent Not discussed in Vendor specific Improve thermal efficiency by using 3-4 TO 3- 2

capacitor failure resulting in improper report programs forced air cooling. Manufacture 6

output. improvements such as adding a fuse

module. [2]

Aging due to local heat buildup results in Occasional Not discussed in Vendor specific Improved maintenance and testing 3-7, 4-13, 3

short circuit of the SCR and an inverter report programs done more often. [2] & 5-7

failure.

Transformer aging caused by over Not stated Not discussed in Vendor specific Improved maintenance and testing XIII, 1-6, 4

heating, electrical transients, and report programs done more often. [2] 3-9, & 5-6

personnel error results in charger/invertor

failure.

Electrolytic capacitors, fuses, magnetics Not stated Plant maintenance Vendor specific Establish a comprehensive XIII, 4-15, 5

(inductors and transformers) and programs maintenance program that & 7-4

semiconductors failure results in addresses inspection, testing,

charger/invertor failure. predictive and corrective

maintenance [2]

Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated IEEE 308,279,317; IEEE 308,279, Detailed survey of PM, surveillance 5-1 thru 5- 1

RG 1.106,1.63; 317; RG 1.106, techniques, and oper. exp. review 13, 6-5

NEMA; UL 1.63; NEMA; maintenance data. PRA to thru 6-7

UL determine importance [2]

Failure to open or failure to close Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 2

RG 1.106,1.63; 317; RG 1.106, 4-20,4-

NEMA; UL 1.63; NEMA; 21,5-1

UL thru 5-13

Inadvertent trip, failure to trip Occasional to IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 3

Frequent RG 1.106,1.63; 317; RG 1.106, 4-20, 4-

NEMA; UL 1.63; NEMA; 21,5-1

UL thru 5-13

Open circuits Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, .4

RG 1.106,1.63; 317; RG 1.106, 4-20,4-

NEMA; UL 1.63; NEMA; 21,5-1

UL thru 5-13

Failure to open or failure to close Occasional IEEE 308,279,317; IEEE 308,279, Not stated 3-4, 4-6, 5

RG 1.106,1.63; 317; RG 1.106, 4-20,4-

NEMA; UL 1.63; NEMA; 21,5-1

_ UL thru 5-13

Response on incorrect signal Frequent IEEE 308,279,317; IEEE 308,279, Not stated 3-4, 4-6, 6

RG 1.106,1.63; 317; RG 1.106, 4-20, 4-

NEMA; UL 1.63; NEMA; 21,5-1

UL thru 5-13

Open or short circuits Occasional IEEE 308,279,317;

RG 1.106,1.63;

NEMA; UL

IEEE 308, 279,

317; RG 1.106,

1.63; NEMA; UL

Not stated 3-4, 4-6,

4-22, 5-1

thru 5-13

7
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers

Reviewed by: Jerry Edson, INEL

Item System StructureJComp Subcomponent Materials Manufacturer

Page 25A

ARD mechanism ARD effects

8 Motor Control Center TERMINAL BLOCK Phenolic Not stated VIBR, WEAR Mechanical stresses

9 Motor Control Center Terminal Block Phenolic Not stated ELETEMP Conduction paths

are formed

10 Motor Control Center Thermal Overloads Phenolic, silver Not stated ELETEMP, FAT Overheating

plating, copper,

vulcanized rubber

11 Motor Control Center Thermal Overloads Phenolic, silver Not stated CORR, CORR/PIT Surface degradation

plating, copper,

vulcanized rubber

12 Motor Control Center Thermal Overloads Phenolic, silver Not stated WEAR, CONTAM Out of calibration,

plating, copper, sticking

vulcanized rubber

13 Motor Control Center Starter/Contactor Lubricant, adhesive, Not stated FAT, CORR, Mech. stresses,

neoprene, silicone, CORR/PIT, surface degradation,

polyester, phenolic, CONTAM foreign substance

rubber, silver alloy,

coppper, stainless

steel

14 Motor Control Center Fuse Not stated Not stated Not stated Material degradation

causes open circuits

15 Motor Control Center Coils Phenolic, fiberglass, Not stated CURSTR Overcurrent causes

copper wire, teflon overheating and

insulation breakdowr

16 Motor Control Center Trip and Control Not stated Not stated Not stated Drifting of setpoint,

out of calibration

17 Motor Control Center Trip and Control Not stated Not stated CONTAM Degradation of

contact surfaces,

buildup of grease

and dirt

18 Motor Control Center Cabinets Steel Not stated Not stated Not stated

Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 SOV - ASCO Coils Elastomers ASCO MOIST-EL, Decreased insulatior

ELETEMP and coil resistance

2 SOV - ASCO Core Disc Buna-N, EPDM ASCO ELETEMP, RAD Hardening,

decreased

elongation

SOV - ASCO Seat Buna-N and nylon ASCO ELETEMP, RAD Hardening,

metal and EP decreased

elongation

4 SOV - ASCO Body O-Rings Buna-N, EPDM ASCO ELETEMP, RAD Hardening,

decreased

elongation
Table A.2 Gall Report for NPAR Reports Page 25B

Document: NUREG/CR-5053, Operating Experience and Aging Assessment of Motor Control Centers

Reviewed by: Jerry Edson, INEL

Effect of Aaina on Comlbonent Function Contrib to Failure Retnorted nroos Rel.oroas Reoort Recommendations Pace No. Item

Poor connection/open circuit Occasional IEEE 308,279,317; IEEE 308,279, Not stated 3-4, 4-6, 8

RG 1.106,1.63; 317; RG 1.106, 4-22, 5-1

NEMA; UL 1.63; NEMA; thru 5-13

UL

Ground/short Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 9

RG 1.106,1.63; 317; RG 1.106, 4-22, 5-1

NEMA; UL 1.63; NEMA; thru 5-13

UL

Open circuit Frequent IEEE 308,279,317; IEEE 308,279, Not stated 3-4, 4-6, 10

RG 1.106,1.63; 317; RG 1.106, 4-23,4-

NEMA; UL 1.63; NEMA; 24, 5-1

UL thru 5-13

Would not operate Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 11

RG 1.106,1.63; 317; RG 1.106, 4-23,4-

NEMA; UL 1.63; NEMA; 24,5-1

UL thru 5-13

Tripped and response on incorrect signal Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 12

RG 1.106,1.63; 317; RG 1.106, 4-23,4-

NEMA; UL 1.63; NEMA; 24, 5-1

UL thru 5-13

Failure to open or close Frequent IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 4-6, 15

RG 1.106,1.63; 317; RG 1.106, 4-23,4-

NEMA; UL 1.63; NEMA; 24, 5-1

UL thru 5-13

Premature operation Frequent IEEE 308,279,317; IEEE 308,279, Not stated 4-6, 4-23, 14

RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5-

NEMA; UL 1.63; NEMA; 13

UL

Open circuit, short/ground Occasional IEEE 308,279,317; IEEE 308,279, Not stated 3-4, 4-6, 15

RG 1.106,1.63; 317; RG 1.106, 4-24, 5-1

NEMA; UL 1.63; NEMA; thru 5-13

UL I

Response on incorrect signal Occasional IEEE 308,279,317; IEEE 308, 279, Not stated 4-6, 4-24, 16

RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5

NEMA; UL 1.63; NEMA; 13

UL

Sticking and material degradation result in Rare IEEE 308,279,317; IEEE 308, 279, Not stated 4-6, 4-24, 17

faure to operate RG 1.106,1.63; 317; RG 1.106, 5-1 thru 5-

NEMA; UL 1.63; NEMA; 13

UL I

Not stated Not stated IEEE 308,279,317; IEEE 308, 279, Not stated 3-4, 5-1 1

RG 1.106,1.63; 317; RG 1.106, thru 5-13

NEMA; UL 1.63; NEMA;

UL

Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Water enters during MSLB/LOCA Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 9, 28- 1

conditions. Failure to operate report if EQ'd, plant 31, 41-48,

specific 75-78

programs

Leakage Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 9, 28- 2

report if EQ'd, plant 31, 73,

specific 75-78

programs

Leakage. Laquer like organic deposits Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 9, 28- 3

surrounding the metal to metal seats report if EQ'd, plant 31,75-78

caused failure to transfer. specific

programs

Failure to transfer Frequent Not discussed in

report

10 CFR 50.49

if EQ'd, plant

specific

programs

Not stated 6-7, 9, 28-

31,74,

75-78

4
Table A.2 Gall Report for NPAR Reports Page 26A

Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

5 SOV - ASCO Housings, Washers, Not stated ASCO Not stated Not stated

Core Spring,

Gaskets

6 SOV - VALCOR Coils Elastomers Valcor MOIST-EL, Decreased coil and

ELETEMP insulation resistance

7 SOV - VALCOR Seats EPR Valcor ELETEMP, RAD Hardening and

decreased

elongation

8 SOV - VALCOR Shaft Seal O-Ring EPR Valcor ELETEMP, RAD Hardening and

decreased

elongation

9 SOV - VALCOR Upper Assembly EPR Valcor ELETEMP, RAD Hardening and

Seal O-Ring decreased

elongation

10 SOV - VALCOR Shaft, Cage, Ports Not stated Valcor Not stated Not stated

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System

Reviewed by: Jerry Edson, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 1E Power General

2 1 E Power Transformer General

3 1 E Power Transformer Insulating Oil Mineral oil, systhetic Not stated MOIST-EL, Degraded insulation

chlorinated aromatic ELETEMP value

hydrocarbon

4 1 E Power Transformer Core (Magnetic Copper, aluminum, Not stated FAT, ELETEMP Magnetic core

Circuit and silicon steel, deformation

Windings) cellulose, phenolics,

fiberglass, varnish,

epoxy

5 1 E Power Transformer Core (Magnetic Copper, aluminum, Not stated ELETEMP, VIBR, Arcing, hot spots,

Circuit and silicon steel, MOIST-EL, winding insulation

Windings) cellulose, phenolics, VOLSTR, CURSTR, degradation

fiberglass, varnish, CORR/OX

epoxy

6 1 E Power Transformer Case (Tank) Structural steel, Not stated FAT Failure of tank

paints welds, moisture seal

cracking

7 1 E Power Transformer Insulating Gas Nitrogen, air, Not stated MOIST-EL Insulation

flourocarbon breakdown

8 1 E Power Transformer Core (Magnetic Copper, aluminum, Not stated FAT, ELETEMP Magnetic core

Circuit and silicon steel, deformation

Windings) cellulose, phenolics,

figerglass, varnish,

epoxy

9 1 E Power Transformer Core (Magnetic Copper, aluminum, Not stated MOIST-EL, Arcing, hot spots,

Circuit and silicon steel, ELETEMP, winding insulation

Windings) cellulose, phenolics, CORR/OX, degradation

figerglass, varnish, CURSTR, VIBR,

epoxy VOLSTR

101 E- Power Transformer case (Tank) Structural steel,

paint

Not stated FAT Failure of tank

welds, moisture seal

cracking
Table A.2 Gall Report for NPAR Reports Page 26B

Document: NUREG/CR-5141, Aging and Qualification Research on Solenoid Operated Valves

Reviewed by: Jerry Edson, INEL IFffect of Aninin on •nmh~nnmnt F..rHtnn ir, ':nntrih to F~I:ihm I~l•nortL~d nrons; Rel.rnroas Renort Recommendations PaeN.Item .... .. ' " ,...... ~ r ..... " .. . . ..... - - -. -.....-- - - ... r'-r . . ..- - .. - . --..-.. ....... ... Not stated Not stated Not discussed in 10 CFR 50.49 Not stated 9 5

report if EQ'd, plant

specific

programs

Water enters during MSLB/LOCA Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 11, 6

conditions. Failure to operate report if EQ'd, plant 20-28, 41-

specific 48, 75-78

programs

Not stated Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 11, 7

report if EQ'd, plant 20-28, 41-

specific 48, 75-78

programs

O-rings adhered to the guide tube - Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 11, 8

caused sticking and failure to transfer report if EQ'd, plant 20-28, 41-

specific 48, 73-78

programs

O-rings adhered to seat - caused sticking Frequent Not discussed in 10 CFR 50.49 Not stated 6-7, 11, 9

and failure to transfer report if EQ'd, plant 20-28, 41-

specific 48, 73-78

programs

Not stated Not stated Not discussed in 10 CFR 50.49 Not stated 11 10

report if EQ'd, plant

specific

_programs I

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated RG 1.118, IEEE- RG 1.108, Eval. surveillance & monitoring 49, 51, 1

338, IEEE,943 1.118, 1.129; practices. Determine which 54,71

IEEE 338, 387, components contribute most to

450 system unavailability [4]

Not stated Representative plant Vendor specific Industry continue developing 66, 70 2

programs monitoring techniques. Transf. and

surge suppressor aging studies

should be performed [4]

Reduction in dielectric strength resulting Not stated Not discussed in Vendor specific Not stated 20, 21,22 3

in internal shorts and winding failures report programs

Vibration and excessive temperature Not stated Not discussed in Vendor specific Not stated 20, 21,22 4

cause the magnetic core circuit to report programs

become deformed and loosen and can

result in failure of the windings

Winding-to-winding short circuit, winding- Not stated Not discussed in Vendor specific Not stated 20, 21,22 5

to-case short circuit report programs

Leakage, moisture instrusion resulting in Not stated Not discussed in Vendor specific Not stated 21,22 6

degradation of the insulating oil report programs

Reduction in dielectric strength resulting Not stated Not discussed in Vendor specific Not stated 21,22 7

in internal shorts and winding failures report programs

Deformation and loosening of the Not stated Not discussed in Vendor specific Not stated 21,22 8

magnetic core resulting in winding failures report programs

Winding-to-winding short circuit, winding- Not stated Not discussed in Vendor specific Not stated 21,22 9

to-case short circuits report programs

Moisuture intrusion and leakage of the

gas coolantfinsulation resulting in failure

of the winding insulation

Not stated Not discussed in

report

Vendor specific

programs

Not stated 21,22 10
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System

Reviewed by: Jerry Edson, INEL

Item System StructurelComD SubcomDonent Materials

Page 27A

Manufacturer ARD mechanism ARD effects

11 1E Power Cable Insulation XLPE, EPR, silicon Not stated ELETEMP, RAD, Embrittlement of

or butyl rubber, MOIST-EL, insulation, treeing

Kapton, PE, PVC, AGRCHEM

teflon, CSP

12 1 E Power Cable Jacket CSP Not stated ELETEMP, RAD, Embrittlement of

MOIST-EL, insulation

AGRCHEM

13 1 E Power Connections and Not stated Not stated Not stated FAT Cracking

Terminations

14 1 E Power Electrical Cable Cable Clamp Stainless steel Not stated Not stated Not stated

15 1 E Power Electrical Cable Terminal Strip Glass filled phenolic Not stated Not stated Not stated

Assembly

16 1E Power Electrical Cable Shrink Tubing Polyolefin Not stated Not stated Not stated

17 1 E Power Electrical Cable Plug Sleeve and Bronze Not stated Not stated Not stated

Coupling Ring

18 1E Power Electrical Cable O-Ring Seal Elastomer Not stated Not stated Not stated

19 1 E Power Electrical Cable Contact Socket Copper Not stated Not stated Not stated

20 1 E Power Electrical Cable Interfacial Seal Dow Corning Not stated Not stated Cracking

Sylgard

21 1 E Power Electrical Cable Insulator, Plug Skirt Polysulfone Not stated Not stated Cracking

22 1 E Power Electrical Cable Washer Stainless steel Not stated Not stated Not stated

23 1 E Power Electrical Cable Module Assembly Brass Not stated Not stated Not stated

24 1 E Power Circuit Breaker Insulation Polyester, glassfiber. Not stated ELETEMP Reduced insulation

filled epoxy resins, value

phenolic

25 1 E Power Circuit Breaker Contacts Silver alloy in copper Not stated CURSTR, VOLSTR Poor electrical

base contact

26 1 E Power Circuit Breaker Arc Chutes Not stated Not stated ELETEMP Structural damage to

the arc chutes

27 1 E Power Circuit Breaker Overload Not stated Not stated ELETEMP Reduced overload

Mechanism rating

28 1 E Power Circuit Breaker Connections Not stated Not stated VIBR Loose connections

L29 1 E Power Circuit Breaker Lubricant Not stated Not stated ELETEMP, Hardening of the

AGRCHEM, lubricant

CONTAM

301 E Power Circuit Breaker Frame Painted or Not stated Not stated Not stated

electroplated steel
Table A.2 Gall Report for NPAR Reports Page 27B

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System

Reviewed by: Jerry Edson, INEL Effect of Aaina on Corn onent Function Contrib to Failure Reoorted oroos Rel.Droas Report Recommendations Paae No. Item

Embrittlement results in cracking which Occasional Not discussed in No specific Not stated 22,-23, 11

permits moisture to enter and result in report program 25, 41

conductor-to-conductor and conductor-toground shorts. Treeing results in

conductor-to-conductor and conductor-toground shorts

Embrittlement results in cracking and Occasional Not discussed in No specific Not stated 22, 23, 12

moisture instrusion report program 25, 41

Not stated Not stated Not discussed in Plant specific Not stated 23,24 13

report progarms

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 22,25, 14

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 15

Vendor specific 49, 56

_ programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 16

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 17

Vendor specific 49, 56

programs

Pressure leak Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 18

Vendor specific 49, 56

_ programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 19

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 20

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 21

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 22

Vendor specific 49, 56

programs

Not stated Not stated RG 1.63, IEEE-317 10 CFR 50.49, Not stated 24,25, 23

Vendor specific 49, 56

_ programs

Excessive temperature caused by poor Not stated Not discussed in ANSI/IEEE Not stated 25, 26,27 24

contact, large currents, or elevated report 741-1986

environment degrades the insulation Section 7,

resulting in shorts and arcing vendor specific

Degraded/poor contacts result in Not stated Not discussed in ANSI/IEEE Not stated 25, 26,27 25

degraded or open circuits report 741-1986

Section 7,

vendor specific I

Flashover/arcing, failure to extinguish the Not stated Not discussed in ANSI/IEEE Not stated 25, 26,27 26

arc report 741-1986

Section 7,

vendor specific

Premature trip at low current Not stated Not discussed in ANSI/IEEE Not stated 25,26,27 27

report 741-1986

Section 7,

vendor specific

Improper operation and open circuits Not stated Not discussed in ANSI/IEEE Not stated 25, 26,27 28

report 741-1986

Section 7, vendor specific

Improper operation, failure to open or Not stated Not discussed in ANSI/IEEE Not stated 25, 26, 27 2Zc

close report 741-1986

Section 7,

vendor specific

Not stated Not stated Not discussed in

report

ANSI/IEEE

741-1986

Section 7,

vendor soecific

Not stated 25, 26, 27 3C
Table A.2 Gall Report for NPAR Reports Page 28A

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1E Power System

Reviewed by:

Item System

Jerry Edson, INEL

Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

31 1 E Power Circuit Breaker Housing, Doors Painted sheet steel Not stated Not stated Not stated

32 1 E Power Circuit Breaker Mechanisms Cast bronze and Not stated CORR, AGRCHEM, Reduced force,

steel, stamped steel WEAR, VIBR, FAT, increased friction,

CONTAM embrittled mat.

33 1 E Power Relays Coil Insulation Not stated Not stated VOLSTR, Reduced insulation

ELETEMP value

1 E Power Relays Moving Parts Not stated Not stated WEAR, FAT Increased friction,

binding

35 1 E Power Relays Contacts Not stated Not stated WEAR, CORR, Poor electrical

VIBR, CONTAM contact

36 1 E Power Relays Connections Not stated Not stated VIBR, ELETEMP Loose or poor

electrical

connections

37 1 E Power Relays Coil Bobbin Not stated Not stated ELETEMP Accelerate aging

38 1 E Power Chargers and Circuit Breaker Not stated Not stated CONTAM, Increased friction,

Inverters LOSLUB, WEAR, binding, loss of

CORR/PIT continuity

39 1 E Power Chargers and Fuse Not stated Not stated THERM-CY, FAT Metal fatigue,

Inverters melting of link

40 1 E Power Chargers and Relay Not stated Not stated CORR/PIT, Loss of continuity

Inverters CORR/OX

41 1 E Power Chargers and Electrolytic Not stated Not stated ELETEMP, VIBR Loss of electrolyte,

Inverters Capacitors failure of leads

42 1 E Power Chargers and Oil Filled Capacitors Not stated Not stated ELETEMP, VIBR Dielectric

Inverters breakdown, failure o

leads

43 1 E Power Chargers and Magnetics Not stated Not stated ELETEMP, LOW Degraded insulation,

Inverters (Transformer, TEMP, VOLSTR, cracked moisture

Inductor) VIBR seals, broken wires

44 1 E Power Chargers and Silicon Controlled Not stated Not stated ELETEMP Over voltage or over

Inverters Rectifiers current caused by

transients

45 1 E Power Chargers and Resistor Not stated Not stated VIBR, ELETEMP Decrease in

Inverters resistance, lead falls

46 IE Power Chargers and

Inverters

Printed Circuit

Boards

Not stated Not stated TEMP, THERM-CY,

CORR, VIBR

Cracking of circuit

lines, open circuits,

loose connections
Table A.2 Gall Report for NPAR Reports Page 28B

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1 E Power System

Reviewed by: Jerry Edson, INEL Effect of Aaina on Comoonent Function Contrib to Failure Reported nroas ReI.nron~ Renort Reconimendation~ Pane No. Item

Not stated Not stated Not discussed in ANSI/IEEE Not stated 25, 26, 27 31

report 741-1986

Section 7, _ vendor specific

Improper operation, failure to oper or Not stated Not discussed in ANSI/IEEE Not stated 25, 26, 27 32

close report 741-1986

Section 7,

vendor specific

Excessive temperture from ohmic heating Not stated Not discussed in RG 1.118, Not stated 25,26, 33

or the environment causes insulation report IEEE 338-1987 27, 28

failure and results in failure of the relay to

operate

Misopertion, failure to operte, slow or Not stated Not discussed in RG 1.118, Not stated 25, 26, 34

sluggish operation, inadvertant contact report IEEE 338-1987 27, 28

closure

Open circuit, failure to close, arcing, Not stated Not discussed in RG 1.118, Not stated 25,26, 35

increased temperature due to ohmic report IEEE 338-1987 27,28

heating

Open circuit heating at the socket/pin Not stated Not discussed in RG 1.118, Not stated 25,26, 36

interface report IEEE 338-1987 27,28

Coil failure Not stated Not discussed in RG 1.118, Not stated 25, 26, 37

report IEEE 338-1987 27,28

Failure to operate, failure to open Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 38

PE5, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

1944,

Fails open (opens prematurely) Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 39

PE5, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

_944,

Open circuit or coil, contacts open Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 40

PE5, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Loss of capacitance or open circuit Frequent IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 41

causes the chargerfinverter to have PE5, IEC 146-2, NEMA PE5, 60-64

improper output ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Loss of capacitance or open circuit Frequent IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 42

causes the charger/inverter to have PE5, IEC 146-2, NEMA PES, 60-64

improper output ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Failure of device due to short circuit (turn- Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 43

to-tum or turn-to-ground) or change in PE5, IEC 146-2, NEMA PE5, 60-64

inductance ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Failure of device due to open or short Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 44

circuits PE5, IEC 146-2, NEMA PES, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Failure of device due to open circuit or Rare IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 45

change in value of resistor PE5, IEC 146-2, NEMA PES, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Item

Output changes from desired value Frequent IEEE-446, NEMA

PE5, IEC 146-2,

ANSI/IEEE-944

IEEE 446,

NEMA PE5,

IEC 146-2,

ANSI/IEEE

944,

Not stated 29-36, 55,

60-64

46
Table A.2 Gall Report for NPAR Reports

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1 E Power System

Reviewed by: Jerry Edson, INEL

Page 29A

Item Strruet~re/Cnmn Sub~nmnonent Mnt~ri~l•

47 1 E Power Chargers and Surge Suppressor Not stated Not stated VOLSTR, CURSTR Semiconductor

Inverters breakdown

48 1 E Power Chargers and Connections Not stated Not stated MECHSTR Fatigue failure of

Inverters wire at terminals

49 1 E Power Chargers and Meters Not stated Not stated CONTAM Increase in bearing

Inverters friction

50 1 E Power Chargers and Switch Not stated Not stated CORR, CORR/PIT Loss of continuity

Inverters across contacts

51 1 E Power Chargers and Potentiometer Not stated Not stated ELETEMP Loss of continuity

Inverters

52 1 E Power Batteries Grids/Plates Lead-calcium alloy Not stated OVERCHG, Accelerates

ELETEMP, corrosion and

CONTAM oxidation

53 1 E Power Batteries Active Material Lead cdioxde and Not stated GAS Dislodges active

lead sulfate material

54 1 E Power Batteries Separator Rubber/glass matt Not stated ELETEMP Accelerates

deterioration of

electrical insulation

55 1 E Power Batteries Electrolyte Sulfuric acid and Not stated CONTAM Hydrolysis of the

water water and loss of

electrolyte

56 1 E Power Batteries Vent Fused alumina Not stated MECHSTR Vent breaks allowing

contamination to

enter

57 1 E Power Batteries Top Connectors Lead-calcium alloy Not stated ELETEMP, CORR, Low electrolyte level

EMBR causes corrosion

and embrittlement

58 1 E Power Batteries Terminals Lead-calcium alloy Not stated CORR/OX, CORR Poor electrical

contact with external

busses

59 1 E Power Batteries Container and Top Polycarbonate, Not stated MECHSTR, Oxidation of lead

Cover styrene acryolonitrile, CORR/OX causes plate growth

acrylo-butadiene

I styrene

Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Inverter Resistors Carbon conposition Not stated ELETEMP & MOIST Ohms decrease -

temperature, & ohm.

increase - moisture

2 Inverter Wire Not stated Not stated Not stated Turns contact
Table A.2 Gall Report for NPAR Reports Page 29B

Document: NUREG/CR-5181, Nuclear Plant Aging Research: The 1 E Power System

Reviewed by: Jerry Edson, INEL

Effect of Aqinq on ComDonent Function Contrib to Failure Reported roeas Rel.nroas Report Recommendations Pace No. Item

Semiconductor breakdown due to Rare IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 47

overheating causes short circuits and PE5, IEC 146-2, NEMA PE5, 60-64

improper output ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Improper output due to open or short Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 48

circuits PE5, IEC 146-2, NEMA PES, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE

944,

Improper indication Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 49

PE5, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE 944

Improper output due to switch failing open Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 50

or closed PES, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE 944

Improper output due to open or short Occasional IEEE-446, NEMA IEEE 446, Not stated 29-36, 55, 51

circuit PE5, IEC 146-2, NEMA PE5, 60-64

ANSI/IEEE-944 IEC 146-2,

ANSI/IEEE 944

Corrosion/oxidation causes plate growth Frequent RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 52

resulting in reduced capacity and stresses IEEE 450- 36, 37,

the container 1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Dislodging active material from the plates Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 53

causes loss of capacity IEEE 450- 36, 37,

1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Loss of electrical insulation between Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 54

plates causes short circuits and loss of IEEE 450- 36, 37,

capacity 1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Loss of electrolyte results in loss of Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 55

capacity IEEE 450- 36, 37,

1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Contaminates in the electrolyte result in Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 56

reduced capacity IEEE 450- 36, 37,

1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Embrittled top conductors are susceptible Frequent RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 57

to breaking and causes loss of capacity IEEE 450- 36, 37,

1987, Tech 38, 50,

_Spec Surveil. _54, 62-65

Poor electrical contact results in loss of Not stated RG 1.129, IEEE-450 RG 1.129, Not stated 30,31, 58

capacity and may result in total battery IEEE 450- 36, 37,

failure 1987, Tech 38, 50,

Spec Surveil. 54, 62-65

Plate growth and handling stresses Frequent RG 1.129, IEEE-450 RG 1.129, Not stated 30, 31, 59

results in cracked containers which allow IEEE 450- 36, 37,

electrolyte to escape resulting in reduced 1987, Tech 38, 50,

capacity or total failure Spec Surveil. 54, 62-65

Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Resistance change causes improper Not stated Not discussed in Vendor Individual fusing of filter capacitors 3-23 1

output. report specific, Tech. to preclude a capacitor failure in the

Spec., IEEE short circuit mode [2]

446, NEMA

When turns of wire in resisor make

contact it decreases total resistance of

resistor resulting in improper output.

