NUREG-1801, Vol. 1

Generic Aging Lessons 

Learned (GALL) Report 

Summary 

U.S. Nuclear Regulatory Commission 

Office of Nuclear Reactor Regulation 

Washington, DC 20555-0001
NUREG-1801, Vol. 1

Generic Aging Lessons

Generic Aging Lessons 

Learned (GALL) Report 

Summary

Manuscript Completed: April 2001 

Date Published: July 2001 

Division of Regulatory Improvement Programs 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Commission 

Washington, DC 20555-0001
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I
Abstract

The Generic Aging Lessons Learned (GALL) report contains the staff's generic evaluation of the 

existing plant programs and documents the technical basis for determining where existing 

programs are adequate without modification and where existing programs should be augmented 

for the extended period of operation. The evaluation results documented in the GALL report 

indicate that many of the existing programs are adequate to manage the aging effects for 

particular structures or components for license renewal without change. The GALL report also 

contains recommendations on specific areas for which existing programs should be augmented 

for license renewal. 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 and that no further staff review is required. The focus 

of the staff review is on the augmented existing programs for license renewal. The incorporation 

of the GALL report information into NUREG-1800, "Standard Review Plan for Review of License 

Renewal Applications for Nuclear Power Plants," as directed by the Commission, should 

improve the efficiency of the license renewal process.

April 2001 iii NUREG-1801
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NUREG-1801 iv April 2001
TABLE OF CONTENTS 

Page 

A B S T R A C T .......................................................................................................................... iii 

LIST OF CONTRIBUTORS - 1999-2001 ............................................................................. vii 

A BBR EVIATIO N S ............................................................................................................... A 

IN T RO D U CT IO N ................................................................................................................. 1 

GALL REPORT EVALUATION PROCESS ......................................................................... 1 

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

SUMMARY AND RECOMMENDATIONS ............................................................................ 4 

APPENDIX: PLANT SYSTEMS EVALUATED IN THE GALL REPORT (VOLUME 2) 

LISTS OF ITEM NUMBERS IN THE GALL REPORT (VOLUME 2) ................ A-i 

LIST OF TABLES 

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

System Evaluated in Chapter IV of the GALL Report ............................................. 5 

Table 2. Summary of Aging Management Programs for the Engineered 

Safety Features Evaluated in Chapter V of the GALL Report ................................. 16 

Table 3. Summary of Aging Management Programs for the Auxiliary 

Systems Evaluated in Chapter VII of the GALL Report .......................................... 19 

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

Conversion System Evaluated in Chapter VIII of the GALL Report ........................ 25 

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

Component Supports Evaluated in Chapters II and III of 

the G A LL Report .................................................................................................... 28 

Table 6. Summary of Aging Management Programs for the Electrical 

Components Evaluated in Chapter VI of the GALL Report ..................................... 35 

April 2001 v NUREG-1801
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NUREG-1801 April 2001 vi
LIST OF CONTRIBUTORS - 1999-2001

License Renewal and Standardization Branch 

Office of Nuclear Reactor Regulation 

P. T. Kuo Section Chief 

S. Lee Team Leader

R. Anand 

T. Bloomer 

S. Chey 

M. Comar 

J. Dozier 

R. Franovich 

S. Green 

S. Hoffman 

P. Kang 

E. Kleeh 

S. Koenick 

W. Liu 

S. K. Mitra 

K. Rico 

D. Solorio 

J. Strnisha 

0. Tabatabai-Yazdi 

H. Wang

Technical Support 

Technical Coordination (on rotation) 

Clerical Support 

Technical Support (on rotation) 

Technical Coordination 

Technical Coordination (on rotation) 

Clerical Support 

Technical Support 

Technical Coordination 

Technical Coordination (on rotation) 

