NUREG/CR-5490

PNL-7190

Vol. 1

Regulatory Instrument Review:

Management of Aging of LWR

Major Safety-Related Components

(

Prepared by Bs V. Werry

Pacific Northwest Laboratory

Operated by

Battelle Memorial Institute

Prepared for

U.S. Nuclear Regulatory Commission
/

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NUREG/CR-5490

PNL-7190

Vol. 1

R9, RV

Regulatory Instrument Review:

Management of Aging of LWR

Major Safety-Related Components

Manuscript Completed: May 1990

Date Published: October 1990

Prepared by

E. V. Werry

Pacific Northwest Laboratory

Richland, WA 99352

Prepared for

Division of Engineering

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission

Washington, DC 20555

NRC FIN B2865
ABSTRACT

This report comprises Volume 1 of a review of U.S. nuclear plant regulatory instruments to determine the amount and kind of information they contain

on managing the aging of safety-related components in U.S. nuclear power

plants. The review was conducted for the U.S. Nuclear Regulatory Commission

(NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant

Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g.,

NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for

safety-related information on five selected components: reactor pressure

vessels, steam generators, primary piping, pressurizers, and emergency diesel

generators. Volume 2 will be concluded in FY 1991 and will also cover

selected major safety-related components, e.g., pumps, valves and cables.

The focus of the review was on 26 NPAR-defined safety-related aging issues,

including examination, inspection, and maintenance and repair; excessive/

harsh testing; and irradiation embrittlement. The major conclusion of the

review is that safety-related regulatory instruments do provide Implicit

guidance for aging management, but include little explicit guidance. The

major recommendation is that the instruments be revised or augmented to

explicitly address the management of aging.

iii
CONTENTS

ABSTRACT . . . . . .. . . . . . . . . . . . . . . . .

PREFACE . . . . . . . . . . . . . . . . . . . . . . . . . ..

ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . .

ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . .

SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.0 INTRODUCTION/PURPOSE. . . . . . . . . . . .

2.0 SELECTION OF INSTRUMENTS, COMPONENTS AND ISSUES, AND

METHODOLOGY . . . . . . . . . . . . . . . .

2.1 REGULATORY INSTRUMENTS REVIEWED. . . . . . . .

2.2 MAJOR COMPONENTS . . . . . . . . . . ........

2.3 AGING ISSUES ....................

2.4 REVIEW CRITERIA. . . . . . . . . . . . . . . . . . .

2.5 REVIEW METHODOLOGY . . . . . . . . . . . . . . . . .

2.6 REVIEW EXAMPLES. . . . . . . . . . . . . . . . . . .

3.0 DISCUSSION. . . . . . . . . . . . . . . . . . . . . . . .

3.1 REGULATORY INSTRUMENTS AND AGING MANAGEMENT. . . . .

3.2 REGULATORY INSTRUMENTS AND THE AGING ISSUES . . . .

3.2.1 Code of Federal Regulations . . . . . . . . .

3.2.2 Technical Specifications. . . . . . . . . . .

3.2.3 Standard Review Plans . . . . . . . . . . . .

3.2.4 Regulatory Guides . . . . . . . . . . . . . .

3.2.5 ASME Boiler and Pressure Vessel . . . . . . .

3.2.6 Generic Safety Issues . . . . . . . . . . . .

. . ..

. . ..

. . ..

. . . .

* . . .

. . . .

iii

vii

ix

xi

xv

1.1

2.1

2.1

2.3

2.4

2.6

2.7

2.8

3.1

3.1

3.1

3.1

3.3

3.4

3.4

3.5

3.6

3.7

. . .

. . ..

. . ..

. . ..

. . ..

. . . .

. . . .

3.2.7 Institute of Electrical and Electronic Engineers

Standards . . . . . . . . . . . . . . . . . . . . . g

v
3.2.8 American Nuclear Society Standards. . . . . . . . . .

3.2.9 General Correlation of Implied Aging. . . . . . . . .

4.0 CONCLUSIONS AND RECOMMENDATIONS ................

4.1 CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . .

3.8

3.8

4.1

4.1

4.2 RECOMMENDATIONS. . . . . . . . . . . . . . . . . . . . .

5.0 SUGGESTED FUTURE REGULATORY INSTRUMENT REVIEW ACTIVITIES. . .

5.1 CONTINUATION OF THE GUIDE TO REGULATORY INSTRUMENTS. . .

5.2 COMPUTER DATA BASE FOR THE REGULATORY INSTRUMENT REVIEW.

6.0 OBSERVATIONS OUTSIDE THE SCOPE OF THE REVIEW. . . . . . . . .

7.0 REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . .

APPENDIX I - GLOSSARY OF AGING ISSUES . . . . . . . . . . . . . .

APPENDIX II - REGULATORY INSTRUMENT REVIEW FOR

REACTOR PRESSURE VESSEL. . . . . . . . . . . . . . .

APPENDIX III - REGULATORY INSTRUMENT REVIEW FOR

STEAM GENERATOR . . . . . . . . . . . . . . . . . .

APPENDIX IV - REGULATORY INSTRUMENT REVIEW FOR

PRIMARY PIPING . . . . . . . . . . . . . . . . . . .

APPENDIX V - REGULATORY INSTRUMENT REVIEW FOR

PRESSURIZER (INTERNALS AND SUPPORT PIPING). . . . . .

APPENDIX VI - REGULATORY INSTRUMENT REVIEW FOR

EMERGENCY DIESEL GENERATOR . . . . . . . . . . . . .

::

. .

4.1

5.1

5.1

5.1

6.1

7.1

1.1

1I.1

. . 111.1

,. . IV.1

, . V.1

. . VI.1

vi
PREFACE

This report was developed to provide a preliminary assessment regarding

the extent of those regulatory instruments that contain information pertinent

to managing aging. Assessments of the applicable regulatory instruments

regarding aging management is complex and subject to differences in interpretation. Therefore, the perspectives in this report should be considered

preliminary. These perspectives are not established needs or views and do

not reflect regulatory positions or requirements.

vii
ACKNOWLEDGMENTS

The author of this report acknowledges the support and technical guidance provided by J. P. Vora and C. Z. Serpan, Jr., of the Nuclear Regulatory

Commission (NRC) during the course of the regulatory instrument review task

under the Nuclear Plant Aging Program. A special thanks goes to V. N. Shah

of the Idaho National Engineering Laboratory for his contribution to the

review by providing the "Understanding and managing aging tables and figures

for the RPVs and reactor piping systems." The author also wishes to thank

the following Pacific Northwest Laboratory staff for their contributions to

this report: A. B. Johnson, Jr., for Project Management support and technical guidance; and to E. F. Love, P. M. Daling, B. W. Smith, S. H. Bush,

W. N. McElroy, J. W. Jaeckle, S. R. Doctor, J. C. Spanner, K. R.

Hoopingarner, R. J. Kurtz, R. H. Ferris and W. B. Scott for their expertise,

review of the instruments, and input to the review of the regulatory instruments. A special thanks to J. W. Nageley for his timely editing effort for

the review and report.

ix
ACRONYMS

A&E Architect Engineer

ACI American Concrete Institute

ANL Argonne National Laboratory

ANS American Nuclear Society

ANSI American National Standards Institute, Inc.

ASME American Society of Mechanical Engineers

ASTM American Society of Testing and Materials

BPVC Boiler and Pressure Vessel Code

BTP Branch Technical Position

BWR Boiling Water Reactor

CCS component, systems or structure

CFR Code of Federal Regulations

DMS diminishing manufacturing source

EDG emergency diesel generator

EMTB Material Engineering Branch

EPRI Electric Power Research Institute

FSAR Final Safety Analysis Report

GDC General Design Criteria

GSI Generic Safety Issues

HAZ heat affected zone

HPI high pressure injection

IEEE Institute of Electrical and Electronic Engineers

IGSCC intergranular stress corrosion cracking

ISI inservice inspection

xi
LE life extension

NDE nondestructive examination

NDT nondestructive testing

NFC National Fire Code

NPAR Nuclear Plant Aging Research

NPP nuclear power plant

NRC Nuclear Regulatory Commission

NSSS nuclear steam supply system

NUMARC Nuclear Management and Resources Council

NUPLEX Nuclear Plant Life Extension

NUREG Nuclear Regulatory Commission Report

PLEX Plant Life Extension

PNL Pacific Northwest Laboratory

P/T pressure/temperature

PTS pressurized thermal shock

PVRC Pressure Vessel Research Committee

PWR pressurized water reactor

QA quality assurance

RCC reactor core cooling

RCPB reactor coolant pressure boundary

RCS reactor coolant system

RG NRC Regulatory Guides

RHR residual heat removal

RPV reactor pressure vessel

RT(NDT) reference nil-ductility temperature

SAR Safety Analysis Report

xii
SCC stress corrosion cracking

SG steam generator

SRP Standard Review Plan

SSE safe shutdown earthquake

SWG Special Working Group

TDI Transamerican DeLaval Inc.

TS Technical Specification

xiii
This report comprises Volume 1 of a review of U.S. nuclear plant regulatory instruments to determine the extent that they contain information pertinent to managing aging of safety-related components in nuclear power

plants. The instrument review was conducted for the U.S. Nuclear Regulatory

Commission (NRC) under the NRC Nuclear Plant Aging Research (NPAR) program.

As used in this report, an "instrument' is a procedure or document as in

an instrument of government, e.g., the Code of Federal Regulations. The

terms regulatory instruments or instruments are used throughout this report

and in this context are not to be confused with an instrument of measurement,

e.g., a pressure gauge or flow meter. Eight regulatory instruments were

selected for the review:

* Code of Federal Regulations (CFR)

* Technical Specifications (TS)

* Standard Review Plan (SRP)

* NRC Regulatory Guides (RG)

* American Society of Mechanical Engineers (ASME) Boiler and Pressure

Vessel Code (BPVC), Sections III and XI

* Generic Safety Issues (GSI)

* American Nuclear Society (ANS) Standards

* Institute of Electrical and Electronics Engineers, Inc. (IEEE)

Standards.

Historically, all these regulatory instruments have been used for the design,

construction, start-up and operation of Nuclear Power Plants. In this, their

primary purpose has been to protect the health and safety of the general

public. The intent of this review was to determine the degree of emphasis on

the management of aging found in the instruments now in use. No attempt was

made to take into account that approximately 50% of the Nuclear Power Plants

now operating were licensed before 1975. Therefore, not all of the plants

were licensed under the same set or edition of instruments noted above. The

review of the applicable instruments was based on the technical issues

related to aging. The descriptions included are the author's and do not

represent NRC considerations for license renewal.

The components on which the review focused were five light water reactor

major safety-related components: reactor pressure vessels, steam generators,

primary piping (reactor coolant piping), pressurizer vessel, and emergency

diesel generators. (Cables, containment and basemat and selected pumps and

xv
valves will be investigated in FYs 1990 & 1991 and will be published as

Volume 2.) The components were selected from the NPAR program document

NUREG-1144, Nuclear Plant Aging Research Program Plan, that has identified a

list of components of current interest and concern relative to the management

of aging. The components are high priority, safety-related components that

have been, in varying degrees, subject to aging problems.

The focus of the review was on 26 NPAR-defined aging issues, including

generic issues, e.g., examination, inspection and maintenance, embrittlement,

corrosion, erosion, and thermal cycles; and component specific issues, e.g.,

steam generator tube specific - intergranular attack, fretting and denting,

and emergency diesel generator specific - harsh and frequent testing.

Each regulatory instrument was evaluated for each aging issue chosen for

each component, e.g., for the RPV and the aging issue of corrosion, each

instrument was evaluated for aging features that provide implied or explicit

direction in the management of corrosion. The results of the review are

contained in tables in appendixes for each of the major components.

The principal conclusion is that aging management does exist in the

safety-related regulatory instruments; however, the information is largely

implied. The emphasis of the instruments appears to be on initial design,

construction, qualification and start-up and actions to address aging problems that develop after the problem is found. Finally, it was also concluded

that revisions should be made in the instruments to explicitly address aging.

The major recommendation is that the existing body of regulatory

instruments should directly address aging and the management of aging. The

difficulties, however, with any revisions are acknowledged, and it is

recommended that a project plan for the revision process be evaluated and

defined. The planning should include evaluations of ongoing NRC aging

research and industry aging-related research, e.g., Electric Power Research

Institute and individual utilities, and the development of a realistic time

frame for implementation of the revisions.

It is also suggested that all regulatory instrument review information

be installed in a computer data-based system for broader use by the NRC and

others.

A number of observations outside the scope of the review were developed

during the analysis of the review by PNL staff. The principal observations

are 1) evaluation of component replacement methods as an aging management

procedure should be addressed in the regulatory instruments for augmentation

of safety and cost effectiveness; 2) aging management could be enhanced by

improvement of NDE methods and inspection tools; 3) the ASME BPVC, as the

major contributor to design and construction and aging management, provides a

valuable contribution to the NPP industry; however, improvements in the Code

are needed to address component material deterioration, design that encourages and allows for repair, replacement, and improved inservice inspection,

and improvements in the time cycle for revising the Code (ASME is currently

xvi
addressing hard to backfit design problems in Section III and the problems of

long time cycles in Section XI); and 4) a safe and well-maintained plant,

i.e., a plant with excellent maintenance methods and procedures, is likely to

be a plant that is successfully managing the aging of its components and

systems.

xvii
1.0 INTRODUCTION/PURPOSE

This report comprises Volume 1 of a review of U.S. nuclear plant regulatory instruments to determine the extent that they contain information pertinent to managing the aging of safety-related components in nuclear power

plants (NPPs). The review was conducted for the U.S. Nuclear Regulatory

Commission (NRC), Office of Nuclear Regulatory Research, by the Pacific

Northwest LaboratorykaJ under the NRC Nuclear Plant Aging Research (NPAR)

Program (NRC 1987a). In conducting the review, the focus was on safetyrelated aging as it relates to selected safety-related components in Nuclear

Power Plants (NPPs). NPAR has defined aging as "the cumulative degradation

that occurs with the passage of time in a component, system of structure."

Therefore, the essential elements of the review on which this report is based

may be presented as follows:

REGULATORY INSTRUMENTS

SAFETY-RELATED NPP COMPONENTS - & SAFETY-RELATED AGING ISSUES

As used in this report, an "instrument" is a procedure or document as in

an instrument of government, e.g., the Code of Federal Regulations. The terms

regulatory instruments or instruments are used throughout this report and in

this context are not to be confused with an instrument of measurement, e.g., a

pressure gauge or flow meter. The regulatory instruments reviewed for safetyrelated information are listed in Section 2.2. Each is described in the body

of this report. Historically, these safety-related regulatory instruments

have been used as the basis for the design, construction, start-up, equipment

qualification, and operation of NPPs. Their primary purpose has been to

protect the health and safety of the general public. This review was undertaken to determine the degree of emphasis, if any, regarding the inclusion of

explicit requirements for the management of aging found in the instruments now

in use. No attempt was made to take into account that approximately 50% of

the NPPs now operating were licensed before 1975. Therefore, not all the

plants were licensed under the same set or edition of instruments noted in

Section 2.1. The review of the applicable instruments was based on the

technical issues related to aging. The descriptions included are the author's

and do not represent NRC considerations for license renewal.

The components on which the review focused are the reactor pressure

vessels; steam generators; primary piping (reactor coolant piping); pressurizer vessel, with special emphasis on pressurizer spray and surge lines and

(a) Operated for the U.S. Department of Energy by Battelle Memorial

Institute.

1.1
internals; and the emergency diesel generators. (Underway or planned are

reviews for cables, containment and basemat and selected pumps and valves;

this work will be published as Volume 2 in FY 1991).

To determine whether the selected instruments contain significant aging

safety-related information related to the five safety-related components, the

review concentrated on NPAR defined safety-related aging issues. A complete

list of the 26 identified aging issues is found in Section 2.3. These aging

issues include examination, inspection and maintenance, embrittlement,

corrosion, erosion, and thermal cycles; and component--specific issues, e.g.,

steam generator tube specific--denting, fretting and crevice intergranular

attack, and emergency diesel generator spesific--harsh and frequent testing.

Each aging issue is defined in Appendix I. aJ

The results of the review on which this report is based are contained

in tables in Appendixes II a through VI entitled "Regulatory Instrument

Reviews": Appendix II for Reactor Pressure Vessels; Appendix III for Steam

Generators; Appendix IV for Primary Piping (Reactor Coolant Piping); Appendix V for Pressurizer Internals; and Appendix VI for Emergency Diesel

Generators.

Section 2.0, "Selection of Instruments, Components and Issues, and

Methodology," describes the regulatory instruments, the selection of components, the rationale for the aging issues, the instrument review criteria,

and the review methodology. Also included in Section 2.0 are two typical

examples of how to use the tabular data in Appendixes II through VI.

Section 3.0, "Discussion," provides background information on the regulatory instruments versus aging management and the aging issues. Specific

examples of aging management guidance, either direct or indirect, are provided

for each instrument.

The "Conclusions and Recommendations," "Suggested Future Regulatory

Instrument Review Activities," and "Observations Outside the Scope of the

Review" are found, respectively, in Sections 4.0, 5.0 and 6.0 of this report.

(a) The regulatory instruments, e.g., Code of Federal Regulations and

American Society of Mechanical Engineers Code, frequently make use of the

Appendix A, B, etc., within their text; therefore, the appendixes

attached to this report will be designated in Roman numerals to distinguish them from those found in the instruments.

1.2
2.0 SELECTION OF INSTRUMENTS. COMPONENTS AND ISSUES. AND METHODOLOGY

This section describes regulatory instruments, the selection of the

major components, the rationale for selection of the aging issues, and the

development of the review criteria and methodology. Examples of how to use

the review information contained in appendixes are included.

2.1 REGULATORY INSTRUMENTS REVIEWED

The following regulatory instruments were reviewed for this report.

While not necessarily all inclusive, they are the most important and applicable to the pressure boundary aspects of the current components. IEEE

Standards were added to the list to account for the electrical aspects of the

emergency diesel generators and pressurizer. IEEE Standards were not

considered in the reviews of RPV, steam generator (SG), or the primary

piping. PNL staff with experience in the aging issues and familiarity with

the applicable regulatory instrument performed the reviews and interpreted

the instrument text.

* Standard Review Plan (SRP)

* Code of Federal Regulations (CFR)

* NRC Regulatory Guides (RG)

* American Society of Mechanical Engineers (ASME) Boiler and Pressure

Vessel Code (BPVC), Sections III and XI

* Generic Safety Issues (GSI)

* Technical Specifications (TS)

* Institute of Electrical and Electronics Engineers, Inc. (IEEE) Standards

* American Nuclear Society (ANS) Standards.

Each instrument is described below.

* Standard Review Plan. The SRP is published by the NRC and provides

guidance for the review of Preliminary Safety Analysis Reports (SAR)

and the Final Safety Analysis Reports (FSAR) for plant design and operations. The SRP contains 18 chapters and covers all facets of NPP

operations, including plant descriptions, design and construction,

safety features, instrumentation, electrical power, radiation protection, waste management, quality assurance, and human factors engineering. The SRP also presents specific Branch Technical Positions (BTPs)

that are developed and published by branches within the NRC, e.g., BTP

ISCB 19 by the Information Security Branch found in SRP Chapter 7,

Instrumentation and Controls.

2.1
* Code of Federal Regulations. These regulations codify general and

permanent rules published in the U.S. Federal Register by the Executive

departments and agencies of the U.S. Federal Government. With reference

to this report, these codes establish the rules for design, construction

licensing and operation of commercial NPPs. For the NRC, a federal

agency, the most significant CFR relating to commercial reactors is

Title 10, Chapter 1, Part 50, Domestic Licensing of Production and

Utilization Facilities. Part 50 includes important appendixes, such as

the General Design Criteria requirements, specific material requirements

for reactor vessels, emergency planning, and quality assurance criteria

for NPPs.

* Regulatory Guides. These guides are published by the NRC in 10 broad

divisions, including Division 1, Power Reactors. The guides are available to the public and NPP licensees. They provide general guidance to

applicants and describe methods acceptable to the NRC staff, to implement specific parts of the Commission's regulations and, to delineate

evaluation techniques used by NRC staff for specific problems and postulated accidents. The RGs often explain and detail acceptable methods

for the rules found in the CFRs.

* American Society of Mechanical Engineers. Boiler and Pressure Vessel

Code. Sections III and XI. The ASME Code establishes the rules of

safety governing design, construction, operation and testing of NPP

components and systems. Section III covers a broad range of components

and systems including, pressure vessels, piping, pumps, valves, supports

and core internals. Section XI provides rules for inservice inspection

of components and systems. Section XI constitutes the requirements of

examinations, testing and inspection to maintain an NPP in a safe and

expeditions manner. Section XI is applicable when the requirements of

the Construction Code, e.g., Section III, have been satisfied. The ASME

Code Editions, Addenda and Code Cases used by the owners of NPPs are

subject to acceptance by the NRC. The ASME codes are frequently referenced in the CFRs. The ASME Maintenance and Operation (O&M) committees

provide an important function through the testing of pumps, valves and

snubbers.

* Generic Safety Issues. GSIs are published by NRC to identify safety

issues generic to NPPs. The GSIs can cover a wide variety of subjects;

however, for the purposes of this review, the GSIs used are those that

are predominately concerned with material degradation and operations

that cause degradation of plant components. When a solution to the

generic issue is found, the usual result is an NRC Generic Letter or an

NRC NUREG report that provides an industry wide dissemination of the

solution.

* Technical Specifications. Technical Specifications are NPP mandatory

operational specifications that provide instructions for limiting conditions and surveillance requirements for plant operations. License

applications for authority to operate an NPP are required to supply

Technical Specifications as enumerated in 10 CFR 50, Section 50.36.

2.2
* Institute of Electrical and Electronic Engineers Standards. The IEEE

Standards present criteria and requirements for electrical systems that

are specifically related to providing protection to the health and

safety of the public. The standards included in this review are principally those prepared by the IEEE Nuclear Power Engineering Committee.

The IEEE Standards, through the Equipment Qualification (EQ) standards

define "qualified life" and provide guidance for requalification or

replacement of components when their qualified life is reached. The

IEEE standards are not mandatory and use of the standards is wholly

voluntary. Use of the standards, as acceptable practice, are subject to

the approval of the regulatory agency, i.e., the NRC. Specific IEEE

standards are frequently called out and/or qualified in the Regulatory

Position Section of the RGs as acceptable to NRC staff.

* American Nuclear Society Standards. The ANS standards are agreements

among designers, engineers, governmental regulatory agencies, manufacturers, and nuclear scientists. The standards are developed to provide

current practices on various subjects that affect NPPs. Among the subjects are criteria for earthquake Instrumentation, various safety

guides, selection and training of personnel, QA, security for NPPs, and

auxiliary feedwater system for PWRs. The ANS standards are frequently

published as American National Standards with the approval of the

American National Standards Institute (ANSI). ANS standards are guides

for prospective use and are not mandatory; the designers are not

restricted to the ANS standards and may propose alternate criteria to

provide adequate safety.

These instruments are listed in column 2 of the component reviews Appendixes

II through VI.

2.2 MAJOR COMPONENTS

The following components were chosen for the current review. They were

selected from the major LWR plant elements of current interest in the NPAR

program, as found in Table 5.3 of the NPAR program document NUREG-1144,

Nuclear Plant Aging Research Program Plan. These selected components are

recognized by the NRC as safety-related components that historically, in

varying degrees, are subject to aging problems. Finally, the selected

components provide a good mix for the review by covering the three major

design disciplines, i.e., structural, mechanical and electrical. The

components are listed in Column 1 of Appendix II through VI.

* reactor pressure vessel

* steam generator

* primary piping (reactor coolant piping)

2.3
* pressurizer

* emergency diesel generator.

2.3 AGING ISSUES

Listed below is a list of the component aging issues used in the

instrument review.

* corrosion

* corrosion/erosion

* crack initiation and flaw propagation

* creep/swelling

* element burnout(s)

* erosion

* examination, inspection and maintenance and repair

* excessive/harsh testing

* fatigue

* fracture toughness

* intergranular stress corrosion cracking

* irradiation embrittlement

* low-flux long-time irradiation of vessel internals and supports

a seismic failure/damage

* specific environmental factors, e.g., moisture, oxidation, chemicals,

oils, and dust.

* stress corrosion

* stud failure

* thermal cycles

* thermal embrittlement

* thermally induced bending

2.4
* thermally induced mechanical wear

* transient thermal loads

* tube specific - denting, fretting and crevice corrosion

* vibration

* wear

* weldments - specific to dissimilar metals of safe ends.

For illustrative purposes, some of the aging issues of the instrument

review are shown below.

For the reactor pressure vessel (RPV),

* IRRADIATION EMBRITTLEMENT - degradation of the structural integrity of

vessel materials due to the consequences of long-term exposure to high

radiation levels that induce changes in the vessel's material

properties.

* FATIGUE - degradation associated with cyclic loading, transient cycles,

and thermal and pressure cycles.

For the steam generator (SG),

* CORROSION - degradation associated with the deterioration of material

surfaces, chiefly, through chemical actions. The chemical reaction is

influenced by environment of the material or component.

* TUBE SPECIFIC (DENTING, FRETTING AND CREVICE CORROSION) - aging issues

associated with the generator tubes include denting caused by the

crevice corrosion of the tube support plate and tube sheet material;

fretting is caused by the wear action between the tubes, tube supports

and antivibration bars; crevice corrosion due to localized stagnant

solutions in lap Joints, holes, welding surfaces, etc.

All specific aging issues were derived from the general guidance found

in NUREG-1144, Rev. I., Section 2.1 (NRC 1987a). Typical degradation

mechanisms are neutron embrittlement, fatigue, erosion, corrosion, oxidation,

thermal embrittlement, and chemical reactions. Aging is also induced by

stressors, e.g., service wear, testing, improper installation, and application and maintenance.

Each aging issue was considered, and those believed by PNL staff to be

specific to the components were chosen for the review. The aging issues for

each component were then grouped into principal categories that define the

mechanics or phenomena of the aging processes for the component. For a

typical example see Appendix III, page 11I.9, item (50), Dynamic effects,

that includes vibration, thermal cycles and erosion.

2.5
Aging issues are not necessarily specific or all inclusive for each

component nor do they manifest themselves in the same way for each component.

For example, neutron embrittlement is not typical to all components. Radiation is unique to the RPV and is not generally regarded as a problem in the

other review components. On the other hand, the RPV as a pressure retaining

component has many safety-related degradation problems that are common to all

vessels and piping systems.

The aging issues for each component are found in column 3 of the review

Appendixes II through VI.

2.4 REVIEW CRITERIA

The review criteria chosen to examine the regulatory instruments answer

three questions: 1) Do the instruments address aging? 2) If so, in what

form is the aging addressed? For example is aging management implied or

explicit and is the guidance or direction adequate or incomplete for the

aging issue? 3) What are the current initiatives that would change the

instruments to address aging and life extension?

The review criteria as they appear in the component review sections are

noted below with a brief definition:

1. Aging Features:

2. Life Extension

Features:

3. Current

Initiatives:

4. Aging Needs:

5. Life Extension

Needs:

What parts of the instrument, if any, identify the

management of component aging. Are aging issues

addressed by the instrument? Is the information

implied or explicitly expressed?

Does the instrument address life extension or

component replacement needs?

Is work currently underway to update or change

the instrument to include aging features or life

extension features? What, if any, is the status

of special working groups, of technical committees,

or of on-going research that could lead to the

revision of the instruments to include these

features?

What changes or revisions generally are needed in

the instrument to address aging issues?

Does the instrument require further investigation/

research of the aging issue to accommodate life

extension? How could the instrument be used or

modified to meet life extension needs?

The review criteria are listed in columns 4 through 8 on each page of

the component review sections, Appendixes II through VI.

2.6
2.5 REVIEW METHODOLOGY

Each regulatory instrument was examined for data for each designated

major component's aging issues. Thus the regulatory instrument review for a

component with five aging issues required five reviews for each instrument.

The review relative to the components was carried out in the generic sense;

that is, no distinction was made for the different configurations or manufacturers of SGs or for RPVs, or for PWRs versus BWRs. However, the review

does account for the regulatory documents that specifically address a design

configuration or type of reactor. The general approach was to review the

instrument for reference to the aging issues or for a specific reference to

the major components by name or system.

Typically, minimal specific component or aging issues references, by

name, are found in the regulatory instruments. The principal reference is to

systems, such as the reactor coolant system or reactor containment. However,

there are some exceptions; Appendix G, in 10 CFR 50, is specific for fracture

toughness requirements and Appendix H is specific for surveillance requirements to monitor changes in fracture toughness. If the instrument revealed

any relationship or potential relationship to the aging issue, further

analysis was conducted to determine the explicit and/or implied relationship.

The related information, if found, was analyzed by using the review criteria

of Section 2.4. Applicable results of the five review criteria analysis were

entered in columns 4 through 8 for each of the aging issues designated for

each component (see Appendix II through VI). Special attention was given to

the current initiatives criteria, and a number of on-going actions were noted

throughout the review. Criteria 1, Aging Feature, is the key criteria of

this review and provides the bulk of the information found in the regulatory

instruments and indeed provides the emphasis to examine the instrument in

more detail. The larger instruments, e.g., the SRP and ASME code, were

investigated by subsections, chapters, etc., and those sections that were

completely unrelated to the aging issues were ignored for detailed analysis.

The smaller instruments, e.g, RGs and IEEE standards, were investigated as a

whole. Many of the instruments were eliminated by title or subject or

objectively determined not to be related to the aging issue(s).

2.6 REVIEW EXAMPLES

Two examples from the PNL regulatory instrument review are shown below.

Example I examines the NRC RGs for the issue of EXAMINATION, INSPECTION AND

MAINTENANCE AND REPAIR as they apply to the RPVs. Example 2 examines the

GSIs for the issue of IRRADIATION EMBRITTLEMENT as applied to the RPVs. Each

example begins with a question, followed by an answer.

ExamDle 1

Do the RGs refer to the aging issue of EXAMINATION, INSPECTION AND

MAINTENANCE AND REPAIR with respect to RPVs?

2.7
* On page 11.5 of Appendix II, five entries are shown for the RGs items

(15) through (19). For example, item (15), RG 1.150, indicates that

this RG does have an Aging Feature (Column 4), "UT of RPV welds,"

discusses evaluation of prior UT examinations for determination of crack

growth rates, and Life Extension Features (Column 5), "Inservice inspection (ISI)," discusses continued structural integrity of reactor through

reliable flaw detection vessels. No Current Initiatives (Column 6) were

found; the entry refers to Note 1, page II.3 which indicates a need for

further study. Aging Needs and Life Extension Needs (Columns 7 and 8)

were shown to be suggestions for improved flaw detection and assessment.

The comments (Column 9) note that cracks may propagate from cladding

into the steel (shell) in the RPV and raises the question that 100% UT

may be required for BWR to assess under cladding cracks.

Example 2

Do the GSIs refer to the aging issue of FRACTURE TOUGHNESS with respect

to RPVs?

As shown on page II.10 of Appendix It, three entries, items (56) through

(58), were made for the GSI relative to the noted issue. The first

entry, Item (56), indicates that GSI A-li (Column 3) does have an Aging

Feature (Column 4). Column 4 notes that "As plants accumulate more and

more service time, neutron irradiation reduces the material fracture

toughness and initial margins of safety." The GSI does not discuss

Life Extension Features (Column 5) and it has no Current Initiatives

(Column 6). For the Aging Needs (Column 7) and Life Extension Needs

(Column 8), an entry is made indicating that further analysis is needed

to resolve these review criteria. The comment (Column 9) indicates the

priority for this issue has been resolved with the issuance of

NUREG-0744 (NRC 1982).

2.8
3.0 DISCUSSION

Although the review data on regulatory instruments developed in this

study, as presented in the Appendixes II through VI for each component,

appear to be comprehensive, the reader is cautioned that the magnitude of the

literature, research time, and funding levels did not permit an exhaustive

study of all the text, references and background documentation on each

instrument. The review is, however, a good overview of the degree to which

aging guidance is found in the regulatory instruments. The following sections provide discussion and insights as to the effectiveness of the safety

regulations to provide guidance for the management of aging.

3.1 REGULATORY INSTRUMENTS AND AGING MANAGEMENT

The PNL review revealed that, in effect, the regulatory instruments do

contain information that does relate either directly or indirectly to current

safety-related concerns and aging management. A strong corollary exists

between safety and aging management, i.e., it is implied that a safe plant is

more likely to be well maintained and more effectively monitored for problems

and degradation. Yet, generally speaking, the instrument review does not

reveal explicit requirements for aging and life extension needs or features.

The majority of related information, i.e., the aging features of the instruments, is interpreted by PNL staff to be implied guidance. The implied guidance or, in some cases mandatory guidance, i.e., the technical specifications

(TSs), have been useful in the management of aging. Simply stated, the

safety-oriented regulatory instruments used for NPP have indirectly managed

aging through safety-oriented design and safe operations.

3.2 REGULATORY INSTRUMENTS AND THE AGING ISSUES

This section presents the key objective of the review, which is contained in the question, "Do the regulatory instruments address aging issues?"

In this section, a general assessment statement is provided for each instrument relative to the aging issues.

Each issue is listed in Section 2.3 and defined in the glossary of

Appendix I. Examples of specific features in each regulatory instrument that

address aging issues are included with a typical degree of depth on how the

instrument addresses an issue. (In this section, the instruments are

discussed in the order that they appear in the review data, Appendix II

through VI.)

3.2.1 Code of Federal Regulations

The CFRs are the principal base for all the regulations that mandate the

design, construction, inspection and operation of the components chosen in

this review. Appendix A, General Design Criteria for Nuclear Power Plants

(GDC), 10 CFR 50, provides the largest measure of implied aging management.

3.1
The GDC of Appendix A coupled with Section 50.55a, Codes and Standards,

provides the broad base design and inspection requirements.

The CFRs tend to be generic in description because they often address

broad plant categories such as the reactor coolant pressure boundary. In

this review, four of the components considered are within the reactor coolant

pressure boundary. Consequently, the Criterion needs given in 10 CFR 50,

Appendix A, implies aging management even though the component is not

mentioned in specific description. In general, the review components, with

the exception of the RPV, as referenced in 10 CFR 50, Appendix G and H, are

not discussed in the CFRs. Aging and life extension are not explicitly cited

in the text. NPAR aging, as defined in the introduction, does not appear.

The implied aging features as found in the review, are based principally on

the assumption that a reactor designed, constructed, tested and operated

within the rules of 10 CFR 50 will provide the licensee a facility that can

be managed for aging. Aging does appear in 10 CFR Part 50, §50.49, "Environmental qualification of electric equipment important to safety for nuclear

power plants," (e), (5). This aging is in reference to equipment qualified

by test and preconditioned by natural or accelerated aging. Also, in 10 CFR,

Part 50, Section 50.109, Backfitting, c, (8), states that "the potential

impact of difference in facility type, design or age on the relevancy and

practicality of the proposed backfit," will be considered when addressing

backfit requirements. Yet in these examples, the "aging" and "age" are not

used in the same context as NPAR defined aging.

The following are typical examples of the more specific requirements of

CFRs; while not using the terms aging and life extension, these examples may

be regarded as aging management guidance:

10 CFR 50, Appendix A, General Design Criteria for Nuclear Power Plants,

Criterion 51, states that "The reactor containment boundary shall be

designed with sufficient margin to assure that under operating, maintenance, testing, and postulated accident conditions (1) its ferritic

materials behave in a nonbrittle manner and (2) the probability of

rapidly propagating fracture is minimized. The design shall reflect

consideration of service temperatures and other conditions of the

containment boundary material during operation, maintenance, testing,

and postulated accident conditions, and the uncertainties in determining

(1) material properties, (2) residual, steady state, and transient

stresses, and (3) size of flaws." Aging and life extension are not

specifically used in the above quote; however, the criterion does

address a number of aging issues identified in this review including,

irradiation and thermal embrittlement, fracture toughness, fatigue,

thermal cycles, crack formation and growth, testing and maintenance and

seismic failure/damage. The criterion terminology of "under operating,

maintenance, testing, and postulated accident conditions" encompasses

all plant operating phases and strongly advocates a design that assures

material reliability throughout the plant's operating period.

3.2
* Appendix A, Criterion 2, address the aging issue of seismic failure/

damage. The criterion states that "structures, systems and components

important to safety shall be designed to withstand the effects of

natural phenomena such as earthquakes, tornadoes, hurricanes, floods,

tsunami, and seiches without loss of capability to perform their safety

functions." The design is subject to the most severe (historically)

known natural occurrence, to the combinations of normal conditions and

accident conditions and natural phenomena and, to the importance of the

safety function performed.

3.2.2 Technical Specifications

The TSs are mandatory requirements that provide the safety limits, the

limiting safety systems settings, the limiting conditions for operations and

the surveillance requirements for NPPs. TSs should not be confused with or

called "guides" because they provide specific mandatory rules for operation

of a particular plant. They are required for NPP operations by the rules of

the CFRs and are enforced for the life of the plant. TSs may provide aging

management through enforcement of limits that are set at acceptable levels or

procedures which will control, reduce, mitigate, detect or preclude aging

degradation. The TSs, for example, require that safety-related equipment be

in acceptable operable condition or, if not repaired within a specific time

frame, the plant will be shut down. TSs also require records to be maintained for operating cycles, e.g., cyclic loading/P/T cycles. These records

can provide documentation for material life or life extension documentation.

The TSs reference the ASME code, Section XI, for inservice inspection.

The following are examples of specific TS applications that contain

implied aging management.

* Technical specifications require inspection for "wall penetrations" or

other modes of SG tube wall thinning. This requirement addresses the

aging issue of erosion. The present inspection technique is eddy

current for a fraction of the SG tubes on a 12-to-24 month basis.

* Thermal pressure cycles are recorded during thermal/pressure reactor

coolant heat-up or cool-down on the primary side only. These cycles are

useful for aging management by providing records for evaluation of the

reactor coolant system P/T and PTS history.

* TSs require primary reactor coolant system (RCS) chemistry control and

the retention of water analyses and associated records. This information is useful in determining the water chemistry history of RCS and is

useful in the management of aging and life extension.

* The TSs require inspection of component and equipment mechanical

restraints, snubbers, on a periodic basis. Failure of visual or

functional tests require maintenance or replacement.

3.3
3.2.3 Standard Review Plan

The SRP by definition (see Section 2.1) provides a plan "for the review

of safety analysis reports (SARs) for nuclear power plants." The SRP consists of eighteen chapters, ranging from site description of the plant and

design of structures and components to human factors engineering. The principal concern of the SRP is safety, e.g., does the SRP review of the FSAR

indicate that a plant can be started and operated safely and, if a failure

occurs, can the plant be shut down in a safe manner? The SRP, typically,

wants to know whether the plant design/procedures comply with applicable

CFRs, such as 10 CFR 50.55a, inservice inspection. Many of the implied aging

features in the SRP occur because of references to the ASME Code, 10 CFR 50,

General Design Criteria and other standards.

Specific examples of aging related guidance in the SRP are as follows:

* SRP 5.2.3, Reactor Coolant Pressure Boundary Materials, discusses the

review of suitable materials and review of procedures for manufacturing

and welding. The SRP has implied aging management by determining

whether the plant design has used the right materials, i.e., correct

materials will or should stand up to the plant operation and

environment.

* SRP 3.9.2 has an aging feature for the dynamic effects of vibrations

through the review of the structural and functional integrity of the

piping systems under vibratory loads.

3.2.4 Regulatorv Guides

The RGs are principally issued to describe methods acceptable to NRC

staff and to provide guidance to applicants in the use of the 10 CFR 50

regulations, especially as applied to the GDC. The "Introduction" of a RG

will frequently refer to the importance of safety and safety systems;

"aging," on-the-other-hand, is not part of the text. Yet some of the RGs do

discuss the aging issues. Information on corrosion, vibration, progressive

tube deterioration, and secondary water chemistry maintenance, e.g., may be

found in the "Discussions section of RG 1.83; however, the purpose of RG 1.83

is for guidance in the performance of inservice inspections (ISI) for steam

generators. Some individual RGs may be specific to a single component or

part of a component, and these individual RGs tend to support the direct

management of aging, even though the intent of an RG is to promote safety.

Examples of aging management guidance in RGs are shown below:

Degradation of steam generator tubes has been identified as a problem

because of mechanical damage or progressive deterioration caused by

inadequate design, manufacturing errors, or chemical imbalance. Tube

problems are caused by a number of mechanisms including, IGSCC, IGA,

pitting, denting, fatigue, wastage and erosion/corrosion. Management

of the tube degradation is assisted by RG 1.121, "Bases for Plugging

Degraded PWR Steam Generator Tubes." The guide describes methods

3.4
acceptable to the NRC staff for establishing limiting safe conditions

of SG tube degradation. Conditions beyond the limiting safe conditions

should result in removal from service by plugging (welding each end) of

the tubes.

Regulatory Guide 1.85 allows the use of approved ASME "Code Cases," thus

providing a mechanism to use current repair and replacement techniques

within the Jurisdiction of the code. These alternate methods within the

jurisdiction of the code may provide improvements in repairs and materials that could enhance aging management and life extension.

3.2.5 ASME Boiler and Pressure Vessel

The ASME Boiler and Pressure Vessel Code, especially Section III and

Section XI, are used for the design and construction of NPPs. Section XI,

inservice inspection remains in effect throughout the life of a plant and

provides inspection criteria, intervals, and acceptable methods. Sections of

the ASME code are mandated in 10 CFR 50, Section §50.55a, Codes and Standards, which specifically notes that "Structures, systems, and components of

boiling water and pressurized water-cooled nuclear power plants must meet the

requirements of the ASME Boiler and Pressure Vessel Code." Manufacturers and

designers are expected to use sound engineering practice and Judgment within

the rules of the Code. The expressed purpose of the Code is to provide

protection of life and property and a margin for deterioration in service for

a reasonably long, safe period of usefulness. The review, however, reveals

that material deterioration is not fully addressed and needs attention. The

ASME Code does, in general, address "life of plant" issues and, in some

cases, it is very specific, e.g., corrosion allowances for vessel and pipe

thickness. The Code also provides for use of current technology for repairs/

replacement and materials by the use of approved Code Cases. The Code is a

living document which is currently revised and published every three years,

e.g., the latest was published July 1, 1989. Addenda are issued in December

of the years between major publications. Code interpretations are usually

provided twice a year as an update service to the various sections.