Not stated Not discussed in

report

Vendor

specific, Tech.

Spec., IEEE

446, NEMA

Not stated 3-23 2
Table A.2 Gall Report for NPAR Reports Page 30A

Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger

Reviewed by: L. C. Meyer, INEL Item Svstem StruictureJCnmn Subc~omnonent Materinlk Manufacturer ARD meichanism ARD effects

3 Inverter Electrolytic Not stated Not stated Not stated Capacitance

Capacitors decreases with age

4 Inverter Ceramic Capacitor Not stated Not stated Not stated Unstable

capacitance value

5 Inverter Silicon Controlled Silicon Not stated ELETEMP Deterioration of the

Rectifiers thermal joint

compound

6 Inverter Various Electrical Not stated Not stated Not stated No aging effects

Components noted for 12 year old

equipment

7 Battery Various Electrical Not stated Not stated Not stated No aging effects

Components noted for 12 year old

equipment

Document: NUREG/CR-5280 V1, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 DS-206/DS-416 Power Operated Spring steel Westinghouse WEAR, LOSLUB, Wear out, loss of

Circuit Breakers Mechanisms CORR/UA material, friction, &

corr product buildup

2 DS-206/DS-416 Contacts Contacts mounted Westinghouse WEAR, CURSTR, & Wear from

Circuit Breakers on high strenght CORR/UA operation, pitting, &

insulating base and erosion from arcs

steel arm

DS-206/DS-416 Arc Chutes Steel and arc Westinghouse WEAR, & CURSTR Erosion & burned

Circuit Breakers resisting plastic splitter plates

plates

4 DS-206/DS-416 Amptector Trip Unit Not stated Westinghouse VIB, CURSTR, & Loose parts,

Circuit Breakers (Electronic VOLSTR component burn out

Components) or degraded

operation

DS-206/DS-416 Current Magnitude Current transformers Westinghouse CURSTR, & Dielectric properties

Circuit Breakers and Direction VOLSTR degraded from

Sensors electrical stresses

6 DS-206/DS-416 Optional Electro-mechanical Westinghouse VIB, CURSTR, & Not stated

Circuit Breakers Accessories devices, switch, and VOLSTR

solid state device

7 DS-206/DS-416 Electrical and Not stated Westinghouse VIB, CURSTR, Coil burnings,

Circuit Breakers Mechanical VOLSTR, LOSLUB, binding of linkage,

Components in & WEAR wear, overheating, &

General dust

Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers (Mechanical Cycling)

Reviewed by: L C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

DS-416 Breaker/480 Structural Steel Westinghouse VIB & CORR Vibration will loosen

V Components parts, corrosion

I1 'I i____Idegrades metals

2 DS-416 Breaker/480

V

Contact Assembly Insulating material

and stainless steel

Westinghouse WEAR & CURSTR Wear & loss of

material from arcing.
Table A.2 Gall Report for NPAR Reports Page 30B

Document: NUREG/CR-5192, Testing of A Naturally Aged Nuclear Power Plant Inverter and Battery Charger

Reviewed by: L. C. Meyer, INEL

Effect nf Aainn on Comnongent F,.netinn (Cnntrih tn Fnilure Reporvted nrna• ReI.nroos Renio irt Recommendations Paaes No. Item

Distortion of signals to SCRs may result Not stated Not discussed in Vendor Not stated 3-23 3

in improper putput. report specific, Tech.

Spec., IEEE

446, NEMA

Not stated Not stated Not discussed in Vendor Not stated 3-23 4

report specific, Tech.

Spec., IEEE

446, NEMA

Over heating of SCRs may result in SCR Not stated Not discussed in Vendor Not stated 4-1 5

failure and loss of output. report specific, Tech.

Spec., IEEE

446, NEMA

None Not stated Not discussed in Vendor Not stated 4-3 6

report specific, Tech.

Spec., IEEE

1_ 1 1446, NEMA I

None. Not stated Not discussed in Vendor specific Not stated 3-1, 4-1, 7

report progarm, Tech. & 4-3

I__ _ _ I___ _Spec. Surveil.

Document: NUREG/CR-5280 V1, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Excessive force or rubbing causes Occasional Not discussed in Vendor specific Twelve recommendations given 2-7, 6-2, 1

distortion & wear out, rust on pivotal parts report , IEEE 741- relating to three separate issues & 7-4

& trip gears can cause hang up, hardened 1986 Section 7 covering reliability, pole shaft welds,

or improper lubricants or lubricant and maintenance. [2]

application can cause sluggish operation.

Contacts wear from repeated operations, Occasional Maintenance per Vendor specific Filing or dressing with abrasive cloth 2-9, 6-2, 2

arcing causes pitting, contacts become owners group MPM , IEEE 741- is not recommended [2] & 7-6

mottled, dirty, and eroded due to arc WORGTSDS416 1986 Section 7

burning. Contacts over heat from

resistance due to weak springs.

Slots in arc chute gradually erode with arc Frequent Maintenance per Vendor specific Life of the DS-16 breaker should be 2-9, 6-3, 3

interruptions, fault currents cause heavy owners group MPM , IEEE 741- 5000 cycles or 20 years. [2] & 7-6

erosion, and throat of the arc chute WORGTSDS416 1986 Section 7

enclosure becomes bumed and coated

with soot from arc interruptions.

Vibration may loosen parts, voltage and Occasional Maintenance per Vendor specific Life of the DS-16 breaker should be 2-9, 6-3, 4

current stress may cause part bum out or owners group MPM , IEEE 741- 5000 cycles or 20 years. [2] & 7-6

insulation damage. Electrical stress WORGTSDS416 1986 Section 7

reduces dielectric properties I

Not stated Not stated Maintenance per Vendor specific Not stated 2-12 5

owner'sgroup MPM , IEEE 741-

WORGTSDS416 1986 Section 7

Not stated Not stated Maintenance per Vendor specific Not stated 2-12 & 2- 6

owner's group MPM , IEEE 741- 13

WORGTSDS416 1986 Section 7

Most breaker problems result from control Occasional Owner's group Vendor specific Twelve recommendations given 2-1, 7-1, 7

problems involving contacts, coil recommended , IEEE 741- related to reliability, weld failures, & 7-4.

bumings, and trip device bindings, maintenance 1986 Section 7 and maintenance [2]

followed by operating mechanism

problems. Loss of lubrication, erosion of

contacts, burning of arc chutes, & loss of

acjustment are from aging

Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers (Mechanical Cycling)

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure to operate Rare Not discussed in Vendor specific Not stated 3-2 & &2

report IEEE 741-

I 1 1 11986 Section 7

Unreliable contact Not stated Not discussed in

report

Vendor specific

I IEEE 741-

1986 Section 7

Not stated 3-2 & 6-2 2
Table A.2 Gall Report for NPAR Reports Page 31A

Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers (Mechanical Cycling)

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 DS-416 Breakerl480 Power Operated Steel Westinghouse WEAR, FAT, & EX Wear, fracture, and

V Mechanism FORCE distortion.

4 DS-416 Breaker/480 Pole Shaft Steel Westinghouse FAT, & EX FORCE Cracking,

V misalignment, &

binding due to poor

welds

DS-416 Breaker/480 Charging System Steel, carbon brush Westinghouse WEAR, FAT, & Wear on moving

V (Rachet, Motor, in motor, insulation CURSTR parts & electric

Brushes, Oscillator., varnish on motor motor burn out

Spring) windings

6 DS-416 Breaker/480 Electrical Coils Not stated Westinghouse CURSTR Extended duration of

V (UVTA, STA, AND current flow caused

Closing Coil) burn out

DS-416 Breaker/480 Sensors, Amptector I Not stated Westinghouse Not stated Extended

V Trip Unit, & Arc energizatbon of coils.

Chutes

Document: NUREG/CR-5334, Severe Accident Testing of Electrical Penetration Assemblies

Reviewed by: L C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 D. G. O'Brien SEALS Silicon O-ring D. G. O'Brien ELETEMP, MOIST- Seal cracks and

Electrical EL, AND RAD moisture intrusion.

Penetration

2 D. G. O'Brien Electrical Not stated Not stated ELETEMP, MOIST- Moisture or

Electrical Components (Wire, EL, AND RAD contaminants

Penetration Insulation, and caused electrical

Connectors) shorts to ground

Westinghouse Seals Silcion O-ring Westinghouse ELETEMP, MOIST- Seal cracks and

Electrical EL, AND RAD moisture intrusion

Penetration

4 Westinghouse Electrical Not stated Westinghouse ELETEMP, MOIST- Insulation

Electrical Components (Wire, EL, AND RAD degradation

Penetration Insulation, and

Connectors)

CONAX Electrical Seals Viton O-rings Conax ELETEMP, MOIST- Seal cracks and

Penetration EL, AND RAD moisture intrusion

6 CONAX Electrical Electrical Not stated Conax THERM, MOIST- Embrittlement and

Penetration Components (Wire, EL, AND RAD cracking

Insulation, and

Connectors)

Document- NUREG/CR-5383, Effect of Aging on Response lime of Nuclear Plant Pressure Sensors

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Pressure Diaphragm Not stated Not stated VIBR FAT PRESS Deformation,

Transmitter cracking, and

hysteresis of diaphragm

2 Pressure Mechanical Unkages Not stated Not stated PRESS CORR Changes in system

Transmitter CORR/OX restoration ability

3 Pressure

Transmitter

Electronics

Seals Not stated Not stated EMBR Moisture on electronics
Table A.2 Gall Report for NPAR Reports Page 31B

Document: NUREG/CR-5280 V2, Age-Related Degradation of Westinghouse 480-Volt Circuit Breakers (Mechanical Cycling)

Reviewed by: L C. Meyer, INEL

E~ffect of Aa]inn on Comr,•nnnt FIinotion tontrib to Faiilure Renorted n~rons ReILnrons Rebort Recommendations Paaie No. Item .......... - o"'nt Function to r ..... r"ns . ... R"-o. . R commendations

Aging degradation in parts between the Occasional Not discussed in Vendor specific Monthly inspection and every 50 to 6-2 & 6-5 3

motor and the poles redistributes the force report , IEEE 741- 100 cycles inspect parts vulnerable

transmitted from the charging motor 1986 Section 7 to aging, maintenance & lubrication

causing large unbalanced stresses in at 250 cycles [2]

subcomponents & wear

Once cracks grow to a quarter the size of Not stated Not discussed in Vendor specific Monthly inspection and every 50 to 6-2 & 6-5 4

an effective weld the five levers report , IEEE 741- 100 cycles inspect parts vulnerable

connecting the pole contacts become 1986 Section 7 to aging, maintenance & lubrication

misaligned and caused excesssive at 250 cycles [2]

movement leading to fracture, binding and

other problems.

Wear of ratchet wheel, holding pauls, Not stated Not discussed in Vendor specific Assure design adequacy by 6-2, 6-4 5

motor crank, and handle dominated the report , IEEE 741- inspection, enhanced inspections

aging of the charging system. Carbon 1986 Section 7 and maintenance & install cycle

brushes needed frequent maintenance, counter. [2]

Sluggish operation, binding, failure to Freq when Not discussed in Vendor specific Assure design adequacy by 4-18 6

operate. mechanism binding report , IEEE 741- inspection, enhanced inspections

1986 Section 7 and maintenance & install cycle

I__ _counter. I_ [2] 1

Not stated Not stated Not discussed in Vendor specific Not stated 3-2 7

report , IEEE 741-

1986 Section 7

Document: NUREG/CR-5334, Severe Accident Testing of Electrical Penetration Assemblies

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Cracks in the seals from high temperature Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 4-1, 4-16, 1

and radiation allows moisture to leak into IEEE 323-1974 vendor specific leak potential is highly dependent on and 7-1

penetration resulting in electrical faults. DESIGN STD the temperatures to which the EPA

is subject [2]

Short to ground and electrical faults due Not stated IEEE 317-1976 AND 10 CFR 50.49, Not stated C-1, 4-16, 2

to moisture intrusion. IEEE 323-1974 vendor specific and 7-1

DESIGN STD

Seal cracks allow moisture intrusion into Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 1-3, 5-1, 3

penetration resulting in electrical faults. IEEE 323-1974 vendor specific leak potential is highly dependent on 5-15, and

DESIGN STD the temperatures to which the EPA 7-1

is subject. [2]

Decreased insulation resistance results in Rare IEEE 317-1976 AND 10 CFR 50.49, Not stated 4-1,4-16, 4

excessive leakage currents. IEEE 323-1974 vendor specific and 7-1

DESIGN STD

Seal cracks allow moisture intrusion Rare IEEE 317-1976 AND 10 CFR 50.49, Each design should be tested. The 6-1, 6-13, 5

resulting in electrical faults. IEEE 323-1974 vendor specific leak potential is highly dependent on and 7-1

DESIGN STD the temperatures to which the EPA

is subject. [2]

Electrical faults due to moisture intrusion Occasional IEEE 317-1976 AND 10 CFR 50.49, Look at types of cables and 6-1, 6-13, 6

through connectors. IEEE 323-1974 vendor specific connectors rather than penetration and 7-1

DESIGN STD design to improve future electrical

I__ _ _ __ __penetrations. [2] 1 1 1

Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Response time degradation for pressure Not stated RG 1.118, IEEE RG 1.118, Revise RG and standards to take 23,115 1

transmitter 338, & ISA Standard IEEE 338, into account recent advances in

67.06 Tech Spec testing technology and other

surveillance available information. [2]

Response time degradation for pressure Not stated RG 1.118, IEEE RG 1.118, Revise RG and standards to take 23,115 2

transmitter 338, & ISA Standard IEEE 338, into account recent advances in

67.06 Tech Spec testing technology and other

I I I I surveillance available information. [2]

Hesponse time degradation for pressure

Iansmitter

Not stated RG 1. 118, IEEE

338, & ISA Standard

67.06

RG 1.118,

IEEE 338, 10

CFR 50.49,

Tech Specs

Revise RG and standards to take

into account recent advances in

testing technology and other

available information. [2]

23, 115 S
Table A.2 Gall Report for NPAR Reports Page 32A

Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors

Reviewed by: E. W. Roberts, INEL

Item System StructureJComi, Subcomponent Materials Manufacturer ARD mechanism ARD effects

rPressure Electronic Not stated Not stated ELETEMP RAD Changes in value of

Transmitter Components MOIST-EL electronic

Electronics components

Document: NUREG/CR-5448, AGING EVALUATION OF CLASS 1E BATTERIES: SEISMIC TESTING

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Batteries Not stated Not stated SEISMIC Plate movement or

IT breakup

Document: NUREG/CR-5461, Aging of Cables, Connections, and Electrical Penetration Assemblies Used in Nuclear Power Plants

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

I Cable Insulation EPR, CSPE, EPDM, Ten manufactures MOIST-EL, Insulation

XLPE, silicon listed ELETEMP, AND degradation, short

rubber, butyl rubber, RAD and open circuits

polyethylene, and 13

others used less

often

2 Cable Jacket Neoprene, hypalon, Ten manufactures MOIST-EL, Jacket degradation,

XLPO, CSPE, & listed ELETEMP, AND cracks, and

CPE, RAD discoloration

3 Connections Terminal Blocks Phenolic with glass Seven listed ELETEMP, RAD, & Loose connections,

or cellulose filler with VIB cracks and short

metal terminals circuits

4 Connections Splices Crimp type ring lugs, Raychem ELETEMP, VIB, Loose connections

copper conductor, AND RAD and loss of dielectric

nylon or kynar isolation

insulation, and

Raychem heat

shrink tubing

Connections Coax Connectors Metal with organic Not stated ELETEMP AND Insulation

insulation such as RAD degradation

__ _teflon

6 Electrical Seal Material Steel tubes, seal Conax, O'Brien, and ELTEMP & RAD Seal leaks and

Penetrations materials are Westinghouse cracking

polysulfone, metalglass, and epoxy

7 Electrical Electrical Wire or Insulations (XLPE, Ten manufacturers ELETEMP AND Change in dieletric

Penetrations Cable EPR, EPDM & listed RAD properties,

Polymide) and embrittlement, and

jacket(CSPE, SPE, cracking

Hypalon, FR, and

I___ 1__ 1__ fiberglass) I I I

Document: NUREG/CR-5546, An Investigation of The Effects of Thermal Aging on the Fire Damageability of Electric Cables

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electrical Cables Insulation XPE, and interstitial Rockbestos ELETEMP Not stated

material (Nylon &

paper)

2 Electrical Cables Jacket Neoprene Rockbestos ELETEMP Embrittlement and

cracking

3 Electrical Cables Insulation EPR, and interstitial Boston Insulated ELETEMP Not stated

material (Nylon & Wire

paper)

4 Electrical Cables Jacket Hypalon Boston Insulated ELETEMP Embrittlement,

Wire dielectric loss and

forms cracks
Table A.2 Gall Report for NPAR Reports Page 32B

Document: NUREG/CR-5383, Effect of Aging on Response Time of Nuclear Plant Pressure Sensors

Reviewed by: E. W. Roberts, INEL

F~ffect af Aainna n Comnonent Funnction Contrib to Failure Reuorted nroan Rel.eroas Report Recommendations Paae No. Item

Effect. 9Response on Function... ro-f . .... r'-n _______ r --Falr_______ time degradation -RG for pressure Notstated RG 1.118, IEEE 1.118, e

transmitter 338, & ISA Standard IEEE 338, into account recent advances in

67.06 jTech Spec testing technology and other

_ _ surveillance available information. [2]

Document: NUREG/CR-5448, AGING EVALUATION OF CLASS 1E BATTERIES: SEISMIC TESTING

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

No effect on bat capability if maintained to Not stated IEEE STD 450, RG RG 1.129, Batteries not maintained per IEEE 35.

IEEE Std 450, RG 1.1.29 and MFG 1.129, & Mfg IEEE 450- 450, RG1.129, & MFG rec. need

recommendations recommendations 1987, Tech adv.monitoring tech. to determine

_____ Spec Surveil. seismic capability. [2]

Document: NUREG/CR-5461, Aging of Cables, Connections, and Electrical Penetration Assemblies Used in Nuclear Power Plants

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Thermal and radiation effects cause Not stated EQDB, IEEE 323- No specific Not stated 8,24, &

insulation degradation leading to cracking 1974 & IEEE 383- program 40

which allows moisture to intrude and then 1974 testing

shorts or current leakage results.

Jacket/insulation interaction effect was

also noted.

Thermal and radiation effects cause Not stated EQDB, IEEE 323- No specific Not stated 8, 24, & 2

jacket material degradation leading to 1974 & IEEE 383- program 40

cracking which allows moisture to intrude 1974 testing

into the insulation, jacket/insulation

interaction effect was also noted in the

sandia report.

Loss of dielectric isolation or loose Not stated Not discussed in Plant specific Not stated 11, 27, & 3

connections to disrupt a circuit, leakage report programs 41

paths through moisture films, and

insulation resistance decrease in presents

of steam.

Insulaton vulnerable to aging, loss of Not stated Not discussed in 10 CFR 50.49 Not stated 11, 27, & 4

dielectric isolation sufficient to disrupt a report 42

circuit or loose connections

Decreased insulation resistance results in Not stated Not discussed in Plant specific Not stated 27 5

excesive leakage current. report programs

Seal cracks and leaks result in moisture Not stated Not discussed in 10 CFR 50.49, Not stated 14, 28, & 6

intrusion and electrical faults. report vendor specific 42

program

Insulation degradation and jacket cracking Not stated Not discussed in 10 CFR 50.49, Not stated 14, 28, & 7

leading to short or open circuits and report vendor specific 42

degraded signals. program

Document. NUREG/CR-5546, An Investigation of The Effects of Thermal Aging on the Fire Damageability of Electric Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

None Not stated Not discussed in No specific Not stated 10,'13,

report program and 32

Failure to protect conductors and Not stated Not discussed in No specific Not stated 21, 24, 2

insulation, report program and 32

Reduced the thermal damage threshold. Not stated Not discussed in No specific Not stated 21, 24, 3

report program and 32

Reduced thermal damage threshold. Not stated Not discussed in No specific Not stated 21, 24, 4

report program and 32
Table A.2 Gall Report for NPAR Reports Page 33A

Document: NUREG/CR-5560, Aging of Nuclear Plant Resistance Temperature Detectors

Reviewed by: L. C. Meyer, INEL

Item System StructurelComD Subcomponent Materials Manufacturer ARD mechanism ARD effects

I Resistance Seal Not stated Five Companies ELETEMP, MOIST- Dry out, shrink, &

Temperature Usted EL, VIB, & THERM- crack

Detector (RTD) CY

2 Resistance Insulation MgO Five Companies MOIST-EL Moisture degrades

Temperature Listed insulation

Detector (RTD)

3 Resistance Sensing Element Platinum Five Companies ELETEMP, MOIST- Noisy, cal shift, &

Temperature Usted EL, VIB, & THERM- degraded element

Detector (RTD) CY

4 Resistance Sheath Stainless steel Five Companies ELETEMP, VIB, & Not stated

Temperature Usted THERM-CY

Detector (RTD)

Document: NUREG/CR-5619, The Impact of Thermal Aging on the Flammability of Electric Cables

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Electric Cables Neoprene jacket, Rockbestos ELETEMP Not stated

cross-linked

polyethylene (XPE)

insulated

Electric Cables Hypalon jacket, Boston Insulated ELETEMP Not stated

ethylene-propylene Wire

rubber (EPR)

insulated

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Jerry Edson, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electrical

Components

Document: NUREG/CR-5655, Submergence and High Temperature Steam Testing of Class 1E Electrical Cables

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Electrical Cable EPR, XLPO, 12 Mfg ELETEMP RAD Insulation failure

silicone, kapton, MOIST-EL

kerite, coaxial

2 Electrical Cable EPR, XLPO, 12 Mfg ELETEMP RAD Some insulation

silicone, kapton, MOIST-EL failure

31 ElectricalCable kerite, coaxial

3 Electrical Cable EPR, XLPO, 12 Mfg ELETEMP RAD Some insulation

silicone, kapton, MOIST-EL failure

kerite, coaxial I I _ _

Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Instrumentation

System

Indicator Not stated Not stated ELETEMP VIBR Indicator failure
Table A.2 Gall Report for NPAR Reports Page 33B

Document: NUREG/CR-5560, Aging of Nuclear Plant Resistance Temperature Detectors

Reviewed by: L. C. Meyer, INEL Efifect of Aninn on Com~onnent Furnction Contrib to Failur'e Renorted n)roaa Rel[.nroos Renort Recommendations Paae No. Item

Sea] may dry out, shrink, or crack allowing Occasional Not discussed in IEEE 338- Not stated 25, & 27 1

moisure intrusion and degraded report 1987, RG

performance of RTD. 1.118, ISA

67.06, Tech

Spec

Moisure intrusion from a leaking seal will Occasional Not discussed in IEEE 338- Not stated 28 2

degrade the insulation, report 1987, RG

1.118, ISA

67.06, Tech

Spec

Long term high temp exposure affects Occasional Not discussed in IEEE 338- Calibrate RTDs and perform 28,167, 3

material properties, vibration may cause report 1987, RG response time tests prior to 180, and

response time degradation, and therm-cy 1.118, ISA installation in a plant. [2] A8

can cause calibration shift. 67.06, Tech

Sheath not normally effected by aging Rare Not discussed in IEEE 338- Not stated 15, 25 & 4

during qualified life of RTD. report 1987, RG 27

1.118, ISA

67.06, Tech

1 Spec I I _ I

Document: NUREG/CR-5619, The Impact of Thermal Aging on the Flammability of Electric Cables

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Reduction in flammability Not stated Not discussed in No specific No further investigation needed 21 1

report program

Reduction in flammability Not stated Not discussed in No specific No further investigation needed 21 2

report program

Document: NUREG/CR-5643, Insights Gained From Aging Research

Reviewed by: Jerry Edson, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

For electrical components, this report . Not stated Not discussed in Component Not stated 1

contains information identical to that in report specific

other NPAR reports. See the following programs

NUREG/CR reports: 4457, 5448, 4564,

5051, 5192, 5461, 5655,4156,4939,

4234 v1 & v2, 5141,4819 v1 & v2, 5181,

4747 v1, 4967, 4740

Document: NUREG/CR-5655, Submergence and High Temperature Steam Testing of Class 1 E Electrical Cables

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Pag No. Item

Not stated Not stated IEEE 383 No specific Not stated 2, 35 1

program

Not stated Not stated IEEE 383 No specific Not stated 2, 35 2

program

Not stated Not stated IEEE 383 No specific Not stated 2, 35 3

program

Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Frequent Not discussed in

report

RG 1.118,

IEEE 338-

1987, ISA

67.06, Tech

Spec

Develop methods to prevent infant

mortality. Testing for synergistic

effects of aging. Develop industry

wide data base [2]

11,24,38

,65

I
Table A.2 Gall Report for NPAR Reports Page 34A

Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components

Reviewed by: E. W. Roberts, INEL item •;v~tem •tructurneJC~mn •ubtcnmnnnent Matewkihl_ U~nmmf=tst~rgs ARI'l mee4htnimm &~fl effc.e~t~

2 Instrumentation Sensor Not stated Not stated ELETEMP VIBR Sensor failure,

System PRESS-CY MOIST- response time

EL degradation, drift

3 Instrumentation Controller Not stated Not stated ELETEMP VIBR Failure, response

System MOIST-EL time degradation,

drift

4 Instrumentation Controller Not stated Not stated ELETEMP VIBR Calibration shift

System MOIST-EL slow responce time

5 Instrumentation Annunciators Not stated Not stated ELETEMP VIBR Visual unit failure

System MOIST-EL sound alarm failure

6 Instrumentation Recorders Not stated Not stated ELETEMP VIBR Failure to record

System MOIST-EL

Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Protective Relay - Not stated General Electric Not stated Oxidation on

10, 13, & 24 Years contacts, increased

Old(GE) operating

'I _temperatures

2 Control Relay Not stated Kiockner Moeller Not stated None

3 Control Relay - 2 & Not stated Struthers Dunn Not stated Slight discoloration

12 Years Old of armature and

contact conn. finger

4 Control Relay Not stated Westinghouse Not stated None

5 Electronic Relay Not stated Blaser Electric Not stated Not stated

6 Auxilliary Relay Not stated General Electric Not stated Worn contacts and

dust inside case

7 Auxilliary Relay Not stated Westinghouse Not stated Contact worn,

discolored and pitted

with age

8 Timing Relay Not stated Agastat Not stated Increased pickup

voltage and op.

temp. with age

9 Molded Case Circuit Not stated Square D Not stated None - 6 year old

Breakers

10 Molded Case Circuit Not stated Westinghouse Not stated None - 18 & 30 year

Breakers old

11 Molded Case Circuit Not stated Klockner Moeller Not stated Overheating

Breakers (discoloration) of

case & spliting of

tubing

12 Molded Case LIrcuit

Breakers

Not stated ITE Not stated Overheating/distorati

on/damage to

thermal element &

trip mec
Table A.2 Gall Report for NPAR Reports Page 34B

Document: NUREG/CR-5700, Aging Assessment of Reactor Instrumentation and Protection System Components

Reviewed by: E. W. Roberts, INEL Effect of Aaina on Comoonent Func~tion Contrib to Fnilure Renorted nroas Rel.nroas Renort Rtecommendatlons Pacae No. Item

Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 2

report IEEE 338- mortality. Testing for synergistic 41,65

1987, ISA effects of aging. Develop industry

67.06, Tech wide data base [2]

Spec Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11, 13, 26 3

report IEEE 338- mortality. Testing for synergistic 43,65

1987, ISA effects of aging. Develop industry

67.06 wide data base [2]

Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 4

report IEEE 338- mortality. Testing for synergistic ,47,65

1987, ISA effects of aging. Develop industry

67.06, Tech wide data base [2]

Spec

Not stated Frequent Not discussed in RG 1.118, Develop methods to prevent infant 11, 13, 26 5

report IEEE 338- mortality. Testing for synergistic 48,65

1987, ISA effects of aging. Develop industry

67.06 wide data base [2]

Not stated Occasional Not discussed in RG 1.118, Develop methods to prevent infant 11,13,26 6

report IEEE 338- mortality. Testing for synergistic 48,65

1987, ISA effects of aging. Develop industry

67.06, Tech wide data base [2]

Spec

Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Higher contact resistance, differences in Frequent Yes - not specifically IEEE 741-1986 Modify current practices to include 3-1 & 7-3 1

induction pickup, significant variation in identified Section 7 the addition of infrared temperature

time/current charateristic. measurement with cover off and

relay energized. [2]

None NONE Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7- 2

identified Section 7 the addition of infrared temperature 3

and vibration measurements. [2]

Contact resistance increased with age Rare Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7- 3

identified Section 7 the addition of infrared temperature 3

and vibration measurements. [2]

None Not stated Yes - not specifically IEEE 741-1986 Modify current practices to include 3-18 & 7- 4

identified Section 7 the addition of infrared temperature 3

and vibration measurements. [2]

Not stated Not stated Yes - not specifically IEEE 741-1986 Not stated 3-32 & 7- 5

identified Section 7 3

Pickup voltage exceeded acceptance Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-36 & 7- 6

criteria identified Section 7 measurement and vibration testing to 3 _ current plant practices. [2]

Increased contact resistance Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-36 & 7- 7

identified Section 7 measurement and vibration testing to 3

current plant practices. [2]

liming accuracy not within typical Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-52 & 7- 8

required accuracy identified Section 7 measurement, inrush current and 3

vibration testing to current plant

practices. [2]

None Not stated Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7- 9

identified Section 7 measurement and vibration testing to 3

current plant practices. modify

instantaneous trip test. [2]

Exceeded typical accept. criteria for Rare Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7- 10

instantaneous trip (125%) time. identified Section 7 measurement and vibration testing to 3

current plant practices. modify

instantaneous trip test. [2]

300% overcurrent trip delay exceeded Occasional Yes - not specifically IEEE 741-1986 Add infrared temperature 3-65 & 7- 11

acceptance criteria. identified Section 7 measurement and vibration testing to 3

Damaged/misaligigned trip pin caused current plant practices. modify

overheating and failure to perform instantaneous trip test. [2]

instantaneous trip when required.