Technical Support 

Technical Support 

Technical Coordination 

Technical Coordination 

Technical Coordination 

Technical Coordination 

Technical Coordination 

Technical Support

Office of Nuclear Reactor Regulation

H. Ashar 

G. Bagchi 

M. Banic 

C. Berlinger 

C. Carpenter 

P. Y. Chen 

T. Cheng 

S. Coffin 

J. Davis 

D. Dorman 

T. Eaton 

B. Elliot 

J. Fair 

D. Frumkin 

G. Galletti 

G. Georgiev 

C. Gratton 

F. Grubelich 

M. Hartzman 

R. Hermann 

A. Hiser 

C. Holden

Structural Engineering 

Technical Coordination 

Materials Engineering 

Technical Coordination 

Materials Engineering 

Technical Coordination 

Structural Engineering 

Materials Engineering 

Materials Engineering 

Quality Assurance 

Plant Systems Engineering 

Materials Engineering 

Mechanical Engineering 

Plant Systems Engineering 

Quality Assurance 

Materials Engineering 

Plant Systems Engineering 

Mechanical Engineering 

Mechanical Engineering 

Materials Engineering 

Materials Engineering 

Electrical Engineering

April 2001 vii NUREG-1 801
LIST OF CONTRIBUTORS - 1999-2001 (continued)

Office of Nuclear Reactor Regulation (continued)

S. Hou 

N. lqbal 

D. Jeng 

K. Karwoski 

Y. Kim 

W. Koo 

C. Lauron 

A. Lee 

Y. Li 

J. Ma 

K. Manoly 

J. Medoff 

K. Parczewski 

P. Patnaik 

J. Peralta 

J. Rajan 

P. Shemanski 

E. Sullivan 

J. Tatum 

B. Thomas 

E. Weiss 

S. West 

K. Wichman

Materials Engineering 

Plant Systems Engineering 

Structural Engineering 

Materials Engineering 

Structural Engineering 

Materials Engineering 

Materials Engineering 

Structural Engineering 

Mechanical Engineering 

Structural Engineering 

Structural Engineering 

Materials Engineering 

Chemical Engineering 

Material Engineering 

Quality Assurance 

Mechanical Engineering 

Electrical Engineering 

Materials Engineering 

Plant Systems Engineering 

Plant Systems Engineering 

Plant Systems Engineering 

Plant Systems Engineering 

Materials Engineering

Office of Nuclear Regulatory Research

Team Leader

A. Beranek 

J. Boardman 

J. Costello 

M. Dey 

0. Gormley 

H. Graves 

C. Hsu 

D. Jackson 

B. Jones 

M. Kirk 

R. Lloyd 

M. McNeil 

J. Muscara 

H. Ornstein 

S. Pullani 

A. Serkiz 

K. Shaukat 

M. Wegner

Technical Editor 

Reactor Systems Engineering 

Structural Engineering 

Reliability and Risk Analyst 

Mechanical Engineering 

Structural Engineering 

Mechanical Engineering 

Materials Engineering 

Nuclear Engineering 

Materials Engineering 

Reactor Systems Engineering 

Materials Engineering 

Metallurgical Engineering 

Reactor Systems Engineering 

Reactor Systems Engineering 

Mechanical Engineering 

Mechanical Engineering 

Reactor Systems Engineering

NUREG-1801

J. Vora

viii April 2001
LIST OF CONTRIBUTORS - 1999-2001 (continued)

