NUREG-1801, Vol.1, Rev. 1

Generic Aging Lessons

Learned (GALL) Report

Summary

Manuscript Completed: September 2005

Date Published: September 2005

Division of Regulatory Improvement Programs

Office of Nuclear Reactor Regulation

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001
NUREG-1801 Vol. 1, Rev. 1 ii September 2005

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September 2005 iii NUREG-1801 Vol. 1, Rev. 1

ABSTRACT

NUREG-1801, “Generic Aging Lessons Learned (GALL) Report,” is referenced as a technical 

basis document in NUREG-1800, “Standard Review Plan for Review of License Renewal 

Applications for Nuclear Power Plants” (SRP-LR). The GALL Report identifies aging 

management programs (AMP), which were determined to be acceptable programs to manage 

the aging effects of systems, structures and components (SSC) in the scope of license renewal, 

as required by 10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear 

Power Plants.” 

The GALL Report is split into two volumes. Volume 1 summarizes the aging management 

reviews that are discussed in Volume 2. Volume 2 lists generic aging management reviews 

(AMRs) of SSC that may be in the scope of License Renewal Applications (LRAs) and identifies 

GALL AMPs that are acceptable to manage the listed aging effects. Revision 1 of the GALL 

Report incorporates changes based on experience gained from numerous NRC staff reviews of 

LRAs and other insights identified by stakeholders.

If an LRA references the GALL Report as the approach used to manage aging effect(s), the 

NRC staff will use the GALL Report as a basis for the LRA assessment consistent with 

guidance specified in the SRP-LR.
NUREG-1801 Vol. 1, Rev. 1 iv September 2005

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September 2005 v NUREG-1801 Vol. 1, Rev. 1

TABLE OF CONTENTS

Page

ABSTRACT............................................................................................................................... iii

LIST OF CONTRIBUTORS – 2004-2005................................................................................. vi

ABBREVIATIONS ..................................................................................................................... viii

INTRODUCTION ..................................................................................................................... 1

BACKGROUND ........................................................................................................................ 1

OVERVIEW OF THE GALL REPORT EVALUATION PROCESS ......................................... 2

APPLICATION OF THE GALL REPORT ................................................................................ 3

APPENDIX: LISTING OF PLANT SYSTEMS EVALUATED IN 

THE GALL REPORT (VOLUME 2)...................................................................... A-1

LIST OF TABLES

Table 1. Summary of Aging Management Programs for the Reactor Coolant

System Evaluated in Chapter IV of the GALL Report............................................ 7

Table 2. Summary of Aging Management Programs for the Engineered

Safety Features Evaluated in Chapter V of the GALL Report ............................... 31

Table 3. Summary of Aging Management Programs for the Auxiliary 

Systems Evaluated in Chapter VII of the GALL Report ......................................... 47

Table 4. Summary of Aging Management Programs for the Steam and Power

Conversion System Evaluated in Chapter VIII of the GALL Report ...................... 67

Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of 

the GALL Report ..................................................................................................... 77

Table 6. Summary of Aging Management Programs for the Electrical

Components Evaluated in Chapter VI of the GALL Report ................................... 93
NUREG-1801 Vol. 1, Rev. 1 vi September 2005

LIST OF CONTRIBUTORS 

License Renewal and Environmental Programs Section of Division of Regulatory Improvement 

Programs, Office of Nuclear Reactor Regulation

P.T. Kuo Program Director

S. Lee Section Chief

S. West Section Chief

J. Zimmerman Section Chief

J. Dozier Team Leader

K. Chang Mechanical Engineering

K. Cozens Materials Engineering 

G. Cranston Reactor Systems Engineering

D. Guha Systems Engineering

M. Heath Mechanical Engineering

S. Hoffman Mechanical Engineering

A. Hull Materials Engineering

K. Hsu Materials Engineering

M. Lintz Mechanical Engineering

D. Merzke Mechanical Engineering

K. Naidu Reactor Engineering

J. Rajan Mechanical Engineering

R. Subbaratnam Mechanical Engineering

T. Terry Civil Engineering

L. Tran Electrical Engineering

P. Wen Electrical Engineering

Office of Nuclear Reactor Regulation

T. Chan Section Chief

S. Coffin Section Chief

S. Jones Section Chief

R. Jenkins Section Chief

L. Lund Section Chief

R. Karas Section Chief

K. Manoly Section Chief

M. Mitchell Section Chief

J. Nakoski Section Chief

D. Terao Section Chief

S. Weerakkody Section Chief

H. Ashar Structural Engineering

S. Bailey Mechanical Engineering

T. Cheng Structural Engineering

R. Davis Materials Engineering

B. Elliot Materials Engineering

J. Fair Mechanical Engineering

G. Georgiev Materials Engineering
September 2005 vii NUREG-1801 Vol. 1, Rev. 1

LIST OF CONTRIBUTORS (continued)

A. Keim Materials Engineering

N. Iqbal Fire Protection Engineering

D. Jeng Structural Engineering

K. Karwoski Materials Engineering

C. Lauron Chemical Engineering

L. Lois Reactor Systems Engineering

Y. Li Mechanical Engineering

R. McNally Mechanical Engineering

J. Medoff Materials Engineering

D. Nguyen Electrical Engineering

A. Pal Electrical Engineering

K. Parczewski Chemical Engineering

J. Strnisha Mechanical Engineering

P. Shemanski Electrical Engineering

Office of Nuclear Regulatory Research

A. Hiser Section Chief

J. Vora Team Leader

J. Davis Materials Engineering

P. Kang Electrical Engineering

Parallax, Inc

A. Baione Team Leader

M. Bowman Mechanical Engineering

D. Jones Programming

K. Larsen Technical Editing

E. Patel Mechanical Engineering

R. Wells License Engineering
NUREG-1801 Vol. 1, Rev. 1 viii September 2005

ABBREVIATIONS

ADS automatic depressurization system

AFW auxiliary feedwater

AMP aging management program

ASME American Society of Mechanical Engineers

B&W Babcock & Wilcox

BWR boiling water reactor

BWRVIP boiling water reactor vessel internals project

CASS cast austenitic stainless steel

CE Combustion Engineering

CEA control element assembly

CFR Code of Federal Regulations

CFS core flood system

CLB current licensing basis

CRD control rod drive

CRGT control rod guide tube

CS carbon steel

CVCS chemical and volume control system

DHR decay heat removal

DSCSS drywell and suppression chamber spray system

ECCS emergency core cooling system

EDG emergency diesel generator

EQ environmental qualification

FW feedwater

GALL generic aging lessons learned

HP high pressure

HPCI high-pressure coolant injection

HPCS high-pressure core spray

HPSI high-pressure safety injection

HVAC heating, ventilation, and air conditioning

IASCC irradiation-assisted stress corrosion cracking

IGA intergranular attack

IGSCC intergranular stress corrosion cracking

IR insulation resistance 

IRM intermediate range monitor

ISI inservice inspection

LER licensee event report

LG lower grid
September 2005 ix NUREG-1801 Vol. 1, Rev. 1

ABBREVIATIONS (continued)

LP low pressure

LPCI low-pressure coolant injection

LPCS low-pressure core spray

LPRM low-power range monitor

LPSI low-pressure safety injection

MIC microbiologically influenced corrosion

MSR moisture separator/reheater

NEI Nuclear Energy Institute

NPAR Nuclear Plant Aging Research

NPS nominal pipe size

NRC Nuclear Regulatory Commission

NSSS nuclear steam supply system

NUMARC Nuclear Management and Resources Council

ODSCC outside diameter stress corrosion cracking

PWR pressurized water reactor

PWSCC primary water stress corrosion cracking

QA quality assurance

RCCA rod control cluster assembly

RCIC reactor core isolation cooling

RCP reactor coolant pump

RCPB reactor coolant pressure boundary

RCS reactor coolant system

RG Regulatory Guide

RHR residual heat removal

RWC reactor water cleanup

RWT refueling water tank

SBO station blackout

SC suppression chamber

SCC stress corrosion cracking

SDC shutdown cooling

SFP spent fuel pool

SG steam generator

SLC standby liquid control

SRM source range monitor

SRM staff requirement memorandum

SRP-LR Standard Review Plan for License Renewal

TLAA time-limited aging analysis

UCS Union of Concerned Scientists

UV ultraviolet
NUREG-1801 Vol. 1, Rev. 1 x September 2005

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September 2005 1 NUREG-1801 Vol. 1, Rev. 1

INTRODUCTION

NUREG-1801, “Generic Aging Lessons Learned (GALL) Report,” is referenced as a technical 

basis document in NUREG-1800, “Standard Review Plan for Review of License Renewal 

Applications for Nuclear Power Plants” (SRP-LR). The GALL Report identifies aging 

management programs (AMP) that were determined to be acceptable to manage aging effects 

of systems, structures and components (SSC) in the scope of license renewal, as required by 

10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants.” 

The GALL Report is comprised of two volumes. Volume 1 summarizes the aging management 

reviews that are discussed in Volume 2. Volume 2 lists generic aging management reviews 

(AMRs) of SSCs that may be in the scope of license renewal applications (LRAs) and identifies 

GALL AMPs that are acceptable to manage the aging effects. 

If an LRA references the GALL Report as the approach used to manage aging effect(s), the 

NRC staff will use the GALL Report as a basis for the LRA assessment consistent with 

guidance specified in the SRP-LR.

BACKGROUND

Revision 0 of the GALL Report

By letter dated March 3, 1999, the Nuclear Energy Institute (NEI) documented the industry’s 

views on how existing plant programs and activities should be credited for license renewal. The 

issue can be summarized as follows: To what extent should the staff review existing programs 

relied on for license renewal in determining whether an applicant has demonstrated reasonable 

assurance that such programs will be effective in managing the effects of aging on the 

functionality of structures and components during the period of extended operation? In a staff 

paper, SECY-99-148, “Credit for Existing Programs for License Renewal,” dated June 3, 1999, 

the staff described options for crediting existing programs and recommended one option that the 

staff believed would improve the efficiency of the license renewal process.

By staff requirements memorandum (SRM), dated August 27, 1999, the Commission approved 

the staff’s recommendation and directed the staff to focus the staff review guidance in the 

Standard Review Plan for License Renewal (SRP-LR) on areas where existing programs should 

be augmented for license renewal. The staff would develop a “Generic Aging Lessons Learned 

(GALL)” report to document the staff’s evaluation of generic existing programs. The GALL 

Report would document the staff’s basis for determining which existing programs are adequate 

without modification and which existing programs should be augmented for license renewal. The 

GALL Report would be referenced in the SRP-LR as a basis for determining the adequacy of 

existing programs.

This report builds on a previous report, NUREG/CR-6490, “Nuclear Power Plant Generic Aging 

Lessons Learned (GALL),” which is a systematic compilation of plant aging information. This 

report extends the information in NUREG/CR-6490 to provide an evaluation of the adequacy of 

aging management programs for license renewal. The NUREG/CR-6490 report was based on 

information in over 500 documents: Nuclear Plant Aging Research (NPAR) program reports 

sponsored by the Office of Nuclear Regulatory Research, Nuclear Management and Resources 

Council (NUMARC, now NEI) industry reports addressing license renewal for major structures 

and components, licensee event reports (LERs), information notices, generic letters, and 
NUREG-1801 Vol. 1, Rev. 1 2 September 2005

bulletins. The staff has also considered information contained in the reports provided by the 

Union of Concerned Scientists (UCS) in a letter dated May 5, 2000.

Following the general format of NUREG-0800 for major plant sections except for refueling 

water, chilled water, residual heat removal, condenser circulating water, and condensate 

storage system in pressurized water reactor (PWR) and boiling water reactor (BWR) power 

plants, the staff has reviewed the aging effects on components and structures, identified the 

relevant existing programs, and evaluated program attributes to manage aging effects for 

license renewal. This report was prepared with the technical assistance of Argonne National 

Laboratory and Brookhaven National Laboratory. As directed in the SRM, this report has the 

benefit of the experience of the staff members who conducted the review of the initial license 

renewal applications. Also, as directed in the SRM, the staff has sought stakeholders’ 

participation in the development of this report. The staff held many public meetings and 

workshops to solicit input from the public. The staff also requested comments from the public on 

the draft improved license renewal guidance documents, including the GALL Report, in the 

Federal Register Notice, Vol. 65, No. 170, August 31, 2000. The staff’s analysis of stakeholder 

comments is documented in NUREG-1739. These documents can be found on-line at: 

http://www.nrc.gov/reading-rm/doc-collections/.

Revision 1 of the GALL Report

The GALL Report has been referenced in numerous license renewal applications (LRA) as a 

basis for aging management reviews to satisfy the regulatory criteria contained in 10 CFR Part 

54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants,” Section 54.21, 

”Contents of application – technical information.” Based on lessons learned from these reviews, 

and other public input, including industry comments, the NRC staff proposed changes to the 

GALL Report to make the GALL Report more efficient. A preliminary version of Revision 1 of the 

GALL Report was posted on the NRC public web page on September 30, 2004. The draft 

revisions of GALL Vol. 1 and Vol. 2 were further refined and issued for public comment on 

January 31, 2005. In addition, the staff also held public meetings with stakeholders to facilitate 

dialog and to discuss comments. The staff subsequently took into consideration comments 

received (see NUREG-1832) and incorporated its dispositions into the September 2005 version 

of the GALL Report.

OVERVIEW OF THE GALL REPORT EVALUATION PROCESS

The results of the GALL effort are presented in a table format in the GALL Report, Volume 2. 

The table column headings are: Item, Structure and/or Component; Material, Environment; 

Aging Effect/Mechanism; Aging Management Program (AMP); and Further Evaluation. The 

staff’s evaluation of the adequacy of each generic aging management program in managing 

certain aging effects for particular structures and components is based on its review of the 

following 10 program elements in each aging management program:

AMP Element Description

1. Scope of the program The scope of the program should include the specific structures 

and components subject to an aging management review.

2. Preventive actions Preventive actions should mitigate or prevent the applicable 

aging effects.

3. Parameters monitored or 

inspected

Parameters monitored or inspected should be linked to the 

effects of aging on the intended functions of the particular 
September 2005 3 NUREG-1801 Vol. 1, Rev. 1

AMP Element Description

structure and component.

4. Detection of aging effects Detection of aging effects should occur before there is a loss of 

any structure and component intended function. This includes 

aspects such as method or technique (i.e., visual, volumetric, 

surface inspection), frequency, sample size, data collection and 

timing of new/one-time inspections to ensure timely detection of 

aging effects.

5. Monitoring and trending Monitoring and trending should provide for prediction of the 

extent of the effects of aging and timely corrective or mitigative 

actions. 

6. Acceptance criteria Acceptance criteria, against which the need for corrective action 

will be evaluated, should ensure that the particular structure and 

component intended functions are maintained under all current 

licensing basis (CLB) design conditions during the period of 

extended operation.

7. Corrective actions Corrective actions, including root cause determination and 

prevention of recurrence, should be timely.

8. Confirmation process The confirmation process should ensure that preventive actions 

are adequate and appropriate corrective actions have been 

completed and are effective.

9. Administrative controls Administrative controls should provide a formal review and 

approval process.

10. Operating experience Operating experience involving the aging management program, 

including past corrective actions resulting in program 

enhancements or additional programs, should provide objective 

evidence to support a determination that the effects of aging will 

be adequately managed so that the structure and component 

intended functions will be maintained during the period of 

extended operation.

If, on the basis of its evaluation, the staff determined that a program is adequate to manage 

certain aging effects for a particular structure or component without change, the “Further 

Evaluation” entry would indicate that no further evaluation is recommended for license renewal. 

Chapter XI of the GALL Report, Volume 2, contains the staff's evaluation of generic aging 

management programs that are relied on in the GALL Report, such as the ASME Section XI 

inservice inspection, water chemistry, or structures monitoring program. 

APPLICATION OF THE GALL REPORT

The GALL Report is a technical basis document to the SRP-LR, which provides the staff with 

guidance in reviewing a license renewal application. The GALL Report should be treated in the 

same manner as an approved topical report that is generically applicable. An applicant may 

reference the GALL Report in a license renewal application to demonstrate that the programs at 

the applicant’s facility correspond to those reviewed and approved in the GALL Report.

If an applicant takes credit for a program in GALL, it is incumbent on the applicant to ensure that 

the plant program contains all the elements of the referenced GALL program. In addition, the 

conditions at the plant must be bounded by the conditions for which the GALL program was 

evaluated. The above verifications must be documented on-site in an auditable form. The 

applicant must include a certification in the license renewal application that the verifications 

have been completed. 
NUREG-1801 Vol. 1, Rev. 1 4 September 2005

The GALL Report contains one acceptable way to manage aging effects for license renewal. An 

applicant may propose alternatives for staff review in its plant-specific license renewal 

application. Use of the GALL Report is not required, but its use should facilitate both preparation 

of a license renewal application by an applicant and timely, uniform review by the NRC staff.

In addition, the GALL Report does not address scoping of structures and components for 

license renewal. Scoping is plant specific, and the results depend on the plant design and 

current licensing basis. The inclusion of a certain structure or component in the GALL Report 

does not mean that this particular structure or component is within the scope of license renewal 

for all plants. Conversely, the omission of a certain structure or component in the GALL Report 

does not mean that this particular structure or component is not within the scope of license 

renewal for any plants.

The GALL Report contains an evaluation of a large number of structures and components that 

may be in the scope of a typical LRA. The evaluation results documented in the GALL Report 

indicate that many existing, typical generic aging management programs are adequate to 

manage aging effects for particular structures or components for license renewal without 

change. The GALL Report also contains recommendations on specific areas for which generic 

existing programs should be augmented (require further evaluation) for license renewal and 

documents the technical basis for each such determination. In addition, the GALL Report 

identifies certain SSCs that may or may not be subject to particular aging effects, and for which 

industry groups are developing generic aging management programs or investigating whether 

aging management is warranted. To the extent the ultimate generic resolution of such an issue 

will need NRC review and approval for plant-specific implementation, as indicated in a plantspecific FSAR supplement, and reflected in the SER associated with a particular LR application, 

an amendment pursuant to 10 CFR 50.90 will be necessary.

In the GALL Report, Volume 1, Tables 1 through 6 are summaries of the aging management 

review. These tables contain the same information as Tables 3.1-1 to 3.6-1, respectively, in the 

SRP-LR. These tables also include additional seventh and eighth columns that identify the 

related generic item and unique item associated with each structure and/or component (i.e., 

each row in the AMR tables contained in Volume 2 of the GALL Report). A locator for the plant 

systems evaluated in Volume 2 is also provided in the Appendix of Volume 1. 

The Appendix of Volume 2 of the GALL Report addresses quality assurance (QA) for aging 

management programs. Those aspects of the aging management review process that affect the 

quality of safety-related structures, systems, and components are subject to the QA 

requirements of Appendix B to 10 CFR Part 50. For nonsafety-related structures and 

components subject to an aging management review, the existing 10 CFR Part 50, Appendix B, 

QA program may be used by an applicant to address the elements of the corrective actions, 

confirmation process, and administrative controls for an aging management program for license 

renewal.