Instantaeous trip inoperable/out of

tolerance on 2 phases. 300% overcurrent

trip does not meet acceptance ctiteria.

Frequent Yes - not specifically IEEE 741-1986

identified ISection 7

Add infrared temperature

measurement and vibration testing to

current plant practices. modify

instantaneous trip test. [2]

3-65 & 7-

3

12
Table A.2 Gall Report for NPAR Reports Page 35A

Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp SubcomDonent Materials Manufacturer ARD mechanism ARD effects

3 Metal Clad Circuit Not stated Westinghouse Not stated Main/arcing contacts

Breakers pitted, insulation ,

split, damaged parts

14 Metal Clad Circuit General Electric Not stated Back connections

Breakers oxidized. binding of

dashpot

Document: NUREG/CR-5772 V1, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica

Conductor Cables polyethylene and Listed AND OXI DAT property - insulation

cross linked resistance (IR)

polyolefin

2 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica

Conductor Cables polyethylene and Listed AND OXIDAT property -

cross linked capacitance & diss.

polyolefin factor

3 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in electrica

Conductor Cables polyethylene and Listed AND OXIDAT property -

cross linked polarization index

polyolefin

4 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in

Conductor Cables polyethylene and Listed AND OXI DAT mechanical property

cross linked - elongation & tens.

polyolefin strength

5 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in

Conductor Cables polyethylene and Listed AND OXIDAT mechanical property cross linked - hardness

polyolefin

6 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in

Conductor Cables polyethylene and Listed AND OXIDAT mechanical property

cross linked - indenter modulus

I_ polyolefin

7 600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in

Conductor Cables polyethylene and Listed AND OXIDAT mechanical property

cross linked - bulk density

___polyolefin

600 V, Single Insulation Cross linked Four Suppliers ELETEMP, RAD, Changes in

Conductor Cables polyethylene and Listed AND OXIDAT mechanical property

cross linked - mandrel bend test

polyolefin

9 600 V, Single Insulation Cross linked Four Suppliers MOIST-EL Moisture absorbed

Conductor Cables polyethylene and Listed into a cable acts as

cross linked plasticizer

polyolefin

10 600 V, Single Jacket Neoprene, Four Suppliers ELETEMP, RAD, & Jacket - elongation

Conductor Cables chlorosulfonated Listed OXIDAT & tensil strength

polyethylene

(CSPE), & CPE

11 600 V, Single Jacket Neoprene, Four Suppliers ELETEMP, RAD, & Jacket - hardness

Conductor Cables chlorosulfonated Listed OXI DAT and indenter

polyethylene modulus

(CSPE), & CPE

Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

600 V I&C Cables Single and Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in electrical Multiconductor AND OXIDAT property - insulation

Cable Insulation resistance (IR)

600 V l&C Cables Single and

Multiconductor

Cable Insulation

Ethylene propylene Five Suppliers Listed! ELETEMP, RAD,

I AND OXIDAT

Changes in electrical

property - polarizator

index
Table A.2 Gall Report for NPAR Reports Page 35B

Document: NUREG/CR-5762, Comprehensive Aging Assessment of Circuit Breakers and Relays

Reviewed by: E. W. Roberts, INEL

Effect of Aaina on (Cnmnnn~nt Fgunenfin Ce~ntrih tn Fnilgr.• R.~nnrtu-d nron~q Rel~nroas Renort Recommendations Pacae No. Item

Long time delay varied between 110% and Rare Yes - not specifically IEEE 741-1986 Add infrared temperature 3-89 & 7- 13

150% of setting identified Section 7 measurement and vibration testing to 3

current plant practices. modify

instantaneous trip test. (2]

One phase failed to trip on long time delay Frequent Yes - not specifically IEEE 741-1986 Add infrared temperature 3-89 & 7- 14

overcurrent. Short timedelay overcurrent identified Section 7 measurement and vibration testing to 3

trip not within acceptance criteria, current plant practices. modify

instantaneous trip test. [2]

Document: NUREG/CR-5772 V1, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item Not determined since report only Not stated Not discussed in No specific "Not stated 6, 257, 40, 1

addressed detection methods report program and App

C

Not determined since report only Not stated Not discussed in No specific Not stated 6, 28, & 2

addressed detection methods report program App D.

Not determined since report only Not stated Not discussed in No specific Not stated 6, 28, and 3

addressed detection methods report program App C

Not determined since report only Not stated Not discussed in No specific Not stated 6, 30-33,

addressed detection methods report program 39, and

App E.

Not determined since report only Not stated Not discussed in No specific Not stated 6, 34, 56, 5

addressed detection methods report program and App

F.

Not determined since report only Not stated Not discussed in No specific Not stated 33, 38, & 6

addressed detection methods report program 39

Not determined since report only Not stated Not discussed in No specific Not stated 35 & 56 7

addressed detection methods report program

Not determined since report only Not stated Testing per IEEE No specific Not stated 47 TO 54, 8

addressed detection methods 383-1974 program & 57.

Not determined since report only Not stated Testing per IEEE No specific Not stated 54 & 57 9

addressed detection methods 383-1974 program

Not determined since report only Not stated Testing per IEEE No specific Not stated 33, 39, & 10

addressed detection methods 383-1974 program 56

Not determined since report only Not stated Not discussed in No specific Not stated 39 & 56 11

addressed detection methods report program

Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not determined since report only Not stated Not discussed in No specific Not stated 31, 32, 52 1

addressed detection methods. report program TO 58,

73,74, &

Appendix

I

Not determined since report only

addressed detection methods.

Not stated Not discussed in

report

No specific

program

The electrical measurements were

not effective for monitoring aging

13,32,

46, & 73
Table A.2 Gall Report for NPAR Reports Page 36A

Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 600 V I&C Cables Single and Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Aging effects on

Multiconductor AND OXIDAT capacitance and

Cable Insulation dissipation factor

4 600 V I&C Cables insulation Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in

AND OXIDAT mechanical property

- elongation & tens.

strength

600 V I&C Cables Insulation Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in

AND OXIDAT mechanical property

- hardness

6 600 V I&C Cables Insulation Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in

AND OXIDAT mechanical property

- indenter modulus

7 600 V I&C Cables Insulation Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in

AND OXI DAT mechanical property

- bulk density

8 600 V I&C Cables Insulation Ethylene propylene Five Suppliers Listed ELETEMP, RAD, Changes in

AND OXIDAT mechanical property

- cracking

9 600 V I&C Cables Insulation Ethylene propylene Five Suppliers Listed MOIST-EL Moisture absorbed

into a cable acts as a

ELETE__P,_ plasticizer

10 600 V I&C Cables Jacket CSPE and CPE Five Suppliers Listed ELETEMP, RAD, & Jacket - elongation

OXI DAT & tensil strength

11 600 V I&C Cables Jacket CSPE, & CPE Five Suppliers Listed ELETEMP, RAD, & Jacket - hardness

OXI DAT and indenter

modulus

Document: NUREG/CR-5772 V3, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electrica

Types silicon rubber, & Listed AND OXIDAT property - insulation

polymide (Kapton) resistance (IR)

2 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electricaJ

Types silicon rubber, & Listed AND OXIDAT property -

polymide (Kapton) capacitance & diss.

factor

31 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in electrical

Types silicon rubber, & Listed AND OXI DAT property -

_ polymide (Kapton) polarization index

4 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in

Types silicon rubber, & Listed AND OXIDAT mechanical property

polymide (Kapton) - elongation & tens.

strengIth

5 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in

Types silicon rubber, & Listed AND OXIDAT mechanical property

polymide (Kapton) - hardness

Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in

Types silicon rubber, & Listed AND OXIDAT mechanical property

polymide (Kapton) - indenter modulus

71 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in

Types silicon rubber, & Listed AND OXIDAT mechanical property

polymide (Kapton) - bulk density

Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers ELETEMP, RAD, Changes in

Types silicon rubber, & Listed AND OXIDAT mechanical property

I polymide (Kapton) - brittleness

9 Miscellaneous Cable Insulation FR insulation, coax, Three Suppliers MOIST-EL Moisture absorbed

Types silicon rubber, & Listed decreases insulation

polymide (Kapton) resistance

10 Miscellaneous Cable Jacket FR & fiberglass Three Suppliers ELETEMP, RAD, & Jacket - elongation

Types braided Listed OXIDAT & tensil strength

11 Miscellaneous Cable Jacket FR & fiberglass Three Suppliers ELETEMP, RAD, & Jacket - hardness

Types braided Listed OXIDAT and indenter

modulus
Table A.2 Gall Report for NPAR Reports Page 36B

Document: NUREG/CR-5772 V2, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Not determined since report only Not stated Not discussed in No specific Not stated 33, 36, & 3

addressed detection methods. report program 46

Not determined since report only Not stated Not discussed in No specific Not stated 36 TO 41,

addressed detection methods, report program & 46

Not determined since report only Not stated Not discussed in No specific Not stated 43, 46, 5

addressed detection methods. report program and

Appendix

F

Not determined since report only Not stated Not discussed in No specific The Franklin indenter is 17, 42, & 6

addressed detection methods. report program recommended because it is a good 46

indicator of aging for jacket and EPR

materials. [4]

Not determined since report only Not stated Not discussed in No specific Not stated 43, 46, & 7

addressed detection methods. report program Appendix

F

Not determined since report only Not stated Testing per IEEE No specific Follow IEEE 383-1974 66, 74, & 8

addressed detection methods. 383-1974 program requirements. [4] 75

Not determined since report only Not stated Not discussed in No specific Not stated 58 & 74 9

addressed detection methods. report program

Not determined since report only Not stated Not discussed in No specific Not stated 73 & 75 10

addressed detection methods. report program

Not determined since report only Not stated Not discussed in No specific Not stated 46 & 73 11

addressed detection methods. report program

Document: NUREG/CR-5772 V3, Aging, Condition Monitoring, and Loss-of-Coolant Accident (LOCA) Tests of Class 1 E Electrical Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No.. Item

Not determined since report only Not stated Not discussed in No specific Not stated 30, 38, 1

addressed detector methods, report program 40, & 51

Not determined since report only Not stated Not discussed in No specific Not stated 32, 38, & 2

addressed detector methods, report program Appendix

D

Not determined since report only Not stated Not discussed in No specific Not stated 31, 38, & 3

addressed detector methods. report program Appendix

C.

Not determined since report only Not stated Not discussed in No specific Not stated 34, 35, & 4

addressed detector methods. report program Appendix

E

Not determined since report only Not stated Not discussed in No specific Not stated 36 & 5

addressed detector methods. report program Appendix

G

Not determined since report only Not stated Not discussed in No specific The indenter is a good indicator of 36, & 6

addressed detector methods, report program aging for silicon rubber and Kerite Appendix

jacket materials, but not for coax F

jackets [4]

Not determined since report only Not stated Not discussed in No specific Not stated 36 & 7

addressed detector methods. report program Appendix

G

Not determined since report only Not stated Testing per IEEE No specific IEEE 383-1974 requirements. [4] 45 TO 48, 8

addressed detector methods. 383-1974 program & 52.

Not determined since report only Not stated Not discussed in No specific Not stated 52 9

addressed detector methods, report program

Not determined since report only Not stated Not discussed in No specific Not stated 6, 13, & 10

addressed detector methods. report program 35

Not determined since report only Not stated Not discussed in No specific Not stated 16 & 36 11

addressed detector methods. report program
Table A.2 Gall Report for NPAR Reports Page 37A

Document: NUREG/CR-6095, Aging, Loss-of-Coolant Accident (LOCA), and High Potential Testing of Damaged Cables

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

#12 AWG, 1 C, Insulation Ethylene propylene Okonite RAD, ELTEMP, & Cracks, degraded

Cables MOIST-EL, & insulation resistance

VOLTSTR for damaged cable

2 #12 AWG, IC, Jacket Chlorosulfonated Okonite RAD, ELTEMP, & Cracks

Cables polyethylene (CSPE) MOIST-EL, &

VOLTSTR

#12 AWG, IC, Insulation Silicon rubber Rockbestos RAD, ELTEMP, & Fragile & cracks

Cables MOIST-EL, &

__ _VOLTSTR

4 #12 AWG, 1 C, Jacket Figerglass braid Rockbestos RAD, ELTEMP, & Not stated

Cables MOIST-EL, &

VOLTSTR

5 #12 AWG, 1 C, Insulation Cross linked Brand Rex RAD, ELTEMP, & Voltage breakdown

Cables polyethylene with no MOIST-EL, & and moisture and

jacket VOLTSTR high temp

degradation

Document: SAND--88-0754, Time-Temperature-Dose Rate Superpositions: A Methodology for Predicting Cable Degradation Under Ambient Nuclear Power Plant

Reviewed by: L C. Meyer, INEL

tem System SEructureiComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

2 Electrical Cable Jacket Neoprene Not stated THERM & RAD Drop in elongation

21 Electrical Cable Jacket Hypalon Not stated THERM & RAD Drop in elongadion

3 Electrical Cable Jacket PVC Not stated THERM & RAD Elongation reduced

from initial value

4 Electrical Cable Insulation Low density Not stated THERM & RAD Embrittlement &

polyethylene discoloration

Electrical Cable Insulation Chemically Cross Not stated THERM & RAD Elongation decrease

linked polyethylene

Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Electrical Switchgeai Metal Housing Not stated GE, Westinghouse, FAT, MECHSTR Cracked welds,

System ITE/BB deformation of circui

breaker rails

2 Electrical Switchgeaj Metal Housing Not stated GE, Westinghouse, CONTAM, CORR Rust pitting, and

System ITE/BB corr of structural

members and

fasteners

3 Electrical Switchgeai Primary Insulating Not stated GE, Westinghouse, EMBR Insulation failure

System ITE/BB

4 Electrical Switchgeai Primary Insulating Not stated GE, Westinghouse, CONTAM, EMBR Decrease in surface

System ITE/BB resistance

5 Electrical Switchgeai Primary Insulating Not stated GE, Westinghouse, ELETEMP, Decrease in

System ITE/BB CONTAM, EMBR volumetric and

surface resistance

6 Electrical Switchgear Horizontal Racking Not stated GE, Westinghouse, WEAR Binding of drawout

Mechanism ITE/BB unit

7 Electrical Switchgeal Vertical Racking

Mechanism

Not stated GE, Westinghouse,

ITE/BB

WEAR Lifting motor failure
Table A.2 Gall Report for NPAR Reports Page 37B

Document: NUREG/CR-6095, Aging, Loss-of-Coolant Accident (LOCA), and High Potential Testing of Damaged Cables

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Longitudinal cracks were through to Occasional Not discussed in No specific Not stated 4, 5,10, & 1

conductor and adjacent to damaged area, report program 18

insulaton resistance degrades until failure

occurs.

Jacket cracking can propagate to the OCASSIONAL Not discussed in No specific Not stated 4, 5, 10, & 2

insulation report program 18

Some cables showed degradation during Rare Not discussed in No specific Not stated 4 & 16 3

accident tests, on one cable a crack was report program

found acdacent to the damaged area.

Not stated Rare Not discussed in No specific Not stated 4 & 16 4

report program

No high potential effects found when Rare Not discussed in No specific Not stated 4 5

insulation remaining was 7 mills, no report program

cracks developed from aging. Failure of

cables during LOCA testing were at

damaged locations

Document: SAN D--88-0754, lime-Temperature-Dose Rate Superpositions: A Methodology for Predicting Cable Degradation Under Ambient Nuclear Power Plant I

Reviewed by: L. C. Meyer, INEL

Effect Of Aging on uomponent iunction Contrib to iallure Reportea progs Rel.progs Report uecommendations rage rNo. item

Jacket failed to provide protection from Rare Not discussed in No current Not stated 28 to 34 1

moisture, report programs

Jacket failed to provide protection from Rare Not discussed in No current Not stated 34 to 38 2

moisture. report programs

Jacket failed to provide protection from Occasional Not discussed in No current Not stated 43 3

moisture, report programs

Embrittiement causes cracking and allows Frequent (for 1960 Not discussed in No current Not stated 44 4

moisture intrusion resulting in failure to cable) report programs

accurately transmit voltage or current.

Embrittlement causes cracking and allows Rare Not discussed in No current Not stated 12 & 54 5

moisture intrusion resulting in failure to report programs

accurately transmit voltage or current.

Document: SAN D93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Structural degradation caused by material Not stated Various No specific Not stated 4-7 1

fatigue can lead to the loss of structural recommendations program for

integrity, made for this

maintenance subcomponent

Contaminants and moisture can cause Not stated Various No specific Not stated 4-7 2

corrosion/rust of the metal housing recommendations program for

system, resulting in a loss of structural made for this

integrity. maintenance subcomponent I

Insulation deterioration results from Not stated Various No specific Not stated 4-7 3

ambient temperatures with ohmic heating recommendations program for

and can result in a loss of insulating made for this

properties and flashover of insulation. maintenance subcomponent

Normal voltage in combination with Not stated Various No specific Not stated 4-7 4

humidity, dirt, and contaminants can lead recommendations program for

to surface current tracking which can made for this

result in insulation failure and flashover maintenance subcomponent

Normal voltage in combination with Not stated Various No specific Not stated 4-7 5

thermal deterioration, humidity, dirt, and recommendations program for

contaminants can lead to a decrease in made for this

volumetric and surface resistance which maintenance subcomponent

can result in bus insulation failure and

fiashover.

Wear from many racking cycles can lead Not stated Various Vendor specific Not stated 4-7 6

to a binding of the drawout unit which can recommendations programs

result in the inability to connect the made for

breaker for operation. maintenance I

Wear from many racking cycles can lead

to a lifting motor failure which can result in

the breaker not being able to be

connected for operation.

Not stated Various

recommendations

made for

maintenance

Vendor specific

programs

Not stated 4-8 7
Table A.2 Gall Report for NPAR Reports

Document- SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Item Svstem Structure/Comp Subcomponent Materials Manufacturer ARD mechanism

Page 38A

ARD effects

8 Electrical Switchgear Arcing Contacts Not stated GE, Westinghouse, CURSTR Arcing contact bum

ITE/BB up and vaporization

9 Electrical Switchgeal Main Contacts Not stated GE, Westinghouse, CURSTR Contact burning or

ITE/BB welding

10 Electrical Switchgeai Main Contacts Not stated GE, Westinghouse, VIBR, WEAR Contact burning or

ITE/BB welding

11 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, CONTAM, ENVIR Deterioration of

Spring and Solenoid ITE/BB greases

Operated Mech

12 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, ENVIR, MECHSTR, High friction betweer

Spring and Solenoid ITE/BB WEAR moving parts

Operated Mech

13 Electrical Switchgeaj Stored Energy Not stated GE, Westinghouse, VIBR, WEAR Movement of

Spring and Solenoid ITE/BB components and

Operated Mech loss of tolerances

14 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, FAT, CONTAM Broken welds

Spring and Solenoid ITE/BB

Operated Mech

15 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, WEAR Wear of spring

Spring and Solenoid ITE/BB charging mechanism

Operated Mech components

16 Electrical Switchgear Stored Energy Not stated GE, Westinghouse, ELETEMP Trip or close coil

Spring and Solenoid ITE/BB bum out

Operated Mech

17 Electrical Switchgeat Solenoid Operated Not stated GE, Westinghouse, ELETEMP Solenoid coil bumou

Mechanism ITE/BB

18 Electrical Switchgeai Solenoid Operated Not stated GE, Westinghouse, CURSTR, Insulation

Mechanism ITE/BB ELETEMP deterioration

19 Electrical Switchgear Arc-Chute Not stated GE, Westinghouse, ELETEMP, EMBR Material degradation

ITE/BB

20 Electrical Switchgeai Primary Disconnect Not stated GE, Westinghouse, WEAR Disconnect wear,

ITE/BB spring relaxation

21 Electrical SwitchgeamSecondary

Disconnect

Not stated GE, Westinghouse, ITE/BBWEAR Spring relaxation
Table A.2 Gall Report for NPAR Reports Page 38B

Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear P6wer Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported proqs Rel.progs Report Recommendations Page No. Item

Fault current operation can cause contact Not stated Various IEEE 308-1980 Not'stated 4-8 8

deterioration and lead to contact bum up recommendations Section 7.4 &

and vaporization which degrades the made for 7.5

breaker's function, maintenance

Fault current operation can lead to contact Not stated Various IEEE 308-1980 Not stated 4-8 9

deterioration which can result in the recommendations Section 7.4 &

breaker's function being degraded. made for 7.5

maintenance

Movement of components and loss of Not stated Various IEEE 308-1980 Not stated 4-8 10

tolerances from mechanical cycling can recommendations Section 7.4 &

lead to high resistance at the contact made for 7.5

interface which in turn can lead to contact maintenance

burning or welding. This can result in

degraded breaker function.

Ambient temperatures can cause greases Not stated Various Vendor specific Not stated 4-8 11

to deteriorate leading to binding of latches recommendations programs

and high friction in mechanism. These made for

can result in slow or no open or close maintenance

operation.

Mechanical cycling of the stored energy Not stated Various Vendor specific Not stated 4-8 12

spring can cause mechanical wear of recommendations programs

mechanism parts which leads to high made for

friction between moving parts. This can maintenance

result in binding of mechanism and

latches, slow or no open or close

operation.

Mechanical cycling can cause a loss of Not stated Various Vendor specific Not stated 4-8 13

tolerances and movement of components. recommendations programs

This can result in binding and/or failure to made for

operate. maintenance

Mechanical cycling can lead to pole shaft Not stated Various Vendor specific Not stated 4-9 14

weld fatigue which can lead to broken recommendations programs

welds. This can result in jamming, made for

slowing, or failure to operate. maintenance

Mechanical cycling can lead to wear of Not stated Various Vendor specific Not stated 4-9 15

spring charging mechanism components recommendations programs

which can result in failure to charge made for

closing springs and failure to close, maintenance

Prolonged energization of the control coils Not stated Various No specific Not stated 4-9 16

can lead to elevated temperatures which recommendations program for

can lead to trip or close coil bum out. made for this sub

This can result in failure to open, failure to maintenance component

close, or failure to operate.

Prolonged energization of solenoid coil Not stated Various No specific Not stated 4-9 17

can cause elevated temperatures in the recommendations program for

coil which can lead to solenoid coil made for this sub

burnout. This can result in the breaker maintenance component

failing to close.

Electrical cycling can cause insulation Not stated Various No specific Not stated 4-9 18

deterioration which can lead to solenoid recommendations program for

coil burn out This can result in a failure made for this sub

to close. maintenance component

Fault current operation can cause Not stated Various Vendor specific Not stated 4-9 19

elevated temperatures in the arc-chute recommendations programs

which can lead to material degradation of made for

the arc-chute. This can result in maintenance

degraded function of the arc-chute.

Many racking cycles can cause Not stated Various No specific Not stated 4-9 20

disconnect wear and spring relaxation recommendations program for

which can lead to high resistivity made for this mechanism

connections. This can result in degraded maintenance

disconnect function.

Many racking cycles can cause spring relaxation which can lead to high

resistivity connections. This can result in

degraded disconnect function.