The following are examples of the Code that are related to agingmanagement issues:

* A strong implied aging features exist in Section III, Class I, piping.

If corrosion or erosion is expected, the piping thickness, shall be

increased over the design thickness to be consistent with the specified

design life.

* The ASME Code recognizes that problems exist and, consequently, the code

is under continuous revision to effect improvements and changes. For

example, a Section XI, Special Working Group (SWG), has implemented

revisions to IWA 2400 which will delete the current 40-year operating

limit of nuclear plants. A SWG has been set up to consider the development of a new Section XI, Article IWX-8000, called Requalification of

Fatigue Life. A Section III, SWG is also reviewing fatigue curves to

determine revisions to accommodate operation beyond the 40 years. A new

3.5
Subsection IWT for Section XI is now under consideration by ASME; the

subsection addresses the aging-related issue of erosion-corrosion.

3.2.6 Generic Safety Issues

Generic Safety Issues, as their name implies, are concerned with safety

issues common to all NPPs or to types of LWRs, PWRs or BWRs. The GSIs do not

explicitly reference aging management. The GSIs are, however, concerned with

many of the aging issues, and the reader will note that, in the reviews,

Appendix II through VI, the aging issues for each component are frequently

the subject of a GSI, including cracking and degradation of bolts, mitigation

of steam generator rupture/degradation, SCC, fracture toughness, corrosion of

interior metal surfaces, control of overfilling transients, pressurized

thermal shock, and neutron irradiation of RPY welds. Thus the GSIs identify

many aging issues as problems, and this identification process does assist in

the management of aging. When a solution to the problem is determined,

management of the problem, i.e., the aging issue, is addressed by the NRC

usually through Generic Letters, NUREGs and the SRP/BTP.

Examples of applicable aging issue subjects found in GSIs are listed

below.

* GSI A-1l notes that as plants accumulate increasing service time that

neutron irradiation reduces the fracture toughness and the initial

margins of safety. This issue was thought to have been resolved by

NUREG-0744 (NRC-1982); however, a need to monitor and analyze trends of

nil-ductility temperature exists; that is, what are the impacts of

extended life on brittleness? A related GSI is USI A-49. This issue is

concerned with irradiation of reactor vessel weld and plate materials

and the reduction of fracture toughness in these materials.

* GSI 29 addresses cracking and degradation of bolts and studs from stress

corrosion, fatigue, and boric acid corrosion.

* GSI A-15 addresses the aging issue of corrosion activated by neutron

flux. Operation of LWRs result in slow corrosion of interior metal

surfaces of the primary coolant system.

* GSI A-12 addressed the problems of lamellar tearing and low fracture

toughness in SG and reactor pump supports. This problem was also

addressed in NUREG-0577 (NRC-1979), Potential for Gas Fracture Toughness

and Lamellar Tearina on PWR Steam Generator and Reactor Coolant Pump

Supports.

GSI A-3 and A-4 reported the SG tubing degradation due to wastage and

SCC in Westinghouse SG (A-3) and Combustion Engineering SG (A-4).

3.2.7 Institute of Electrical and Electronic Engineers Standards

Many of the IEEE standards provide qualification/acceptance criteria;

thus they tend to dictate an aging management perspective through

3.6
qualification testing. The IEEE standards cover a multiplicity of subjects

related to electrical and electronic systems. Numerous IEEE standards are

dedicated specifically to the nuclear industry's Class IE equipment, and it

is these specific standards that this review investigated. The IEEE standards are frequently referenced in the regulatory instruments, such as the

SRP. The regulatory basis for the use of the IEEE standards is found in the

CFRs and the RGs. The NRC RGs frequently, in the 'Regulatory Position* section, list the IEEE standards that are acceptable (with exceptions) to the

NRC staff for satisfying the Commission's regulatory requirements. The

standards are generally not acceptable in whole and the "Regulatory Position"

will state the exceptions or other requirements. The majority of IEEE standards are jointly approved by the ANSI and may be designated as ANSI/IEEE and

published as an American National Standard.

The following are some specific examples of the explicit and implied

aging management found in the IEEE standards:

* The IEEE standards require that an assessment of the effects of aging

must be addressed when considering the ability of equipment to perform

safety functions. Types of aging that must be addressed include vibration, wear, and natural and environmental conditions. Standard 323

recognizes the need for aging management and defines the steps to

address aging. This standard defines aging and explicitly address the

subject. IEEE 323 defines aging as "the effect of operational, environmental, and system conditions on equipment during a period of time up

to, but not including design basis events, or the process of simulating

these events."

* IEEE standards recommend establishment of procedural practices to obtain

the qualifying (test) data. The data is required to qualify that the

equipment will meet its performance requirements following one safe

shutdown earthquake (SSE). Included are tests for vibrational aging,

seismic aging and normal operating loads. IEEE 323 defines qualification as "the generation and maintenance of evidence to ensure that the

equipment will operate on demand to meet the system performance

requirements."

* IEEE 934 standard addresses an aging perspective by providing criteria

for the use of replacement parts for both construction and operations.

The standard requires acceptance testing of parts for wear, fatigue,

defects and insulation breakdown prior to release to service. Failure

of parts provides aging management by addressing the aging issues, e.g.,

wear and fatigue and insulation breakdown.

3.2.8 American Nuclear Society Standards

The ANS prepares and publishes standards for the design and operation of

NPPs. The standards are usually published as Joint American National Standards Institute (ANSI) and ANS standards. The ANSI/ANS standards tend to be

more safety specific than are the other instruments included in this review.

The ANS standards do not, however, explicitly mention aging or aging

3.7
management. They were included in the review because they do address a

number of the aging issues for various components.

Some examples of the ANS standards that can be related to implied aging

are as follows:

* ANS-3.2 provides requirements and recommendations for administrative

control, including written procedures for activities associated with NPP

operation to help ensure that operations are carried out without undue

risk to health and safety of the public. Among the activities are aging

activities of inspection, testing and maintenance and repair.

* ANS-58.11 provides design criteria for achieving and maintaining cold

shutdown conditions from a hot standby or post accident condition. This

standard is explicit to safety; however, aging management of pressure

and temperature cycles are addressed and adverse conditions are modulated by the suggested design criteria that confront nuclear safety

issues of reactivity control, RCS integrity, P/T control, heat removal,

and inventory control.

3.2.9 General Correlation of Implied Aging

While the above examples for all of the regulatory instruments and

indeed the instrument review itself tend to correlate with the "implied"

aging scenario, most of the instruments were developed to emphasize plant

design and construction, plant pre-operational stages, and SARs. The instruments include concepts related to pertinent aging issues, but they were not

written to solve aging problems or manage those issues. However, it is also

true that some of the instruments apply throughout the life of the plant.

The SARs are effective for the life of the plant and receive annual updates.

Codes and standards, such as IEEE standards, that are noted in the SARs or

other correspondence/agreements become a life-of-plant commitment. The Code

of Federal Regulations apply throughout the life of the plant. The TSs apply

throughout the length of the license and the ASME B&PV Code, Section XI,

applies as long as the plant operates. In addition, the NRC Regulatory

Guides apply and may become part of the license commitment if the utility

commits to the guidance of the RG. GSI resolutions can be implemented

throughout the life of the NPPs and become part of the licensing base.

3.8
4.0 CONCLUSIONS AND RECOMMENDATIONS

The following conclusions and recommendations were derived from the work

completed to date on the five components selected for the first part,

Volume 1, of the regulatory instrument review.

4.1 CONCLUSIONS

The following are the central conclusions derived from the review:

* The instruments included in this review, with minor exceptions, do not

explicitly use aging or life extension terminology. The instruments, by

definition, are dedicated to safety and have the ultimate purpose to

establish and maintain safe operation of NPPs. Yet aging management

does exist in them because safety-related design, construction and

operation are consistent with the principles needed to provide aging

management and life extension. This is to say, the technology associated with providing safety is congruous with technology required for

management of aging.

* The emphasis in the regulatory instruments is on design, construction,

equipment qualification and on the final safety review that will provide

a safe plant at start-up. Specific actions to address aging and aging

management, on the other hand, are generally initiated after a plant is

placed in service.

* Revisions should be made to the instruments that explicitly address

aging, see 4.2, Recommendations. Revisions will be difficult to

achieve. Revisions of an instrument by instrument basis is the most

practical approach at this time.

4.2 RECOMMENDATIONS

The following are the primary recommendations identified as a result of

the review:

The content of the regulatory instruments need to be changed to

explicitly address the consequences of component, systems or structures

(CSS) aging rates. Aging (degradation) rates are often not explicitly

addressed in the body of the instruments and a key principal in the

management of aging is understanding the rate of degradation over time.

Emphasis on CSS aging rates, in the body of regulatory instruments, will

serve five purposes: 1) establish an explicit need in NPP functional

design criteria; 2) accelerate the improvement in trending and the

methods of obtaining trending data; 3) accelerate the upgrading of

applicable codes and standards; 4) accelerate the improvement in NDE

tools and methods; and 5) improve CSS design and improve the design

margins or the factors of safety needed.

4.1
* Project planning for revisions to the instruments will be a key feature

in the success of any revision strategy and should address, as a

minimum, the following questions:

1. Should the individual instruments be changed or should a new

comprehensive regulatory guide be prepared to address the aging

management issue?

2. What is the status of current industrial aging-related activities,

such as EPRI research efforts, Nuclear Management and Resource

Council (NUMARC) and Nuclear Plant Life Extension Committee

(NUPLEX) reports, industry sponsored working group guidelines,

documents and standards? (All sound solutions to aging problems

should be included in the revision process.)

3. What is the status of existing national society codes and standards

relative to aging initiatives? This status check should include

codes and/or standards of societies such as ASME, ANS, ANSI,

National Fire Code (NFC), American Society of Testing and Materials

(ASTM), American Concrete Institute (ACI), IEEE, and PLEX. (ASME

has been given the overall PLEX responsibility for all standards

groups.)

4. What is a realistic time frame for implementation of the revisions?

4.2
5.0 SUGGESTED FUTURE REGULATORY INSTRUMENT REVIEW ACTIVITIES

The following are activities that should be considered for future work

associated with this review task.

5.1 CONTINUATION OF THE GUIDE TO REGULATORY INSTRUMENTS

During the course of this instrument review, a Technical Evaluation

Report containing the results of the review on LWR reactor pressure vessels

was published: PNL-6848, Guide to Regulatorv Instruments for LWR Reactor

Pressure Vessels: Aging and License Renewal Considerations. The results

contained in PNL-6848 are included in this report as Appendix II. It is

suggested that the results of all the reviews, Appendix III, IV, and V and

the reviews of FY 1990, be added to PNL-6848.

5.2 COMPUTER DATA BASE FOR THE REGULATORY INSTRUMENT REVIEW

It is suggested that the basic data from the Regulatory Instrument

Review, Appendixes II through VI, be installed on a computer data-base system

to make the information available for broader use. Information collected on

other components should be added to the data base as it becomes available.

5.1
6.0 OBSERVATIONS OUTSIDE THE SCOPE OF THE REVIEW

The following are observations and recommendations that arose out of the

review results that are not directly related to the objectives of the instrument review. They are based on the analysis of the instruments used to conduct the review, mainly on a close review of the comments included in the

tables in Appendixes II through VI. For final validation, these observations

should be subject to further study.

COMPONENT REPLACEMENT

In general the regulatory instruments reviewed do not address component

replacement as an aging management tool. Many components have design

features for replacement and have been replaced well within the 40-year

license period. Components such as, pumps, valves, motors, electrical and

instrument controls fall within this category and are routinely replaced.

Some components, notably the SG and primary piping, were never intended to be

replaced; yet, a number of these replacements have been made within the

40-year license period. Some replacement direction is provided through

components under TS surveillance and replacements will be made if repairs

cannot be successfully performed. Also, electrical qualified (EQ) components

within containment will be replaced according to their lifetime qualification

testing. Thus, the scenario is that replacements are taking place because of

design and necessity and within the Jurisdiction of regulations/codes. The

emphasis of the body of instruments, however, does not address replacement as

a management tool. It is concluded that the instruments revisions should

emphasize replacement methods by encouraging design for routine replacement

and by encouraging improvement in CSS life assessment methods, including

improved material degradation trends and component life predictions.

A factor in replacement methods is Diminishing Manufacturing Sources

(DMS) or the increased unavailability of parts and components from manufacturers. DMS results in an increased vertical unsupportability of aging

components and subsystems. DMS also results in an increase in maintenance

costs. The NRC has identified DMS problems (NRC 1986) within the nuclear

industry. These problems have resulted in down time and the necessity to

operate in a degraded mode because of unavailable replacement parts. DMS has

been identified by the Department of Defense (DOD) as a serious and prevalent

problem. The DOD has, however, taken aggressive action to counteract the DMS

phenomenon, e.g., using performance specifications rather than plant specifications, using improved long range forecasting and using improved procurement techniques. It is suggested that improved component NPP replacement

methods should recognize the DMS problem and actively pursue solutions

similar to the DOD strategy.

IMPROVED ISI METHODS AND TOOLS

The regulatory instrument review revealed that the management of aging

could be enhanced with improved ISI tools, e.g., Appendix II, page I1.13,

item (83) of this review for the reactor pressure vessels, with reference to

6.1
RG 1.150, states that improved flaw detection for the distribution of microflaws is needed. Also Appendix III, page III.13, item 92, addresses the

aging issue, embrittlement, for the steam generator, with reference to

10 CFR 50, Appendix A, Criterion 51. Criterion 51 stipulates that the containment pressure boundary be designed for operating, testing and postulated

accidents such that the ferritic materials behave in a non brittle manner.

The Aging Needs, Column 7 for item 92 states that 'Methods to measure

embrittlement properties" are needed. The Life Extension Needs Column 8

states that "Improved NDE techniques to determine embrittlement properties"

are needed. Therefore, for item 92, the review recognizes the need for

improved NDE to provide in-situ embrittlement evaluation to verify that the

containment material is behaving in a non brittle manner as stipulated in

Criterion 51. Based on the results of the review, research is needed to

improve traditional NDE and dsvjlop new NDE techniques for management of

aging in the following areas: a

1. Effective means to determine fracture toughness and strength, and material embrittlement, including embrittlement induced by irradiation,

hydrogen, and thermal changes. For example, embrittlement appears as a

problem in nine out of eleven priority rankings (NRC 1987b) for PWR components shown in the priority rankings of NPAR degradation mechanisms.

2. Assessment of magnetic methods for material properties measurements to

detect aging degradation of NPP steel materials should be encouraged and

continued. Magnetic methods (Jiles 1988) may provide the techniques and

have advantages over other NDE for in-situ evaluations especially as

applied to the prediction of fatigue or creep damage.

3. Assessment of the use of acoustic emission (AE) for evaluating the

continued serviceability of materials should be encouraged. AE is a

unique tool that should have capabilities in environmental hardening,

toughness, fatigue, and yield strength (Spanner 1979; Spanner 1985; Dal

Re 1986).

4. Additional improvements are needed for the evaluation of stress corrosion cracking and intergranular attack on the outside diameter and

inside diameter of steam generator tubes. Current technology has problems in this area; in most cases, cracks in the U bends or tube sheet

area cannot be detected until they are through-wall. NDE technology

improvements are also needed in vessel evaluation. Current methods

cannot, with proven accuracy, detect shallow flaws of most interest in

vessel fracture evaluations.

5. Studies are needed to determine NDE time intervals for inspection and

the amount (coverage) of inspection needed to manage the aging process.

(ASME Risk-Based and Reliability studies should provide a probabilitic

basis for optimizing the level of NDE, as well as the intervals.)

(a) This observation supports the need for the current work in NDE to

improve existing techniques and develop new ones.

6.2
WATER CHEMISTRY CONTROL

Water chemistry control is an important aging factor in the operation of

LWRs, including steam generator tube corrosion in PWRs. Although considerable work on this factor has been conducted, especially in the 1970s, more

research may be required before existing guidelines and/or instruments can be

revised. As noted in the review, Appendix I1I, page 111.17, item 125,

control of primary side water chemistry is technically controlled by the TSs.

The comments of item 125 (Column 9) note that secondary side water chemistry

is administratively controlled and not controlled by the TSs. The comments

indicate that improvements should be made in the management of the SG's

secondary water side chemistry.

EMPHASIS ON THE ASME CODE

The ASME BPVC Code is a principal instrument used in the design and construction of LWRs and it provides significant guidance and insight into the

management of aging. The code is a living document with ongoing revisions,

and many of the aging issues noted in this review are currently being

addressed by ASME code committees and special working groups, e.g., the

current PVRC Section III/XI committee, is addressing code limitations

including PLEX. However, special emphasis needs to be placed in the

following areas:

1. Code revisions are needed that more vigorously address material and/or

component deterioration as functional criteria of the design.

2. The Code's emphasis on plant design requirements that allow for component

ISI, repairs and replacements should continue. Improvements in the code

that prescribe alternate or better design methods for ISI, repairs and

replacements should be encouraged.

3. It has been estimated that a change in the Code takes about eight to ten

years to fully implement. When appropriate, shorter time intervals are

needed for implementing changes in the Code. The time cycle for specific

items that did not appear in earlier codes needs to be shortened. (In some

instances the time cycle has been shorten; it can be done. For example a

new subsection for Section XI, [WT on erosion and corrosion, was approved by

ASME's Main Committee within a three year time frame and in two years after

ASME's Council on Codes and Standards gave the go-ahead. An additional

problem, however, exists after the ASME involvement and that is the

implementation through 10 CFR 50, 50.55a Codes and Standards. Thus, a

change in code can also be coupled with the implementation delays. ASME

Code Case(s) procedures and the RGs that identify acceptable cases certainly

help the overall picture, but they are not the total answer.)

6.3
7.0 REFERENCES

U.S. Nuclear Regulatory Commission (NRC). 1987a. Nuclear Plant Aging

Research (NPAR) Program Plan. NUREG-1144, Rev. 1., Washington, D.C.

U.S. Nuclear Regulatory Commission (NRC). 1987b. Residual Life Assessment

of Major Light Water Reactor Components--Overview. NUREG/CR-4731, Vol. 1

EGG-2469, eds., V. N. Shah and P. E. MacDonald, Idaho National Engineering

Laboratory, Idaho Falls, Idaho.

U.S. Nuclear Regulatory Commission (NRC). 1982. Resolution of the Reactor

(Task A-li) Vessel Materials Toughness Safety Issues. NUREG-00744,

Washington, D.C.

U.S. Nuclear Regulatory Commission (NRC). 1979. Potential for Low Fracture

Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant

Pump Supports. NUREG-0577, Washington, D.C.

Jiles, D. C. 1988. Review of Magnetic Methods for Nondestructive Evaluation.

Center for Nondestructive Evaluation, Iowa State University, Ames, Iowa.

U.S. Nuclear Regulatory Commission (NRC). 1986. Status of Maintenance in

the U.S. Nuclear Power Industry - 1985. NUREG-1212, Vol. 2, Washington, D.C.

Spanner, J. C., Sr. 1979. Acoustic Emission - Some Examples of Increasing

Industrial Maturity. American Society for Testing and Materials,

Philadelphia, Pennsylvania.

Spanner, J. C., Sr. 1985. Acoustic Emission. Pressure Vessel and Piping

Technologv 1985 - A Decade of Progress. American Society of Mechanical

Engineers, New York, New York.

Dal Re, V. January-March 1986. Fracture Toughness Measurement of a NiCrMo

Steel by Acoustic Emission. Journal of Acoustic Emission, Vol. 5, No. 1,

pp. 39-44. Acoustic Emission Group, University of California at Los Angeles,

Los Angeles, California.

7.1
APPENDIX I

GLOSSARY AGING ISSUES
APPENDIX I

GLOSSARY OF AGING ISSUES

corrosion - Corrosion is an aging issue that applies to all components in

varying degrees and is manifested in different ways. Corrosion in the broad

sense is the deterioration of material surfaces, chiefly, through electrochemical reactions and is influenced by the environment of the material or

component, e.g., high humidity. A familiar example is the rusting of iron.

Corrosion is also linked to other aging issues by causing an acceleration of

the degradation, e.g., stress corrosion cracking, irradiated assisted

corrosion cracking, corrosion fatigue, and corrosion/erosion.

corrosion/erosion - Corrosion/erosion occurs when the eroding fluid (liquid

or gas) or particulate matter is in the presence of or contains corrosion

causing products, i.e., the corrosion reaction is accelerated by the relative

movement of the corrosive fluid and the metal surface. This mechanism

involves the effects of mechanical wear or abrasion. Characteristics of

corrosion/erosion are the appearance of grooves, gullies, waves, round holes

and valleys on the surface of the component. An example of corrosion/erosion

is tube wall thinning caused by impingement of water droplets containing

suspended solids.

crack formation and flaw growth - Material crack formation and fatigue growth

of flaws are indicators of material degradation and possible failure by

through-wall cracks. A crack is a discontinuity at a particular location in

a material as a result of localized excessive elastic/plastic deformation. A

crack will propagate as long as the tensile stress acting on the component

supplies sufficient energy to sustain a new crack surface (this aging issue

is related fatigue and SCC, i.e, without a driver a crack will not grow).

Present methods of flaw and crack detection are not 100% effective and

improvements are needed for evaluation of crack initiation and growth. The

issue also encompasses human factors of NDE staff, e.g., training.

creep/swelling - Creep is defined as the progressive deformation of a

material at constant stress. Creep failure (fracture) or stress rupture

exhibits the influence of relative high temperatures on long-time loadbearing characteristics. The creep temperature is often expressed as a

homologous temperature, i.e., the ratio of the operating temperature T to the

absolute melting temperature Tm (K). Creep of load carrying components

becomes of importance at a homologous temperature greater than a ratio of

0.50. Load carrying components operating in the temperature range of 5380C

to 8700C (10000F to 16000F) are susceptible to creep. Generally, creep is

not a major problem in LWRs because of their temperature operating levels.

These levels at around 550¶F are below the creep range for ASME Code

materials specified in ASME BPVC, Section III. This aging mechanism, however, is of interest to the NPAR program because of its impact on electrical

components/systems. An increase in the dimensions of components (e.g., fuel

elements, and fuel cladding) swelling is caused by the accumulation of

I.1
fission product atoms in the structural lattice of components. The fission

products occupy a larger volume than the original material which caused

swelling.

element burnout(s) - Element burnouts and repair and replacement of heaters

are identified as an aging issue for the pressurizer vessels.

erosion - Erosion is a broad aging issue that is principally associated with

fluid flow in components. High velocity water impingement can erode the

walls of pipe and fittings. By definition pure erosion is the mechanical or

wear action of a fluid and/or particulate matter on the surface of component

parts. Erosion is usually accelerated by the presence of solid particles in

flowing fluid. The possible consequences of typical erosion is the thinning

of a pipe wall to failure.

examination, inspection and maintenance and repair - These activities may be

considered aging issues because the management of aging is affected by these

activities and in some cases aging is accelerated by poor examination, harsh

inspection, and improper maintenance and repair. Also conditions may exist

that do not permit adequate performance of the activities.

excessive/harsh testing - Testing programs and procedures that require excessive testing can lead to accelerated aging, e.g., harsh testing programs

associated with the emergency diesel generators have been identified as

contributors to aging.

fatigue - Fatigue in reactor operations is broadly defined as structural

weakness and loss of resiliency in materials resulting from stressors, e.g.,

vibrations and thermally-induced fatigue cracks. Fatigue is defined as the

phenomenon leading to fracture under repeated or fluctuating stresses having

a maximum value less than the tensile strength of the material. Stress

induced by stratified flow is an example of thermal fatigue. As the name

implies, in stratified flows the cool water flows on the bottom of the pipe

while steam flows on the top. These conditions can cause temperature

differences that can lead to thermal cycling and fatigue of piping systems,

e.g., pressurizer spray line and vessel nozzles.

fracture toughness - Fracture toughness is a material property that relates

to the ability to resist fracture. Fracture toughness is related to the

unique stress intensity level that causes failure in a component (is also

called the critical stress intensity level). Its measure is the stress

intensity factor, which incorporates both geometrical terms (the crack length

appears explicitly, while the crack tip radius is assumed to be very sharp)

and the stress level. It is an embrittlement aging issue specific to NPPs

because ferritic materials suffer from decrease in fracture toughness as a

result of irradiation. The CFRs specifically provide limits for the RPV

material tests, i.e., initial Charpy tests of material shall be 75 ft-lb

(102J) and throughout the life of the vessel shall not be less than 50 ft-lb

(68J). Additionally, the material RTNDT is limited by the PTS screening

rule.

1.2
intergranular stress corrosion cracking (IGSCC) - IGSCC is a preferential

corrosion at the grain boundaries of a susceptible metal or alloy in the

presence of a chemically aggressive environment, e.g., hot oxygenated water,

and a tensile stress. IGSCC has occurred in austenitic SS in oxidizing

environments such as BWRs. It also has occurred in SG tubes, safe ends, and

type 304 SS piping. The principal concern is that SCC can cause ruptures,

leakages, and plant shutdowns.

irradiation embrittlement - Irradiation embrittlement is defined as a

decrease in fracture toughness due to long-term exposure to nuclear radiation. High neutron fluence levels can cause embrittlement in the RPV

beltline region as well as other reactor internals and core supports. A

reduction in tensile ductility is also caused by the neutron exposure.

low-flux long-time irradiation of vessel, vessel internals and supports -

This aging issue is principally identified for the RPVs and vessel supports.

Long-term flux reduces toughness and initial margins of safety in RPVs.

seismic failure/damage - Aging issues associated with earthquake damage were

considered. Although not a classic aging issue, NPPs are required to evaluate seismic conditions and the consequences of natural phenomena and the

damage that may result from these events. Aging could weaken a component so

that it would not be able to withstand a seismic event.

specific environmental factors, e.g., moisture, oxidation, chemicals, oils,

and dust - Environmental factors can induce aging in many NPP components.

For this review the factors of moisture, chemicals, oils, dust, etc., are

primarily of concern in the operation, testing, and performance of the EDGs.

Because these factors can induce aging, physical location, surroundings,

housekeeping and maintenance are important to EDGs. All these factors or

elements can accelerate many of the aging mechanisms associated with the

operation of diesel engines and their support equipment.

stress corrosion cracking (SCC) - SCC is degradation associated cracking

accelerated by the combined effect of constant tensile stress, corrosion

environments and susceptible microstructures. The stress may be residual in

the material, as from cold working or heat treatment, or it may be externally

applied. The observed crack may be transgranular or intergranular, depending

on the nature of material and the environment. This term is a broader aging

term than IGSCC and has been linked to bolting degradation in many cases as a

principal aging problem, e.g., leaking steam through gaskets can react with

the bolting lubricants and cause SCC.

stud failure - This aging issue is a factor in degradation of closures,

flanges, manways, etc., through the cracking of bolts and studs from stress

corrosion, fatigue, and corrosion.

thermal cycles - Aging issues are aligned with temperature cycles. Thermal

cycling induces stress through thermal gradients/temperature changes.

Thermal cycling induces thermal stress, low-cycle thermal fatigue, and high

cycle fatigue (water temperature fluctuations). Low-cycle fatigue is defined

1.3
as fatigue caused by high stresses and low numbers of cycles. Significant

plastic strains occur during each cycle. Cycle lives are less than 104 to

100. High-cycle fatigue is defined as fatigue caused by low stresses and

high numbers of cycles. Strain cycles are in the elastic range. Cycle lives

are greater than 10 to 100.

thermal aging embrittlement - Thermal embrittlement is defined as a reduction

in the ductility of a susceptible material due to a chemical change

influenced by high temperature for long times. Thermal embrittlement of cast

stainless steel components (pump housing, valve bodies, piping and fittings,

etc.) is possible over periods of many years, resulting in increased critical

flaw sizes. Thermal aging can significantly reduce fracture toughness and

ductility of LWR reactor components materials. The rate of thermal

embrittlement generally increases with increase in temperatures; however,

specific material compositions of various steels are factors in thermal

embrittlement.

thermally induced bending - This aging issue is principally (for this review)

associated with the pressurizer caused by high-and low-cycle thermal loads at

the water-steam interface in the vessel wall. (Thermally induced bending

stresses can be a factor at other locations).

thermally induced mechanical wear - This aging issue is principally (for this

review) associated with the heater failure in pressurizers caused by wearing

and thinning of the heater due to rubbing action with supports because of

thermal growth.

transient thermal and pressure loads - Transient or short thermal loads have

been identified (for this review) as the transients effecting the pressurizer

during heatups, cooldowns, testing, and abnormal events. For example,

transients can occur in a few seconds and cause temperature changes of 55 C

(1006F) in the surge-line nozzle.

tube specific - denting, fretting and crevices - These aging issues are SG

tube specific. Denting results from crevice corrosion of the tube support

plate and tubesheet materials; corrosion of carbon steel support plate and

tubesheet squeezes the tube outside diameter and can result in decrease of

thermal efficiency and cracking in the tube. Crevices provide areas for

localized corrosion due to stagnant solutions in lap joints, holes, welding

surfaces etc. Fretting in SGs results principally from wear action between

the tube and tube supports and antivibration bars.

vibration - Vibration is a broad aging issue that can cause degradation in

many of the components. Vibration by definition is any physical process

which produces cyclic variations or motion. It is an aging issue to the

extent that the vibration may cause failure or damage to a component.

Excessive vibration can damage components by wear and promote material

mechanical fatigue and pipe weld fatigue cracking. Vibration is a dynamic

action and is associated in this review primarily with piping systems and the

EDG. Dynamic loads are caused by response of the component to an oscillating

input, e.g., flowing water or a rotating equipment.

I.4
wear - Wear usually results from the relative motion between two surfaces.

Wear is the removal of discrete particles of material from a solid surface by

the relative motion between that surface and one or more contacting surfaces.

Wear is accelerated by hard and abrasive particles or action of fluids

(erosion), vibration, or corrosive environments. The common result of wear

is the reduction of thickness or damage to the mating surfaces. Wear is of a

concern in rotating machinery, e.g., in pumps and EDGs and the other

equipment/parts, e.g., valves stems and seats, and other mechanism subject to

motion and vibration.

weldments - specific to dissimilar metals of safe ends - Weldments are formed

by the welding together an assembly of pieces such as pipe to nozzles. Safeend weldments have specific problems due to dissimilar metals. Among these

are low-cycle thermal and mechanical fatigue, and IGSCC in the heat affected

zone (HAZ) in the base metal.

I.5
APPENDIX II

REGULATORY INSTRUMENT REVIEW FOR REACTOR PRESSURE VESSEL
Understanding and managing

aging of PWR reactor pressure

vessels

Temrperaturo iF

-4O -200 0 200

l l l l

Mateas Vessel Low alloyabon .t SASS3S-1

SA50W2 &SD3028

Cladding 1rType 30 55 nd 309 SS,

Wuldments Submerged we (grnular Itux -linde

M0 91 124 nd 1092

miller wirel narrow gap submerged

mr. shielded metal arc, and

electrostag Closu studs SA-S40 Or. 924 Clas S

Neutron flux an fluenee, temperaUr, recor coolant, cyclic the rma and mechanical load

preloeds, and borie aeid leakage

cg200

I

Ur 41

Upper shelf

Unirradidetd (ductile Iailure)

Ductile to biittle

transition temperature

Lower shelf

(brittle failure) i sladiated

a0

16

u _ _ _ . _ _. u

-300 -1 0 iSO 300 Stressors

VWd

Environment

Temperature (C)

Effect of Irradiation on the Charpy impact energy for a nuclear

pressure vessel steel. Typical PWR vessel showing Important degredation sites.

UNDERSTANDING AGING MANAGING AGING

(Materials, Stressors, & Environment Interactions)

Sites I Aging Concerns Inservice Inspections, Surveillance, and Monitoring I Mitigation

eit Ine region irredlation embrttflament

* Chemical composition of

Wesse materials (Cu. Ni, P)

* Drop In upper shelf onerg (USE)

* Shift In relerenc nil-ductiflty

trons llntempenrtue (FT )

Environmentai fatigu

i-4

1-4q

NRC Requirements

Survelilance program to heess

irradiation damae, Le., shift In RTOT

and drop In USE (I0 CPR 50 AM H.

Rag. Guide 1.99 Rev. 2)

Pressurized thermal shock PS) screei

crtierb (10 CFR 10.631t

FTS rule, RQ 1.154

Dameg evaluation (10 CFR 50 App. 0)

Pressure -Temperature (M) limIts during

hestup, cooldown, crIticality, and Inservce

leakage and hydrostaic pressure test to

prevent nonductile fracture (lbch. Spec

requimment, 10 CFR SO AMF 0)

P-T limits are also applied to non-i

lbitline egion j

Low temperature overpressurizatlon (LTOP)

prtection setpoint (Tech. Spec. requirement

VolumetrI examination of at we ld

durn sech Inspection interval (10 CPR 50.59,

iW&250M Rag. Gude 1.150, Rev. 1)

Flaw evaluation (tO CVR 5D55a, JOO.3000)

Lakage and hydrostatic pressure tests

(10 CM 50.5sa, IWA-WSOC)

Recommendations

Include fracture toughness end tensile

test specimen In surveillance program

Develop use of reconstituted and

miniture semens

Deveop techniques for In situ

determination of mechanical propetltb

Peorm acceteeked irradiaton tests

of reconstituted specimens

Revise Rbtg. Cuod 1.". Rev. 2 to account

for phosphonrs with kow copper

Use state-of-the-art ultrason inspection

technies for piprod melhlHtyo deec

detection, otzing, and characterization

Automated mplitude-based sye ms Tip diffraction techniques

Lg-diaetr focused tranaducer

Uae fatie crack growth curves

(ASME SC Xl, Appeix A)

Develop acoustic amieslo monitoring to'

detet crack growth (Nonmnar"

appewdix Is being developed for

ASME Sction XI)

Neutron flux reduction

Inservice annealing

(ASTM E 509-86)

Determine efhets of

annealig and ovembi Itlement rate

Oullefiinlet nonlies Evionmenm tat gus Volumetric examination of sit nonzle-to-vessel Use on-line fatiue monitoring

wels and nozzle inside radu sections (monitorIng of pipe wait ltmperatures Irradiation embittlement during each Inspection Interval 1WS-2500) nd coolant fows, temperatures. and

Function of nozzle eevation prs )

Potential impact Of Volumetrc and surface examination of sit Evatuate Irradiation .mbritfltem nt

kRag. Guide 1.119, Rev. 2) dIssimilar metal weids during each inspection damage

IntervralPIWB-2S00)

Instrumentaion nonbles Ernvlrnmentit ltigu Visual examinalon of external weld

CRDM housing nozzles surface of 25% ot nonles during system hydrostatic test IW-2500)

Environmental fatigus Volumetric and surtace examinailon of it

Closure studs -prnied cycles during heed replacement studs and threads in flange stud holes itorc id corrosion if leakage occurs) during each inpect on interval (iW-2500)

rev. S
Understanding and managing

aging of BWR pressure vessels

1aterials

Stresors

and

lEnvronient

Vessel - Low silcy carbon steel

SA.638.t. SA.3020

Cladding Type 3068 S or 5.SS.

Nozzle SA-508-2

Sole Ends wpe 304 SS, Type 316 E5. Inconel S8-166, Inconel 5-16Z7

SA-5061-

Thermal Sleeve.- Type 304 SS

Closure Studs SA-U40 Gr. 822 or 023

Weldenis . SA"193 Or. it

Opereatlnal transients, neutron flux and fluence.

temperature, and isct coolant

tI amer

Typical SWN pressure vessel Cross aection of fedwster nozzle with cracking locatIon

6-1

UNDERSTANDING AGING MANAGING AGING

(Materials, Stressors, and Environmental Interaotions)

Sites Aging Concerns Inservice Inspection, Surveillance, and Monitoring Mitigation

Feedwater nozzle* and HIg.cycl thermal 'Ugw caused NRC Requirements Rscommendmtcon Modify design,

ssle end welds by leedwaler leikage Use on-line fatigue monitoring procedures, and

Environmental fatigue Volumetric examination ofall1 nozzle-to-vessel (moniring of pipe wal tuempertures u r mov edwater welds and nozzle inside radus sections during coolan flows, temperatures, and pressures nozzle cladding to each InspectIon Interval (IWO-2500) Develop criteria or assessing high-cycle prevent batigue _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~~ f tig ue d a m ag e crac ktn g Volumetric and surface examination of all faiudmg cckn

Recirculation Inletoulet 1GSCC crack InItIated In HAZ may propagate dissimilar metal welds during sach inspection Develop on-line corrosion monitoring Implement hydrogen

nozzlee and dbissmilbr Into be metal interval (IWi32600) Evaluste long-term stlects ol hydrogen rwduce IGSCC

metal w eld Environmental t'ue water chemistry damage

Weods IGsCC crack Initiated In HAZ may propagate Visual examination of all accessible Interior Develop robotics system for remote -Control rod drive Into bae metal by corrosion andhor attachment welds during each Inspection Inspection probe positioning and

stub tubes environmental fatigue Interval (PWO-260) scanning

-Interior attachments

eitirne Region Irradiation embrittlement Surveillance program to assess shift In br Revise Rg. Guide 1itS, Rev. 2 to Insrvwce annaling

Chemical composition of vessel meterials and drop In USE (10 CFR li App. H, account or phosphorous when copper (ASTM E t609)

(Cu, Ni P) Reg. Gukde 199, Rev. 2) content le low -Drop In upper shelf energy (USE) Detemnine effects of Shift In reference niI-ductility-transiton- D ie 5vluatUon (10 CFR 50 App. G) Use Itntso-the Inpaction nneling and

tempera tre (Ro) PrssrrT Pressre-teperatre lmit during Improved reliability of rembrittlement rats (PT) liits dring defect detection, sizing,an AWe ae me susceptible than be heatup, cooldown. criticallty. and Inservice characterization mplement neutron

meta leakage and hydrostatic pressure tests to lux reduction

Flux is lower then that In PWR vessel prevent nonductile fracture (Tech. spec. Develop robotics system for remote pgrem

requlrment, 10 CFR 50 App. M) Inspection probe positioning and

Environmental fatigue [P-T limits are also applied to non- batllne canning

region] Include fracture toughness nd btensle

Volumetric examination of all se11 welds during tedt*pecim In urvillanc pmgr m

each Inspection Interval (10 CFR sSUe, Develop use of reconstituted and

IWS-2500. Reg. Guide 1,150, Rev. 1) miniature specimens and accelerated

Flow evsksetion (10 CFR 60.55a, IWB-3000) Irradiation of recondtitued specimen

Use fatigue crack growth curves (ASME

Leakage and hydrostatic pressure tests (10 CFR Section Xi, Appendix A)

5O55a, IWA 4000, IWO-5000)

Develop acoustIc emission monitoring to

detec crack growth (nonmandatory

appendix Is being developed by ASME

Section XI)

Closure Studs Fatigue, tting Volumetric and surface examination of al studs

and threads In flange stud holes during each InspectIon Interval tIWO-2500)

External attachment Lowcyce th rmnat and mechanical fatigue Volumetric or surface examination (IWI-2500) welds such as skirt

supports

MV. 4 ml*
REGULATORY INSTRUMENT REVIEW FOR REACTOR PRESSURE VESSEL

(1)

EXAMINATION, IiiSPECTION fAND StIML.-

LAN"U (115)

REG. INSTRUIENT

DDLUMN 3

10 CFR 50 Appe.

A Criterion 32

AGING fEATURES

The RPv should be de- signed to permit inspections.

LIFE EXTENSION

FEATURES

COLmUM S

NM

CURREtlT INITIATIVES

CCLLUNI 6

AFPropriate megures are being defined for plunts where

inspections are

difficult.

AGIG NtEEDS

COUItI 7

t/A. Design donn t

ehaws over time.

(2) 10 CFR 50, All Inspection proer

Apx. C (111) as per the ASHE eode.

(3) 10 CfO S0 Surveillance mVor InservIco axaineation or fracture toud-nese

NM Evayulte effects of age

an the material proper- tien used in the calculations (see epbrit- tlment Issue).

Appm. C (V5.

C.

10 CFN 50,

AP.N H

Alternate criteria inwiving ISI per ASE Section Xl

LIFE ExTENSION NEEDS

CO~teqe 8

RPVs need to be consid- ered for aeceptability

if crItical ares afre

not eityy inepected.

Inspections My need to use different procedures

aimed at detecting

eging/degradetion for

tife evalustion includ- ing irradiation and fatIgue failure mdes.

Are r_ operating limits ad Ine etion frequn- cies need for life exteneion? Inspection criteria for irradiation

and fatigue failure

mdes myb ned

Asument of the withdrewet scheckte and rsaier of saotes my be

ed. Copsutes my

need to be reinserted or

pre-irrediated caeutes my roed to be inserted. Anesteling effects need

iwestioation.

The unr eiability of

dcetectlor iolng ft a

because of clading effects should be ad- dressed. Ntam factor

effects of lDE staff should also be addressed.

Assesx t of acceter- ated Irrediation effects.

ceExTS

COLtM 9

The pressure boissary should be designed to permit

inspections and qropzria meterlal surveillance progrum for the RsV p, e ging related criteria my red to be written and referenced by this criterion. Currently the plants are required to apply criterion

32 or mee a best effort to inspeet the RPV.

Should reflect life xtsensIon decislons ad aging research. Evidence for aging of RPV hardare includes erosive degradetion of thimble tubes. A need

axists for a new ben tine esxainetion.