The GALL Report provides a technical basis for crediting existing plant programs and 

recommending areas for program augmentation and further evaluation. The incorporation of the 

GALL Report information into the SRP-LR, as directed by the Commission, should improve the 

efficiency of the license renewal process and better focus staff resources. 
September 2005 5 NUREG-1801 Vol. 1, Rev. 1

Table Column Headings

The following describes the information presented in each column of Tables 1 through 6 

contained in Volume 1 of this report. These tables present the relationship between the SRP-LR 

lines, the unique AMR line-item identifier (unique item) and the chapter-specific generic item 

that can be referenced repeatedly within a given chapter of GALL Vol. 2.

Column 

Heading Description

ID A unique row identifier. This identifier is useful in matching the row with the 

row in the corresponding 3.X-1 Table in the SRP-LR (where the “X” represents 

the chapter number within the SRP-LR). Thus, the Table 1 row labeled ID 1 in 

GALL Vol. 1 represents the same information contained in the row labeled ID 

1 in Table 3.1-1 of the SRP-LR.

Type Identifies the plant design that the item applies to (i.e., BWR or PWR or both).

Component Identifies the structure or components to which the row applies

Aging Effect/ 

Mechanism

Identifies the applicable aging effect and mechanism(s). See Chapter IX of 

Volume 2 for more information.

Aging 

Management 

Programs

Identifies the time limited aging analysis or aging management program found 

acceptable for properly managing the affects of aging. See Chapter X and XI 

of Volume 2.

Further 

Evaluation 

Recommended

Identifies whether further evaluation is required, and references the section of 

the SRP-LR that provides further information on this evaluation.

Related 

Generic Item

Identifies the item number in Volume 2, Chapters II through VIII presenting the 

detailed information summarized by this row. This chapter-specific generic 

identifier is used in the AMR subsystem rows and can appear multiple times 

within a chapter.

Unique Item The unique item is an AMR line-item identifier which is coded to indicate the 

chapter, AMR subsystem and unique row number within GALL Volume 2 (i.e., 

VIII.B1-1 is the first row in the steam and power conversion system, main 

steam system table, row 1). 
NUREG-1801 Vol. 1, Rev. 1 6 September 2005

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September 2005

7 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

1 BWR Steel pressure vessel support skirt 

and attachment welds

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c)

Yes, TLAA R-70 IV.A1-6

IV.A2-20

2 BWR Steel; stainless steel; steel with 

nickel-alloy or stainless steel 

cladding; nickel-alloy reactor vessel 

components: flanges; nozzles; 

penetrations; safe ends; thermal 

sleeves; vessel shells, heads and 

welds

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) and 

environmental effects are 

to be addressed for Class 

1 components

Yes, TLAA R-04 IV.A1-7

3 BWR Steel; stainless steel; steel with 

nickel-alloy or stainless steel 

cladding; nickel-alloy reactor coolant 

pressure boundary piping, piping 

components, and piping elements 

exposed to reactor coolant

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) and 

environmental effects are 

to be addressed for Class 

1 components

Yes, TLAA R-220 IV.C1-15

4 BWR Steel pump and valve closure bolting Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) check Code 

limits for allowable cycles 

(less than 7000 cycles) of 

thermal stress range

Yes, TLAA R-28 IV.C1-11

5 BWR/ 

PWR

Stainless steel and nickel alloy 

reactor vessel internals components

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c)

Yes, TLAA R-53 IV.B1-14

IV.B2-31

IV.B3-24

IV.B4-37
NUREG-1801 Vol. 1, Rev. 1

8 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

6 PWR Nickel Alloy tubes and sleeves in a 

reactor coolant and secondary 

feedwater/steam environment

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c)

Yes, TLAA R-46 IV.D1-21

IV.D2-15

7 PWR Steel and stainless steel reactor 

coolant pressure boundary closure 

bolting, head closure studs, support 

skirts and attachment welds, 

pressurizer relief tank components, 

steam generator components, piping 

and components external surfaces 

and bolting

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c)

Yes, TLAA R-13

R-18

R-33

R-73

IV.C2-23

IV.C2-10

IV.D1-11

IV.D2-10

IV.A2-4

8 PWR Steel; stainless steel; and nickelalloy reactor coolant pressure 

boundary piping, piping components, 

piping elements; flanges; nozzles 

and safe ends; pressurizer vessel 

shell heads and welds; heater 

sheaths and sleeves; penetrations; 

and thermal sleeves

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) and 

environmental effects are 

to be addressed for Class 

1 components

Yes, TLAA R-223 IV.C2-25

9 PWR Steel; stainless steel; steel with 

nickel-alloy or stainless steel 

cladding; nickel-alloy reactor vessel 

components: flanges; nozzles; 

penetrations; pressure housings; 

safe ends; thermal sleeves; vessel 

shells, heads and welds

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) and 

environmental effects are 

to be addressed for Class 

1 components

Yes, TLAA R-219 IV.A2-21
September 2005

9 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

10 PWR Steel; stainless steel; steel with 

nickel-alloy or stainless steel 

cladding; nickel-alloy steam 

generator components (flanges; 

penetrations; nozzles; safe ends, 

lower heads and welds)

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c) and 

environmental effects are 

to be addressed for Class 

1 components

Yes, TLAA R-221

R-222

IV.D1-8

IV.D2-3

11 BWR Steel top head enclosure (without 

cladding) top head nozzles (vent, top 

head spray or RCIC, and spare) 

exposed to reactor coolant

Loss of material due 

to general, pitting and 

crevice corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is 

to be evaluated

R-59 IV.A1-11

12 PWR Steel steam generator shell 

assembly exposed to secondary 

feedwater and steam

Loss of material due 

to general, pitting and 

crevice corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is 

to be evaluated

R-224 IV.D2-8

13 BWR Steel and stainless steel isolation 

condenser components exposed to 

reactor coolant

Loss of material due 

to general (steel only), 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is 

to be evaluated

R-16 IV.C1-6

14 BWR Stainless steel, nickel-alloy, and 

steel with nickel-alloy or stainless 

steel cladding reactor vessel 

flanges, nozzles, penetrations, safe 

ends, vessel shells, heads and 

welds

Loss of material due 

to pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is 

to be evaluated

RP-25 IV.A1-8
NUREG-1801 Vol. 1, Rev. 1 10 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

15 BWR Stainless steel; steel with nickelalloy or stainless steel cladding; and 

nickel-alloy reactor coolant pressure 

boundary components exposed to 

reactor coolant

Loss of material due 

to pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is 

to be evaluated

RP-27 IV.C1-14

16 PWR Steel steam generator upper and 

lower shell and transition cone 

exposed to secondary feedwater 

and steam

Loss of material due 

to general, pitting and 

crevice corrosion

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry 

and, for Westinghouse

Model 44 and 51 S/G, if 

general and pitting 

corrosion of the shell is 

known to exist, additional 

inspection procedures are 

to be developed. 

Yes, detection of 

aging effects is 

to be evaluated

R-34 IV.D1-12

17 BWR/ 

PWR

Steel (with or without stainless steel 

cladding) reactor vessel beltline 

shell, nozzles, and welds

Loss of fracture 

toughness due to 

neutron irradiation 

embrittlement

TLAA, evaluated in 

accordance with 

Appendix G of 10 CFR 50 

and RG 1.99. The 

applicant may choose to 

demonstrate that the 

materials of the nozzles 

are not controlling for the 

TLAA evaluations.

Yes, TLAA R-62

R-67

R-81

R-84

IV.A1-13

IV.A1-4

IV.A2-16

IV.A2-23
September 2005 11 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

18 BWR/ 

PWR

Steel (with or without stainless steel 

cladding) reactor vessel beltline 

shell, nozzles, and welds; safety 

injection nozzles

Loss of fracture 

toughness due to 

neutron irradiation 

embrittlement

Reactor Vessel 

Surveillance 

Yes, plant 

specific

R-63

R-82

R-86

IV.A1-14

IV.A2-17

IV.A2-24

19 BWR Stainless steel and nickel alloy top 

head enclosure vessel flange leak 

detection line 

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

A plant-specific aging 

management program is 

to be evaluated because 

existing programs may 

not be capable of 

mitigating or detecting 

crack initiation and 

growth due to SCC in the 

vessel flange leak 

detection line.

Yes, plant 

specific

R-61 IV.A1-10

20 BWR Stainless steel isolation condenser 

components exposed to reactor 

coolant

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

Inservice Inspection 

(IWB, IWC, and IWD), 

Water Chemistry, and 

plant-specific verification 

program

Yes, detection of 

aging effects is 

to be evaluated

R-15 IV.C1-4

21 PWR Reactor vessel shell fabricated of 

SA508-Cl 2 forgings clad with 

stainless steel using a high-heatinput welding process

Crack growth due to 

cyclic loading

TLAA Yes, TLAA R-85 IV.A2-22
NUREG-1801 Vol. 1, Rev. 1 12 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

22 PWR Stainless steel and nickel alloy 

reactor vessel internals components 

exposed to reactor coolant and 

neutron flux

Loss of fracture 

toughness due to 

neutron irradiation 

embrittlement, void 

swelling

FSAR supplement 

commitment to (1) 

participate in industry RVI 

aging programs (2) 

implement applicable 

results (3) submit for 

NRC approval > 24 

months before the 

extended period an RVI 

inspection plan based on 

industry recommendation.

No, but licensee 

commitment to 

be confirmed 

R-122

R-127

R-128

R-132

R-135

R-141

R-157

R-161

R-164

R-169

R-178

R-188

R-196

R-205

R-212

R-216

IV.B2-9

IV.B2-3

IV.B2-6

IV.B4-1

IV.B2-18

IV.B2-17

IV.B2-22

IV.B3-16

IV.B3-12

IV.B3-10

IV.B3-20

IV.B4-46

IV.B4-16

IV.B4-12

IV.B4-31

IV.B4-24

IV.B4-41

23 PWR Stainless steel reactor vessel 

closure head flange leak detection 

line and bottom-mounted instrument 

guide tubes

Cracking due to 

stress corrosion 

cracking

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant 

specific 

R-74

RP-13

IV.A2-5

IV.A2-1

24 PWR Class 1 cast austenitic stainless 

steel piping, piping components, and 

piping elements exposed to reactor 

coolant

Cracking due to 

stress corrosion 

cracking

Water Chemistry and, for 

CASS components that 

do not meet the NUREG0313 guidelines, a plant 

specific aging 

management program

Yes, plant 

specific 

R-05 IV.C2-3
September 2005 13 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

25 BWR Stainless steel jet pump sensing line Cracking due to cyclic 

loading

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant 

specific 

R-102 IV.B1-12

26 BWR Steel and stainless steel isolation 

condenser components exposed to 

reactor coolant

Cracking due to cyclic 

loading

Inservice Inspection 

(IWB, IWC, and IWD) and 

plant-specific verification 

program

Yes, detection of 

aging effects is 

to be evaluated

R-225 IV.C1-5

27 PWR Stainless steel and nickel alloy 

reactor vessel internals screws, 

bolts, tie rods, and hold-down 

springs

Loss of preload due to 

stress relaxation

FSAR supplement 

commitment to (1) 

participate in industry RVI 

aging programs (2) 

implement applicable 

results (3) submit for 

NRC approval > 24 

months before the 

extended period an RVI 

inspection plan based on 

industry recommendation.

No, but licensee 

commitment to 

be confirmed 

R-108

R-114

R-129

R-136

R-137

R-154

R-165

R-184

R-192

R-197

R-201

R-207

R-213

IV.B2-33

IV.B2-38

IV.B2-5

IV.B2-25

IV.B2-14

IV.B3-6

IV.B3-7

IV.B4-6

IV.B4-19

IV.B4-14

IV.B4-9

IV.B4-33

IV.B4-26

28 PWR Steel steam generator feedwater 

impingement plate and support 

exposed to secondary feedwater

Loss of material due 

to erosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant 

specific 

R-39 IV.D1-13

29 BWR Stainless steel steam dryers 

exposed to reactor coolant

Cracking due to flowinduced vibrationA plant-specific aging 

management program is 

to be evaluated.

Yes, plant 

specific 

RP-18 IV.B1-16
NUREG-1801 Vol. 1, Rev. 1 14 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

30 PWR Stainless steel reactor vessel 

internals components (e.g., Upper 

internals assembly, RCCA guide 

tube assemblies, Baffle/former 

assembly, Lower internal assembly, 

shroud assemblies, Plenum cover 

and plenum cylinder, Upper grid 

assembly, Control rod guide tube 

(CRGT) assembly, Core support 

shield assembly, Core barrel 

assembly, Lower grid assembly, 

Flow distributor assembly, Thermal 

shield, Instrumentation support 

structures)

Cracking due to 

stress corrosion 

cracking, irradiationassisted stress 

corrosion cracking

Water Chemistry and 

FSAR supplement 

commitment to (1) 

participate in industry RVI 

aging programs (2) 

implement applicable 

results (3) submit for 

NRC approval > 24 

months before the 

extended period an RVI 

inspection plan based on 

industry recommendation.

No, but licensee 

commitment 

needs to be 

confirmed 

R-106

R-109

R-116

R-120

R-123

R-125

R-138

R-143

R-146

R-149

R-155

R-159

R-166

R-172

R-173

R-175

R-176

R-180

R-181

R-185

R-193

R-202

R-209

R-214

IV.B2-42

IV.B2-36

IV.B2-30

IV.B2-8

IV.B2-2

IV.B2-10

IV.B4-7

IV.B2-24

IV.B2-12

IV.B3-28

IV.B3-2

IV.B3-15

IV.B3-11

IV.B3-21

IV.B4-34

IV.B4-36

IV.B4-44

IV.B4-43

IV.B4-2

IV.B4-5

IV.B4-18

IV.B4-10

IV.B4-29

IV.B4-22

IV.B4-40
September 2005 15 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

31 PWR Nickel alloy and steel with nickelalloy cladding piping, piping 

component, piping elements, 

penetrations, nozzles, safe ends, 

and welds (other than reactor vessel 

head); pressurizer heater sheaths, 

sleeves, diaphragm plate, manways 

and flanges; core support pads/core 

guide lugs

Cracking due to 

primary water stress 

corrosion cracking

Inservice Inspection 

(IWB, IWC, and IWD) and 

Water Chemistry and 

FSAR supp commitment 

to implement applicable 

plant commitments to (1) 

NRC Orders, Bulletins, 

and Generic Letters 

associated with nickel 

alloys and (2) staffaccepted industry 

guidelines.

No, but licensee 

commitment 

needs to be 

confirmed 

R-01

R-06

R-88

R-89

RP-22

RP-31

IV.D1-4

IV.D2-2

IV.C2-21

IV.A2-12

IV.A2-19

IV.C2-24

IV.C2-13

32 PWR Steel steam generator feedwater 

inlet ring and supports

Wall thinning due to 

flow-accelerated 

corrosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant 

specific 

R-51 IV.D1-26
NUREG-1801 Vol. 1, Rev. 1 16 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

33 PWR Stainless steel and nickel alloy 

reactor vessel internals components

Changes in 

dimensions due to 

void swelling

FSAR supplement 

commitment to (1) 

participate in industry RVI 

aging programs (2) 

implement applicable 

results (3) submit for 

NRC approval > 24 

months before the 

extended period an RVI 

inspection plan based on 

industry recommendation.

No, but licensee 

commitment to 

be confirmed 

R-107

R-110

R-113

R-117

R-119

R-121

R-124

R-126

R-131

R-134

R-139

R-144

R-147

R-151

R-158

R-160

R-163

R-168

R-174

R-177

R-182

R-187

R-195

R-199

R-204

R-211

R-215

IV.B2-41

IV.B2-35

IV.B2-39

IV.B2-29

IV.B2-27

IV.B2-7

IV.B2-1

IV.B2-4

IV.B2-19

IV.B2-15

IV.B2-23

IV.B2-11

IV.B3-27

IV.B3-4

IV.B3-14

IV.B3-13

IV.B3-8

IV.B3-19

IV.B4-35

IV.B4-45

IV.B4-3

IV.B4-17

IV.B4-11

IV.B4-8

IV.B4-30

IV.B4-23

IV.B4-39
September 2005 17 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

34 PWR Stainless steel and nickel alloy 

reactor control rod drive head 

penetration pressure housings 

Cracking due to 

stress corrosion 

cracking and primary 

water stress corrosion 

cracking

Inservice Inspection 

(IWB, IWC, and IWD) and 

Water Chemistry and for 

nickel alloy, FSAR 

supplement commitment 

to implement applicable 

plant commitments to (1) 

NRC Orders, Bulletins 

and Generic Letters 

associated with nickel 

alloys and (2) staffaccepted industry 

guidelines.

No, but licensee 

commitment 

needs to be 

confirmed 

R-76 IV.A2-11

35 PWR Steel with stainless steel or nickel 

alloy cladding primary side 

components; steam generator upper 

and lower heads, tubesheets and 

tube-to-tube sheet welds

Cracking due to 

stress corrosion 

cracking and primary 

water stress corrosion 

cracking

Inservice Inspection 

(IWB, IWC, and IWD) and 

Water Chemistry and for 

nickel alloy, FSAR 

supplement commitment 

to implement applicable 

plant commitments to (1) 

NRC Orders, Bulletins 

and Generic Letters 

associated with nickel 

alloys and (2) staffaccepted industry

guidelines.

No, but licensee 

commitment 

needs to be 

confirmed 

R-35 IV.D2-4
NUREG-1801 Vol. 1, Rev. 1 18 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

36 PWR Nickel alloy, stainless steel 

pressurizer spray head

Cracking due to 

stress corrosion 

cracking and primary 

water stress corrosion 

cracking

Water Chemistry and 

One-Time Inspection and, 

for nickel alloy welded 

spray heads, provide 

commitment in FSAR 

supplement to submit 

AMP delineating 

commitments to Orders, 

Bulletins, or Generic 

Letters that inspect 

stipulated components for 

cracking of wetted 

surfaces.

No, unless 

licensee 

commitment 

needs to be 

confirmed 

R-24 IV.C2-17

37 PWR Stainless steel and nickel alloy 

reactor vessel internals components 

(e.g., Upper internals assembly, 

RCCA guide tube assemblies, Lower 

internal assembly, CEA shroud 

assemblies, Core shroud assembly, 

Core support shield assembly, Core 

barrel assembly, Lower grid 

assembly, Flow distributor 

assembly)

Cracking due to 

stress corrosion 

cracking, primary 

water stress corrosion 

cracking, irradiationassisted stress 

corrosion cracking

Water Chemistry and 

FSAR supplement 

commitment to (1) 

participate in industry RVI 

aging programs (2) 

implement applicable 

results (3) submit for 

NRC approval > 24 

months before the 

extended period an RVI 

inspection plan based on 

industry recommendation.