Not stated Various

recommendations

made for

maintenance

No specific

program for

this mechanism

Not stated 4-10 21
Table A.2 Gall Report for NPAR Reports Page 39A

Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Item System StructureIComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

22 Electrical Switchgear Mechanical Interlock Not stated GE, Westinghouse, WEAR Wear/damage of

ITE/BB mechanical interlock

23 Electrical Switchgear Auxiliary Switch Not stated GE, Westinghouse, WEAR, MECHSTR Burnt contacts

ITE/BB

24 Electrical Switchgear Current and Not stated GE, Westinghouse, EMBR, ELETEMP Insulation

Potential ITE/BB deterioration

Transformers

25 Electrical Switchgear Undervoltage Trip Not stated GE, Westinghouse, ELETEMP, EMBR Insulation

Attachment ITE/BB deterioration

26 Electrical Switchgear Undervoltage Trip Not stated GE, Westinghouse, WEAR Wear of latch

Attachment ITE/BB

27 Electrical Switchgear Undervoltage Trip Not stated GE, Westinghouse, WEAR High friction betweer

Attachment ITE/BB moving parts

28 Electrical Switchgear Control Wiring Not stated GE, Westinghouse, ELETEMP, Loss of electrical

ITE/BB MECHSTR, VIBR and mechanical

properties

29 Electrical Switchgear Shunt Trip Not stated GE, Westinghouse, ELETEMP Coil deterioration

Attachment ITE/BB

30 Electrical Switchgear Shunt Trip Not stated GE, Westinghouse, VIBR, WEAR Loss of tolerances

Attachment ITEIBB

31 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse, WEAR, FAT Spring relaxation

Device (Electro- ITE/BB

Mechanical)

32 Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse, WEAR, ENVIR Armature

Device (Electro- ITE/BB mechanical wear

Mechanical)

Electrical Switchgear Overcurrent Trip

Device (ElectroMechanical)

Not stated GE, Westinghouse, CONTAM,

ITE/BB IMECHSTR Seal degredation
Table A.2 Gall Report for NPAR Reports Page 39B

Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Effect of Aaina on Comoonent Function Contrib to Failure Reported oroas Rel.Droas Report Recommendations Paae No. Item

Many racking cycles can cause Not stated Various Vendor specific Not stated 4-10 22

wear/damage from friction. This can recommendations - Mechanism

make it possible to remove or insert the cb made for not safety rel.

into compartment with main contacts maintenance

closed. This could jeopardize personnel

safety.

Mechanical cycling of the auxiliary switch Not stated Various Vendor specific Not stated 4-10 23

can cause contact deterioration which can recommendations - Mechanism

lead to burnt contacts. This can result in made for not safety rel.

contact failure, maintenance I

Temperature and electrical cycling can Not stated Various No specific Not stated 4-10 24

cause insulation deterioration which can recommendations program for

lead to shorted windings. This can result made for this

in degraded function of the transformer maintenance subcomponent

which can cause failure of undervoltage

and control functions.

Constant coil energization can cause Not stated Various Vendor specific Not stated 4-10 25

elevated temperatures which can lead to recommendations programs

insulation deterioration. This can result in made for

the breaker tripping open due to coil maintenance

failure.

Mechanical cycling can cause wear of Not stated Various Vendor specific Not stated 4-10 26

latch which can lead to latch failure. This recommendations programs

can result in a failure to trip on made for

undervoltage condition. maintenance

Mechanical cycling can cause high Not stated Various Vendor specific Not stated 4-10 27

friction between moving parts which can recommendations programs

lead to a lack of adequate force to trip the made for

breader in an undervoltage condition, maintenance

High resistance connections, damage due Not stated Various No specific Not stated 4-10 28

to maint, and vibr can cause a loss of recommendations program for

elect and mech properties, leading to made for this

elevated temp and mech damage. This maintenance subcomponent

can result in insulation deterioration and

short to ground resulting in failure to

operate.

Prolonged energization can cause Not stated Various Vendor specific Not stated 4-11 29

elevated temperatures in the coil which recommendations programs

can lead to coil deterioration. This can made for

cause coil failure and result in a failure of maintenance

the shunt trip to operate.

Cycling and vibration can cause a loss of Not stated Various Vendor specific Not stated 4-11 30

tolerances on its mounting leading to recommendations programs

loosening or misalignment This could made for

result in the device not actuating the trip maintenance

mechanism. I

Prolonged spring compression can cause Not stated Various Vendor specific Not stated 4-11 31

spring relaxation leading to metal fatigue recommendations programs

in the spring. This could result in made for

setpointltime delay drift which could maintenance

cause the overcurrent trip device to have

improper operation or failure to operate.

Mechanical cycling and elevated Not stated Various Vendor specific Not stated 4-11 32

temperatures can cause friction or recommendations programs

degraded lubricant which can lead to made for

mechanical wear in the armature. This maintenance

can result in setpoint/time delay drift with

the potential loss of overcurrent

protection.

Mechanical cycling in conjunction with dirt

or contaminants can lead to seal

degradation which can result in dashpot

leakage and setpointltime delay drift. This

can result in the potential loss of

overcurrent protection.

Not stated Various

recommendations

made for

maintenance

IEEE 308-1980

Sections 7.4 &

7.5

Not stated 4-11 33
Table A.2 Gall Report for NPAR Reports Page

Document: SAND93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K. D. McCarthy, INEL Item System SkructurelComD Subcomeonent Materials Manufacturer ARD mechanism ARD effects

40A

34 - Electrical Switchgear Overcurrent Trip Not stated GE, Westinghouse, ELETEMP, Electrical componen

Device (Solid State) ITE/BB CURSTR, aging

MECHSTR

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL Item SytmStructure/Como Subcomoonent Materials Manufacturer ARD mechanism ARD effects

1 Battery Chargers, Circuit Breakers Not stated Not stated CORR Contact pitting

Inverters, & UPS's

2 Battery Chargers, Circuit Breakers Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

3 Battery Chargers, Circuit Breakers Not stated Not stated WEAR Attrition

Inverters, & UPS's

4 Battery Chargers, Relay Not stated Not stated ENVIR Chemical or physical

Inverters, & UPS's degradation

5 Battery Chargers, Circuit Breakers Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

or physical

degradatio

6 Battery Chargers, Circuit Breakers Not stated Not stated. CURRSTR Equip temp rise,

Inverters, & UPS's equipment

degradation,

7 Battery Chargers, Relay Not stated Not stated ELETEMP Chemical or physical

Inverters, & UPS's degradation

8 Battery Chargers, Transformer Not stated Not stated CORR Loss of material;

Inverters, & UPS's corrosion product

buildup

9 Battery Chargers, Circuit Boards Not stated Not stated CORR Loss of material;

Inverters, & UPS's corrosion product

buildup

10 Battery Chargers, Switches Not stated Not stated CORR Contact pitting

Inverters, & UPS's

11 Battery Chargers, Relay Not stated Not stated CORR Contact pitting

Inverters, & UPS's

12 Battery Chargers, Potentiometer Not stated Not stated CORR Contact pitting

Inverters, & UPS's

Battery Chargers,

Inverters, & UPS's

Switches Not stated Not stated FAT Cumulative fatique

damage
Table A.2 Gall Report for NPAR Reports Page 408

Document: SANiD93-7027, Aging Management Guideline for Commercial Nuclear Power Plants - Electrical Switchgear

Reviewed by: K D. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Elevated temperature, electrical transients Not stated Various IEEE 308-1980 Not stated 4 o.

and mechanical shock result in material 1

recommendatons Sections 7.4 &

degradation from component aging. This made for 17.5 can result in erroneous solid-state device I maintenance

output/operation and potential loss of

overcurrent protection.

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL Effect of Aaina on Comnonent Function - - Contrib - ---.. to Failure Renorted *- nrnas - - Rel.nrons Report Recnmmendatienn.,an Nn. Item 

Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19, 5-15 1

impeadance, heat build-up, and signal inspection, IR program for

transmission failure. scanning this mechanism

Fatigue due to high cyclic operation and Not stated Tactile inspection, No specific Not stated 4-20, 5-16 2

vibration, resulting in contact degradation, vibration observation, program for

loose connections, reduced force output IR scanning this mechanism

and component failure.

Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21, 5-16 3

operation caused by routine operation and program for

periodic testing and adjustment, results in this mechanism

rubbing surfaces, binding of linkages,

erosion of contacts and metal surfaces,

burning of arc chutes, and loss of

adjustment.

Drifting of the electronic setpoint can Not stated Calibration, No specific Not stated 4-21, 5-14 4

cause misoperation or component failure. operational program for

surveillance this mechanism

Continuous load coupled with poor Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 5

contact mating, and fault currents can inspection programs

cause deterioration of contact support

insulation, and possible phase-to-ground

faults

Damage to contacts and arc chutes Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 6

occurs regularly due to normal fault inspection programs

interruption.

Coil heating due to continuous, long-term Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 7

energizing of the coil, causing material inspection programs

degradation due to accelerated chemical

reactions/reduced dielectric strength.

Temperature and moisture create Not stated Visual inspection Vendor specific Not stated 4-19, 5-14 8

environmental stresses on transformers programs

which could result in corrosion of the

windings. A reduction of the dielelctric

strength or insulation resilience may

occur, causing the transformer to

ultimately fail.

Temp and moisture create environmental Not stated visual inspection, on- Vendor specific Not stated 4-19, 5-15 9

stresses, and deposited contaminants line monitoring programs

may affect electronics such as printed

circuit boards, resistors, and capacitiors,

resulting in corrosion of these

components, which may lead to

open/short circuits at the termin

Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19, 5-16 10

impeadance, heat build-up, and signal inspection program

transmission failure.

Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19, 5-14 11

impeadance, heat build-up, and signal inspection program

transmission failure.

Corrosion can result in high contact Not stated Cleaning, visual No specific Not stated 4-19, 5-16 12

impeadance, heat build-up, and signal inspection program

transmission failure.

F-atigue due to high cyclic operation and Not stated

vibration, resulting in contact degradation,

loose connections, reduced force output

and component failure.

Tactile inspection,

vibration observation,

IR scan

Vendor specific INot stated 4-20,5-16 131

surveillance
Table A.2 Gall Report for NPAR Reports Page 41A

Document: SAN D93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Item SytmStructurelComD Subcomoonent Materials Manufacturer ARD mechanism ARD effects

14 Battery Chargers, Relay Not stated Not stated FAT Cumulative fatique

Inverters, & UPS's damage

15 Battery Chargers, Potentiometer Not stated Not stated FAT Cumulative fatique

Inverters, & UPS's damage

16 Battery Chargers, Switches Not stated Not stated WEAR Attrition

Inverters, & UPS's

17 Battery Chargers, Relay Not stated Not stated WEAR Attrition

Inverters, & UPS's

18 Battery Chargers, Potentiometer Not stated Not stated WEAR Attrition

Inverters, & UPS's

19 Battery Chargers, Potentiometer Not stated Not stated ENVIRO Chemical or physical

Inverters, & UPS's degradation

20 Battery Chargers, Surge Suppressors Not stated Not stated ENVIRO Chemical or physical

Inverters, & UPS's degradation

21 Battery Chargers, Circuit Boards Not stated Not stated ENVIRO Chemical or physical

Inverters, & UPS's degradation

22 Battery Chargers, Electronics Not stated Not stated ENVIRO Chemical or physical

Inverters, & UPS's degradation

23 Battery Chargers, Electronics Not stated Not stated CORR Loss of material;

Inverters, & UPS's corrosion product

buildup

24 Battery Chargers, Wire Not stated Not stated CORR Loss of material;

Inverters, & UPS's corrosion product

buildup

25 Battery Chargers, Cooling Fans and Not stated Not stated CORR/OX Loss of material;

Inverters, & UPS's Cooling Fan Motors corrosion product

buildup;internal

damage

Battery Chargers,

Inverters, & UPS's

Cabinet Not stated Not stated CORR/OX Loss of material;

corrosion product

buildup;internal

damage
Table A.2 Gall Report for NPAR Reports Page 41 B

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Effect of Aaina on Comoonent Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Fatigue due to high cyclic operation and Not stated Tactile inspection, Vendor specific Not stated 4-20, 5-14 14

vibration, resulting in contact degradation, vibration observation, surveillance

loose connections, reduced force output IR scan

and component failure.

Fatigue due to high cyclic operation and Not stated Tactile inspection, Vendor specific Not stated 4-20, 5-16 15

vibration, resulting in contact degradation, vibration observation, surveillance

loose connections, reduced force output IR scan

and component failure.

Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21, 5-16 16

operation caused by routine operation and program

periodic testing and adjustment, results in

rubbing surfaces, binding of linkages,

erosion of contacts and metal surfaces,

burning of arc chutes, and loss of

adjustment.

Physical deterioration due to the cyclic Not stated Tactile inspection No specific Not stated 4-21, 5-14 17

operation caused by routine operation and program

periodic testing and adjustment, results in

rubbing surfaces, binding of linkages,

erosion of contacts and metal surfaces,

burning of arc chutes, and loss of

adjustment.

Physical deterioration due to the cyclic Not stated Not discussed in No specific Not stated 4-21, 5-16 18

operation caused by routine operation and report program

periodic testing and adjustment, results in

rubbing surfaces, binding of linkages,

erosion of contacts and metal surfaces,

burning of arc chutes, and loss of

adjustment.

Drifting of the setpoint can cause Not stated Calibration, Tech IEEE 308-1980 Not stated 4-21, 5-16 19

misoperation or componenet failure. Spec, I/0 logging, Section 7, Tech

output Spec surveil.

Drifting of the electronic setpoint can Not stated Calibration No specific Not stated 4-21, 5-15 20

cause misoperation or componenet program

failure.

Drifting of the electronic setpoint can Not stated Calibration, Tech Tech Spec. Not stated 4-21, 5-15 21

cause misoperation or componenet Spec, 1/0 logging, required

failure. output surveillance

Drifting of the electronic setpoint can Not stated Calibration, Tech Tech Spec. Not stated 4-21, 5-15 22

cause misoperation or componenet Spec, I/0 logging, required

failure, output surveillance

Temp and moisture create environmental Not stated Visual inspection, Vendor specific Not stated 4-19, 5-15 23

stresses, and deposited contaminants output programs

may affect electronics such as printed

circuit boards, resistors and capacitors

resulting in corrosion of the components,

which may lead to open/short circuits at

the terminals. I

Temp and moisture create environmental Not stated Visual inspection, No specific Not stated 4-19, 5-16 24

stresses, and deposited contaminants output program

may corrode shields or conductor strands,

terminations, etc. eventually causing

failure of the circuit due to overheating or

dielectric insulation breakdown.

Temp and moisture create environmental Not stated Visual inspection IEEE 334-1974 Not stated 4-19, 5-16 25

stresses, and deposited contaminants Section 14.2.3

may increase contact resistance.

Vibration can promote loosening

connectons resulting in localized heating

and more oxidation.

Temp and moisture create environmental

stresses, and deposited contaminants

may over time can degrade and give way

to oxidation corrosion.

Not stated Visualjnspection No specific

program

Not stated 4-20, 5-17 26
Table A.2 Gall Report for NPAR Reports Page 42A

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

27 Battery Chargers, Transformer Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

28 Battery Chargers, Inductors Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

29 Battery Chargers, Capacitor Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

30 Battery Chargers, SCR's Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

31 Battery Chargers, Diodes Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

32 Battery Chargers, Surge Suppressors Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

33 Battery Chargers, Circuit Boards Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

34 Battery Chargers, Electronics Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

35 Battery Chargers, Wire Not stated Not stated FAT Cumulative fatigue

Inverters, & UPS's damage

No stte FA

36 Battery Chargers,

Inverters, & UPS's

Cooling Fans and

Cooling Fan Motors

Not stated Not stated FAT Cumulative fatigue

damage
Table A.2 Gall Report for NPAR Reports Page 42B

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Effect of Aaina on ComDonent Function Contrib to Failure Reported eroas Rel.Droos Report Recommendations Paqe No. Item

High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20, 5-14 27

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure. I

High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20, 5-14 28

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure.

High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20, 5-14 29

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure. IHigh frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20, 5-15 30

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure. I

High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20, 5-15 31

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure.

High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20, 5-15 32

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure.

High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20, 5-15 33

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure. I

High frequency vibration caused by Not stated Tactile/audible Vendor specific Not stated 4-20, 5-15 34

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular malnt also

moves/bends wires/connectors causing

conductor or insulation failure.

High frequency vibration caused by Not stated Tactile/audible No specific Not stated 4-20, 5-16 35

ferromagnetic resonance can cause inspection, vibration program

fatigue resulting in loose parts, open observation, IR scan

circuits causing loss of signal or sporatic

operation. Regular maint also

moves/bends wires/connectors causing

conductor or insulation failure.

Vibration induced fatigue in motor mounts

can occur due to improper sheave

alignment and dynamic imbalances.

Not stated Tactile/audible

inspection, vibration

observation, IR scan

IEEE 334-1974

Section 14.2.3

Not stated 4-20, 5-17 36
Table A.2 Gall Report for NPAR Reports Page 43A

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Item System Structure/Comp SubcomDonent Materials Manufacturer ARD mechanism ARD effects

37 Battery Chargers, Cooling Fans and Not stated Not stated WEAR Attrition

Inverters, & UPS's Cooling Fan Motors

38 Battery Chargers, Transformer Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR or physical changes

39 Battery Chargers, Inductors Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

40 Battery Chargers, Capacitor Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

41 Battery Chargers, Diodes Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

42 Battery Chargers, Surge Suppressors Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

43 Battery Chargers, Circuit Boards Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

44 Battery Chargers, Electronics Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

45 Battery Chargers, SCR's Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

46 Battery Chargers, Switches Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR or physical changes

47 Battery Chargers, Wire Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR, or physical changes

EMBR

48 Battery Chargers, Cooling Fan Motors Not stated Not stated THERM-CY, Deterioration of

Inverters, & UPS's ELETEMP, insulation, chemical

VOLSTR, CURSTR, or physical changes

EMBR

49 Battery Chargers, Transformer Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

50 Battery Chargers, Inductors Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

51 Battery Chargers,

Inverters, & UPS's

SCR's Not stated Not stated CONTAM Buildup of deposits;

loss of desired

surface properties
Table A.2 Gall Report for NPAR Reports Page 43B

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Effect of Aaina on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Shafts and bearings are susceptible to Not stated Noise observation IEEE 334-1974 Not'stated 4-21, 5-17 37

normal wear, and wear due to Section 14.2.3

misalignment, imbalances, and inherent

eccentricity of the rotor. On dc motors,

brushes and commutators are also

subject to wear.

Overvoltage or turn-to-turn shorts can Not stated Cleaning, Vendor specific Not stated 4-22, 5-14 3E

cause high internal tempreratures, visual/tactile/audible program

causing insulation to fail, causing local inpection

heating and deterioration of materal

resulting in dielectric failure.

Overvoltage or turn-to-turn shorts can Not stated Cleaning, Vendor specific Not stated 4-22, 5-14 3S

cause high internal tempreratures, visual/tactile/audible program

causing insulation to fail, causing local inpection

heating and deterioration of material

resulting in dielectric failure.

Overvoltage can cause voltage stress Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-14 4C

causing loss of capacitance, breakdown inspection, program

of dielectric. measuement, part

replacement

Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 41

internal stresses can cause dielectric inspection, program

breakdown resulting in change in output temperature &

signal. input/output

Heat due to overcurrent conditions and Not stated Cleaning, visual No specific Not stated 4-22, 5-15 42

internal stresses can cause dielectric inspection, program

breakdown and misoperation or failure of temperature &

the device. input/output

Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 43

internal stresses can cause dielectric inspection, program

breakdown and misoperation or failure of temperature &

components, open/shorts of circuits, input/output

Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 44

internal stresses can cause dielectric inspection, program

breakdown and misoperation or failure of temperature &

components, open/shorts of circuits, input/output

Heat due to overcurrent conditions and Not stated Cleaning, visual Vendor specific Not stated 4-22, 5-15 45

internal stresses can cause dielectric inspection, program

breakdown and misoperation or failure of temperature &

components, open/shorts of circuits, input/output

Heat due to overcurrent conditions and Not stated Cleaning, visual No specific Not stated 4-23, 5-16 46

normal operations, and due to contact inspection, program

resistance, can cause dielectric temperature logging

breakdown of supports and insulation,

and misoperation or failure of

components.

Thermal effects on wire and cable leading Not stated Cleaning, visual No specific Not stated 4-23 47

to embrittlement, and insulation failure. inspection, program

Ohmic heating and heat from surrounding temperature &

environment degrades insulation, resulting input/output

in short circuits.

Heat due to overcurrent conditions and Not stated Cleaning, visual IEEE 334-1974 Not stated 4-23, 5-16 48

normal operations, can cause dielectric inspection, Section 14.2.3

breakdown and failure, temperature &

input/output

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 5-14 49

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 5-14 5C

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components. I I I I _II

Fouling due to accumulation of insects,

dirt, and dust, can reduce heat

dissipation, cause overheating, and

eventual failure of components.

Not stated Cleaning, visual

inspection

No specific

programs

Not stated 4-23, 5-15E 51
Table A.2 Gall Report for NPAR Reports Page 44A

Document: SAND93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

52 Battery Chargers, Diodes Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

53 Battery Chargers, Capacitor Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

54 Battery Chargers, Surge Suppressors Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

55 Battery Chargers, Circuit Boards Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

56 Battery Chargers, Electronics Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

57 Battery Chargers, Wire Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

58 Battery Chargers, Relay Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

59 Battery Chargers, Circuit Breakers Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

60 Battery Chargers, Switches Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

61 Battery Chargers, Potentiometers Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

62 Battery Chargers, Cooling Fan Motoers Not stated Not stated CONTAM Buildup of deposits;

Inverters, & UPS's loss of desired

surface properties

63 Battery Chargers, Relay Not stated Not stated LOSLUB Viscosity change,

Inverters, & UPS's loss of lubricicty

64 Battery Chargers, Circuit Breakers Not stated Not stated LOSLUB Viscosity change,

Inverters, & UPS's loss of lubricicty

Document: SAN D93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Transformer Metal (Tank) Enclosure and Cover jRdegradation Low-alloy steel Not stated ENVIR Chemical/physical

Transformer Metal Enclosure

(Tank) and Cover

Low-alloy steel Not stated. CORR Loss of material;

corrosion product

buildup
Table A.2 Gall Report for NPAR Reports Page 44B

Document: SAN D93-7046, Aging Management Guideline for Commerical Nuclear Power Plants - Battery Chargers, Inverters and Uninteruptable Power Supplies

Reviewed by: Michael W. Vaughn, INEL

Effect of Aaina on ComDonent Function Contrib to Failure ReDorted Droas Rel.oroas Report Recommendations Paqe No. Item

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 5-15 52

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 5-1 4 53

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 5-15 54

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 5-15 55

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 5-15 56

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 5-16 57

dirt, and dust, can reduce heat inspection programs

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 4- 58

dirt, and dust, can reduce heat inspection programs 24, 5-14

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual Vendor specific Not stated 4-23, 4- 59

dirt, and dust, can reduce heat inspection programs 24, 5-15

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 4- 60

dirt, and dust, can reduce heat inspection programs 24, 5-16

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual No specific Not stated 4-23, 4- 61

dirt, and dust, can reduce heat inspection programs 24, 5-16

dissipation, cause overheating, and

eventual failure of components.

Fouling due to accumulation of insects, Not stated Cleaning, visual IEEE 334-1974 Not stated 4-24, 5-17 62

dirt, and dust, can reduce heat inspection SECTION

dissipation, cause overheating, and 14.2.3

eventual failure of components.

Material set occurs when the organic Not stated Tactile inspection, Vendor specific Not stated 4-24, 5-14 63

materials used as lubricants in those operational programs

subconponents harden, gel, or adhere to

adjacent materials, which can cause

binding of the devices, resulting in faulty

operation. I

Material set occurs when the organic Not stated Tactile inspection, Vendor specific Not stated 4-24, 5-14 64

materials used as lubricants in those operational programs

subconponents harden, gel, or adhere to

adjacent materials, which can cause

binding of the devices, resulting in faulty

operation. I

Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Chipping, cracking, or peeling of the Not stated Visual inspection, Vendor specific Not stated 4-7, 5-3,

enclosure's protective coating cleaning, pressure surveillance, 5-1 1

I I I testing I IEEE 308-1980 5-1

Exposed metal develops rust and

Dorrosion

Not stated visual inspection,

cleaning, pressure

testing

Vendorspecific

surveillance,

IEEE 308-1980

Not stated 4-7, 5-3,

5-15

2
Table A.2 Gall Report for NPAR Reports Page 45A

Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 Transformer Metal Enclosure Low-alloy steel Not stated ENVIR, EMBR Deterioration of

(Tank) and Cover organic components

4 Transformer Metal Enclosure Low-alloy steel Not stated FAT Cumulative damage

(Tank) and Cover from cyclic vibration

or thermal stress

5 Transformer Primary and Not stated Not stated ELETEMP Chemical or physical

Secondary degradation: thermal

Windings, Uquid- distortion

Immersed

6 Transformer Primary and Not stated Not stated VIBR, VOLSTR, Loosening, reduced

Secondary EXFORCE tolerances, distortion

Windings, Liquid- or bending

Immersed

7 Transformer Primary and Not stated Not stated ELETEMP Chemical or physical

Secondary degradation; thermal

Windings, Dry-Type distortion

8 Transformer Primary and Not stated Not stated VIBR, VOLSTR, Loosening, reduced

Secondary EXFORCE tolerances, distortion

Windings, Dry-Type or bending

9 Transformer Magnetic Core Not stated Not stated VIBR, MECHSTR, Loosening,

EXFORCE distortion,

deterioration of mect

function

10 Transformer Magnetic Core Not stated Not stated EMBR/TE Loss of fracture

toughness

11 Transformer Insulation Not stated Not stated ELETEMP, Chemical or physical

VOLSTR degradation,

degradation of

insulation

12 Transformer Insulation Not stated Not stated MOIST-EL, Loss of dielectric

CONTAM properties, buildup o

deposits

13 Transformer Insulation Not stated Not stated Not stated High acidity resulting

in more water

retention

Transformer Insulation Not stated Not stated CORR/OX Loss of material;

corrosion product

buildup;internal

damage
Table A.2 Gall Report for NPAR Reports Page 45B

Document: SAN D93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Gaskets and other organic seals used in Not stated Visual inspection, Vendor specific Not stated 4-7, 5-15 3

construction of the enclosure degrade due cleaning surveillance,

to exposure to heat, ultraviolet radiation, IEEE 308-1980

moisture, or chemicals, while under

mechanical stress or compression.

polymeric seal materials embrittle and

harden

Can affect areas of high local stress such Not stated visual inspection, Vendor specific Not stated 4-7, 4-8, 4

a welds, tank edges, etc., resulting in tank cleaning, pressure surveillance, 5-3,5-15

leaks (oil or gas-filled units) and testing IEEE 308-1980

potentially a loss of structural intergrity.

May induce accelerated degradiation of Not stated Electrical testing, Vendor specific Not stated 4-8, 5-4,

surrounding organic materials, visual inspection, surveillance, 5-15

cleaning IEEE 308-1980

Movement and vibration allow windings to Not stated Electrical testing, Vendor specific Not stated 4-9, 5-4, 6

change clearances/tolerances required for visual inspection, surveillance, 5-15

maintaining satisfactory dielectric cleaning IEEE 308-1980

strength, which can result in dielectric

breakdown and localized discharge. Can

cause mechanical stress on electrical

connections

May induce accelerated degradation of Not stated Electrical testing, Vendor specific Not stated 4-9, 5-4, 7

surrounding organic materials, visual inspection, surveillance, 5-15

Degradation of winding conductor cleaning IEEE 308-1980

connections due to high resistance

connections causing localized heating.

Movement and vibration allow winding to Not stated Electrical testing, Vendor specific Not stated 4-9, 5-4, 8

change clearances/tolerances required for visual inspection, surveillance, 5-15

maintaining satisfactory dielectric cleaning IEEE 308-1980

strength, which can result in deilectric

breakdown and localized discharge. Can

cause mechanical stress on electrical

connections.