10 CFR SO Appm C (IV) requirnts at be satisfied prior to life axtension. squirmnts for operation

is 10 CFx S0 Appx. C (IV) is not satisfied: Beitline ftls exmined as per ASME Section XI. Work Is needed to include life extension decisions ard aging research. Inspection examptione will neod to be reconsidered for life extension.

no _ternat lturveillence progree Is required for SPt for thith It cen be deinstrated the peak

neutron flusnt.,7t the ead of the design life witl

rot exced 10 nlem (E >1 May). The capeule

progre should be as per ASTN E-IOS. Capsule otcationa ad wlthdrmeet schedutes are reguired. Madifl- cations to ASTl E-I1S for cpule withdr-wal *cho

for ne fuel management progrm are in progress.

Similar designed ad operated reactors my use Integrated ourvailtareo progr.

Current ftlt detection system are not 100% effec- tive. Detection syst should be ibproved.

Accessibility to SWR PRvs is a problem; remote sctnnrs are ne dd.

Extand ticense If sufficient margins exist.

.-

CA)

(O) Copeule survey proFem. xron to exist. Assessment of the with- drool schedute and ruber of sampLes my be neded. Alternate test- ing methods (i.e. minisaples) should be

coamiddred.

(S) Tech Spec 4.0.5 O S erences ANNE Section

Xl .

FetIr. Adeences In ailable

tDE technology are nedd to detect sohattw

floes of t interest in vessel fracture

evaluations.

(6) Tech Spec 4.4.9.1.2 Capsule Suvey Program urveitlenea of

WV tranient

temperatures

Testing ampte freqiun

cy. Alternate testing methods lie. minisamles) should be

considered.

General NotesI

I. A I" ldicete furthed Ntudy/Iieetl tlla to _bd. es 

2. For the Nis, xrXsotwet mum the enle safety leae is roolved, not necessarily the egirs lsen.

3. For miseng Of aberevletirm, ecrornE and Initlilaio, used throghoAt, o ecronym on peg xi, Xill and xNiM of the report.

-- Reactor Pressure VesseL
Cta tlNt ISStE BEG. INSTALMENT AGING FEATAES

(XLttt I SP CtctdUM 3..u.. 3 4

(7) EIS tctd) SttP 3.9.2.1.4 tlOttE

LIFE EENSIWI

FEATURES

US

aLRyT INITIATIVES tCOLUM 6

NOME

AGING NEEDS M UItA t7

5A

LIFE EXTEtSICtt MEES tCOL:W~tt

Should the SAP edtress life ectension?

(a)

(9)

SAP Inservice Inepectian code USNE

5.2.1.2.11.2 C"s ard EG mW icabi lity.

SWP 5.2.4.11.4 In service inspection USME Intervals.

mm

mm

Need to verity that the USE

reference code cases

cover an adeqate tie

spn for reactor opra- tin.

COMENTS

CU1LS~a 9

Testing during pre-poeratioa and stanhup test prroar ThIts aection diee not aply aft r the start

of plant operatiorn.

Acceptable code cases for insarvice irnpectiin are found in Bag. ulde 1.147. Cods cans t at be revieSd every three years.

Eequired in ections ant be performd en reactor coolant preasre beuddry components durin each

10-year Interval of service as per ASE Section XI

IWfA-2000. option.. impose inspection plan A.

(10)

(12)

SEP 5.3.1.1.3 aorslsstructive exmin- UOSE tinr CWE)

SRP 5.3.1.1.6 surveillaice det, coltec- USE tion over vessnl life- tim.

SEP 5.3.1.11.6 NateriaL Surveillance. WE

SxP 5.3.1.111.6 Flume calculation or USW survel lance.

US

USE

US

See note 1.

US"

t-t

Dotes inpection freqeer- cy need to be Increased

In the test ten vor interval? More exten- sive euaXinations my be

needed.

Asseamnt of the withdral adiaedlh aid nuter of smples my he nded. Atternate teat- ing methods (i.e., minis.ptes) should be considered.

Asessment of the withdreaat schedule mnd nuber of smplee my be

needed. Alternate teat- ing mathade (i.e. mtnisuptes) should be contidered.

Assessment of the with- draIt schedule and

ruber of s*ptes my be ndd. Alternate teet lng method (I.e. WMlisIptes bould h be

conrlidred.

fppropriate reutlatory inotruents xat be

ecdifled for aging. Alternate testing _thod i~e tt i ni-saptes), should be considered. tEvime of cIrOaerenr

tial wslde ad the effects of streiing era

also needed.

Should the SaP adress

tifE extension?

Should the SEP atrese

tIfe extension?

Should the SP ddress

life extenalon?

Should the SRP addes

Life extension?

Should the SiP address life extelson?

Special tethods for tIE other than those in ASHE

should be reviewed.

iPV asuveilelnce mat be performed to monitor chaines in fracture toushneos properties.

No interail surveillence program Is required it 7it

is rown thet the flumee silt be less than 10 nloe, tE * I Nev). If this is not Not, a surveillate proarn is needed as per ASTM EiMS. Irra- diation _ge is a tess severe prdble for kIsn

then for PURs.

End-of-life fluencet mt be Less than the asximas or t ac beas erveillaice per ASTT EtIE.

The SIP provide a sa ary oF the requirements for

fracture toughtess, pressure, taperature, ad

suirtace reuirments s stated In ASlE codes

Vd 10 Cfl 50

Bow life extension docunent that reflects tim pester than forty

years?

(13)

(14) SEP 53S3 ETP Frecture toushiesse

5-2A preeur, toeperature. ad a t c rewUire- mnts.

WM

-- Reector Pressure Vessel
IUPONIENT

(13)

(16)

(1?)

BII$ (contd)

(18)

(19)

(203

(21)

tEC. INSTRIIENT AGING FEATIEn COLtlh 5 aimO 4

RC 1.150 VJT of WV wtids.

R0 1.154 In situ teat for fstiue.

RC 1.4 Trace .lnt efftcts on lectrolag welAd: reIid- uL lsteeats not cam sidered.

NO 1.65 ,Dtju for crOck, tc. in Studs.

RC 1.2 In situ test for fatlgus.

A5 Sc Xi idontifies the rules end 10-2200 rmquiremnts f or Inrpec- t 2310 I tiln responsibiiilles. Iu-2400 accessibility, e iratimo methods, pirOffit

qual ifications frequency and records. Hinim.. bais for slt require- -nts.

CSI 29 Cracking end dsqradstion of bolts end *tuis from stress corrosion,

fatigue, boric acid

corrosion nd erosion corrosion.

LIFE EXTmIiil

ExAiJRES

COLLMte 5

Inervice lntpec- tirn ISl)

iOE

OAREs? IIIITIATIWS

1St

lmll

eSOE

ROSE

Sec Xl under revieu for life extension opplicability

601MGt 56CS

Setter flew detection

syste are d for distributed micro-felws.

ieeds resulatory posttin developwant.

Asees Effects of rssidutt *lnnts.

Revise 1C 1.65

N.eds regulatory position de It .

Atlaeote testing oee*- ode (i.e. minf-asoptes) should be camridered.

osen the inapetion frequemcy or fraction Impacted need to be

incre-ed for extteded life? Do records n.d to be Miinteined and analyzed for trerds of replaced studs ard bolts?

Further wnilysis needed.

LItE SXTElgiS I~i31aS LiV EU10II NED

Ihmn factors of "E should be evxlusted, i.e.. flaw incorrectly sized should be evelded.

seeds regulatory Poi- tion developoant.

Needs regulatory posi- tion developnt.

Revise to 1.65

seeds reiulatory p051- lion dlqnt.

N/A

Further anelysis n d.

Further nawlyse nnd.

CIL" 9

lOE of woids for crock initiation and Growth. kew detection eystin would cotatitute a Mjor it fefort. Is 100l UT required for ONs, to ane urdr clading cracks? Creach my pisto from cladding into steel in the "V.

Applies to pre-totrtup vibration tests. The VA does not coenider fluane effects.

Applies to pre-startup Vibration tests. The NG does not conelder flouece effects.

The doc ont slow for the Mnitoring of studs for _ e with tiem.

Applies to pre-startup vibration tet$. The to doe not ctaulder ftuwt effects.

Applies to the prie retainint c an only. The only life uteneion application is the detaen, fabrie tion, instellation xnd in ltion of replace- MOnt c wuntS. Specific raquiremit are Found In AxE Set Xi 110-25W0.

Bolting deogrdation or failure In nuclear pewa plants

Priority - HIlt Proposed Imnpedng i10T of bolts eaa outage. xteding on outage 1.5 da. This Isaw is treed than stutds nd bolts for the AV.

LUwalyzed Y tihewet stress during netural ce tion cooldown . Priority -- ID"i

Additionol low toopersture overpressure protection for Lafa * Priority -- "1IN1

Stre corroeion crafting of pressure bounry ferritic steals in selected environnit

Priority -- LOW

C ltsseifled as Licensing Ilesa

'-4'-a

(7,

(22) DO179

OSI 94

astIII

Axilt terature gradi- mE wnts that could cme theel stress in the fleow *re or In the Studs. Cycling over the life of the plant my redxo fetiga _rgin.

eIar overpreesur. of the iNe KS, In coobinatlon with the existaence of flows, could result in a bCrttt1 failure of the RPY.

Stress corrosion cracking mE

NaOE

(2M) further wNalysis needed. Further Analysis neded

(24) ROME Further analysis nd. Further analysis n d.

-- Reactor Pressure Vesel
VOMOULkNT ISSUE

-922I- COL

(25) ElS (contd)

(26)

(27)

REG. INSTRUMENT

GSI A-11

AMI& FEATaRES

COLUi.N 4

As plants accum (ate

Increasing ervice time,

neutron irradiation

redjces the eaterial

fracture tamhess anrd

inital irgine of safety.

LIFE EXTEASION

FCAIIIAES titREAit IiIITIATIOIS

CDLM

A=IAG tiEEDS

CaLmed 7

monitor md analyze

trends of Nilt-Ductitity

temperature

LIFE EXEISMIOK NEEDS

Further analysis needed.

COINIiE9TS

M~oI- a

GSI A-26 ToIughess at low teera- NOE

ture

USt A-R9 iucron irradiation of NONE

the reactor pressure

vessel weld nd plate

mterfals decrage the

fracture toughness of the

eateriats.

Further mialysis needed. Further Analysis needed.

Reactor vee materials toughness

. Priority -- RESOLVED with issunce of IIMEG-07U And Geric Letter A2-66 See A-49 for a related discASion. Ractor Preasure Vessel

Reactor Pressure Vessel Transient

. Priority -- RESOLVED with pbli cation of W1EAs-0224 and WP 5.2 * urous reported presre transients In Pwes share TS pressure ard terature limits were exceeded. iMaority at solid water condition of startup or shutdon arid reLatively tow reactor

temperature. Less toughness at low teeereture,

therefore aore susceptible to brittle fracture.

Preesurited Thermat Shock (PIS)

* uesolution for aging sill be affected by licensee actions that include anrealing and fuet mensesent practices to reduce flue at reactor pressure vessel.

Load, load combinations, stress limits * Priority-- NIGa * see iaEG-28o0 Skpl

Priasry syatm vibratiare

. Priority -- RESOLVED

Monitor And neltyxe

trade of Ail-Suctility

toperature.

Further mnelysis needed.

Further analysis is

ned to daternine what

impact life extension

wilt have on the

brittleness of RPV

materials.

Further Anelysis needed. F-i

P-4 (28) CSI 1-6 Through watt cracks and OiE

fatigue crack growth

UWE

(291 GSI C-l2 Structural damge by

vibrations of sufficient

magnitude, Fretting dum

to deficient design and

material selection for

anti-vibration bars.

Fatigue faiiure, particuterty at nozzles whare

stresses are highest.

Further analysis needed. Further Analysis needed.

RPV IRRADIAIIONi EI6iT-

(30) TLEIiET , FRACTURE

TOUIGNESS (IEFT)

(31)

(32)

1D CPR 50. 554 Syste aerd comonent

designs shall eet ASKE

requiremnts.

10 CFR 50.60 Acceptable criteria for

fracture prevention.

tO CFR 50.61 fracture toughness reqiirssents to protect

against PTS

Reference documents need

to reflect aging.

NONE

See note 1.

Sef erence decrmnts need

to reflect aging.

lopedt of aging on

Increased risk for PISrelated event occurrence

neded to be addressed.

Related documents need

to be reviswed for life

extension.

Amw document section my

be needed to address life extension.

P19 needs to be better uiderstood for the pltnt conditions that would exist after life estan- amie.

ASxE reluirmeents at be mat throughout the operating life. ASiE Section Xl it currently urder review

for Li aplicability.

Raferences 10 CFR 50 Appx. arnd A.

Provides fracture toughness requirments for protection against pressurized thereal shock. Celculation

of 5 1DaI for the RPV nrd the overtay clad irrediation r . Renireent may need to be charged to

reflect potential new failure modes caused by irradiation _ge. A need "xita for the improvement

of smaningfut fltw population data aid for identifyIng the influence this data has on probabilistic

fracture Aanlysis.

-- Seactor Pressure Vessel
COPENiT ISSUE

COtLNM I CoLllt

(33) LEFT (contd)

(34)

(35)

RES. INSTRLMENT

CaLUse 3

TO CFR SO0

Apsx. A Criterion 31.

AGIN FEATRES

canL 4

Design Margin apifIcetions.

LIFE EXTENSIOiM

FEATLRES

CaLUn S

NE

aggRENT hIITIAl1VES

HURE

AGING NEEDS

CoatL 7

Are margins quantified

a a function of tepee

we or are they bsad

only on initial design?

Erhanced IDE of vessel

my be needed.

Inapection scope my

need to be tereased.

10 CFR 50, Fracture touaass repx. G quCiraents for ferritic

steets referenced to ASIE

Section III codes.

10 CFR 50, Fracture toughness reAppx. C (1ii) quirmesnts as per the

ASHE codas. Altl Irepctien progr_ es per the

ASME coed.

NM1 INE

WK HUE

LIFE EXTEeSIU SEEDS

Evaluation of APIE

Section Xl AWNp. A for

argin fior exturded

duty, ctrsarison to

refurbien activities

such as usetirg.

Effact of ursewti on

fracture toughess and

crack tip geatries

(aice- _ge adification by diftfsional

eachani_ during e

neating).

Inspection my need to

uce different procetures

aimed at detecting

egir/deeradetion for

life extension including

irradiation and fatigue

fai Lure ads.

Need to determine affacts of anne ting.

Are new operatiq Limits

ad Inspection frequrn

cies needed for life

extension? Inmpection

criteria for Irradiation

ad fatigut failure

modes my he needd

Ansesmamt of the withdrenk schedule ad

mur of sptles ay be

d. Amneling effects need investigetion.

The pressure boundary should he designed with suffictiet margin to prevent brittle fracture and rapid

propagationf fractures, The design reflects water- ial propertiesa effects of Irradietion, the size of flu, and the stresses that ar experienced. This

section doee not pply efter the start of plait

operations.

Should reflect life extenscon decision and aging research. uss the fluts of ASME Section Xl.

Appandix A.

Should reflect ELfe extension decisions and aging research. Evideae for aging of RAf hardiare in- ctudes erosive dweration of thidute tuies.

COEtS

CaLnM 9

(36)

_-

1-4

tO CFR 50 Fracture tougmess reApes. C (IV) quirannts.

tO CFR So, Inservice examination

Appx. C (V) (B) requirenits.

NE HUNE Review of frequancy of

assessments of RPV K location on tquprseeli

ad upperehelf tossiess reduct ion.

Evaluate effects of age on the materials proper- ties used In the catcu- Eations.

(37) xolE HURE

Includes Chxrpr upper ef energy restrictions, and

teaperature Iimitatioas for operations and tests.

AsWus the fl1t of ASE Section Xl, AppfdiX A.

Reuirm ts may need to he chonged to reflect

potential new faiture wodes caned by irradiation

dags, fatigpa, erosion, aet.

10 CFR 5S Alpx 0 (IV) requirments mat be satisfied

prior to life extension. Aequiremants for operation

if 10 CFI 50 Appx. C (IV) Is not satisfied: letttine

nlms examined as per ASXE Section XI; evidence of

fracture toughness from tests; existence of wfsfcient safety margins. lork is needed to include life

extermion decision and aging research. Inspection

exsmptions sill nred to he reconsidered for life

extension.

No msterial surveillance prop-m is required for

HIPVs for dhdch It ctn be duetrated the peek

neutron flutsnst* te and of the design Life wilt net exceed 10' r_ (E * I Xev). The capeule

progra should he ma per ASTT E-t85. Capsule tocatios and withdrewal dhuedules are required. lodificatitrs to ASIM E-185 for capsule withtdral ach_

for new fult _asamaut progra are in progress.

Similar designed and operated reactors my use

integrated surveillance progr_.

Trend deta to project when flux raductions are

needed.

(38) IO CFI 50,

Appe. N

Capsule srvey progr'°. N' Assessmnt of the with- drueet schedule ad

iusber of saples my be

needed. Alternate testIng amh' (i.e. minisples) should be

considered.

(39) Tesh Spec P/T Curve Adjustments Acmal Ing, re3/4.4.9 placement

HUE Extand radiation sig Reed to determine the

curve to higher fluer effects of etanling.

ces.

-- Reactor Pressure Vessel
LIFE EXTENSION

COIENT INSLE REt. INSTRUMENT AGliN FEATURES FEATlRES F RRENT INITIAIVES

(40) IEFT (cantd) lat Spec Capsule Survey Progrs Fuel Managent NONE 4.4.9.1.2

(41) SRP 5.3.1.1.1 Material irradiation resistaice. mm

(42) SOP 5.3.1.1.3 Nrdestructive examine- NlOE

tirn.

SUP 5.3.1.1.5 Fracture toughnrss catcu- INOE

ltion. (43)

tE

MAE

NiONE

NaNE

AGleC NEEDS

Testing sapte frequency. Alternate testing _thods (i.e., ainil

Ralpte) shouLd be cormidered.

Need to assess if design

data bases are suffi- cintty coepltet with respect to fLuenc.

Alternate testing meth doa (i.e., sini-samptes) should be csrldered.

Many of the vessels with low uwper-shetf weld prtblt are ring forged vessels. Present crmprtetionat methods are based an axis-syetric

(2-0) aalysis. The effects of streasirg are thought to be poatndtialy sisnificant and this my reqire a 3-D analysis esdot with

appropriate streaming siulatian. CalciuationaL _ethoda are stendard regardless of materiaL.

Record keepins.

Assessment of the with- drwat schedule ad nuaer of smptes my be ned. Alternate test- Ina methods (i.e. minisamples) should be cormidered.

Assessnt of the with- drawel schule and cudr of samples my be needed. Alternate test- inS methods (i.e. minisamples) should be considered.

LIFE EXTENSIOl NEEDS

Acceletatad Irr. f- fact.

Should the SRP addr-ss tife extension?

Should the SRP addrss life extesion?

Minor revision of exist- irg document is nd to reflect the _sease of material property

degradetians. A date ae reference for aged, anneeled materials is neded, or the expected resuLt should be st rdizel.

Should the SRP ddress Life extension?

Should the SRP address life extension?

Should the SAP address life exteriin?

Estend License if sufficient margins exist.

Deasl with the Initial design choice of materiaLs. Adeqpacy for ure of saterisls is to be assessed an the basis of mecricat and physicsl properties, effects of irradiation, corrosion resistaice, and faolitability. This section does not apply after the start of plant operetions.

Spatial mathods for WDE other then those in AWtE should tb reviled.

Fracture toughness tests mat be performed on ltl ferritic tests sptiin. Fracture toughness is characterized by a reference temperature.

RPV surveillance mit be performed to lonitor theses in fracture toughness properties.

No meteriel su-veilasce progres is reqired if 7it is xqlos that the flunce witLt he lee then 10 iv s' It 1kw - If this is not mt. a wsailt- tare prosras is nedd as per ASTh E165.

End-of-tife fltuae mat be les then the mxis or suveillance mat be as per ASTil El8S.

COaTS

COLELe 9

i-4

I-4

;O

(44) SRP 5.3.1.1.6 Data collection over vessel lifetima.

(45) UP 5.3.1.11.6 Materalt Surveillatce. ioE

(46) SRP 5.3.1.111.6 Fiuence calculation or iNOE

surv litane.

* Reactor Presse Vessel
(4?)

ISSUE

CMtW 2

REG. INSTRUEINT

CAtUl 3

SRP BTP-YTEB

5-2 A

AMIS PFEATIRES

tOtliti 4

Fracture toughness

presse. tmeratze*

mnd surveilttace requireWants.

LIFE EXTEESIo"

FEATURES

cl2M S

mg

CIRRET INITIATIVES

CDLUM 6

NON/E

(48) lEFT (centd) EC l1)15 In situ test for fatigue. NE NCIIE

AGING WEEDS

C.tged 7

Appropriate regulatory

instruients mast be

modified for aging.

Alternate testing mothode 1e. mini-saptes)

ohould be conidared.

Needs regulatory poeition develtt.

Need to account for

phosphoroues with low

Copper.

Appropriete development

of ny new starderde.

(49) EC 1.99 Rev. 2 Ftuanee/chesitry factors NtW

for troteitien teeperature shift.

(50) RK 1 XXX (New Identifies the physicaRC - not rum, dosimetry requiraesnts

bared yet) for PW ftuence catcutatimen. E cesdations

are based en eurrent

Indeutry practice ad

state-of -the art dosimetry methods.

ASlE Sae III MT shift

Licensee RTpT

An tyles

ider review for

generat applicabitity.

LIFE EXTESIOII NEEDS

Should the SRP ddress

life aetenImn?

Needs regutatory posotion development.

Irradiation series to

ftunes appropriate for

life extension. Revision

to K foer Bit P/T ctaves.

Assessnt of needo for

any new standards.

N/A

5/A

U/A

COMENTas

CDLUMI 9

Suemary of the requiremnts for fracture toughness,

pressure, teoperature, and seeveiItwnce reeiraents

es etated In ASE aid I0 CFR 50.

Applies to pre-startep vibration tests, The RE does

not consider fluence effects.

Conservative predictim of NOT shift a a function

of fluwnce md alloy centent. May conrtitute a

penalty for VA P/t cur-v rastriction n RPVS. There

Is a revision of ASTT E-900 in progress. Ther is

also a yet unnsdered RK for physics dosimetry.

Irradiatimn effacts mnd fracture toughness informtion for bese metal welds mid clads to high tuerces

needs to be evaluated.

This is a new regulatory guide. Tha mthods aid

assurptions presented In this guide wilt provide en

acceptable approach for determining pressure vessel

dage (t1 Nev) fltuences for irput to the RTPTS

prescriptin given in 10 CFR 50.61.

The code is baed en fossil fuel experience and does

not Include fLuernce-ceusd problt_. This section

does not apply after the start of plant operations.

This appendix is non-maidetory. Conteins procaderes

for obtaining attoowbte loadings for ferritic pressure retaining interials. Methods for calculating

critical stress intensity factors, allowable prexurns, ard Rhell ard hend service lisits are given.

monles, flanges and shetl regions are considered.

Service limits and hydrostatic test temperature

limits ar given. Equiremnts mey need to be

changed to reflect potential new failure m

cased by irradiation doge EOT mergins are

being re-evaluated for xFV hydrotest.

This appondix Is nn-mnetory. It centains procadres for sccpting fleos that *xced ItlB-3500

stmards. Includes rules mid equatims for fracture

toughness determination, fatigue crack growth rate

analysis, ad cacutation of irradiation effects en

I for the WV. It also Includes crack growth

re curves. eqirments my ned to be chqnged to

reftect potential new failure modes caused by irradiation _a .

I-4

1-4

1,0

(51)

B -2160 YB-2331

RB-3124

ASME Sac Ill

Appx. G-2000 (52)

(53)

Protection against ncdictite vesset failure.

Ns, except for Section uider review l/A

original design for tife extension

considerations, applicability.

IM Section under review U/A

for life extesImon

applicability

Ke Section widr review N/A

for life extension

applicability, There

is a yet urnanered

EQ for physics

dosimetry thet wilt

reate to this

*action

ASXE SaC XI Analysis methods for

Appx A. fracture toughness ard

irradiation effects.

-- Eeactor Pressure Vessel
LIFE EXTIJSIOS COMPNIENT ISSE AEC. INSTRUMENIT ACING FEATUES FUATUES CIRENT INITIATIVES COf L I COULE 2 cc ILL3 COaLU 4 cILUL 5 ODLM 6

(54) IEFT (contd) AVE Sec XI Fracture toughness crite- NONE SectIon undor review Apps. C ri. See comments. for tlfe extensien

sapliceablity.

ACING NEEDS

A need *Aists to ce- Aldar ny special requireints for fltw in

circumferential welds.

LIFE EXTENSIS0 NEEDS

COLNA

W/A

(55)

(56)

(sr)

CSI 94 maJor overpresoure of the ll CS, If cosbinod with crItical size crack, could result In e brittle failure of the reactor vessel.

CSt A-Il As pLtnts accusaote more NWM erd more service Liam, neutron irradiation radxceo the aternad fracture toughness ard InItial eurgins of

safety.

CSI A-26 Toughness ot low twper.- NOsE ture

UISI A-49 Neutron irradiation of IONE the reactor presoure vessel weld and plate seterials decreses. fracture touwhnes of

materials

CSI 1-6 Through well crecke mad NONE fatigue crack growth

NOiE

NOE

NONE

NONE

Further enelysis needed. Further analysls needed.

Further analyosi needed. Further arilysis needed.

Further analysls needed. Further aralysis nmaded

Further anelysis needed. Further xnayefs needed.

Further mielysos needed. Further analysis needed.

caTS

This appendix is non- _tory. Fracture toughiess criteria for protection agaeint feilure. For ex- e. e, AT asrgins re beinq re-evelueted for SPV hydrotest. Pr*cedres for obtaining alloweble Load- ings for forritic pressure retaining moteriels. Calculation of stress internsity factors. Allowable pressure aq~etions that cmn elso be used for noz- zles, flanges And ohelt regien. Service limits and hydrostatic test taperature raquiremnts spetifled. Solting reqirtments to prevant feilure.

Additionat tow teerature overpressure protection for WAS5

- Priority -- MIEN

Reactor vessel esteniels toushness * Priority -- RiSOLVED with osatICe of Mii-C0744 and Caener Letter U-66

See A-49 for a reletated discussion.

Reactor Pressure Vessel Traneient

. Priority -- RESOLVED with pelication of UREGC-O224 and SRP 5.2

N umnerous reported pressure trenmients In PMM ihere TS pressure aid teepersture limits were exceeded. iejority et olid mater condition of starstp or shutdown and relatively low renctor tapereture. Less toughness at low toagerstur, therefore sre suaceptible to brittle fracture.

Pressurized There.l Shock

For life exteneion analysis for resolution of CSI should address licenses Actions stah as annealing and fuel mtngement.

Loods, toed co btnattons, stress limite . Priority -- NICG

* See MSEG-210 SupI

xeanelysis recedd to determine IF cycle limits can be extd. thermal barrier reseerch needed.

tSP guidee initlal design. This section dxes not Apply after plant startup.

Acceptable code csee for Inservice inspection ere found in Sg. Guide 1.147.

-4

-4

C4 (5M)

(59)

SP`Y

(61)

FATIGC Tech Spec Cytlic loadings. P/T 4.4.9.1.2 records.

SAP 3.9.1 Transient Inac ed

fatgue. Perform fatigue analysis In design stage.

SRP Inservice inspection code 5.2.1.2.11.2 cawe And SC applicability.

Analysso, therm

barriers.

mOmI

NONE Actuel loading antysis. Evaluete cycle limits.

alOE 5/A Should the SOP addres

Life extension?

(6?) xrJIE Adequate tcle for the NMIE

Le of code cases.. Code

cases expire or sre

reviowed every three

years.

-- Reactor Pressure Vesoe*
LIFE ESTENSION

oMtSET ISSUE tES. INSYTRiEST AGISG FEAWUkES FEArtRES

COLUMN 1 C= 2 COLUMN 3 CriOHN 4 COLMNl

(63) KG 1.2 In situ test for fatis. mm1

CuLRRet INITIATIVES

NOLUMN 6

OfNE

ROE

AGINlG IIEEDS ~ifXll 7

teed regulatory pooltion development.

ieede revision; no

anforctmnt capebilIty.

(64) SC 1.48 Prediction of cycles.

(65) Fatigue tcontd) ASKE Sec IlI Thm t and pesotre r exscept for

i2 3000 cyycle. Cesign ard anaty- original design.

101-3222.4 Big.

Section uner review N/A for lIfe extensein

applicability.

LIFE EtSUrK b HEEDS

Needs regulatory posttlion dewtopment.

Doctsantation of the

sctuel service history

N/A

Further analysis needed.

Further analysis ndd.

Ctrn 0TS

M-tz 9

(66)

(67)

GSI 29

GSI 79

GSI 94

Cracking and degradetion

of bolts *nd studs from

stress corrosion,

fatigue, ad boric acid

corrosion.

Axica teperalture gradi

ants that could came

thterat stress in the

fling ares or In the

stul. Cycling over the

life of the plant my

reduo fetigte magin or

usace factor

Major overpressure of the

tCS. If cobirmd with

critical size crack,

could result in a brittle

tfalure of the reactor

vessel.

WME WOIE Doen the Inpetion

frequency or fraction Inspected need to be Increesed for extAded

life.

Further analysis nede.

t-'-_4

1.-s

(68)

OE

tOE

itC

NO

fpplien to pre-starto vibration tets. The SC does

not consider fluence effcts.

Design los we not the _ As ctutal. Need to

accotait A, NS C, D, teds throu Iut lif*.

Plants no spersting need to start castIng mid

doctnting the cyclic history of each plant so

coeprlsons cn be Made to asemed design cycles

following the design code. This section does not

apply after the start of plant operetiaie.

Bolting degradation or falttew in raicter poeer

plants Priority HIGH

. Proposed inspecting ID0 of bolts each outage,

xteldineg an outsee 1.5 days.

Unatalyzed reactor vesslt thermat stress during

nettre tconvection sooldon

. Priority -- tEDtll

Reactor Pressure Vessel Trawient

. Priority -- NESLVED with putbication of

tUREC-t0224 aid SRP 5.2

Starous reported presslee traleinta In Pus

there TS pressure and tempereture limits were

exceeded. Majority at solid water condition of

startup or asutdam and relatively otw reactor

teeperature. Less teteseos at tol teraturee

therefore more susceptibe to brittle fracture.

Preseurised Thermal Shock

Loads, load cabinations, stress limits

* Priority .- NIGH

. See 056-28"0 StP

Primary systes vibrations

. Priority -- RtESLVED

(70)

(71)

(72)

US) A-49 Neutron Irradiation of

the reactor prsssure

vessel Held and plate

Materials decresss the

fracture tourghnes of the

materials.

GSI 8-6 Throth mtal cracks and

fatigue crack growth

GSI C-12 Structural dags by

vibrations of sufficient

asgnittud. Fretting dug

to deficient design mid

moteriat selaction for

anti-vibration bars.

Fatigue fallture perticu

larly at the nozzle thore

stresses are highest.

Aurther melysie de. Further analysis needed.

Further antysis needed. Further analysis need.

further analysis nded. further mrulysis neXd

NE Further anatysis neebde. Further lysis needd.

iector h Prassure Vessel
COMPONENT

COLUMN I

RW)

,73)

LIfE EXTENSION

ISSUE RE. INSTRU1IEXT AGING FEA1URES FEATURES CURRENT INITIATIVES

COLUhH 2 COLUN S COLPN 4 COLAIN S COLUMX 6

LW FLUX, LONG TIXE

IRRADIATION OF

VESSEL AIID EXTERNAL

SUPPORTS

AfIlG HEEDS

tOUlsa 7

Tlme-taperature effects not uiderstood.

LIFE EXTENSIO NEEWS

unklunn at this time.

COME N TS

COLUNN 9

There are ACRS letters Identifying the issue. The

NIC is beginning to research the issue. there is

evidence of larger RT shifts In NiU PRVs then

previously espected. is not yet knoin wether tow

flux conditions re significant contribjutins to the

shifts.

(74)

175)

(Not used)

GSi A-11 As plants acciumlat owe JK)E

and mor service tIme,

neutron Irradiation

redcwes the material

fracture toughness and

initial margins of

safety.

tSI A-26 Toushns at low tempers- CE

turt

NOXE Further analysIs neded. Further analysIs needed.

(76) Further Analysis needed.

tI-I

PO. (77) CSI A-49 Neutron irradatIon of NONE

the reactor pressure

vessel weld and plsts

saterlals decreases the

fracture toughness of the

materlals.

Tech Spec 4 0.5 References ASNE Section Repalr.

Xi.

NE Further analysis needad. Further analysis neaded.

Re ctor wast materials toughness * Priority -- RESOLVED with Issuance of HRJEE-0744

nd Generic Letter tt2-66 * See A-49 for a related discussion.

P5V transIents

Priority -- RESOLVED with pblilcetion of NRaES- 0224 and SRP 5.2 Numerous reported pressure transients In PWRs shere TS pressure and tesperature limits sere

exceeded. Majority at slid water cordition of

startup or shutdosn end relativaly low reactor tesperature. Less toughness at tow teoperatureso therefore ore susceptible to brittle fracture.

Pressurized Thereat Shock

Current ftlw detection system are not 100S effec- tive. Dtection sysot my need to be Ilproved.

Bolt torque data may be collected mnd stress cycle analysIs performed to justify life estermlon.

Environrentat conditlons nust be controlled aurlng fabrication of auutenittc stainless steets to reduce

the possibility of senaitizatlon and aicrofissuring. This section doss not eppty after the start of plant

operations.

RW CRACK INITIATION,

178) STUD FAILaE, FLAW

PRCPA5AhIWO (CISF)

NONE Ruin factors of NOE

should be evaluated;

missed ttl_ or Incorrectly sized should be

avoided. Inspection

criteria for nrw, irrediation lnduced fallure mds that my occur

may be needed.

Docueitation for data

eualysis needed in lieu

of a replaceaent policy.

Shoutd the SRP ddress

life extenslon?

(79) Tech Spec

3/4.4. 10

SPP 4.5.2.

Ill. 4

Refererces ASE Section

Xi .

Envi rouwital control

Dats retentlon. Replacent.

NE

NONE Ftuane effects not

fully decumnted.

N/A; Eieted to fabrication

(A0) NE

-- Reactor Pressure Vessel
COMPONENT ISSUE RE. INSTRAIENT

COALM I cOLR AOLW 2 3

(t1) CISF (contd) SRP

5.2.1.2. 11.2

LIFE EXTENSIOl

AGIND FEATLUES FEATURES

CLUs. 4 aCtiL S

Inservice inspection code E

cse and RN appticability.

CRRENT INITIATIVES

COLUIN 6

IOIE

AGINC NEEDS

CaLsa 7

Need to verify that the

reference code cases

cover an adequate time

span for reactor operation.

LIFE EXTEHSIOWI NEEDS OJUENTS La^tet o COtgi 9

mi HRC accepted code cases for ISI are found in

ED 1.14?

(82)

(83)

(BK)

(c5)

SRP 5.3.1.1.3 Nondestructive exmins- NMOE

tions

AC 1.150 UT of RPV aide. . Monitoring Better flaw detection

syst ar need d for

distributed micro-,flotw

RC 1.65 SE/UT for crack, etc. in studs.

ASIE Sac III Acceptable fla, and

IIH50DO bercheerking Irdtctitone coverd

ASIE Sec XI Acceptable flea ad ItlA-33DD benchirking Indications ItlA-34W covered.

ISI

AdeouteLy covers

acceptable fts

ad betinrkirg

indications.

Inspection and

annitorine.

"tWE Aevis RN 1.65

Sectio under review A/A

for life extension

applicability.

Section urder review N/A

for life exteneion

applicability.

Should the SRP address

life extension?

IDE human factors methods need evaltution for

clssed ftls or Incorrectty sized flats.

Inspection criteria for

new failure modes my be

needed.

Aevise AC 1.65

N/A

N/A

Further analysis needed.

Further analysie needed.

t-s

CA3

(86)

(87) CSI 29

(88) CSI 79

Cracking and degradation NOE

of bolts and stucd froE

stress corrosion,

fatigue, boric acid

corrosion and rosion

corrosion.

Axial teeperature gradi- NOME

ents that could cane

therml stress in the

flange area or in the

studs. Cycling over the

life of the plant my

redtie fatigue mrgin or

waage factor

major ov rpreSUre of the NONE

ACS, If combined with

critical size crack.

could result in a brittle

failure of the reactor

vessel.

Stress corroesion cracking NMl

AWE

AWNE

Does the inepection

frequency or fraction

inspected need to be increased for ctended

life?

Further analysis needed.

Special mthods for SOE other than those in ASIE

should be reviewed.

SDE of aleds for crack initiation ad growth.

ISI of studs for dage with tim. Updating of

RC 1.65 is recomended.

Ftsw detected and benchmarked in Section Itt, and

xonitored and repaired by Section XI rules. This

section does not apply after the start of plant

cperat Ions.

Research or code work needed on the safety and risk

ieprovesent of imspaction mthods and tim periodc

ihen the original design period is exceeded. Acceptable methods of establishing such guidelines and

practices are needed.

koting degradation or failure In nuctear poater

plants

Priority - HIGH

Proposed inspecting 10X of bolts each outage,

cxterding an outage 1.5 days.

inanatyzed reactor vessel thermt stress during

naturat convection cootdoen

* Priority -- NEDIiM

Additional low temperature overpracstre protection

for ti~e

* Priority *- HAIH

Stresa corrosion cracking of pressure boundary

ferritic *te ts in selected environeents

. Priority -. LW C Lssified as Licensing Issue

(89) CS1 94 Further analysis needed. Further enalysis needed.

Further analysi neded. urther analysis ned. (90) GSI III

-- Reactor Pressure Vessel
CCOWENT ISSUE RECG. IUSTEiUET MISh FEATURES

CotW I 1A L Z COup 3 COaLIs 4

(91) CISF (contd) CSI S-6 Through iall cracks mnd

fatigue crack grost

(92) CSI CU12 Structural dae by

vibrations of sufficient magnitude. Fretting dos to deficient design and material selection for

sntl-vibration bars. Fatillgu fiture particularty at the nozzle dhire

stresses are highest.

LIFE EXtlESIOwi

fATORES CUxREI lllIAlIltS AGING SEEU LIFP EXTENSION SEEDS CrOENTS

COUM S . . CN 6 COttsl 7 CLtoM a COLUs 9

leON NW Further analysis ned. Further analysis ned. Loede laod combinatior, $tsesx limits

* Priority - RIGII * see 1,11110-2800 QquI'-

- NNE Further analysis nedsd. Further anaLysis nd d. Primary aystem vibrations

* Priority -- RESOVED

RPV

(93)

(94)

(95)

CORROSIOt

Tech Spec Cheistry control

3/4.4.7

SRP 4.5.2.1.2 NIOE

SVA

NW

mm

aNE

P-i

P-4

4-i

(96) SRP 4.5.2.11.4 fitE NM

(97) Sx.°

5.2.1.2.i4.2

SFP 5.2.4.11.4

Inservice inspection code NW case sad RC ayplicability

In service Inspction Nt Interva ls

ae

flit

l/A

Update/oxtify the ap- propriate regulatory Inetruoents.

Determine the aeqacy

of the three year timt Interval for code case

ae related to ISI. Don inspection interval

period need to be de- cressed in the Lest ten

year Interval?

seed ssesmnt of

chdges in the proper- ties aI the corrogive

environment as a turc

tion of tim_/fluence.

'N/A

(95)

lI/A

sew life extension docuxsnt needed beyond

40 years

Should the WSP address Life extension?

sE

Sow life extension decuxent that reflecte

tim greater than forty

ye rs?

New life extension guidonce neded bayed

40 wars.

New life extension guidence ned bayend

40 yars.

ie. life estension

docutent ned

This may be minor Issue In RPvs. There Is no evi- denc of internal prbem. Leaks frm external

ources hev caused corroding on the externat ar- face.

Adequte prograt exist for aCs chaistry control.

Pracese controls are needed during mswfacture and centructlon In order to lessen the likelihood of

SC. This section does not pply after the start of plant operations.

Acceptance criteria for uestenitic stainLess steels

referenced to SG 1.44 nd 1.31.

S6RC accepted code cas are found in o 1.147.

5e0.ired itnspction an the SPY pressure botxdary aring each 10 year interval of service Is per Sec XI lIA-A20o. Question Ia. .ehould Int4ection Progrn

* he used?

Adeqacy for Lao of materials is to he assessed on

the basis of mechanical and physical properties. effects oi irradiation corrosion resistace, old

fsbrictility. This section doe not aeloy after the

start of plant operatins.

The effects of special febricotion processes on stres corrosion characteristics snt he evsluated.

This section dos not apply after the start of plant

operations.

Special methods for Iet other than those in ASI

should he reviwed.

(99)

(100)

(101)

SRP 5.31.1 1 1 aterlul corrosion rosle NOe

tance.

SRP 5.3.1.1.2 fliE flNE

SRP 5.3.1.1.3 oroaestritive e demina- hto

tlone

ae

ae

NO"

- Reactor Pressire Vessel
CO04OENT ISSUE afa. iastTW AGING FEATLI*S

COLLWI I M 2 CORIN CaWLW 4

(102) CORMIONi (contd) SeP 5.3.1.1.7 iME

LIFE EXTENSION

NWE

CURRETe INITIATIVES

NWi

"15 No WED

NIA

LiPt "1TENSION W1EDS

COLia A

Now life extension

uidance e beyond 40 yews.

(103)

(1K)

StP 5.3.1.111.2 OaWE X-uE V/A New life extension

ldence needed boVad 40 years.

Now l Ife ektauonso

donce n dId bond 40 yers.

SeP S.3..t111i4 NW P/A

-TI

UiItU 9

A deelgn valtutien of the aetilos propertlie of

the reector vaeee footne is pe fori d to mwnre re st to lCC. This section Oem not apply att r

the Strt of plant oper tian.

Special mosf acturln5 processes wro reviwad for

effects on atnro corrosion cracking. This section

does not apply dfter the twrt of plant speratiorm.

Special processes ued on forritic rd mutnitle

stainless $twl( mat be vet fled to conform to sWpoprI ate controls to avoid contdinnt Ion nd

somititation that can Increase the poseibility of gCC. This section does not apply aft r the start of

plant operations.