No, but licensee 

commitment 

needs to be 

confirmed 

R-112

R-118

R-130

R-133

R-150

R-162

R-167

R-186

R-194

R-203

R-210

IV.B2-40

IV.B2-28

IV.B2-20

IV.B2-16

IV.B3-5

IV.B3-9

IV.B3-23

IV.B4-20

IV.B4-13

IV.B4-32

IV.B4-25

38 BWR Steel (with or without stainless steel 

cladding) control rod drive return line 

nozzles exposed to reactor coolant

Cracking due to cyclic 

loading

BWR CR Drive Return 

Line Nozzle

No R-66 IV.A1-2
September 2005 19 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

39 BWR Steel (with or without stainless steel 

cladding) feedwater nozzles 

exposed to reactor coolant

Cracking due to cyclic 

loading

BWR Feedwater Nozzle No R-65 IV.A1-3

40 BWR Stainless steel and nickel alloy 

penetrations for control rod drive 

stub tubes instrumentation, jet pump 

instrument, standby liquid control, 

flux monitor, and drain line exposed 

to reactor coolant

Cracking due to 

stress corrosion 

cracking, 

Intergranular stress 

corrosion cracking, 

cyclic loading

BWR Penetrations and 

Water Chemistry

No R-69 IV.A1-5

41 BWR Stainless steel and nickel alloy 

piping, piping components, and 

piping elements greater than or 

equal to 4 NPS; nozzle safe ends 

and associated welds

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

BWR Stress Corrosion 

Cracking and Water 

Chemistry

No R-20

R-21

R-68

IV.C1-9

IV.C1-8

IV.A1-1

42 BWR Stainless steel and nickel alloy 

vessel shell attachment welds 

exposed to reactor coolant

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

BWR Vessel ID 

Attachment Welds and 

Water Chemistry 

No R-64 IV.A1-12

43 BWR Stainless steel fuel supports and 

control rod drive assemblies control 

rod drive housing exposed to reactor 

coolant

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

BWR Vessel Internals 

and Water Chemistry

No R-104 IV.B1-8
NUREG-1801 Vol. 1, Rev. 1 20 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

44 BWR Stainless steel and nickel alloy core 

shroud, core plate, core plate bolts, 

support structure, top guide, core 

spray lines, spargers, jet pump 

assemblies, control rod drive 

housing, nuclear instrumentation 

guide tubes 

Cracking due to 

stress corrosion 

cracking, intergranular 

stress corrosion 

cracking, irradiationassisted stress 

corrosion cracking

BWR Vessel Internals 

and Water Chemistry

No R-92

R-93

R-96

R-97

R-98

R-99

R-100

R-105

IV.B1-1

IV.B1-6

IV.B1-2

IV.B1-3

IV.B1-17

IV.B1-7

IV.B1-13

IV.B1-10

45 BWR Steel piping, piping components, 

and piping elements exposed to 

reactor coolant

Wall thinning due to 

flow-accelerated 

corrosion

Flow-Accelerated 

Corrosion 

No R-23 IV.C1-7

46 BWR Nickel alloy core shroud and core 

plate access hole cover (mechanical 

covers)

Cracking due to 

stress corrosion 

cracking, intergranular 

stress corrosion 

cracking, irradiationassisted stress 

corrosion cracking

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry

No R-95 IV.B1-4

47 BWR Stainless steel and nickel-alloy 

reactor vessel internals exposed to 

reactor coolant

Loss of material due 

to pitting and crevice 

corrosion

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry

No RP-26 IV.B1-15
September 2005 21 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

48 BWR Steel and stainless steel Class 1 

piping, fittings and branch 

connections < NPS 4 exposed to 

reactor coolant

Cracking due to 

stress corrosion 

cracking, intergranular 

stress corrosion 

cracking (for stainless 

steel only), and 

thermal and 

mechanical loading

Inservice Inspection 

(IWB, IWC, and IWD), 

Water chemistry, and 

One-Time Inspection of 

ASME Code Class 1 

Small-bore Piping

No R-03 IV.C1-1

49 BWR Nickel alloy core shroud and core 

plate access hole cover (welded 

covers)

Cracking due to 

stress corrosion 

cracking, intergranular 

stress corrosion 

cracking, irradiationassisted stress 

corrosion cracking

Inservice Inspection 

(IWB, IWC, and IWD), 

Water Chemistry, and, for 

BWRs with a crevice in 

the access hole covers, 

augmented inspection 

using UT or other 

demonstrated acceptable 

inspection of the access 

hole cover welds

No R-94 IV.B1-5

50 BWR High-strength low alloy steel top 

head closure studs and nuts 

exposed to air with reactor coolant 

leakage

Cracking due to 

stress corrosion 

cracking and 

intergranular stress 

corrosion cracking

Reactor Head Closure 

Studs

No R-60 IV.A1-9
NUREG-1801 Vol. 1, Rev. 1 22 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

51 BWR Cast austenitic stainless steel jet 

pump assembly castings; orificed 

fuel support 

Loss of fracture 

toughness due to 

thermal aging and 

neutron irradiation 

embrittlement

Thermal Aging and 

Neutron Irradiation 

Embrittlement of CASS

No R-101

R-103

IV.B1-11

IV.B1-9

52 BWR/ 

PWR

Steel and stainless steel reactor 

coolant pressure boundary (RCPB) 

pump and valve closure bolting, 

manway and holding bolting, flange 

bolting, and closure bolting in highpressure and high-temperature 

systems 

Cracking due to 

stress corrosion 

cracking, loss of 

material due to wear, 

loss of preload due to 

thermal effects, 

gasket creep, and 

self-loosening

Bolting Integrity No R-10

R-11

R-12

R-26

R-27

R-29

R-32

R-78

R-79

R-80

IV.D1-2

IV.C2-7

IV.C2-8

IV.C1-12

IV.C1-10

IV.C1-13

IV.D1-10

IV.D2-6

IV.A2-6

IV.A2-7

IV.A2-8

53 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

closed cycle cooling water

Loss of material due 

to general, pitting and 

crevice corrosion

Closed-Cycle Cooling 

Water System

No RP-10 IV.C2-14

54 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping elements 

exposed to closed cycle cooling 

water

Loss of material due 

to pitting, crevice, and 

galvanic corrosion

Closed-Cycle Cooling 

Water System

No RP-11 IV.C2-11
September 2005 23 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

55 BWR/ 

PWR

Cast austenitic stainless steel Class

1 pump casings, and valve bodies 

and bonnets exposed to reactor 

coolant >250°C (>482°F)

Loss of fracture 

toughness due to 

thermal aging 

embrittlement

Inservice inspection 

(IWB, IWC, and IWD). 

Thermal aging 

susceptibility screening is 

not necessary, inservice 

inspection requirements 

are sufficient for 

managing these aging 

effects. ASME Code 

Case N-481 also provides 

an alternative for pump 

casings.

No R-08 IV.C1-3

IV.C2-6

56 BWR/ 

PWR

Copper alloy >15% Zn piping, piping 

components, and piping elements 

exposed to closed cycle cooling 

water

Loss of material due 

to selective leaching

Selective Leaching of 

Materials

No RP-12 IV.C2-12

57 BWR/ 

PWR

Cast austenitic stainless steel Class 

1 piping, piping component, and 

piping elements and control rod 

drive pressure housings exposed to 

reactor coolant >250°C (>482°F)

Loss of fracture 

toughness due to 

thermal aging 

embrittlement

Thermal Aging 

Embrittlement of CASS

No R-52

R-77

IV.C1-2

IV.C2-4

IV.A2-10

58 PWR Steel reactor coolant pressure 

boundary external surfaces exposed 

to air with borated water leakage

Loss of material due 

to Boric acid corrosion

Boric Acid Corrosion No R-17 IV.A2-13

IV.C2-9

IV.D1-3

IV.D2-1
NUREG-1801 Vol. 1, Rev. 1 24 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

59 PWR Steel steam generator steam nozzle 

and safe end, feedwater nozzle and 

safe end, AFW nozzles and safe 

ends exposed to secondary 

feedwater/steam

Wall thinning due to 

flow-accelerated 

corrosion

Flow-Accelerated 

Corrosion 

No R-37

R-38

IV.D1-5

IV.D2-7

60 PWR Stainless steel flux thimble tubes 

(with or without chrome plating)

Loss of material due 

to Wear

Flux Thimble Tube 

Inspection

No R-145 IV.B2-13

61 PWR Stainless steel, steel pressurizer 

integral support exposed to air with 

metal temperature up to 288°C 

(550°F)

Cracking due to cyclic 

loading

Inservice Inspection 

(IWB, IWC, and IWD)

No R-19 IV.C2-16

62 PWR Stainless steel, steel with stainless 

steel cladding reactor coolant 

system cold leg, hot leg, surge line, 

and spray line piping and fittings 

exposed to reactor coolant

Cracking due to cyclic 

loading

Inservice Inspection 

(IWB, IWC, and IWD)

No R-56 IV.C2-26

63 PWR Steel reactor vessel flange, stainless 

steel and nickel alloy reactor vessel 

internals exposed to reactor coolant 

(e.g., upper and lower internals 

assembly, CEA shroud assembly, 

core support barrel, upper grid 

assembly, core support shield 

assembly, lower grid assembly)

Loss of material due 

to Wear

Inservice Inspection 

(IWB, IWC, and IWD)

No R-87

R-115

R-142

R-148

R-152

R-156

R-170

R-179

R-190

R-208

IV.A2-25

IV.B2-34

IV.B2-26

IV.B3-26

IV.B3-3

IV.B3-17

IV.B3-22

IV.B4-42

IV.B4-15

IV.B4-27
September 2005 25 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

64 PWR Stainless steel and steel with 

stainless steel or nickel alloy 

cladding pressurizer components

Cracking due to 

stress corrosion 

cracking, primary 

water stress corrosion 

cracking

Inservice Inspection 

(IWB, IWC, and IWD) and 

Water Chemistry

No R-25 IV.C2-19

65 PWR Nickel alloy reactor vessel upper 

head and control rod drive 

penetration nozzles, instrument 

tubes, head vent pipe (top head), 

and welds 

Cracking due to 

primary water stress 

corrosion cracking

Inservice Inspection 

(IWB, IWC, and IWD) and 

Water Chemistry and 

Nickel-Alloy Penetration 

Nozzles Welded to the 

Upper Reactor Vessel 

Closure Heads of 

Pressurized Water 

Reactors

No R-75

R-90

IV.A2-9

IV.A2-18

66 PWR Steel steam generator secondary 

manways and handholds (cover 

only) exposed to air with leaking 

secondary-side water and/or steam

Loss of material due 

to erosion

Inservice Inspection 

(IWB, IWC, and IWD) for 

Class 2 components

No R-31 IV.D2-5

67 PWR Steel with stainless steel or nickel 

alloy cladding; or stainless steel 

pressurizer components exposed to 

reactor coolant

Cracking due to cyclic 

loading

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry

No R-58 IV.C2-18
NUREG-1801 Vol. 1, Rev. 1 26 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

68 PWR Stainless steel, steel with stainless 

steel cladding Class 1 piping, 

fittings, pump casings, valve bodies, 

nozzles, safe ends, manways, 

flanges, CRD housing; pressurizer 

heater sheaths, sleeves, diaphragm 

plate; pressurizer relief tank 

components, reactor coolant system 

cold leg, hot leg, surge line, and 

spray line piping and fittings

Cracking due to 

stress corrosion 

cracking

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry

No R-07

R-09

R-14

R-30

R-217

IV.C2-2

IV.D1-1

IV.C2-5

IV.C2-22

IV.C2-27

IV.C2-20

69 PWR Stainless steel, nickel alloy safety 

injection nozzles, safe ends, and 

associated welds and buttering 

exposed to reactor coolant

Cracking due to 

stress corrosion 

cracking, primary 

water stress corrosion 

cracking

Inservice Inspection 

(IWB, IWC, and IWD), 

and Water Chemistry

No R-83 IV.A2-15

70 PWR Stainless steel; steel with stainless 

steel cladding Class 1 piping, fittings 

and branch connections < NPS 4 

exposed to reactor coolant

Cracking due to 

stress corrosion 

cracking, thermal and 

mechanical loading

Inservice Inspection 

(IWB, IWC, and IWD), 

Water chemistry, and 

One-Time Inspection of 

ASME Code Class 1

Small-bore Piping

No R-02 IV.C2-1

71 PWR High-strength low alloy steel closure 

head stud assembly exposed to air 

with reactor coolant leakage

Cracking due to 

stress corrosion 

cracking; loss of 

material due to wear

Reactor Head Closure 

Studs

No R-71

R-72

IV.A2-2

IV.A2-3
September 2005 27 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

72 PWR Nickel alloy steam generator tubes 

and sleeves exposed to secondary 

feedwater/ steam

Cracking due to OD 

stress corrosion 

cracking and 

intergranular attack, 

loss of material due to 

fretting and wear

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-47

R-48

R-49

IV.D1-23

IV.D2-17

IV.D1-22

IV.D2-16

IV.D1-24

IV.D2-18

73 PWR Nickel alloy steam generator tubes, 

repair sleeves, and tube plugs 

exposed to reactor coolant

Cracking due to 

primary water stress 

corrosion cracking

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-40

R-44

IV.D1-18

IV.D2-12

IV.D1-20

IV.D2-14

74 PWR Chrome plated steel, stainless steel, 

nickel alloy steam generator antivibration bars exposed to secondary 

feedwater/ steam

Cracking due to 

stress corrosion 

cracking, loss of 

material due to 

crevice corrosion and 

fretting

Steam Generator Tube 

Integrity and Water 

Chemistry

No RP-14

RP-15

IV.D1-14

IV.D1-15

75 PWR Nickel alloy once-through steam 

generator tubes exposed to 

secondary feedwater/ steam

Denting due to 

corrosion of carbon 

steel tube support 

plate

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-226 IV.D2-13

76 PWR Steel steam generator tube support 

plate, tube bundle wrapper exposed 

to secondary feedwater/steam

Loss of material due 

to erosion, general, 

pitting, and crevice 

corrosion, ligament 

cracking due to 

corrosion

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-42

RP-16

IV.D1-17

IV.D2-11

IV.D1-9
NUREG-1801 Vol. 1, Rev. 1 28 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

77 PWR Nickel alloy steam generator tubes 

and sleeves exposed to phosphate 

chemistry in secondary feedwater/ 

steam

Loss of material due 

to wastage and pitting 

corrosion

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-50 IV.D1-25

78 PWR Steel steam generator tube support 

lattice bars exposed to secondary 

feedwater/ steam

Wall thinning due to 

flow-accelerated 

corrosion

Steam Generator Tube 

Integrity and Water 

Chemistry

No R-41 IV.D1-16

79 PWR Nickel alloy steam generator tubes 

exposed to secondary feedwater/ 

steam

Denting due to 

corrosion of steel tube 

support plate

Steam Generator Tube 

Integrity; Water 

Chemistry and, for plants 

that could experience 

denting at the upper 

support plates, evaluate 

potential for rapidly 

propagating cracks and 

then develop and take 

corrective actions 

consistent with Bulletin 

88-02.

No R-43 IV.D1-19

80 PWR Cast austenitic stainless steel 

reactor vessel internals (e.g., upper 

internals assembly, lower internal 

assembly, CEA shroud assemblies, 

control rod guide tube assembly, 

core support shield assembly, lower 

grid assembly)

Loss of fracture 

toughness due to 

thermal aging and 

neutron irradiation 

embrittlement

Thermal Aging and 

Neutron Irradiation 

Embrittlement of CASS

No R-111

R-140

R-153

R-171

R-183

R-191

R-206

IV.B2-37

IV.B2-21

IV.B3-1

IV.B3-18

IV.B4-4

IV.B4-21

IV.B4-28
September 2005 29 NUREG-1801 Vol. 1, Rev. 1

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

81 PWR Nickel alloy or nickel-alloy clad 

steam generator divider plate 

exposed to reactor coolant

Cracking due to 

primary water stress 

corrosion cracking

Water Chemistry No RP-21 IV.D1-6

82 PWR Stainless steel steam generator 

primary side divider plate exposed to 

reactor coolant

Cracking due to 

stress corrosion 

cracking

Water Chemistry No RP-17 IV.D1-7

83 PWR Stainless steel; steel with nickelalloy or stainless steel cladding; and 

nickel-alloy reactor vessel internals 

and reactor coolant pressure 

boundary components exposed to 

reactor coolant

Loss of material due 

to pitting and crevice 

corrosion

Water Chemistry No RP-23

RP-24

RP-28

IV.C2-15

IV.B2-32

IV.B3-25

IV.B4-38

IV.A2-14

84 PWR Nickel alloy steam generator 

components such as, secondary 

side nozzles (vent, drain, and 

instrumentation) exposed to 

secondary feedwater/ steam

Cracking due to 

stress corrosion 

cracking

Water Chemistry and 

One-Time Inspection or 

Inservice Inspection 

(IWB, IWC, and IWD). 

No R-36 IV.D2-9

85 BWR/ 

PWR

Nickel alloy piping, piping 

components, and piping elements 

exposed to air – indoor uncontrolled 

(external)

None None NA - No AEM or 

AMP

RP-03 IV.E-1

86 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping elements 

exposed to air – indoor uncontrolled 

(External); air with borated water 

leakage; concrete; gas

None None NA - No AEM or 

AMP

RP-04

RP-05

RP-06

RP-07

IV.E-2

IV.E-3

IV.E-4

IV.E-5
NUREG-1801 Vol. 1, Rev. 1 30 September 2005

Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

87 BWR/ 

PWR

Steel piping, piping components, 

and piping elements in concrete

None None NA - No AEM or 

AMP

RP-01 IV.E-6
September 2005 31 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

1 BWR/ 

PWR

Steel and stainless steel 

piping, piping components, 

and piping elements in 

emergency core cooling 

system 

Cumulative fatigue damage TLAA, evaluated in 

accordance with 10 

CFR 54.21(c)

Yes, TLAA E-10

E-13

V.D2-32

V.D1-27

2 PWR Steel with stainless steel 

cladding pump casing exposed 

to treated borated water

Loss of material/ cladding 

breach 

A plant-specific aging 

management program 

is to be evaluated. 

Reference NRC 

Information Notice 94-

63, “Boric Acid 

Corrosion of Charging 

Pump Casings Caused 

by Cladding Cracks."

Yes, verify that 

plant-specific 

program addresses 

cladding breach

EP-49 V.D1-32

3 BWR/ 

PWR

Stainless steel containment 

isolation piping and 

components internal surfaces 

exposed to treated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

E-33 V.C-4

4 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to soil

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program 

is to be evaluated.

Yes, plant specific EP-31 V.D1-26

V.D2-27
NUREG-1801 Vol. 1, Rev. 1 32 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

5 BWR Stainless steel and aluminum 

piping, piping components, 

and piping elements exposed 

to treated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

EP-26

EP-32

V.D2-19

V.D2-28

6 BWR/ 

PWR

Stainless steel and copper 

alloy piping, piping 

components, and piping 

elements exposed to 

lubricating oil

Loss of material due to 

pitting and crevice 

corrosion

Lubricating Oil Analysis 

and One-Time 

Inspection

Yes, detection of 

aging effects is to 

be evaluated 

EP-45

EP-51

V.A-21

V.D1-18

V.D2-22

V.D1-24

7 BWR/ 

PWR

Partially encased stainless 

steel tanks with breached 

moisture barrier exposed to 

raw water

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program 

is to be evaluated for 

pitting and crevice 

corrosion of tank 

bottoms because 

moisture and water can 

egress under the tank 

due to cracking of the 

perimeter seal from 

weathering.