Office of the General Counsel

J. Euchner 

B. Poole 

R. Weisman 

M. Young

Legal Counsel 

Legal Counsel 

Legal Counsel 

Legal Counsel

Argonne National Laboratory

Y. Y. Liu Principal Investigator

K. Brown 

0. Chopra 

D. Diercks 

R. Fabian 

D. Henley 

A. Hull 

L. Kickels 

D. Ma 

J. Robson 

L. Salinas 

K. Schroeder 

R. Seidensticker 

W. Shack 

V. Skonicki 

V. Shah 

B. Shelton 

S. Tam

Technical Editor 

Materials Engineering 

Materials Engineering 

Quality Assurance 

Mechanical Engineering 

Materials Engineering 

Clerical Support 

Mechanical Engineering 

Clerical Support 

Clerical Support 

Clerical Support 

Mechanical Engineering 

Materials Engineering 

Clerical Support 

Materials and Mechanical Engineering 

Reactor and Plant Systems Engineering 

Materials Engineering

Brookhaven National Laboratory

R. Morante 

P. Bezler 

J. Braverman 

G. DeGrassi 

C. Hofmayer 

R. Lofaro 

S. Shteyngart 

S. Signorelli 

M. Subudhi 

M. Villaran 

J. Xu

Principal Investigator 

Mechanical Engineering 

Containment Structures 

Mechanical Engineering 

Structural Engineering 

Electrical Components 

Clerical Support 

Clerical Support 

Mechanical Engineering 

Electrical Engineering 

Structural Engineering

April 2001 ix NUREG-1801
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NUREG-1801 X April 2001
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 

IS1 inservice inspection 

LER licensee event report 

LG lower grid 

LP low pressure 

LPCI low-pressure coolant injection 

LPCS low-pressure core spray

April 2001 xi NUREG-1801
ABBREVIATIONS (continued)

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 

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 xii April 2001
INTRODUCTION

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 in 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. 

GALL REPORT EVALUATION PROCESS 

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, licensee event 

reports (LERs), information notices, generic letters, and 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 issued the draft improved license 

renewal guidance documents, including the GALL report, for public comments in the Federal 

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

comments is documented in NUREG-1739.

April 2001 1 NUREG-1801
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 the review of the following 10 

program attributes (or elements):

Element Description

1. Scope of the program 

2. Preventive actions 

3. Parameters monitored or 

inspected 

4. Detection of aging effects 

5. Monitoring and trending 

6. Acceptance criteria 

7. Corrective actions 

8. Confirmation process 

9. Administrative controls 

10. Operating experience

The scope of the program should include the specific structures 

and components subject to an aging management review. 

Preventive actions should mitigate or prevent the applicable 

aging effects. 

Parameters monitored or inspected should be linked to the 

effects of aging on the intended functions of the particular 

structure and component. 

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. 

Monitoring and trending should provide for prediction of the 

extent of the effects of aging and timely corrective or mitigative actions. 

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. 

Corrective actions, including root cause determination and 

prevention of recurrence, should be timely. 

The confirmation process should ensure that preventive actions 

are adequate and appropriate corrective actions have been 

completed and are effective. 

Administrative controls should provide a formal review and 

approval process. 

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.

NUREG-1801 April 2001 2
If, on the basis of its evaluation, the staff determines 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 staff evaluation is recommended for license 

renewal. Otherwise, the entry would recommend areas in which the staff should focus its 

review. The Commission's regulations in 10 CFR 54.21 (c) require an evaluation of time-limited 

aging analyses (TLAAs). Examples of TLAAs are applicant analyses of metal fatigue and 

environmental qualification (EQ) of electric equipment. The GALL report in general refers the 

reader to the SRP-LR for guidance on how TLAAs should be evaluated. However, 10 CFR 

54.21 (c)(1)(iii) allows a TLAA-associated aging effect to be managed by an aging management 

program. The GALL report, Volume 2, Chapter X, provides the staff's evaluation of several 

TLAAs under 10 CFR 54.21 (c)(1)(iii) based on the initial license renewal reviews. 

Chapter Xl 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 Xl 

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 and that 

no further staff review is required, as described in the next paragraph. If the material presented 

in the GALL report is applicable to the applicant's facility, the staff should find the applicant's 

reference to the GALL report acceptable. In making this determination, the staff should consider 

whether the applicant has identified specific programs described and evaluated in the GALL 

report. The staff, however, should not conduct a re-review of the substance of the matters 

described in the GALL report. Rather, the staff should ensure that the applicant verifies that the 

approvals set forth in the GALL report for generic programs apply to the applicant's programs. 