Intdd to cover dsigm. cnautruction nd accept- wnc* testing of th pressts retainirs emrnts. The ace should be rtainaed. It does not a&des,

aging or life extenion. This section dose not apply

at r tte St art of plant operations.

Appties to the prwesue retaining coonents only.

The only tif extension sPpication Is the design, fr~Ication, Inatottatlt en inspection of replace-

_ent cwpIuuts. The scope of Inapectiens my nr d to he broaded to covar a*ew that serl not Previousty considered. Alt high stoas. wre yed to be

considered. lSould be expaded to cover vismat exalknution of the m1 exttrior for cotrosion.

(105)

(106)

t-a

L"

ASK Sec III Corresion attowentes am

-A2160 provided. NB-3121

ASKE Sec Xi Identifies the rules Wd

IvA-220D rewiremsnsu for Inspac- ilA-2300 tion respaubilities. IW4A-2400 accessibility examsnetian Mthd petlgo.l

qaltification freqincy nd records. iqinilm bhsis for all requrieonts.

C51 29 Cracking amd degradation of bolts ard studs from

stres corrosion. fatigue, boric acid

c err nd ssion corrosion.

, E section uarr revise NiA

for tlif extension

appliembitity.

Section Xti undr N/A revie for *pplic.-

bIttity

5/A

N/A

(¶07)

(¶05)

(109)

mm lIlE Os the inspection

fraimoy or fraction

inspected need to be

Incraased for extande Mste.

Further siulysis _seded. letting daersdstion or failure in ructeer pflr

plants

Priority - 5IXN Proposd irSPactins 10of bolts sach outa, 4Xtcndtino n outage 1.5 days.

Stres corrosion catckin Of pressure boundary forritic steels In salectad nvironsents

. Priority - LO * Classified as Licenming Issue

Primry str vibratiti

* Priority -- 5sIvE

CSI III Street corrosion trackin MaE NeON Further rnalis wadd. further analysis nd.

esl C-l2 Structural damage by vibratinoa of sufficient magnitude. Fretting 14A

to deficient dssign nd

"eteria selection for

ntl-vfbration bhrs. Fatiaa failtures particutlrty at the nozzle where stresss are high

est.

Further mulysis I .

rctor e- Pressure Vessel
APPENDIX III

REGULATORY INSTRUMENT REVIEW FOR STEAM GENERATOR
Understanding and managing aging of PWR steam generator tubes

Materials

Steam

Generator

Types

Stiresorn

and

Environment

Tubes Incone 6O0 or 090

Tube Sheot SA 508 clad with NCr-F alloy (equivalent to se Is8) Tube Supports SA 285 Or. C Frritic SS 1TVpe 405 or 406

Sleeves Incoml 625 or nickel bonded on outside

surface of Inconef 600 or 6890

Plugs Inconel 600

Recirculating Westinghouse, Combustion Engineering

Once-Through babcock & Wilcox

Reaidual Stres, primary coolant c1emistry (primarily

hydrogen concentratlon), secondary coolenl chemistry (chloride, oxygen. copper, uIfates), phocphete chemistry,

resin leage from condensate poliher, bracish water,

temperature, fnow-Inuce vibratlons, flow-volocitise. Nd

operating transIents

Onca-Through steam generator with Indicated prblenm areas

-4

Understanding Aging

(Materials, Stressors, and Managing Aging Environmental Interactions)

Types Sites Aging Concerns Inservice Inspection, Surveillance, and Monitoring Mitigation

Recirculating U-bends, roil trensitlon, and PWSCC (Pure water SCC) NRC Requivements Recommendations Prevent transient conditione In secondary inside dented reaions Tubes with low mill-annealing water chemistry, install titters between

Surface _ temperature are Noe Volumetric examination of hot Follow S1eam Generaor condensate polishera end team

Tube plugs susceptble b sifde, U-bend poltion, and Owners Groups' guidelines tor generators. Use ultrallhratUon of makeup (optionally) cold leg sde of continuous monitoring and water and remedy condenser leakage a Recirculating Hot-leg tubes In tube-to- IGSCC, IGA tubes In recirculating steam control of secondary wat quruleky a po5sible Outside tubeshet crevice region generators (IWI-2500) chemistry Use shotpeening and rotopeening to

Surface introduce compressive residual stresses

Volumetric examination of the Reduce uncerttintie In on tube Inner urface In the roil

*nrtre length of tubing In Inspection results and transition region, aN anneel U-bends to

Cold sludge leg pile a~~de ~ in once-through steam quantity flew growth rates reduce PWSCC Cold log *Id* In *bdg pile or Ptbg generators (IW-2500) where caele containing copper Monitor fild performance of Apply nicefl platng on the Inner surface

deposIts Is found Frequency of Inspection and vnrtou sleeve designs of the tubes to prevent PWSCC crack

number of tubes to be Initiation nd propagation Inspected (minimum of 3% of Perform Inservice inspection Tubes ind e tube ouppt regons oentingtlltu of tube plugs Use tube rolling to eliminate tube he et

Tubes In tube support ntglon* Denting all tutc*) are dittermhed crevices and use crevice flushing, by Toeh. Specs. (Reg. Guide 1.83) crevice alkalinity neutraliatlon, alkaline

impurity control, acid chloride

Standards for allowable flws elIminatIon, hot soaks, sludge lncing,

Inadequltely supported tube High-cycle fatigue in recirculating steam pressure pulst, water slap, chemical

It denied neaw the top generators (standards or cleaning, and borie acid additions

support plate once-through steam to control IGAJIGSCC support plate ~~~~~~~~generators are being prepered)

QW9-3521) ElIminate copper pickup by use of

titanium or ateinles ste condenser

Contact points between tube Fretting Flow aeptance crterha tubes, and replace the copper-bearing and ant ivtbrstlon ber determined by Tech Specs. 5liop' In the foedwater train to reduce

(IWo-3630) pitting and denting

Use all-voletile treatment water

hehmitry, sludge lncing, chemical Tubes above tube t Wasteg Critefi5 fo doemining Cleaning, hot aoak, hot blowdown and

necessity o plugging flushing, wnd *elmination of hideout o graded tubes chemical concentration to control

(Peg. G uide t1i2t) wa tg e

Once-Through Tubes Erosion-corrosion

Outside Unscheduled Inservice Use chemistry control to prevent Surbsce Fall Impaction of each steam concentration of Impurities leeding to

generator when Is required ~~~~~~~~fatIgue crack Initiation In once-through primary to secondary tube semgnrtr

Tubes In upper tubosheet Environmental leaks exceed the limits Use lane-flow blocker In once-through

region tatigue delind In Tech. Spes. steam generators to mltigete erwironmental fatigue

rev. 4 *7UM
STEAM

GEIIERAIOR

(1)

ISSUE

COLUNe

STRESS:

VESSEL PROBLEMS

INTERGRANIKAI

STRESS CORROSION

CEACKTC G- IGSCC

MELMENETS

FATTIGUI

%MTI NG jIBE PROBLEMS

*IGSCC/SCC

*FATIO.E

F RETTIING

*CREVICES TUBE SHEET

REGULATORY INSTRUMENT REVIEW FOR STEAM GENERATORS

LIFE EXTENSICO

REG. INSTRUMENT AGIG FEATIURES FEATURES COtRERT E IXIATIAvES AGING NEEDS LIFE EXTENSION XEEDS

MUNN 3 COLUMN 4 4h COLUMN S 6 COLUMN 7 COILMl a

Cf's

10 CFR 50 Records. Records indicate Mone. Material Evaluation- Time intervals and

Appendis A mintscice amount of coverage may records adequacy.

problew. need review to assure adeq.acy of Inspection.

R S Cod EMTS cot~wa 9

Eefereeices ASXE Code ISI Requirearenco.

(2) Appendix B ruality AosurAr1a.

TIS

3/4.4.5

P"' ;.)

(3) TSa requires Inspecttion for wit penetra- tions (via any mode of

wIt thiing).

More.

xont.

Proper GA witl assure that Odeqiate nd accurate mintonatce records are recored and proper procedures

are followd.

Mone, not ddressed.

oore, not addressed.

Mona, not addressed.

MoRe not addressed.

MOa. Erbritttament Fatigue

Stress.

Xone. Iproved inspectionr

for fretting/denting/

ICSCC are needed.

loproved methods of

detection for sizing

cracks and ICA need to

be reviewe/researched.

Depends on the ade- quacy of section xl,

IS'.

M/A-Section, TSs.

3/4.4.0.5.

Depends on the adequacy of Section

Xl, ISI requirernnts/

reports vs. license

rneawt n eeds.

References AShE code for ISI requirerents.

Current inspection techrique is eddy current

teoting of a fraction of tube huedie every

12-24 calendar months. No requirement con- cerning the SG shall or secondary side of the tube bundIe. Root-cuse, analysis requirements for tubs aIt thinning are not explicitly delineated. Reporting require- ments would have to be expanded.

This I5 requires ASMEE Section Xl ISIt Inspections

IWA - TSS 3/4.4.0.5.

10 expand the scope of the required inopec- tions the Section Xl requiremtnts would have

to be changed or additional requirements

would have to be added to TS 4.4.10 to specify

the types/frequency of inspections Ad tests required. (The ISo currently cover the SG tube

test frequency; Section Xl doesnrt ddress the frequency.) See Section Xi analysis.

Does not address rapid SG teoperature transients

caused by feedwatereaergency, feedwster transients,

or rapid depressurizatlons of the secondary side. however. tnstnces of transients or rapid depressurizatfon would be reportable incidents.

14)

(s)

5/4.4.10

314.4.0.5

ASNE, Section

Xi ISI, Inspections are

required.)

Mono.

mne.

Mn.

N/A

Depends on the

adequacy of Section

Xl. tSI rsuireenta reports vs. aging

needs.

(6) 3/4.4.9.1.1 Thersal/pnressure cycles are recorded during RCS

heatuop or cooatdaim

(priomry side only).

Cycles are recorded. might be useful In

evalueting theretl/ pressna- cycle

history/savarity.

General Motes:

1. A rp Indlcates further study/investigatfon ia needed.

2. For the GSM, -resolv.r meam the generic safety issue is resolved, not necessariLy the aging isue.

3. For moaning of abbreviations. acroartsr and initiativ, used througbout, se ecronam on pge xi, xli, d Xgifl of the report.

-. Stem Generator
CPNT IhSU

COLUPO t CIL

STRESS (contd)

(7)

LIFE EXTENSION

REG. INSTRUMENT AGING FEATURES FEATLRES CURRETg INITIATIVES AGING NEEDS LIP!1 EXTEWSIN NEEDS

COLUN 3COLUMN 4 * jOUM. CLPW COLMN COUM a

WE1TS

McCaIl 9

Tis

(Alt) Section Xi VA rn operating plant

criteria Is deWALopirn several rno

(n am tory)

appendices to

address raturn to service situations when ccraonant TS

hae been exceeded.

5a

(O) 3.9.1 General Posip Criteria (DC): desIgn

with aufficient esrgin.

Also iDC 1 2.14;

10 CFR 100 Appendix A d 10 Ccm S0.

AppWojlx S.

Norm (except for initial margins). Nons. Evaluate transient used In the design ad

fatigue analysis.

(9) 3.9.3 Material Integrity. References ASIE

Code.

gon.

(10) 5.2.3 Review suitability of esterials chosen, Perform tests (fracte

toehess). Review pro- cedures of manuacturing And welding. WE per

Section III. R8-20W.

Mrne. lone.

I-i

I-4

bp-u

(A)

Covers all reactor crooant pressure bounry.

ASME Sec XI reqjrnts my not be adaqet for deterioration. A naw Apperdix IV updetes ET And my assist In these requiremnts.

Doesnt ddres specific gtr Issues; Section

11, Class I copnent design criteria mst be

followed for pressure beuatry.

(11) 5.2.4 General.

(12)

(13)

(14)

(15)

5.2.1.1 Ant met 10 CT! 50.55 (t.e., met ASI req irmnts for prese" banlraea).

5.4.2.1 Oserall Integrity Rafae nces ASE.

5.4.2.2 Referencs

Regulatory Guide 1.83.

Maw.

Ibne.

Mon.

None.

Mon.

Yes.

on.

Man.

None. In Rewrite. Specific inforeatlon

nmde to be camil led

with referece to a 16.

Eliminete unintentional

d'Id . 40-years constraint In lRC Roo and Codes rnd Staedrds.

Mew Guides needed to establish a deterioration overview of cronant.

MUEG-0313 ppiles to contairnmet boundary piping, not to #t tuces. 1.83

NRPLEX Code" Standorde Work. Identify obvious charges--

fatigue Iltfr 0313.

-- Stem tonerator
(16)

ISSLE REG. IMSTBRUEST

$TIES$ Ccontd) Rrs (Contd)

LIFE EXTENSION

AGalx FEATURMES CaRRENt INITIATIVES AGIYC IEEDS LIft EXTENSIOX MEEMS COLMIG 4 CLLM 5 C 6 WU* ELl 7 COLIAM B

COMMENTS

CQLL 0

No expticit refer nce

to agiq: provides an xRC acceptable List of approved ASW code cases for Section Ill.

(17)

(1S)

1.121 Defines stress limits

for filaed tube.s

1.147 No explicit referme

to aging; provides an

YRC acceptable list of approved ASK code

cases for Section XI.

The BC mist, life NC revisions we

extension by pro- made to include or

viding acceptance exclude appropriate

method of approved Code Cae.

(ASME) mterials acceptable to current pproved Cods

Ca".

slon.. C 1.121, Rev. 1,

being developed from

Stem Generator

Integrity Progra_.

The Mt *seiste life RC revisions re Made

extmision by provid- to incltue or *xclude

fng acceptance mth- apropriete Code Cases. od of approved

(ASxE) Inepection

nethds uswing current

Code Cases .

M/A N/A

None. AME code Margins should be Maintained.

ASME Code Cass wre not andatory. Code Caen

provide a mechatiss to use elterrate methods

within jurisdiction of tha code. The case

re usutlly sopersaded (annulled) by revisions

to the code, i.e., the case becina port of

the code. in other Instancese the case my be reverned or dropped As n applicable mthod.

K/A ASHE Code Case oe not indetory. Code Cases

provide a aechwniss to us. alternete methods within jurisdiction of the code. The ce oe usually seperseded (Anutlled) by revisions

to the code, i.e.. the case bcome pert of

the code. in other Instaes, the cae my be

reversed or drspped as on aWpicable method.

Ag

(I9) Section Ill I_-

e-4

Requstification of A now ppendix is coonents. under consideration

which sy be used

to regulate coponents which have

e*cedod the rules

for cyclic operation

in Section III,

1-3Z2224. A Task

Group he been formed

to address the Isms.

This also aptlies to

Section XI.

fatigue curve Section Yl SC on revisiols. Operating Plant Criteria is reviewing

fatigue curves in

Section ILL to

determine If they can

be revised to accoosedate operation

beyond 40 years.

Beqemlificatlon

rule. for components.

laproved Ersi-of-Life projections, 40 years

nd beyond.

From Attacment Ill of the Meeting Agenda for

AME55MVCS (Bord lotor Code. nd Stardarde)

Steering Cmmittee on PLEY (p. 8); Codes nd

stansirde auch as SPV Section Vil for pres- sure vessels, 31.1 Cods for Poser Piping, nd

116 Valve Stasderda fall within the Jurisdic- tian of the AiiE ioard on Pressure Tecinology

Codes end Sta erds (SPTCS). Both NMCS ENd WATCS report to the ASWE CoGUcCil on Codes end

Standards. Consideration of Section Vil nd

I31.1 sllt be undr PLEY since they wsre

extenslvely u ed In the corntrixtion of

nuclear poser plants prior to the publicstion of AxE WV Cods. Section III.

Studies wre ueder my to sess the mgnitues

of the effects of actual envireroentat conditions. Code curvee we beaed on smoth

speclems In air at room temarature. wherm

Materiels in se-vice have such rouher

surfaces Ntd Mr exposed to Iflosing ceont at operating teeratures. The actual

surf ace re oe prone to crack Initiation.

Studies Ned resrch to asses maqtntude of effect of environmental factors could reault

in need for now Reg. Guide, Reg. Instruments

Naedwr Code revisiacs.

(20) FatiNIe.

-- Stem Generator
CMWOMT 2ISE PEG. INSTOIPIEI?

STRESS (contd) AME (cofltd) (21) subsection

a

NC

of

AS9E Cock providee

requirents for design, *.g.. P _,eage

temperature uvd

echnirt tood, to eeeu*e the strength ut Integrity of the pressure bmirvioy.

LIFE EXTENSIUN

FEATUtES

own eopticit. yet

provides Buidnce rnd oets forth rules for ropeir*

Wd replacmnts of eod comoents.

CUR*RET INiTIATIVES AGING 0NEE LIFE EXTESIO2 l NEEDS iOXENTS

CO~LL" 6 Cott" 7 - calus a COLL" 9

Iept fed in the desifn Cuidln A neede to for Ctes I £eUSt5. AM Ce requite detipn criteria (Ce cover the limits of special consideration for weteriel sohject

coments). ceomoent deterioration, to thimning by corrosion, erosion. chanicat 0resion,r othmr Iwfrmwentat effects end "ta have proisiw wad for the effects urtniq the desitn or specified life bye sutlabte increase In or sedition to ths thicknees of the base ntael over that detrmined by the design.

Rules cover design wW constructitn roqire- Rnts but do not cover deteriorathen.

(22) Section Xi Conditifo Asosewent.

(23) Is hav been etceeded.

Messi ification Consideration of Conition Asesent of system *nd develptt of erAwe Informstiordvta. ceepononts. Article 6IW 8n,

Reqtification for Fatigue Life.-

VA6 on perst Ing

Ptlnt Criteria

developing rseat

now normanodtory ndices to areo return to servie situations =n cUmonent TS hav been exced

Acceptonce 0mwe. kmn.

Stanrds.

Acceptutce 0mw. paw. Stederde.

Acceptane Nam. oow. Stonderds.

Acceoptae 0omw. 0mw.

Reqalificstien

of systm wd

Wir iemiration of operating license.

n-4

e-4

VI4

(24)

(25)

(26)

(27)

(26)

(29)

(30)

600-3510

60B-3512

IW0-3516

M0-3519

6113-3520

6515-2500

000-3521

Acceptasce Sttrlrde.

Acceptonce ittederds.

Acceptuise Stuvbrde.

Acceptonce Standards.

Acceptonc. Stasherde.

r.de of pluwed or

repltced tubes.

Standrds.

Acceptence

Standrds.

Nomw.

Code evaluetion limits

for attasbte tndice- timw of deterioration suhold be detawined.

Iseum now Requletory

Guide 1.53.

Ale4le Indication

for U-bit flee is now 405 through-well.

iroth rate euggeets thits i toe hiDh.

Present rutle limit peer but do not specify the udr of defective tbuts that a stein generator can contein before reptacement is reqoired.

3n inspection is not edeqte and full tlngth s needed (ttube ehent to tuoe shect). Currant rutsn eqire secIuntiel 151 if ftlo(s) are detected. i.e. If ewething Is feasd suPe size in incre

Number of btus plugwed in a stem generator could Influence license rrnsit.

Xom.

Regulatory Guide 1.83.

N0m.

Yee.

Shmber of plugged or

repteced totee.

Stem t- enrstor
Crit" ISaUE

STRESS (contd)

(31)

RES. IMSTALWAJT

ASHE (contd)

1113-24 13,

IWB-2430,

LIFE E TENiSION

AGIllsFTU*ES FEAltiS

Cam 4OSI CURRENT INITIATIVES MillS llIAS CIiL" 7 LIFE EXES~esION NEEDS CtOLUMN a COMENTSrMwei 9

NOW. bnoe. Yes.

(32) lu -3630 Rewrite of Regulatory Guide 1.83.

Detection ad sizing

of SCC and ICA.

Should have Increased examination program after detection of flee 3-1/2 years between

eaminatior s ono permitted.

States that evaluation of cracks or IGA, etc., shatt bt performd by analysis acceptabte to

regulatory authority.

Appendix IV rewrite In process.

This section of ASE (Section X) may be transferred to Saction V. Section XI will be

replaced with a perforeance demntration ond

qualification guideltin. This Is in the process of being written now but could take

two ywrs.

(33) Appwdix IV gone.

(34)

(35)

(36)

C618 1e Failures of partially

degraded stem genrator tdees.

29 Cracking _d degradetion

of bolts ad studs from

stress corrosion,

fatigue, boric acid

corrosion, nd erosion/

corrosion.

35 Loose obJecte in sec'ondary piping could becom missiles during

stem generator blowrn

and rupture one or ore

tutbes

66 mitigate or reduce

stem generator tube degradations _nd ruptures.

67 3

III Stress corrosion crack- ing in stem geurator.

gone.

None.

gone.

Nore.

None.

lore.

tore. Does the irepection

frequency or fraction

Inspected nred to ho increased for exterded

life?

gore. Determine ,Aether

priority of the issue chanae for longer plent life.

Mone.

"OM. ?

Nawe. lin0s. Stem-line Ereak with Consequential Sll LOCA

o lplmented with Ti] action pln Item I.C.1

of ilSEG-0737. * Sgplemnted by kRC Generic Letter O. 02-33.

olting Degradation or Failure In Sucie r

Power Plents

* Priority - RIAl * Proposed Inspecting 10X of bolts each outage, extending en outage 1.5 days.

Degredation of Internal Apturtenances in LlRS * Related to 0-60

Priority - Low.

Stem Generator Reqjirements

* Priority - NIcN.

Stem Garerator Staff Actions

* Priority - LOW.

Stress corrosion cracking of pressure bwdary

ferritic steels in selcted envirornmts.

(37)

(38)

(39)

-- Stem Generator
COL(L

e4)

ism REG. INTUttMENT

STRESS (contd) Wes (contd)

A-3

5.4

AGI=N FEATrES

ceLIU 4

stem generator tutx

Integrity degroded due to waste and stress

corrosion cracking.

Stem Generator tu.e Integrity degraded de

to autage end stres corrosion cracking.

WlFE EXTExsIle

FEATUtE5 aCIRENT INITIATIVES AGING NEEDS LIiF FEVSSEI1 ilSED

CoLtm S tDLU 6 COwLM 7 ie- COUM COWUN 9

(41)

on.

None.

Nn.

.one.

Note.

None.

sestinnoase Stem generator Tuie Integrity

* See E ii-03n. * Degradation decreased by conversion from

ihosphats to on *tl-votltive water treatsme. Denting siceb toem to primary side

stres corrosion continues to be a probte.

C stem Generator Tube Integrity

o s 0MG-D371.

Degradation decresed by cwesrsion free

thosbhte to on stl-volatile water treatmmn. Denting which tlee to prisery-sids

stres corrosion continues to be a probt_.

EM Stem GCnrstor Tube Integrity

I se NUREG-03fl.

Fracture Toues_ of Stem Generator end

Reactor Coolant Ftup mports

* Solution meed availabte in October 19583

w.ith publicetion of IES-0577.

* pegls. to now construction mn S,

Section 5.3.4 is aised.

Primary coolont systan decontaninetion and

stm Eeuxretor dhmicat cleening.

(42) A-$

(43)

_-J

(44)

A-12 Leaster teering and tlw fracture touvr^ese of

stee gnrator und reactor iop support

waterians.

A- 5 Operation of La results In stow corrosion of

interior astsl surfaces of the privery coolent oyotee. Those are activated by neutron

fltux mn circulated tihroeh reactor mid

plate-out.

LIJA-47 Define geieric criteria for ptent specific

reviews for stee generator overfill

traisients In Prs and reactor overfill* In

As.

5-60 Presence of loose object In prienry coolent sys- tee can be Indicative

of degred reactor safety systee resulting

fro fait lure or eken- Ing cosponent.

km.

Moro.

kiem.

km.

(45) Safety tqltications of Control System

I Need to dess rupture of instrument

onsing lines.

(46) None. xm. Ferfort trend eaelysis

on toose pert e nttormng data.

Loome Part Monitoring SyStn

Priority - REOseLE.

- Stee Generator
COMONENiT ISS.E

COLL I CLLM

STRESS (cmntd)

(47)

REG. INeSTRUMENT AGIN FEATURES COLUVOI 3 ~ Caiie 4

AMS

3.2 aM".

(48) 5.37

(49) 5.3.10

?--I

iI

(50) DYNAMIC EffECTS * VIluATlIO

* TRERIAL CYCLES

* EROSION

(51)

(52)

(53)

(54)

CiTe

10 CFO 50,

Appendix A

Appendix B

TS6

3/4.4.5

3/4.4.10

4.0.5

AsE Code Class

Maintenance

cowittee

3/4.4.9.1.1

xCS heat-up/

coot -damw

Nione.

Records.

tut Ity Assurance.

TS resuires eddy cureent testing of

tubes that could Indicate tues session (shell not addressed).

wic .

Thermt Cycles are recorded during US

haat-up and coot-down.

LIFE EXTEXStIOx

FRAIIARES

X vim of plant

procedwes/records

coutd give inesiht

into deterioration.

Revile of plant

procodures/records

could give inisiht Into deterioratien.

Review of pltnt

procedures/records

could give ire iaiht

Into d terioratlon.

Yes.

Yes.

None* Mt addres ed

Moes. not

addressed.

Mores not addresed.

CUiRREsT IXITIATIVf S

Mores.

Maw.

MGM.e

t1"

to Ia 7 C airn a

M a w . If w.

Ma.

Maw.

Moteriat Evlust ion.

tStrittes nt fs tl.w Stress.

tlm.

Nol.

Ifw. Inspect ysendery side of tuIes for

vibration (fretting) *ed shell erosion).

Interval between

esa nmed to be rvied.

iMethods of detecting

end sizing cracks nd 1i. need to be revwleed.

leports froms Inrspec tione could be uwad

to evaluste tues erosin coenditions. theefh root-ce

anatysis _y be locking.

D ar on adequay of

Section XS IS1 requiremuits aind other

requirenarts already in plice.

CtlTS

COUSIN 9

Otifty A isuenco docuintation andlor racords are requird to ohe NWd eveuate deterioration of a crnt

References ASE Code for 11.

Referencees ASJE Code for ISI.

Eddy cuiraent testing fired watt thinning btu

not ncessrily the m of thinning etless the utility included this in Its correspondIng report of the Inspection to the MRC.

Oily a fract Ion of the total evter of tuber wr rae lred to be inspected during en outage.

TS 4.4.10 defers to T.5 4.0.5 which specifies that the ASN. Section XT, rquiremente wr ppicable. Se Sactlon Xi analysis.

Does not eddeess rapid SO toerature trmnisnnts caied kty feehater/sirgncy feedwater tremiients (e.g. transients

associated with fooestor/mrsency feedweter SC over-fooding or rapid loses at fesdater praheeting).

i". M/A

ionts. The theriNt cyctes are

recorded and retained. Perhaps useful in

evatueting cycle

history/agwelty.

- Stem Generator
00100MENT him

MLL I U

DIMOIC EFFECTS

(55) (Contd)

REG. ImSTRlUEet ACING IOTtEfs CQLUtiN 3 mumt 4

3.9.2 Review of the criteria.

LIFE5 EXIENS ION

FEAIIAES CURENeT INITIATIVES AGING EMC LIFE EXTlENSION NEEDS COW""S

COUINe 9

test Im poedrs n

daneaic Iaty it.

I5O 3.9.3 Ilaterie Integrity.

Of?) 5.2.4 General.

Norm.

Yef. ASK.

Nove.

Mona.

mu.

NoIe. Cplete aI relable

cote bees.

Norm, tye.

SAe structust hA iunctionet integrity ider vibratory loeding.

Cmpete mD reliable

date be".

A91E SWe Yl XruireMta My not be adequate

for deterioration.

Dosm t ad m specific Isemma; Section III

not be followed.

(5M)

(59)

(40)

(44)

(62)

3.2.1.1 lemt meet 10 CtF 50.55e (i.e.. Mt ASE Section

fi1 reqiirants for

pressure bmclodries).

5.4.2.1 Overetl Inteerity,

Refernces ASE.

5.4.2.2 l1fernerf

ewluatory Guide 1.83.

1.121 beft ms diaicA Loading

consideratiorns over Img tube fail ture.

1.147? No explicit reference

to agin; providee an RC acceptable list Of Doved AWE codt

cae for Section It.

1.85 No explicit refenc* to ainC; provides on IlC acceptable list of approved AIE coda case for Section 1I1.

None. Nons.

11".

norc. In *eweit*. Too. aew Guldes nerd to establish a deterioration

overview of component.

Limited. NG 1.121 limited to the integrity. Consideration of other Lam term failur structural deoration. resistance of SG vessel. i.e., vessels.

I/A ttA

.-4

0-4

(63)

The RG assists life to revislln are made extenion by provid- Inctude or ecslude

In acceptimcs Math- appropriate Ce

ad for epproved Cae.

(AVE) inqpction

Methods Ling currgnt Code Cas.

The MG asallts life NG revisLau We me extension by provid- Include or eclude ing aceptance mth- appropriate Code Cases. ad for approved

(AfE) _ateries

acceptable to current approved Code Cases.

A9E Code Cae ae not _xtory. Code Cases

provide a medimnime to was alternate methods within jurildiction of the code. The case. are usually spuerseded Cmvstled) ty revislons to the code, I.e.. the ca e pert of the code. In otler instcea. the case ay be reverd or d *ope an m Wicable method.

AWSE Cod Cas ae not etory. Code Cases

provide a Mechanism to uie alternate methode

within Jurisdiction of the code. The cases we umually superseded (tmettld) by revislon to th code, I.e., the caee part of

the code. In other instancee, the c-s may be reversed or r ane nappicable method.

N/A I/A

(64)

AN

Section 111l Subsection tien

NC

Np

AS91 Code provide.

rPeramts for desisn. e.g., presmue.

temperature mi sechanical lade, to aseure the strength W integrity of the pressure bmtary.

Iona esplicit yet,

provides Guidane rid sets forth

rules for r"peir and ropteaments od code ompnents.

Imptled in the deeign Guidance Is naeda to destin criteria (ee cover the limits of comnts). c mot deteriorattion

foer Class I comewts, AME Code reqires special consideration for materisi subject to thinning by corrosion, erosion. mechatical draion or other onviraramntsl effects ai l htve provisions _d for the effects doting the design or specified life by a

uitable increase in or *elton to the thickness of the bes Metal over that deter- Mined by the design.

Iules cover design int conatruction reqire. nets but de not cover deterioration.

Steam Generator
Lift EXTENSION OMlE t ISSUE REG. INISTRALKENT AGIlI FEATWRES FEATLIEES fOLWI CSLLI 2 COLUMI 3 CQ 4tM A COL S

DYNAMIC EFFECTS ASM (contd)

(65) (contd) Section Xl Corrosion ad Erosion.

CUARElt IEITIATiVES ACIRC MEM LIFE EXTENSION hEEDS COLUIIII 6 COLUMIN 7 COLWM a

A nre VA on pipe

wIa-thinnin has

been estaltiahed nd

WilL review this

lasut with EPI.

tain at" of conern

at this time is the

effects of trosioev

corroion on pipin in

non-suclear applications MSIUASHE

*3tC-1901K HM for

Wotrminire the RosininR Strength of

Corrod d Pirxttne S

Rewrite at Regulatory yes. 1su now Regutatery

Guide 1-81t Guide 1.o3.

None tbne Evatu ti0n nd guld t

For allowable Indles

ltors wd doterlora

tten limits houtd be

detere d ed.

memArs

Th SectIon XI Sutbgroup on Mestructlve Examination is currently developing a CaW ad n dattory ppandix on Ultresonic Detection d i._7eastjfnt of EreoimvrCrrosihn.

Amsi/ASW 3-31.6 may have limited appication to nistl r fecilities.

13 inspection Is not adequate ad full length is needed (tUbt Sheot to tuoe sheet). Current rules require, spatiat ISl, If flats) are detected. I. * if ethinw is ioud* siple size Ia increased. (The tut# "ptirg 1s *et by the Ts, not by Section tli)

Preset rules limit power but do not apecify

the ner of defective tubs that a stem generator ean contain before ropLaeonit Is

ecssry.

(66)

(67)

Iw7-2500 moa.

IWS-3510 Acceptance Stadards.

F-4

i.-I

CD (68)

(69)

(70)

(71)

(72)

IWt-3512

Itd-3516

IIL-3519

I11-3520

IW5-3521

Acceptance Statdards.

Accaptance Standards.

Acceptance Statdards.

Acceptance Staidards.

tader of ptumed or repleced tutee.

None.

Acceptance

Standerds.

Acceptance

Standards.

Acceptawa

Stardards.

ArAptSA

Staidards.

Acceptance

Standards.

Number of plugged

or replaced tues.

None.

Ma.

Iwb.

None.

tbne.

0.

-ar.

Mar.

Allowable indication mst of tues ptuged In a steam generator for U-herd flaw Is could Influence license renewal.

40Y throth-wett;

growth rate etafests

this is too high.

This my not be conservative oeoth, h.e., all indication of a

flew should require

pltus.

-- Stem Senerator
MUMtM1 COSIN

DUNMIC EFFECTS

(73) fcaned)

NEG. INESIMMENT

ASHE Ccmtd)

11II-2413, 2430

LIFE EXTENISION AGING MATIMES FEATMES Ot*UM~T INITIATIVES AGING NEEDS LIFE EXTENSION NEEDS

COaLUM 1. *W****MN CLM ** 6~J WOLMS 7 COLLPI a CENTS

MIAMI 0

Morm. None. YTo.

(74) 1IMI-36" *Ma.

xon.

Regulatory Gild. 1.83 Yes. detectimn nd sizing of ScC nrd li.

Shoutd tae Increased examination proeram efte f eactien of f1lat 3-1J2 years betewen examinations Is now possible.

States that evaluation of cracks or ICA, etc., shalt be perfoowed by aIlysis acceptable to

regiuatory ateorityi

(751) p is IV M". Appendix IV rewrite In procee4.

This section of ASe (Salion Xl) my be

trosf erred to Mactimn V. Sectin xl will be replaced with a perforae - trotlon nd

quslificatin Guideline. This is In the procese of beIng written now but could take

two were.

(76)

(77)

18

35

i"

I-4

I.- (78) 60

Looe* cbjects In secondsry pipiog could c I missiles djring

stem Generator bteosdsn xnd rupture e or more tubxe. Prsencs of toor objects I pliss a

Systm has ifa led.

Lemiltr teering

represents a resution In toad a joint coutd handle, particularly

uner aersency condi- time sch as seismic conditions.

mitigate or redeos stem generator tL*w'

degraistions ard ruptures.

More.

Nn.

NOn.

Na'.

M".

11n.

Nn.

Stem-tine break with conepanntifa emtl iOCA.

Degrodation of Interact APPUrtmesc in LiRs * Priority - LOW.

Lamttl Tlering of temctor tystem Structural

supports

Is a subtask unider A-12.

(79,) eS N". Stem Generator Neqjirants Feur Item Priority . NItC.

(80) 67 7

ilare.

Nam.

Mo.

Nam.

N'.

5te Generator Staff Actia's ! Priority . LW.

esatinshouae Stem generator Tabs Integrity * Sam 9fte-03711. (S1) A-3

stem Generator
(8LU

(ez)

IS"E

DYNAMIC EFfECTS

Icrt4d

LIFE EXIENSION

REC. lNlSTUMEl A61C0 FEATEUES FEATRS CLAEMM INITIATIVES AGIG EEMS LIFE EXTENSION NEEDS

COUSINl 3 _ tcaL" a6 4 S9 tC ielI I C7.OLLM a

gill"es

COLUH 9

GISs icontO)

A-4 tam. hon.

(AS) A-5 *obe Cracs of urakim

origin propagated In

the circumferantial

direction by fltw

indjced vibratiot.

Erosion cavitation

Pheomen.

A-12 Lassiter tering end Ia.-

fracture tluJrOM of

ste gesurator eNd

reactor pW eu4 port

Materials.

(84)

(SB)

Mon.

Xar.

one.

11r.

11r.

Sa".

OE Stem _ erator T1he Integrity

* sIo . -0371.

iS& Stem Gernrator lube Integrity

* SIUIEC 5-0371.

Fracture Toghness of Ste Gawerator end

Retator Cooltnt Pk S'pports

Solution mod available in October t93t

with publication of 5*50-0577.

In tUe cte of Xortb Anna Iicensee agreed

to raise terature above 22-F before

preauarizing above 1100 PSi.

Safety Iplaicatione of Control System.

Loos Part Solitotring Systm

Priority - ESOVEDO

USIA-47 Contribution of control

Syst' faitures resultIng In overfilling

traratents wd pros- surized tlhert shock.

More.

(56) Xcr. 1-.1 '.-4

1-60 Presence of too" object in priMary

coolant systn can be

indicative of degraded

reactor uftah systin

resuLting froms foled

or weakened cponent.

A3S

IS?) 3.2 ilne.

ISO) 5.37

Review of ptant

procedares/records

could give Itlasht into deterioration.

erives of pltnt

procedures/records

could give insight

Into deterioretion.

Seview of plant

procaures/records

could give Insight

into deterioratfon.

Sa.

Sa".

ir.

Ease. 0l4elity AS urnce detoUentetion end/or records

er rewired to shw and evaluate deteriorstion of a cmponnt.

Saw.

cm9) 5.3.10 Xron. Xone. h r .

-- Stem Generator
COaiPNT IUW AEG. IISIcMtNT AGIN FEATIAES

U I coLlt 2 COLUMN 3 COuLUM 4

SIItRAL INTEGRITY es

(90) * PSACIW TOMfEI 10 CfE so, Rom d

* ElITTtENT appsodix A tIEUNAL

* SEISMIC (DAMAGE)

FASaIRES

(9i) _ x A Design be for proCriterion 2 tection dof ewipent from natural VI - -

inclurin4 cn ts

IoportUnt to safety.

(92) Criterion 51 Woaw expticit/ tiputatese aector

Preesur Boundary to

be designed to include

cornideretions (suficiint _frginx/fctor of safety) for pressure

ontatinmt under opersting, testing, nW

poetuieted eccident Conditions suci that

the prem" bourdory

ferritic _tonrals

behave in * eewrittle

_ner.

(93) Appedix a 'Q'ality Assurane.

TSe

(94) 314.4.5 U/A

(95) 3/4.4.10 mI.

(96) 3/4.4.7.9 Require periodic

testing of snu e

esa1ciated with the

SG And piping.

LIFE EXTPIOX1

Yes.

Eoe explicit; provides direction to

u t ee

blnet historical

phenonans for the

design. I.e.. this

conretive design

be".

Wont explicit; Implied by the dIgn

if the ferritic

*torilt contimre to show ni-brittte

prCetiee.

yes.

on, not

addresesd.

ewne. rot

oddresed.

bone, not

ddressed.

CUF EtT INITIATIVS AGING WES

OWN 6 COL~UMN 7

Wore. Materiel Eveluation.

eone. oruric and specific

designs) mat meet

Current nd bI

natural pdin.

Wbnx. mthods to asses

irittled prop rtes.

LIPS SXTERSI9 WEDS

Intervels between *fre aees AK for 1i1.

ex need to be

reviewed.

Design mat meet current Wegulation should be upted to refl ct

design criteria for the life extuwion options mid the option

pteoe. to ssaluste nuctear f*cilities for

plant aging.

lined lNDE techniques Wegulation criteria needs updsting to

to determine Orittlt- fehtune Life exteneiin applicatien.

ment prprties.

I-.. Wine.

Won.

o n .

W e.

Embrittlemnt IFtipes Provide adits/records of References ASE Code for I1I resqirents.

Stress, methods of detection

and sizing cracks

Nd IGA.

WA 7 TtS ruires periodic eddy current testing of

SG 11-tame.

S/A 7 This TS rquires ISI ASK. Section Is. If Section

XI is et sfowato, and the TSs re to be expended.

this my be whore the revisions should occur.

This TS Is limited with reference to the seismic

isum i.e., seienic monitoring of the sits Is

required. Wother refernces oe ends. In addition, periodic tenting of the SG sr*bers doe

not occur. The utilities are unble to do so.

.- Stem Generator
ComisMT

(9?)

(98)

LIFE EXTESlIOiN Is". REG. iSTIUiMLIET AGIG FEATWIS FEATURES CMlILL 2 O MINIMd 4 LAI

STRMLCIAi. INTEGRITY Ts (all) (COMOd)

CtlOENT INITIATIvES ASlhC NEEDS LIFE EXTfESION 0 EEDS C.ttl A CoLtue 7 C 8ais 

Workinr Sroue on Operating Plant COf teris, proposd addition to Article 11W-3S0 of Section Xi. Would contain rules and forlutns for perforilng an aluation of a c-m pon nt's fitness for continued service when either TSa or elemnts of Its con- strurtiaendeien

iil-tatione had been ecded

TTNMIS9

3.9.3 -d 3.9.3

A pnix A

(99) 5.2.3

I-.4

0-4

(SO0) 5.2.4

Materilt Intearity Reference to ASHE

Section III nrd GDC 1,2,4.14,15.

Reriew suitability of materials chosen. Per- fore tests (fracture

tougess). Review pro- cedures of amufacturung and welding. iDE test- ng es per Sectiton I, Me-2500.

Reeqire II Progrem of WeU (CDC32) to eases structural end leak-tight integrity.

Must met 10 CFA 5O.55S

(i.e., meet ASlE Sec- tion III rquirmnnts for pressu boundaries).

Overall IntWrity Meet CDC 1,14,15,31 mid IS CFO so, Appuitix A. Nave sufficiunt design mergin. eview nltectlon rd fabricatien of meterlals. lust met ASK code.

Rehren Agg. Nm (except for originat design eag lre).

km.

Nn.

Mom.

hom.

More. Covers alt reactor coolent pressure beouaery.

MoM. Y". Loeding crminationm. syste operating trawients, and stress limits.

Based on rquirits of 10 CFR 5055a and detailed in ASEK Section Xi.

(101) 5.2.1. Nn.

Nm.

mone.

(102) 54.2.1

Doesn't ddress specific essun; Section 111 mat to folttred.