Yes, plant specific E-01 V.D1-15
September 2005 33 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

8 BWR/ 

PWR

Stainless steel piping, piping 

components, piping elements, 

and tank internal surfaces 

exposed to condensation 

(internal)

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program 

is to be evaluated. 

Yes, plant specific E-14

EP-53

V.D2-35

V.A-26

V.D1-29

9 BWR/ 

PWR

Steel, stainless steel, and 

copper alloy heat exchanger 

tubes exposed to lubricating oil

Reduction of heat transfer 

due to fouling

Lubricating Oil Analysis 

and One-Time 

Inspection

Yes, detection of 

aging effects is to 

be evaluated 

EP-40

EP-47

EP-50

V.A-17

V.D1-12

V.D2-14

V.A-12

V.D1-8

V.D2-9

V.A-14

V.D1-10

V.D2-11

10 BWR/ 

PWR

Stainless steel heat exchanger 

tubes exposed to treated water

Reduction of heat transfer 

due to fouling

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

EP-34 V.A-16

V.D2-13

11 BWR Elastomer seals and 

components in standby gas 

treatment system exposed to 

air - indoor uncontrolled

Hardening and loss of 

strength due to elastomer 

degradation

A plant-specific aging 

management program 

is to be evaluated.

Yes, plant specific 

5)

E-06 V.B-4
NUREG-1801 Vol. 1, Rev. 1 34 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

12 PWR Stainless steel high-pressure 

safety injection (charging) 

pump miniflow orifice exposed 

to treated borated water

Loss of material due to 

erosion

A plant-specific aging 

management program 

is to be evaluated for 

erosion of the orifice 

due to extended use of 

the centrifugal HPSI 

pump for normal 

charging. 

Yes, plant specific E-24 V.D1-14

13 BWR Steel drywell and suppression 

chamber spray system nozzle 

and flow orifice internal 

surfaces exposed to air -

indoor uncontrolled (internal)

Loss of material due to 

general corrosion and 

fouling

A plant-specific aging 

management program 

is to be evaluated.

Yes, plant specific E-04 V.D2-1

14 BWR Steel piping, piping 

components, and piping 

elements exposed to treated 

water

Loss of material due to 

general, pitting, and 

crevice corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated

E-08 V.D2-33

15 BWR/ 

PWR

Steel containment isolation 

piping, piping components, 

and piping elements internal 

surfaces exposed to treated 

water

Loss of material due to 

general, pitting, and 

crevice corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated

E-31 V.C-6
September 2005 35 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

16 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to 

lubricating oil

Loss of material due to 

general, pitting, and 

crevice corrosion

Lubricating Oil Analysis 

and One-Time 

Inspection

Yes, detection of 

aging effects is to 

be evaluated

EP-46 V.A-25

V.D1-28

V.D2-30

17 BWR/ 

PWR

Steel (with or without coating 

or wrapping) piping, piping

components, and piping 

elements buried in soil

Loss of material due to 

general, pitting, crevice, 

and microbiologicallyinfluenced corrosion

Buried Piping and 

Tanks Surveillance 

or 

Buried Piping and 

Tanks Inspection

No 

Yes, detection of 

aging effects and 

operating 

experience are to 

be further evaluated

E-42 V.B-9

18 BWR Stainless steel piping, piping 

components, and piping 

elements exposed to treated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking and 

intergranular stress 

corrosion cracking

BWR Stress Corrosion 

Cracking and Water 

Chemistry

No E-37 V.D2-29

19 BWR Steel piping, piping 

components, and piping 

elements exposed to steam or 

treated water

Wall thinning due to flowaccelerated corrosionFlow-Accelerated 

Corrosion 

No E-07

E-09

V.D2-31

V.D2-34
NUREG-1801 Vol. 1, Rev. 1 36 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

20 BWR Cast austenitic stainless steel 

piping, piping components, 

and piping elements exposed 

to treated water (borated or 

unborated) >250°C (>482°F)

Loss of fracture toughness 

due to thermal aging 

embrittlement

Thermal Aging 

Embrittlement of CASS

No E-11 V.D2-20

21 BWR/ 

PWR

High-strength steel closure 

bolting exposed to air with 

steam or water leakage

Cracking due to cyclic 

loading, stress corrosion 

cracking

Bolting Integrity No E-03 V.E-3

22 BWR/ 

PWR

Steel closure bolting exposed 

to air with steam or water 

leakage

Loss of material due to 

general corrosion

Bolting Integrity No E-02 V.E-6

23 BWR/ 

PWR

Steel bolting and closure 

bolting exposed to air –

outdoor (external), or air –

indoor uncontrolled (external)

Loss of material due to 

general, pitting, and 

crevice corrosion

Bolting Integrity No EP-1

EP-25

V.E-1

V.E-4

24 BWR/ 

PWR

Steel closure bolting exposed 

to air – indoor uncontrolled 

(external)

Loss of preload due to 

thermal effects, gasket 

creep, and self-loosening 

Bolting Integrity No EP-24 V.E-5
September 2005 37 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

25 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to closed 

cycle cooling water >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking

Closed-Cycle Cooling 

Water System

No EP-44 V.A-24

V.C-8

V.D1-23

V.D2-26

26 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to closed 

cycle cooling water

Loss of material due to 

general, pitting, and 

crevice corrosion

Closed-Cycle Cooling 

Water System

No EP-48 V.C-9

27 BWR/ 

PWR

Steel heat exchanger 

components exposed to closed 

cycle cooling water

Loss of material due to 

general, pitting, crevice, 

and galvanic corrosion

Closed-Cycle Cooling 

Water System

No E-17 V.A-9

V.D1-6

V.D2-7

28 BWR/ 

PWR

Stainless steel piping, piping 

components, piping elements, 

and heat exchanger 

components exposed to 

closed-cycle cooling water

Loss of material due to 

pitting and crevice 

corrosion

Closed-Cycle Cooling 

Water System

No E-19

EP-33

V.A-7

V.D1-4

V.D2-5

V.A-23

V.C-7

V.D1-22

V.D2-25
NUREG-1801 Vol. 1, Rev. 1 38 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

29 BWR/ 

PWR

Copper alloy piping, piping 

components, piping elements, 

and heat exchanger 

components exposed to closed 

cycle cooling water

Loss of material due to 

pitting, crevice, and 

galvanic corrosion

Closed-Cycle Cooling 

Water System

No EP-13

EP-36

V.A-5

V.D1-2

V.D2-3

V.A-20

V.B-6

V.D1-17

V.D2-21

30 BWR/ 

PWR

Stainless steel and copper 

alloy heat exchanger tubes 

exposed to closed cycle 

cooling water

Reduction of heat transfer 

due to fouling

Closed-Cycle Cooling 

Water System

No EP-35

EP-39

V.A-13

V.D1-9

V.D2-10

V.A-11

31 BWR/ 

PWR

External surfaces of steel 

components including ducting, 

piping, ducting closure bolting, 

and containment isolation 

piping external surfaces 

exposed to air - indoor 

uncontrolled (external); 

condensation (external) and air 

- outdoor (external)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No E-26

E-30

E-35

E-40

E-44

E-45

E-46

V.A-1

V.B-3

V.D2-2

V.C-2

V.C-1

V.B-2

V.E-7

V.E-8

V.E-10
September 2005 39 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

32 BWR/ 

PWR

Steel piping and ducting 

components and internal 

surfaces exposed to air –

indoor uncontrolled (Internal)

Loss of material due to 

general corrosion

Inspection of Internal 

Surfaces in 

Miscellaneous Piping 

and Ducting 

Components

No E-25

E-29

V.B-1

V.A-19

V.D2-16

33 BWR/ 

PWR

Steel encapsulation 

components exposed to airindoor uncontrolled (internal)

Loss of material due to 

general, pitting, and 

crevice corrosion

Inspection of Internal 

Surfaces in 

Miscellaneous Piping 

and Ducting 

Components

No EP-42 V.A-2

34 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to 

condensation (internal)

Loss of material due to 

general, pitting, and 

crevice corrosion

Inspection of Internal 

Surfaces in 

Miscellaneous Piping 

and Ducting 

Components

No E-27 V.D2-17

35 BWR/ 

PWR

Steel containment isolation 

piping and components 

internal surfaces exposed to 

raw water

Loss of material due to 

general, pitting, crevice, 

and microbiologicallyinfluenced corrosion, and 

fouling

Open-Cycle Cooling 

Water System

No E-22 V.C-5
NUREG-1801 Vol. 1, Rev. 1 40 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

36 BWR/ 

PWR

Steel heat exchanger 

components exposed to raw 

water

Loss of material due to 

general, pitting, crevice, 

galvanic, and 

microbiologicallyinfluenced corrosion, and 

fouling

Open-Cycle Cooling 

Water System

No E-18 V.A-10

V.D1-7

V.D2-8

37 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion

Open-Cycle Cooling 

Water System

No EP-55 V.D1-25

38 BWR/ 

PWR

Stainless steel containment 

isolation piping and 

components internal surfaces 

exposed to raw water

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion, and 

fouling

Open-Cycle Cooling 

Water System

No E-34 V.C-3

39 BWR/ 

PWR

Stainless steel heat exchanger 

components exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion, and 

fouling

Open-Cycle Cooling 

Water System

No E-20 V.A-8

V.D1-5

V.D2-6
September 2005 41 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

40 BWR/ 

PWR

Steel and stainless steel heat 

exchanger tubes (serviced by 

open-cycle cooling water) 

exposed to raw water

Reduction of heat transfer 

due to fouling

Open-Cycle Cooling 

Water System

No E-21

E-23

V.A-15

V.D1-11

V.D2-12

V.D2-15

41 BWR/ 

PWR

Copper alloy >15% Zn piping, 

piping components, piping 

elements, and heat exchanger 

components exposed to closed 

cycle cooling water

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No EP-27

EP-37

V.A-22

V.B-7

V.D1-19

V.D2-23

V.A-6

V.B-5

V.D1-3

V.D2-4

42 BWR/ 

PWR

Gray cast iron piping, piping 

components, piping elements

exposed to closed-cycle 

cooling water

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No EP-52 V.D1-20

43 BWR/ 

PWR

Gray cast iron piping, piping 

components, and piping 

elements exposed to soil

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No EP-54 V.B-8

V.D1-21

V.D2-24

44 BWR/ 

PWR

Gray cast iron motor cooler 

exposed to treated water

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No E-43 V.A-18

V.D1-13
NUREG-1801 Vol. 1, Rev. 1 42 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

45 PWR Aluminum, copper alloy >15% 

Zn, and steel external 

surfaces, bolting, and piping, 

piping components, and piping 

elements exposed to air with 

borated water leakage

Loss of material due to 

Boric acid corrosion

Boric Acid Corrosion No E-28

E-41

EP-2

EP-38

V.A-4

V.D1-1

V.E-9

V.E-2

V.D2-18

V.E-11

46 PWR Steel encapsulation 

components exposed to air 

with borated water leakage 

(internal)

Loss of material due to 

general, pitting, crevice 

and boric acid corrosion

Inspection of Internal 

Surfaces in 

Miscellaneous Piping 

and Ducting 

Components

No EP-43 V.A-3

47 PWR Cast austenitic stainless steel 

piping, piping components, 

and piping elements exposed 

to treated borated water 

>250°C (>482°F)

Loss of fracture toughness 

due to thermal aging 

embrittlement

Thermal Aging 

Embrittlement of CASS

No E-47 V.D1-16
September 2005 43 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

48 PWR Stainless steel or stainlesssteel-clad steel piping, piping 

components, piping elements, 

and tanks (including safety 

injection tanks/accumulators) 

exposed to treated borated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking

Water Chemistry No E-12

E-38

V.A-28

V.D1-31

V.D1-33

49 PWR Stainless steel piping, piping 

components, piping elements, 

and tanks exposed to treated 

borated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry No EP-41 V.A-27

V.D1-30

50 BWR/ 

PWR

Aluminum piping, piping 

components, and piping 

elements exposed to airindoor uncontrolled 

(internal/external)

None None NA - No AEM or 

AMP

EP-3 V.F-2

51 BWR/ 

PWR

Galvanized steel ducting 

exposed to air – indoor 

controlled (external)

None None NA - No AEM or 

AMP

EP-14 V.F-1
NUREG-1801 Vol. 1, Rev. 1 44 September 2005

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

52 BWR/ 

PWR

Glass piping elements 

exposed to air – indoor 

uncontrolled (external), 

lubricating oil, raw water, 

treated water, or treated 

borated water 

None None NA - No AEM or 

AMP

EP-15

EP-16

EP-28

EP-29

EP-30

V.F-6

V.F-7

V.F-8

V.F-10

V.F-9

53 BWR/ 

PWR

Stainless steel, copper alloy, 

and nickel alloy piping, piping 

components, and piping 

elements exposed to air –

indoor uncontrolled (external)

None None NA - No AEM or 

AMP

EP-10

EP-17

EP-18

V.F-3

V.F-11

V.F-12

54 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to air –

indoor controlled (external)

None None NA - No AEM or 

AMP

EP-4 V.F-16

55 BWR/ 

PWR

Steel and stainless steel 

piping, piping components, 

and piping elements in 

concrete

None None NA - No AEM or 

AMP

EP-5

EP-20

V.F-17

V.F-14
September 2005 45 NUREG-1801 Vol. 1, Rev. 1

Table 2. Summary of Aging Management Programs for the EngineeredSafety Features 

Evaluated in Chapter V of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

56 BWR/ 

PWR

Steel, stainless steel, and 

copper alloy piping, piping 

components, and piping 

elements exposed to gas

None None NA - No AEM or 

AMP

EP-7

EP-9

EP-22

V.F-18

V.F-4

V.F-15

57 PWR Stainless steel and copper 

alloy <15% Zn piping, piping 

components, and piping 

elements exposed to air with 

borated water leakage

None None NA - No AEM or 

AMP

EP-12

EP-19

V.F-5

V.F-13
NUREG-1801 Vol. 1, Rev. 1 46 September 2005

This Page Intentionally Left Blank
September 2005 47 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

1 BWR/ 

PWR

Steel cranes - structural

girders exposed to air –

indoor uncontrolled (external)

Cumulative fatigue 

damage

TLAA to be evaluated for 

structural girders of 

cranes. See the Standard 

Review Plan, Section 4.7 

for generic guidance for 

meeting the requirements 

of 10 CFR 54.21(c)(1).

Yes, TLAA A-06 VII.B-2

2 BWR/ 

PWR

Steel and stainless steel 

piping, piping components, 

piping elements, and heat 

exchanger components 

exposed to air – indoor 

uncontrolled, treated borated 

water or treated water

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 CFR 

54.21(c)

Yes, TLAA A-34

A-57

A-62

A-100

VII.E1-18

VII.E3-17

VII.E1-16

VII.E3-14

VII.E4-13

VII.E1-4

3 BWR/ 

PWR

Stainless steel heat 

exchanger tubes exposed to 

treated water

Reduction of heat 

transfer due to fouling

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-62 VII.A4-4

VII.E3-6

4 BWR Stainless steel piping, piping 

components, and piping 

elements exposed to sodium 

pentaborate solution >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated

A-59 VII.E2-2

5 BWR/ 

PWR

Stainless steel and stainless 

clad steel heat exchanger 

components exposed to 

treated water >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking

Plant specific Yes, plant specific A-71

A-85

VII.E3-3

VII.E3-19
NUREG-1801 Vol. 1, Rev. 1 48 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

6 BWR/ 

PWR

Stainless steel diesel engine 

exhaust piping, piping 

components, and piping 

elements exposed to diesel 

exhaust

Cracking due to stress 

corrosion cracking

Plant specific Yes, plant specific AP-33 VII.H2-1

7 PWR Stainless steel nonregenerative heat exchanger 

components exposed to 

treated borated water >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking and 

cyclic loading

Water Chemistry and a 

plant-specific verification 

program. An acceptable 

verification program is to 

include temperature and 

radioactivity monitoring of 

the shell side water, and 

eddy current testing of 

tubes.

Yes, plant specific A-69 VII.E1-9

8 PWR Stainless steel regenerative 

heat exchanger components 

exposed to treated borated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking and 

cyclic loading

Water Chemistry and a 

plant-specific verification 

program. The AMP is to 

be augmented by verifying 

the absence of cracking 

due to stress corrosion 

cracking and cyclic 

loading. A plant specific 

aging management 

program is to be 

evaluated.

Yes, plant specific A-84 VII.E1-5
September 2005 49 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

9 PWR Stainless steel high-pressure 

pump casing in PWR 

chemical and volume control 

system 

Cracking due to stress 

corrosion cracking and 

cyclic loading

Water Chemistry and a 

plant-specific verification 

program. The AMP is to 

be augmented by verifying 

the absence of cracking 

due to stress corrosion 

cracking and cyclic 

loading. A plant specific 

aging management 

program is to be 

evaluated.

Yes, plant specific A-76 VII.E1-7

10 BWR/ 

PWR

High-strength steel closure 

bolting exposed to air with 

steam or water leakage.

Cracking due to stress 

corrosion cracking, 

cyclic loading

Bolting Integrity

The AMP is to be 

augmented by appropriate 

inspection to detect 

cracking if the bolts are 

not otherwise replaced 

during maintenance.

Yes, if the bolts 

are not replaced 

during 

maintenance

A-104 VII.E1-8

11 BWR/ 

PWR

Elastomer seals and 

components exposed to air –

indoor uncontrolled 

(internal/external) 

Hardening and loss of 

strength due to 

elastomer degradation

Plant specific Yes, plant specific A-17 VII.F1-7

VII.F2-7

VII.F3-7

VII.F4-6

12 BWR/ 

PWR

Elastomer lining exposed to 

treated water or treated 

borated water

Hardening and loss of 

strength due to 

elastomer degradation

A plant-specific aging 

management program that 

determines and assesses 

the qualified life of the 

linings in the environment 

is to be evaluated.