Loosining of the core due to vibration, Not stated Electrical testing, Vendor specific Not stated 4-10, 5-4, 9

shock, or severe electrical transients, can visual inspection surveillance, 5-15

cause wear or deterioration of the IEEE 308-1980

insulation once dislocation occurs may

lead to sufficient insulation damage to

allow electrical failure

A result of relatively high thermal Not stated Electrical testing, Vendor specific Not stated 4-10, 4- 10

exposure resulting from core and winding visual inspection surveillance, 11,5-4, 5-

losses, causing weakening or failure of IEEE 308-1980 15

the laminations, causing increased eddy

currents and core losses.

Partial or localized breakdown of the Not stated Sampling and Vendor specific Recommended laboratory and/or in- 4-11, 5-5, 11

dielectric capacity of the material, which analysis, cleaning, surveillance, situ analysis to detect impending 5-15, 5-22

may in turn produce other eleterious replacement IEEE 308-1980 breakdown of dielectric [2]

effects such as the formation of additional

gaseous byproducts, decomposition of

the surrounding insulating fluid.

Particulates contaminants and moisture Not stated Sampling and Vendor specific Recommended laboratory and/or in- 4-12, 5-5, .12

may result in blockage of passages analysis, cleaning, surveillance, situ analysis to detect impending 5-16, 5-22

leading to hot spots. Chemical replacement IEEE 308-1980 breakdown of dielectric [2]

contaminants may have adverse effects

on the material properties, water reduces

dielectric strength causing partial

discharge or dielectric breakdown

High acidity results in more water being Not stated Sampling and Vendor specific Recommended laboratory and/or in- 4-12, 5-5, 13

held in solution and therefore reduced analysis, cleaning, surveillance, situ analysis to detect impending 5-16, 5-22

dielectric strength. Also affects the replacement IEEE 308-1980 breakdown of dielectric [2]

deterioration and decomposition of solid

insulating materials reducing the dielectric

strenth I I I I I

Formation of sludge which can impead

circulation creating hot spots. Dielectric

properties associated with the sludge may

also differ, oxygen will also increase the

acidity of the insulating fluid

Not stated Sampling and

analysis, cleaning,

replacement

Vendor specific

surveillance,

IEEE 308-1980

Recommended laboratory and/or insitu analysis to detect impending

breakdown of dielectric [2]

4-12, 5-5,

5-16, 5-22

14
Table A.2 Gall Report for NPAR Reports Page 46A

Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Item System StructurefComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1i Transformer Insulation Not stated Not stated ELETEMP Chemical or physical

degradation; thermal

distortion

16 Transformer Bushings Not stated Not stated THERM-CY Degradation due to

exposure to

elements and temp

cycles

17 Transformer Bushings Not stated Not stated CONTAM Buildup of

deposits:loss of

desired surface

properties

18 Transformer Bushings Not stated Not stated ENVIRO Chemical or physical

degradation

19 Transformer Bushings Not stated Not stated VOLSTR Dielectric stress

causing degradation

of insulation

20 Transformer Cooling System, Not stated Not stated FAT, WEAR Attrition and

Liquid-Immersed cumulative fatigue

and Dry-Type damage over time

21 Transformer Cooling System, Not stated Not stated CONTAM Buildup of deposits;

Uquid-Immersed loss of desired

and Dry-Type surface properties

22 Transformer Oil Preservation and Not stated Not stated ENVIRO, ELETEM- Chemical or physical

Sampling System degredation

23 Transformer Oil Preservation and Not stated Not stated WEAR Attrition

Sampling System

24 Transformer Tap Changers Not stated Not stated WEAR Attrition

25 Transformer Tap Changers Not stated Not stated VIBR, MECHSTR Loosening,

deterioration of

mechanical function

26 Transformer Tap Changers Not stated Not stated ELTEMP, THERM- Chemical or physical

CY degradation,

insulation

deterioration

27 Transformer Protection and Not stated Not stated ENVIRO, EMBR Chemical or physical

Monitoring Systems degradation, loss or

fracture toughness

28 Transformer Protection and Not stated Not stated THERM-CY Deterioration of

Monitoring Systems insulation
Table A.2 Gall Report for NPAR Reports Page 46B

Document: SAND93-7068, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: Michael W. Vaughn, INEL

Effect of Aaina on Component Function Contrib to Failure Reported proas Rel.proas Report Recommendations Paae No. Item

The elevated temperatures cause thermal Not stated Visual inspection, Vendor specific Not stated 4-13, 5-7, 15

deterioration and dielectric breakdown insulation resistance surveillance, 5-16

testing, clean IEEE 308-1980

Breakdown of gaskets and seals, and all Not stated Visual inspection, Vendor specific Manage bushing flashover by 4-14, 5-7, 16

organic materials due to heat caused by power factor testing, surveillance, controling airborne dust and/or salt 5-16, 5-22

current in the conductor, solar radiation, cleaning IEEE 308-1980 spray accumulation in combination

etc. with rain/humidity [2]

The combination of dirt, dust, salt, and Not stated Visual inspection, Vendor specific Not stated 4-14, 5-7, 17

other contaminants, alone or with water or power factor testing, surveillance, 5-17

other liquid can form a conductive path cleaning IEEE 308-1980

leading to flashover of the bushing.

Factors such as ultraviolet radiation, Not stated Visual inspection, Vendor specific Not stated 4-14, 5-7, 18

humidity, etc. can cause degradation over power factor testing, surveillance, 5-17

time cleaning IEEE 308-1980

Improper storage or loss of insulating oil, Not stated Visual inspection, Vendor specific Not stated 4-14, 5-7, 19

or voltage transients, can degrade the power factor testing, surveillance, 5-17

dielectric properties. Dielectric stress cleaning IEEE 308-1980

from potential gradient between the

central conductor and other surfaces.

Bearings and other parts wear over time Not stated Visual inspection, Vendor specific Not stated 4-15, 5-8, 20

due to friction and other stresses placed monitor, adjust, surveillance, 5-17

on them. This is accelerated by such lubricate, clean IEEE 308-1980

stresses as frequent motor starting and

stopping, undue vibration or

transverse/longitudinal load placed on the

driven unit.

Fouling of heat transfer surfaces such as Not stated Visual inspection, Vendor specific Not stated 4-16, 5-8, 21

radiators due to dirt, debris, or other monitor, clean surveillance, 5-17

materials IEEE 308-1980

Elevated temperatures and exposure to Not stated Visual inspection, Vendor specific Not stated 4-16, 5-9, 22

the elements can cause thermal and wear adjust, surveillance, 5-17

degradation to components. repair/replace, clean IEEE 308-1980

Wear to components such as sampling Not stated Visual inspection, Vendor specific Not stated 4-17, 5-9, 23

and isolation valves, fittings, and pressure adjust, surveillance, 5-18

regulating valves, can result in leakage of repair/replace, clean IEEE 308-1980

fluids, binding and/or malfunctioning of

devices.

Wear to components due to friction. Not stated Visual inspection, Vendor specific Not stated 4-18, 5-9, 24

adjust, surveillance, 5-18

repair/replace, IEEE 308-1980

_lubricate, clean

Vibration and mencanical stresses can Not stated Visual inspection, Vendor specific Not stated 4-18, 5- 25

result in a loss of adjustment in parts adjust, surveillance, 10, 5-18

repair/replace, IEEE 308-1980

lubricate, clean

Degradation of organic insulating Not stated Visual inspection, Vendor specific Not stated 4-18, 5- 26

materials in motor windings, insulators on adjust, surveillance, 10, 5-18

main contacts, and materials used in repair/replace, clean IEEE 308-1980

related electrical components which can

reduce their dielectric as well as

mechanical properties.

Degradation of organic materials used to Not stated Visual inspection, Vendor specific Not stated 4-19, 5- 27

seal the relay, can embrittie and harden functional testing surveillance, 11,5-18

the gaskets allowing leakage, possibly IEEE 308-1980

leading to the component failure.

Repeated heating and cooling of the Not stated Visual inspection, No specific Not stated 4-20, 5- 28

temperature indicator elements due to functional testing program 10,5-19

load variation induces thermal stresses

which may eventually result in open-circuit

failure of the element.
Table A.2 Gall Report for NPAR Reports Page 47A

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: K. D. McCarthy, INEL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

I Motor Control Center Motor Not stated GE, Westinghouse, THEM-CY, EMBR Loss of electrical

C-H, KM and mechanical

properties of

insulator

2 Motor Control Center Motor Not stated GE, Westinghouse, MOIST-EL, Loss of surface

C-H, KM CONTAM, ENVIR insulating properties

3 Motor Control Center Motor Not stated GE, Westinghouse, MOIST-EL, Loss of volumetric

C-H, KM CONTAM, ENVIR insulating properties

4 Motor Control Center Motor Not stated GE, Westinghouse, WEAR, CORR/OX, High resistance

C-H, KM CONTAM electrical

connections

5 Motor Control Center Motor Not stated GE, Westinghouse, MECHSTR, VIBR Loosening/loss of

C-H, KM fasteners

6 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR Contact surface

Breakers glass polyester, C-H, KM deterioration

contact- silver or

tungsten

7 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, FAT, MECHSTR Fatigue of various

Breakers glass polyester, C-H, KM circuit breaker

contact- silver or components

tungsten

8 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, WEAR, CONTAM Wear of internal

Breakers glass polyester, C-H, KM components

contact- silver or tungsten

9 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, ELETEMP, Loose or high

Breakers glass polyester, C-H, KM CORR/OX, VIBR resistance elect

contact- silver or connections or tungsten terminations

10 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR Thermal trip setpoint

Breakers glass polyester, C-H, KM variations

contact- silver or

tungsten

11 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CONTAM, ENVIR Deterioration of

Breakers glass polyester, C-H, KM lubricants

contact- silver or

tungsten I I I

Motor Control Center Molded-Case Circuit

Breakers

Case-phenolic or glass polyester,

contact- silver or

tungsten

GE, Westinghouse,

C-H, KM

ENVIR Current limiting fuse

failure
Table A.2 Gall Report for NPAR Reports Page 47B

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Power and Distribution Transformers

Reviewed by: K. D. McCarthy, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Page No. Item

Exposure to ambient temps and ohmic Not stated Various Vendor specific Not stated 4-4, 4-5,

heating can lead to loss of insulating recommendations programs 5-15

properties and thermally induced made for

cracking. This has the potential of maintenance

causing a flashover of the component

insulation and loss of structural integrity.

Voltage and humidity can affect energized Not stated Various Vendor specific Not stated 4-6, 4-7, 2

insulation that is dirty or deteriorated and recommendations programs 5-15

cause surface tracking paths on the made for

insulator. This can lead to flashover. maintenance

Simultaneous exposure of thermally Not stated Various No specific Not stated 4-6, 4-7; 3

deteriorated insulation to temp, voltage, recommendations program for 5-15

humidity, dirt and contaminants can result made for this

in loss of volumetric insulating properties, maintenance subcomponent

leading to increased surface and

volumetric leakage currents and possible

flashover

Poor mating surface contact or sharp Not stated Various Vendor specific Not stated 4-5, 4-8, 4

bends/current flow restrictions near recommendations program 5-15

crimps or terminations can cause high made for

resistance elec connections which can maintenance

result in excessive heating and potentially

fire.

Over-torquing of fasteners, and fasteners Not stated Various Vendor specific Not stated 4-8, 5-15 5

loosened by various external stresses recommendations program

(non-seismic) could cause loss of made for

structural integrity or affect electrical maintenance

connections.

High temps that accompany fault currents Not stated Various No specific Not stated 4-9, 5-15 6

may cause contact material to vaporize, recommendations program for

inducing a loss of contact surface material made for this

and pitting. This could cause the maintenance subcomponent

contacts to bum or weld together and

result in breaker failure.

Cyclic stress can cause fatigue failure of Not stated Various No specific Not stated 4-9, 5-15 7

various circuit breaker components such recommendations program for

as contact assemblies, operating made for this

mechanisms, breaker housing. Fatigue maintenance subcomponent

may be evidenced by progressive

cracking and ultimate failure of the

component.

Inadequate or degraded lubrication, Not stated Various No specific Not stated 4-9, 5-15 8

normal component wear, or wear caused recommendations program for

by contaminants (from other degraded made for this

material or from external sources) can maintenance subcomponent

cause the breaker to malfunction.

Operation of the breaker and non-seismic Not stated Various No specific Not stated 4-9, 5-15 9

vibration cause loose connections. recommendations program for

oxidation or contamination of contact made for this

surfaces and sharp bends in wiring near maintenance subcomponent

terminations can cause high resistance

connections. These can cause excessive

heating or fire.

Exposure to fault currents can cause Not stated Various No specific Not stated 4-10, 5-15 10

variations in the thermal trip setpoint of a recommendations program for

circuit breaker. This can cause the CB to made for this

trip at progressively lower current levels, maintenance subcomponent

potentially causing nuisance tripping.

Contamination, aging, evaporation, and Not stated Various No specific Not stated 4-10, 5-15 11

ambient temperatures can cause recommendations program for

lubricants to deteriorate, this can slow or made for this

completely prevent operation of a breaker, maintenance subcomponent I

Fuses degrade slowly over time until

eventually the current-carrying capability

of the fuse is reached during

normal/transient load operation, resulting

in nuisance current interruptions.

Not stated Various

recommendations

made for

maintenance

Replace when

inoperative

Not stated 4-10, 5-1 Z 12
Table A.2 Gall Report for NPAR Reports Page 48A

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K. D. McCarthy, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

13 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR, Surface current

Breakers glass polyester, C-H, KM CONTAM trackingAoss of

contact- silver or insulating properties

tungsten

14 Motor Control Center Molded-Case Circuit Case-phenolic or GE, Westinghouse, CURSTR, Thermally induced

Breakers glass polyester, C-H, KM ELETEMP degradation

contact- silver or

tungsten

15 Motor Control Centes Magnetic Not stated GE, Westinghouse, ELETEMP Insulation

Contactors/Starters C-H, KM deterioration

16 Motor Control Center Magnetic Not stated GE, Westinghouse, ELETEMP Organic component

Contactors/Starters C-H, KM breakdown

17 Motor Control Center Magnetic Not stated GE, Westinghouse, VIB, WEAR Cyclic fatigue

Contactors/Starters C-H, KM

18 Motor Control Center Magnetic Not stated GE, Westinghouse, WEAR, VIB, Wear of contactor

Contactors/Starters C-H, KM CONTAM and starter

subcomponents

19 Motor Control Center Magnetic Not stated GE, Westinghouse, CONTAM Contact surface

Contactors/Starters C-H, KM degradation

20 Motor Control Center Thermal Overload Not stated GE, Westinghouse, WEAR, CURSTR Degradation of

Relays C-H, KM heater or bimetallic

elements

21 Motor Control Center Thermal Overload Not stated GE, Westinghouse, CONT, WEAR Binding of

Relays C-H, KM mechanical

components

22 Motor Control Center Thermal Overload Not stated GE, Westinghouse, CONT Contact surface

Relays C-H, KM degradation

23 Motor Control Center Thermal Overload

Relays

Not stated GE, Westinghouse,

C-H, KM

ELETEMP, EMBR Thermal degradation

of organic materials
Table A.2 Gall Report for NPAR Reports Page 48B

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K D. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recomrmendations Page No. Item

Voltage and humidity can affect energized Not stated Various . No specific Not stated 4-10, 5-15 13

insulation that is dirty or deteriorated and recommendations program for

cause surface tracking paths on the made for this

insulator. Breaker arc-chute insulation is maintenance subcomponent

especially susceptible to surface current

tracking. This can lead to flashover.

Fault currents can produce high Not stated Various No specific Not stated 4-11, 5-15 14

temperatures and currents that can recommendations program for

rapidly damage contacts, arc-chute made for this

surfaces and other organic materials, maintenance subcomponent

Continuous load currents can produce

ohmic heating in poor connections.

These can cause cb failure. I

During operation, the heat generated in Not stated Various Vendor specific Not stated 4-12, 5-16 15

the coil during energization could cause recommendations program

insulation deterioration of the coil itself. made for

This can lead to coil failure, maintenance

Prolonged coninuous energization of the Not stated Various No specific Not stated 4-12, 5-16 16

contactor coil could result in excessive recommendations program for

temperatures that cause the organic made for this

compounds that encapsulate the maintenance subcomponent

contactor to degrade. This could shorten

life and lead to coil burnout.

Cyclic fatigue can occur in magnetic Not stated Various Vendor specific Not stated 4-13,5-16 17

contactors if subjected to extremely high recommendations program

cycle operation. This can lead to heat made for

generation because of higher resistivity, maintenance

misalignment of contact, binding of

armature, preventing full contact mating

and arcing.

Binding of the contactor assembly, Not stated Various Vendor specific Not stated 4-13, 5-16 18

binding of contactor armature, binding of recommendations program,

the contactor mechanism are all caused made for replace when

by wear, vibration and contamination, maintenance failed

These can result in poor contactor/starter

operation and failure.

Dust, dirt, and foreign materal can lead to Not stated Various Vendor specific Not stated 4-13, 5-16 19

coil burnout, pitting of contact surfaces, recommendations program

and breakdown of adhesives and made for

lubricants. They can also prevent the maintenance

contact from closing. All the above can

cause the contactor or starter to fail.

In bimetallic devices, variations in the Not stated Various Vendor specific Not stated 4-14, 5-16 20

current flowing through the heater will recommendations program,

result in variations in device setpoint, made for replace when

These variations may be caused by maintenance failed

changes in the characteristics of the

heater element

Mechanical interference, dirt and friction Not stated iVarious Replace when Not stated 4-14, 5-17 21

may cause mechanical interference recommendations failed

resulting in binding of mechanical made for

components. maintenance

Dust, dirt, and foreign material can lead to Not stated Various Vendor specific Not stated 4-14, 5-17 22

coil burnout, pitting of contact surfaces, recommendations program,

and breakdown of adhesives and made for replace when

lubricants. They can also prevent the maintenance failed

contact from closing. All the above can

cause the relay to fail. I

Elevated temperatures caused by the

heaters cause aging of the heater element

support material. Failure of the support

block results in possible failure of the

overload relay to perform its required

function.

Not stated Various

recommendations

made for

maintenance

Vendor specific

program,

replace when

failed

Not stated 4-14, 5-17 23
Table A.2 Gall Report for NPAR Reports Page 49A

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K D. McCarthy, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

24 Motor Control Center Thermal Overload Not stated GE, Westinghouse, ELETEMP, Loose or high

Relays C-H, KM CORR/OX, VIBR resistance elec

connections or

terminations

25 Motor Control Center Miscellaneous Not stated GE, Westinghouse, ELETEMP Thermal breakdown

Relays C-H, KM of organic materials

26 Motor Control Center Miscellaneous Not stated GE, Westinghouse, CONT Contact surface

Relays C-H, KM degradation

27 Motor Control Center Miscellaneous Not stated GE, Westinghouse, WEAR, VIBR Wear of mechanical

Relays C-H, KM parts

28 Motor Control Center Miscellaneous Not stated GE, Westinghouse, ELETEMP, Loose or high

Relays C-H, KM CORR/OX, VIBR resistance elect

connections or

terminations

29 Motor Control Center Miscellaneous Not stated GE, Westinghouse, VOLTSTR Coil dielectric

Relays C-H, KM breakdown

30 Motor Control Centes Control Not stated GE, Westinghouse, ELETEMP Winding insulation

Transformers C-H, KM degradation

31 Motor Control Centes Control Not stated GE, Westinghouse, CURSTR Winding conductor

Transformers C-H, KM failure

32 Motor Control Center Control Not stated GE, Westinghouse, ELETEMP, Loose or high

Transformers C-H, KM CORR/OX, VIBR resistance elect

connections or

terminations

33 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, ELETEMP, Loose or high

C-H, KM CORR/OX, VIBR resistance elect

connections or

terminations

34 Motor Control Center! Terminal Blocks Not stated GE, Westinghouse, ELETEMP, EMBR,

C-H, KM I ENVIR

Degradation or

organic materials
Table A.2 Gall Report for NPAR Reports Page 49B

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K. D. McCarthy, INEL

Effect of Aaina on Comoonent Function Contrib to Failure Reported Droas Rel.proas Report Recoin mendations Paae No. Item

Operation of the relay and non-seismic Not stated Various Vendor specific Not stated 4-15, 5-17 24

vibration cause loose connections. recommendations program

Oxidation or contamination of contact made for

surfaces and sharp bends in wiring near maintenance

terminations can cause high resistance

connections. These can cause excessive

heating or fire.

Prolonged continuous energization of the Not stated Various No specific Not stated 4-12, 5-17 25

relay could result in excessive recommendations program for

temperatures that cause the organic made for this

compounds that encapsulate the maintenance subcomponent

contactor to degrade. This could shorten

life and lead to coil burnout.

Dust, dirt, and foreign material can lead to Not stated Various No specific Not stated 4-15, 5-17 26

coil burnout, pitting of contact surfaces, recommendations program for

and breakdown of adhesives and made for this

lubricants. They can also prevent the maintenance subcomponent

contact from closing. All the above can

cause the relay to fail.

Wear can lead to setpoint drift, Not stated Various No specific Not stated 4-17, 5-17 27

mechanical fatigue, surface burning recommendations program for

caused by arcing, and insulation made for this

deterioration. These can result in reduced maintenance subcomponent

mechanical tolerances, jamming and

binding of moving parts.

Operation of the relay and non-seismic Not stated Various No specific Not stated 4-17, 5-17 28

vibration cause loose connections, recommendations program for

Oxidation or contamination of contact made for this

surfaces and sharp bends in wiring near maintenance subcomponent

terminations can cause high resistance

connections. These can cause excessive

heating or fire.

Inductive voltage surges resulting from Not stated Various No specific Not stated 4-18, 5-17 29

current interruptions can stress the relay recommendations program for

coil. The inductive surge may cause coil made for this

dielectric breakdown at the weak points in maintenance subcomponent

the insulation, which can rapidly lead to

insulation failure.

Ohmic heating and breaker internal Not stated Various No specific Not stated 4-18, 5-17 30

ambient conditions cause elevated recommendations program for

temperatures which lead to winding made for this

insulation degradation. This can produce maintenance subcomponent

shorted transformer winding, resulting in

faulty voltage/current transformation or

open circuit conditions.

Primary or secondary winding failure can Not stated Various No specific Not stated 4-18, 5-17 31

result from continuous use for extended recommendations program for

periods or from excessive current drawn made for this

through the winding from attached control maintenance subcomponent

power loads.

Non-seismic vibration can cause loose Not stated Various No specific Not stated 4-18, 5-17 32

connections. oxidation or contamination of recommendations program for

contact surfaces and sharp bends in made for this

wiring near terminations can cause high maintenance subcomponent

resistance connections. These can cause

excessive heating or fire.

Operation of motor control center Not stated Various No specific Not stated 4-19, 5-17 33

components and non-seismic vibration recommendations program for

cause loose connections. Oxidation or made for this

contamination of surfaces and sharp maintenance subcomponent

bends in wiring near terminations cause

high resistance connections. These can

lead to heating or fire. I I I

Terminal blocks and the organic glue or

agent used to mount them may degrade

because of ohmic heating, ambient

temperature, humidity and vibration. This

can result in embrittlement of the terminal

blocks and loosening from their mounting

surfaces.

Not. stated Various

recommendations

made for

maintenance

No specific

program for

this

subcomponent

Not stated 4-19, 5-17 34
Table A.2 Gall Report for NPAR Reports Page 50A

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K. D. McCarthy, INEL

Item System Structure/ComD SubcomDonent Materials Manufacturer ARD mechanism ARD effects

35 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, EXFORCE, Degradation of

C-H, KM MECHSTR terminal block

hardware

36 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, MOIST-EL, Loss of surface

C-H, KM CONTAM, ENVIR insulating properties

37 Motor Control Center Terminal Blocks Not stated GE, Westinghouse, MOIST-EL, Loss of volumetric

C-H, KM CONTAM, ENVIR insulating properties

38 Motor Control Center Control Wiring Copper wire GE, Westinghouse, ELETEMP, EMBR Insulation

insulated by ethylene C-H, KM degradation

propylene rubber or X-linked poly

39 Motor Control Center Control Wiring Copper wire GE, Westinghouse, ELETEMP Conductor

insulated by ethylene C-H, KM degredation

propylene rubber or

X-linked poly

40 Motor Control Center Control Wiring Copper wire GE, Westinghouse, VIBR, CORR/OX, Loose or high

insulated by ethylene C-H, KM ELETEMP, CONT, resistance elect

propylene rubber or EXFORCE connections or

X-linked poly terminations

41 Motor Control Center Fuse Not stated GE, Westinghouse, FAT Cyclic failure

C-H, KM

42 Motor Control Center Fuse Not stated GE, Westinghouse, CORR/OX, CONT High resistance

C-H, KM contact surfaces

43 Motor Control Center Fuse Not stated GE, Westinghouse, ELETEMP, Loose or high

C-H, KM CORR/OX, VIBR, resistance elect

CONT connections or

terminations

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K. D. McCarthy, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Battery Container Polycarbonate, C&D, GNB, Exide CORR/SCC, Cracks in container

styrene acrylonitrile, ELOTEMP, FAT

butadiene, styrene

2 Battery Electrolyte Sulfuric acid and

water

C&D, GNB, Exide CONTAM Electrolyte

consumed, water

loss
Table A.2 Gall Report for NPAR Reports Page SOB

Document: SAND93-7069, Aging Management Guideline for Commercial Nuclear Power Plants - Notor Control Centers

Reviewed by: K. D. McCarthy, INEL

Effect of Aaina on Comnonent Function Contrib to Failure Reported Droas Rel.mroas Report Recom,miendations Paae No. Item

Terminal block hardware degrades Not stated Various No specific Not stated 4-19, 5-17 35

primarily as a result of stresses produced recommendations program for

during normal use. Improper made for this

maintenance techniques exacerbates this maintenance subcomponent

degredation.

Voltage and humidity can affect energized Not stated Various No specific Not stated 4-20, 5-17 36

insulation that is dirty or deteriorated and recommendations program for

cause surface tracking paths on the made for this

insulator. This can lead to flashover. maintenance subcomponent I

Simultaneous exposure to thermally Not stated Various No specific Not stated 4-20, 5-17 37

deteriorated insulation to temp, voltage, recommendations program for

humidity, dirt and contaminants can result made for this

in loss of volumetric insulating properties, maintenance subcomponent

leading to increased surface and

volumetric leakage currents and possible

flashover.

Insulation degradation can occur with Not stated Various No specific Not stated 4-20, 5-17 38

exposure to elevated ambient recommendations program for

temperature, ohmic heating of the made for this

conductor, and excessive ohmic heating maintenance subcomponent

that accompanies high resistivity

connections.

Conductor degradation may result from Not stated Various No specific Not stated 4-20, 5-17 39

bending, pulling, or crimping of the recommendations program for

conductor or from localized heating (either made for this

from an external heat source or ohmic maintenance subcomponent

heating within the wire).

Loose or high resistance connections or Not stated Various No specific Not stated 4-21, 5-17 40

terminations may occur from bending or recommendations program for

pulling on wire, vibration of components, made for this

inadequate torquing of fasteners, or maintenance subcomponent

oxidation/corrosion/contamination of

contact surfaces.