To Met the CDC 1, the acceptable meteoiats re specified in Section III, pndix 1I Section 11, Ports AtC. Nat also meat RS 1.5. To meet CC 1i14, mnd 31, the fracture toughness mast met 10 CFR S0, Appendis G. ndl section I1 15-2300 and ASE, Appendix C 6-2800. for weldingse ASlE Code Satform III and TS.

(103) 5.4.2.2 Reference, Regulatory

Guide 1.3. brm. Rewrite in process. Ves. Now quide needed to establish a deterioration overview of cronent.

-- StBe Generator
ODNhEUT SN REG. INST5IIET

ST"TUmL NEGIT M

(104) (contd) 1.121

AGIeC NATURES

efins mthod for calculating minima

acceptable tdb wall

thickness.

LiFt ITtElIOia

PEATIMS aEQEOT INITIATiIVE AGING REM1

CORNL COLUN Mg 7 LIFE MlTEHr WEDS

Long-ter failure r lstane of K vessel.

(MhDN 9

Limited. E0 1.121 limited to Consideration of otier tuie Integrity. strtural degradetion,

L.e., ve...ls.

(105)

(106)

1.14? XD explicit refere to aging; provides an UR acceptable list of

approved A91E code

caes for Section XI.

1. ilSN0 eplicit refererpe

to aInc. provides n X1C scceptabe list of

aoved ASKE cod Cos" for Section 11.

The t esisto life KG revisions We med.

exteiwion by proid- Include or eactuds !nq acceptance moth- appropriate Code Came.

ad for 91rovsd (ASE) Inection

mthodi using aurent Coce Cos".

Tha £0 feafst. life KO revIalona wr. eateision by provid- to incude or aetude

ins atteptac meth- aMpropriate Code C_.me. ed for aved

(ASE) moteriaIS acetab to aurrca approved Code

Case.

s/A i*/A APE Code Cae ae rat dltory. Cods Cases

provide a machorls_ to use alternate methods within Juriediction of the code. The ra"

re us..tty st erd (annuillad by revisions to thi cod. i.e.. thi cam bacs part of

the code. In other Instanmes the case my be

reversed or droped a u n appicobte method.

ASIE Cods Cme we net dstory. Code Cases

proiade *a mechenfo to use alternate methods

within Jlurisdictln of the code. The case we uwsutly s eparsd (wurwted) by reviwso to the cods, I.e. the ca eco s s part of

the codes In other inetmnces, the came my he reversed or drepd as m n tlicable method.

*/A M/A

(107) Sactian III,

leimection

PC

eF

ASE Cod* provide

roiirownts for design. e.g., press'e t"rature nd

mechanical foods. to amoeur the strength

and Integrity of the pregsue br.

lonei expticit; yet

provides gudnrce wed aid sets forth rutes

for repalrs Nd repacmntst of code crionunts.

Imptied In the desion

criteria (soe coints).

Cuidast Is needed

to cover tie limdts

ef rI nt deteriortion.

*-I

_-I

1.

Ln

For Clas& I ceonts, ASE Code reuires epecial consideration for meterial scbiect to thining by corrosion, erasion. _echaical

abrasion or other snvironmental effects nd shall how preoisions mde for the effects durang the deign or specified life by a suitable incrse In or adfifon to the

thickness of the baes metal over that determined by the design.

sules cover design and censtruction reqiromints but de nt cover deterioration.

Present guides limit pwer .but do not specify

the rer of defective tutes that a steam genrator can contain before replacesont is

requird.

(105) nWE-3510 Accaptuste StuKWiderd. Aceptant.

stnrdsrds.

Sons. tOM. Evetuetitn mnd guide for altlewle Irdicetiens and deteriora- tion limits should be d*etorined.

(109)

(110)

IW.1-3512 Acceptu'cm Standards.

ii-3516 Accaptaice Itsasierde.

ACceptasI

Standards.

Acceptance

Stanclrds.

bna.

Xa. 5w.

-- Stem Generator
aOWCAMEN la Et. INstRUmEAr ODUM I OU UI

SbTMXTUaAL INEGRITYb ASE (contd)

(Ill) (covit) lwa-3519

(112) lIW1-3520

(113) lwo-200

(114) IW.-3521

AMIO MEATIAES

Accaptunce ttaerwdee..

AcceptMnca Stanidards.

None.

Numer of plugged! or replaced td.@..

LIFE EXTENSIONl

FUATURES

Acceptenca

Standrds.

Acceptence

Standards.

bimber of plge

at~ replaced tubes.

SR£A1I IITIAlIVES

Non.

ion.

begulatory uide 1.83.

bmw.

LIFE XTE0SIG NEEDS

1MWu new Regulatory

bulde 113.

Allowabit irdicatlOn for U-bnd flaw is 'aw 40: throu-*walt.

Growth rat. aeets this to too high.

iOlOaTS

COLL" 9

b,.r of tiieg pluag In a stem generator

could lnfluo* r lceie rrw{al.

(115) l*-2413,

a4go in. oen. Yc$.

(116) Regulatory buode 1.U3. Tm detection nd alzing of SM and lil.

(117) Article IV bore. more.

6-t

0-4

Should hae Increaaed eamiation progrew miter detection of f*a1s 3-1/2 years between exinatimw Is now poaaible.

States that evaluation of cracks or tCA. *tc., shalt be perforid by enalysis acceptable to regulatory authority.

Regulatory Authority hk been rewritten end

a In final stow.

This aection of A"hE (Section tS) _y be

trawfefrrd to Sectiwn V. Section XI will be reptated with a performice demuatratiun and qalification guideline. this is in the

procaaa of being written now but could tae two yews.

uat I ty Asurance documentat fon and/or records are re irad to omw and .valuate deterioratimn Of a Comonent.

An (Ila) 3.2

(119) 5.37

AMn.

bAre.

bMG.

beview of plant procero es/records could give inetiht

into deterioration.

Review of plant

proc duroe/record could give innight Into deterioration.

bevies of plant proce dwrearecords could give insight into deterioration.

in.

bone.

Aone.

Nm.

born.

None.

Xle.

bale.

M. (120) 5.3.10

-- Stem Caierator
LIFE EXTENSION COMPOENT ISSU MGB. 155151J51T AGING FEATWRES FEATURES CURRENT INITIATIMI AGING NEEDS

10505115N CIFIS

(121) INTERS CIMSZISI 10 CFU 50 10, Records. Yes. None. Noterial Evaluation.

* lIMULITIES Appendix A *INTEUGAMULAR

ATTACK CIBA)

*IRRAIATION ENl- FANO0 EFFECTS

(INRFASS0 SAaOLYTIC DGI5PCOI13ON OF WAlES AND CONmESER INLEAKAGE INFLUENCES WATER CHE"ISSTR)

LIFE EXrENEIIU NEEDS M5tU" a a nENrS

MINOt 9

Intervalt betwtn ais Anfeiices ASK for ISI r irenvts.

needs to be reviewed.

(122) Appeoiis 8 Dual ity Assuance.. Y . Non. Embrtttlweu Fettlws

StremU.

nthd of detection and sizing for cracks ard ICA ned to be revi5sd.

T'o

(123) 3/4.4.5 Edly crwrent testinw

could detect wet thinning dus to cdhinstry

problem.

-

NoWe. not addresed.

Nop. not addeesed.

Nope.

mone.

Ems.

Inmpction r pornt could be e Id to took at *t estertets

for dhmfstry-apecific

Iearns.

N/A

t/A

(124) 3/4.4.10 Yqaires AhE,

4.05 Section xi, rWqireMonte for M.

Inspction rorts

eight be usful for raiwet criteria

review If reqirmats

for reports were mads

sor Specif ic.

Depends on iwhtluer

reports/records of

ASE, Section XI. are

adequate to be useful.

Primery sIds chmistry

mrtysis records we retained. perhaps

useful In evlusting s4

history with regard

to chemtstry of fluid

(RCS).

(125) 3/4.4.4.?7 Reauree priory coolant Nwn. not (CI5) demistry control. as d

This TS reqfires maky crurrnt testing of SG U-tubes.

IA effects ma U-tube wett thickness could be

detected tthou the crae Is not necessarily

Inferred. Reportine requirements would have to be

This TS reoaires the requirnts of IS 3/4.4.0.5

CASINE, Section XI. ISI) be potlied to SG.

GENERAL CORROION NOTE: Technital Specificstiona do not ad*," secondary (steam plant

side) ciemistry control at alt. This is

ware dhemicel attack of U-tds wuld seen

the mat likely. Therefors, especially for

old 525, sacmdery chemistry end its bearing

mn U-tuhs Integrity wcutd be of greet

isportance. (Secandary aide cheeistry is

dinistratively controlled bit rat by

TSt)

Limits placed on Ct, F. ad dissolved

oeypen. Are thli, adeqte?

Steaed state

P . met. r Limit Trarslerit Limit

(dissoLvtd 02)* 4.10 PP v °° Pon

(C1 ) 4.1s an o1.50 po

(F ) <0.15 pi 150 pan

*I/A If C3 to. is <250-F.

*- Stev GeCerator
rUat

(126)

(12?)

(128)

[ism 850. IKSTMJEMI

COLM2 CDLM

COMICIN (contd) Sof

3.9.3

A51G PII-S 71iWO FEFR CLtity. 4

MatCerial Integrity.

LIFE EXTENSIOI FEATUhER O.355 IN.IIATIVtS AGIN5 CRESS LIFE EXTENSIONt NEEDS CCIEXTS

COt'LUM 9

(129)

(ItO)

S.2.3 Corroslon.

S.2.4 General.

5.2.1.1 "Mt met 10 CP1 90.55S

(i.e., mt ASK Sec- titn III rquirerentU

for preaire bonarl ies).

5.2.4.1 ihat mat CDC 1. 1415

nrd 31 of 10-CFt5S05 As fdix A. The desitn mat have Sufficient

owein. Rewuires review selection Oid fabrication

of Moterials. Fracture prevention Oriteria mat

be satisfied.

STP WTI 5 3 Maintain wet r choe

istry. Guidea to design to pere-nt

sludgp butid-up.

5.4.2.2 Reference Guide 1.83.

10.4.8 Stm generetor blow- doen system revieb design bael.. CDC 14: secondary water

chemsitry.

References ASIE.

None.

Cans.

Neam.

ione.

xore.

None.

oNea.

Ye..

50,0.

More.

Yes. Covers eonetruttion nty.

ASHE Sae XI requfiroentU -y not be Keloque for deterioration.

7 Doesn t dres specific Isss; Section III

msat b followed.

7 To meet the iOC 1, the acceptae materiels are speciflad In section 1II, Appendix I,

Section 11 Parts A.R C. Must ates met Regulatory Guide 1.85. For welding see

Sectiens III and ItX. To met corroslon- resistance. s Section IX, Part OW. Articles

1, I. 111 and IV, Referenc. DP MES S-3 uatert Chemistry for Stem Generaters).

e1e.

(131) Maintaining -gone

water citmistry.

Actually _tione slone-term reliable operatiorn." Referonce Regulatory Guide 1.37.

(132) Cone. Rewrite In precess. Yes.

i-_

X74

e.w Guide, need to establish a deterioration

overviiw of coeponont.

(133) None. inn. Review only initial design of the syte-m.

to (134) 1.121

(135) ASiHt

Section 111

Subection

itsC NC

UP

Degrsdation growth

allowance Included In minimum tub wall determination.

ASK Cede provides rocivirmonts for

desisn, e.g.. preesure, tapeeatue and

medcanical ltods. to asur the stroneth and integrity ef the

pres ure btoudary.

Limited. Revisleon of ES 1IZI t Rtter definition of par atialy sdrsases degradatIon growth

degradation growth rate. needed for

allowances fer tunes. specific defecta.

Setter mdets of dgra-e dation growth needsd to protect remining tube

Integrity.

Guidance Is needed to corer the limits of comfont deteriora- tion.

Xone-qepllict; yet

provide. guidm re

and sets forth rule. for repair*

mnd reptacgemnte of

code comonents.

Implied In the design desitn criteria (see

cobnts).

Available data froe accelerated laboratory

tests. May rot be useful for predicting SG

performance.

For Class I components. AM Code reojire

special coneideration for materiel subject

to thiming by corroslon, erosion, *echonical abrasion or other nvironmntal effects and

shall hwe provisions made for the effets during the design or specified life by a switable increae In or eddition to the

thickness of the bose meat over that deter- mined by the deeisn.

Rules cover desigt mnd construction retresnntu but do rot coer deterioration.

-- Stem nerator
COPONENT

(136) CEORRlI tcontd)

RE. IMSIMIMEIIT

ODLIq 3

ASME (cntd)

Section Xi

I1-310

A31GI: FMATtffS

Acceptance Stmndrds.

LIFE EXTENSION

FEltWIFS

tOtUINI 5

Acceptance

Stanrds.

CURENTe INITIATIVES AGING 55505

COLUMN 6 CO~~LUMN I

lions. NonMa.

LIFE E8EI5 NlEEDS

Evalurtion Ad Guide

for atowbie indics- tiens n.d deteriorstin limits should be determined.

.,ml;

Present pAides liet pear but do nlt spacity

the Rabi of defective tubes that a stem

Generator can contain before reptecnt is required.

(13?)

(136)

(139)

(140)

(141)

IUB-3512

155-3516

155-3519

IWB-3520

255-2500

Acceptance Standards.

Acceptance Stav'arde.

Acceptaaca Staiderde.

Acceptance Staudards.

Maw.

Acceptance

Stavrds.

Acceptance

Stabrds.

Acceptance

Standards.

Acceptan5

Standrds. st*.

tMo.

11".

11".

Nor,.

Ma.

11w.

ion.

Nore. MOM.

Regutatory Guide Yes. Guide 1.83.

1.83.

lsar now Owaatory Guide 153.

(142) I51-3521 Nuber of tubaes ptuagod.

, of tub

plumged.

Xon.

Alloweble Indication for U-batd fla is mm 408 thru malt, Growth rate aUgests this is

too hish.

(143)

'-4

&-4

P-.

LC)

(144)

(145)

155-2413, 2430

tU -3630

Appedix IV

"am. yet.

3% inspection It not edequatc and full ltngth

is ed (tub shoot to tube sheet). Cifrent

rule reuire sequential 11. If ftlWs) are

detected. i.e.. If s rnthing is found, saple

aIoe Is Increaaed.

Aont of tubes ptugged in aster generator could

InfLumica titers renewal.

Should ham Incroased exalination progrs

after detection of tta: 3-V/2 years bet~en

examination Is mm poebe.

States that evalnation of cracks or ICA, etc..

shalt be performed by aalysis acceptabte to

regutatory sucrorlation. Appdlx IV rewite In process.

This section of ARE (section XI) my be

transferred to Section V. Section XI wilt contain perforoa demntration end qunlificstiwi rules. This could tek two

Years.

Naw. Rseutatory Guide

1.83.

Oetection nd aizing of SCC md ICA.

Mane.

-- Stem Generator
COLFUT|

( 146)

(147)

(148)

CORROSION (esntd)

REG. INSTRIL&IVET

tas

35

66

AMI"SFEATWRES

MI"tigate or- reckic item gwlsrgtor tate

degradations and rupture @.

(149)

(150)

(151)

(152)

6-4

1-4

"3) (153)

(154)

67 7

III Stress corrosion crackins in stem generator.

A-3 Stem Generator tube

integrity degraded 0Je

to watageadt stress corroeion cracking.

6-4 stem Generator tuie integrity dgraded duo to wastage end stress

corrosion cracking.

A-5 I

A-12 Laseltar teering and low fracture t(sednese

of Stem Generator and

reactor pW LWprt mteriats.

A-15 Cperation of LiR

results in slow corro- sion of interior motel

surfaces of the pri-

_ry coolant systm.

then activated by neutron flux mn circu- lating throup the

reactor and ptate-out. once plated, they c'av't Ce rved by plant

ester chdeistry systee.

LIFE EXTENSIOI

FEATUES

iCOULS 5

Noni.

i".

gn.

Sol.

on.

None.

For.

CaRENT INITIATIVES AGilC NiEEOS LIfE EXTENSIO NEECJS

mOLILial 6 COLUNe 7 CASUVA a

mons. 7 I

More. 7 7

Non. 77

oils. 7 7

oils. 7

7 ? 7

7 7 7

None. Assess the afficiency

of wster chesistry

syotee to met axtended

plant life.

TDIWAIS

COLU*I 9

Stem-line break with cornsequetial _Sal1 LOCA.

egradat ion of Intarel Apisrtoa cs in LiNe

^ Priority - LOW.

Stem Generator aqairments

Four Item Priority - MON.

Stem Generator Staff Actlwne

* Priority - LOW5.

Stress Corrosien Cracking of Pressure

Boundary Ferritic Stoels in Selected

Envi ronents.

Westinghouse Stem Generator Tkae IntWrity

* See REG-0371.

* Degradation decreed by conversion frr

Aaoepate to an all-voiative ester treat-

_ent. Denting which ilede to prisary side

streso corrosion ctntinues to be a probtes.

CE Stem Generator Tite Interity

See MJNS-0371.

Gagredation decreased by coniargion fros

phosphate to en ati-volative wster treat-

_ent. Denting hich lea to primary sidr

stress corrosion centinues to be a probim.

SWU Stem Generator Tube Integrity *ee WMG`0371.

Fracture Torgtneee of Stem Generator and

Reactor Cooltnt Pulp S ortg

* Solution d available in October 1983

with pubtlicatirn of UMEG-0577.

Priesry coolant systes deconteeinetirn and

stem generaor chamicl cleaning.

(155)

-- Stem Salsrator
(156)

Is"M REG. ldIlflTRU

CoLum 2 QDLUM 3

CiweORtSI (contd) OSIs (cmtd) 1-60

AMIW FEATURES COLLINN

Preeen.e of tooe object in ptItary coolnt syst can be indicative of derided

ractor safety syst_

reteLting from failure

or weiakning conit.

LIFE ExNE ION PEAIi OMRRElET IWITIATIVES AGIN0 NEEDS LIFE EXTENION NEiDS

SI . CLL.UW 6 CoLa I 7 CaM a

WeIETS

COUiPei 9

one. km. Lome Part Monitoring teta Priority - RESOLVED.

(157) 3.2

O") 5.37

lone.

orm.

new.

Reise of ptint

proceires/recorde

could Gin Iright

Into detleroratim.

Revis of plant

prororue/records

could gin insight

Into deterioration.

levis of pint

procedkree/ecr

could give insgiht

into detarioratimn.

km. kn.

tm. iM.

hne. Outity Aseraice decmntatlon ndor racerS

required to dhmw aid miuti deterioration of e

conm'mt.

Nmw.

Nt. (159) 5.3.10 km. km.

SUlVEILLAKE

(160) * TESTIN

INSPECTIO

* ItAINTERAMCE A

REPAIR

* MW! LEANING & REPAIR * RDEf

* INFMTIUJDATA

i tE9UI~~101111VEIITS

FREQUENCY

DATA CLLCTI

- DATA EVALUATION

KEEPIN

10 CFR 50 Survelllance Progra PNw progratic ProgrtIc cr1- Overal l guidnce/ critea- statdard taeH- type staiderd planning for aurveilthat coud, by Ref., being considerd by twnc prgrm. beoes a part oF NUPLEX for ntire 10 CPR 50 If It nuietar pLtnt und *t

are eatabLiahed comoents of concern.

by a etanderdes tr at reqneat of MPLEX.

This atanderd would *erve as a guide to a

nucleer utiLity in bee their demiplant-specifie program

pint It would provide overall guld nce for

ates generator Iase.

Suggested that this Prertic-ritCrterlr standerd bts a p enrt stanad and that

other deuohtsr staderd may be nseded to specify Ineptimn techniques, the svaluation

aid identification of aging mchanim, the

estabtleFlnt of special or erhanced mints- - pr m, mnd the developwt mid

ieptentation of recordeeping and trading

pragreg. Guidane couid *stt be provided separately for evelueting the effcts of pint

trewin events on _coponent Or Syatee life.

This standard is expected to be 0eed by nucleer utilitlee to eetabtiah a plan for aaseeang the feasibility of a pi nt life

extension proram nd for developing ind Implemnting auch a proge dere practical. It would aoist utility perannew in identify

Ing actiws required to preserve a pi nt life

axteion option aid for identifying need for quclpnt testing. Inpection, monitoring

and s nt. It wiii provide a frnmeerk for qddrasaing future regulatory requirNemta

- they sight f fect the extenion of plant life mid to eoart particular pint operating and mintenmece practice -e an Integrat part

of pruient pi nt ng nt.

(prepared by J. Christle for KIWIE Codei mnd Stnd rdd Su bcsittee.)

-- tem nerator
(162)

ismf REG. INSTRUMENT

COUN2 CXM

SURVILLANCE (contd) CiSc (contd)

TSe

3.4.4.5

AGINC FiATURES

Could lead to URC rule charges.

LIFE EXTENSION FEATURES

eq.Wires eddy eurrent one, not testing of sa U-tubes. addressed.

CiURENT INITIATIVES

CtLUM 6

iUPLEX Codes Wn

Stendsrds Identifica- tidon Nu r PWR.0 On stem Gienrator (44

coents). UPLEX I to be prepared.

1o.

None..

.on.

A.

Non.

Non.

AGING NEDS LIFE EXTENSION MEEDS COLUt 7 CxiU1 iia

N/A

CtlOMTS

iOLUIIII 9

escriptioni Develop UT teCInlqje And ISI

progrm for detection nd sizing of ftsr In stem generators.

TS reiles eddy ceurrnt testing of GA U-tubes. ICA effects on U-tbe weatt thicknsse crld be detected thoigh the came is not netesoorily

Inferred. Rieorting rooluiremnts would hve to be expsnod.

This TS r-res the reqir-ints oi TS 3/4R.4.0.S

(ASKE Section XI, ISI) to be applied to the Stem

Gonerator.

(163)

(164)

(165)

(166)

(167)

P-i

;la

3/4.4.10 ReWires ANE Non. not 3/4.0.5 Section XI, treetment addressed. for SO with regard to

mintenerre if Code Closs 1, 2, or 3.

3.9.3 Noterist Integrity. Reference Al Codes.

5.2.3 Corrosion end Stress. eons.

5.2R4 Generat. eone.

5.2.1.1 Mwst Met 10 CFR 30.55. NSo.

(i.e., met ASME Section III reqiireonts for pressure bonderies).

5.4.2.1 Overall Integrity Nonr. Referenee ASME Codes.

5.4.2.2 Stem Generator Tube ISI In-service Inspection

(GDC-32) Reference

to G i.il3 sod TO for esach SSS ragptlier

(E-ola0103, 0212.

0152).

6.6 In-service Inspection None. of Clas 2 & 3 caenents

(G seconrdry ide.)

10.3.6 10E n d clearing (Stem None. Geierotor shelt side) cith referentc to

RN 1.37 for cleaning. Alto 10 CFR 50 50.55.,

end Appendix A.

P4E

Yes.

Yes.

None.

Covers construction onty.

ASiE Soe XI requirmant, my not be odequete for deterloration.

Doen't adr-es specific issues; Section III ant be fotlajed.

W/A

(168)

(169)

(170)

(171)

Non.

Inepection Progrm to detect geing ies it

effective? onn't prnt aging.

Progrm bmad on 10 CFR 50.55 aSndetailed in Section XI.

Concernd with Class 2 6 3 cpnents, therefore only shell Ide of i;C. einly ref erences other docur ts to fotlow.

"Nne.

-- Stem Generetol
COOMENT IlS" REG. INSRIEISENT

S*WVILLANVE (contd) SRet (cxntd)

(52) 17.2

AGING EAn*ES M~as 4

Imlemet GA pi agreM.

Eddy-Curreflt of Tubes.

LIFE EXTENSION

FEATURES CURRENT INIITIATIVES ACING NEEDS

tOLUII 5 tttUOI 6 tOtUPIR 7 LIFE EXTENSIOA NEEDS Ct"Ui S

CuNENTS

Mutil 0

None.

geonitorfra.

SEP doe not provide an in-depth description of GA reqiremnt and doest address aging

per N.

(173) 1 .83 Rev. 1 PC 1.3* eVW. 2, Better equilnt nd beinr developed methods for defect

troe St_ Generator detection, characterit- Integrity Progrm. tim, md elttiin reeded.

(174)

(OMl,

1.NS5 No explicit reference

to aging; allows use

of ASKE proved ad IlC coX ct *pplI- cebte to Section Il.

1.147 No espicit referano. to olien; atows uss

of ASHE aeproved ad UEC code tee app l -

calbl to Section Xi.

Me RC Implies life NC revieslo sre extenslon by provid- md to Inotuee or Irn ecceptonce meth- exclude appirprite

ad forepproved code Cam_.

(ASK) _tenrts

eccepteble to eur

rent Cdoe Cas.

The NC inplies life NC revsieu we extanelon by preovid- _dr to Include or Ing acceptonce meth- exclude eppropriate od for approved Cde Coxe.

(APES Inspection eathod uing aua- rent Cede Coxe.

onitoring. ASK Section XI Speclt lorkng roup

develepirq prtforwce deometrstirn

reqwirmnlm for ET inrpections.

N/A

N/A

Netter detection ad sizing of defects eded eelaty for

Creeak.

Nore eccurate Informtion nreded on defect type ad size to pre- dict remining tube Integrity.

N/A

W/A

Rev.2 of NC 1.83 dees not ddres performeae drustratlon issues.

APE Code xes are rat _ndetory. Code Cam"

provide a mech*nim to use alternete methods within Juraldiction of the code. The cases

we usually stpereded (annulled) by revlelons to the code, I.e. the cne bI pert of the code. In other Inrtres. the cae y be reverted or dred as n applicable method.

ASUE Code Cases we not Mdatory. Code Cases

provide a _ nI Ism to uae Atternute methods within Jurlediction of the code. The cases

we usuatly spersaded anriutled) by revisimnr to the code, i.*.. the cAse becones pert of

the code. In other Instances, the case my be reversed or tropped As An appl Icabl, method.

)_4

C.e

(176) 1.158 ualification for

In petlion personnel.

Need methodology for qutifying ET inFpec- tors.

(177)

ASM

Section Ill,

Susection

WE

of

Requiremnts-futtstrength nd pressura

Integrity.

Nonr. Non. l/A xaw guide to cover limit of deterioration

is rd.

jules cowr coutruction roqirmlrnts but do

not cover deterioration.

(175) Section XI lieterit mnd co nret

condition assessnnt.

jet. Info.hDate Mm Nnmndietory beset e they apply IdhI on Record

to roiesc for xe ping bha passed

licee extersiorn/ the SWC-PEX.

rnermms.

tef. Info/data

bases to sepport

exteens/lronewets.

As materials ad caunnts age, the pradictive capabilities for p"yiat and inchnicalt property changes mint Improve. Since during a plmnt'a eervice tife An incrersing amunt of

Inforeetloredeta will be aRlable from

isaveittaneo progres, batter pro- ctee to eavluate ad ue. this Infor- intioxVdats mat ba developed.

(179) Suillanct. New baseline A n0M teok group examination on Beeline Eaxtreqhimnet. netion hls been estebliehed.

Evatuate * aw

beline examine tlon for license extension

reotjnts.

-- Stem Gerrator
COMPOINET IS5m AG. INSITM bD AGING FUATt"S COLUPIN I CbLex 2 COLUM 3 COLLOW 4

ilAEILLAUCE (contd) ASK (cantO) (iSO) Section XI Altows for Inopoctiol

beytrd 40 yers.

(l6t) monitoring mnd Testing.

(182) t nitoring and Testing.

(1813) Inforoet ion md Oate for trend cuave

projection.

(14) Fatige faitures.

LIFE EXtasalN

FEAIUES CURENT INtTIATIVES

aienas to Insec- SW bau tepc- tin PlRn A mid santed rsvisions to 0 ihich arm ur- Iht.24300 which rutty bted a *a Witt det the 40-year operating 40-year limit cur- tite based n fews rentty csntained In intersl, the ts Section XI. Also, of uidtch * 40. reviauing need ter ore freqent

inveptiora.

Infloratio0tVe Oavstowt of Tom for trand cuwves. *ai techiqes to

datect age-related deadstien nd

fetlIon beino

conridered.

InfotmtiVn/Dts Cnsideiring hydro- for trund curves. static testing

trends kitr change. or, needed

frr aging effects.

Records- SW Is considering

IformatirVOsts. develont of mstory ap xdia

for racoroeaping.

Anticipate nid Fails. monitoring evoid fttigus tachnolosy developed failwre. mid dmtratad.

Sevrt faciitie,

ae proceeding.

eon. RSeuiatory Guide 1.83.

830 5EEDS ULIPS EXTENSION WEW "INSI 7 Catlm a

Uttmied swrteitnie aveiIttnmc heyond

boyid 40 years. 40 yers.

=eleet

the frequeny of inspection should depmnd an the degrdadetion soheniss end the candition of the copent.

Into tion nid Dats.

Information mnd Oats.

Inforattion d Coto for trend cuavew.

Sxperlmc NWd toot detA for hiuh-cyle effects.

too.

Nmnitoting/tesing

honitarife~testins

tec ntru .

Xecords- this Appndiio uouid provide the InformtiondOts. utility mear etil guldmnce as to the type of rcords which su be beneficial In a otins a ticann satenrien

4eepAatary scoop ) Faileso mliketly from cycles considered tense of alternate in design. Dsaign approach Is coneervative. approach to design Coopont features InStueid to preclule basis fatigue faitlure. Coonents hava hidh

toltrarm. to flews.

b) Patlgue cracking hao ocurred drisg

operations:

vibration; rapid thert cycling; Pri-A1istiMO f lam

o ther coiditla not - -mdered in desiag.

tIssu ns isWtstory U inspection Is not edowate tid full tenth Guide 1.83. is needed (tubs sheet to Ute shoet). Current rules rewire socportiat Ul3. If fl Os) a detected. i.e.. if sNothing is fouAd. r ple site Is Increased.

15 M) t1tt-2500 .ons.

- Stem Gioator
(186)

(187)

(188)

(189)

(190)

(191)

Is" iEC. Ih5TRhENT

OL~t 2 tntu i 3

SUW iLtAtE (contd) ASM (eertd)

IWB-3510

I53-3512

ItS-3516

I1IM-3519

Ist-3520

IUO-3521

X.LR 4

Acceptone Standrd.

Acceptace Standd.

Accepturce Standard.

Acceptance Stdit.

Acceptance Standed.

rn.

LIFS EXtENtSIO

FEATURS

Acceptance

Standrd.

Acceptance

Stanbrd.

Acceptance

Standard.

Acceptence

Staderd.

Acceptance

St-ord.

es.

tl"RET INilTIATIVES ACINGi RlEM

etiLUiii A GU 7

kn. kM.

LIiE F S mEn

Eltuation iG tGide for ltelt.e indite- tie aid deteriora- tion limits should

be deterined.

Oest?,

mtUPIn 9

11".

km.

Rem.

Rm".

km.

km.

M.

m.

Aiiotbte Indication for Uiband Fto is an 405 through-wet(.

Growth re shome this Is too high.

nt of ttbe pted in a stem sr tor could vive VAdwI. for liens rentes.

(192)

s-I

a.r

flW-2413, 2430

(193) Iti-3630

(194)

(195)

(196)

Appudix IV

18

29

Rone.

k m .

He.

Visut exeairetion ts the peary mthod to

detect degradation by acid corrosion or

erosionfcorrosion.

Regulatory Ghide 1.83.

km. Yes.

M.

Should have increeaed emination progri

eft r detection of ftlea 3-1i/ years beteen exasinetione Is ew posible.

ten detection and Stein thst evatwation of cracks or ISA, etc.,

sizing of St snd ICA. Salt be perforeed by anlysii acceptable to regulatory authority.

Appendix IV rewite In puosss.

This section of AS (Section XI) oy be trateferred to Sectfon V. Section Xi will be

replaced with a perforane _Atration and qtleification uideine. This Is in the prons of bei written now but could take two year.

Stem-tine beak with consequntat Small A.

km Roating Dieredetion or Fature in nultear plants * Prioritty * Rit.

k0.

k m .

k m .

k" .

I

Reed NM for teating bolts aid studck Row the i npection

frequency or fraction

Inspected need to be Increpase for ntetdlife?

-Stm Cnerster
COLLM It iCOLUt41 2

PAVEILLANCE (contd)

(197)

AEG. INiSTRUMSENT

GMl (contd) 35

(190) 66

A9G F=ATIMES

CQLIW 4i

Loos Part anitorini

prograr.

itiste ,or raedc st generator tute

degra-ltion nd

ruoure.

Wtemant Tnbe

Inspections.

?

(199)

(20')

(201)

(202)

(203)

(204)

(205)

67

A-3

A-4

_-

A-S Nra.

A-12 Laster tearing ewd

low-rttcre toulm

of sttm*u gierator and reactor pW siWort

materiats.

A-IS Cperation of LkR

resultt in stIae corro- sion of interior matal

ejrfaces of the primary

coolant sy*tV. 'hi s

ar activated by neutren ftun udtn circulatins

throwlih the reactor end plate out. Radiation levels incrase In the

priasry systtm. thus

cosplicating routine inspection ani

mainteance.

USIA-47 Define generic criteri for plant specific

revies for stem

generator overfill transients In Pws wnW

reactor overfitts in

bms.

FEATURES

None.

Ra".

None.

Mons.

CURRENT INITIATIVES AGING NEWS LIFE1 EXTENSION WAS

COLUMN 6 K.CfLwO ? COLWWA a

a"n. I 7

None. 7 7

Nione. 7 7

lione. I7

Mone. 7

Arnie. 7 ?

a cn . 7 ?

aawe. Assess ispect of Increases In radiation tevels on Inmpaction

and minteaioe.

eTS

COLLONI 9

Degradation of Internil Apjrtenances in LItb * PriorITY - LOW.

Stem Generator Requirenuts

Foeu Item Priority - HtGM.

Stem Generator Staff Actions

* Priority - LW.

Wesetinghousje Stem Generator Tuts Integrity

oSee NUREG-0371l.

CE Rosin Generator Tube Integrity

o s awJft-037i.

iY Stem Generator Tube Integrity

* See *siG-0371.

Fracture T rousa of Stem Generator mid Reactor Coolant Pump S, ports * Solution mode available in October 1913

aitl piblication of UEcG-0577.

Primary Cooltnt System Decontamination and

Steam Generator Cilmicel Cleaning.

None. ? Safety Implications of Control System.

-- Stem Generator
WUENT ISSUE

tZIRWILLAMCE (contd)

(206)

(20?)

LIFE EXTENiSION KG. IiSTLMmT AiGIN FEATURES FEATIAXS CaRNTw INITIATIVES AXING KMU LIFE EXIENiSIWN NEEDS COLUM 3 CLUMN 4 OU CM M COLL 7 causi S

GSls (contd)

1-60 Prwoceof Loose MNam. oa". Perform trwd1 analysis

COMMENtS

OeUI 9

object In primary cooi

ant system can be indicative of degraded

reactor safety systms resulting from fatlure

or weakening cronent.

erae.

on loa, part monitorIrv data.

Loose Pert Moitoring Systma Priority - RESOLVED.

Ms

3.2

(208) 5.37 erone.

Nione.

Review of plant

procedures/record

could give Insight Into deterioration.

Revier of ptant

procedures/records

could give insight

Into deterioration.

Review of plant

procedures/records

could give ireight

Into deterioration.

None. mons. eone. ruatity Assurnce decawntation end/or records are required to shor end evaluate deterioration of a coonmat.

None.

aere.

Nen.

110e.

eerie.

(209) 5.3.10 gone.

i-4

;a-

- Steam Gonerator
APPENDIX IV

REGULATORY INSTRUMENT REVIEW FOR PRIMARY PIPING
Understanding and managing

aging of PWR RCS piping and nozzles

Materials Main coolant pipe - Centrilugally cost SS-Gr. CFBA and

CF8M (W), Tlype 30415 and 316S5 (ea W plants). SA-516 Or. 70 (CE).

SA-106 Gt C (11W)

Fittings Statically Cast SS Or. CF8A and

CF8M QO; SA-S1 Or. 70. Type 309L

SS (CE. BiW); ,Type 3051 SS (85W)

Cladding 1T" 305L SS (CE. B&W)

Type 304L SS (89W elbows)

Surge and Spray lines Type 315 SS, Cast SS -Or. CF8M

(surge line in some CE plants)

Charging, satety Injection,- Type 316 SS

and residuat heat removal

tines

Nozzles on main coolant * SA 105 Or. 2 (CE), Type 304N SS 01)

pipe

Sote ends Type 316 SS. Inconel 5-166 (CE, B&W)

Thermal sleeves Inconed 56&16

Stressors & Operationdi transients, temperaiume, flowInduced vibratlons, stratified

Environment lions, thermal striping, valve kge, and thermal Shockb

, wall)

Cold leg A- Cros

Reactor vessel

Typical RCS piping for W 4-loop plant

s-over ISe

Continuous roilecd 'Spot welds (4)

bead on sleeve

Typical nozzle-thermal leeve assembly for a W plant

sUNDERSTANDING AGING MANAGING AGING

(Materials, Stressors, & Environment Interactions) MANAGING _AGING

Sites Aging Concerns Inservice Inspections, Surveillance, and Monitoring Mitigation

Nozzles and thermal sleeves Low- and high-cycle NRC requirements Recommendations Maintain full flow In spray

thermal and mechanical fatigue Perform more frequent examinations line and operate It continuously Charging VolumetdC and surface examination of nozzle welds and horIzontal to prevent stratified flow

Safety Injection of 25% of butt welds, Including the piping welds having significant and thermal shock conditions following welds during each Inspection fatigue damage Redesign surge and splay line

Surge Interval (10 CFR 50.55a, IWB-2500): Determine fatigue damage by on-line piping by replacing short

Spray - All terminal ends In each pipe monitoring of pipe wall temperatures horizontal sections with sloped connected to vessels and coolant flows, temperatures, and sections to prevent stratified _________________________ to ~~~~~~~ pressures In nozzles and horizontal flow conditions

Terminal end dissimilar Low- and high-cycle thermal All dissimilar metal portions of piping subject to

metal welds and mechanical fatigue welds operational transients, Including Redesign piping to eliminate

(between carbon steel stratified flows and thermal sleeves deleterious effects of valve

components and stainless All welds having leakage

steel piping) cumulative usage factor Perform nondestructive examinations

equal to or greater than 0.4 and loose parts monitoring to Minimize valve leakage Surge and spray lines Low- and higth-cycle assess status of thermal sleeves Maintain smaller temperature

thermal and mechanical fatigue All welds having primary plus Develop use of acoustic emission differences between

Charging, safety Inlection, and secondary stress Intensity range method to detect crack growth In the pressurizer and hot leg

residual heat removal lines equal to or greater than 2.4 Sm base metal and welds coolants during heat up

to first Isolation valve Some welds are required to be Develop techniques to monitor actual and cool down

Isamecwelds auren requhIrsedction bedegree of thermal embrittlement in cast Inspected during each inspectlon stainless steel piping: Maintain smaller temperature

Cost stainless steel Thermal embrittlement interval Analytical modelling of Inservice differences between the

piping dgdtonpressurizer and spray line

Hot leg Coolant temperature Flaw evaluation Metallurgical evaluation tocoolnt

Ferrite content and (10 CFR 50.55a, IWB-3000) characterize microstructure

Cross-over leg spacing Lekg n hdottc rsueNOE to establish correlation Cro shoder lg - Chemical composiion Leakage and hydrostatic pressure between ultrasonic attenuation

Cold leg -Chemical compositiona tests (10 CFFR 50.55s, IWA-5000) and fracture toughness

Monitor valve leakage In safety Injection Fittings Cycle counting of specified and residual heat removal lines

design transients

Surge line (Tech. Spec. requirement) Develop UT to detect flaws In cast

stainless steel piping

rev. 4 stat
REGULATORY INSTRUMENTS REVIEW FOR PRIMARY PIPING

UIFE EXTENS1IO

Mr.. lIlNSTALET AlxG FEAIUES FEATtUES csuahr ItITIATIVES AGiCx IMDS LIFt EXTESUi OIEEOS

COLUMN 3 caOLUM 4 j S COLUM 6 COLUMN 7 caWL a

PlIPNG

(1)

'taB

* IACKEIW.SC

a. FERAITIS DIS.

SIMILARM ETALS OF SAFE E 58 * FATIGUE

a. LOWi CYCL.E FAIGUE b. TIONAL At - MECHANICAL. (SEE FIST? COROTr

OF COLUMs 9)

I~aSI

cTm

10 CUR S0 MkpIex codes and Standerds work.

Idmntify obvous

Chag" macil va SIC In NJIAG-0tIS.

Itimtinate applicaloto ulintentimnl embedde 40-year conmtraints In

Regulatory Inatnowt codas end etendorda.

Fatilue is generic te *1 t s of ptant, nd cames and "tent differ from plant to plant. It Is also recognized that now unwique e h prvblus de exist blt~. Pks nWd Ts.

Forty-year onstrinta do not apply to sit &sine factors; i.e.. fat Ig is a cyctlc pI R id could bame cemalve after 5 or 10 ywr of eperation

(2)

ISO

3/4.0.5 & A/.4.10 Mx. xmn . a whether

Section Xi ISI reqiremisareports ae dmiute vs. ialt ntsda owe attention.

monX ( commat). Cycles re recorded.

Nidit be _eful In evaluatins thermal prusaur cycle history.

- an wether Smctin Xi tit reiare- mns/raporte we adeqtae vs. w t ne

IN" Attntion.

Effective _ethbdt to sonitor fatius cycles

for magnitd and effect over ths cra- ponrant service lift.

This TS reqaires AsS Section Xi raclee-nts coecernin ISI nd MAintenrnce for AMC piping

IUW T.S. 3S4 4.0.5).

(3)

(4)

"_

314.4.9.1.1 Primary side thensel/ pressure cycles re recordai during xU

eat-up nd rcoldeown.

TS* All

SME

3.9.1 Meeting CTC IS: design with sufficient _nrgin. Also. ceC 12.14; 10 CIF S0. Appmidix I

(QC): 10 CFA 100,

Appendix A.