Yes, plant specific A-15

A-16

VII.A3-1

VII.A4-1
NUREG-1801 Vol. 1, Rev. 1 50 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

13 BWR/ 

PWR

Boral, boron steel spent fuel 

storage racks neutronabsorbing sheets exposed to 

treated water or treated 

borated water

Reduction of neutronabsorbing capacity 

and loss of material 

due to general 

corrosion

Plant specific Yes, plant specific A-88

A-89

VII.A2-5

VII.A2-3

14 BWR/ 

PWR

Steel piping, piping 

component, and piping 

elements exposed to 

lubricating oil

Loss of material due to 

general, pitting, and 

crevice corrosion

Lubricating Oil Analysis 

and One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-30 VII.C1-17

VII.C2-13

VII.E1-19

VII.E4-16

VII.F1-19

VII.F2-17

VII.F3-19

VII.F4-15

VII.G-22

VII.H2-20

15 BWR/ 

PWR

Steel reactor coolant pump 

oil collection system piping, 

tubing, and valve bodies 

exposed to lubricating oil

Loss of material due to 

general, pitting, and 

crevice corrosion

Lubricating Oil Analysis 

and One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated

A-83 VII.G-26

16 BWR/ 

PWR

Steel reactor coolant pump 

oil collection system tank 

exposed to lubricating oil

Loss of material due to 

general, pitting, and 

crevice corrosion

Lubricating Oil Analysis 

and One-Time Inspection 

to evaluate the thickness 

of the lower portion of the 

tank

Yes, detection of 

aging effects is to 

be evaluated

A-82 VII.G-27

17 BWR Steel piping, piping 

components, and piping 

elements exposed to treated 

water

Loss of material due to 

general, pitting, and 

crevice corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

A-35 VII.E3-18

VII.E4-17
September 2005 51 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

18 BWR/ 

PWR

Stainless steel and steel 

diesel engine exhaust piping, 

piping components, and 

piping elements exposed to 

diesel exhaust

Loss of material/ 

general (steel only), 

pitting and crevice 

corrosion

Plant specific Yes, plant specific A-27 VII.H2-2

19 BWR/ 

PWR

Steel (with or without coating 

or wrapping) piping, piping 

components, and piping 

elements exposed to soil

Loss of material due to 

general, pitting, 

crevice, and 

microbiologically 

influenced corrosion

Buried Piping and Tanks 

Surveillance 

or 

Buried Piping and Tanks 

Inspection

No 

Yes, detection of 

aging effects and 

operating 

experience are to 

be further 

evaluated 

A-01 VII.C1-18

VII.C3-9

VII.G-25

VII.H1-9

20 BWR/ 

PWR

Steel piping, piping 

components, piping 

elements, and tanks exposed 

to fuel oil

Loss of material due to 

general, pitting, 

crevice, and 

microbiologically 

influenced corrosion, 

and fouling

Fuel Oil Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

A-30 VII.H1-10

VII.H2-24

21 BWR/ 

PWR

Steel heat exchanger 

components exposed to 

lubricating oil

Loss of material due to 

general, pitting, 

crevice, and 

microbiologically 

influenced corrosion, 

and fouling

Lubricating Oil Analysis 

and One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated

AP-39 VII.H2-5
NUREG-1801 Vol. 1, Rev. 1 52 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

22 BWR/ 

PWR

Steel with elastomer lining or 

stainless steel cladding 

piping, piping components, 

and piping elements exposed 

to treated water and treated 

borated water

Loss of material due to 

pitting and crevice 

corrosion (only for 

steel after 

lining/cladding 

degradation)

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

A-39

A-40

VII.A3-9

VII.A4-12

23 BWR Stainless steel and steel with 

stainless steel cladding heat 

exchanger components 

exposed to treated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

A-70 VII.A4-2

24 BWR/ 

PWR

Stainless steel and aluminum 

piping, piping components, 

and piping elements exposed 

to treated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

A-58

AP-38

VII.A4-11

VII.E3-15

VII.E4-14

VII.A4-5

VII.E3-7

VII.E4-4

25 BWR/ 

PWR

Copper alloy HVAC piping, 

piping components, piping 

elements exposed to 

condensation (external)

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant specific A-46 VII.F1-16

VII.F2-14

VII.F3-16

VII.F4-12

26 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping 

elements exposed to 

lubricating oil

Loss of material due to 

pitting and crevice 

corrosion

Lubricating Oil Analysis 

and One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-47 VII.C1-8

VII.C2-5

VII.E1-12

VII.E4-6

VII.G-11

VII.H2-10
September 2005 53 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

27 BWR/ 

PWR

Stainless steel HVAC 

ducting and aluminum HVAC 

piping, piping components 

and piping elements exposed 

to condensation

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant specific A-09

AP-74

VII.F1-1

VII.F2-1

VII.F3-1

VII.F1-14

VII.F2-12

VII.F3-14

VII.F4-10

28 BWR/ 

PWR

Copper alloy fire protection 

piping, piping components, 

and piping elements exposed 

to condensation (internal)

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant specific AP-78 VII.G-9

29 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to soil

Loss of material due to 

pitting and crevice 

corrosion

A plant-specific aging 

management program is 

to be evaluated.

Yes, plant specific AP-56 VII.C1-16

VII.C3-8

VII.G-20

VII.H1-7

VII.H2-19

30 BWR Stainless steel piping, piping 

components, and piping 

elements exposed to sodium 

pentaborate solution

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-73 VII.E2-1

31 BWR Copper alloy piping, piping 

components, and piping 

elements exposed to treated 

water

Loss of material due to 

pitting, crevice, and 

galvanic corrosion

Water Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-64 VII.A4-7

VII.E3-9

VII.E4-7

32 BWR/ 

PWR

Stainless steel, aluminum 

and copper alloy piping, 

piping components, and 

piping elements exposed to 

fuel oil

Loss of material due to 

pitting, crevice, and 

microbiologically 

influenced corrosion

Fuel Oil Chemistry and 

One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-35

AP-44

AP-54

VII.H1-1

VII.H2-7

VII.G-10

VII.H1-3

VII.H2-9

VII.G-17

VII.H1-6

VII.H2-16
NUREG-1801 Vol. 1, Rev. 1 54 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

33 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to 

lubricating oil

Loss of material due to 

pitting, crevice, and 

microbiologically 

influenced corrosion

Lubricating Oil Analysis 

and One-Time Inspection

Yes, detection of 

aging effects is to 

be evaluated 

AP-59 VII.C1-14

VII.C2-12

VII.E1-15

VII.E4-12

VII.G-18

VII.H2-17

34 BWR/ 

PWR

Elastomer seals and 

components exposed to air –

indoor uncontrolled (internal 

or external)

Loss of material due to 

Wear

Plant specific Yes, plant specific A-18

A-73

VII.F1-6

VII.F2-6

VII.F3-6

VII.F4-5

VII.F1-5

VII.F2-5

VII.F3-5

VII.F4-4

35 PWR Steel with stainless steel 

cladding pump casing 

exposed to treated borated 

water

Loss of material/ 

cladding breach

A plant-specific aging 

management program is 

to be evaluated. 

Reference NRC 

Information Notice 94-63, 

“Boric Acid Corrosion of 

Charging Pump Casings 

Caused by Cladding 

Cracks."

Yes, verify plantspecific program 

addresses 

cladding breach

AP-85 VII.E1-21

36 BWR Boraflex spent fuel storage 

racks neutron-absorbing 

sheets exposed to treated 

water

Reduction of neutronabsorbing capacity 

due to boraflex 

degradation

Boraflex Monitoring No A-87 VII.A2-2

37 BWR Stainless steel piping, piping 

components, and piping 

elements exposed to treated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking, 

intergranular stress 

corrosion cracking

BWR Reactor Water 

Cleanup System

No A-60 VII.E3-16
September 2005 55 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

38 BWR Stainless steel piping, piping 

components, and piping 

elements exposed to treated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking

BWR Stress Corrosion 

Cracking and Water 

Chemistry

No A-61 VII.E4-15

39 BWR Stainless steel BWR spent 

fuel storage racks exposed 

to treated water >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking

Water Chemistry No A-96 VII.A2-6

40 BWR/ 

PWR

Steel tanks in diesel fuel oil 

system exposed to air -

outdoor (external)

Loss of material due to 

general, pitting, and 

crevice corrosion

Aboveground Steel Tanks No A-95 VII.H1-11

41 BWR/ 

PWR

High-strength steel closure 

bolting exposed to air with 

steam or water leakage

Cracking due to cyclic 

loading, stress 

corrosion cracking

Bolting Integrity No A-04 VII.I-3

42 BWR/ 

PWR

Steel closure bolting 

exposed to air with steam or 

water leakage

Loss of material due to 

general corrosion

Bolting Integrity No A-03 VII.I-6

43 BWR/ 

PWR

Steel bolting and closure 

bolting exposed to air –

indoor uncontrolled (external) 

or air – outdoor (External)

Loss of material due to 

general, pitting, and 

crevice corrosion

Bolting Integrity No AP-27

AP-28

VII.I-4

VII.I-1

44 BWR/ 

PWR

Steel compressed air system 

closure bolting exposed to 

condensation

Loss of material due to 

general, pitting, and 

crevice corrosion

Bolting Integrity No A-103 VII.D-1

45 BWR/ 

PWR

Steel closure bolting 

exposed to air – indoor 

uncontrolled (external)

Loss of preload due to 

thermal effects, gasket 

creep, and selfloosening 

Bolting Integrity No AP-26 VII.I-5
NUREG-1801 Vol. 1, Rev. 1 56 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

46 BWR/ 

PWR

Stainless steel and stainless 

clad steel piping, piping 

components, piping 

elements, and heat 

exchanger components 

exposed to closed cycle 

cooling water >60°C 

(>140°F)

Cracking due to stress 

corrosion cracking

Closed-Cycle Cooling 

Water System

No A-68

AP-60

VII.E3-2

VII.C2-11

VII.E3-13

VII.E4-11

47 BWR/ 

PWR

Steel piping, piping 

components, piping 

elements, tanks, and heat 

exchanger components 

exposed to closed cycle 

cooling water

Loss of material due to 

general, pitting, and 

crevice corrosion

Closed-Cycle Cooling 

Water System

No A-25 VII.C2-14

VII.F1-20

VII.F2-18

VII.F3-20

VII.F4-16

VII.H2-23

48 BWR/ 

PWR

Steel piping, piping 

components, piping 

elements, tanks, and heat 

exchanger components 

exposed to closed cycle 

cooling water

Loss of material due to 

general, pitting, 

crevice, and galvanic 

corrosion

Closed-Cycle Cooling 

Water System

No A-63 VII.A3-3

VII.A4-3

VII.C2-1

VII.E1-6

VII.E3-4

VII.E4-2

VII.F1-11

VII.F2-9

VII.F3-11

VII.F4-8

49 BWR/ 

PWR

Stainless steel; steel with 

stainless steel cladding heat 

exchanger components 

exposed to closed cycle 

cooling water

Loss of material due to 

microbiologically 

influenced corrosion

Closed-Cycle Cooling 

Water System

No A-67 VII.E3-1

VII.E4-1
September 2005 57 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

50 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to closed 

cycle cooling water

Loss of material due to 

pitting and crevice 

corrosion

Closed-Cycle Cooling 

Water System

No A-52 VII.C2-10

51 BWR/ 

PWR

Copper alloy piping, piping 

components, piping 

elements, and heat 

exchanger components 

exposed to closed cycle 

cooling water

Loss of material due to 

pitting, crevice, and 

galvanic corrosion

Closed-Cycle Cooling 

Water System

No AP-12

AP-34

VII.A3-5

VII.A4-6

VII.C2-4

VII.E1-11

VII.E3-8

VII.E4-5

VII.F1-15

VII.F2-13

VII.F3-15

VII.F4-11

VII.H1-2

VII.H2-8

VII.E1-2

VII.F1-8

VII.F3-8

52 BWR/ 

PWR

Steel, stainless steel, and 

copper alloy heat exchanger 

tubes exposed to closed 

cycle cooling water

Reduction of heat 

transfer due to fouling

Closed-Cycle Cooling 

Water System

No AP-63

AP-77

AP-80

VII.C2-3

VII.E3-5

VII.E4-3

VII.F1-13

VII.F2-11

VII.F3-13

VII.F4-9

VII.C2-2

VII.F1-12

VII.F2-10

VII.F3-12
NUREG-1801 Vol. 1, Rev. 1 58 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

53 BWR/ 

PWR

Steel compressed air system 

piping, piping components, 

and piping elements exposed 

to condensation (internal)

Loss of material due to 

general and pitting 

corrosion

Compressed Air 

Monitoring

No A-26 VII.D-2

54 BWR/ 

PWR

Stainless steel compressed 

air system piping, piping 

components, and piping 

elements exposed to internal 

condensation

Loss of material due to 

pitting and crevice 

corrosion

Compressed Air 

Monitoring

No AP-81 VII.D-4

55 BWR/ 

PWR

Steel ducting closure bolting 

exposed to air – indoor 

uncontrolled (external)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No A-105 VII.F1-4

VII.F2-4

VII.F3-4

VII.F4-3

VII.I-7

56 BWR/ 

PWR

Steel HVAC ducting and 

components external 

surfaces exposed to air –

indoor uncontrolled (external)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No A-10 VII.F1-2

VII.F2-2

VII.F3-2

VII.F4-1

57 BWR/ 

PWR

Steel piping and components 

external surfaces exposed to 

air – indoor uncontrolled 

(External)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No A-80 VII.D-3

58 BWR/ 

PWR

Steel external surfaces 

exposed to air – indoor 

uncontrolled (external), air -

outdoor (external), and 

condensation (external)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No A-77

A-78

A-81

VII.I-8

VII.I-9

VII.I-11
September 2005 59 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

59 BWR/ 

PWR

Steel heat exchanger 

components exposed to air –

indoor uncontrolled (external) 

or air -outdoor (external)

Loss of material due to 

general, pitting, and 

crevice corrosion

External Surfaces 

Monitoring

No AP-40

AP-41

VII.G-6

VII.H2-4

VII.F1-10

VII.F2-8

VII.F3-10

VII.F4-7

VII.G-5

VII.H2-3

60 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to air -

outdoor (external)

Loss of material due to 

general, pitting, and 

crevice corrosion

External Surfaces 

Monitoring

No A-24 VII.H1-8

61 BWR/ 

PWR

Elastomer fire barrier 

penetration seals exposed to 

air – outdoor or air - indoor 

uncontrolled

Increased hardness, 

shrinkage and loss of 

strength due to 

weathering

Fire Protection No A-19

A-20

VII.G-1

VII.G-2

62 BWR/ 

PWR

Aluminum piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting and crevice 

corrosion

Fire Protection No AP-83 VII.G-8

63 BWR/ 

PWR

Steel fire rated doors 

exposed to air – outdoor or 

air - indoor uncontrolled

Loss of material due to 

Wear

Fire Protection No A-21

A-22

VII.G-3

VII.G-4

64 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to fuel oil

Loss of material due to 

general, pitting, and 

crevice corrosion

Fire Protection and Fuel 

Oil Chemistry

No A-28 VII.G-21

65 BWR/ 

PWR

Reinforced concrete 

structural fire barriers –

walls, ceilings and floors 

exposed to air – indoor 

uncontrolled

Concrete cracking and 

spalling due to 

aggressive chemical 

attack, and reaction 

with aggregates

Fire Protection and 

Structures Monitoring 

Program

No A-90 VII.G-28
NUREG-1801 Vol. 1, Rev. 1 60 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

66 BWR/ 

PWR

Reinforced concrete 

structural fire barriers –

walls, ceilings and floors 

exposed to air – outdoor

Concrete cracking and 

spalling due to freeze 

thaw, aggressive 

chemical attack, and 

reaction with 

aggregates

Fire Protection and 

Structures Monitoring 

Program

No A-92 VII.G-30

67 BWR/ 

PWR

Reinforced concrete 

structural fire barriers –

walls, ceilings and floors 

exposed to air – outdoor or 

air - indoor uncontrolled

Loss of material due to 

corrosion of embedded 

steel

Fire Protection and 

Structures Monitoring 

Program

No A-91

A-93

VII.G-29

VII.G-31

68 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

general, pitting, 

crevice, and 

microbiologically 

influenced corrosion, 

and fouling

Fire Water System No A-33 VII.G-24

69 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting and crevice 

corrosion, and fouling

Fire Water System No A-55 VII.G-19

70 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologically 

influenced corrosion, 

and fouling

Fire Water System No A-45 VII.G-12

71 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements exposed to moist 

air or condensation (Internal)

Loss of material due to 

general, pitting, and 

crevice corrosion

Inspection of Internal 

Surfaces in Miscellaneous 

Piping and Ducting 

Components

No A-23 VII.G-23

VII.H2-21
September 2005 61 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

72 BWR/ 

PWR

Steel HVAC ducting and 

components internal 

surfaces exposed to 

condensation (Internal)

Loss of material due to 

general, pitting, 

crevice, and (for drip 

pans and drain lines) 

microbiologically 

influenced corrosion

Inspection of Internal 

Surfaces in Miscellaneous 

Piping and Ducting 

Components

No A-08 VII.F1-3

VII.F2-3

VII.F3-3

VII.F4-2

73 BWR/ 

PWR

Steel crane structural girders 

in load handling system 

exposed to air- indoor 

uncontrolled (external)

Loss of material due to 

general corrosion

Inspection of Overhead 

Heavy Load and Light 

Load (Related to 

Refueling) Handling 

Systems

No A-07 VII.B-3

74 BWR/ 

PWR

Steel cranes - rails exposed 

to air – indoor uncontrolled 

(external)

Loss of material due to 

Wear

Inspection of Overhead 

Heavy Load and Light 

Load (Related to 

Refueling) Handling 

Systems

No A-05 VII.B-1

75 BWR/ 

PWR

Elastomer seals and 

components exposed to raw 

water

Hardening and loss of 

strength due to 

elastomer degradation; 

loss of material due to 

erosion

Open-Cycle Cooling 

Water System

No AP-75

AP-76

VII.C1-1

VII.C1-2

76 BWR/ 

PWR

Steel piping, piping 

components, and piping 

elements (without 

lining/coating or with 

degraded lining/coating) 

exposed to raw water

Loss of material due to 

general, pitting, 

crevice, and 

microbiologically 

influenced corrosion, 

fouling, and 

lining/coating 

degradation

Open-Cycle Cooling 

Water System

No A-38 VII.C1-19

VII.C3-10

VII.H2-22
NUREG-1801 Vol. 1, Rev. 1 62 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

77 BWR/ 

PWR

Steel heat exchanger 

components exposed to raw 

water

Loss of material due to 

general, pitting, 

crevice, galvanic, and 

microbiologically 

influenced corrosion, 

and fouling

Open-Cycle Cooling 

Water System

No A-64 VII.C1-5

78 BWR/ 

PWR

Stainless steel, nickel alloy, 

and copper alloy piping, 

piping components, and 

piping elements exposed to 

raw water

Loss of material due to 

pitting and crevice 

corrosion

Open-Cycle Cooling 

Water System

No A-43

A-53

AP-53

VII.C3-2

VII.C3-7

VII.C1-13

VII.C3-6

79 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting and crevice 

corrosion, and fouling

Open-Cycle Cooling 

Water System

No A-54 VII.C1-15

80 BWR/ 

PWR

Stainless steel and copper 

alloy piping, piping 

components, and piping 

elements exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologically 

influenced corrosion

Open-Cycle Cooling 

Water System

No AP-45

AP-55

VII.H2-11

VII.H2-18

81 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping 

elements, exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologically 

influenced corrosion, 

and fouling

Open-Cycle Cooling 

Water System

No A-44 VII.C1-9

82 BWR/ 

PWR

Copper alloy heat exchanger 

components exposed to raw 

water

Loss of material due to 

pitting, crevice, 

galvanic, and 

microbiologically 

influenced corrosion, 

and fouling

Open-Cycle Cooling 

Water System

No A-65 VII.C1-3
September 2005 63 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