The focus of the staff review should be on augmented programs for license renewal. The staff 

should also review information that is not addressed in the GALL report or is otherwise different 

from that 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 and are documented on-site in an auditable form. 

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

April 2001 3 NUREG-1801
not mean that this particular structure or component is not within the scope of license renewal 

for any plants. 

SUMMARY AND RECOMMENDATIONS 

The GALL report contains an evaluation of a large number of structures and components. The 

evaluation results documented in the GALL report indicate that many of the generic existing 

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 for license renewal and 

documents the technical basis for each such determination. 

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

review. These tables are the same as Tables 3.1-1 to 3.6-1, respectively, in the SRP-LR, except 

for an additional sixth column in Tables 1 to 6 that identifies the specific item numbers assigned 

to each structure and/or component (i.e., each row in the section tables contained in Volume 2 

of the GALL report). Descriptions of the specific item numbers used in the GALL report, Volume 2, Chapters II through VIII, are given in the Appendix of Volume 1. A locator for the 

plant systems evaluated in Volume 2 is also provided in the Appendix of Volume 1. The specific item number and associated aging effect serve as a pointer to the technical evaluation for the 

specific structure and component addressed in Volume 2 (Tabulation of Results). 

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.

NUREG-1801 4 April 2001
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report

Aging Further Item 

Aging Effect! Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL

Reactor coolant 

pressure 

boundary 

components

Cumulative 

fatigue damage

TLAA, 

evaluated in 

accordance 

with 10 CFR 

54.21 (c)

NUREG-1 801

BWR/ 

PWR

Yes, TLAA IV.A1 .1-b, 

IV.A1.2-a, 

IV.A1.2-b, 

IV.A1.3-a, 

IV.A1.3-d, 

IV.A1.4-b, 

IV.A1.5-b, 

IV.A1.6-a, 

IV.A1.7-a, 

IV.A2.1-b, 

IV.A2.1 -e, 

IV.A2.2-c, 

IV.A2.3-c, 

IV.A2.4-a, 

IV.A2.5-d, 

IV.A2.8-a, 

IV.B1 .1 -c, 

IV.B1 .2-b, 

IV.B1 .3-b, 

IV.B1 .4-b, 

IV.B1.5-b, 

IV.B1 .6-b, 

IV.B2.1-c, 

IV.B2.1-h, 

IV.B2.1-m, 

IV.B2.2-c, 

IV.B2.2-f, 

IV.1B2.3-d, 

IV.B2.4-g, 

IV.B2.5-d, 

IV.B2.5-j, 

IV.B2.5-p, 

IV.1B3.2-f, 

IV.B3.4-d, 

IV.B3.5-g, 

IV.B4.1 -d, 

IV.B4.2-d, 

IV.B4.3-f, 

IV.B4.4-e, 

IV.B4.5-f, 

IV.1B4.6-f, 

IV.C1 .1-b, 

IV.C1 .1-d, 

IV.C1 .1-e, 

IV.C1.1-h, 

IV.C1.2-a, 

IV.C1.2-f, 

IV.C1.3-d,

April 2001 5
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Reactor coolant Cumulative TLAA, Yes, TLAA IV.C1.3-g, PWR pressure fatigue damage evaluated in IV.C2.1 -a, 

boundary accordance with IV.C2.1 -b, 

components 10 CFR IV.C2.2-a, 

54.21 (c) IV.C2.2-b, 

IV.C2.2-c, 

IV.C2.3-a, 

IV.C2.3-d, 

IV.C2.4-a, 

IV.C2.4-d, 

IV.C2.5-a, 

IV.C2.5-d, 

IV.C2.5-e, 

IV.C2.5-f, 

IV.C2.5-q, 

IV.C2.5-t, 

IV.C2.5-w, 

IV.C2.6-a, 

IV.D1 .1-a, 

IV.D1 .1-b, 

IV.D1.1-h, 

IV.D1.2-d, 

IV.D2.1-c, 

IV.D2.1 -g, 

IV.D2.2-e. 