Nn. cycles Nameeilted with start- Ws and shutisw t a" recordad nW

countted

Section Xi A an 0W *rating Plant Criteria

is deveilping us non- _ tory appendixes to addrer return to service sittatis

dh.n TS hew been exrceeed.

EPxl-spxonred fatlia awitortnr ZFatigum- Pro could ilpact the credibility of 1S

cycle coont data. Fatieu-Pro Is reported to be a seusr of the severity of the cycles during operation. LO.. my oporating Cycles ae les severv then xseaed dwing the design.

(S) WmOn (except for initial sargins). xa. 7 Evelute tramients ued in the design and fatlie altysis.

(6) 52.1.1 mat met 10 CtF se.ss.

(I.e., met AM51 Section III reaire- xln for preseurs

bowdaI as).

M m . Ma. None. I iont specifically dram eny am i1swe ASJI Section fit, mat be followed.

G-nral Motes:

1. A .1. Indictaes further stuidy/frwetigation is needed. 2. for the Oils, *rootl0 eme the gtenic stfety isu Is ragolvad, not necessarily the agint is'ua. 3. for amnino of brevietlirn. ecry, nd Initiati, wsd throclhuxt, es scrall on pass xi, xil n d xwii of the report.

-- Primary Piping
COMPONENT ISSUE REG. 15STOLM15T

STRESS (contd) IRse (cofltd)

(?) 5.2.3

AGING FEATOUES

Calm.z 4

Review suitebility of Materlals diosoen. prfor tests (fracture

touimess). Review procodeMs, of .ssfectur

welding. S ectlon III 10-2500, -2550, snt

1- 2570.

LIFE EXTENSION

PCATUWES CURRENT iINTIATIVES AGING HEOS LIFE EXTE5SiIN NEEDS jals CO!LUMN 6 COLUMN 7 CoatgE a

111"s. ? I

catas 9

Covers Ott IeXctar Coolant Pressur kundery iiteffels

(a) 1.147 Xo asplicit referance to *gino; provides an IRC ecsptlet list of

toved ASU code

cases for Section XI.

(9) 1.85 No eplicit r tfereics

to eins; provides an WRC acceptabte list of

wprovd ASK codc cases for Section Ill.

AW

(10) Section Ill

CA3

me IG op(fees (Ife, Pf revslns aee

extension by provid- NNW to include or Ing actptam Moth- exclud epprotriate od for spproved Codo Cases.

(AWE) inspection

_ttod using cur- rent Cods Cse.

The PG implies life PG revisio n we extension by provid- ae to include or Ing acceptance seth- xaclude MpM iosts ad for approved Code cases. (SE) Code Case

Materias nd testIng accepotble to 55C staff.

Retqtificeiton A naw appendix Is

of Cents. undser considerstion ,hich Mey be ed

to rsqslifty ce- pMnlots which hav xceeded the rutes

for cyclic qor- lion In Section

111, 111-322.4. A task group has bean forsed to ejies the issu..

Ths elso applies to Section XI.

fatigue auive Section XI, V on revisions. Operatinf Plant Cri- terin Is reviewing

fatilus curves In Section ill to deteneine if they

can be revised to eNMdete ewr- tion bynd 40

years.

A/A

N/A

Evaluste ns apndix.

A/A

II/A

Seqiulficetion Rutol for cosponnts.

ASE Code Cases ae nt *tory. Code Cas

provide a _odhanis to uwe siteto sthd within jurisdiction of the code. The cas aes usaly superseded (mntalled) by revislo

to the cod, i.e.. the cas bece_ pert of the code, in other instances, the cas Mey be

reversed or dr Id a n MO Icaete Method.

ASK Code Cass se not Itory. Code Cas

provide a pechenie to we eteinso. methods

within Jurisdiction of the code. Th caes ae Usually suprseded (muttled) by revisions the cods. I.e., the cas Iacme pert of the cods. In other Instances, th cae way bh revered or dropped as an appliaeble method.

(11) Fatigue. l od oed-of-life proJections, 40 yor rd bod.

Studios we undor my to aeess the senuItude

of the effects of ectust swirormmnt conditionm. Code curvee are bed on moth pecianse In air *t roes teretu re. wemss

mteristl In sevice hov moch rouge r ="a s md ar OapOsd to flowing coolant et operating etu Th u al surf ces

e sis pow to creok Initiation. Studio and resarch to _ee mgnituds of effeet of enviramat fectors could result In rned for mm Regulatory fulds, Repittory inetru-

_ts ar'dr code revisiorn.

Priestry Piping
COMP(MEhl IWE- COLUMN I COf

SIRESS (contd)

(12)

(13)

(14)

AEtG. lIMSTMM&IiI

caml 3

AShE (contd)

Susection

teal

AGliilT FLALURES

CaLti! 4

Provides for design

toads affecting the

strength nd integrity of the presoure

botudary.

LIFE EXTEUSION

FEATURlES

COLMi S

aone-axplicitJ

provides rutes

for repair i/or

replaceant of

code conents.

CiRRENT INITIATIVES

COLUN 6

Section Xl Condition Asesosent.

TSO have been

exceeded.

Laaaitfication of Consideratil of

systa end co devetlpnt of new

ponaents. -rticle tIn-MS

Reqatitfication for

Fatigue Life.0

SiW on (peratina

Plant Criteria is

developing nu fnor

watory apandfxos

to ddres- return to

service aituatitiw,

when MS have bean

exceeded e

on. on.

ACll WEEDS

Cte 7

Sept led in the design criter ia (a comnts).

Condition Aosessment

Inferuetion/dete.

ions.

UtFE E=ctlhI NEEDS CaeEeTS

CLwta ii CoLLEri 9

Guidance Is need ASKE Code for Class I coeponents-piping

to cover the limits design required ahen corrosion or erosion

of rponant de erio- is expected; the piping thicknese shall be

ration. increased over the other design requireaente.

Tita attlowar shall be consistant with the

specified design life.

Rutes cover design and construction requiremanta but do not cover deterioration.

RLselification of

syst and c0sponnts

following expiration of operating license.

ime. PiJ pipe crecks

^ Priority - LW ESOLVED. ^ Corrosion cracking In taw-pressure piping

Is addressed In C-7.

? Detached thermal sleeves - The thermal steaves were Instatled In the safety injection sccsulator

piping nozzle connections to the reactor cootent

system cold tags piping. Found at bottom of reactor

vassete.

7 Long range plan for dealing with stress corrosion

cracktn in VA piping - solution available.

(15) "Is

14 C-.

(16) ?3

Cracking in hih pressure piping In PMes as

a result of corrosion.

vibratory and thnerml

fatigue, ad dYnric

loading.

Fetiiue failure robtla connected with

nozzLe-theral slewe

asotibes.

ICSC camed leaks In

heat-alffcted zeiss of

the safe-nd-to-pipe

welds.

MoM.

(11) W6 Nore. 7

(58)

(19)

(Not mod)

A- 10 VA feedeter cracking

dus to high-cycle

fat i ge coned by

fluctuations in water

tearatura within the

vessel in the nozzle

regis.

Mons. ions. gm feedater notte cracking solutitms vdor itproved repair

methods.

-- Primary Piping
(20)

119*

STRESS (cmitd)

REG. INSTRUMENT

GSIs (contd)

LIFE EXTENSION

MlIC FEEATATIES C UR HEATURES T iiTIATIVES AGING #ETDS LIFE EXlTENSION lEEDS mt~.i 4 6 m C S tOM 7 catm a CMENTS

C01t a

(21)

(22)

A-IS Operation of LIt re- suits In stao corrosion

of interior Mt Iurface, of the primary

coolant stm, then these prodcts are

activated by neutren ftux old dWn circutatad

throuih the reactor

ptate-out occurs.

A-42 Pipe cracking duc to

ICSCC of awenitic stainless steel

ceptibie to this by

being sanitized by

pst-meld heat treatMont or by seruiliza- tion of a nerroe heataffected oarf new aids.

E-6 Through-waLL cracks and fatigue crack

growth.

M. km. Primary cooLant syste_ decontminaticn _rd

St_ gaurator chemiecl cleaning.

U".

kmo.

km.

km.

Ianc. Iore effective lDE to

a*eure abenco of IGSCC. especially

wider weld-overlay repaired areas.

Evalrate nued to

replace susceptible

and/or weld-overtly repaired piping.

MOM.

Pipe cracks In 9iWs * Priority - RESltfD.

Loads, load cebinatior. and stress limits. * Priority - HIH. see uEG-2800 SupI.

Piping Smduerk Problm.

PIE Syste Piping

* Priority - RESOLVED.

ISI reseerch needs houtjld be Identified.

Assisted effects (Note: exposura rates in

ex-vessel c enents may be too low to

caus an effect).

i-. (23)

(24)

(25) DYNAMIC EFFECTS

* VIBATION * ITHERAL CYCLES a. THEifil AGING

b. THEIRMA SHlM

* EROSION

a. COMBiNATION--

EfOSIDH

EROIONi

3-25

C-7

k m .

km.

I

Cobinatios of faril- 7

catiorn stress ard wnviro"RelaL corditlen ae resulted in isolated Instances of

stress corrosion crack- ing of loa-pressure 304

piping.

Cas

10 CFx 50. Appendlix 0,

t. tt mid IV

ISI progre per AIE

Cods raquirnts.

km. None. ISI coverigs may need

to be increased. III criteria my be different far License

Ramat.

Prixsry Piping
COMENT ISSA

iXKUM~ I COLLWI 2

DYXMIC EFFECTS

(26) (cantd)

(27)

(2d)

(29)

REG. liRSTMEtiT AGilS FEAfTtSES

COLumi 34OUS' i

INS

3/' 0.5 Xor. 3/4.4.10

3/4.4.9.1.1 RCS thermi cycles are recorded during

heat-ups mid cooldomn.

3.9.2 Review the criterla testiq procsures

nd dynemic enelysis.

5.2.1.1 Not met 10 Cf2 SO SS

(i.e, met AM, Section Mii. red irmete).

LIFE EXTENS1OW

FEA.IE OURMNT INKIETWIVES AGING NamO LIFE IXEMNSION lEEDS

COLM CDUM cCOtie 7 axU am =ET'S

M".

M".

eor.

IOne. Depende on Thether Section Xi ISI repiremants/reports we mte vs. dast neede me attention.

eoM. Cycles we recorded. Hisht be ineful in the evelustion of therml

cycle history.

? Ntu.

Depen on wiether

Section Xi 11 reqireMontslreports an adequete vs. what needs wre attention.

NW need to evaluate thermel cycle history.

This TS reWire ASE Section Xi, requirent

concerning ISi and mintenance for all RCS piping that is code time 1, 2, or 3 (161 TS. 3/S0.5).

Assur tructural and finctional integrity unider vibratory loadings.

Doesn't rse specific Issues; AE Section Iti sot he followAd.

OM". tne. i1".

(30) I.147 io explicit refere to aging; provides en

itRC accepeaml list of AM15 aroved code cas spplic ble to

Section Xi.

a~

(31) 1.89 ho explicit referansa

to esing; provides an XRC acceptable Ilit

of ASK approved coed

cases applicable to Section Ill.

meth loiplies life la rAsila we mum extenslon by provid- to Includ or exclude ing ecceptance meth- appropriate Code Case.

od for aWroved (ASE) Inspection mathad using ,r- rent Code Ces.

The RC iptifee lIfe RC revisioas we ewde extaulon by provid- to includ. or eclude

ins ecceptmics mth- sppropreite code Cases. ad for approved

(ASlE) Code Case seterials ind

testing acceptable

to NEC staff.

V/A */A ABE Code Case re not mndatory. Code Cases

provide a mdanilm to use alternite methods within jurisdictiou of the code. The cases We usually Sprseded ( aislltd) by revision

to the code, i.e., the se becomes pert of the code, In other inutakcss, the cas my be reeys or dropped as n alI cable thea

NM Code Ce" we not mesdtory. Code Cases

provide a mechanies to use alterntet _sthads within jurisdiction of the code. The cases re usually Sersreded (1ail lad) by reviloins the code. I.e., tih case becom5 part of the code, In other instances, the cas my be reversed or rlopped as an alicable method.

5/A N/A

(32) AMESaction Ili

Subseotion

NC

Provides for design

requirmruts for ilet load, earthquake, vibration,

RV thrusts , ight nid the effUcte of thernl expermion nd contrstlon.

Mi explicit;

provldea rules for

rpair riWor repltcment of code conents.

ispiled in the design criteria. Guideice is needed to cowr the Ilimits

of ceonent deterio- ration.

AN* Code for Class I comqonente-piping design rauired dean corrosion or eroe0on is axpcted; the piping thickness ehall be

Incrmeed ovwr the othwr delin requirwnts. This allowance shall be consistent with the specified design life.

Rules cover design nd construction require-

_nUt but do not cer deterioration.

Primary r- Piping
DYNMIC EFFECTS

(31) (cofltd)

AEG. INSTRUMEENT

ASK (corad)

Section Xi

LI1FE EXTENSION AGING=NTI*ES FEA1tWN

Corrosion aid Erosion.

CURRENT INITIATIVES AGING NENDS LIFE EXTENMSION NEDS tOffllT 6llTAv COLL 7 CM" a

A ne SA en pipe 7

will-thinning has been estalished and

wilt review this issue with EPRE.

Pain wat of cnern

at this tips IS the

effect of erosion/ corrosion on piping

in neornucler eppli- cations (ANSI/AYE

*-311-1984). the Remaning Stra'gth of Corroded Pipelines.

tO9VNTS

.t10W 9

The suc principtlly applies to secondery system. not prim".

The Section XI S~group on tolastructive Examina- tion is currently developing a Code Case and non-

_IStory n dis on UT Detection and Mesuremnt of Erosiantorroseon.

ANI11/ASE -1G-1v nal for Determining the emtinin Strength of Corroded Pipelines,5

ddrese non-nueteer applications, but my hew application to nuclear ccments.

(34) (Not used)

"ts

(35) 14

(36) 73

(37) 86

Cracking in high pres- sure piping in PFAN es

a result of corroeion. fatigue, and dynpmic

loading.

Fatigue failure probtkef tcnnected with

nozzie-thetml sleeve ass"eblies.

IGSCC-c uud leeks in heat-affected zones of

the safe-end-to-pipe welds.

Uwter hmer incidents

involving stem gWaier tor feod rings and piping, emrgency core cooling system, Rim

system. contairnent spray, service weter

feedweter and stem lines.

None.

Nons.

hon.

on. Detached thermel Sleeves

* Thermt sleeves mIntalled in the safety

Injection accumtator piping nozzle connectiont, to the reactor coolant system

cold tlo piping. em found at the bottom of reactor vessels.

Long-range pltn for deating with stress corrosion cracking In SM piping o Solutien available.

1on. ene. PuA pipe cracks * Priority - tlW. PREStVED.

* Corrosion cracking in tow-pressure piping Is adsrssad in C-7.

None.

*Oon.

None.

(38)

(39)

tlot used)

A-1 1on. uater hmr fESOLfD 3/158.4 with pmbtication of

1EC-0927. (Colett resolution of ltl water h er protblm rntine se a ded teble question.)

Primary Piping
COPOEN IS"U

tDLL I COLU411 2

DYSSIIC EFFECTS

(401 (contd)

(41)

MG6. INSTMA*NT

GSIS (contd)

AGIING FEtWS Ca =i 4

ItFE EXTEN 101e FEATURE:0 OURRtNr INITIATIVES AGING NEEDS LIFE EXTENSION NEEDS COMMWST

MftI- 0

A- 10 6SW fet .tr cracking

CAs to hilgh-cycle

fatigue cased by fluctuattis in meter

tIFr&ture within the vssel In the nozzl

region.

k-l Ciperation ot LWt resuits In strl corro- sion of Interior eetel surfaces of the primry cool nt system, then

thee produts re ectivated by noutren flux and Wmn circulated

thrcsgh the reactor

plate-out ccurs .

on. Nn. PA feetdwter noute cracking.

Here. Ne. ? Primey coolant systes decontasinetion mnd staae Generator edical cleaning.

t42)

(43)

(44)

(45)

(hot used)

(Not ued)

(Not ued)

(Not we d)

(46) STOWCURAAA INTEGRITY * PACTUhI

* TOUGHINESS EM*ITTLEIIEaT

* TNEEIINL

* SEISMIC (OAMAGE1 FAILUnES

* LANGE11, SNUBMSaS AND AICCES

(47)

(48)

£185

10 CFR So,

Appendix A,

General Design

Criteria (ODC)

Provides printipel

design criteria for the testing and per t

requirenta for

ronents.

tr. xn. M/A, doennt chane over tim. Does the existing design (generic or specIfic), _eat the acrrnt (present ti_) acceptable

testing ard perforeente standarde for life ex- tension?

Appendix A, Design of crqwnurt,

should he bcc tighod with censideration for netural phenome.

euch me esrthpukes,

tornaes, end flows.

Design Is based an historical date

from the tim of original license;

sacafacy nd inforaetisn my

have been altered.

N-.

N-n. £ew~irafiits May change

ver tit. gtrtwal5

events mY slte thet design bse.

kn. Depends an adether

AME Section Xt ISII rowirments are

aedqmt vs. what needs more attentin.

Anslyse of currant kawn conditions as

applicable will be requird.

Depands an bhether

AS, Section Xl ISI,

raqirmusnts are adaqate vs. chat nnedx Ost attention.

Generic or site specific research my be Criterion 2 necessary.

this IS requires the requirmnts of l.S. 4.0.5. (ASK, Section XI; 1t1) be applied to RCS piping.

asS

3/4.0.5 & 3/4.10saw.

- Priesry Piping
CayU I toUM Z

STRItETUAL INTEGRITY

(49) (cntd)

REG. INSTEW"ENT

COtUM 3

TSs (ctntd)

3/4.7.9

AGI*G PEATtWES

Reqires periodic testing of gaiters.

LIFE EXTEuSIOi

FEATuRES CURLENT INITIATIVES MGING NPS COUMz 5 aCttl 6 aOlLt" 7 LifE EXTENSIN NIEES

CuOtUM a

Could be modifled to asure records wer

adeqete for Lt

s wnt.

teLr 9

Non.

(501 Ts5

None. ight need to e and to Include deed weight

swuports. ndiors, ate., of necessary.

Inspection are to be the bis for Pwoor evelation.

working troup on rW orating Ptant Criteria;

a proposed addition to Article IU-S3l00 of Sctin XI uoutd contain rutes and formulae for performing in evltuetion of e cnsnen se

fitness for continued service ten either

lSe or ltemnts of its conatruetiouv design lieitation hbd been exceeded.

This TS reuire periodic functional teting of

Snubers.

(51)

1-4

ko 052)

(53)

(504)

(55)

Se

3.6.2 Rlvaeu origtnel systa

design adequcy

STP PEN 3-1 Stress sd fatigue

imits; deAlgn retuire- vnts; Inspection of

wde.

3.9.3 nd Reference to ASPE

33.93, Section III and DC

Appeix A 1,2.4. M4 15.

5.2.1.1 mast _st 10 CPA 50.55a

(i.e., Wt ASE.

Section tII, requirements for pressure bosateriae).

5.4.3 fleting requirsents

of SRP, Section 3.9.1,

3.9.2, 3.9.3, 5.2.3, ntd 5.2.4.

Yas. Nono. Non.

Non. None.

Neinty concerned with the consequnce of a pipe brak (pipe whip and Jet forces). BY knowing wirs aid how a pipe is met Likely

to break, lopties providing adeqate design _argins to prevent such carreses (i.e., the piping Nyotem Is analyzed thorotughy).

Brake ar uuanty at points of high stress nd ftigue (terminal ati ad nozzles).

Loading cmbintiton, systin operational

tralsient*, ad stresa limits. Nene. (exsept for original design

arginr).

oae.

MOM.

NOne.

None.

Non.

Non.

None.

056) at

1.31, Rev 3 Controi of ferrite in stainless steet otde to limit eferacracting.

bnt. Define level of ferrite Determine life expec- nd to resist nvi- toncy of wmd overley

rorsentattry rsisted repairs.

cracking.

Intent of EC 1.31 _sn't to specify ferrite

level ned to reist erecting. Reits from 6PTI MP T302-2 suggest currently accepted ferrite levele my be too lam.

-- Priary Pipite
CEWVQMT IS"

COL -- LxL

STRLU1TnU" INTEGRITY

(5I) (contd)

(58)

(59)

(60)

(61)

(62)

REG. IMSlImAT AGING FEATURES

CowLN 3 rcOlLM 4

RS4 (contd) 1.46 Protection eairst

pipe whip inside

contairnmnt.

1.147 No explicit rhferecs

to uire; provides an

tRC acceptable list of AE aproved Cads

Caels appicablo to

Section Xi.

1.46 Design nd eoading

cominatteon for seismic Category 1,

fluid systan cownas.

1. aS no expticit referenco

to aging; provides an RC acerptable list of ASO approved cr

Coasts appitel@ to

Section 111.

AgE

Section III Provides for design

suixection rectutraernus for he ibpect ltod, orth11C qjse, vibrations, KV thrttts, weights nd the effects of thermal

expaenion and contraction.

14 Crackirn In high pra- aura piping in Me5 an a resuLt of corrosion. vitbratory nd thermal

fatigue, Nrd dppasic

loading.

a'

LIFE EXVENSIO

FEAnleii CURREN IXITIAIIVES AGING MuS LIFE EXTEMSIO KEDS cat w 5 COLuM 6 COLlil I COULN a

wilthdrwn 3/1/M. a"n. See 3.9.2

The MG isplies life xC revisions art _l dA MIA extenion by provid- Intiude or exctide ing acceptance math- appropriate Code Cas. ad for approved

(ASI) inspection methed using eur- rant Cde4 Case.

wil thdrawn 3/1/VM. . S.o SxP 3.9.3

The CC tpties tife to revisions are "e extesion by provid- to inctiue or ecltude Ing mpance math- appropriate Code Cases.

ad for approved

(AE) Code Case

motrilts and testing Acceptable

to Mc staff.

Mo exptcit;

provides rutee for

repair anidor

replacsount of cods cmonants.

K/A MIA

ims

WilJIM 9

Cast Mtsinlass Steel is a Generic issue in primary

piping syateas, i.e., flanges. pW casing, etc.

AE Cade Cas ar not eNwWtorY. Code Cat"

provide a machantas to was alternate asthoda within Jurisdiction of the code. the Cae re usually uersbd (isaited) by revisions to the code. i.e.. the case becoms part of the code, in other Instancesr the cs may be ravarsed or dropped as an pt licabte _thod.

Med Cade Cases re not madetory. Code Cases

provide a madisnias to ume alternate _sthods

within jurisdiction of the code. Th caes re uwsuly sperseded (neetled) by revisions the code, i.e.. the case bvcos part of the

code, In other inotances, the case my be reversad or dropped As an applicable mathod.

ASI Cade for Class I coponunts-plping design, reqires dn corrosion or erasion Is expected the piping thickness shll he increased over the other desin reuir anta. This allowance ehalt he coruistent with the specified design life. Rules cover design nd construction requirents but do not cover deterioration.

Pvt pipe crechs Priority LOW. U /IS.LI ^ Corrosion cracking In law pressure piping is addressed In C.?.

b-J

C0

no led In the

bsign criteria.

Nokm.

6uida Is nede

to cover the limits of toeponewt deterioration.

xore. None. "one.

(63)

(6)

Long-rune plan for dealing with stress corrosion cracking In VAS piping.

Piping review comittee recomendetiona . 'No aignificant cag in put1ic safety witt result fram resotutionf this Iseue.

119 o n . Xone. Mao,. None. M1".

- Primary Piping
UFE EXTtVSImN

cap" MT I REGaf . hNSItUENT AING O fEAIEO FEATLNUES CaLRRENT IiIATIVES AGING LIFE EXTINSIN NEEDS

Gan I COLllt 2 Cr COLUM 4 CCCUJ 5 UN 6 OLW 7 COLUIM a

SITUIIAU INTEGRITY G 1s (contd)

(65) (Comtd) A-1 ater ir Incidnts ibns. Non. 7 7

iivolvini ates Samrator fed ringS NW

Piping. emergency r

cost ings ystem, OHN

eyetem, centai Pto

spray, service weter feedter nW stem

innes.

(6) A-if Om femchter crereking l . b nra. 7

Oe to himih-cycle

fatigue cammed by fluctuations In moter

terature within the

vassal In the nozzle region.

(67) A- Is peratien of LW re- thnr tons. 7 7

sults in atom corrosion

of interior Metal ur- feces of the primary

colant system, tn thmes product are

activated by neutron

ftus and whon circutated through the reactor

plate-out oc"".

(6a) 4-42 on. ions. o. tons. tkw.

(69) *-6 Nong. o, lins, ge". gone.

(70) 5-25 7 lons. I 7 7

(71) C-7 lone. 50n6. gene. 7 7

COIla 9

waterhe r

* tSocn 3/15/84 with publication of

11MG-0927.

mm feedwater nstzzl cracking.

Primary coolant evetm decentaminatien and

stem gnreator Chemical ceaning.

Pipe cracks in WAS

* Priority - RESMVED.

Loods, load combinations nd stress limits

* Priority - 5IGN.

Piping ienciwark Proems.

P"a ystas Piping

* Priority -ISOL.ED.

C-4

I-A

Primary Pipinr
COMPONENT ismE

WATERS GSENISTRY

IPIURlITIES

*INTERGRAMaLAR

ATTACK (lOA) *CcjiBMAT I O--

CORROSIONEDSHMIO

*IsRanAllAIO

ASSISTED 5.2.3

EFFECTS

(INCREASED RADIOLYTIC DECaOS MITION OF WiTER)

REC. IibSTRirgNT

COLUMN" 3

Cf

10 CFO 50,

Aeodis A

General Desigs

Criteria (CDi

AGIN6 fEATiRE5

cd.aui 4

Provides principal

design criteria for corporent testing end perfornce reqwirrts.

LIFE EtIERSIGI

FEATURES CURRNT INIITIATIVES AIIGBE EDS =ii70

iorn. MoMu. B/A. doeen't c~e

over time.

LIFE ESXTIB51i IksS

Gos the existing

dniu gnleric or speIfic). met currently

acceptable testing end

performance stuoierds

for litf extlenion?

~gcis SSLIMM9

(73)

174)

TOO

3/4.0.5 & 3/4.4.10

Reqwires ASEK Section

Xl ISt for code class

1, 2, and 3 crtents.

hon.

Mon.

own.

Mwn.

B/A

3/4.4.4.7 Requires chemistry I/A

control of the primiry

(RCS) coolant.

Depmna oan wether

reports/records of

AAIE section XI, Mre

dqeete to be w"ful.

RCS ater chemistry

records are retained. Perhaps useful In

evalusting piping his- tory with regerd to

(RCS)

this TS reWireu the requirments of T.1. 3/4.0.5

(ASKE Section Xl ISII to be applied to code class

1. 2, 3 piping. (hate: closs 2 & 3 are Generally not primary systems.)

KC chemistry limits are show below. Are these

adequte for the corrosion lIeu?

Steady State

Paaeter Limit Trani nt Cialt

(dissolvd 02)* 4.10 AN 0.00 Wm

(Cl)5 .<0 15 p '1.50 ppe

A i^ t . i4s *S .2 5P 50 Wm

M/A if RCS temp. is -250-F.

I-.

I'M

(75)

-S

5.2.1.1 lst met 10 CFR 50.55.

(i.e. met ASE

Section III reir.-

ments for pressueboupdiae ).

Revie. suitability

of materials chosen.

NiOE testing per ASNE

Section I, ii-2500.

1on. Bor. Men. oan et address ecifIc issues; ASiE

Section II at be followed.

(76) 5.2.3 Born. 7 ge. Covers slt rector coolant pressure bouxbry materials.

a" (77) 1." Process controls to

minimie sensitization

in stainless ateet wetds.

Bor . ione. Setter understanding of retltionship

tween welding process eWd sensitization.

iGternine life expec- tancy of sen itized

materiel *nd rAeisergrade stainless stOel.

MAC Prorr_ on OEvalnution of tillded and

Repair-Welded Staintess Steal for ULW

Service Initiated work in this er" but was

not coepleted. A well dfort My be ongoing.

-- Prioery Piping
COMaONET IS"M

CORMSoCIA (coitd!)

(?S)

"a6. INSTIMEMT

SON Ccantd)

1.56, Rev. 1

LIFE EXTENSION AGING FUTURES FEATURES OMURNINIT IATIVES

Cantrotl vof ter 1P". CcL i. rogorm an MA*

puri ty iNMI15. pipe crack rmSodies.

ci9)

(AG)

AIMI

Section III

Subsection

awl

NC

14

(81) 73

Provide. for desin loo affecting the

strength and intgrity of the presasre btndry.

Cracking In hish prae- s" piping In Puts *

a remutt of corrosion. vibratory and theret

fatigue* and demloc loading.

Fatigje falturI prob- tm eenneted with

nmtle-thett Stoe .asethliee.

IGSCC-csmd ltee in heat-affected onne of

the cafe-ahd-to-pIpa

Stree corrosiod cracking in stem _ terer.

"GM.

Ne.

Ne.

Ottr nowtod" of affect Of ipurities

an cracking.

141 led in the deslgn criteria (aes Coents).

1one.

(azi 86

Man eaplicit;

provides rute foe reeir ndor replace- ent of code

ceanant$-

Nn.

Ne.

None.

.ono.

NorM.

"One.

M.

Mn.

NOM.

Nam.

Nam.

ttFE EMSVIONg INEEDS W TS

Cltl B _ NES 9

Life epectancy of 1 1.56 limit. enly coithtivity, pil ad cracked pipee on Chloride content of water. Other apecies

presune of isp-itles. need to he cuwidered Secant recearch

amegeete lifits y not be tow enouh. a*RE-0313 inclesbe guidetinre for 5WR piping

(IGSCC sitigation).

Cuidence is nd AN Cade for Class I cments piping design

to cower the tinits rqired then corroeson or erosion is epected;

of compnet deterio the piping thickness ehelt he increased ovr the

ration. other design requirents. This attloence shall

be coiatont with the specified desigan ife.

Nutee cover deain and construction rajireinnts but do not cover deterioration.

liw. P1A pipe cracks

* Priority - LO. RESOVED.

Corroieon cracking In ltwpreaure piping

Is adreasa in C-7.

7 Detached therial sleav

* Priority -

^ the thert see Ins talled In the eafaty Injection accumistor piping mnle

cornectiena to the cold teg piping were

fotnd at the bottem of reactor veesetc.

t Lon-rase plan for deating with atress corrosion cracking In PAi piping.

* Solution availeble.

t Stros corroelon cracking of pressurm Hunabry ferrItIc stsil in selected

anvirom rts.

None. Piping review c ittee recudetions - fto aignificant chawe in ptblic safety wilt result

frin resolution of this flws..

Nam. Water hemor.

Name. KR fhedater nestle cracking.

(83) lit

(54) 119 N".

Nm.

NOne.

Ne.

Na.

flr.

(M5)

(86)

A-i

A-10

Primary Piping
(87)

CORASION tcW~td) Ills (cantd) A-15

LIF E XTENSICO CRSN AGING FEATMI*S 941*1 *M I IVElIS AGING NOEM LIFE EXTENSION KOS1 tC.UiW 4 (JLL 5 CLIMN ttiUM 7 tG iii a Comm'Ts

COUSIN 9

Operation of LWR rM suits In slow corrosion

of ainter aosmtal surf acm of the primary coolant system. Oen thus. prjutsN awe activated by nasatran lima an shenf circulatad

trugh Ome reactor

plate-out ccurs..

hem.

None. hons. Primary coolant systsm dscantasinstlio and

stem Generator chasical cleatnin.

(SO) M". Ne. NE. None. Pipe cracks in WAs

Priority - eSOLVE0.

(89) 8-6 ns. W". bore. ne. Load&, loud c InbtiOW, old aCres. limits Priority - Mail.

(90) *-2S Ne. hone.

(91) C-? a". NE. 161 . Pit Syom Pipins * Priority RESOLVED

(95) SluNGILLAOICE:

* 1111189

* IMaPECtIati

REPAl AS * IN8

CTs

10 CfR SO,

Appenix A,

Genural oesign

Criteria (UC)

Provide. principal

design criteria for the txsting and per- foracs reqwiroents for coonints.

Ne. bo. V/A, dIeIn t cha

over tim. Ooe. the exlatins deelan (atwric or Specific) met aur.

runtly aept-bl testin aid perform- mace steviards for

life Nxtanieon

Anlyue of current knzAn emiditiorn a

epplicale will be

"Wired.

(93) Appidix A. Design of componta Criterion 2 should be accmpished with considaratlon for natural phauoir

such as* etthqakes. torndoes nd floo.

Oesign is booed an hlstorically data rrm the time of original license;

aceuracy am inforsution my have

been altered.

Noew. N jirsr nt my r cherwa

oWr tim. "sstura nnt& my alter the deslgn base.

Gonvic or site specific research my be necear .

(94)

TOO

3/4.0.5 & 3/4.10 R*sjres ASE, section xi, treatmt of piping with reard

to mIitrnce and ISI if code class 1, 2. or 3.

.s. NE. a/A TS requre the provialens of TJ. 3/4.0.5

(ASE, Section XI. Insrvice inspction) be

apwlied to Code Class 1, 2 * 3 Piping.

-- Prisary Piping
LIEEXTENSIGN OMMlTS is"1 PEG. INSTOMTE Mi1sS FUAURES FEAUIWES CURRENT INITIATIVES AGIN NEEDS LIFE EXTENIiON lEMI

(95) SIBVEILLANCE Ccontd) TS& (contd) NIPE. 12-4311 WILX report to be prepared an reactor coolest press~ue

bourdmry piping

(me soments).

(S6) 5.2.1.1

(97) SZ.4

WIIt met 10 CFt 50.55a tl.*., met ANE,

Section III, reqiresnts for preemie

bosoiderles).

Reire III Progree af

MO (CUC-32) to s the structuretl teak- tight Integrity.

leptnmt OR progur.

Visra Impection of Intruint lines.

Systus for detection

of toek eg In the M.

None. Moo. Non.

ton.

(90)

(99)

(100)

17.2

1.11

1.45 t-i

U,1

(101)

(102)

1.5a Rev I Osullfication for inpection personel.

1.147 Mo expticit re es to aging; provides an iC tccept lbt list

of ADe opproved coce

cas e plicble to Sectiot XI.

XNa. ? "na.

MonitorinQ. Mo. gone.

Mono. AWL devt t Correlate teak rate of aceaitic leek with crack size to aonitoring. dbfina acceptsuce

theits.

IAtitoritq. AKE Section XI Better detection wd

doevloping criteria sizing of crack-typs

for perfohece de- defects. stration qultiflcation

of Inspectore.

The AN pItmis life S1 revisions oe sede V /A ettnsion by provid- to Include or excluds Ing atccptance meth- propriste Code Caes.

od for approved (CAE) inpection

Muthode uing surrent Code Cas.

10".

pone.

etter training met qualification procedres. Io vd in- spection mthod for coers-grln _terisls

(wide, east 55, etc.).

N/A

uN s

eme 9

Description: Perfoen walt thickness trrelqng on

prinary/aecadary pipinE syste. Aleo requ.irewnta for tronalont niiitoring of priesry pipinq highstress tocationa snd theret dty. Estabtloh piping vibration and dnric effects nt piping/stidin spprt locatitna for war/corrosion.

Could toed to ISs modificationa of PeC rule changes or codes mat Stantorde.

Dosn't ad*e"spepcific issues; AWE

Section III at be folltead.

Based on requiresents of 10 CPR 50.55. ard detailed in AWE, Section XI.

Ooennt dees aging per a; just states

that a CA progres s required.

AKi hoe devetoped in acotatic leak moitoring

ystn f roe taboratoy experiownts. The sys- te n field validetion.

AWE Cod. Case we not mntory. Code Caes

provide a mcluonlo to ue alternate athode within juriadietion of the code. The came uially uwe aepersedad (wuttld) by revision

to the code, I..,* the cue becom part of the code. In other inatonss. the cas my be

reversed or dropp d ee n ppticabt _ethod.

Prhery P- Piping
LIFE EXTENSION

CO"P111XT MA0 55. IMISTALANMT AGIMG FEATME FEATURES CURRMN MINITIATIVES AGIMG humD LIFE XTESISION KOS

QW I a COLUMN 3. CZUMtIM 4 ......... AKM.L..... C)j........ OLa 7 C OLUMN a COMMETS

MLoo 9

MS ILLAMCS (contd) R0c (cantd)

( 103) MUReG- liol USPE-12-4240 MOEX rport tO be prepared an rtsctor recirculation tines

(see crnts).

Dcesriptinmi iner eas rceircuattion piping

inspection Intervts nd pereontaee to

cr ply with tAtai1Dol. Dewelp crack growth 1uvee for motonitic xs in SiC uwirroent,

considering 1121 nd other wld tretLmnts.

DewLop nrpectiraV ntoring prorvin for

thetI aerittlemnt of duplex cast S5 pmp nld valve bodies.

Early plants deeignsd to sieplif ed criteria

of AMEO VI II rd WS. . (104) ASK

Section III

5-3600

Codr rqwirmnts updated to Inceltu

transiont cnsideratons starts4 testing for vibration and thermal diSplact ents

rqui red.

(105) Section XI lMIterial nd cero- ef. Info./dots nwnt cidition bsese xx they Wpy

28aes$MKt. to raqasats for

I cence extension/ raniits.

Mo nonndetory Sam other cotuirs. appendix an record- keeping has passed

"C-PtLE.

xdf. Intfo/dot bvee to im rt

extnsiau/rurraats.

As natarialO MId cQ.Wits ao, tht

predictive cpebilitias for physical and mchanical prtperty chne ant Improve.

Since, ruino a plant' service life, n In- creasing _ t of informatiaVdats will be

eveileble frow surveillante pro"rS better procxduree to evaltute end uss this Informtion'dets can and mat he developed.

(104) Sutveitllnce. e.. basetlin Smi- A nw task Mrip an See other columns.

ration rouirommnte. besetine eSamination has baen astebtishad.

Possible need to re rair A now basetine

eamination for a ticonse extenion

reqIust.

(10o) Altlow far Inspae- tioer beyond 40 yevrs

Ch(nse to inupec- PA has ioplinnted 'xtended nd*or

,tion Plans A And S revisisne to ttA- arionced surawiln te

which ae currantly 2400 wshich Mill beyand 40 yer. based an a 40-year delete the 40-year

operiting Life based limit currently conn four Intervals, tained In Section XI.

the m of which Also revieSing naed * 40. for mre frequent _ nd

extensive inspections.

Suveillane beond 40 yeas.

(106) monitoring And testing.

Inforatioidsta Deval4 t of now Information, data, for trend curves. axm technilrms to aid asasoeants. detect see-related

daoradtion nrd fatissa being cansidered.

Itcorda, ineorem A t is coreidering Inforemtion And date tion/data. developnt of a non for trand curvs. mandatory Appendix for rfcr, dFpinr.

hanitorinefteeting

t -ehnu.

(109) Information and data for trind projections.

Records. InformationV

dots.

This appendix amtd provide the utility

with ouildne as to the records needed to

muprt a license extension request.

-- Primary Piping
LIfE EXTENSOlN

OEgMP t ISCJE RG. INSTRUMENT AGING FEATUEIS ffUNES

t XUM I COLUMN 2anu~l 3 EOL"n 4 COtt= 5

SUVIUANCE (contd) ASME (contd)

(10) Fatima failures. Anticipate aid avoid fatigue failures.

CL0M T INIIIATIVES AING NEEmm CIUMt e _ COLUNtt 7

fatigue monitoring iEperience ad test

tedIlogy developed dat f or high-cycle

NW d troted; effects.

several utilities

poe aiing.

LI Ft ttte NEEDS

tgulatory accptance of alt te pah to design baees.

COMETS

COLUMN 9

a) Failures unikely from cycles considered In deaipn. nseip a h is caw rvativa.

Cronent features loltuded to preclude fatigue failtur. Ceononta have high

te'ree to floa..

b) Fatigue cracking ha_ ecurred eirnq

operation:

. vibration

* rapid thiet cycting . pro-existing ft_ . other c 1dtio nrot conaidered In deign.

W14 (111) 14

(112) 73

(113) 86

Cracking in hig pres- eta piping in PW* as

a reault of corrosion,

vibratory wd thermal fatigue, and dynmic

loading.

fatie failure problet connected with nozzle-thermat ateen wzseetlIes.

ICSCC-camed tlek* in heat-affected zone of the asfe-end-to-pipe

wide.

Stress corroslon crack- Ing In SteiN gaertOr.

am.

*OM.

Non.

Mom.

Mom.

None.

3mwe.

3mwe.

Nn.

Non.

Mom.

M".

0o.

3m.

Wm.

Detached thewt elev *l - The thermat atevm in teliad In the cafety Injection accumulator

piping nozzle connuctions to the cold tl piping asia four at the bottom of reactor vessels.

Lonw -wne plan for dzaling with stres corrosion cracking In GM piping -solution available.

Stres corroeion cracking of prssure bwkery

ferritic toelts in Selected awirormehto.

3mw. tl. Pull pipe cracks * Priority - LW RSLVED. a Corroeion cracking in tow-prisacre piping

is addsed in C-7.

(114) I11

(115) 119 Nam.

Nom.

Gon.

sae. Piping review cmmittee io3 tiomn - -No significent chang In pubtic safety wiit result from resolution of this Iseeone. vater h .

Nn. M fllOI dter nmzzle cracking.

(116)

(117)

A-1

A- 10

-- Priery Piping
LIFE EXTEISIM CUeQEXT Is"J MEG. IMMANJENT MING f&ATUMS FEATURES OUSMii IMITIATIWES MGIMIS VME LIFE 6)(rsINi lEWS

SABEILLAIC Itmond) "I1s Ccontd) (118) A-iS ~~~~~~~peartlio of LUR r.- hnm. kmw. muits in slow corrosian of Intarlor mmctl Sur- faces of the primay coolant syat.m thai these produts we

activated bi' neutron fluxt NW m~en circulated through the reettr Piae-cut occurs.