Cyclic fatigue of the fuse holder is Not stated Various No specific Not stated 4-21, 5-18 41

primarily associated with the installation or recommendations program for

removal of fuse elements; usually some made for this

sort of frictional arrangement is employed maintenance subcomponent

to keep the fuse secure and properly

connected.

High resistance contact surfaces may Not stated Various Vendor specific Not stated 4-21, 5-18 42

result from corrosion, oxidation, or recommendations programs

contamination of the surfaces in contact made for

with the fuse element itself. This condition maintenance

may result in a loss of continuity or

increased localized heating.

Loose or high resistance connections or Not stated Various No specific Not stated 4-21, 5-18 43

terminations may occur from vibration of recommendations program for

components, inadequate torquing of made for this

fasteners, or maintenance subcomponent

oxidation/corrosion/contamination of

contact surfaces.

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K 0. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Cracks in container caused by Not stated IEEE Std-450,535, Tech Spec. Not stated 4-17, 21, 1

mishandling during 10 CFR surveillance, 25, 26

maintenance/installation, seismic events, 50.49,NMAC TR- RG 1.129,

plate growth and improper use of grease 100248 IEEE 450

or cleaning solvents lead to electrolyte

leakage resulting in reduced capacity.

Sulfation caused by undercharging &

impurities consume electrolyte and results

in reduced capacity.

Not stated IEEE Std-450,535,

10 CFR

50.49,NMAC TR100248

Tech Spec.

surveillance,

RG 1.129,

IEEE 450

Not stated 4-23 2
Table A.2 Gall Report for NPAR Reports Page 51A

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

3 Battery Electrolyte Sulfuric acid and C&D, GNB, Exide GAS, ELETEMP Gassing causes

water water loss from

electrolyte

Battery Plates Lead antimony, lead C&D, GNB, Exide FAT, ELETEMP, Increased

calcium, lead MECHSTR mechanical stress

on plates

5 Battery Plates Lead antimony, lead C&D, GNB, Exide GAS Active material

calcium, lead shedding from plates

6 Battery Plates Lead antimony, lead C&D, GNB, Exide CORR/OX Increase in battery

calcium, lead internal resistance

7 Battery Plates Lead antimony, lead C&D, GNB, Exide CONTAM Local action at plate

calcium, lead

8 Battery Cell Top Straps Not stated C&D, GNB, Exide CORR/OX Increased battery

internal resistance

9 Battery Cell Top Straps Not stated C&D, GNB, Exide FAT Increased

mechanical stress

on cell top straps

10 Battery Separators Rubber/glass mat, C&D, GNB, Exide Not stated Hydration caused by

polyethylene electrolyte low

specific gravity

11 Battery Separators Rubber/glass mat, C&D, GNB, Exide ELETEMP Thermal aging

polyethylene caused by excessive

electrolyte

temperature

12 Battery Terminal Posts Lead alloy, copper C&D, GNB, Exide CORR High connection

inserts resistance and

embrittlement of

material

13 Battery Terminal Posts Lead alloy, copper

inserts

C&D, GNB, Exide FAT Cracked or broken

terminal posts
Table A.2 Gall Report for NPAR Reports Page SIB

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Effect of Aaina on ComDonent Function Contrib to Failure Reported Droas Rel.nroas Report Recommendations Paie No. Item

Gassing and electrolyte evaporation occur Not stated IEEE Std- Tech Spec. Not stated 4-23 3

from overcharging and excessive 450,535,10 CFR surveillance,

temperatures. Gassing and evaporation 50.49, NMAC TR- RG 1.129,

main cause of water loss in electrolyte. 100248 IEEE 450

Results in reduced capacity.

Repeated thermal and mechanical Not stated IEEE Std- Tech Spec. Not stated 4-22 4

stresses from battery charge/discharge 450,535,10 CFR Surveillance,

cycles and seismic events can cause loss 50.49, NMAC TR- IEEE 450-1987

of active material or loss of electrical 100248

continuity, resulting in reduced battery

capacity or total loss of battery output.

Active material shedding from plates Not stated IEEE Std- Tech Spec. Not stated 4-23 5

results in sediment buildup at the bottom 450,535,10 CFR Surveillance,

of cell. this can cause short circuits 50.49, NMAC TR- IEEE 450-1987

between the positive and negative plates, 100248

resulting in reduced capacity and

eventually the inability to hold a charge.

Corrosion caused by oxidizing Not stated IEEE Std- Tech Spec. Not stated 4-22 6

environment that exists at the positive 450,535,10 CFR Surveillance,

plates. Plates become brittle and break 50.49, NMAC TR- IEEE 450-1987

down, decreasing their cross sectional 100248

area and increasing resistance. This

leads to seismic vulnerability and

decreased battery capacity.

Electrochemical reactions due to Not stated IEEE Std- Tech Spec. Not stated 4-21 7

impurities in the electrolyte cause local 450,535,10 CFR Surveillance,

action at the plates resulting in decreased 50.49, NMAC TR- IEEE 450-1987

battery capacity and potential 100248

overcharging of the positive plates.

Corrosion caused by oxidizing Not stated IEEE Std- Tech Spec. Not stated 4-22 8

environment that exists at the positive 450,535,10 CFR Surveillance,

plates. Straps become brittle and break 50.49, NMAC TR- IEEE 450-1987

down, decreasing their cross sectional 100248

area and increasing resistance. This

leads to seismic vulnerability and

decreased battery capacity.

Repeated thermal and mechanical Not stated IEEE Std- Tech Spec. Not stated 4-22 9

stresses from battery charge/discharge 450,535,10 CFR Surveillance,

cycles and seismic events can cause 50.49, NMAC TR- IEEE 450-1987

fatigue failure. This can cause loss of 100248

electrical continuity, resulting in reduced

battery capacity or total loss of output.

Hydration causes material chemical Not stated IEEE Std- No program Not stated 4-21 10

changes in separators. Formation of 450,535,10 CFR specific to this

metallic lead on surface of separators 50.49, NMAC TR- material

builds numerous short circuit paths 100248

between pos & neg plates, resulting in

inability to hold charge. I

Excessive electrolyte temp caused by Not stated IEEE Std- No program Not stated 4-23 11

overcharging or excessive ac ripple on the 450,535,10 CFR specific to this

charger output reduces dielectric strength 50.49, NMAC TR- material

of separator mat'l and causes structural 100248

deterioration, resulting in reduced battery

capacity or inability to hold charge.

High connection resistance and Not stated IEEE Std- Tech. Spec. Not stated 4-22 12

embrittiement of material in terminal posts 450,535,10 CFR surveillance,

results in decreased battery output and 50.49, NMAC TR- IEEE 450-1987

overheating of the posts. 100248

Repeated or improper torquing of

connections during instal/maint can result

in cracked or broken terminal posts. This

results in increased connection resistance

or loss of electrical continuity, resulting in

reduced capacity or loss of battery output.

Not stated IEEE Std450,535,10 CFR

50.49, NMAC TR100248

Tech. Spec.

surveillance,

IEEE 450-1987

Not stated 4-22 13
Table A.2 Gall Report for NPAR Reports Page 52A

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Item SytmStructure/Come Subcomaonent Materials Manufacturer AFliD mechanism ARD effects

14 Battery Terminal Posts Lead alloy, copper C&D, GNB, Exide CORR Fouling of terminal

inserts posts

15 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide CORR High connection

bars resistance,

embrittlement

16 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide FAT Cracked or broken

bars intercell connectors

17 Battery Intercell Connectors Lead plated copper C&D, GNB, Exide CORR Fouling of intercell

bars connectors

18 Battery Terminal Post Seals Not stated C&D, GNB, Exide FAT Cracking of the

terminal post seals

19 Battery Battery Racks Steel Not stated CORR, FAT Rack structure

weakened

20 Battery Container Polypropylene C&D, GNB, Exide CORR/SCC, FAT Cracks in container

21 Battery Container Polypropylene C&D, GNB, Exide FAT Fatigue cracking of

cover

22 Battery Electrolyte Potassium C&D, GNB, Exide Not stated Decreased

Hydroxide conductivity of

electrolyte

23 Battery Electrolyte Potassium C&D, GNB, Exide GAS Gassing causes

Hydroxide water loss from

electrolyte

24

Battery Plates Nickel hydroxide,

cadmium hydorxide

C&D, GNB, Exide Not stated Aging of active

material
Table A.2 Gall Report for NPAR Reports Page 52B

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Effect of Aaina on ComDonent Function Contrib to Failure Reoorted oroas Rel.proas Report Recommendations Paqe No. Item

Fouling of terminal posts can occur due to Not stated IEEE Std- Tech. Spec. Not stated 4-24 14

accumulation of dirt, dust, and leaked 450,535,10 CFR surveillance,

electrolyte. This can cause corrosion at 50.49, NMAC TR- IEEE 450-1987

the electrical connections, short circuits, 100248

and battery grounding, resulting in

degraded battery output, discharge or

overheating. I

Excessive ambient humidity, external dust Not stated IEEE Std- Tech. Spec. Not stated 4-22 15

and dirt, electrolyte leaks and spills can 450,535,10 CFR surveillance,

cause corrosion of connectors. This 50.49, NMAC TR- IEEE 450-1987

results in high connection resistance and 100248

embritilement resulting in decreased

battery output and overheating of

connectors.

Repeated or improper torquing of Not stated IEEE Std- Tech. Spec. Not stated 4-22 16

connections during install/maint can result 450,535,10 CFR surveillance,

in cracked or broken intercell connectors. 50.49, NMAC TR- IEEE 450-1987

This results in increased connection 100248

resistance or loss of elec continuity,

resulting in reduced capacity or loss of

battery output.

Fouling of intercell connectors can occur Not stated IEEE Std- Tech. Spec. Not stated 4-24 17

due to accumulation of dirt, dust, and 450,535,10 CFR surveillance,

leaked electrolyte. This can cause 50.49, NMAC TR- IEEE 450-1987

corrosion at the electrical connections, 100248

short circuits, and battery grounding,

resulting in degraded output, discharge or

overheating.

Fatigue failures can occur in post seals Not stated IEEE Std- Tech. Spec. Not stated 4-23 18

due to improper handling, plate growth, 450,535,10 CFR surveillance,

excessive corrosion which stresses the 50.49, NMAC TR- IEEE 450-1987

seals and covers. This can cause a loss 100248

of electrolyte and venting of gases,

resulting in reduced capacity or loss of

output..

Electrolyte leaks or spills, humidity and Not stated IEEE Std- Tech. Spec. Not stated 4-22 19

high temp can cause corrosion of battery 450,535,10 CFR surveillance,

rack which can weaken the structure. 50.49, NMAC TR- IEEE 450-1987

This can cause structural failure and loss 100248

of supported battery.

Damage to container is caused by Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-25 20

improper use of greases and cleaning CFR 50.49,EPRI surveillance,

solvents which react with container NMAC TR-1 0248 IEEE 1106-

material or weaken the structure. This 1987

can lead to reduced capacity.

Thermal expansion and improper handling Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-25 21

introduce stresses to container cover CFR 50.49,EPRI surveillance,

which can cause cracking. This can result NMAC TR-1 0248 IEEE 1106-

in gas release, possible air intrussion, and 1987

loss of electrolyte which may result in

conductive paths to ground and loss of

capacity.

Material chemical changes occur due to Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-24 22

carbonation of potassium hydroxide CFR 50.49,EPRI surveillance,

electrolyte when exposed to carbon NMAC TR-1 0248 none for this

dioxide in air, which decreases comp.

conductivity of electrolyte. This increases

battery internal resistance and decreases

capacity.

Gassing & electrolyte evaporation is due Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-26 23

to overcharging and elevated temp. CFR 50.49,EPRI surveillance,

These cause electrolyte water loss, which NMAC TR-1 0248 IEEE 1106-

will reduce battery capacity. Evaporation 1987

also contributes to water loss.

Recrystallization of the nickel hydroxide in

the positive plates causes gradual aging

of the active material. This results in

reduced capacity.

Not stated IEEE Std-1106,10

CFR 50.49,EPRI

NMAC TR-1 0248

Tech. Spec.

surveillance,

none for this

comp.

Not stated 4-24 24
Table A.2 Gall Report for NPAR Reports Page 53A

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Item Svstem StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

25 Battery Separators Plastic C&D, GNB, Exide ELETEMP Reduced delectric

strength of separator

material

26 Battery Terminal Posts Not stated C&D, GNB, Exide CORR Failure of terminal

posts

27 Battery Terminal Posts Not stated C&D, GNB, Exide FAT Cracked or broken

terminal posts

28 Battery Terminal Posts Not stated C&D, GNB, Exide CORR Corrosion, short ckts

and grounding

caused by fouling

29 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide CORR Failure of intercell

bars with stainless connectors

steel hardware

30 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide FAT Cracked or broken

bars with stainless intercell connectors

steel hardware

31 Battery Intercell Connectors Nickel-plated copper C&D, GNB, Exide CORR Corrosion, short

bars with stainless ckts, grounding

steel hardware caused by fouling

32 Battery Terminal Post Seals Not stated C&D, GNB, Exide FAT Fatigue cracking of

post seals

33 Battery Battery Racks Steel Not stated CORR, FAT Rack structure

weakened

34 Battery Pressure Relier Not stated Not stated Not stated Malfunction of valve

Valve

35 Battery Electrolyte Not stated Not stated Not stated Dryout of electrolyte

36 Battery Electrolyte Not stated Not stated ELETEMP Thermal runaway
Table A.2 Gall Report for NPAR Reports Page 53B

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K. D. McCarthy, INEL

Effect of Aqinq on Component Function Contrib to Failure Reported proqs Rel.proqs Report Recommendations Paqe No. Item

Overcharging or excessive ac ripple on Not stated IEEE Std-1 106,10 No program Not stated 4-26 25

charger output cause excessive CFR 50.49,EPRI specific to this

electrolyte temp which reduces the NMAC TR-10248 subcomponent

dielectric strength of separator matl &

deteriorates mech strength. This results

in reduced capacity & eventual inability to

hold charge.

Humidity, dust, and elevated temperatures Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-25 26

can lead to corrosion of the terminal CFR 50.49,EPRI required

posts. This can lead to failure of terminal NMAC TR-10248 surveillance.

posts. IEEE 1106

Repeated or improper torquing of Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 2-25 27

connections can result in cracked or CFR 50.49,EPRI required

broken terminal posts. This results in NMAC TR-10248 surveillance.

increased connection resistance or loss of IEEE 1106

continuity. This results in reduced

capacity or total loss of output. I

Fouling of terminal posts caused by Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-24 28

accumulation of dirt dust, and leaked CFR 50.49,EPRI required

electrolyte can cause corrosion, short NMAC TR-1 0248 surveillance.

circuits between pos and neg posts, and IEEE 1106

battery grounding. This results in

degraded output batt discharge, or

overheating of connections. I

Humidity, dust, and temperature can lead Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-25 29

to corrosion of intercell connectors. This CFR 50.49,EPRI required

can lead to failure of the intercell NMAC TR-1 0248 surveillance.

connectors. _IEEE 1106

Repeated or improper torquing of Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-25 30

connections can result in cracked or CFR 50.49,EPRI required

broken intercell connectors. This results NMAC TR-1 0248 surveillance.

in increased connection resistance or loss IEEE 1106

of continuity which reduces battery

capacity or results in total loss of battery

output.

Dirt, dust, and leaked electrolyte cause Not stated IEEE Std-1 106,10 Tech. Spec. Not stated 4-26 31

fouling of intercell connectors, fouling CFR 50.49,EPRI required

coupled with moisture condensation leads NMAC TR-10248 surveillance.

to corrosion, which causes current paths IEEE 1106

to ground. This results in degraded batt

output discharge or overheating of

connections.

Excessive stresses caused by thermal Not stated IEEE Std- 1106,10 Tech. Spec. Not stated 4-25 32

expansion, corrosion of terminal posts, CFR 50.49,EPRI required

and improper handling can lead to fatigue NMAC TR-10248 surveillance.

cracking of terminal post seals, leading to IEEE 1106

gas release, air intrusion, loss of

electrolyte. Results in conductive paths to

ground. I

Humidity, dust accumulation, and Not stated IEEE Std-1106,10 IEEE 1106- Not stated 4-25 33

temperature can lead to corrosion in the CFR 50.49,EPRI 1987

battery racks. This can cause structural NMAC TR-1 0248

failure and loss of supported battery.

Wear occurs due to relative movement Not stated IEEE Std-1 106,10 No program Not stated 4-27 34

between contacting internal parts and can CFR 50.49,EPRI specific to this

cause malfunction of valve. This can NMAC TR-1 0248 subcomponent

allow gases and vapors to escape,

resulting in lowered gas recombination

efficiency. This can lead to dryout.

Overcharging, elevated temperatures, Not stated IEEE PAR 1188, 10 Tech. Spec. Not stated 4-27 35

failed pressure relief valve or cracked CFR 50.49, NMAC surveillance,

container or seal can lead to dryout of TR-100248 IEEE 450 &

electrolyte. This can result in battery 1106

failure. I _ I I

Elevated temperature, improper (high)

float voltage, or excessive ac ripple from

battery charger can cause thermal

runaway. This can result in battery

failure.

Not stated IEEE PAR 1188, 10

CFR 50.49, NMAC

TR-100248

Tech. Spec.

surveillance,

IEEE 450-1987

Not stated 4-28 36
Table A.2 Gall Report for NPAR Reports Page 541A

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects 37j Battery Electrolyte jNot stated Not stated Not stated Memory effect

Document: TIRGALEX, Plan for Integration of Aging and Ufe-Extension Activities

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Cable Not stated Not stated Not stated ELETEMP, RAD, Not stated

MOIST-EL, & VIB.

2 Conectors Not stated Not stated Not stated ELETEMP, RAD, Not stated

MOIST-EL, & VIB.

Switchgear Not stated Not stated Not stated WEAR & LOSLUB Not stated

4 Relays Not stated Not stated Not stated CORR, WEAR, & Not stated

ELETEMP

Document: WYLE 60103-1, Test Plan of Molded Case Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plar

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Vl Molded Case Circuit 15 Relay Types and 3 Not stated Three mfg. listed Not stated Not stated

Breakers Types of Circuit II Breakers

Document: WYLE 60103-2, Test Plan of Metal Clad Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for ---- NPAR Prc

Reviewed by: L. C. Meyer, INEL

Document: WYLE 60103-3, Test Plan of Auxiliary Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- (NPAR) Program Phasi

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

I 1 Auxiliary Relays Not stated Not stated Westinghouse Not stated Not stated

Document: WYLE 60103-4, Test Plan of Control Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for ---- (NPAR) Program, Phas

Reviewed by: L.C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1T IControl Relays Not stated INot stated Three mfg.s listed INot stated INot stated

Document: WYLE 60103-5, Test Plan of Protective Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Rese

Reviewed by: L. C. Meyer, INEL

Item System Structure(Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1l1 1 Protective Relays INot stated Not stated GE & Westinghouse Not stated INot stated
Table A.2 Gall Report for NPAR Reports Page 54B

Document: SAND93-7071, Aging Management Guideline for Commercial Nuclear Power Plants - Stationary Batteries

Reviewed by: K D. McCarthy, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Relprogs Report Recommendations Page No. Item

Successive small discharge cycles can Notstated IEEE PAR 1188,0 Tech. Spec. Not stated 4 37

lead to a memory effect in a sintered plate CFR 50.49, NMAC surveillance,

nickel-cadmium battery. This can result TR-100248 IEEE 450-1987

in reduced capacity. ___

Document: TIRGALEX, Plan for Integration of Aging and Life-Extension Activities

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated IBE79-01, NUREG- No specific Five recommendations are given for A31-A36 1

0588, 10CFR 50.49, program resoMng aging and life extension

& RG 1.89 issues [4]

Not stated Not stated IBE79-01, NUREG- No specific Five recommendations are given for A31-A36 2

0588, 10CFR 50.49, program resolving aging and life extension

& RG 1.89 issues [1]

Not stated Not stated Generic Letter 83-28 IEEE 741-1986 Three issues requiring followup are A51 & 3

concerns and Tech Section 7 listed. [1] A53

Specs

Not stated Not stated Generic Letter 83-28 Dependent Followup on calibration frequency for A52 & 4

concerns and Tech upon type and protective relays, seismic fragility, A53

Specs function of the and effect of common mode failure

I relay on safety [1] 1 1

Document: WYLE 60103-1, Test Plan of Molded Case Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plani

Reviewed by: L. C. Meyer, INEL iNotstae Effect of Aging on Component Function INot Contrib to Failure I~ Reported ~ progs Rel.progs °I~ Report Recommendations Page No. Item

report program, _ _ _ _ _ _te JNot discussed in No staepecific Not stated111 I application

__7 dependent

Document: WYLE 60103-2, Test Plan of Metal Clad Circuit Breakers for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- NPAR Pro!

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in RG 1.118, Not stated

report IEEE 338-

I I 1987, TECH.

SPEC. MAINT.

Document: WYLE 60103-3, Test Plan of Auxiliary Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for --- (NPAR) Program Phase

Reviewed by: L C. Meyer, INEL

Document: WYLE 60103-4, Test Plan of Control Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for ---- (N PAR) Program, Phas

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in No specific Not stated 3"1 1

report program 131 F

Document: WYLE 60103-5, Test Plan of Protective Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Rese

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

INotstated Not stated Not discussed in Tech Spec Not stated 4-1 1

IIreport isurveillance III II
Table A.2 Gall Report for NPAR Reports Page 55A

Document: WYLE 60103-6, Test Plan of Timing Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Reseai

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Tiin Reas Ntsae Not stte Agatat OXI DAT Degradation caused I'1~~~ Reay No sttdsIe Iiin a by oxidation surfacel

Document: WYLE 60103-7, Test Plan of Electronic Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Res

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects
Table A.2 Gall Report for NPAR Reports Page 55B

Document: WYLE 60103-6, Test Plan of Timing Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Researc

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Relay failure due to contact oxidation Occasional Not discussed in Application 1Not stated 4-1

caused by low current application of silver report dependent,

alloy contacts. Tech Spec j Surveill.

Document: WYLE 60103-7, Test Plan of Electronic Relays for the Comprehensive Aging Assessment of Circuit Breakers and Relays for Nuclear Plant Aging Rese

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

rNot stated I Not stated I Not discussed in lApplication INot stated 14-1 1
Table A.2 Gall Report for NRC Generic Letters Page IA

Document: GL 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

11 Not stated Not stated Solenoid operated No tated Not stated Not stated Not stated

Valves 

1
Table A.2 Gall Report for NRC Generic Letters Page 1B

Document: GL 91-15, Operating Experience Feedback Report Solenoid-Operated Valve Problems at U.S. Reactors

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Reference to case report study NUREG- Not stated Not discussed in Vendor specific Review info and consider actions as 1

1275, volume 6, "Operating Experience report program appropriate [4]

Feedback Report-Solenoid-Operated

Valve Problems,' February 1991
Table A.2 Gall Report for Information Notices Page 1A

Document: IN NO. 89-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil, and Lube Oil Systems Which Render Emergency Diesel Generators Inoperat

Reviewed by: E. W. Roberts, INEL

Item System StructureIComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Document: IN NO. 89-17, Contamination and Degradation of Safety-Related Battery Cells

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

2111Battery Cells Copper Not stated CONTAM Electrolytic transfer1 Connections 111of copper to battery

___________ ___________I ________ I _________I ________ I lead term/plates

Document: IN NO. 89-20, Weld Failures in A Pump of Byron-Jackson Design

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Pump Welds Not stated Byron Jackson VIBR Weld cracks

Document: IN NO. 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters

Reviewed by: E. W. Roberts, INEL

Item System StructureIComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

141 Pressure Not stated Rose Not stated Loss of oil from

sensing module

Document: IN NO. 89-43, Permanent Deformation of Torque Switch Helical Springs in Umitorque SMA-Type Motor Operators

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Torque Switch HelicalSprings Not stated Limitorque MECHSTR Permnent

deformation of

SI_ I_ I_ I I Ihelical spring

Document: IN NO. 89-64, Electrical Bus Bas Failures

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

6 lcrclBus INoryl Insulation No ttdNot stated CONTAM EMBR Electrical ground

7 fault, short to ground

Document: IN NO. 89-66, Qualification Life of Solenoid Valves

Reviewed by: E. W. Roberts, INEL

Item System St'ucture/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

7 Duel-Coil Solenoid I Elastomer Seat Ethylene Propylene Automatc Switch CONTAM Sticky and deformedi

Valve Dimer (EPDM) Co. ELETEMP seats

Document: IN NO. 89-79, Degraded Coatings and Corrosion of Steel Containment Vessels

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

8 Containment Coatings Not stated Not stated MOIST-EL Coating failure F-1 - l~~VesselsIIIIII

Document: IN NO. 89-84, Failure of Ingersoll Rand Air Start Motors as A Result of Pinion Gear Assembly Fitting Problems

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD ni

Diesel Generator ]Air Starter Pinion 1 Tang and Retainer Not stated Ingersoll Rand WEAR
Table A.2 Gall Report for Information Notices Page I1B

Document: IN NO. 89-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil, and Lube Oil Systems Which Render Emergency Diesel Generators Inoperativ

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

,noperability of EDG Not stated Not discussed in Vendor lReview info and take actions as 1

Ireport specific, RG jappropriate. [4]

I I1.08,IEE __________387, __________1 IEEE 749 _____________-

Document: IN NO. 89-17, Contamination and Degradation of Safety-Related Battery Cells

Reviewed by: E. W. Roberts, INEL

Effect of Aqing on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Loss of battery capacity INot stated Tech. spec requires ITech. Spec. Review info and take actions as

Sexam, clean, & test IRG 1. 129, appropriate (4]

_connections IEEE 450-1987

Document: IN NO. 89-20, Weld Failures in A Pump of Byron-Jackson Design

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

recirculation loop Brke n rngan ipele otstte -fatnes Nt isuse i Vndr evewino ndtaeactions as f 3 report specific, may appropriate [4]

have Tech.

_Spec. surveil

Document: IN NO. 89-42, Failure of Rosemount Models 1153 and 1154 Transmitters

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Transmitter failure Not stated Not discussed in Bul 90-1 Suppl, Review info and take actions as 4

IIIreport 1 I appropriate [4]1

Document: IN NO. 89-43, Permanent Deformation of Torque Switch Helical Springs in Umitorque SMA-Type Motor Operators

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.proas Report Recommendations Page No. Item

Operability problem with valve motor Not stated Not discussed in Vendor Not statedsI

operator report specific,NU

[ _ _ _ __ _ __ _ _ __ _ _I _ __ _ _ I__ INUREG-1 352 _ _ _ _ _ _ _ _ _ _ I__ _ _ _

Document: IN NO. 89-64, Electrical Bus Bas Failures

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Inoperable electrical bus Not stated Not discussed in IEEE 338- lReview info and take atosa

report 71987, RG appropriate [4 I

1.118, IEEEI I

741-1986

Document: IN NO. 89-66, Qualification Life of Solenoid Valves

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Valves fall to operate as required Frequent Not discussed in Application Review info and take actions as 1 71

report dependent, appropriate [4] 1 i

may have Tech I I ______________________________ _______________Spec req ___________________

Document: IN NO. 89-79, Degraded Coatings and Corrosion of Steel Containment Vessels

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Oxidation and pitting of steel tanks Not stated Not discussed in Vendor specific Review info for applicability and take 8

Ireport lactions as appropriate [4]

Document: IN NO. 89-84, Failure of Ingersoll Rand Air Start Motors as A Result of Pinion Gear Assembly Fitting Problems

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Diesel generators would not start Frequent Not discussed in RG 1.108,IEEE Review info and consider actions asI9

report 387,IEEE appropriate [4]

749,Tech.