83 BWR/ 

PWR

Stainless steel and copper 

alloy heat exchanger tubes 

exposed to raw water

Reduction of heat 

transfer due to fouling

Open-Cycle Cooling 

Water System

No A-72

AP-61

VII.C1-6

VII.C1-7

VII.C3-1

VII.G-7

VII.H2-6

84 BWR/ 

PWR

Copper alloy >15% Zn 

piping, piping components, 

piping elements, and heat 

exchanger components 

exposed to raw water, 

treated water, or closed cycle 

cooling water

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No A-47

A-66

AP-32

AP-43

AP-65

VII.C1-10

VII.C3-3

VII.G-13

VII.H2-13

VII.C1-4

VII.A4-9

VII.C2-7

VII.E3-11

VII.E4-9

VII.A3-6

VII.A4-8

VII.C2-6

VII.E1-13

VII.E3-10

VII.E4-8

VII.F1-17

VII.F2-15

VII.F3-17

VII.F4-13

VII.H1-4

VII.H2-12

VII.E1-3

VII.F1-9

VII.F3-9
NUREG-1801 Vol. 1, Rev. 1 64 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

85 BWR/ 

PWR

Gray cast iron piping, piping 

components, and piping 

elements exposed to soil, 

raw water, treated water, or 

closed-cycle cooling water

Loss of material due to 

selective leaching

Selective Leaching of 

Materials

No A-02

A-50

A-51

AP-31

VII.C1-12

VII.C3-5

VII.G-15

VII.H1-5

VII.H2-15

VII.C2-8

VII.F3-18

VII.C1-11

VII.C3-4

VII.G-14

VII.H2-14

VII.A3-7

VII.A4-10

VII.C2-9

VII.E1-14

VII.E3-12

VII.E4-10

VII.F1-18

VII.F2-16

VII.F4-14

VII.G-16

86 BWR/ 

PWR

Structural steel (new fuel 

storage rack assembly) 

exposed to air – indoor 

uncontrolled (external)

Loss of material due to 

general, pitting, and 

crevice corrosion

Structures Monitoring 

Program

No A-94 VII.A1-1

87 PWR Boraflex spent fuel storage 

racks neutron-absorbing 

sheets exposed to treated 

borated water

Reduction of neutronabsorbing capacity 

due to boraflex 

degradation

Boraflex Monitoring No A-86 VII.A2-4
September 2005 65 NUREG-1801 Vol. 1, Rev. 1

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

88 PWR Aluminum and copper alloy 

>15% Zn piping, piping 

components, and piping 

elements exposed to air with 

borated water leakage

Loss of material due to 

Boric acid corrosion

Boric Acid Corrosion No AP-1

AP-66

VII.A3-4

VII.E1-10

VII.I-12

89 PWR Steel bolting and external 

surfaces exposed to air with 

borated water leakage

Loss of material due to 

Boric acid corrosion

Boric Acid Corrosion No A-79

A-102

VII.A3-2

VII.E1-1

VII.I-10

VII.I-2

90 PWR Stainless steel and steel with 

stainless steel cladding 

piping, piping components, 

piping elements, tanks, and 

fuel storage racks exposed 

to treated borated water 

>60°C (>140°F)

Cracking due to stress 

corrosion cracking

Water Chemistry No A-56

A-97

AP-82

VII.A3-10

VII.A2-7

VII.E1-20

91 PWR Stainless steel and steel with 

stainless steel cladding 

piping, piping components, 

and piping elements exposed 

to treated borated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry No AP-79 VII.A2-1

VII.A3-8

VII.E1-17

92 BWR/ 

PWR

Galvanized steel piping, 

piping components, and 

piping elements exposed to 

air – indoor uncontrolled

None None NA - No AEM or

AMP

AP-13 VII.J-6

93 BWR/ 

PWR

Glass piping elements 

exposed to air, air – indoor 

uncontrolled (external), fuel

oil, lubricating oil, raw water, 

treated water, and treated 

borated water

None None NA - No AEM or 

AMP

AP-14

AP-15

AP-48

AP-49

AP-50

AP-51

AP-52

VII.J-8

VII.J-10

VII.J-7

VII.J-9

VII.J-11

VII.J-13

VII.J-12
NUREG-1801 Vol. 1, Rev. 1 66 September 2005

Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

94 BWR/ 

PWR

Stainless steel and nickel 

alloy piping, piping 

components, and piping 

elements exposed to air –

indoor uncontrolled (external)

None None NA - No AEM or 

AMP

AP-16

AP-17

VII.J-14

VII.J-15

95 BWR/ 

PWR

Steel and aluminum piping, 

piping components, and 

piping elements exposed to 

air – indoor controlled 

(external)

None None NA - No AEM or 

AMP

AP-2

AP-36

VII.J-20

VII.J-1

96 BWR/ 

PWR

Steel and stainless steel 

piping, piping components, 

and piping elements in 

concrete

None None NA - No AEM or 

AMP

AP-3

AP-19

VII.J-21

VII.J-17

97 BWR/ 

PWR

Steel, stainless steel, 

aluminum, and copper alloy 

piping, piping components, 

and piping elements exposed 

to gas

None None NA - No AEM or 

AMP

AP-6

AP-9

AP-22

AP-37

VII.J-23

VII.J-4

VII.J-19

VII.J-2

98 BWR/ 

PWR

Steel, stainless steel, and 

copper alloy piping, piping 

components, and piping 

elements exposed to dried 

air

None None NA - No AEM or 

AMP

AP-4

AP-8

AP-20

VII.J-22

VII.J-3

VII.J-18

99 PWR Stainless steel and copper 

alloy <15% Zn piping, piping 

components, and piping 

elements exposed to air with 

borated water leakage

None None NA - No AEM or 

AMP

AP-11

AP-18

VII.J-5

VII.J-16
September 2005 67 NUREG-1801 Vol. 1, Rev. 1

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

1 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

steam or treated water

Cumulative fatigue 

damage

TLAA, evaluated in 

accordance with 10 

CFR 54.21(c)

Yes, TLAA S-08

S-11

VIII.B1-10

VIII.B2-5

VIII.D1-7

VIII.D2-6

VIII.G-37

2 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

steam

Loss of material due to 

general, pitting and 

crevice corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-04

S-06

VIII.A-15

VIII.C-3

VIII.A-16

VIII.C-4

3 PWR Steel heat exchanger components 

exposed to treated water

Loss of material due to 

general, pitting and 

crevice corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-19 VIII.E-37

VIII.F-28

4 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

treated water

Loss of material due to 

general, pitting and 

crevice corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-09

S-10

VIII.B2-6

VIII.C-6

VIII.D2-7

VIII.E-33

VIII.B1-11

VIII.C-7

VIII.D1-8

VIII.E-34

VIII.F-25

VIII.G-38

5 BWR Steel heat exchanger components 

exposed to treated water

Loss of material due to 

general, pitting, 

crevice, and galvanic 

corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-18 VIII.E-7
NUREG-1801 Vol. 1, Rev. 1 68 September 2005

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

6 BWR/ 

PWR

Steel and stainless steel tanks 

exposed to treated water

Loss of material due to 

general (steel only) 

pitting and crevice 

corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-13 VIII.E-40

VIII.G-41

7 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

lubricating oil

Loss of material due to 

general, pitting and 

crevice corrosion

Lubricating Oil 

Analysis and OneTime Inspection

Yes, detection of aging 

effects is to be 

evaluated

SP-25 VIII.A-14

VIII.D1-6

VIII.D2-5

VIII.E-32

VIII.G-35

8 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

raw water

Loss of material due to 

general, pitting, 

crevice, and 

microbiologicallyinfluenced corrosion, 

and fouling

Plant specific Yes, plant specific S-12 VIII.G-36

9 BWR/ 

PWR

Stainless steel and copper alloy 

heat exchanger tubes exposed to 

treated water

Reduction of heat 

transfer due to fouling

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

SP-40

SP-58

VIII.E-13

VIII.F-10

VIII.E-10

VIII.F-7

VIII.G-10

10 BWR/ 

PWR

Steel, stainless steel, and copper 

alloy heat exchanger tubes 

exposed to lubricating oil

Reduction of heat 

transfer due to fouling

Lubricating Oil 

Analysis and OneTime Inspection

Yes, detection of aging 

effects is to be 

evaluated 

SP-53

SP-62

SP-63

VIII.G-8

VIII.G-12

VIII.G-15
September 2005 69 NUREG-1801 Vol. 1, Rev. 1

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

11 BWR/ 

PWR

Buried steel piping, piping 

components, piping elements, and 

tanks (with or without coating or 

wrapping) exposed to soil

Loss of material due to 

general, pitting, 

crevice, and 

microbiologicallyinfluenced corrosion

Buried Piping and 

Tanks Surveillance 

or 

Buried Piping and 

Tanks Inspection

No 

Yes, detection of aging 

effects and operating 

experience are to be 

further evaluated 

S-01 VIII.E-1

VIII.G-1

12 BWR/ 

PWR

Steel heat exchanger components 

exposed to lubricating oil

Loss of material due to 

general, pitting, 

crevice, and 

microbiologicallyinfluenced corrosion

Lubricating Oil 

Analysis and OneTime Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-17 VIII.G-6

13 BWR Stainless steel piping, piping 

components, piping elements 

exposed to steam

Cracking due to stress 

corrosion cracking

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

SP-45 VIII.A-11

VIII.B2-1

14 BWR/ 

PWR

Stainless steel piping, piping 

components, piping elements, 

tanks, and heat exchanger 

components exposed to treated 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-39

SP-17

SP-19

SP-42

VIII.F-3

VIII.B1-5

VIII.C-2

VIII.D1-5

VIII.E-30

VIII.F-24

VIII.G-33

VIII.E-31

VIII.E-38
NUREG-1801 Vol. 1, Rev. 1 70 September 2005

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

15 BWR/ 

PWR

Aluminum and copper alloy piping, 

piping components, and piping 

elements exposed to treated water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

SP-24

SP-61

VIII.D1-1

VIII.D2-1

VIII.E-15

VIII.F-12

VIII.G-17

VIII.A-5

VIII.F-15

16 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping elements; 

tanks, and heat exchanger 

components exposed to treated 

water

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry 

and One-Time 

Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-21

S-22

SP-16

VIII.E-4

VIII.E-36

VIII.F-27

VIII.B1-4

VIII.C-1

VIII.D1-4

VIII.D2-4

VIII.E-29

VIII.F-23

VIII.G-32

17 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping elements 

exposed to soil

Loss of material due to 

pitting and crevice 

corrosion

Plant specific Yes, plant specific SP-37 VIII.E-28

VIII.G-31

18 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping elements 

exposed to lubricating oil

Loss of material due to 

pitting and crevice 

corrosion

Lubricating Oil 

Analysis and OneTime Inspection

Yes, detection of aging 

effects is to be 

evaluated 

SP-32 VIII.A-3

VIII.D1-2

VIII.D2-2

VIII.E-17

VIII.G-19
September 2005 71 NUREG-1801 Vol. 1, Rev. 1

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

19 BWR/ 

PWR

Stainless steel piping, piping 

components, piping elements, and 

heat exchanger components 

exposed to lubricating oil

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion

Lubricating Oil 

Analysis and OneTime Inspection

Yes, detection of aging 

effects is to be 

evaluated 

S-20

SP-38

VIII.G-3

VIII.A-9

VIII.D1-3

VIII.D2-3

VIII.E-26

VIII.G-29

20 BWR/ 

PWR

Steel tanks exposed to air –

outdoor (external)

Loss of material/ 

general, pitting, and 

crevice corrosion

Aboveground Steel 

Tanks

No S-31 VIII.E-39

VIII.G-40

21 BWR/ 

PWR

High-strength steel closure bolting 

exposed to air with steam or water 

leakage

Cracking due to cyclic 

loading, stress 

corrosion cracking

Bolting Integrity No S-03 VIII.H-3

22 BWR/ 

PWR

Steel bolting and closure bolting 

exposed to air with steam or water 

leakage, air – outdoor (external), 

or air – indoor uncontrolled 

(external); 

Loss of material due to 

general, pitting and 

crevice corrosion; loss 

of preload due to 

thermal effects, gasket 

creep, and selfloosening 

Bolting Integrity No S-02

S-32

S-33

S-34

VIII.H-6

VIII.H-1

VIII.H-5

VIII.H-4

23 BWR/ 

PWR

Stainless steel piping, piping 

components, and piping elements 

exposed to closed-cycle cooling 

water >60°C (>140°F)

Cracking due to stress 

corrosion cracking

Closed-Cycle 

Cooling Water 

System

No SP-54 VIII.E-25

VIII.F-21

VIII.G-28

24 BWR/ 

PWR

Steel heat exchanger components 

exposed to closed cycle cooling 

water

Loss of material due to 

general, pitting, 

crevice, and galvanic 

corrosion

Closed-Cycle 

Cooling Water 

System

No S-23 VIII.A-1

VIII.E-5

VIII.F-4

VIII.G-5
NUREG-1801 Vol. 1, Rev. 1 72 September 2005

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

25 BWR/ 

PWR

Stainless steel piping, piping 

components, piping elements, and 

heat exchanger components 

exposed to closed cycle cooling 

water

Loss of material due to 

pitting and crevice 

corrosion

Closed-Cycle 

Cooling Water 

System

No S-25

SP-39

VIII.E-2

VIII.F-1

VIII.G-2

VIII.E-24

VIII.F-20

VIII.G-27

26 BWR/ 

PWR

Copper alloy piping, piping 

components, and piping elements 

exposed to closed cycle cooling 

water

Loss of material due to 

pitting, crevice, and 

galvanic corrosion

Closed-Cycle 

Cooling Water 

System

No SP-8 VIII.E-16

VIII.F-13

VIII.G-18

27 BWR/ 

PWR

Steel, stainless steel, and copper 

alloy heat exchanger tubes 

exposed to closed cycle cooling 

water

Reduction of heat 

transfer due to fouling

Closed-Cycle

Cooling Water 

System

No SP-41

SP-57

SP-64

VIII.E-11

VIII.F-8

VIII.G-11

VIII.E-8

VIII.A-2

VIII.E-14

VIII.F-11

VIII.G-14

28 BWR/ 

PWR

Steel external surfaces exposed to 

air – indoor uncontrolled (external), 

condensation (external), or air 

outdoor (external)

Loss of material due to 

general corrosion

External Surfaces 

Monitoring

No S-29

S-41

S-42

VIII.H-7

VIII.H-8

VIII.H-10
September 2005 73 NUREG-1801 Vol. 1, Rev. 1

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

29 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to 

steam or treated water

Wall thinning due to 

flow-accelerated 

corrosion

Flow-Accelerated 

Corrosion 

No S-15

S-16

VIII.A-17

VIII.B1-9

VIII.B2-4

VIII.C-5

VIII.D1-9

VIII.D2-8

VIII.E-35

VIII.F-26

VIII.G-39

30 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to air 

outdoor (internal) or condensation 

(internal)

Loss of material due to 

general, pitting, and 

crevice corrosion

Inspection of 

Internal Surfaces in 

Miscellaneous 

Piping and Ducting 

Components

No SP-59

SP-60

VIII.B1-6

VIII.B1-7

VIII.G-34

31 BWR/ 

PWR

Steel heat exchanger components 

exposed to raw water

Loss of material due to 

general, pitting, 

crevice, galvanic, and 

microbiologicallyinfluenced corrosion, 

and fouling

Open-Cycle 

Cooling Water 

System

No S-24 VIII.E-6

VIII.F-5

VIII.G-7

32 BWR/ 

PWR

Stainless steel and copper alloy 

piping, piping components, and 

piping elements exposed to raw 

water

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion

Open-Cycle 

Cooling Water 

System

No SP-31

SP-36

VIII.A-4

VIII.E-18

VIII.F-14

VIII.G-20

VIII.E-27

VIII.F-22

VIII.G-30
NUREG-1801 Vol. 1, Rev. 1 74 September 2005

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

33 BWR/ 

PWR

Stainless steel heat exchanger 

components exposed to raw water

Loss of material due to 

pitting, crevice, and 

microbiologicallyinfluenced corrosion, 

and fouling

Open-Cycle 

Cooling Water 

System

No S-26 VIII.E-3

VIII.F-2

VIII.G-4

34 BWR/ 

PWR

Steel, stainless steel, and copper 

alloy heat exchanger tubes 

exposed to raw water

Reduction of heat 

transfer due to fouling

Open-Cycle 

Cooling Water 

System

No S-27

S-28

SP-56

VIII.G-16

VIII.E-12

VIII.F-9

VIII.G-13

VIII.E-9

VIII.F-6

VIII.G-9

35 BWR/ 

PWR

Copper alloy >15% Zn piping, 

piping components, and piping 

elements exposed to closed cycle 

cooling water, raw water, or 

treated water

Loss of material due to 

selective leaching

Selective Leaching 

of Materials

No SP-29

SP-30

SP-55

VIII.E-19

VIII.F-16

VIII.G-21

VIII.A-6

VIII.E-20

VIII.F-17

VIII.G-22

VIII.E-21

VIII.F-18

VIII.G-23
September 2005 75 NUREG-1801 Vol. 1, Rev. 1

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

36 BWR/ 

PWR

Gray cast iron piping, piping 

components, and piping elements 

exposed to soil, treated water, or

raw water

Loss of material due to 

selective leaching

Selective Leaching 

of Materials

No SP-26

SP-27

SP-28

VIII.E-22

VIII.G-25

VIII.A-8

VIII.E-23

VIII.F-19

VIII.G-26

VIII.A-7

VIII.G-24

37 BWR/ 

PWR

Steel, stainless steel, and nickelbased alloy piping, piping 

components, and piping elements 

exposed to steam

Loss of material due to 

pitting and crevice 

corrosion

Water Chemistry No S-05

S-07

SP-18

SP-43

SP-46

VIII.B2-3

VIII.B1-8

VIII.B1-1

VIII.A-12

VIII.B1-3

VIII.A-13

VIII.B2-2

38 PWR Steel bolting and external surfaces 

exposed to air with borated water 

leakage

Loss of material due to 

boric acid corrosion

Boric Acid 

Corrosion

No S-30

S-40

VIII.H-9

VIII.H-2

39 PWR Stainless steel piping, piping 

components, and piping elements 

exposed to steam

Cracking due to stress 

corrosion cracking

Water Chemistry No SP-44 VIII.A-10

VIII.B1-2

40 BWR/ 

PWR

Glass piping elements exposed to 

air, lubricating oil, raw water, and 

treated water

None None NA - No AEM or AMP SP-9

SP-10

SP-33

SP-34

SP-35

VIII.I-5

VIII.I-6

VIII.I-4

VIII.I-7

VIII.I-8
NUREG-1801 Vol. 1, Rev. 1 76 September 2005

Table 4. Summary of Aging Management Programs for the Steam and Power Conversion System 

Evaluated in Chapter VIII of the GALL Report

ID Type Component Aging 

Effect/Mechanism

Aging 

Management 

Programs

Further Evaluation 

Recommended

Related

Generic

Item

Unique

Item

41 BWR/ 

PWR

Stainless steel, copper alloy, and 

nickel alloy piping, piping 

components, and piping elements 

exposed to air – indoor 

uncontrolled (external)

None None NA - No AEM or AMP SP-6

SP-11

SP-12

VIII.I-2

VIII.I-9

VIII.I-10

42 BWR/ 

PWR

Steel piping, piping components, 

and piping elements exposed to air 

– indoor controlled (external)

None None NA - No AEM or AMP SP-1 VIII.I-13

43 BWR/ 

PWR

Steel and stainless steel piping, 

piping components, and piping 

elements in concrete

None None NA - No AEM or AMP SP-2

SP-13

VIII.I-14

VIII.I-11

44 BWR/ 

PWR

Steel, stainless steel, aluminum, 

and copper alloy piping, piping 

components, and piping elements 

exposed to gas

None None NA - No AEM or AMP SP-4

SP-5

SP-15

SP-23

VIII.I-15

VIII.I-3

VIII.I-12

VIII.I-1
September 2005 77 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

PWR Concrete (Reinforced and Prestressed) and Steel Containment 

BWR Concrete (Mark II and III) and Steel (Mark I, II, and III) Containment

1 BWR/ 

PWR

Concrete elements: 

walls, dome, 

basemat, ring girder, 

buttresses, 

containment (as 

applicable). 