PWR Steam Loss of material Inservice Yes, detection of IV.D1.1-c, 

generator shell due to pitting and inspection; aging effects is to IV.D2.1-e. 

assembly crevice corrosion water chemistry be further 

evaluated 

BWR Isolation Loss of material Inservice Yes, plant specific IV.C1.4-b. 

condenser due to general, inspection; 

pitting, and water chemistry 

crevice corrosion 

BWR/ Pressure vessel Loss of fracture TLAA, Yes, TLAA IV.A1.2-c, 

PWR ferritic materials toughness due to evaluated in IV.A1.3-e, 

that have a neutron irradiation accordance with IV.A2.3-a, 

neutron fluence embrittlement Appendix G of IV.A2.5-a. 

greater than 10 CFR 50 and 

1017 n/cm2 RG 1.99 

(E>1 MeV) 

BWR/ Reactor vessel Loss of fracture Reactor vessel Yes, plant specific IV.A1.2-d, 

PWR beltline shell toughness due to surveillance IV.A2.3-b, 

and welds neutron irradiation IV.A2.5-c. 

embrittlement 

PWR Westinghouse Loss of fracture Plant specific Yes, plant specific IV.B2.4-f, 

and Babcock & toughness due to IV.1B4.5-i. 

Wilcox (B&W) neutron irradiation 

baffle/ former embrittlement and 

bolts void swelling

NUREG-1801 6 April 2001
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Small-bore Crack initiation Inservice Yes, parameters IV.C1.1-i, 

PWR reactor coolant and growth due to inspection; monitored/ IV.C2.1 -g, 

system and stress corrosion water chemistry; inspected and IV.C2.2-h. 

connected cracking (SCC), one-time detection of aging 

systems piping intergranular inspection effects are to be 

stress corrosion further evaluated 

cracking (IGSCC), 

and thermal and 

mechanical 

loading 

BWR Jet pump Crack initiation Plant specific Yes, plant specific IV.A1 .1-d, 

sensing line and and growth due to IV.B1I.4-d. 

reactor vessel SCC, IGSCC, or 

flange leak cyclic loading 

detection line 

BWR Isolation Crack initiation Inservice Yes, plant specific IV.C1.4-a. 

condenser and growth due to inspection; 

SCC or cyclic water chemistry 

loading 

PWR Vessel shell Crack growth due TLAA Yes, TLAA IV.A2.5-b. 

to cyclic loading 

PWR Reactor Changes in Plant specific Yes, plant specific IV.B2.1-b, 

internals dimension due to IV.B2.1-f, 

void swelling IV. B2.1 -j, 

IV.B2.2-b, 

IV.B2.2-e, 

IV.B2.3-b, 

IV.1B2.4-b, 

IV.B2.4-d, 

IV.B2.5-b, 

IV.B2.5-f, 

IV.B2.5-1, 

IV.B2.6-b, 

IV.B3.1 -b, 

IV.B3.2-c, 

IV.B3.3-b, 

IV.B3.4-b, 

IV.B3.4-f, 

IV.B3.5-c, 

IV.B4.1 -c, 

IV.B4.2-c, 

IV.B4.3-c, 

IV.1B4.4-c, 

IV.1B4.5-c, 

IV.B4.5-h, 

IV.1B4.6-c, 

IV.B4.7-c, 

IV.1B4.8-b.