(119) ~~~~~A-g2 hoe.b . pam. Mine. Mons.

(120) 1-6 hone. ha, lione. Nomw. Nam.

CDLUMNi 9

Primary Coodmnt sAt_ dacntmintlrn -d

Atm Or tator dwalcel cleaning.

Pipe crocks In ism

' Priority - AESID.

Loads, lead comtination5. aid stress limits Priority - A101.

Piping Sntimark ProEems.

Pg System Piping

* Priority - RESLIOD.

(121)

(122)

3-25

C-7

bons.

hat.

Momo.

ah. 'man.

O-4

I-.

Primory Piping
APPENDIX V

REGULATORY INSTRUMENT FOR PRESSURIZER (INTERNALS AND SUPPORT PIPING)
Understanding and managing aging

of pressurizer, surge & spray lines

Materials Vesse * shell, A-33 GL. B. Class 1.

Cladding, Type 304 SS & NIr-Fe Alloy

Heater * Sheath, In1o Insulation MgO

Fittings Statically cast 8S -GrC aF8A and

CF8M MW) SA 516 Gt 70, Tpe 309L

SS PE.C BS&V Type 306L ss tSbY

cladng * lype 306L 88 (CE), Type 304L 8

03W"

Spray ftn

/ tD

Clrcumferantial . I

weldsI Wolof

leve

N eater support

surge line- Elecblcal heater

7T.plca W pressurizer andcontin

Heater mndcoed! by 4 ]

Clad MM

Lo head fM f

eleaen (N-Cr-F.)-0

Defier

S blee to heater wd

sleene to clad weld

r shing

Surge one * Type 316 8S cast SS 3r CF8M

tome (CE plants)

Spray Una * Type 31 SS

Nozzles on main coolant pipe * SA 105 G3t 2 CM, Type 304 N SS (V%)

Thermal sleeve * hnol BB16

Operational bansent temperature, flaw Induced vibrats,

strtifed flowe, thermal sbipping, thennrd shocks, heater

mechanical wear and element burnout and erosion and corrosion

Typicl CE heatr equipment Stressore

end

Environment

UNDERSTANDING AGING MANAGING AGING

(Materials, Stresors, & Environment Interactions)

Sites Aging Concerns Inservlce Inspections, Surveillance, and Monitoring Mitigation

Nozzles and thennal sle. Low and high-cycle thermal NRC requirements Recommendations Maintain full flow In spray One end

operate It continuoualy to prevent

* Instrumentation Eroaion Volumetric and surface examination of 25% of Perform more frequent examination of nozzle welds having sbatfled flow and thermal shock

Surge butt welds Including the following welds each high cumulative usage factor. conditions

* Spray Inspection Interval 10 CFR 505sa. IW-25W0:

Determine fatigue damage by on-lOne monitoring of coolant eplasce horizontal section of spray

* Al dissilaer metal welds and piping temperstures, and flow rate In nozzes and One with eloped ection to prevent

Terminal end dhsImIlar metal Low-Cycle thermal and * An welds having cumulative usage factor horizontal portions of piping during operational transient, stratfiled flow condition

wslds (between carbon teel mechanrcal fatigue equal to or greater than 0.4 stratified flows, and thermal ahocks.

components and staInless * An welds having da Intenslty range of Redesign piping to ellminate valve

teel piping 2 4 8m Perform nondestruwtive eaminations and Ioea parts leakage

monitoring to assess status of thtermal gleeve develop

Same welds are required to be Inspected Improved NDE method to delect crack growth In te baa Preventhiv or predictive

during each Inspection Interval metal and welds maintenance far heater replacement

Csst shainls steel piping Low-cycle thermal and mechatnl- Cal fytiguem Aw detectbu end evaluation 10 CFR Develop techniques to monitor actua degree of thermal se Improved stem pecling

* Sul" nn Thermal embdrtement 50.559, NB-3000 embrItiamlern ag.. develop Improved NDE methods and matehria

* pry lne Erosion spray valve tools using magneti properties measurements and

V EBori acid Corrosion Leakage Hydrostsac pressure tests 10 CFR acoustic emission

Fillings Stem packing/wear and 50.558, IWB5Z0 degradation with age and Monilor valve Wea

Service lfe ASME Section m, N9-3210 and ASME Section

Bellow degradation )U, aI Develop UT to detect flaws on cast stainless steel piping

Cycle counting of specified design transenls

Header sheth filurs Small LOCA via healer ebement Tech Spec's requframente and heater sleeve * Cycle counting of epaciflad design

tranelents

Vag" wan High and low cycle thermal * Leakage rate.

ht1gw * AT lmits for heatup/coodoown
COPOENTs is"

ODU CLV

REGULATORY INSTRUMENT REVIEW FOR LWR PRESSURIZER VESSEL

LIFE EXTENSION

ACE. INSTSRiUET x lit FiTxtES FEATLURES ClUUExl ISIl1AIIVES SAM56 t.l E xIF ESImI NlEED'S COLUMN 3 C 4 CiILU 5 coI oJ C1iV 7 COLtLN a

come

MOW'1

COhLUMN9

PRSSMaIZE1

CLtIMTED TO

INTERALS AL SPECIALITT

IThEM)

(I)

WEATER(E) PROLElS THIESNAL IND:A MECHANICA. WEAR, ELEMEN SLIRMLIT(S)

(Geral

statesant). a"e. iot. segulatiuu are needed

that dross aging of preemur bassry cow

FMnts.

Regulatlon wra needed

that ader. u tiens rao.w.

(2)

(3)

IO CFit SO 0, the I shatt be de&si- Appendix A, ed. fabricated and tested Criterion 14 so a 'low probability- of

abormol tlekae end

ro" rupture xst. The criterion ilpt lez that the design shalt sccaout for mechanical deereation

of the heater shdsthi and

stems.

Scn. Preest,. bouadry internets of the veesels should be adzessed In the regulations.Preset,. butn-ry Internlts of the vessel. should he aessed In the rasulatione.

Provides record of

heeter replacmnt, i.e.,

operating history goad or bad for the specific presurizer.

The Code of Federal Regulation (CFft) dese not

explicitly dees the Intervals of the pressurlzer or the vessel n t ortine wPy/surge piping. Since the preesurizer is pert of the act prMe~

botmdsry, the rules set forth by the Cm principally

apply to the vessel shall, the - rto NWd spray/

surge line. for deeimg. fabrication, operation and preoperationt testing. Applicabl* section noted for the pressurizer deeredetion isste wre ibplled aging feeturee for the internelsand associated piping.

Failure of the heater sheath and heater steeve hew rezutted in presse boaadery leaks. oaster bun-out is not a safety issue me thee my to

replaced. Neeter leakag, however, is a safety

Isomu.)

Providea seine muet by reqiring replaceaent of heaters to maintain a level of power (heter) irput capacity. i.e.. the hater* must al*vys perform at a prescribed leveln th forc- ing surveillance an repeir.

TS6

3/4.4.3 Providts adatory res- toration rolirmonts for heater *t 'ta.

Iandatory stu l- tlnce could provide record for pres sre cycles.

a/A

(4)

si

(general

statmntl 1one. Nn. SAI need to ddrss failure mechanism of the beeters. i.e., Is

replacesmnt the only effective agIng mew

wmmt proieduro for the heaters?

laoundency and ese of The presurizer heater, ere not explicitly adressed heater replacsnt should in the Ms5 . eater alsvo failure, hav resulted be vatsuttd for ticam In pressau e bsundary iCt fahilurs. Detective hest- rutml criteria. Test- ora ad poor design e the probable cames for the mn of heater. should in- preesca. bootdary failures; however, sinel my be a ctuds exceasiw current factor In the failtures, e.g., sering and Thinning

leakage. dee to rubbins action with soewrts caused by thetml growth. Although heater. ar easy to replace, a technicat safety issus extsts become of the potential tehzok peti that could reoult in a primary contailrent leak.

Verify that the inspc- tion la sdote for tlica ruveel.

(I) Ceqtree taI proeram to ae0s leaktight

Integrity.

ir. Provides for selected

IASIE Section XI) code inpection of meds for the life of the plant.

Ge er sl t Motes:

1. A ?7 indirmtoe further stuy/tinvoetigation is needd.

2. For the MSI, areolve me the generic eafety I1aue to reotlved, not necearily the aging is'ta.

3. For meaning of ton ero and initiatle tsed throughout, see ecranr on page i, xii, and x1li of the rmport.

- Preurizer Vesset
COPUExT IS=uE

CLUMN I c L 2

NEATERS (contd)

16)

(7)

(a)

(9)

(10)

(11)

FEG. INSTtMNET

tCOLU 3

(Gareral

stattnt)

AM cods

Section 1II (GeraL)

else

C51 13

51.1-1983 Plt

55.11

ICEE

3ZS

AGINt EARES

tClm 4

lne explicit.

Man explicit.

LIFE EXTENSION

FEAUWRES

COLici t

Noeeplicilt.

CURENT INITIATIVES AGING Nu"D

COLUtN 6 S"UMN 7

7 Rovislona roe" that expleictly srees the agIng of plant cageMants Ned systm.

own explicit.

LIFE EXtiErmo NmEEDS

mthW S

Nelesorsise that *etiiletty ddress

life extensian nd licens rmmwt.

Aesursinc that tht

current rqetent

inethoa/repeir of

fai led heters We

adequte boyce the

pleat lieatse

reneals date.

Effects of procmiror

rellebility on licese extanelon.

Mar.

COMNTS

COLU. 9

The UC Rewlttory Guldon (aft) do not expticitty ed*,a the internotl of the pressurizer.

ASE caiea raeurints re priarity

Caered wil preseus. bmatry Integrity; e , *ectia of the code, howeve, cover

other conerns such aa Section I IIW that cowe reactor eore Intermis, not

the presure boundary.

_tt Ir t LOCA from extu-ed r heating of presurtlar heater,.

Operatlons wintm e, ad testing roWire- mwnts ae ed only to the extent that they effect deeign provision.

Extended overheating of Iae. heaters, cyclic fetiga.

mid service Near.

Estbtlihea the eactoer riginel deeign

safety criterie mnd fhne- criteria could tianwt design recoire- sport LK. wants of structwese

syst_. mnd cpnnts of stetiatwy 1im .

Providee deelig criterie Addroeaes cefety

for "yta and oIpmit fnietliaw that a

necassery to achi mnd closely aligned Mintain a safe shiutdoin with aging If ni of the reactor to cold Correctly con- shutdesn caidition from trolled, e.g., a hot standy or poet reactivity MCE. accidant canditlon. heat remval. o

mam; sm Wee Effects of overheating dropped. on pressurler

relIabilty.

1 None.

ire

it

Nor. w.

Ability to pe rfor sfety fhrction dur to the affect

of aging at he ed:Issd. Types of aIng incetudo

vibration and eer.

Provides crIteria for pro- tctions requrmnts for

Ctns IE pawer systin. Protection from electrical

or eha cal e_ or feilures within a tIes frse too short for apr star action. Doesn't In- cude rpysic al design

fectars such in fires,

pipe whip, etc.

iCS integrity Ineltding pres- surenmrd Iwen- tory control.

Acceptce and qatifyine records. Maw. mom. IEEE stadhrde 323 c oped to other Instriants revlewd recagnize the nwed for eging and deffnee etepe to addrea, aging sc he age conditioning and netural *ping criterIa.

The protection refdrs to swe c nd end execute feetursn, e.g, switch gear protection standy

power protection ond sage protection. Protection shell be designed to slime for periodic testing.

(12) 741

'' Pressurizer Vessel
LIFE EXTENSION

CtuPENI ISSUE R. INSTRUMENT AGING FEATLRES FEATUiES

COLUMN I COLUMN 2COLUMN 3CUOLLAt COLUMN 5

ilRiRENT INITIATIVES AMII NEEiDS LIFE EXTEuslaI WADS

OLUN 6 ODcrLL4I 7 COLUMi a noteS 0

(13) 934

344

Provide crte ria for

reoplacnt parts, both construction ad rration. Reiqures Inspection

ad testing of perts prior

to release for service.

Acceptance testing

ad records that

wy be applicable

to Lit e.g.. failure revite for

War. fatisue. original dafects,

insutation break

dvoa etc.

San.

Ao".

Non. Stadard detlaminsr selection of required parts

for Clat II equipswnt, e.g., Identification ad

failwe revite. However, required design cha re outside the scope of this stadard.

(04) EsteS lakes recoindd Acceptace ard Niow.

practices to obtain data qualifying

to wulify that the quip- records.

sent witt Perform en SSE after - ON. Included

re taets for vibrationel egtng, mimic sping ptaS narmt operation toads.

(tS) SURtE SRAY LINES,

NOZZLE PRiLEMS o STRATIFIED FLOW,

TRAXSIEST THERMAL

LOADS, TtlElAL

SHOEK; hSULltIG It LOW-CYCLE 1tlEiC9-- %AL FATIGUE

Csa

10 CAi so,

Criterion IS

tCS shalt be designed for

sufficient Hargin to asar that the design

cordition rot be exceeded during noral operation or anticipated operationat occurrces. This

criterion teplies that

thereat shack rd other

factors in the design of

the pressure bota"ry should be inclusde.

Nn. Reviason needed to

eging or life of plant

considerations.

Revision heeded to

address operatiaw

beynd the plant's

tices rmeel det*.

(16) I1a3/4.4.92 Providee for control

over the ray eater

ATs; restricts AT to

a a". differential

of 3201F.

Addresecs tructurat integrity of pressre

retaining capnents.

Records for cycles. a/A Could provide a record

of comoent service ptlicobts to llacma

renet, I.e., has the ervic _aceed TS Temearture lailis?

None. Are the originat design

_asamtioen valid for

t icene rammat?

Provides aging mnient by restricting the

temprature AT.

(17) 3.9.3 Design in accordane with ASHE III

& 10 CFR-SO, Generat

Design Criteria

1.2,4.14 ad espec- tally CDC #15 that

stipulates the

deign shalt hove

sufficient margins such that operations

including loading cominations ad

traisients witt rot sxeed the original

design cuditions.

-- Prentsi-er Vness
COMhEMT I=E I ag. iNSTOIEES

PAWG It SPRAY LISES Ti Ccomtd)

(is) (centd) 3.9.1

LIFE EXTENSION AMilS FEATUEES FEATURES CURENT INITIATIVES AGING NEEM LIFE ESISEEIDS NEMD CLUMNI 4 - OUM5CL CINU11 7 UUJE S$ OIENT2

cous 9

Adreses ftigum awl sty... ad Meeting the requiresants of 10 CFR-50

GEC n15. Specificsaty

dess the acceptability of the design relativ

the nub r of cyclee end

navals expected emr tie tfe of the plait.

No explicit referance

to seinr; hese. pro- vides an NEC accepteble

(ftt Of drov ASK

Code Cam for Section

Xi.

Provides _cceptae 7

criteria applicable

to licene ramevet.

Tb. PC Imixp Il Iife, RC revisions we madb

extemion by pro- to include or sextude viding acceptane apropriate Code Cee.

_sthod for approved

(UE) in4pection esthode usine eur- ren? Code Can.

(19) 1.147

verifictiotn of the rur of cycles ad Waits.

NIA

letter Usderstamding

of tie rtationrahip atmeen welding process WA senitizatin is

Neeuaresnt of _eteriet

fatigue life.

Adeqate event rO eW opeptine history

n_< ethodr nedd to predict the *naitdt

fatigue ltif of the

eprey/surge lIn ca the awd of the plant e licee rameet dete.

(20)

(21)

144 Repir of PM tines.

Proem controts to minimize sraslizetion

in steintise *teet maide.

No. Noe. I

N/A

Daterminstion of life eepectamcy of sensitized eterielt ad nucelsr

grab stainlese teote is nd.

iep re d-of-tift projectins, 40 yesrs

awd beyand Accurate recording awl records for pressure awd tht traswients we needed to deterine fatigue dm0. to

spray awd surge tine.

LE Code Cas We nrt es.dtory. This AG presants a NC staff a cable list of ASHE councit pproved Code Cae for use In inspec- ti1 ard repeir of cosepm a as required by 10 CFQ 50s, Appndix A, wd Section 50.515.

INC progrge an -vsltation of Melded and Repqir-Meid Stainless Steat for List Service Initiated sork in this roo ebut ma not coopleted. A Smlt effort my be Ongoing.

Studies wm under may to assess thie msnituds of the effects Of ectual moirarmxntel

comditions. Code curves re based on soth opecimmna In *ir at roa tprsture, idees _e _steriels in service have muih roudher surfscesa ored we osed to flowing coolant at operating teeperatoes. The sctusl surfaces we mm prom to track Initiation. studies

and research to mesxs xnitud of effect of nwviroent factors could result in need for mrw Regulatory Guide. Regulatory instru- entos xnor code revision.

a Coc

Section III Aresses fxtigue.

0,

Fatigus cur Section Xi, SVA an revision. Operating Plane Cri- teris Is reviewing ftisus curves in

Section III to deter- mine If they can be

revised to Acc sde q lreion btyand 40

ye r . U S E S o n fLEX hts rc d

that _ppropriate XI d tteto investigate acre frnt NEE a sure. tine mIds than currently reuired by Sac. Xi, 15.

(22) ^ eoelon (mtt 0-3210 Special

thiminni) cosaideretione

of 55-3121 (Sectiam Ill)

IlterIlt "Jetct to

erosi0n corroslon awn _nkhaxicat ebresion nat

h e silitionr t atl thiicknee to account for thee anticipsted con- osditilone.

None explicit; bow design should provide culda for the ade- qawy etof t design

byrd the 40-year

Interval.

7 Ip tled In the deelin

criteria.

guidanee is needed to

cover the limits of c I t deterioration.

1t-3121 states 14terist eoEcto thinning by corrosion. erosio, mnicat xtrosion, or other awrovmnat effects shalt have provisin tD for thee effects during the design or specified tiff of th crponant by a sitabl

Increese in or sddition to the thickness of th be Meta over that determined by the design foraulxs.0

multe vr design and construction require- sants but do not cover deterioration.

-- Presgurizer Vesset
~COMOENTs Ia.

COLMI I -- mKL

SLOGN & S1PRAY LINES

(23) (contd)

AEG. IbSTEIIENV

Gil 47

LIFE EXTENiSION AGING FEATIRES FEATURE aRREsT lotITIATIVES AGING NEEDS LIFE EXTENSION NEEDS

COLmin a COMEENTS

C tLje 9

Therat streU resulting fram scatained operation

of UIPI.

te. a"e. Effects an presamricer

reLiability at pt nts at ehich presasizer has ben over heated

and cootod

Mec concluded there IS no direct safety itplicetion of overfeeding nd over- cooling prerwier with lPI.

(24)

(25)

AMB

51.1-1933 PW EstebtiAls the raeleer Original design safety criteria nd criteria could funttionel design roqire ar t a. wnts of structus,

syste, art d cowunts

of stationary Pt.

58.11 Provides design criteria Addresses saty for syst mnd eqipmnt fumctions that are nscessary to achieve ad closely Aligned esintain a safe shutdWan with aging If rot of the reactor to cold correctly controlled, shutdown conditions frem *e.., reactivity, KS a hot Stfaby or post heat rmoval. nd tCS accident condition, integrity including prassmra ad iran- tory control.

tone. ono. 51.1 is for Pta nd 52.1 is for Mis. The standerds are essentially the am. operaties, eintence, and testing requiremnts are covered only to the atent that they affect design previsions.

ton. tons.

SPUAY MEMD CR5B (26) * THERiAL .INUCEO, 10 CUR 55e EtWirTLET.ENT Codes and * ESOSIOS Standards

(21) Tse

3/4.4.9.2

Regulation refers to ASE

Section III for design of closs 1 cmonants. Ipplied that erosion will be adkessed in piping systes design.

Provides for specific AT (1OOf) heatup ad AT (200F) cooldes in any 1-hour period ad mx pry ester differential

at 320-F.

Vonet.

hsterial subJect to erosion, corroeion. ad _esidnicel abrlasln ant have additional tali

thicnes to actmnt for these anticipeted conditiono.

Meoa. tevision needed to Revision needed to tddress aging. ae operation

beyond the plant's Iliceise ranawel dets.

REcorde for cycles. OVA Could provide a record of ceonent *ervice applicabl to litens renewal, I.e., has the service _xceeded TS teerature limits?

Provides aging eanagmit by restricting the teerature Ala.

(28) Section III Non.

oNam.

(29) NR-3210 Specalt considerstionr

of t-3121 (Section 111)

Mn eplicit; hb.- ever, design should provide guidence for the aiaeocy of the design beyaid the 40-year interval.

Implied In the design criteria.

hone.

Guidsnce is nde to cover the Imilts of crwnt deterioration.

AVE cods roqirmnts are exclusively concerned with pressure bondery integrity.

58-3121 states 4wateriatl sbject to thinning by corrosion, erosion, mehanicsl abrasion, or other anvirornentat effects shall have provision mod for these effects during the design or specified titf of the ceonent by a suitable increase in or aeddition to the thickness of the tse metal over that determined by the design formute .

0

Rule cover dlsign ad cesatruction reqire- ments but do not cover deterioration.

-- Pressurizer Vessel
SPRAY HEAM (cantd)

(30)

NES. IHSIRMTHH

SRu 47

LIFE EXTENSION

MuGsN REAI$ FEAni*ES CtNREX INITIATIVES AGIm NEEDS LIFE EXTgwuOw NEEDS

calmCOLO" 5 ODUM a~m. 7 cOaum" a MHETS COUSIN 9

thmrol stress resulting

frre siutained operation

of IPI.

Ne. Effects an pres uri er reLiability at plents

et idieh preesurizer has been overfed Mnd

coated.

NRC coicluded there Is no direct Safety

itplication of overfaeding end ov reooling pressurizer with HP).

(3t)

(32)

vM

51.1-I30 FUR 52.1-1903 "o

58.11

Estai btt the nsutolr safety criteria Wd functienet design requfre Monts of structures

Syste NW cnd ernnts of etatirey HoPs.

Provides deasgn criteria for syste nd wipeent

necessary to Aehi" and maintain a safe dwtdoun of the reactor to cold shutdoan csnditiens from

a hot stwdt or post accident cendition.

Originel dign

criteria could

sport LA.

brne. 51.1 is for fet nd 52.1 is for Suis. The stndrde ae sentiauiy the sw. erations,

_iinteswece, ad testing requirements er covered

rnly to the extent that they affect design provisiorn.

Addresse safoty

funtti0w that are

cloaely aigned

with eairg If not correctly controlled e.g . reactivity, KS

heat resa. rnd KCS

Integrity inctudine

presaue ard inverr tory control.

(33) SIELL uetERsAt

SHELL BARRLIt 1

STEM SPACE: lItG & LOW CYCLE THER- PAL SENDING AT ATYER TO STEAM

INTERFACE

Csse

10 CPU 55e. Codes aid stwndrds

Regulation references

designiIn accordence with AIE Code Sactitn

uuu for clm I ccp- mtsa. b pliad that the

design will dre highnd low-cycle fatigue. bendinf stress. etc.

Hon. Regulatian revision n d to address

aging.

Regulation revisien needed to adess

cpretins beyond the pltnt s license renewat date.

(34) 3/4.4.9.2 Provides for apecifIc

At (10t0F) heatup nd AT (2003F) cooLden in an y hour period

nd Mx. say water ditftrential at 320F.

Records for cycles. H/A

(35) 2.1.1 Establishes madatory hidu-tturetue tlidt

for the pressuritzr (highest reactor cooltnt tauperature).

2.1.2 Establishes diatory highprnessue iadt for

the reactor coolent

ysytem,

Auto trip providee records of traneient

coruitions.

Auto trip provides racords of tren ient

conditiosn.

i/A

H/A

Could provide a record

of compoent srvice applicable to licerse renewal, i.e., has the

service exced TS teweraturs limits?

Could provide a record

of transient corditionr end o nitaring of cyclic events.

Could provide a record of trensient corditions

ed monitoring of

cyclic events.

Provides aing _nsont by restricting the

temperature Al.

Provides *ging mewag t by establishing the upper saterial terstura limits.

Provides aging ingeet by establishing the

high-press" limits. (36)

-- Pressurizer Vessel
COMPONIE

(ST)

Is"

SELL. INTERNAL.

(wiltd)

RE5. INSTeEMMT

SOP

3.9.3

Lift EXUE5SIMN AGING FORTUNEIS 'EATURES OMOEMY inTIATIVES AGIN6 NEEDS

COUSIN 4 ......OUI Lj..... C 7l _ LIFE UTIEMIN RUGS

Are the originial deelen

assumptions valid for licenee toweul?

IU1ENTS

COLaS 9

Addres structurtl integrity of pres"sretaining coronts.Decisn in accor- dance with A51K IIl mid 10 CII SO

Genral Desisn

Criteria i. 2, 4. 14, 15. mid N e

ciltty GDC *15

thet stipulatec the dusign shall

he sufficient ertin such that

that operations incrtufiN loa'ing

loading crabine- tins mid tran- ient will rat exceed the original

design cerditione.

5m.

(38) 5.2.2 Ovepreture prot ction. Overpresmur

protection.

V/A

(39) L9.1 Adde es fatigue mid

*trew ard meeting the requirmnto of 10 CEO

50 0EC *5. Specificatly aess the accpts- bility of the design reta- tliv the nubr of cyctes

aN events epected over the life of the plant.

Prwvide acceptance

criterIa apticale

to tircan renasal.

verificetion of the

raber of cycles ai Oevnts.

Probebty adsate for

ticuiae renewai for this specific ~et. Suiros

protection for the life of plant events.

Adqute event records

Wet operatinr history needed. alth de re

rim to predict the aveltble fatipa lIfe of the presrurixr daolt

At the id of the plaitns

lictms reneat dote.

tequalificetien Rutce

for crpnents.

*evilw stipuletee that ovarpressure protection out

be avattabtl (ahfety/retlef valves) for the prec- suriw SIO S of atltrabte pressure for traml nts or operational occurruae woe or mr time during

the life of the plant.

;0

A Cose

(40) Section III Iseq~lification of Itemtification

compoents. of comonents.

A tus appbidis Is undor caidereltion

which may be used to

rmqulify coonents wuich hwv exceeded the rulsa for cyclic

operation in Sec- tion Ill. d-3222.4. A tlek rcup has

bean IoIu to Adres

the iss. This olso

app le to Section xi.

evaluate nru nAidix.

-- Pressurizer Vessel
LIFE EXTSNSIWILF ETNIO ED U*PUCENT Is". VEG. l115tRtiIfET AGINIG FEATI)RES FEAIWSS CURRENT INITIATIVES Atiet NEEDS1 MUEMVESI5 at 01915 CII 011Cm 9

SHELL iiNTERL ASME Code

141) (cantd) (cantd) Fatigue. Fatigue cwe Section XI, VA on revisions. Operatin Ptnt Cri- teri is reviewing

fatigue curves in

Section III to deter- min if they can be revised to o rcoo- dote operation beyour

40 yews.

Moe. Improved mndof-life projecthone 40 years

nd ed

ttudles ae uwder way to assess the Meunitude of

the effects of ectiat evirorwmntat conditions. Code ctves we based an smooth specimen In air at roc teeratuwe, vhreas Materialts in service have

Much rougher aurfates and re exposed to ftowilr coolrnt at operating tmyeratures. The actual surfeces are mr pron to ractk initiation. Studies

and research to mess Magnitude of effect of of nviusesntat fectore could result in nred for new Regulatory Guide, Regulatory Instruewnts w

or code revisions.

(42) Section XI Condition assessment. Reatification Consideration of Condition assesomt, of stem and devlicpment of nre Informatlon/dete.

canants. Article 11X-8GW

Rteqmlfictlon for

Fatigue life. An AiSK Kt has bein formed on

Fatigue In lif. The

moal of the US Is to provide a mecmenlme for rtelief then the

fatigue design limit Is reached. (TMe limt

would be deterined by

developing Monitoring and evaluation techniques.)

Requatifitation of atys rnd components following eapiration of

operating license.

(43) 151 47 Thermel stress resulting fro susteined operation

of liPt

Na . Xone. Effects on presourizer

reliability at plants

at which pressurizes has been overfed and

cooted.

mRC cwctuded there Is no direct safety

lepti catin of overftoding aid overcooling pretr oaler with "PI

Zi

(44) 51.1-1963 P1R 52.1-tse3 VAR

Establishes the nuclear Original design

safety criteria and criteria could functionalt design rewpire- IIort La.

wits Aof tructures,

systems, ard coonents

of stationary ffs.

"One. Cone. 51.1 as for PF~s aid 52.1 is for Mis. The stndrde We essentlatty the o. Opperation,

inte te, and teatinil recpuirnta re covmd onLy to the atant that they affect design

provisions.

(45) 58.11 Provides design criteria

for ayst_ nd quipmnt

necessary to achieve and

meintain a aet ehutdmnn of the reactor to cold hutdown condition froe

a hot standby or post accident condition.

AddresseS asfety

fiuction that are

closeLy alignd

with eging If not correctly controlled. e.g., reactivity, IcC

heat rval, mid KCS

integrity Including pressure and Irn- tory control.

Cone.

- Pressurizer Vessel
COMPONENT IS"E

COUM COLM2

TMERMAL. SLEEVE(S)

(4) * TMEUIAL STRESSt FAT IQE

(47)

(48)

149)

AEG. IiSTALMllT

COLUMN 3

AGINGPETIEMSl LIfE EXTENSION

FEATURES OERilNT IMIITIATIVES AGING NEEDS

COLUFA 5 COLUMN 6 aOLtlM 7

IS&

3/4.4.9.2 Providaa for specific

AT CiixJF) heetip and AT (200) toolgdoun in any I-hour period end mx. spray Diter

differential at 3Z0P.

2.1.1 Estebtlisha _adtory

hish-teerature limit for thi pressurizer

(highest reactor coolant

temperature).

3.9.1 Addresse fatigue end

stress and mating the requirmnots of 10 CFX

Si GDC 15. Spcifical- ly ddrerc the acceptability of the design relative the nuner of cyctes nId evnts

expected over the life of the plant.

Section XG Fatl_.

Records for cytles. 1 /A

Auto trip provides 7 I/A reords of tranients condittions.

Provides acceptance 7 Verification of the criteria eplicable nuer of cycles id

to license rasmal. events.

fatigue curve Section XI, Sv on Measuremnt of material revisions. Operating Plant Cri- fatigue life.

teril is reviaeing fatigue curves in

Section III to detersine it they can b revised to accoate

operation beyond 40

years.

LIFE EXTEhSI hEDS

Could provide a record of tcmont service app0icable to tgiar renmwal.

i.a., has the Service axcedod 1S terature

limits?

Could provide a record of tran Int conditions and

onitoring of cyclic

events.

CiaETS

CoUi" 9

Providem aging menaement by restricting the te4 aratura ATs.

Provides aging moa5mnt by estlablishing the upper

material tesrsture limits.

Adequate event records mnd operating history

needed. Methods are needed to predict the available fatigue life

of the pressurizer shell

at the end of 40 Vors.

Improved mId-of-tife projections. 40 yers and bhyind.

Accurate recording mnd records for prasaure A

thermal tranients er

needed to deteine fat igm de to

spray mnd surge lines.

Studies are uider way to assess the mognitude of the ef fcts of actual envirocmntsl conditions. Code curvea e based on smooth specimmen in air at roin tuqperature, dhereas

materials in service have much roucjhor

surfaces and are exposed to flowing cool nt at sperating temperatures. The actual surfaces

are sure prgr to crack initiation. Studies

mnd research to _m e magnitude of effect of anvirontstat factors could result In need for ns Regulatory Guide, Regulatory Instrum*nts meler code revision.

0

(50)

ANS

S1.1-19i3 PWR 52.1-1963 Mm

Establishas the nuclear original design

safety criteria and criteria could

fuhctional design reuire- spWrt Lt. ments of structures,

systam and cooponents of stationary UPs.

None. Mone. 51.1 Is for PMe nd 521 Is for SEis. The standrds er essentielLy the sam. Operations,

maintenance, and testing requiremants re covered

only to the extent thet they fet t design provisions.

(SI) - SHEATHES; CEMtii- CALLY INDLICED) tGSCC & FATIajE.

I GENERAL:s WRATED COOLANiT LEAKSI

IIgaT~Ii/CLOUEES;

$CC, LUMNICA- TtION. MOISn"E

gINVIRCOsEIT

Ma

10 CIR SSa, Codes ind

Standards

Regulation requires de- ign, fabrication mnd conOtruction in ccordenc

AsIE Code Section lit, class I components. Code

reqiuires ttention given to

corrosion, erosion. emnvi ronsental effects; this Isplies the regulation addresss the aging issue.

Mone. None. improvements in the ASYE Code are needed to ddress deteriorstion of materials.

-- Pressurizer Vessel
(52)

ISSMI

:'I WOMl~ (contd!)

LiFt EXTENSION REG. INSTRUMiENT AGING FEATNEES FEATURES CURRENT INITIATIVES AGING NEEDS LIFE EXTENSIONi NEEDS COLYM CtOtLLIN 4 taiOLei S COUM 6 iOe 7 taLU101 a

T5glNTS

Caiteri

am

5.2.3 ateriel arwe roviused for suitability for the servite. Iaview of meaufecturaing nd welding

is also inctuded.

eone. Nn. Wane.

(53) a." efin teak detection _thods for RCPI leeks that ewortor potentlil

changes in conialrmnt envirornwit. osch as

increesing hueldity.

Should provide records of pest

plnt coneditlons

And current Leak status for

evaltution of License recvl

apptlications.

AIM. has developed In the current RG en ecouetic eathod position adeqate for for teek wonitoring. eging oenegemt?

Is the current RC The AL acoustic laoratory experimantet position edequete for _ethio need to be verified by field tests. license ranewel?

(54)

ASE Ce 16-3210 Special

oensiderations

of 1N-3121

(Section IM

Reeqiirmnts iplied for the specific pressrrizer perts. The intent of thl code is bt e

saterial ubject to

erorion. corrosion, and machaniclt ebrbsiln that

mat hove additional etl thiCknesS to account for the gnticipeted

conditions.

1Ne expticit; how- ever, design should provide guidence for

the adequecy of the design beyond the 40 year interval.

7 Implied in tie design

criteria. Guidence Is neded to Cover the limits of cosmnt deterioretion. Adeptete eonitorinu is needed to detect boric acid leakage end corrosion.

11-3121 states _Materiel subject to thiming by corrosion, erosion. mechenicel abreeson, or other envirme*nta effects shall have provision mide for thes affects during the design or specified life of the Ceponent by a suitable Increae in or addition to the thickness of the bas metal over that determined by the design fonoule".

Rutes cover design nd construction require- ments hut do not cover deterioration.

See MAEG/CR-2963.

(56)

CSI A-16 Plhterut of activation proucts; increase in occu tionhrl doses.

Am

51.1-193 PVR Establishes the nueclear saftty criteria nd

functional design repire- wente of structuresn syste. nd c nents of stationery kaps.

58.11 Provides design criteria for systeme Ad eqiuipeent

necessary to ealfeve aid

Mintin a safe shutdoun of the re etor to cold shutdtue conditions from a hot stmdy or post accident cndition.

MOMw. Issue t resolved upon isecae of pidence to

utilities.

Original design criteria could seport Ii.

Adreas sefety ftuntisns that are closely alfgned

with aging if not correctly controlled,

*.g., reactivity, IS

heet rvel, end RCR

integrity Including presure end Invwn- tory control.

Long-termo effects of chemical decontamln- stion agents on the primary coolent system.

11". Ione. querations, mintenance, ard testing requireents are covered ornly to the extent that they affeet design provisions.

(57) sons.

-- Pressurizer vessel
SURVEILLANCE:

(56) *TEST ING *INSPICTIds

M AINTENANCtE & REPAIRS

*MDE

(59) *INMPUITIOM/DATA

:FRbEQENCY

DATA. COLLECTIONE -DATA EVALUAT 011

-TREND CURVES (60) -REWORIRG 9EElING

REC. INSTRUiENT AGING FEATL*ES

C~OLUM 3 COLtrAi 4

CMS

10 Cfx-SO Regulation rquires the

Apperdix A. VPC be deaiand to

Criterion 32 faciltete periodic inspections.

10 Cfe-50. Regulation reg.irs a DA

Apperdiu E plan for design, perations and testing.

10 CfR-SSG, Reulation require $IS

Codes and in accordrnce with ASlKE

Standerds Section XI.

LIFE EXTENSION

FEATWRES CURRENT IRITIAWIVES AGING NEEDS

COLLM SOaUiNo COLUW 7

Inspection records 7 N/A

could establish interity or candition of the compnt.

GA documentation t X/A

sill assist in

license renewal

process.

III records sill 7 N/A

asist in license

renlewa proesses.

lf1)

ism

3/4 4.0.2 S

4.0.5

(62) 3/4.4.3 & Including

4.4.3.1

4.4.3.2

4.4.3.3

6.0 (Administrative controts) 6.10.1

(63)

I-r'o

Provides surveillance

intervals and reforences ASNE Cods Section XI for class I copnents.

tS with its surveillance

reqireents dictate the electrical hester cpcity and water levet of

the pressurizer.

Lists mandatory 5-year

retention records list.

Lists mandatory life of plant period for plant

retention records. Prin- cipal interest is item

6.10.2 *. shich specifies the rscord keeping tim

for traieints or opeaing cycles.

Compent statun records.M/A

Crnpnent status

records.

N/A

Provides record

history of ceomn- ants ad sytem.

I/A

LIFE EXTEBIOII hEEDS aEhIlS

_ COW.5I S CoLtoe 9

Verify that inspection records ae adequate for

license renewal.

Verify that the DA dauswntation is adequate for currant licane renewat

neds.

IS1 Intervals and *xcep- tion allowed my not

fully address tic

renewel concerns or

remjirments.

Records could be u ed for Should provide history of corponant for licene

lice renewal, I.e., renewat application.

verity the history of

csoent integrity.

Records could be used for

license renewal. i.e.,

verify the history of cqont Integrity.

May rewuire longer retention period than S ywrs

for principel inspections, Sta 6.1i1.b. ad d. to

be ppicable for license

renral.

Could provide sufficient information nd recorde

for GA, ISl. water quity

and otherse including

apecific records for componant transient cardi- tions, i.e., TS table 5.7.1

"Coonent Cyclic or Trcmient Limits.e

Is inspection adequte Inspection are to be in accordance with 10 CfR-SO,

for liceras renwl1? Appendix A, Criterion 32 snd 10 CfR-Sh and es

detailed In AKE Section XI.

Is the bA plan adeowte th SRP dom not explicitly addres aging or

for license reneal? license renewt, only that a be plan is repirad.

(64) 6.10.2 Provides record his

tory of components

nd cestm.

N/A

(65) 5.2.4 Requires 11 progra

to asees teaktight

integrity.

17.2 Addresss maintenance

aid testing retative the isplt entation of a Quality Asourance plan.

None.

Records of mintenmnce and testing.

Provides for selected (ASiE Section Xl) cods Inspection of welds for the life of the plant.

Is in-place be plan and record keeping

adeqste for aging

mnsgent records?

(66)

-- Pressurizer Vessel
COMPONENT ISSIE ME. INSTmMIEIGT AGING FEATURESS

COLMN C LU 2 COLUM 3 X 4

LIFE EXTENlSION

VEATLIRES 035R551 INITIATIVES ACING NEEDS LIFE EXTENStION NEES

COUMN 5OUN6CKmIi 7 CQUIRM a NETS5

SUMVILL.ANic (tontd) Ron

(67) I.50 Esteblobes guidance for the qalification

of IDE staff iho perf01 inspectinsr.

tests and exasinations

for Nfp.

Pr.v"ids dsucnt- stion of staff

quaitfcatitns nd quality asstrm*e

recoids (of staff)

for the plant

yA pl n. i.e.. records 'eed for

lI fcense reemi.

GA docuentetion.

7 Improl d qualification guidance my be necess*ry to fully ddress

*ging coneoe.ne.

Irlmpod qualification Saferarm ANSI 115.2.6-197. ujience my te necessary for Lt.

(66) Sfety Guide 30 Estabtishes regulatory

(Ns AG 1.30) position for 04 require- mnts relative to test- Ing of electrical

eqipment.

None. On. Neferences 10 CO 50 pnditx *, OR criteria

for Mm.

(69) ASK Code

Section Xi

(gral)

Metedf 1 Wi ctp- nent ctnditien

Assesismnt.

*ef. info./dteU bses as they

apply to repasts

for exteiions/ renewles.

New nadrtory Soe other coltns. appardtx on rtcffd- keeping hea passed

the SUG-PtEX.

oef. Ilifojoaet

aseem to spot extaiosiorm/raeneaLs.

As materials and coonents age, the

predictive cepebilitias for physical and techenical property changes ust leprove.

Since. uring a plant's service life. in increaing amlunt of inforMation/dats will be avaltable firs surveillance program, butter

procedures to evaltute aid Use this informtion/ata can nd mat be developed. Stratified flow nd thermet aacEk are

major stressors In the base natat nd welds. laed mtcl inspectionr atone are Insufficient

for aschonicel property changes.

(7D) Section Xi Sutveillance.

iNe baseline exm A now taSk group tnstion require- on baslfine

ments have been examination. estebt ifed.

see other columns. Poesibte need to re- quire a new baseline

exsamnetian for a license extiension

reqest.

(7t) Allow for inepectione beysd 40 yers.

thenes to Inspection Plans A and

S wihch we eur- rntty bsed on a

40-year operating tlif besed on four

intervals, the *uf

of which * 40.

SW3 has Implemented

revision to IWA- A4O. which twill

delete the 40-year limit cwrarntly con.

tamed in Section Xi. Also, reviewing need for e frequent wd

extesiwe in aections. inopectior AM PLEX

m is also reviewing Inapection Plan A for

4ptlicetion to PIES or should a new plan

(of higher retimbitity) be devaloped.

Exted Uador wrdiced srveil ttnce beyond 40 ypers.

uwrveittltce beyond 40 yees.