Aging of accessible 

and inaccessible 

concrete areas due 

to aggressive 

chemical attack, 

and corrosion of 

embedded steel

ISI (IWL) and for inaccessible 

concrete, an examination of 

representative samples of belowgrade concrete and periodic 

monitoring of groundwater if 

environment is non-aggressive. 

A plant specific program is to be 

evaluated if environment is 

aggressive.

Yes, plant-specific, if 

the environment is 

aggressive

C-03

C-05

C-25

C-26

C-27

C-41

C-42

C-43

II.A1-4

II.A1-7

II.A2-4

II.B3.1-1

II.B1.2-5

II.B2.2-5

II.B3.2-5

II.B1.2-2

II.B2.2-2

II.B3.2-7

II.A2-7

II.B3.1-6

2 BWR/ 

PWR

Concrete elements; 

All

Cracks and 

distortion due to 

increased stress 

levels from 

settlement 

Structures Monitoring Program. 

If a de-watering system is relied 

upon for control of settlement, 

then the licensee is to ensure 

proper functioning of the dewatering system through the 

period of extended operation.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

a de-watering system 

is relied upon

C-06

C-36

C-37

II.B1.2-1

II.B2.2-1

II.B3.2-1

II.A2-5

II.B3.1-2

II.A1-5

3 BWR/ 

PWR

Concrete elements: 

foundation, subfoundation 

Reduction in 

foundation strength, 

cracking, differential 

settlement due to 

erosion of porous 

concrete 

subfoundation

Structures Monitoring Program. 

If a de-watering system is relied 

upon to control erosion of 

cement from porous concrete 

subfoundations, then the 

licensee is to ensure proper 

functioning of the de-watering 

system through the period of 

extended operation.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

a de-watering system 

is relied upon

C-07 II.A1-8

II.A2-8

II.B1.2-7

II.B2.2-7

II.B3.1-7

II.B3.2-8
NUREG-1801 Vol. 1, Rev. 1 78 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

4 BWR/ 

PWR

Concrete elements: 

dome, wall, basemat, 

ring girder, 

buttresses, 

containment, 

concrete fill-in 

annulus (as 

applicable) 

Reduction of 

strength and 

modulus due to 

elevated 

temperature 

Plant-specific Yes, plant-specific if 

temperature limits are 

exceeded

C-08

C-33

C-34

C-35

C-50

II.A1-1

II.B3.2-2

II.A2-1

II.B1.2-3

II.B2.2-3

II.B3.1-4

5 BWR Steel elements: 

Drywell; torus; drywell 

head; embedded 

shell and sand pocket 

regions; drywell 

support skirt; torus 

ring girder; 

downcomers; liner 

plate, ECCS suction 

header, support skirt, 

region shielded by 

diaphragm floor, 

suppression chamber

(as applicable)

Loss of material due 

to general, pitting 

and crevice 

corrosion

ISI (IWE) and 10 CFR Part 50, 

Appendix J

Yes, if corrosion is 

significant for 

inaccessible areas

C-19

C-46

II.B1.1-2

II.B3.1-8

II.B1.2-8

II.B2.1-1

II.B2.2-10

6 BWR/ 

PWR

Steel elements: steel 

liner, liner anchors, 

integral attachments

Loss of material due 

to general, pitting 

and crevice 

corrosion

ISI (IWE) and 10 CFR Part 50, 

Appendix J

Yes, if corrosion is 

significant for 

inaccessible areas

C-09 II.A1-11

II.A2-9

II.B3.2-9

7 BWR/ 

PWR

Prestressed 

containment tendons 

Loss of prestress 

due to relaxation, 

shrinkage, creep, 

and elevated 

temperature 

TLAA evaluated in accordance 

with 10 CFR 54.21(c) 

Yes, TLAA C-11 II.A1-9

II.B2.2-8
September 2005 79 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

8 BWR Steel and stainless 

steel elements: vent 

line, vent header, 

vent line bellows; 

downcomers; 

Cumulative fatigue 

damage (CLB 

fatigue analysis 

exists) 

TLAA evaluated in accordance 

with 10 CFR 54.21(c) 

Yes, TLAA C-21

C-48

II.B1.1-4

II.B2.2-14

9 BWR/ 

PWR

Steel, stainless steel 

elements, dissimilar 

metal welds: 

penetration sleeves, 

penetration bellows; 

suppression pool 

shell, unbraced 

downcomers

Cumulative fatigue 

damage (CLB 

fatigue analysis 

exists) 

TLAA evaluated in accordance 

with 10 CFR 54.21(c) 

Yes, TLAA C-13

C-45

II.A3-4

II.B4-4

II.B2.1-4

10 BWR/ 

PWR

Stainless steel 

penetration sleeves, 

penetration bellows, 

dissimilar metal welds

Cracking due to 

stress corrosion 

cracking

ISI (IWE) and 10 CFR Part 50, 

Appendix J and additional 

appropriate 

examinations/evaluations for 

bellows assemblies and 

dissimilar metal welds

Yes, detection of aging 

effects is to be 

evaluated

C-15 II.A3-2

II.B4-2

11 BWR Stainless steel vent 

line bellows, 

Cracking due to 

stress corrosion 

cracking

ISI (IWE) and 10 CFR Part 50, 

Appendix J, and additional 

appropriate 

examination/evaluation for 

bellows assemblies and 

dissimilar metal welds

Yes, detection of aging 

effects is to be 

evaluated

C-22 II.B1.1-5
NUREG-1801 Vol. 1, Rev. 1 80 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

12 BWR/ 

PWR

Steel, stainless steel 

elements, dissimilar 

metal welds: 

penetration sleeves, 

penetration bellows; 

suppression pool 

shell, unbraced 

downcomers 

Cracking due to 

cyclic loading

ISI (IWE) and 10 CFR Part 50, 

Appendix J supplemented to 

detect fine cracks

Yes, detection of aging 

effects is to be 

evaluated

C-14

C-44

II.A3-3

II.B4-3

II.B2.1-3

13 BWR Steel, stainless steel 

elements, dissimilar 

metal welds: torus; 

vent line; vent 

header; vent line 

bellows; downcomers 

Cracking due to 

cyclic loading

ISI (IWE) and 10 CFR Part 50, 

Appendix J supplemented to 

detect fine cracks

Yes, detection of aging 

effects is to be 

evaluated

C-20

C-47

II.B1.1-3

II.B2.2-13

14 BWR/ 

PWR

Concrete elements: 

dome, wall, basemat 

ring girder, 

buttresses, 

containment (as 

applicable) 

Loss of material 

(Scaling, cracking, 

and spalling) due to 

freeze-thaw

ISI (IWL) 

Evaluation is needed for plants 

that are located in moderate to 

severe weathering conditions 

(weathering index >100 dayinch/yr) (NUREG-1557).

Yes, for inaccessible 

areas of plants located 

in moderate to severe 

weathering conditions 

C-01

C-28

C-29

II.A1-2

II.A2-2

II.B3.2-3

15 BWR/ 

PWR

Concrete elements: 

walls, dome, 

basemat, ring girder, 

buttresses, 

containment, 

concrete fill-in 

annulus (as 

applicable). 

Increase in porosity, 

permeability due to 

leaching of calcium 

hydroxide; cracking 

due to expansion 

and reaction with 

aggregate 

ISI (IWL) for accessible areas. 

None for inaccessible areas if 

concrete was constructed in 

accordance with the 

recommendations in ACI 

201.2R.

Yes, if concrete was 

not constructed as 

stated for inaccessible 

areas

C-02

C-04

C-30

C-31

C-32

C-38

C-39

C-40

C-51

II.A1-6

II.A1-3

II.A2-6

II.B3.1-3

II.B1.2-6

II.B2.2-6

II.B3.2-6

II.A2-3

II.B1.2-4

II.B2.2-4

II.B3.2-4

II.B3.1-5
September 2005 81 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

16 BWR/ 

PWR

Seals, gaskets, and 

moisture barriers 

Loss of sealing and 

leakage through 

containment due to 

deterioration of joint 

seals, gaskets, and 

moisture barriers 

(caulking, flashing, 

and other sealants)

ISI (IWE) and 10 CFR Part 50, 

Appendix J

No C-18 II.A3-7

II.B4-7

17 BWR/ 

PWR

Personnel airlock, 

equipment hatch and 

CRD hatch locks, 

hinges, and closure 

mechanisms

Loss of leak 

tightness in closed 

position due to 

mechanical wear of 

locks, hinges and 

closure 

mechanisms

10 CFR Part 50, Appendix J and 

Plant Technical Specifications

No C-17 II.A3-5

II.B4-5

18 BWR/ 

PWR

Steel penetration 

sleeves and 

dissimilar metal 

welds; personnel 

airlock, equipment 

hatch and CRD hatch

Loss of material due 

to general, pitting, 

and crevice 

corrosion

ISI (IWE) and 10 CFR Part 50, 

Appendix J

No C-12

C-16

II.A3-1

II.B4-1

II.A3-6

II.B4-6

19 BWR Steel elements: 

stainless steel 

suppression chamber 

shell (inner surface)

Cracking due to 

stress corrosion 

cracking

ISI (IWE) and 10 CFR Part 50, 

Appendix J

No C-24 II.B3.1-9

II.B3.2-10

20 BWR Steel elements: 

suppression chamber 

liner (interior surface)

Loss of material due 

to general, pitting, 

and crevice 

corrosion

ISI (IWE) and 10 CFR Part 50, 

Appendix J

No C-49 II.B1.2-10

II.B2.2-12
NUREG-1801 Vol. 1, Rev. 1 82 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

21 BWR Steel elements: 

drywell head and 

downcomer pipes 

Fretting or lock up 

due to mechanical 

wear 

ISI (IWE) No C-23 II.B1.1-1

II.B1.2-9

II.B2.1-2

II.B2.2-11

22 BWR/ 

PWR

Prestressed 

containment: tendons 

and anchorage 

components 

Loss of material due 

to corrosion

ISI (IWL) No C-10 II.A1-10

II.B2.2-9

Safety-Related and Other Structures; and Component Supports

23 BWR/ 

PWR

All Groups except 

Group 6: interior and 

above grade exterior 

concrete

Cracking, loss of 

bond, and loss of 

material (spalling, 

scaling) due to 

corrosion of 

embedded steel

Structures Monitoring Program Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-01 III.A1-6

III.A2-6

III.A3-6

III.A5-6

III.A7-5

III.A8-5

III.A9-5

24 BWR/ 

PWR

All Groups except 

Group 6: interior and 

above grade exterior 

concrete

Increase in porosity 

and permeability, 

cracking, loss of 

material (spalling, 

scaling) due to 

aggressive 

chemical attack

Structures Monitoring Program Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-06 III.A1-10

III.A2-10

III.A3-10

III.A4-4

III.A5-10

III.A7-9

III.A9-9

25 BWR/ 

PWR

All Groups except 

Group 6: steel 

components: all 

structural steel 

Loss of material due 

to corrosion

Structures Monitoring Program. 

If protective coatings are relied 

upon to manage the effects of 

aging, the structures monitoring 

program is to include provisions 

to address protective coating 

monitoring and maintenance.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-11 III.A1-12

III.A2-12

III.A3-12

III.A4-5

III.A5-12

III.A7-10

III.A8-8
September 2005 83 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

26 BWR/ 

PWR

All Groups except 

Group 6: accessible 

and inaccessible 

concrete: foundation

Loss of material 

(spalling, scaling) 

and cracking due to 

freeze-thaw

Structures Monitoring Program. 

Evaluation is needed for plants 

that are located in moderate to 

severe weathering conditions 

(weathering index >100 dayinch/yr) (NUREG-1557).

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

for inaccessible areas 

of plants located in 

moderate to severe 

weathering conditions

T-01 III.A1-6

III.A2-6

III.A3-6

III.A5-6

III.A7-5

III.A8-5

III.A9-5

27 BWR/ 

PWR

All Groups except 

Group 6: accessible 

and inaccessible 

interior/exterior 

concrete 

Cracking due to 

expansion due to 

reaction with 

aggregates

Structures Monitoring Program 

None for inaccessible areas if 

concrete was constructed in 

accordance with the 

recommendations in ACI 

201.2R-77.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

concrete was not 

constructed as stated 

for inaccessible areas

T-03 III.A1-2

III.A2-2

III.A3-2

III.A4-2

III.A5-2

III.A7-1

III.A8-1

III.A9-1

28 BWR/ 

PWR

Groups 1-3, 5-9: All Cracks and 

distortion due to 

increased stress 

levels from 

settlement 

Structures Monitoring Program. 

If a de-watering system is relied 

upon for control of settlement, 

then the licensee is to ensure 

proper functioning of the dewatering system through the 

period of extended operation.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

a de-watering system 

is relied upon

T-08 III.A1-3

III.A2-3

III.A3-3

III.A5-3

III.A6-4

III.A7-2

III.A8-2

III.A9-2

29 BWR/ 

PWR

Groups 1-3, 5-9: 

foundation 

Reduction in 

foundation strength, 

cracking, differential 

settlement due to 

erosion of porous 

concrete 

subfoundation

Structures Monitoring Program. 

If a de-watering system is relied 

upon for control of settlement, 

then the licensee is to ensure 

proper functioning of the dewatering system through the 

period of extended operation.

Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program or 

a de-watering system 

is relied upon

T-09 III.A1-8

III.A2-8

III.A3-8

III.A5-8

III.A6-8

III.A7-7

III.A8-7

III.A9-7
NUREG-1801 Vol. 1, Rev. 1 84 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

30 BWR/ 

PWR

Group 4: Radial 

beam seats in BWR 

drywell; RPV support 

shoes for PWR with 

nozzle supports; 

Steam generator 

supports 

Lock-up due to 

wear 

ISI (IWF) or Structures 

Monitoring Program

Yes, if not within the 

scope of ISI or 

structures monitoring 

program

T-13 III.A4-6

31 BWR/ 

PWR

Groups 1-3, 5, 7-9: 

below-grade concrete 

components, such as 

exterior walls below 

grade and foundation 

Increase in porosity 

and permeability, 

cracking, loss of 

material (spalling, 

scaling)/ aggressive 

chemical attack;

Cracking, loss of 

bond, and loss of 

material (spalling, 

scaling)/ corrosion 

of embedded steel

Structures monitoring Program; 

Examination of representative 

samples of below-grade 

concrete, and periodic 

monitoring of groundwater, if the 

environment is non-aggressive. 

A plant specific program is to be 

evaluated if environment is 

aggressive.

Yes, plant-specific, if 

environment is 

aggressive

T-05

T-07

III.A1-4

III.A2-4

III.A3-4

III.A5-4

III.A7-3

III.A8-3

III.A9-3

III.A1-5

III.A2-5

III.A3-5

III.A5-5

III.A7-4

III.A8-4

III.A9-4

32 BWR/ 

PWR

Groups 1-3, 5, 7-9: 

exterior above and 

below grade 

reinforced concrete 

foundations

Increase in porosity 

and permeability, 

loss of strength due 

to leaching of 

calcium hydroxide. 

Structures Monitoring Program 

for accessible areas. None for 

inaccessible areas if concrete 

was constructed in accordance 

with the recommendations in ACI 

201.2R-77.

Yes, if concrete was 

not constructed as 

stated for inaccessible 

areas

T-02 III.A1-7

III.A2-7

III.A3-7

III.A5-7

III.A7-6

III.A8-6

III.A9-6
September 2005 85 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

33 BWR/ 

PWR

Groups 1-5: concrete Reduction of 

strength and 

modulus due to 

elevated 

temperature 

Plant-specific Yes, plant-specific if 

temperature limits are 

exceeded

T-10 III.A1-1

III.A2-1

III.A3-1

III.A4-1

III.A5-1

34 BWR/ 

PWR

Group 6: 

Concrete;

all

Cracking, loss of 

bond, loss of 

material due to 

corrosion of 

embedded steel; 

increase in porosity 

and permeability, 

cracking, loss of 

material due to 

aggressive 

chemical attack 

Inspection of Water-Control 

Structures Assoc with Nuclear 

Power Plants and for 

inaccessible concrete, exam of 

rep. samples of below-grade 

concrete, and periodic 

monitoring of groundwater, if 

environment is non-aggressive. 

Plant specific if environment is 

aggressive.

Yes, plant-specific if 

environment is 

aggressive

T-18

T-19

III.A6-1

III.A6-3

35 BWR/ 

PWR

Group 6: exterior 

above and below 

grade concrete 

foundation 

Loss of material 

(spalling, scaling) 

and cracking due to 

freeze-thaw

Inspection of Water-Control 

Structures Associated with 

Nuclear Power Plants.

Evaluation is needed for plants 

that are located in moderate to 

severe weathering conditions 

(weathering index >100 dayinch/yr) (NUREG-1557).

Yes, for inaccessible 

areas of plants located 

in moderate to severe 

weathering conditions

T-15 III.A6-5
NUREG-1801 Vol. 1, Rev. 1 86 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

36 BWR/ 

PWR

Group 6: all 

accessible/ 

inaccessible 

reinforced concrete

Cracking due to 

expansion/ reaction 

with aggregates

Accessible areas: Inspection of 

Water-Control Structures 

Associated with Nuclear Power 

Plants. 

None for inaccessible areas if 

concrete was constructed in 

accordance with the 

recommendations in ACI 

201.2R-77.

 Yes, if concrete was 

not constructed as 

stated for inaccessible 

areas

T-17 III.A6-2

37 BWR/ 

PWR

Group 6: exterior 

above and below 

grade reinforced 

concrete foundation 

interior slab 

Increase in porosity 

and permeability, 

loss of strength due 

to leaching of 

calcium hydroxide

For accessible areas, Inspection 

of Water-Control Structures 

Associated with Nuclear Power 

Plants. None for inaccessible 

areas if concrete was 

constructed in accordance with 

the recommendations in ACI 

201.2R-77.