April 2001 7 NUREG-1801
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in Type Component Mechanism Programs Recommended GALL 

PWR PWR core Crack initiation Plant specific Yes, plant specific IV.A2.1-f, 

support pads, and growth due to IV.A2.6-a, instrument SCC and/or IV.A2.7-a, tubes (bottom primary water IV.C2.5-j, head stress corrosion IV.D1.1-j, penetrations), cracking IV.D2.1-h, pressurizer (PWSCC) IV.D2.1 -i. 

spray heads, 

and nozzles for 

the steam 

generator 

instruments and 

drains 

PWR Cast austenitic Crack initiation Plant specific Yes, plant specific IV.C2.1 -e, stainless steel and growth due to IV.C2.2-g, (CASS) reactor SCC IV.C2.5-i. 

coolant system 

piping 

PWR Pressurizer Crack initiation Inservice Yes, AMP for IV.C2.5-k, instrumentation and growth due to inspection; PWSCC of IV.C2.5-s. 

penetrations PWSCC water chemistry Inconel 182 weld 

and heater is to be evaluated 

sheaths and 

sleeves made of 

Ni-alloys 

PWR Westinghouse Crack initiation Plant specific Yes, plant specific IV. B2.4-c, and B&W baffle and growth due to IV.B4.5-g. 

former bolts SCC and 

irradiation

assisted stress 

corrosion cracking (IASCC) 

PWR Westinghouse Loss of preload Plant specific Yes, plant specific IV.B2.4-h, and B&W baffle due to stress IV.B4.5-j. former bolts relaxation 

PWR Steam Loss of section Plant specific Yes, plant specific IV.D1.1-e. 

generator thickness due to 

feedwater erosion 

impingement 

plate and 

support

NUREG-1801 8 April 2001
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

PWR (Alloy 600) Crack initiation Steam Yes, effectiveness IV.D1 .2-a, 

Steam and growth due to generator tubing of a proposed IV.D1.2-b, 

generator tubes, PWSCC, outside integrity; water AMP is to be IV.D1.2-c, repair sleeves, diameter stress chemistry evaluated IV.D1 .2-e, and plugs corrosion cracking IV.D1.2-f, 

(ODSCC), and/or IV.D1.2-g, intergranular IV.D1.2-i, 

attack (IGA); or IV.D1 .2-j, loss of material IV.D2.2-a, 

due to wastage IV.D2.2-b, and pitting IV.D2.2-c, 

corrosion, and IV.D2.2-d, 

fretting and wear; IV.D2.2-f, 

or deformation IV.D2.2-g. due to corrosion 

at tube support plate intersections 

PWR Tube support Loss of section Plant specific Yes, plant specific IV.D1.2-h. 

lattice bars thickness due to 

made of carbon flow-accelerated 

steel corrosion (FAC) 

PWR Carbon steel Ligament cracking Plant specific Yes, effectiveness IV.D1.2-k. 

tube support due to corrosion of a proposed plate AMP is to be 

I _ evaluated 

PWR Steam Loss of material Combustion Yes, plant specific IV.D1 .3-a. 

(CE) generator due to flow Engineering feedwater inlet accelerated (CE) steam 

ring and corrosion generator 

supports feedwater ring 

inspection 

BWR/ Reactor vessel Crack initiation Reactor head No IV.A1.1-c, PWR closure studs and growth due to closure studs IV.A2.1-c. 

and stud SCC and/or 

assembly IGSCC 

BWR/ CASS pump Loss of fracture Inservice No IV.C1.2-c, PWR casing and toughness due to inspection IV.C1.3-b, 

valve body thermal aging IV.C2.3-c, 

embrittlement IV.C2.4-c. 

BWR/ CASS piping Loss of fracture Thermal aging No IV.A2.2-d, 

PWR toughness due to embrittlement of IV.C1.1-g, thermal aging CASS IV.C2.1 -f, 

embrittlement IV.C2.2-e, 

IV.C2.5-1. 

BWR/ BWR piping and Wall thinning due Flow No IV.C1.1-a, 

PWR fittings; steam to flow accelerated IV.C1.1-c, 

generator accelerated corrosion IV.C1.3-a, 

components corrosion IV.D1.1 -d, 

IIII IV.D2.1-f.