I I Spec. malnt.
Table A.2 Gall Report for Information Notices Page 2A

Document: IN NO. 90-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and AK Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1o Circuit Breakers Prop Reset Spring Notstated General Electric I FAT Broken spring

Document: IN NO. 90-51, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

11 Emergency n Diesel Governor Control Voltage RsNot Dropping stated Pacific Resistor I ENVIR ELTEMP I Loss of resistance

[Generator ~Power Supply I Resistor I _ I _ _ _ ~value

Documenti IN NO. 90-51-01, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems

Reviewed by: L. C. Meyer, INEL

Document: IN NO. 90-80, Sand Intrusion Resulting in Two Diesel Generators Becoming Inoperable

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manu

1 131 Diesel Generatrors 1 Cylinders I Liners and Piston I Not stated I Not stE

Document: IN NO. 91-20, Electric Wire Insulation Degradation Caused Failure in A Safety-Related Motor Control Center

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

141 1 Motor Control CenterJ Wire PCV - Vegatable oil Not stated ELTEMP Cond cover emits

plasticierR I liquid which hardens

I I I on electrical contact]

Document: IN NO. 91-45, Possible Malfunction of Westinghouse ARD, BFD, and NBFD Relays, and A200 DC and DPC 250 Magnetic Contactors

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

15Relays Coils Epoxy Westinghouse ELTEMP Epoxy becomes fluid

I I when coil is I I energized for ext.

_____________I I ____________ ____________period

Document: IN NO. 91-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

161 Diesel Generators I Filters and Injectors Not stated Not stated CONTAM Excessive

particulate, fouled

filters and injectors

Document: IN NO. 91-62, Diesel Enging Damage Caused by Hydraulic Lockup Resulting From Fluid Leakage Into Cylinders

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

171 Emergency Diesel I Diesel Engine Head Gasket Not stated Not stated Water leaksintOc !Notstated 

Generator -71cylinder

Document: IN NO. 91-78, Status Indication of Control Power for Circuit Breakers Used in Safety-Related Applications

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects [181 Indicator Lights Fuse Holders Not stated Not stated FAT Fuse holder fingers

deformed resulting |

poor elect contact
Table A.2 Gall Report for Information Notices Page 213

Document: IN NO. 90-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and AK Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

fBreaker would attempt to close but would Frequent I Not discussed in RG 1.108JIEEE lReview info and consider actions as 10

trip free 1report 387,IEEE appropriate [4]

I I 749,Tech. _____________ _____________Spec. maint ___________________

Document: IN NO. 90-51, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Edg loses speed control Frequent Scheduled RG 1.108, Review info and consider actions it Replacement IEEE 387, ~applicable [4]

______________ ________ IEEE 749 ____________ ___

Document: IN No. 90-51-01, Failures of Voltage-Resistors in the Power Supply Circuitry of Electric Governor Systems

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item.

Failure of resistor leads to govemnor power Frequent - old; Rare IScheduled TRG 1.108, Review info and consider actions if 1 &2 12

failure in new replacement assembly IEEE 749

results in a backup mechanical govemnor I

taking control of speed. _ _ _ _ _ _ _ _ _ _ _ _

Document: IN NO. 90-80, Sand Intrusion Resulting in Two Diesel Generators Becoming Inoperable

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Ilnoperable diesel generators - Not stated Not discussed in No specific Review info and consider actions if

maintenance activity introduced sand into report program applicable [4]

Idiesel cylinders I I I I

Document: IN NO. 91-20; Electric Wire Insulation Degradation Caused Failure in A Safety-Related Motor Control Center

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Insulates electrial contacts Not stated rNot discussed in No specific ]Review info and consider actions as J I 14J

sreport program appropriate (4]

Document: IN NO. 91-45, Possible Malfunction of Westinghouse ARD, BFD, and NBFD Relays, and A200 DC and DPC 250 Magnetic Contactors

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

IDegrades or delays relay function I Not stated Not discussed in No specific IReview info and consider actions if - 15 Jreport program japplicable [4]

Document: IN NO. 91-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Inoperable diesel generator Not stated Not discussed in No og specific Review info and consider actions as j 16

finperbledieel enratr Nt sate Ireport Iprogram lappropriate [4]1 ___

Document: IN NO. 91-62, Diesel Enging Damage Caused by Hydraulic Lockup Resulting From Fluid Leakage Into Cylinders

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Damage to engine will cause EDG failure Not statedr1 Not discussed t in Vendor specific Review info and consider actions asa17

IIreport Iprogram lappropriate [4]

Document: IN NO. 91-78, Status Indication of Control Power for Circuit Breakers Used in Safety-Related Applications

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Improper indication of motor operation Not stated Not discussed in Vendor specific Review info and consider actions as 18

report program appropriate [4]
Table A.2 Gall Report for Information Notices Page 3A

Document: IN NO. 91-81, Switchyard Problems That Contribute to Loss of Offsite Power

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 Swithcyard Control Zener Diodes Not stated Not stated VOLSTR Zenor diode failure

rISystem II

Document: IN NO. 91-83, Solenoid-Operated Valve Failures Resulted in Turbing Overspeed

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comle Subcomeonent Materials Manufacturer ARD mechanism ARD effects

Ite Sy te .... ....COM Su cmIn ... .. Mate .. .......... ial Ma u .. ac .. u e ..... ........... ... ....

201 Turbine Soleniod- Valves Operated tated arker Hannifin Not stated Imechanically Pilot valve assybound

Document: IN NO. 91-85, Potential Failures of Thermostatic Control Valves for Diesel Generator Jacket Cooling Water

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

21 Diesel Generator Cooling Water Thermostatic Control Not stated Not stated Not stated Valve failure F7 Systemn Valve 1

Document: IN NO. 91-87, Hydrogen Embrittlement of Raychem Cryofit Couplings

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Gas Space Cryofit Coupling T and 50% Titanium Raychem & Circumferential dMBPJHY 

Sampling Une and 50% Nickel) I fracture at the

[ ________ I I_______ I ________ I_______ ________j________jmidpoint I of coupling

Document: IN NO. 92-04, Potter & Brumfield Model MDR Rotary Relay Failures

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects F1Rotary Relay JRotor Coil 1Varnish Potter & Brumfield ICORR JDepo

on rotor

Document: IN NO. 92-27, Thermally Induced Accelerated Aging and Failure of ITE/GOULD A.C. Relaty Used in Safety-Related Applications

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Relay Plastic Armature Not stated ITE/Gould ELETEMP Brittleness and

___ __ ___ __Insulation I _ __ I_ _I I _ _ _

Document: IN NO. 92-44, Problems With Westinghouse DS-206 Type Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

251 Circuit Breaker Reset Spring Notstated Westinghouse FAT Weakened spring

Document: IN NO. 92-48, Failure of Exide Batteries

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

261 DC Power Battery cells Not stated Exdde CORR Cracking of battery 7 1J_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J _ _ _ _ _ 

fa c e

Document: IN NO. 92-78, Piston to Cylinder Uner Tin Smearing On Cooper=Bessemer KSV Diesel Engines

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Diesel Generator Cylinders Walls Not stated Cooper Bessemer CORR Transfer of tin from

KSV cyl. walls and

_______________ ______________________________ ______________________________ I_________lubricaluriitio
Table A.2 Gall Report for Information Notices Page 313

Document: IN NO. 91-81, Switchyard Problems That Contribute to Loss of Offsite Power

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Loss of switchyard control Not stated Not discussed in RG 1.118, Review info and consider actions as

report IEEE 741-1986 jappropriate [4)

ISection 7 1ap p9t

Document: IN NO. 91-83, Solenoid-Operated Valve Failures Resulted in Turbing Overspeed

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Valves failed to close allowing steam to Not stated Not discussed in Vendor specific Review info and consider actions as

cause turbine overspeed report program appropriate [4]

Document: IN NO. 91-85, Potential Failures of Thermostatic Control Valves for Diesel Generator Jacket Cooling Water

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Overheating of diesel generator Not stated Not discussed in Vendor specific Review info and consider actions as 21

IIIreport program jappropriate [4] T

Document: IN NO. 91-87, Hydrogen Embrittlement of Raychem Cryofit Couplings

Reviewed by: L, C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The fractured coupling allowed a reactor Rare 1 Not discussed in No specific Not stated 1 coolant system leak that exceded the 1.0 report program

gpm technical specification limit. I I I I

Document: IN NO. 92-04, Potter & Brumfield Model MDR Rotary Relay Failures

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Mechanical binding of rotor and failure of Not stated Not discussed in Vendor specific IReview info and consider actions as 1231

[relay to operate properly within 2 to 5 sttdreport program ~applicable [4) osdratosa

1years after installation

Document: IN NO. 92-27, Thermally Induced Accelerated Aging and Failure of ITE/GOULD A.C. Relaty Used in Safety-Related Applications

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

[Coil shorts and relay fails to operate Not stated Not discussed in Vendor specificTReviewinfo and consider actions as 24

. __report 

I program appropriate [4]

Document: IN NO. 92-44, Problems With Westinghouse DS-206 Type Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Breaker fails to open when required Not stated Not discussed in Vendor specific Review info and consider action as 25

IIIreport Iprogram lappropriate [4]

Document: IN NO. 92-48, Failure of Exide Batteries

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Lekgeo ndbttr eetrlti cl NtsttdNot discussed in RG 1.129, Review info and consider atoas26}

failure report IEEE 450- applicable [4)

I1987, Tech.

J Spec. Surveil.

Document: IN NO. 92-78, Piston to Cylinder Liner Tin Smearing On Cooper=Bessemer KSV Diesel Engines

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Crankcase explosions and diesel failure rNot stated Not discussed in No specific Review info and consider actions as 271

___ ___ ___ ___ __ __ ___ __I _ ___ __ ___ Ireport program appropriate [4] j_ _ _
Table A.2 Gall Report for Information Notices Page 4A

Document: IN NO. 93-05, Storm-Related Loss of Offsite Power Events Due to Salt Buildup on Switchyard Insulators

Reviewed by: E. W. Roberts, INEL

Document: IN NO. 93-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers due to Support Lever Failure

Reviewed by: E. W. Roberts, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

291 Mold-Case Circuit Support Lever Polycarbonate & Kiockner Moeller CORR FAT 1eFractured support [~[Breakers j(Spring Arm) Glass fiber[er

Document: IN NO. 93-23, Weschler Instruments Model 252 Switchboard Meters

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

30 Indicating Meters I Meter Movement I Not stated Weschler ADH Sticking movement

Document: IN NO. 93-26, Grease Solidification Causes Molded-Case Circuit Breaker Failure to Close

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

31 Mold-Case Circuit Grease Soap-based or clay- I General Electric EaNVIR Drying out of grease,

Breakers based grease Ifriction, gouging of

I111 metal-to-metal

Document: IN NO. 93-33, Potential Deficiency of Certain Class 1 E Instrumentation and Control Cables

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

32 Cables Not stated Not stated REFERENCE Reference nureg/cr- INUREG/CR-5

15772

Document: IN NO. 93-64, Periodic Testing and Preventive Maintenance of Modled Case Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

33 Circuit Breakers Not stated Westinghouse Not stated Thermaland

Type EB and EHB instantaneous trip

not within

specifications

Document: IN NO. 94-04, Digital Integrated Circuit Sockets With Intermittent Contact

Reviewed by: E. W. Roberts, INEL

Item System St'ucture/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1341 1Digital Board Socket Contacts Tin-lead Augat CORR/OX Contact failure

Document: IN NO. 94-33, Capacitor Failures in Westonghouse Easge 21 Plant Protection Systems

Reviewed by: E. W. Roberts, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

351 Westinghouse Eagle, ASTEC America DC Electrolytic Epoxy module AVX ELTEMP Capacitor failure

21 plant protection I Power Supply Capacitors

system I
Table A.2 Gall Report for Information Notices Page 4B

Document: IN NO. 93-05, Storm-Related Loss of Offsite Power Events Due to Salt Buildup on Switchyard Insulators

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Loss of offsite ac power Not stated Not discussed in IEEE 765- Review info and consider actions as 28

Ireport 1983, Plant appropriate [4]

specific _ _ _ _ _ _ __ _

Document: IN NO. 93-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers due to Support Lever Failure

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Breakers tripped without cause f Not stated Not discussed in No specific Review info and consider actions as

1 1 1 report I program lappropria t

e [4]

Document: IN NO. 93-23, Weschler Instruments Model 252 Switchboard Meters

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Inaccurate meter indications Not stated Not discussed in No specific Review info and consider actions as 301

11report Iprogram lappropriate [4]11

Document: IN NO. 93-26, Grease Solidification Causes Molded-Case Circuit Breaker Failure to Close

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Breaker falls to close Not stated Not discussed in No specific Review info and consider actions as

report program lappropriate [4]

Document: IN NO. 93-33, Potential Deficiency of Certain Class 1 E Instrumentation and Control Cables

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

References the result of the NUREG Not stated Not discussed in No specific Review info and consider actions as

Ireport to evaluate plant cables reportI program jappropriate [4]11

Document: IN NO. 93-64, Periodic Testing and Preventive Maintenance of Modled Case Circuit Breakers

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs_ Rel.progs Report Recommendations Page No. Item

Age, failure to excercise, and lack of Not stated Not discussed in Vendor specific Review info and consider actions as 33

maintenance caused breakers trips to go report program, Tech, appropriate [4]

out of specifications ISpec.

Document: IN NO. 94-04, Digital Integrated Circuit Sockets With Intermittent Contact

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Not stated Not stated Not discussed in No specific Review info and consider action as 341 111reportI program jappropriate [4]

Document: IN NO. 94-33, Capacitor Failures in Westonghouse Easge 21 Plant Protection Systems

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Power supply failure Not stated Not discussed in Vendor specific Review info and consider actions as 351

111report Iprogram lappropriate [4]11
Table A.2 Gall Report for Licensee Event Reports Page 1A

Document: LER 88-011-282, Auto-Start of Train A of Auxiliary Building Special Ventilation System as a result of a Radiation Monitor Spike

Reviewed by: L.C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 Ventilation System Radiation Monitor Not stated Not stated Not stated Not stated Rad monitor spike -

attributed to age of

rad mon equipment

Document: LER 88-033-02-327, Unplanned Reactor Trip Signal Due to a Reactor Protection System (RPS) Channel 1 Instrument Failure During RPS Channel 2 C

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

2 Reactor Protection Not stated Not stated Not stated Foxboro Not stated Two transistors

System shorted and bridge

assembly open

circuited

Document: LER 89-001-280, Unplanned Auto Start of #3 EDG Due to Failed Diode

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

V3 Diesel Generator Control Circuit Diode Not stated GM Electro-Motive Not stated Failed diode caused

___________ JDivision jstart relay to actuate

Document: LER 89-002-331, Age-Related Failure of a Governor Printed Circuit Board Results in High Pressure Coolant Injection System Inoperability

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

4 High Pressure Turbine Governor Printed Circuit Board Not stated Woodward Governor ELETEMP Intermitant electronic

Injection System Component Company componet output

Document: LER 89-003-263, Isolation of Reactor Water Cleanup System Due to Capacitor Failure in Filter/Demineralizer Inlet Temperature Indication Switch

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Document: LER 89-006-261, Reactor Trip Due to Loss of Turbine E-H Control Power Supplies

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

6 Turbine Control Power Supply Transistor Not stated JSolid State Controls CURSTR & Transistors

Inc. VOLSTR developed leakage

current

Document: LER 89-010-362, Fuel Handling Isolation System Train 'A" Actuation Due to Power Supply Failure

Reviewed by: L. C. Meyer, INEL
Table A.2 Gall Report for Licensee Event Reports Page 11B

Document: LER 88-011-282, Auto-Start of Train A of Auxiliary Building Special Ventilation System as a result of a Radiation Monitor Spike

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Auto-start of aux building ventilation Not stated 10 CFR 50.73 Vendor specific Not stated 1-3 1

system when not called for. The program

electronics was 16 years old. Root cause

of spike unknown. rad monitor upgrade

pursued.

Document: LER 88-033-02-327, Unplanned Reactor Trip Signal Due to a Reactor Protection System (RPS) Channel 1 Instrument Failure During RPS Channel 2 C

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure of a rcs channel 1 delta T/Tavg Not stated 10 CFR 50.73 Tech. Spec. Not stated 1-4 2

loop instrument caused an unplanned surveillance,

reactor trip signal. Component aging was RG 1.118,

rreaenct d as a possible failure IwEEE 338

mechanism.

Document: LER 89-001-280, Unplanned Auto Start of #3 EDG Due to Failed Diode

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The failure of the diode was attributed to Not stated 10 CFR 50.73 No specific Not stated 11-3

normal aging. the start relay iniated the air surveillance for

start motors and started the diesel when j this component no emergency existed. j

Document: LER 89-002-331, Age-Related Failure of a Governor Printed Circuit Board Results in High Pressure Coolant Injection System Inoperability

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

Failure to operate, reason was Rare 10 CFR 50.73 Tech. Spec. Change out the governor printed 1-4 4

unanticipated age-related response of the Surveillance circuit boards every eight years [4]

printed circuit board's components due to req'd for HPI

long term constant energization and

possibly environmental factors. Vendor

indicated that long term constant current

Iflow could reduce life

Document: LER 89-003-263, Isolation of Reactor Water Cleanup System Due to Capacitor Failure in Filter/Demineralizer Inlet Temperature Indication Switch

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. ItemI1

Unexpected capacitor failure caused

circuit to actuate a portion of the ESF

system. Aging was given as the cause of

the capacitor failure

iNo surveillance 

this specific component

forNot staed 1-3 5 I

Document: LER 89-006-261, Reactor Trip Due to Loss of Turbine E-H Control Power Supplies

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Transistor leakage current caused l Rare 1 CFR 50.73 No specific Not stated

increased gain resulting in higher voltage surveillance for on the output stage of the power supply. this component

the over voltage protective circuitry was

triggered causing the fuse to blow.

degraded transistors attributed to aging.

Document: LER 89-010-362, Fuel Handling Isolation System Train 'A' Actuation Due to Power Supply Failure

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Lost power from the power supply when Rare 110 CFR 50.73 No specific Not stated1-7

the regulator shifted due to the broken surveillance for

screw and allowed a burr on the metal this component

heat sink to penetrate the mica insulation.

a short circuit resulted blowing a fuse.
Table A.2 Gall Report for Licensee Event Reports Page 2A

Document: LER 89-014-271, Reactor Core Isolation Cooling System Inoperable Due to Motor Bum Out

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

8 Reactor Core Motor Operated Motor Not stated Not stated CURSTR Failed armature

Isolation Cooling Valve winding

System

Document: LER 89-015-327, Control Room Isolation Resulting From a Wom Set of Contacts in the 480V Motor Starter for a Main Control Room Ventilation Intake I

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

9 Control Room Motor Starter Contacts Not stated Not stated WEAR Increased contact

Isolation I resistance causing

arcing

Document: LER 89-019-01-325, Failure of Service Water System to Meet Design Requirements

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

10 Service Water Pump Winding Insulation Not stated General Electric 'ELETEMP Degraded insulation

System on motor winding

Document: LER 89-020-01-528, Apparent Ground Causes Control Element Assembly Slip

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

11 Control Element Coil Coil Lead Wire Notstated Combustion Not stated Not aging related

Assembly IIEngineering II

Document: LER 89-031-01-302, Failure of "A 480V Engineered Safeguards Transformer Causes Temporary Interruption of Decay Heat Cooling and a Plant Opera

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

12 ESFAS Transformer Transformer Not stated Not stated Not stated Insulation

Insulation degradation

Document: LER 90-007-01-388, ESF Actuations Due to RPS EPA Breaker Spurious Trip

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

13 ReysteC°Protection oectin Lgic Card Not stated General Electric Not stated Logic card failed

Document: LER 90-018-244, Dropped Control Rod During Rod Control Exercise Causes Automatic Actuation of RPS

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

14 Control Rod Drive Power Bridge I Capacitor INot stated Westinghouse ELETEMP Degraded capacitor

Systemjj_________j_________________I________

Document: LER 90-022-01-344, Degraded Fire Penetration Seals as a Result of Inadewuate Construction Technique

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

151 Various Cable Penetrations Sea Silicon foam WEAR Degradation of foam

I 1 1 " 1 1splits and gaps.
Table A.2 Gall Report for Licensee Event Reports Page 2B

Document: LER 89-014-271, Reactor Core Isolation Cooling System Inoperable Due to Motor Bum Out

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs

Valve failed to close because of failed Rare 110 CFR 50.73 Vendor specific

motor. An incorrect upper bearing gasket testing

thickness resulted in a motor current 20%.

above full rated load which is believed to

have contributed to premature aging.

t Recommendations

ed

Page No. Item

1-48 I - - I

Document: LER 89-015-327, Control Room Isolation Resulting From a Wom Set of Contacts in the 480V Motor Starter for a Main Control Room Ventilation Intake F

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Contacts not conducting properly and Rare 10 CFR 50.73 No specific Not stated 1-3 9

current was arcing over introducing EMI surveillance for

into the circuitry resulting in a spurious this component

high radiation signal that initiated the

control room isolation.

Document: LER 89-019-01-325, Failure of Service Water System to Meet Design Requirements

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Inadequate air flow through the motor Rare 110 CFR 50.73 IEEE 334-1974 No stated winding over a period of time resulted in Section 14.2

thermally aged insulation that resulted in a

turn to turn failure. 7

Document: LER 89-020-01-528, Apparent Ground Causes Control Element Assembly Slip

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

ring defect Rare 10 CFR 50.73 Vendor specific Not statedp4 5 ll

program

Document: LER 89-031-01-302, Failure of "A' 480V Engineered Safeguards Transformer Causes Temporary Interruption of Decay Heat Cooling and a Plant Opera

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Transformer failed causing a cooling IRare 10 CFR 50.73 RG 1.118, Not stated i &3

pump to de-energize and loss of decay IEEE 338-

heat cooling. Power was also interrupted 1987, IEEE

to various plant ventilation systems. Event 741-1986

compounded by personnel error.

Document: LER 90ý-007-01-388, ESF Actuations Due to RPS EPA Breaker Spurious Trip

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The logic card failure caused the trip JOccasional; (12 10 CFR 50.73 RG 1. 118, Not stated 11-5 13

breaker to operate and initiated other esf times/6 Y) IEEE 338-1987

actuations. The card failure was attributed I

to aging and the aging process was found I

to be applicable when the epa logic card I was both in service and in storage. _

Document: LER 90-018-244, Dropped Control Rod During Rod Control Exercise Causes Automatic Actuation of RPS

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Noisy incoming power to the control rod J- Rare 110 CFR 50.73 Vendor specific Not stated 1-8 14

10 (caused the rod to drop) was attributed program

to the degraded capacitor. Elevated jI temperature at the power supply locationI

was the cause of the decreased serviceI

life of the capacitor.J______________________________ ____

Document: LER 90-022-01-344, Degraded Fire Penetration Seals as a Result of Inadewuate Construction Technique

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReL.progs Report Recommendations Page No. Item

Degradation of foam is attributed to aging Occasional 10 CFR 50.73 Vendor specific Not stated1"6 -15

and wear as noted under other defects IIprogram IID
Table A.2 Gall Report for Licensee Event Reports Page 3A

Document: LER 90-023-325, Partial Group 6 Isolation Resulting From Failure of Relay I-CAC-3A

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

16T Containment Isolation Logic coil Not stated General Electric jNot stated FCoil burned up

Isolation Control

Document: LER 90-023-424, Transformer Failure Results in Loss of Steam Generator Level and Manual Reactor Trip

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

[17 Non 1-E Power Transformer INot stated Not stated General Electric Not stated [Internal fault in the

System I"b" phase high side

windings

Document: LER 90-029-01-325, CBEAF SYSTEM Actuation Resulting From the Failure of the 1-D22A-K2 Relay Coil.

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

18 Control Building Arm Logic Relay Not stated General Electric Not stated Cracks on epoxy

Filtration System up (probably

shorted)

Document: LER 91-001-293, Automatic Closing of the Primary Containment System Group 5 Isolation Valves During Sruveillance Testing

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

19 Primary Isolation Electric Govemor Transistor Not stated Not stated Not stated Transistor failed

Control System

20 Primary Isolation Electric Governor Cable Insulation Not.stated Woodward Governor ELETEMP, MOIST, Embrittlement due to

Control System Company & EMBR past exposure to

heat and humidity

Document: LER 91-002-01-327, EGTS Inoperable Because of a Train EGTS Being Out of Service for Filter Testing and B Train Diesel Generator Being Declared I

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Document: LER 91-006-530, ESF Actuation Due to Loss of Power to 4.16 KV Bus

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

22 1 E Power Circuit Breaker Trip Circuit Not stated Not stated TOSTMoisture induced

short circuit in trip

circuit

Document: LER 91-007-456, Rod Control System Failure Causes Shutdown Bank Control Rods to be in a Condition Prohibited by Technical Specifications

Reviewed by: L. C. Meyer, INEL

Item System SlructureiComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

23 Rod Control System Circuit Card 1 Transistor Not stated Not stated Not stated Transistor failed
Table A.2 Gall Report for Licensee Event Reports Page 3B

Document: LER 90-023-325, Partial Group 6 Isolation Resulting From Failure of Relay I-CAC-3A

Reviewed by: L. C. Meyer, INEL

Effect of Aninn on Comnonent Function Contmib to Failure Reuorted nroas -Rel.oroas Renort Recommendations Paae No. Item

Relay failure resulted in partial loss of cac Occasional; (3mi 18 10 CFR 50.73 RG 1. 118, SNot stated 1-3 16

logic and subsequent partial group 6 Mo) IEEE 338-

isolation. This normally energized coil 1987,1Tech

burned up as a result of normal end of life Spec. surv.

failure due to aging.

Document: LER 90-023-424, Transformer Failure Results in Loss of Steam Generator Level and Manual Reactor Trip

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Transformer failed resulted in loss of Rare 10 CFR 50.73 No specific Not stated -

power to speed control circuitry of the 1 B surveillance for

main feedwater pump. Possible this component

premature aging of transformer. I

Document: LER 90-029-01-325, CBEAF SYSTEM Actuation Resulting From the Failure of the 1-D22A-K2 Relay Coil.

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

CBEAF system actuation resulted from Occasional 10 CFR 50.73 No specific Not stated 131

the failed relay. This normally energized surveillance for

relay failed due to cracks in the epoxy this component coating on the coil. This was called a

normal end of life failure due to aging.