The £SE PtEX SuR is reviewing the I npection Pltn A to determine if it should be wed.

-- Presuriwer Vessel
COMONETt

(72)

SUREWILLANCtE (contd) ASME Code

(Conltd)

LIFE EXTENSION

MrING FEATIRSl FEATURES ClARMMY1 IgTIATIVES AGING NEEDS LIFE EXTENSION NEEDS COLLM 4 - OLM 5 OLM COLUMN 7 COiMNs a wigMEMI" COLUMN 9

Monitoring nd

test ing. inforsatiorV'Dets Dvtarpent of new Informat ion, data, for trend curves, exa. tectniiqoxs to nWd aao.se saenta.

detect tso- related degrtdttion aid fatigue being considered.

NoriltorimW/teating

tochniiipmt.

(73) Information and data

for trard curvit projectites.

(74) Fatigue faiLures.

Records, Infors- PA Is considwring Data. develipment of non- modrtnory appeindix

for recordcilwiping.

Anticipate and Fatigue manitoringf

avoid fatigue technolegy developed failures. and doanostrated;

$sv~ral utilities

procedhing.

Informat ion and data for trend cuve.

Experience and test data for high-cycle *ffects.

Recorde, inforuat ion,

aid data.

Regulatory acceptance

of atternate atprodh to design baas.. Addition of fatigue

curves to high cycles is needed for litf xtenittn.

This Apptndix would provide utilities iith guidance as to the recordr needed to support

a titer" extension request.

a) Faitures tunlikely froe cycles conaidered in design. Design approach is conservative.

Ctponwt featurs irncludd to pretlude

fatigue failture. Ctonents have high

toleraince to flaw.

(75)

(76)

a iW-25Wt Weld integrity of heater penetration weide

re qire visurt inspectlion.

R-47 Lonrg-term degredation of Cilas 1, 2, 3 coponent rxa. ts.

Provides criteria for selection, qualification,

Kd training of persicntt for statlionery nuclear powaer plents.

Recrs and acceptISce staiderds.

ISI raquirsonts.

Xon.t Frequncy of

examinat ion.

Issur me dropped Characterize long-tenr frem further degradation of cteconsideration. pneant supports.

Juatify the chtngtie in ISI tntttrnat. Thet existing frequincy my not be sufficient for licente renewal.)

Lentv of 11 insPec- tion needed to verify

adequacy of 5cprts.

b) Fatigue crackiting has occurred during

operating:

* vibration

. rapid thermal cycling . pro-existing flaw . other conditiona not considered in design.

Section XI in Table ILi-250D specifically taddrett the pressurizer; however, only the pressure vessel, piping, nouties. bolts atd hydroastatIc/llakag test. re ddresed. Thie

code do"e not address the presaurizer

internals.

NaC referwencd ASK Code. Section XI end CA Progrs before dropping isaue.

DAS

(77) 3.1 Providee record

on training of staff.

gonm.

(78) 3.2 Provides recawodetionm srmd recquiroments for adainitrative controts,

including oritten pro- cedres, snd EA progrm

to help asture that activitimes of IiPs ore carried out without risk to health

end safety of the pubtic.

Administrative

in-ptlce controles will probably be

required for LR. The essociated OA

documentation Witt be useful for Lt.

Mons. lins. Aong the activities covered under thls standard are design chongoe, f bricating, cteening-decontamingtien inspecting, testing, eaintaining, tAd

reptiring.

-- Pressurizer Vessel
LIFE EXTENSIONI COMPONENT ISSUE REG. iNSTNUMENI AGING FEATURES FEATUMES CURRENT INITIATIVES 841St OEMD LIFE EXTENSIONNE MSS tOuENTS

nxim 9

(79)

2"ZLHANCS (centd) ANS Icentd)

51.1-1983 Pli Estishes the nuctear Original design safety criteria Ed criteri coutd

functioal design reqitre- suport tR. *ants of structure. syst. *nd co ents

of stationary NPPs.

lnlr. Operatioif *intterte, and testing requir cnts ae covered only to the extent that they affect design provisiese.

(f0) 55.11 Provides dsiegn criteria for syste m a d eripemnt

nacessary to achieve Na

maintein a *ea shutdosw of the reactor to cold shutdon coiditlons from

a hot sttndby or peat accident condition.

Addreses safety fiaotienz that we closely

alineda with agina if not corvretly controlled, e.g..

reactivity RSC heat

reval. and RCS

integrity inclueF int pressure and

irnentory control.

Is the design criteria

va Id for Lt?

(81) Tom Provides minimu re- qtirmnts for Inepsetien aid testing of Class IE poer

intrunttation nd centroL etaient &a- Ing c isttrtotien plas.

Records of con- struttion ay be

aW leable to LR.

7 Nam. None. Provides a criteria for correct instellatiesn oAeh

could of ect agfng aspects of the aquiPeent after tart-up and operatien. Cias Ir Is eaiupent that Is essential to _rgency wutd4n. eontsirment Isolation, OCC, mad CIO.

Gn

-- Pressurizer Vessel
APPENDIX VI

REGULATORY INSTRUMENT REVIEW FOR EMERGENCY DIESEL GENERATOR
Understanding and managing aging of emergencey diesel generators

Principal Diesel Engines In Nuclear Seivice

Manufacturer

ALCO

Allis Chalmers

Caterpillar

Cooper Bessemer

Fairbanks Morse

Electro-Motive Division

Nordberg

Transamerica Delaval

Worthington

Others

Materials: (typIcal)

Aloy steels, welded steel plates. castiron includng,

gray. alurnun, stellite seats, forged steels,

ductive Iront, non metallic gaskets, hoses, seals

Capecities:

HP 215 to 670 per cylinder or 8o0 HP to 8390 HP

KW ratings 50, 500,1200, 3000, 6000

Stressors:

Cooling water, lubricating oil, fuel oil, starting air,

Intake and exhaust, deterioration, dynarmic stress,

vibration. themWl fatigue, wear and harsh testing

CUNDERSTANDING AGING

(Stressor & Enviroment Interations) MANAGING AGING

Sites Aging Concems Inservive Inspection, Serveillance Mitigation

* Instrument and control systems Environmentally induced: dust water. NRC Requirements Integrated EDG program of testing,

Governor heat. oil chemical. etc. * RC 1.9...surveillance, maintenance, periodic testing inspection, monitoring, trending Sensors * Maintenance errors: inadequate training, * RG 1.108 ... routine testing, maybe with drawn due and maintenance activities:

Relays maladjustments, etc. to RG 1.9 revisions Tesbng/trending, change testing

* Startup component Fsst a starts and other regulatory Induced * General letter 83.41...fast cold' starts to a slower start test and

* Fuel system factors * 10-CFR-50, appendix A. criterion 4,5,17,18 A 50 acquisibon of these testng ipipng on engine * Design Inadequacy, wrong application. ... pendix A tern .5. prameters ftore tending

Injector pumps or poor component 10 -CFR-5, appendix B. section XI requires...

* Starting system -Operation Induced: Inadequate training components & system to perform satisfactorily Improved inspection of weekly. Controls and skills - 10-CFR-50, 55a Codes & Srd -ASME BPVC monthly, and yearly to determine

Starting air valve * Vibration induced section Ill, IX, IEEE STD 279 envioronmental stressors more Starting motors * Fuel or lubrication degeneration * TS 3t4 8.1 surveillance/inspection for operation & effectively

Air compressor * Gasket. seal, or organic material degeneration shutdown status

* Switchgear system Inadequate spares: quality, strorage, ordering GSI B-56-improve reliability of Eng. Maintenance responsive to test

Breakers problem data and specifications * IEEE standard acceptable for use by NRC-RG 1.9 & Inspection. e.g.. do not over haul

Relays * Corrosion. oxidation unless inspection and trends

Instrument and controls * Thermal stress indicate the need

* Cooling system * Manufacturing or quality problems

Pumps * Fatigue not related to vibration *IncresedtrainingforEDG

Heat exchangers Metal fatigue Staff in on-site maintenance

piping -Wear

* Lubricating system * Bacterial action Systen motifications to mitigate Heat exchangers stressors

Pumps

Lube oil
REGULATORY INSTRUHENT REVIEW FOR ENERG

LillEXSTENSION COMPEi NT MG. IhST5AjUt AGIN FEATWtES FACSURRElNT IKTIATIVES ArIas I CeLUX~~~I 2 COlUM 3 COLUMM 4 m u ul5mLLIbm

ElERGENCT CYCLIC FAhIIUE, CFO

DIESL I1LUIU VIBRATION 10 ChA SO Section Xi of Appendix S Provides records lem. Nam. GEAiAATU AND SERVICE AAperdls Ix requires test progras to id perforxwne

(t) "Sure that c ents history for Et. erd systes perform

correctly.

(2) Appendix A General Dealin Criteria Provides records Interpretation of ho.. including criterion 2. 4, nd performance this CIM x-1may 

5, 17, 1s, Nd so. Of history for OGs. If the mgeettd ths. I s mt leper- revisior to 1.9 we tent U It provides aging proved.

guidance by reqiring

periodic testing Nd

Inspection to evaleute

ceonent condition.

(3) 9.5.7 E0t lub oil systes hu. bons. hont.

review odrese dry starts or lack Of lub

during starts. The UP reqirer a dedicated systes for _riitg pert .

(4) 1.32 gultory position for hens. hone. MGM.

desimn. construction Nrd operation of xPt; agirg features iqplied.

AMi Cods

(5) Section III EDGt by definition are hum h/A h1 . SectIon Xi Clux 1 2. Nd 3

coeponants; howeer, the EVA w not pressure

vesals or piping. etc.

(6) 300 Design bes criteria for Provides en 1 ans. hom. Claus IE WIpuint to aceptable deslxn enbl th_ to met their base for possible

fhaatiule roqirmtents. La.

(7) 32 *Ability to prt.o safety Acceptae a nd Xana. hone.

fuxction OA to the ef- uatilfying fect of aging not he ad- records. dressed. typas of seing inctuds vibration Nd

_ ar.

"Weiea Motes:

1. A e7e Indicates further study/inveetigation Is nudd.

2. For the SIX, *rosolveda men the generic safety Issue Is reeolved, not nesaritly the eging Isaus.

3. For meaning of abarviostiar, acronm, aid Initialim, used thraeghout, ei acresm on papg xi, MI, nd xsii of the report.

ENCY DIESEL GENERATORS

LEEDS LIFE EXIEX101 xEDS KIDSIS

C7LLS am=S 9

Are test documents/ Reuires that written test procedures that sddreea records adequate for Lit? proof test prior to installation. Preoperational

tests Md Operational tests.

Norm. 10 CA SO, A4pepdix A DC, criterion 17. require an

waite EM to provide cnmite poeer to ahfety-retated ccwiants Nd syst_.

The records (history) of

the EDG hould Indicate adete performance to

permit ue beyord 40

Yvas.

Sea cet.

bons.

1-a

Refors to IEEE stedrd 30e-74 as acceptable criteria for design, gevrat operation. Nd testing of OPPe. The RC doee not ddress license renewAl.

The AlE cods As rewired In 10 CF 50.55e xndste

ISI. thes reWiruemts rarely involv EDC 'nltoa a specific pert is dxsisned nd mioufecturad in

accordance with the Cods.

hone. Includes pewer syste. *.. , diesel goenrators:

design base includis malfuiction, accidenta or operating modes that could lead to dsgrsdetion of the *ystu. ialfunctiona re defined Ue nstural

ph ow, e.g., enwironeental factors of pressure. humidity. teratures. nd accidents. e.g., fires.

M"e IEEE *standrd 323 as opposed to other instruments reviewed recosnizes the need for aing Nd defines

stV to udree aIng scb as age conditioning Nd natural aging criteria.

Emergency ieesel Generators
COMONIITe ISSUE REG. Iii11111JR5T

COJ I iAIM COLUP

IEEE (contd)

(a) 3Su

c".U 4146111"

LIFE EVfERSION FEAIUnEI CURRENT IWIIIAiIVES MQI1K OtEM LIFE EXTENSION N M l

...**.ummt******. ML COLUM ? COUMN a COluU 9

Provide principel design ride. an critonr for rocs to set eptolbte design

their functlanet require- bse for possibte mate undr deegig bse" I. cditiens.

IEEE 387 is turrent- ty beln revised.

witI incorpor te Itr. ntdrd 749

ro mml a. J IEEf387 lead aentoens aging 0n "irn _ t techniques.

sn. Provides the tinim= service r~err mnte for the design staff (ME) inctudir operatiormt cycles.

operationaet hour teratures (Me. nd Nor)- Wteooe eiore me. radiation, isuidity, air qt'ity

etc., i.e.. itt the conditoris that houeld be con- iderd In the deslgn. fortysewn (47) design nd

QePPletotn considerations ar given in the

stwbrd.

(9) EXTEuiMt EFviOM- WNETAL FACTO3I,

INCLUDING:

*CHEMiICALS

*OIL$ AND (DMWTiIN PROUCiTS

PATENIA. am NFLATS/(DITACTS

*NATURAL PiWKMi- ESA-EAMTNWgMte,

FIRE ANDi FLOWS,

ETC.

, ei

t10 CF1 50.49 Provides that UWirFon mental specifications be mkitted for electricat afety-retated aqui _t

that sderee viron- m*ntat f etors. e.g., agirq, radiation, teopersta, axd buMxdl Cty, a other condition, e.g., tee of wristiine,

vibrations, ed pipe broks.

Adreaest aging .nd degr dxtion

Issues eomelcabie to enitl*rr of piant for Li..

11n. Are the epecifictioen sufficient for urrent

rgat-tie cedititl?

10 CFOt 50 CDC of ApptodIx A inetud- Addess sturat

APPndix Ir47 2 and 4 reptre ptnin design hss for natural

ptenn, e.g., flon

a4n earthmkeo. rnd effeiles,. e.g., En0 not

be coetibte with normt Operation, accidents sd postutated sislf tIn, sod

pipe dhip,

2.4.2 Refers to 10 Cn! sO MC, (iginit design Criterion 2, 5

cmonots conaiders flood

iepxrtont to safety beins design sod local designed to siofetond the pracipitation,

affecta of iurricones, I.e., this wilt

floode, teou4al and provide rO oltheb.n Ato referm to history. A flood

10 cPR 150 for Identify- history up-dete is

Inse and wlustirm alto required.

hydrologi featurese of

the dite.

#/A tn. tI the ptent a urrent

stotla the so or he a change in selsic cate- gery developed since

original tlicene?

U". Na. is the origin t design ThM CRi principelly provides the criteria for the

odb~te for curront orilinal design. the CnU deft not adress the aging conditiaw, i.e., hai Issues.

the history changed

-- Romergy Dieel orwators
(12)

EXIERMAL t£YftI-M SEJITAL FACTORS

(contd)

LIFE EXTEMlSWm

AE6. ISSTtsoiWo AGING FEATURIS FEATUREli CLUUNT INIIIAIIVS "Jim WANo Lift fAT&shiW VMtS =UOEMT

laft (santd)

3.5.1.1

Relfor to 10 CII 50. AppnidX A, QDC, Criterion

2, for leiteic clossifi- cation to withstand earthntaes without a toe of obitty to perfor. safety functions. AMoo refers te 10 CiI

tO, Apondix A. for the

ptrforoc* tsE).

inltuodirn standl aetl

generator suxiliary systm.

Provides for reiew. and Acceptance of Intenet

and "tstarl m1ssi1e

protection for osfety

reqirad for sofe i"thdon of the plant. Thi ultimatly mitivetes

e or deradtion to the i00 ystem fr0*

01*"11.6.

010M.

The protection mat be for the

life of the plant.

limo. verify that the Ca The tIi principttty providoe the criteria for the

nonts xSismic catWorJoe original dtsignr The CiI do40 not m s the &gfra

huie not chwreed. 'Iwe.

(is) a. SO.,. lone, untles densin hose thiea rqirmnta are princilpely stert-up hoe chaned to marrant rawiroeta, bit rmIn in effect for the lIfe of

ad4itionlt protection the plant. from miassie.

(146 3.11 Provides for eccaptneo criteria stipulatigr thet

the sechanical coaponmot ill ptrfrom stisfactority for the 0

tewth of tifs for 1rh41 its functin is raiired for

hard iA td

awlvosant- .

7.1 Provides acceptance

criteria of Inotrun- tatien nrd controls.

Refers to ID Cl so. wte anr 56E 279 for design basis for noturol ti-

£o, and amwlrnsentot ca eo .

Provides records

for onvirormntat

acceptane and watiftfation.

S/A Should he oacifitc in

etotine thet sccepterae

bcitd he esintainod swar the (ift of plant.

Accaptaas criterio

neodsd for Lit.

Acceptance crilorio

nrmW for La.

This Is principally an acceptate criteria star.dd;

the sP 0do not odorosa the life of plant lasuts.

Althougi the W do" not discuss seine or Li, the

W r lrmesnte whoutd bo usaful to apinr mlee

net L Oif adpoIt records re mIntolnod for

the tife of the plant.

(15) Provides accp- trnce criteria

records. $04

table 7.I. t Acc

tance Criteria.t

Should be specifit In

Sattin that accptance

shpuld be mintained enr the life of plant.

(06) 9.5.4 EDO tatartino) enstn

fuel olt - raview dater- mine the watity of the

ngrins fust Oit. System shoutld h free from oil

degradation to prevent aetins fsilote.

ProvIde s cop tawe criteria md records.

Son. Sons. Accaptance criterie needed for LI. Attouoh the SO doeo not discuss wing or LI. the

9 reiiremsnta should be useful to oaslow mae- et and LI if the raquirsent we aet ad adowats

records w Mintained Ie for the lif of the pint.

Atthough the SW dons not discses wain or Ia, the

W reoirominta Should be useful to seinl _weont end La if the rCtwirnt are aet end seopate retOrdt WIe sinttain d for the lihf of the plant.

(17) 9.5.6 DC mrins stort-systm - Provides records

review rCairx drter- for syste_ st*tus.

minieg the adsqjscy of the qoelty snd condition

Of the air 04pVy

Clan, dry ait reuired.

Ma . Acroptance criteria needed for LO.

-- Ircy Dieel Ganorstors
(XV1tRET

(OM) EXTERnAL tINVIMMYI PACMKS (contd)

RED. IVS715tMIN AGN EAUE FEAMS! (tU INIIIATIVES ACIMQ NEEDS LIFE EXIENSICE NEEDS Cto MS mos cmut,

SRic (contd)

9.5,.

(19) 1.29

1.100

EDW Ongin ib systm - tIb oilt temperatue mat be meintained.

EDC not be designed for seismic cateory I for

55E occurrnes.

Seimic qualifications. principtes, prte* es nd _ td .

1Mor.

1mwe.

NOMe.

5m.

KfA

P/A

Systm records.

The originel design

at be adaquet, for

Current known seismic condition or postuloted conditions.

Li queetios shuld be addresed In the M.

(20) lefers to IEEE *tanhrd 354-87.

(21)

AI Code

Section III Section XI ED1I by definttion are Close 1. 2. ad 3 com Palosz haer, the oft arm not presetre vessels or piping. etc.

11". 1mns. M". Nons. The LASE oe ae required In 10 CPU 50.55e gumisto ISI. The reqirawnto roely Involve iD Lunm a specific rt is designd ad _ut muctured in Wco, . with the Code.

(22) 2.2 Minim Instetntation for syt" irPA of groand rotion to paroide evalustion of dsts

wothuer or not vitrtory intiw hve botn exceeded.

InatrLountation

hcdd provide

records of pltnt service.

M".

N/A MO.

IZri

(23) 2.8 mesthodology Is described to vstaute the fl1o0d having virtually no risk of etceedonce that Vy be maod by precipitation und nsraalt nrd do faitures.

I/A rm.

Nona.

1mw.

None.

Nam.

(24)

(25)

2.10 Defines tE typ of tim- eords of piant ing of plant ower activ- activities that itie requsired in the my assist In LU. ont of on *artiunke nd includes specific

procedures for the evetu- otion of records obtalind fros seismic inetruRentatin specified In AN. 2.2-19Th.

W/A Mons.

2.12 provides gufde(Iewe that sllom reactor designer

to select hazards. e.g.,

neturat, _t-de or cdabinetione of hazards. that effect thE design of syston and comonts.

NO. X/A M".

tergy E- Dieslt generators
ar

(26)

(21))

(25)

(29)

iE5TA. FACTORS

(contd)

REG. sesrosesmr

306

LIFE EXTENSION A01.5 FGAV1R1 FEA1IRES a*ISMINTIiTIATIVES Asieg NUN ~ LIFE EXTEsSIWN NEESO COaUsa AOUI CO M AcDLlsI 7 (aCuLM a COMMENS

9OL

Design be criteria for Provides an eccrp- tins IE qwipmnt to toble design bee ende the. to met their for possible I.R

furctenak rsqaltmaats.

bone.

3Z3 Se~ s adro ability to Acceptane and

perform safety Function lmtifyins th_ to agisg, itetudins records.

factors of nerteal nd uwirormental cordttioas

that mat be addresd.

344 Entabttshe. reced Acceptcand _ nd practices to obtain dtu rpatifying to quatify that the recorde. etipmmnt wilt perform one SE after an CE. inclusd ae taste for

vibratiornl aging. eis- sic asten plus noerm operation toad.

3d7 Provide. prisnipet design Provideeson Accri- criteria for EDli to _est table design base their funtianal require- for poesibte LA. mtts under design be conditiors.

Mon.

More.

Ibse. Inetinc ud pr systems, e.g.* diesel generators; design bas includeb matfirctierm. accidents or operating mdee that could lead to degradation of the syst_. Ntlfuctionr are defined as uturtl phutume. e.g., serthqa kee ndml tooas rd poDtutated peen merm. e4.*evrormantat factor. of presser hamidity, trpenature.. and accidents,

e.g.. fires.

Nam. IEc Rtamird 323 an aopd to other instrnewnto resvid recognitz the need for aseie and define stepe to 6eee atgre ouch as s conditioning nd nrtural aging crit rie.

Sa.

lone. Proridee the *iMA service reqirmente for the design staff (AU) Including operational cyctes, operational hours. ta" tures ("K. end min.), saelsic roop e. radiation, hueidity, and air "lity, i.e.. alt the oandittoe that should be censidered in the design. Fortysevon (47) design and epplication cormiderationr ar given in the

*tand"r

Stndeard as being revised by 111

uorking group 4.2.

M.

..

IlNerasuAL thElItCAL.

(30) PCYSICAL PROCESSE,

* COK505IWN IN All

* TKANhUL 5lOCK

f9.5.7 EOt engins tuthe aystm- ecordr of accep- revie. determines if the tems criteria. tub syatce prevente

deteterioue Mtertal fro thewt shock entering ths tab olt system.

tDC air intake syste - lecorde of accep- revie. determines that no tan, criteria. tern dearadation wilt be e*perienced during

fmel.. pomep output

(contitrexe) etttngs.

one. lebd. acceptane

criteria re-established.

one. "Ofd 409"ptmce

criteri re-ertablishad.

(31) 3.5.1

' leretcy Diesel Generators
coa1t ISSUE REG. INSTRUMEIIT AGING FEATURES COUMNI 1 OMt 2 CLUM 3 CLMN 4

LIFE EX5755ION

FEATWRES OURKET IN ItIATIVES AGING NEMS LIFE EXTENSION NWV"

CO~LON COUM COLUMN 7 taCLUNI a WTI liles 0

INFESNAL CREMICN.

(32) PlIISICAL PNOS5SSES. AND ttflNOSIOi

(contd)

ANE Co

Section III Section Xi EDGt by definition are Clons 1 2, ma 3 cor, penrts; however, the EDGs art not presure v ssels or piping, etc.

ProvidM design be criteria for Cless IE quipmnt to enebl the to met their functional

rewiramonts.

ir. Wr. The AHE codes as raqtred in tO CFt 50.55. ondete ISI. Thebe requirents rarely itnwolve EGG untens gecif ic pert t desind And swif actured in accordulce with the Code.

IEfE

(33) 306 Provide. oncc_ table dekien biee for poesible Lt.

iMa. Nam. Inludne power eyet_, e.g., diesel gueerators

dteign be" include mlfueclions. celdents, or opereting mxs that could tod to degradetion of the stems. eltfunctione are defined oS naturel phanaens. e.g., eertheakes _nd flooh, amd po.- tutated phermam. e.g.. aiviramental tfactors of preesue, huidity. terature nad eeidents, e.g., fires.

(34) 38? Providee prienipel deelgn

criteria for ENO to _et their fiactionsl reqoire- wente unuder denimn bne condititons.

Provides an scco Sta.dird Is being tbtle deslgon bne revised by IfiE for possible it. working group 4.2.

Nar. Iont. Providee the minimum eryice reyiresom" for th deign staff (AE) including oeprtionel cycles,

operationl hours, teturen tox. and min.).

aimagic reonse, radiation, humidity, air qeatity etc.. I.e., all the conditionr that should be contidered In the desipn. Fortyseven (47) deeign and appticatien considerationn are given In the stedrd.

(35) 323 Ability to parfors aefety fiwetion do to the effect of aging at be adereeed. Types of eging Include therea condition.

Acceptmnee end qielifying

records.

Worn. Now. IEEE Ctmuderd 323 os oppoed to other Instruments reviewed recoomizee the need for aging and deMines

et" to av eea aging such os age conditioning and natural aging criteria.

(36) * lINSPECTION

EXCESSIVE, HANStS

TESTING K ALADJUSflENT/

DIISASSEMBLY FOR

(3?)

TIS

3/4.8 None. ono. PIIL stlff through The TUe should consider the NPAR program aging eeduaniaes/aging

Technicl Sppecifl- I cation Aging Task are adreseing the Te for aging

_ie esnt.

Provide evidence that the Te rwe adequet. for

ticee rel., i.e.. are chengee needed in the Tie for In

Oeacribee einlIs AC electrical power requirements

for operating Red shutting doun pl nts.

3/4.8.1 oper- eting stetui

md 3/4.8.1 shutdoen stetus

Surveillane efforts Inspection would detect on Ioeor- record. abl. arerstor by virtue of the necessity to essure on operable

Generateor, _rgant of aging sle iplied.

None. Not o it cble. Records of _intanmeo

Inpection eould provide evidence for setmd Lue of the dienat

generator.

Seergmncy Dieset GeneratorA
a2,01T Is"I

SO*ILLANCA (contd)

(38)

(39)

(40)

(41)

(42)

(43)

MG. INSTRUMEN AGING FATtiES

CO)LUM I Calum 4

UT5

8.1 Appwidis tis of gnrator far 8-A Posting p06e4 1s not

TP ICU(PSB)-B alttWAd; pr*itS ue of Ger-tor In noergency

situatiore.

8.3.1 Provides review nid

optiam criteria for

Operation of stmntby

gegrstor sets, as

ailty me related cpeation at tee than full

toad with no dearedation

for extendmi periods en that no load conditions

shltt be minlimid.

Stipuastes that staff training, testing, praventative mintonance aid repair procedures mitt be

matntained.

8.3.1 STP-8 Provides restrictions for

(PSS) using the too for peak poer situatlion aid

restrict& ovarie of the

EBD.

9.5.5 iSC ogine cooting eater system - review detersines the adequcy of inpection aid testing of the tooting weter System.

9.5.6 106 starting systm -

review deteridnas adaqjaty of the inspettion And testing of starting

syate_.

9.5.4 MAo fuel oil syste -

review doteruines ada- CIANy of insection and testing of fuit oit

systow.

9.5.7 EDO aigine tue syste_

review determines the

odeqiacy of the Iapet- tit0 Ad testing of engine lub system.

LItfE ETEhSIti

FEATLREIS ClAst itNtItATIES AGING IM10 LIPF EXTENSliON IEtS

a S .. tOlLM 6 . ttClUi 7 CULeIN a

Should provide 7 /A I/A

record of uwe

i.*.. total esrvice hurs.

Provides records 1 n. Is the acceptance cri- For LK, the rtd for ace tcce of lret usefut for tlng- _itntee training

stand-by power tern 7saurM that the mat he ahOsn to he adaspplies. EN0 witt be retlb bt, quate for rolltificsnot derade over time. tic" of the to".

eiaiS

auau 9

The UP does not seScificaiy address aging or L*;

however, strongly implies aging Mangegmnt ard La becahe the Mt gtatft the EiO shell not be oa- j)eted to degradation. This my he aased to cover

the life of plant mAd heyod.

Limit* deargration of owimint ord

provides far a

longer and wefut

life.

should provide -demc recorde Wd status for cooling water eyets retative to

La.

should provide

- records

and statue for starting syste

Should provide

adquc recorde and statue for

faiul oil syst.

Mould provide

adequscy records

and status for

engine dai system.

bone. ban. Per Li, the rfw ired operating restrictima

aet be sham to he usefuh for life

extonmim.

gon.

The aiP provides aging Manegment by Specifically

restricting the wu or peek power needs And

cntrolling nrwancy ue of the EGG. The BTP

ressae the prevention of com falilure mode of

the EN me related to win or off-site power.

Although the GAP does not xptlicitly discues aging

_ngn or Lk, the reqirints should rt La ISadec records we eintalned throughout the IIf of the Tplant.

arn.

t1e.

bane.

gne. Atthou6h the AP does not explicitly disouga agirn _nmeinnt or La, the raqirents should i rt it if adm*te rcords ae esintined thrWusht the

tife of the plant.

arnie. Atthoudh the SP dose not explicitly disass aging

_mgmun or La, the reqiremants should a ot Lit if adeate records Are esintained throuxot the

life of the plant.

bin. Attheoih the SW does net explicitly disuss aging

_ _neeft or LI. the reWqironts should e.port LI If adeute re ord _ainteined thrmuihout the

lfe tof the pi nt.

-- Eergency Diesel Gineratore
MM 1

(45)

Is"E

gtWALLAiit Ccmtd)

LIFE EKTEWSIOH

REG. tnNSTKWT AGING FIARREE FEA1WES CURRNTr INITIATIVE AMING NEMD LIFE EXIIINSIDO Muns

M1.10. iISa 4 - CLUN COUM 6 MM 7 MtOON a

1TE COLUMN 9

MiPs (Ccntd)

9.5.6

(46) 13.2.1

EDG agine cosea timn - vi determines the

adequacy of the Inspec- tim ard testing of

nirn*e tobtian systes.

operators and ether nonticansed plant staff

ttainini - the pant staff w, to be trained

to us the EGxs correctly. This lopli.. seine

mgeesift.

Should prvde sdv y records and statum for the

nuine celastion

systet.

Should provide

plant staff perforeance training records, I.*..

adeqacy of our- rent staff.

on. Ine. AMOht the sRP doen not explicitly discuss swir4

MO_ it or LK, the nqeirnt sheutd agprt La if adeqate records re seintained throughout the

if e of the plaint.

Gone. Anr the aernnt records ip to dote for present

staff for adequate LU documentation?

The plaint staff re expected to bnmw how the EDO

operates and performs; frthermore. they are expected to 1m how the fDC Interacts within (Other) plait ntafety-relted Systm. DoCsewntatim

of training and d trations of trained staff could anhdee eing nIt aid L apptlicatiens.

(4?) 1.9 Provides quilification

and periodlic testing, teat _hje and survitl anea ard sintee

0jidence.

Provides records

Nd records - keeping criteria and reporting criteria.

ey be impacted by SPAR EDG studins by

PiL. The aiC hxa

Iaued 1.9 Rev. 3

for eoints,

Nove r 19i .

" Mellato of feat

start testing, Startri-ceolddome raeire- wits era need to ndn agine streseora.

Corrent statumeconition No 1.9 referencen 10 CMR 50 Apeedix A. Criteriemn

of the quipent shoud 17 and 12S aid Appaidix *, Criterion Xl. be -adesesd for Lk..

(48) Safety Guide Ettblibaes regulations OA docurentation.

OWr 30 for GA relative to testing of electrical

ewipment. References

ANll 145.2 and IEEE-336.

1.33 Lefere to overal i earat lptied by

criterion for NPP documentation. operatioL

Status of r ecd ad recordieeping _ethod

need to be verified for

La.

Safety guide referente tO Cx 50 Appendix N, 01 criterion for epa.

(49) 2/A A need exists to deter- mine If the exiting

records aid Oh doerntation are admsato for

La.

(SO)

(51)

1.41 Provides quidune for tenting after a _Joer

modificatio.

1.58 Establiee nguidance for the qemLification of MDE

staff tho perform I In e- time, tests Nad *xsina- tlin during the operatime of OPP&.

Provides recorde

history of now Nodlficatials

Provides docuamn- tation of staff eul ififatfen and OA records, I.e., that is the status

of pest NIE

performance?

7 Pefern to AuSl 145.2.6-75.

(52) 1. 10T Estabf ibtel that the FD desin should allow teat- ing. The G *lso defines

the periodlic pr-operatioenl 1S- th testing

rguirmnita

Esteblishes guid- The NIC intends to

ance for recorde delete xC 106. aid recordkeeping. Guidelines will be In revised NG 1.9.

Testing should be Ioproved and ite iehnged to a selm start streesful starting

to avoid fast-start prceirxe accoipa ied streauorn. by a progres of per- forms onitoring and

trouiding are ned.

gee ogecoeuided Practice for Aging Nitigatimn and leqroved Program for Nuieatr Service Diesel

Genretonrs. AImEO-Ci-t-SO0PO-6309.

IMrmegty Dieeln Camrators
tINKNT ISSlE

COLUM I CO tM 2

SURVEILLANCE Icontd)

(53)

tS4)

(55)

(56)

(57)

(58)

(59)

iEC. INSTRUlMT AGING PFEATURES OLUI I~ 3 COLuMM 4

K Code

Section III EDCs by definition ore

Section XI Ctlee 1. 2 aed S

Coonents; however, the EVA6 are not prCOarW vesels or piping, ete.

"la 5-56 Program to Improv the

reliability of EDG;

gl of 951 success establi loed.

CSI-91 Continuad reliability and operability of

Trnsamerica Die vlv

Inc.. EDOG.

ARSo

3.1 Provides criteria for

selection, qlification,

and training of persontel for statio nry nctlear

power pltets.

3.2 Provides recaedstiore end reouirents for

adeinistrative controls,

including oritton proca.

dures, and GA program to help "ere that activities of iPP* are carried out without risk to the

health and safety of the pubttc.

338 Provides desigi end operational criteria for perielic testing of

afety aystem.

336 Provides minilm reouire- wants for inapection and

testing of Clate IE

power, Instrumrenttion,

and control eqoipaint during construction

piree.

LIFE EXlTENSION

FEATUaRES

Catol

CURRINT 1511 EITIVES

SOns.6

Dilset reliability

progr-n with miiC.

Transesarica

DeLaval. Inc.,

Darers Croup.

ACIX C LIFE EXTEISIOA NEW5DS tesr

W lE ,il _ COLUMN a WL.e15 9

Dcne. rone. The ASK cde as reqired In 10 CiA So ffa _rte

ISI. The. rqlrents rarely involve 04 unole a

specific pert as desllgd and _utfctured In

eccordMc with the Code.

Reliability of £0 as a Effecta of reliability de aleo Regulatory Guidoe 1.10Dt iM CO-O660.

functlon of ae; at decreaean licensing. re effects of ag

effects of testing over

time?

Effects of Stress, Can plants with T10 EC issue involves potential min crAhaft failures.

fatituet testing on TDI contirae to operate; km See laso SED8-534, IIH-113-58. NW nd sM-1216 and

tOG reliability - do T0I to verity operability of other madts)

EN show aging effects TDI E C after thirty

faster than other years of service?

models?

Provides eon. Sate. record or

training of staff.

Administrative Inplace controis

illt probbly be

required for t.R.

The essociated OA documentation ittl

he useful for Lit.

CC.-

ac .

a .

Nn.

i1".

.ons.

hon.

A" the activities covered under this standard are dosimn changes, fabricating cltwning, dacon,

Inspecting, testing, maintaining, sed repairing.

This stsrdard doe not _ndresa esintence.

Provides a criteria for correct Installation whieh could effect aging aspect of the oaopmet after

Startup aid operation. Clan II a Wip nt thet

is esaantial to _argecy shutdon, contaIraent isolation, CC, nd CM.

Acceptance testing of conents for

i.R

Racords of construction may be Applicable to La.

Emergency Disel Generators
LIFE EXTENSION COMPONNT ism REG. INSTEUIHENI AGING FEAfIONES FEATIE COHRENT INITIATIVES AGING NEEDS LIFE EIITNSI NEEDS

CJ... I COUSIN .....OL" 3 . MY" 4 .. LUM .. COU COLN5I 7 caumo a

SAWWIILANUc (eestd) IEEE (Contd)

(60) ?49 Provides stersierd for Recotde of post Standsrd mitt be Leos stressfuL. starting Less Stressful stat~ing

assVENts

CTiTm

perledic testinq of EDC perforence. inctudit availablity tests. systen operatlonel

tests. are irdapendence verification tests.

Impacted ty KG I.e. piwemfues am tests. Procesrwe VWD rest. IEEE ptgmm to delete this stanrd.

(61) 934 Provides crit ris for reptlcemnt parts, both con truction aed operation. equires lIspec- titn aed test of perts

prior to releass for

service.

Acceptance testing

mnd reords that

may be otpleasbte

to LI, e.g.. fat- rs revies for

re. tatfupe,

origint defects. md inuleatien

t .eklowm.

tore. None. Stmndard determies selection of reWired prts for

Cleas IE equipment, e.g., identificatimn mrd failur

reviar. Ibreve . required design chins sre Otside

tre scope of this stmerd.

IC-

-- Emerency Diesel Smrwttors
NUREG/CR-5490

PNL-7190

R9

DISTRIBUTION

No. of

Copies

No. of

Copies

OFFSITE

M. Vagins, Chief

Electrical and Mechanical

Engineering Branch

Division of Engineering

Technology

Office of Nuclear Regulatory Research

U.S. Nuclear Regulatory

Commission

6550 Nicholson Lane

Rockville, MD 20852

30 J. P. Vora, Section Leader

Aging and Components

Division of Engineering

Technology Office of Nuclear Regulatory

Research

U.S. Nuclear Regulatory Commission

6550 Nicholson Lane

Rockville, MD 20852

V. N. Shaw

EG&G Idaho, Inc.

P.O. Box 1625, WCB-3

Idaho Falls, ID 83415

ONSITE

49 Pacific Northwest Laboratory

S. H. Bush

J. A. Christensen

M. E. Cunningham A. B. Johnson, Jr. (20)

L. D. Kannberg

J. W. Nageley W. B. Scott

J. C. Spanner S. Somasundaram

E. V. Werry (15)

Publishing Coordination

Technical Information (5)

C. Cerpan, Chief

Materials Engineering Branch

Division of Engineering

Technology

Office of Nuclear Regulatory

Research

U.S. Nuclear Regulatory

Commission

6550 Nicholson Lane

Rockville, MD 20852

Dist.I
NRC FORM 335 US. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER 12491 (Assigned by NRC. Add Vol.. Supp.. Rev.. NRCM 11032, NWiAdndum Numbers. If any.) 3201.3202' BIBLIOGRAPHIC DATA SHEET

(see instrctionson t versl NUREG/CR-5490, Vol.1

2. TITLE AND SUBTITLE PNL-7190

Regulatory Instrument Review: Management of Aging of LWR 3. DATE REPORTPUBLISHED

Major Safety-Related Components MONTH I YEAR

October 1990

4. FIN OR GRANT NUMBER

B 2865

5. AUTHOR(S) 6. TYPE OF REPORT

E.V. Werry Technical

7. PERIOD COVERED lone/surn Datesi

6. PERFORMING ORGANIZATION -NAME AND ADDRESS Nf RC povide 0/v/on. Off/c or Region, U.& Nuclear Reguitorl Commitsson. and mAilfngsdress. :U contracto,. Provide mrm aid mailgF adJmo)

Pacific Northwest Laboratory

Richland, WA 99352

9. SPONSORING ORGANIZATION - NAME AND ADDRESS Ill NRC. pe e as sO v./f consecwr. provIde NRC Div/s/on. 01/we or Region. U.SN Regu/atorComm/u/on.

9.SPO~NSOR jNG ORGANIZATION-NAM EAND ADDRESS JN~cw -. ffaove-ifcracw, pe o pubNfCIiC tro tkbn. Oak- or fgion, U.SN SkvRkw laut tort Cnkon.

and ma/hg addrs.J

Division of Engineering

Office of Nuclear Regulatory Research

U.S. Nuclear Requlatory Commission

Washington, DC 20555

10. SUPPLEMENTARY NOTES

11. ABSTRACT W0O wdor Jm

This report comprises Part I of a review of U.S. nuclear plant regulatory

instruments to determine the amount and kind of information they contain on managing

the aging of safety-related components in U.S. nuclear power plants. The review

was conducted for the U.S. Nuclear Regulatory Commission (NRC) by the Pacific Northwest

Laboratory under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected

regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations,

were reviewed for safety-related information on five selected components: reactor

pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel

generators. The focus of the review was on 26 NPAR-defined safety-related aging

issues, including examination, inspection, and maintenance and repair; excessive/harsh

testing; and irradiation embrittlement. The major conclusion of the review is that

safety-related regulatory instruments do provide implicit guidance for aging management,

but include little explicit guidance. A major recommendation is that the instruments

be revised or augmented to explicitly address the management of aging.

12. KEY WORDS/DESCRIPTORSIst wt os that , iag/t ie n locating the wport.i 13. AVAILABILITY STATEMENT

unlimited

Regulatory instruments, safety-related components, codes and 14. SECURITYCLAMIFICATION

standards, guides, general design criteria, life extension and fr~s,,

life extension needs, aging management and aging issues including: unclassified

corrosion, erosion, environment effects, harsh testing, wear, (Th/sRaporJ

embrittlement, fatigue. unclassified

15. NUMBER OF PAGES

16. PRICE

NFRC FORM 335 1249)
THIS DOCUMENT WAS PRINTED USING RECYCLED PAPER.
UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 2055

OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

SPECIAL FOURTH-CLASS RATE POSTAGE r FEES PAID

USNRC

PERMIT No. G-ti7