April 2001 9 NUREG-1801
Table 1. Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of the GALL Report (continued)

1 I T

Component 4 4

Reactor coolant 

pressure 

boundary 

(RCPB) valve 

closure bolting, 

manway and 

holding bolting, 

and closure 

bolting in high

pressure and 

high

temperature 

systems

Aging Effectl 

Mechanism

Loss of material 

due to wear; loss 

of preload due to 

stress relaxation; 

crack initiation 

and growth due to 

cyclic loading 

and/or SCC

Aging 

Management 

Programs

bolting integrity

Further 

Evaluation Recommended

Recomended GALL

No IVoA2.2-e, IV.A2.2-f, 

IV.A2.2-g, 

IV.C1.2-d, 

IV.C1.2-e, 

IV.C1.3-e, 

IV.C1.3-f, 

IV.C2.3-e, 

IV.C2.3-g, 

IV.C2.4-e, 

IV.C2.4-g, 

IV.C2.5-n, 

IV.C2.5-p, 

IV.DI.I-f, 

IV.D1.1-f, 

11I no . 11

Item 

Number in

fi .[L'... no I -1\. BWR Feedwater and Crack initiation Feedwater No IV.A1.3-b, control rod drive and growth due to nozzle; CRD IV.A1.3-c. 

(CRD) return cyclic loading return line 

line nozzles nozzle 

BWR Vessel shell Crack initiation BWR vessel ID No IV.A1.2-e. 

attachment and growth due to attachment 

welds SCC and/or welds; water 

IGSCC chemistry 

BWR Nozzle safe Crack initiation BWR stress No IV.A1.4-a, ends, and growth due to corrosion IV.C1.1-f, recirculation SCC and/or cracking; water IV.C1.2-b, 

pump casing, IGSCC chemistry IV.C1.3-c. 

connected 

systems piping 

and fittings, 

body and 

bonnet of valves 

BWR Penetrations Crack initiation BWR bottom No IV.A1.5-a. 

and growth due to head 

SCC, IGSCC, penetrations; 

and/or cyclic water chemistry I loading

NUREG-1801 April 2001

Type

DAIn/ L11V n/ 

PWR

10
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR Core shroud Crack initiation BWR vessel No IV.B1 .1-a, 

and core plate, and growth due to internals; water IV.B1I.1-b, 

support SCC, IGSCC, chemistry IV.B1 .1-f, 

structure, top and/or IASCC IV.B1 .1-g, 

guide, core IV.B1 .2-a, 

spray lines and IV.B1 .3-a, 

spargers, jet IV.B1 .4-a, 

pump IV.B1 .5-c, 

assemblies, IV.B1 .6-a. 

control rod drive 

housing, and 

nuclear 

instrumentation 

guide tubes 

BWR Core shroud Crack initiation ASME Section No IV.B1 .1 -d, 

and core plate and growth due to XI inservice IV.B1 .1-e. 

access hole SCC, IGSCC, inspection; 

cover (welded and/or IASCC water chemistry 

and mechanical 

covers) 

BWR Jet pump Loss of fracture Thermal aging No IV.B1 .4-c, 

assembly toughness due to and neutron IV.B1I.5-a 

castings and thermal aging and irradiation 

orificed fuel neutron irradiation embrittlement 

support embrittlement 

BWR Unclad top head Loss of material Inservice No IV.A1.1-a. 

and nozzles due to general, inspection; 

pitting, and water chemistry 

crevice corrosion 

PWR CRD nozzle Crack initiation Ni-alloy nozzles No IV.A2.2-a, 

and growth due to and IV.A2.7-b. 

PWSCC penetrations; 

water chemistry 

PWR Reactor vessel Crack initiation Inservice No IV.A2.2-b, 

nozzles safe and growth due to inspection; IV.A2.4-b, 

ends and CRD cyclic loading, water chemistry IV.C2.1-c, 

housing; reactor and/or SCC, and IV.C2.2-f, 

coolant system PWSCC IV.C2.3-b, 

components IV.C2.4-b, 

(except CASS IV.C2.5-c, 

and bolting) IV.C2.5-g, 

IV.C2.5-h, 

IV.C2.5-m, 

IV.C2.5-r, 

IV.C2.6-c.