 Yes, if concrete was 

not constructed as 

stated for inaccessible 

areas

T-16 III.A6-6

38 BWR/ 

PWR

Groups 7, 8: Tank 

liners 

Cracking due to 

stress corrosion 

cracking; loss of 

material due to 

pitting and crevice 

corrosion

Plant-specific Yes, plant specific T-23 III.A7-11

III.A8-9

39 BWR/ 

PWR

Support members; 

welds; bolted 

connections; support 

anchorage to building 

structure

Loss of material due 

to general and 

pitting corrosion

Structures Monitoring Program Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-30 III.B2-10

III.B3-7

III.B4-10

III.B5-7
September 2005 87 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

40 BWR/ 

PWR

Building concrete at 

locations of 

expansion and 

grouted anchors; 

grout pads for 

support base plates

Reduction in 

concrete anchor 

capacity due to 

local concrete 

degradation/ 

service-induced 

cracking or other 

concrete aging 

mechanisms

Structures Monitoring Program Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-29 III.B1.1-1

III.B1.2-1

III.B1.3-1

III.B2-1

III.B3-1

III.B4-1

III.B5-1

41 BWR/ 

PWR

Vibration isolation 

elements

Reduction or loss of 

isolation function/ 

radiation hardening, 

temperature, 

humidity, sustained 

vibratory loading

Structures Monitoring Program Yes, if not within the 

scope of the 

applicant’s structures 

monitoring program

T-31 III.B4-12

42 BWR/ 

PWR

Groups B1.1, B1.2, 

and B1.3: support 

members: anchor 

bolts, welds

Cumulative fatigue 

damage (CLB 

fatigue analysis 

exists) 

TLAA evaluated in accordance 

with 10 CFR 54.21(c) 

Yes, TLAA T-26 III.B1.1-12

III.B1.2-9

III.B1.3-9

43 BWR/ 

PWR

Groups 1-3, 5, 6: all 

masonry block walls 

Cracking due to 

restraint shrinkage, 

creep, and 

aggressive 

environment 

Masonry Wall Program No T-12 III.A1-11

III.A2-11

III.A3-11

III.A5-11

III.A6-10

44 BWR/ 

PWR

Group 6 elastomer 

seals, gaskets, and 

moisture barriers 

Loss of sealing due 

to deterioration of 

seals, gaskets, and 

moisture barriers 

(caulking, flashing, 

and other sealants) 

Structures Monitoring Program No TP-7 III.A6-12
NUREG-1801 Vol. 1, Rev. 1 88 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

45 BWR/ 

PWR

Group 6: exterior 

above and below 

grade concrete 

foundation; interior 

slab

Loss of material due 

to abrasion, 

cavitation

Inspection of Water-Control 

Structures Associated with 

Nuclear Power Plants

No T-20 III.A6-7

46 BWR/ 

PWR

Group 5: Fuel pool 

liners 

Cracking due to 

stress corrosion 

cracking; loss of 

material due to 

pitting and crevice 

corrosion

Water Chemistry and Monitoring 

of spent fuel pool water level and 

level of fluid in the leak chase 

channel.

No T-14 III.A5-13

47 BWR/ 

PWR

Group 6: all metal 

structural members 

Loss of material due 

to general (steel 

only), pitting and 

crevice corrosion

Inspection of Water-Control 

Structures Associated with 

Nuclear Power Plants. If 

protective coatings are relied 

upon to manage aging, 

protective coating monitoring 

and maintenance provisions 

should be included. 

No T-21 III.A6-11

48 BWR/ 

PWR

Group 6: earthen 

water control 

structures - dams, 

embankments, 

reservoirs, channels, 

canals, and ponds

Loss of material, 

loss of form due to 

erosion, settlement, 

sedimentation, frost 

action, waves, 

currents, surface 

runoff, seepage

Inspection of Water-Control 

Structures Associated with 

Nuclear Power Plants

No T-22 III.A6-9

49 BWR Support members; 

welds; bolted 

connections; support 

anchorage to building 

structure

Loss of material/ 

general, pitting, and 

crevice corrosion

Water Chemistry and ISI (IWF) No TP-10 III.B1.1-11
September 2005 89 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

50 BWR/ 

PWR

Groups B2, and B4: 

galvanized steel, 

aluminum, stainless 

steel support 

members; welds; 

bolted connections; 

support anchorage to 

building structure

Loss of material due 

to pitting and 

crevice corrosion

Structures Monitoring Program No TP-6 III.B2-7

III.B4-7

51 BWR/ 

PWR

Group B1.1: high 

strength low-alloy 

bolts 

Cracking due to 

stress corrosion 

cracking; loss of 

material due to 

general corrosion

Bolting Integrity No T-27

TP-9

III.B1.1-3

III.B1.1-4

52 BWR/ 

PWR

Groups B2, and B4: 

sliding support 

bearings and sliding 

support surfaces

Loss of mechanical 

function due to 

corrosion, distortion, 

dirt, overload, 

fatigue due to 

vibratory and cyclic 

thermal loads

Structures Monitoring Program No TP-1

TP-2

III.B2-2

III.B4-2

III.B2-3

III.B4-3

53 BWR/ 

PWR

Groups B1.1, B1.2, 

and B1.3: support 

members: welds; 

bolted connections; 

support anchorage to 

building structure

Loss of material due 

to general and 

pitting corrosion

ISI (IWF) No T-24 III.B1.1-13

III.B1.2-10

III.B1.3-10
NUREG-1801 Vol. 1, Rev. 1 90 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

54 BWR/ 

PWR

Groups B1.1, B1.2, 

and B1.3: Constant 

and variable load 

spring hangers; 

guides; stops

Loss of mechanical 

function due to 

corrosion, distortion, 

dirt, overload, 

fatigue due to 

vibratory and cyclic 

thermal loads

ISI (IWF) No T-28 III.B1.1-2

III.B1.2-2

III.B1.3-2

55 PWR Steel, galvanized 

steel, and aluminum 

support members; 

welds; bolted 

connections; support 

anchorage to building 

structure

Loss of material due 

to boric acid 

corrosion 

Boric Acid Corrosion No T-25

TP-3

III.B1.1-14

III.B1.2-11

III.B2-11

III.B3-8

III.B4-11

III.B5-8

III.B1.1-8

III.B1.2-6

III.B1.3-6

III.B2-6

III.B3-4

III.B4-6

III.B5-4

56 BWR/ 

PWR

Groups B1.1, B1.2, 

and B1.3: Sliding 

surfaces

Loss of mechanical 

function due to 

corrosion, distortion, 

dirt, overload, 

fatigue due to 

vibratory and cyclic 

thermal loads

ISI (IWF) No T-32 III.B1.1-5

III.B1.2-3

III.B1.3-3
September 2005 91 NUREG-1801 Vol. 1, Rev. 1

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

57 BWR/ 

PWR

Groups B1.1, B1.2, 

and B1.3: Vibration 

isolation elements

Reduction or loss of 

isolation function/ 

radiation hardening, 

temperature, 

humidity, sustained 

vibratory loading

ISI (IWF) No T-33 III.B1.1-15

III.B1.2-12

III.B1.3-11

58 BWR/ 

PWR

Galvanized steel and 

aluminum support 

members; welds; 

bolted connections; 

support anchorage to 

building structure 

exposed to air -

indoor uncontrolled

None None NA - No AEM or AMP TP-8

TP-11

III.B1.1-6

III.B1.2-4

III.B1.3-4

III.B2-4

III.B3-2

III.B4-4

III.B5-2

III.B1.1-7

III.B1.2-5

III.B1.3-5

III.B2-5

III.B3-3

III.B4-5

III.B5-3
NUREG-1801 Vol. 1, Rev. 1 92 September 2005

Table 5. Summary of Aging Management Programs for Structures and Component Supports 

Evaluated in Chapters II and III of the GALL Report

ID Type Component Aging 

Effect/Mechanism Aging Management Programs Further Evaluation Recommended

Related

Generic

Item

Unique

Item

59 BWR/ 

PWR

Stainless steel 

support members; 

welds; bolted 

connections; support 

anchorage to building 

structure

None None NA - No AEM or AMP TP-4

TP-5

III.B1.1-10

III.B1.2-8

III.B1.3-8

III.B2-9

III.B3-6

III.B4-9

III.B5-6

III.B1.1-9

III.B1.2-7

III.B1.3-7

III.B2-8

III.B3-5

III.B4-8

III.B5-5
September 2005 93 NUREG-1801 Vol. 1, Rev. 1

Table 6. Summary of Aging Management Programs for the Electrical Components

Evaluated in Chapter VI of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

1 BWR/ 

PWR

Electrical equipment 

subject to 10 CFR 50.49 

environmental 

qualification (EQ) 

requirements

Degradation due to various 

aging mechanisms 

Environmental 

qualification of 

electric components 

Yes, TLAA L-05 VI.B-1

2 BWR/ 

PWR

Electrical cables, 

connections and fuse 

holders (insulation) not 

subject to 10 CFR 50.49 

EQ requirements 

Reduced insulation resistance 

and electrical failure due to 

various physical, thermal, 

radiolytic, photolytic, and 

chemical mechanisms

Electrical cables and 

connections not 

subject to 10 CFR 

50.49 EQ 

requirements 

No L-01

LP-03

VI.A-2

VI.A-6

3 BWR/ 

PWR

Conductor insulation for 

electrical cables and 

connections used in 

instrumentation circuits 

not subject to 10 CFR 

50.49 EQ requirements 

that are sensitive to 

reduction in conductor 

insulation resistance (IR) 

Reduced insulation resistance 

and electrical failure due to 

various physical, thermal, 

radiolytic, photolytic, and 

chemical mechanisms

Electrical Cables And 

Connections Used In 

Instrumentation 

Circuits Not Subject 

To 10 CFR 50.49 EQ 

Requirements 

No L-02 VI.A-3

4 BWR/ 

PWR

Conductor insulation for 

inaccessible medium 

voltage (2 kV to 35 kV) 

cables (e.g., installed in 

conduit or direct buried) 

not subject to 10 CFR 

50.49 EQ requirements 

Localized damage and 

breakdown of insulation 

leading to electrical failure 

due to moisture intrusion, 

water trees 

Inaccessible medium 

voltage cables not 

subject to 10 CFR 

50.49 EQ 

requirements 

No L-03 VI.A-4
NUREG-1801 Vol. 1, Rev. 1 94 September 2005

Table 6. Summary of Aging Management Programs for the Electrical Components

Evaluated in Chapter VI of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

5 PWR Connector contacts for 

electrical connectors 

exposed to borated 

water leakage

Corrosion of connector 

contact surfaces due to 

intrusion of borated water 

Boric Acid Corrosion No L-04 VI.A-5

6 BWR/ 

PWR

Fuse Holders (Not Part 

of a Larger Assembly): 

Fuse holders – metallic 

clamp 

Fatigue due to ohmic heating, 

thermal cycling, electrical 

transients, frequent 

manipulation, vibration, 

chemical contamination, 

corrosion, and oxidation 

Fuse holders No LP-01 VI.A-8

7 BWR/ 

PWR

Metal enclosed bus -

Bus/connections 

Loosening of bolted 

connections due to thermal 

cycling and ohmic heating 

Metal Enclosed Bus No LP-04 VI.A-11

8 BWR/ 

PWR

Metal enclosed bus –

Insulation/insulators 

Reduced insulation resistance 

and electrical failure due to 

various physical, thermal, 

radiolytic, photolytic, and 

chemical mechanisms

Metal Enclosed Bus No LP-05 VI.A-14

9 BWR/ 

PWR

Metal enclosed bus –

Enclosure assemblies 

Loss of material due to 

general corrosion 

Structures Monitoring 

Program 

No LP-06 VI.A-13

10 BWR/ 

PWR

Metal enclosed bus –

Enclosure assemblies 

Hardening and loss of 

strength due to elastomers 

degradation 

Structures Monitoring 

Program 

No LP-10 VI.A-12
September 2005 95 NUREG-1801 Vol. 1, Rev. 1

Table 6. Summary of Aging Management Programs for the Electrical Components

Evaluated in Chapter VI of the GALL Report

ID Type Component Aging Effect/Mechanism Aging Management 

Programs

Further 

Evaluation 

Recommended

Related

Generic

Item

Unique

Item

11 BWR/ 

PWR

High voltage insulators Degradation of insulation 

quality due to presence of any 

salt deposits and surface 

contamination; Loss of 

material caused by 

mechanical wear due to wind 

blowing on transmission 

conductors 

Plant specific Yes, plant 

specific

LP-07

LP-11

VI.A-9

VI.A-10

12 BWR/ 

PWR

Transmission conductors 

and connections; 

switchyard bus and 

connections 

Loss of material due to wind 

induced abrasion and fatigue; 

loss of conductor strength due 

to corrosion; increased 

resistance of connection due 

to oxidation or loss of preload

 Plant specific Yes, plant 

specific

LP-08

LP-09

VI.A-16

VI.A-15

13 BWR/ 

PWR

Cable Connections –

Metallic parts 

Loosening of bolted 

connections due to thermal 

cycling, ohmic heating, 

electrical transients, vibration, 

chemical contamination, 

corrosion, and oxidation 

Electrical cable 

connections not 

subject to 10 CFR 

50.49 environmental 

qualification 

requirements 

No LP-12 VI.A-1

14 BWR/ 

PWR

Fuse Holders (Not Part 

of a Larger Assembly) 

Insulation material 

None None NA - No AEM or 

AMP

LP-02 VI.A-7
NUREG-1801 Vol. 1, Rev. 1 96 September 2005

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September 2005 A-1 NUREG-1801 Vol. 1, Rev. 1

APPENDIX

LISTING OF PLANT SYSTEMS 

EVALUATED IN THE GALL REPORT

 (VOLUME 2)
NUREG-1801 Vol. 1, Rev. 1 A-2 September 2005

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2 September 2005

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September 2005 A-3 NUREG-1801 Vol. 1, Rev. 1

Plant Systems 

Evaluated in the GALL Report (Volume 2)

Type System

Section in GALL 

(Vol. 2)

BWR Automatic depressurization system V.D2

BWR Containment structures:

 Mark I steel containments

 Mark II concrete and steel containments

 Mark III concrete and steel containments

Common components

II.B1

II.B2 

II.B3 

II.B4

BWR High-pressure coolant injection V.D2

BWR High-pressure core spray V.D2

BWR Low-pressure coolant injection and residual heat removal V.D2

BWR Low-pressure core spray V.D2

BWR Reactor building III.A1

BWR Reactor building with steel superstructure III.A2

BWR Reactor coolant pressure boundary IV.C1

BWR Reactor coolant system connected systems (up to and 

including the second isolation valve): 

 Automatic depressurization system

 Feedwater 

 High-pressure core spray

 High-pressure coolant injection

 Isolation condenser

 Low-pressure coolant injection

 Low-pressure core spray

 Main steam 

 Reactor core isolation cooling

 Reactor water cleanup

 Recirculation system

 Residual heat removal

 Shutdown cooling

 Standby liquid control

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

IV.C1

BWR Reactor core isolation cooling V.D2

BWR Reactor vessel IV.A1

BWR Reactor vessel internals IV.B1

BWR Reactor water cleanup system VII.E3

BWR Shutdown cooling system (older plants) VII.E4

BWR Standby gas treatment system V.B

BWR Standby liquid control system VII.E2

BWR Suppression pool cleanup system VII.A5

BWR Unit vent stack III.A9

BWR/ PWR Auxiliary and radwaste area ventilation system VII.F2

BWR/ PWR Auxiliary building, diesel generator building, radwaste 

building, turbine building, switchgear room, auxiliary 

feedwater pump house, and utility/piping tunnels

III.A3

BWR/ PWR Carbon steel components V.E, VII.I, VIII.H

BWR/ PWR Closed-cycle cooling water system (reactor auxiliary cooling 

water) 

VII.C2
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4 September 2005

Plant Systems

Evaluated in the GALL Report (Volume 2) (continued)

Type System

Section in GALL 

(Vol. 2)

BWR/ PWR Component supports III.B

BWR/ PWR Compressed air system VII.D

BWR/ PWR Concrete tanks III.A7

BWR/ PWR Condensate system VIII.E

BWR/ PWR Containment internal structures, excluding refueling canal III.A4

BWR/ PWR Containment isolation components (containment isolation 

valves for in-scope systems are addressed in chapters IV, 

VII, and VIII)

V.C

BWR/ PWR Control room/building III.A1

BWR/ PWR Control room area ventilation system VII.F1

BWR/ PWR Demineralized water makeup Not in scope of 

10 CFR 50.54

BWR/ PWR Diesel fuel oil system VII.H1

BWR/ PWR Diesel generator building ventilation system VII.F4

BWR/ PWR Electrical components VI.A, B

BWR/ PWR Emergency diesel generator system VII.H2

BWR/ PWR Extraction steam system VIII.C

BWR/ PWR Feedwater system VIII.D2, D1

BWR/ PWR Fire protection VII.G

BWR/ PWR Fuel storage facility and refueling canal III.A5

BWR/ PWR Heating and ventilation systems VII.F1, F2, F3, F4

BWR/ PWR Main steam system VIII.B2, B1

BWR/ PWR New and spent fuel storage VII.A1, A2

BWR/ PWR Open-cycle cooling water system (service water system) VII.C1

BWR/ PWR Overhead heavy load and light load (related to refueling) 

handling systems

VII.B

BWR/ PWR Potable and sanitary water Not in scope of 

10 CFR 50.54

BWR/ PWR Primary containment heating and ventilation system VII.F3

BWR/ PWR Refueling canal III.A5

BWR/ PWR Spent fuel pool cooling and cleanup VII.A3, A4

BWR/ PWR Steam turbine system VIII.A

BWR/ PWR Steel tanks III.A8

BWR/ PWR Ultimate heat sink VII.C3

BWR/ PWR Water-control structures (e.g., intake structure, cooling tower, 

and spray pond)

III.A6

PWR Accumulators V.D1

PWR Auxiliary feedwater system VIII.G

PWR Chemical and volume control system VII.E1

PWR Combustible gas control (containment H2 control) V.E1

PWR Containment spray system V.A

PWR Containments:

 Concrete containments

 Steel containments

 Common components 

II.A1 

II.A2

II.A3

PWR Coolant storage/refueling water system V.D1
September 2005 A-5 NUREG-1801 Vol. 1, Rev. 1

Plant Systems

Evaluated in the GALL Report (Volume 2) (continued)

Type System

Section in GALL 

(Vol. 2)

PWR Core flood system (see accumulators or safety injection 

tanks)

V.D1

PWR High-pressure safety injection V.D1

PWR Lines to chemical and volume control system V.D1

PWR Low-pressure safety injection V.D1

PWR Shield building III.A1

PWR Reactor coolant system and connected lines (up to and 

including the second isolation valve):

 Chemical and volume control system 

 Core flood system 

 Drains and instrumentation lines

 High-pressure injection system

 Low-pressure injection

 Residual heat removal or shutdown cooling

 Safety injection 

 Sampling system

IV.C2

IV.C2

IV.C2

IV.C2

IV.C2

IV.C2

IV.C2

IV.C2

PWR Reactor coolant system, pressurizer, pressurizer relief tank, 

and other Class 1 components

IV.C2 

PWR Reactor vessel IV.A2

PWR Reactor vessel internals IV.B2, B3, B4

PWR Residual heat removal or shutdown cooling V.D1

PWR Safety injection tanks V.D1

PWR Steam generator blowdown system VIII.F

PWR Steam generators IV.D1, D2

 
NUREG-1801 Vol. 1, Rev. 1 A-6 September 2005

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6 September 2005

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