Document: LER 91-001-293, Automatic Closing of the Primary Containment System Group 5 Isolation Valves During Sruveillance Testing

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Circuit failed to control governor leading to Rare 10 CFR 50.73 No specific Not stated 1-4 19

automatio closure of isolation valves, surveillance for

this component

Cable embrittlement due to thermal aging Rare 10 CFR 50.73 No specific Not stated 1-4 20

was listed as the cause, handling of cable surveillance for

during maintenance and surveillance this component

activities may have contributed to the

cable failure. I I II

Document: LER 91-002-01-327, EGTS Inoperable Because of a Train EGTS Being Out of Service for Filter Testing and B Train Diesel Generator Being Declared Ii

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failed fuse resulted in train B EGTS

being declared inoperable. Frequent

cycling on and off of the air start system

due to an air leak is believed to be have

degraded the fuse resulting in fuse failur,

I m ted 1-5

I 21I 

I v

Document: LER 91-006-530, ESF Actuation Due to Loss of Power to 4.16 KV Bus

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Breaker opened when it was supposed to Rare 10 CFR 50.73 RIG 1. 118, Not stated 152

be closed. A degraded seal around an air IEEE 338-

conditioning duct penetration allowed 1987, IEEE

moisture from a rain storm to enter the 741-1987

plant multiplexer cabinets causing the SECTIC short circuit.

Document: LER 91-007-456, Rod Control System Failure Causes Shutdown Bank Control Rods to be in a Condition Prohibited by Technical Specifications

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Transistor failure caused the circuit to fail Rare 10 CFR 50.73 No specific Not stated 1-4 23

resulting in no motion control for the group surveillance for

1 control rods. Aging degradation was this component fgiven as the cause of the transistor__ fi lure.I
Table A.2 Gall Report for Licensee Event Reports Page 4A

Document: LER 91-008-260, Unplanned Engineered Safety Features Actuation Due to a Failed PCIS Relay

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

I 24 Primary Containmani Logic Relay Coil Not stated General Electric Not stated Burned coil

Isolation System

Document: LER 91-010-01-155, Reactor Protection System Pressure Switches Experiencing Setpoint Drift, Revision 1

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

251 Reactor Protection Switches 1 Not stated Foxboro CORR Corrosion caused

~ System _ switch setpoint drift

I~IDocument: LER 91-014-01-498, Erratic Containment Extended Range Pressure Channel Output

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

261 Containment Pressure Therm isitor Not stated Barton °Not stated Erratic behavior of

Extended Range Transmitter Iinstrument

Pressure Channel _________ _________ _________ __________ _________ _________

Document: LER 91-016-260, Unplanned Engineered Safety Features Actuation Due to a Blown Fuse Caused by a Failed Relay

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

27 ESFAS jRelay coil Not stated General Electric jELETERelay coil failed

Document: LER 91-016-424, Failure to Complete Technical Specification Required Action for Battery Cell Low Voltage

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

28 Various IBattery NA Not stated C & D Batteries Not stated Low cell voltage

I while single cell

1_ _ _ _ _ _ _ _ I c h a r g i n g

Document: LER 91-020-237, Reactor Building Ventilation Isolation and Automatic Standby Gas Treatment Initiation Due to Radiation Monitor Power Supply Failure

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

291 Reactor Building Power Supply Wire Not stated General Electric WEAR Insulation womn and

I Ventilation System nspark caused power

supply failure

Document: LER 91-021-254, RCIC Declared Inoperable Due to High Pump Flow in ISI Required Action Range

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 301 RCIC System JTachometer NA Not stated Not stated JNot stated Instrument drift

Document: LER 91-028-254, Loss of Power to 1A RPS Bus Caused by EPA 1A-1 Tripping on Undervoltage Due to Low M-G Set Output

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

31 M-G Set Voltage Regulator Voltage Rheostat Insulation General Electric Not stated Low voltage from mg set
Table A.2 Gall Report for Licensee Event Reports Page 4B

Document: LER 91-008-260, Unplanned Engineered Safety Features Actuation Due to a Failed PCIS Relay

Reviewed by: L.C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The burned coil cause the normally Occasional 10 CFR 50.73 Tech Spec. Not stated 1-3 24

energized relay to fail resulting in loss of required

logic power and an unplanned actuation of surveillance

the esfas. This was called a thermally

aged relay coil failure. _

Document: LER 91-010-01-155, Reactor Protection System Pressure Switches Experiencing Setpoint Drift Revision 1

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The drift would adversly effect the RPS Rare 10 CFR 50.73 Tech Spec. Not stated 11-2 251

operation. Found during refueling outage required

calibration. I I I surveillance

Document: LER 91-014-01-498, Erratic Containment Extended Range Pressure Channel Output

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs ReI.progs Report Recommendations Page No. Item

A cracked thermistor was found on the Rare 10 CFR 50.73 Tech Spec. Not stated 1-4 26

control card, however the erratic behavior surveillance,

of the pressure transmitter cannot be RG 1.118,

positively attributed to this thermistor. j _ IEEE 338

Document: LER 91-016-260, Unplanned Engineered Safety Features Actuation Due to a Blown Fuse Caused by a Failed Relay

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Unplanned ESFAS actuation due to failed Rare 110 CFR 50.73 Tech Spec. Not stated 1-3 27

relay. The failed relay coil was 15 years jsurveillance,

old and the service life for a normally- not specific

energized coil relay of this type is 15 to 20

years. This was an end of life failure.

Document: LER 91-016-424, Failure to Complete Technical Specification Required Action for Battery Cell Low Voltage

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported prols Rel.progs Report Recommendations Page No. Item

Battery failed to meet technical JRare 10 CFR 50.73 Tech Spec. Not stated 11-4 2

specification while charging. This was surveillance,

considered to be related to battery aging RG 1.118,

phenomena. .I _ IEEE 450 1_

Document: LER 91-020-237, Reactor Building Ventilation Isolation and Automatic Standby Gas Treatment Initiation Due to Radiation Monitor Power Supply Failure

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

system actuation resulted from the power _ surveillance for

supply failure. I Occasional I 1 I 50o Ithis component it e4

Document: LER 91-021-254, RCIC Declared Inoperable Due to High Pump Flow in ISI Required Action Range

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure due to instrument drift caused by IRare 110 CFR 50.73 INo specific INot stated 11-4 [3°

aging surveillancefor

Ithis component1 0

Document: LER 91-028-254, Loss of Power to 1A RPS Bus Caused by EPA 1 A-1 Tripping on Undervoltage Due to Low M-G Set Output

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations -Page No. Item

Cause of dip is unknown, but normal wear Occasional 10 CFR 50.73 Vendor specific Not stated 1-6 31

of the voltage adjustment rheostat was program

supected. It was believed to have

developed a flat spot or corrosion at the

point of the previous adjustment due to

normal wear at that point over a long

period of time.
Table A.2 Gall Report for Licensee Event Reports Page SA

Document: LER 91-028-325, Component Failure of a Reactor Water Cleanup System Isolation Logic Relay Resulted in an Unplanned Engineered Safety Feature

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

32 RWCU Relay coil Insulation General Electric Not stated Relay coil failed after)

insulation breakdow]

Document: LER 91-030-423, Motor Control Center Auxiliary Control Relay Failure Due to Thermal Aging

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

or Control Relay coil Insulation ITE Gould ELETEMP&EMBR Relay coil insulaton I f embrittlement and

failure

Document: LER 92-001-155, Brittle Motor Lead Wires Discovered in VOP-7050 (Main Steam Isolation Valve-MSIV)

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects Li4 Main Steam 1Isolation Valve Motor Lead Wire insulationj Butyl rubber Limitorque ELETEMP &EMBR Brittle and cracked

insulation

Document: LER 92-001-263, Shutdown Required by Technical Specification Due to Inoperable Bellows Leak Detection System for Safety Relief Valves

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

31Bellows Leak Valve Seating Material Cast urethane Automatic Switch ELETEMP Urethane seat

Detection System Company material degraded due to high

temperature

Document: LER 92-001-296, Engineered Safety Feature Actuation Caused by a Failed Relay Coil

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

361 Engineered smcoil Safety Relay Not stated General Electric ELETEMP Degraded insulationl

I Feature Actuating TIcausing coilfalr LJSystem (ESFAS) I_______ I ________I _ ______I _______I _ ______I_______

Document: LER 92-001-339, Reactor Trip Caused by MFRV Closure Upon Failure of Driver Card

Reviewed by: L. C. Meyer, INEL

Item System StructureJComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

Feedwater system Main Feed Power Supply Not stated Not stated Not stated Power supply failed 9 ________Regulating Valve _______J_______j_______ _______jon driver card

Document: LER 92-002-247, Reactor Trip Due to Main Feedwater Regulating Valve Going Closed

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Mani

- 381 Feedwater system f Feedwater ISolenoid Valve I Not stated ] Nots

Document: LER 92-004-389, Manual Reactor Trip Due to Low Steam Generator Water Level Caused by a Failed Circuit in the 2A Feedwater Regulating Control Sy

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

1 391 Feedwater Power Supply JCapacitor I Not stated FNot stated 1 Not stated I Capacitor failed
Table A.2 Gall Report for Licensee Event Reports Page 5B

Document: LER 91-028-325, Component Failure of a Reactor Water Cleanup System Isolation Logic Relay Resulted in an Unplanned Engineered Safety Feature A

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

ESFAS actuation resulted from the relay Occasional 10 CFR 50.73 Tech Spec. not Not stated 1-4 32

failure. Component failure determined to specific for this

be a normal end of life failure due to component

aging. This was a normally energized

relay.

Document: LER 91-030-423, Motor Control Center Auxiliary Control Relay Failure Due to Thermal Aging

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Elevated temperature from continuous Occasional 10 CFR 50.73 Vendor specific Not stated 1-5 33

operation of relays caused embrittlement program

and failure. Heat also discolored other

plastic parts near the coil.

Document: LER 92-001-155, Brittle Motor Lead Wires Discovered in VOP-7050 (Main Steam Isolation Valve-MSIV)

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Loss of isolation capability, the degraded Rare 10 CFR 50.73 Vendor specific Not stated 1-4 34

wire insulation was found in the limit progarm, GL

switch housing as a result of planned 89-10,

maintenance during a scheduled refueling NUREG-1352

outage.

Document: LER 92-001-263, Shutdown Required by Technical Specification Due to Inoperable Bellows Leak Detection System for Safety Relief Valves

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Valve failed to seat due to degradation of Rare 10 CFR 50.73 Vendor specific Not stated 1-6 35

the seating material from exposure to program

temperatures near manufacturers rated

temperature. ___ I

Document: LER 92-001-296, Engineered Safety Feature Actuation Caused by a Failed Relay Coil

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The coil failure iniated partial actuation of OCCAIONAL 10 CFR 50.73 Vendor specific Not stated

the ESFAS system. I Nprogram, Tech. I

Spec. Surveil.

Document: LER 92-001-339, Reactor Trip Caused by MFRV Closure Upon Failure of Driver Card

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

IPower supply failure caused the MFRV Ocsonal 110 CFR 50.73 No specific Not stated1-

valve to fail closed isolating normal program feedwater and causing a reactor trip. InI I I

Document: LER 92-002-247, Reactor Trip Due to Main Feedwater Regulating Valve Going Closed

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Solenoid valve failued relieving air Rare 10 CFR 50.73 No specific Not stated 1-3

pressure to the diaphragm of the program

regulating valve which caused it to go to

the closed position. I I

Document: LER 92-004-389, Manual Reactor Trip Due to Low Steam Generator Water Level Caused by a Failed Circuit in the 2A Feedwater Regulating Control Sy

Reviewed by: L.C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Because of the capacitor failure the lead Rare 110 CFR 50.73 Vendor specificNt stated 1-3 391

lag circuit output current was low and the I program I

steam regulating valve closed. The reactor I I

I ___________ I _________________________ I _______
Table A.2 Gall Report for Licensee Event Reports Page 6A

Document: LER 92-006-331, Emergency Safety Feature Actuation During Modification Acceptance Testing Due to Damaged Switchyard Cable

Reviewed by: L. C. Meyer, INEL

Item System StructurelComp Subcomponent Materials Manufacturer ARD mechanism ARD effects

40 1 E Power Cable Insulation Ethylene propylene Not stated WEATH, CORR, & Insulation degraded,

rubber MOIST galvanic corrosion

rusted wire cores

Document: LER 92-006-354, Reactor Shutdown to Comply With Technical Specification 3.6.1.1, Due to Failure of Suppression Chamber to Drywell Vacuum Breal

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

41 Various Drywell Vacuum Seal Not stated Not stated Not stated Seal degraded due

Breakers to aging

Document: LER 92-007-01-33, Failure of Analog Transmitter Trip System (ATTS) Trip Relays Due to Thermal Aging

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

42 Analog Transmitter Relay coil Not stated Amerace ELETEMP Relay coil wire

Trip System insulation

embritttement

Document: LER 92-009-01-499, Missed Technical Specification Required Surveillance Due to a Faulty Toxic Gas Monitoring System Modem

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

43 Emergency Modem INA Not stated Black Box Not stated Modem failed

Response -- CorporationI

Display System II (ERFDADS)I_______I_______I_______________I_______

Document: LER 92-011-325, Primary Containment Monitoring System Inoperability Due to Relay Failure

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

441 Containment Containment Control Relay Not stated General Electc stated INot Relay failed (end of

Atmospheric Control - Logic life)

(CAC) System I I I I I

Document: LER 92-021-237, Automatic Isolation of Reactor Building Ventilation Due to Radiation Monitor Trip Relay Failure

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

45 Reactor Building RBV Radiation Relay Not stated General Electric Not stated Burned out coil

Ventilation System Monitor

Document: LER 92-034-01-333, Engineered Safety Feature Actuations Due to Transformer Failure

Reviewed by: L.C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

46 ESFAS Transformer NA Not stated General Electric ELETEMP Insulation

degradation in

transfomer
Table A.2 Gall Report for Licensee Event Reports Page 68

Document: LER 92-006-331, Emergency Safety Feature Actuation During Modification Acceptance Testing Due to Damaged Switchyard Cable

Reviewed by: L. C. Meyer, INEL Effect of Aoina on Component Funr-fion Contyib to Failure Reported nrons Rel~oroas Reoort Recommendations P aae No. Item

A tear or crack in the insulation exposed Rare 10 CFR 50.73 No specific Not stated 1-8 40

wires to ambient conditions and moisture program

intrusion with continuous dc potential on

wires may have contributed to galvanic

corrosion leading to an open circuit The

failed circuit caused sf actuation during

Itest.

Document: LER 92-006-354, Reactor Shutdown to Comply With Technical Specification 3.6.1.1, Due to Failure of Suppression Chamber to Drywell Vacuum Break,

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Leak in vacuum breakers was too large

and violated the technical specifications

resulting in reactor shut down. Two of the

three leaking breakers also had seal and

pallet alignment problems. I

Document: LER 92-007-01-33, Failure of Analog Transmitter Trip System (ATTS) Trip Relays Due to Thermal Aging

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.pr0gs Report Recommendations Page No. Item

Debris from the embrittled coil spool was Occasional 10 CFR 50.73 Tech Spec. Not stated 1-5 42

inhibiting movement of the relay plunger required

resulting in sticking relay and excessive Isurvelance

time. The relay had been in service Idelay 14 years which exceeded the

,recommended service life of 3 years

Document: LER 92-009-01-499, Missed Technical Specification Required Surveillance Due to a Faulty Toxic Gas Monitoring System Modem

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Garbled data sent to erfdads computer. Rare 10 CFR 50.73 No specific Not stated 115

Failure of modem attributed to aging. program

Operators were unable to meet technical

specifications requiring the each chemical

detection system be demonstrated

operable every 12 hours. __ _

Document: LER 92-011-325, Primary Containment Monitoring System Inoperability Due to Relay Failure

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure of this relay resulted in loss of I Occasional 10 CFR 50.73 ,Tech Spec. Not stated 1-3

power to various containment isolation required

valves and inoperability of the cac system. III surveillance

Document: LER 92-021-237, Automatic Isolation of Reactor Building Ventilation Due to Radiation Monitor Trip Relay Failure

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Failure oflay coil caused the RBV Rare 10 CFA 50.73 No specific Not stated 1-4

system to actuate. I I program

Document: LER 92-034-01-333, Engineered Safety Feature Actuations Due to Transformer Failure

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Fault in middle phase b winding due to Rare 10 CFR 50.73 RG 1.118, Not stated 1-16 46

dielectric breakdown of insulation caused IEEE 338-1987

transformer failure resulting in ESFAS

actuations. The dielectric breakdown due

to aging resulted in multiple faults.
Table A.2 Gall Report for Licensee Event Reports Page 7A

Document: LER 92-038-255, Reactor Trip Caused by a Loss of the Preferred AC BUS Y-20 Coincident With a Blown Fuse in a Second Channel of the Reactor Pr

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

47 Reactor Protection Inverter Transformer Not stated Sola ELETEMP Transformer coils

System jfailed

Document: LER 93-002-249, Control Valve Fast Closure Half-Scram Pressure Switches Out-of Calibration Due to Setpoint Drift

Reviewed by: L. C. Meyer, INEL

Item System Structure(Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

481 Reactor Protection J Pressure Switch NA Not stated I Barksdale VIB Wear of face of the System J I ________________ ________j________ ________fplunger I

Document: LER 93-003-530, Emergency Diesel Generator Unable to Start and Run in Manual Test Mode

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

49 Emergency Diesel Starting System Relay Not stated Agastat Not stated Relay failed by fault

Generator of a suppression

varistor across coil

Document: LER 93-005-01-275, Medium Voltage Cable Failures Due to Chemical Degradation and Undkown Causes

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

50 Various Cable 12KV Underground Ethylene- Okonite CHEM, CONTAM,& Chemical

Cable propylene=rubber CORR degradation of jacket

(EPR) and neoprene and corrosion of

jacket shield

51 Various Cable 12KV Underground Ethylene- Okonite Not stated Anomalies occurred

Cable propylene=rubber over time

(EPR) and neoprene

jacket

Document: LER 93-005-01-305, Annual Transmitter Calibration Finds a Shift in the Pressurizer High Pressure Reactor Trip Signal Initiation Due to Instrument Drift

Reviewed by: L. C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

521 Reactor Protection Pressure NA Not stated Foxboro Not stated j Transmitter drift

Document: LER 93-007-249, Yarway Reactor Water Level Switch Failure

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

[531 High PRessure H Level Switch I NAy Not stated I Yarway IMECHSTR Spring force

Coolant Injection _______ _______ degradation_______ _______

Document: LER 93-008-237, Yarway Reactor Water Level Switch Failure

Reviewed by: L C. Meyer, INEL

Item System Structure/Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects [41 High PRessure JLevel Switch I NA INot stated Yarway J MECHSTR fSpring force

Coolant Injection degradation '' System (HPCI) I
Table A.2 Gall Report for Licensee Event Reports Page 713

Document: LER 92-038-255, Reactor Trip Caused by a Loss of the Preferred AC BUS Y-20 Coincident With a Blown Fuse in a Second Channel of the Reactor Pro

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The transformer failure resulted from Rare 10 CFR 50.73 Tech. Spec. Not stated 1-8 47

accelerated aging due to improper inemal required

wiring in the inverter. Only one primary surveillance,

winding was connected resulting in RG 1.118

operation at a higher temperature. the Y20 bus power failure tripped the reactor.

Document: LER 93-002-249, Control Valve Fast Closure Half-Scram Pressure Switches Out-of Calibration Due to Setpoint Drift

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

Vibration contributed to the drift of the set Rare 10 CFR 50.73 Tech Spec. Not stated -

point because of wear on the plunger required

face. surveillance

Document: LER 93-003-530, Emergency Diesel Generator Unable to Start and Run in Manual Test Mode

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

The starting system check circuitry relay *Rare 10 CFR 50.73 *RG 1.108, Not stated 1-9 -49

shorted and the resulting current surge IEEE 387-1984

damaged other electrical components on Section 7.5,

the fiber optics card in the EDG starting IEEE 749

circuit. The EDG would not start in the

manual test mode. Component aging was

Ithe cause

Document: LER 93-005-01-275, Medium Voltage Cable Failures Due to Chemical Degradation and Undkown Causes

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progIs Report Recommendations Page No. Item

A ground fault developed at the cable Rare 10 CFR 50.73 No specific Not stated 1-16 50

jacket degradation location (insulation program

breakdown). Excess chlorides and a fatty

acid, ethyl ester compound, were

identified as the chemical that attacked

the cable jacket. Water carried chemical

into conduit. I

Ground fault occurred on cable, water Rare 10 CFR 50.73 No specific Not stated 1-16 51

was in conduit (cable was designed for program

wet conditions) cable removed from

conduit and no root cause identified from

inspections or tests conducted by utility

and manufacturer.

Document: LER 93-005-01-305, Annual Transmitter Calibration Finds a Shift in the Pressurizer High Pressure Reactor Trip Signal Initiation Due to Instrument Drift

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

signal at the required point, The method OEEE 338-1987

of calibration was most probable cause

and aging was the next most likely cause.

Document: LER 93-007-249, Yarway Reactor Water Level Switch Failure

Reviewed by: L C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

specification limits. Excessive set point IEEE 338-1987

Document: LER 93-008-237, Yarway Reactor Water Level Switch Failure

Reviewed by: L. C. Meyer, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Item

[Out of tolerance Frequently j10 CFR 50.73 RG 1.118, Not stated 1-6

_1_ _ 338-19871 ____IIEEE 
Table A.2 Gall Report for Licensee Event Reports Page 8A

Document: LER 93-009-498, Technical Specification 3.0.3 Entry Due to Potentially Undersized Fuses in the Solid State Protection System

Reviewed by: L. C. Meyer, INEL

Item System Structure[Comp Subcomponent Materials Manufacturer ARD mechanism ARD effects

55 Solid State Fuse NA Not stated Not stated Not stated Fuse failed

Protection System
Table A.2 Gall Report for Licensee Event Reports Page 8B

Document: LER 93-009-498, Technical Specification 3.0.3 Entry Due to Potentially Undersized Fuses in the Solid State Protection System

Reviewed by: L. C. Meyer, INEL Effect of Aaina on Component Function Contrib to Failure Reoorted Droas Rel.eroas Reeort Recommendations Paae No. Item

An independent laboratory determined Rare 10 CFR 50.73 No specific Not stated 1-5 - 55

that the fuse did not open as the result of program

a high current fault. It was not possible to

determine whether the fuse had a defect.

LER states that the event was caused by

the random age related failure of a ssps

fuse. I
Table A.2 Gall Report for NRC Bulletins Page 1A

Document: BL 90-01, Loss of Fill-Oil in Transmitters Manufactured by Rosemount

Reviewed by: E. W. Roberts, INEL

Item System Structure/Comp Subcomponent Materials

1 11 Pressure IO-Ring Metal

Transmitters Model

1153 & 1154

Manufacturer ARD mechanism ARD effects

Rosemount Not stated Loss of transmitter

oil
Table A.2 Gall Report for NRC Bulletins Page 1B

Document: BL 90-01, Loss of Fill-Oil in Transmitters Manufactured by Rosemount

Reviewed by: E. W. Roberts, INEL

Effect of Aging on Component Function Contrib to Failure Reported progs Rel.progs Report Recommendations Page No. Iteni

Transmitter drift, slow response, inability Frequent Not discussed in Bul 90-01 Identify transmitters and take

to respond over full range, sustained report Suppl 1, RG appropriate corrective action [4]

zero/span drift, or total failure 1.118, IEEE

338-1987

Distribution for NUREG/CR-6490

Internal:

D. R. Diercks (25) W. J. Shack

H. Drucker C. E. Till

K. E. Kasza (10) R. A. Valentin

C. A. Malefyt M. W. Warnbsganss

L. A. Neimark R. W. Weeks

R. B. Poeppel TIS File

External:

Libraries

ANL-E

ANL-W

Manager, Chicago Field Office, DOE

Energy Technology Division Review Committee:

H. K. Birnbaum, University of Illinois, Urbana

R C. Buchanan, University of Cincinnati, Cincinnati, OH

S.-N. Liu, Fremont, CA

H. S. Rosenbaum. Fremont, CA

R K. Shah, University of Kentucky, Lexington

S. Smialowska, Ohio State University, Columbus

R E. Smith, Altran Corp., Huntersville, NC

INEL Technical Library

J. L. Edson (10), INEL

NUREG/CR-6490

NIC FORM 336 U.A NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER

(2.11) (Assigned by NRC, Add Vol.. Supp.. Rev..

RCM 11 BIBLIOGRAPHIC DATA SHEET and Addendum Numbers. If any.) 32011,3202 BBIGAHCDT HE

(See kuwbans C•n fterel.) NUREG/CR-6490

2. TITLE ANO SUBTI.E ANL-96/13

Vol. 1

Nuclear Power Plant Generic Aging Lessons Learned (GALL) 3. DATE REPORT PUBLSHED

Main Report and Appendix A MONTH YEAR

December 1996

4. FIN OR GRANT NUMBER

J2076 and L1606

5. AUTHOR(S) 6. TYPE OF REPORT

KE Kasza,* D.R. Diercks,* J.W. Holland,* S.U. Choi,* J.L. Binder,* W.J. Shack,* O.K. Chopra,* Technical

D.C. Ma,* A Erdemir,* J.L Edson," LC.Meyer," and E.W. Roberts."*

7 PERIOD COVERED anclusNe Dates)

8. PERFORMING ORGANIATION - NAME AND ADDRESS (WNRC, provide Divext Ofrie or Region. U.S. mNcher Reguleby Commission, and meiling address: if conhactor,

pvoide narme and nie adius.)

*Argonne National Laboratory "*Idaho National Engineering Laboratory

9700 South Cass Avenue Lockheed Idaho Technologies Company

Argonne, IL 60439 Post office Box 1625

Idaho Falls, ID 83415

9. SPONSORING ORGANZATION - NAME AND ADDRESS (ff'NRC. type 'Same as above, dconacor provide NRC Division, Office or Regon. U.S. Nuclear Regulatory Commission.

and madling address)

License Renewal Project Directorate

Office of Nuclear Reactor Regulation

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001

10. SUPPLEMENTARY NOTES

11. ABSTRACT Mw or i--)

Argonne National Laboratory and Idaho National Engineering Laboratory in support of the License Renewal Project Directorate of

the U.S. Nuclear Regulatory Commission (NRC) performed a comprehensive review of literature pertaining to nuclear power plant

aging effects. This generic aging lessons learned (GALL) effort was a systematic review of plant aging information in order to

assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature

on mechanical, structural, thermal-hydraulic, and electrical components and systems reviewed consisted of 163 Nuclear Plant

Aging Research Reports, 31 NRC Generic Letters, 265 Information Notices, 82 Licensee Event reports, 5 Bulletins, and 10

Nuclear Management and Resources Council Industry Reports. The results of these reviews were systematized using a

standardized GALL tabular format and standardized definitions of aging related degradation mechanisms and effects. A

computerized data base has also been developed for all review tables and can be used to search for information on structures,

components, and relevant aging effects. A survey of the GALL tables reveals that all significant component and structure aging

issues are currently being addressed by the regulatory process. However, aging of what are termed passive components and

structures has been highlighted for continued scrutiny.

12. KEY WORDS/DESCRIPTORS (List wors orphvas Vat will assist resemactws in ocating ft repot.) 13. AVAILABILITY STATEMENT

Aging of Nuclear Power Plant Components and Systems unlimited

iense Renewal 14. SECURITY CLASSIFICATION

Age-Related Degradation Mechanisms (Tis Peg)

Component Aging Data Base unclassified

Structure Aging (mis Report)

Generic Aging Lessons Learned unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 336 (2-W This form was electronically produced by Elite Federal Forms. Inc.


Federal Recycling Program

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, DC 20555-0001

SPECIAL STANDARD MAIL

POSTAGE AND FEES PAID

USNRC

PERMIT NO. G-67

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

a,