April 2001 11 NUREG-1 801
Table 1. Summary of Aging Management Programs for the Reactor Coolant System Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

PWR Reactor vessel Loss of fracture Thermal aging No IV.B2.1 -g, internals CASS toughness due to and neutron IV.B2.5-m, 

components thermal aging, irradiation IV.B3.2-e, 

neutron irradiation embrittlement IV.B3.5-f, 

embrittlement, IV.B4.3-d, and void swelling IV.B4.4-g, 

IV.B4.6-e. 

PWR External Loss of material Boric acid No IV.A2.1-a, surfaces of due to boric acid corrosion IV.A2.5-e, carbon steel corrosion IV.A2.8-b, 

components in IV.C2.1 -d, reactor coolant IV.C2.2-d, system IV.C2.3-f, 

pressure IV.C2.4-f, boundary IV.C2.5-b, 

IV.C2.5-o, 

IV.C2.5-u, 

IV.C2.6-b, 

IV.D1.1-g, 

IV.D1 .1-k, 

IV.D2.1 -b, IV.D2.1-j. 

PWR Steam Loss of material Inservice No IV.D2.1-1. 

generator due to erosion inspection 

secondary 

manways and 

handholds 

(carbon steel) 

PWR Reactor Loss of material Inservice No IV.A2.5-f, internals, due to wear inspection IV.B2.1-1, reactor vessel IV.B2.5-o, closure studs, IV.B2.6-c, and core IV.B3.1 -c, support pads IV.B3.2-d, 

IV.B3.3-b, 

IV.B3.5-e, 

IV.B4.2-f, 

IV.B4.4-f, 

IV.B4.6-h. 

PWR Pressurizer Crack initiation Inservice No IV.C2.5-v. 

integral support and growth due to inspection 

cyclic loading PWR Upper and Loss of preload Inservice No IV.B2.1-d, lower internals due to stress inspection; IV.B2.5-i. 

assembly relaxation loose part (Westinghouse) and/or neutron 

noise monitoring

NUREG-1801 April 2001 12
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

PWR Reactor vessel Loss of fracture PWR vessel No IV.B2.3-c, 

internals in fuel toughness due to internals; water IV.B2.4-e, 

zone region neutron irradiation chemistry IV.B2.5-c, 

(except embrittlement and IV.B2.5-g, 

Westinghouse void swelling IV.B2.5-n, 

and B&W baffle IV.B3.3-a, 

former bolts) IV.B3.4-c, 

IV.B3.4-g, 

IV.B3.5-d, 

IV.B4.2-e 

IV.B4.4-d, 

IV.B4.5-d, 

IV.B4.6-d, 

IV.B4.7-d, 

IV.B4.8-c. 

PWR Steam Crack initiation Inservice No IV.D1.1-i, 

generator upper and growth due to inspection; IV.D2.1-a. 

and lower SCC, PWSCC, water chemistry 

heads, and/or IASCC 

tubesheets, and 

primary nozzles 

and safe ends

April 2001 13 NUREG-1801
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued)

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL

vessel internals 

(except 

Westinghouse 

and B&W baffle 

former bolts)

Grack initiation 

and growth due to 

SCC and IASCC

PWR vessel 

internals; water 

chemistry

rVV ri No

i . -CL. PWR Reactor Loss of preload Inservice No IV.B4.3-e, 

internals (B&W due to stress inspection; IV.B4.4-h, 

screws and relaxation loose part IV.B4.5-e, 

bolts) monitoring IV.B4.6-g, 

IV.B4.7-e. PWR Reactor vessel Loss of material Reactor head No IV A2.1-d. 

closure studs due to wear closure studs 

and stud assembly

NUREG-1801

IV.B2.1 -a, 

IV.B2.1 -e, 

IV.B2.1 -i, 

IV.B2.2-a, 

IV.B2.2-d, 

IV.B2.3-a, 

IV.B2.4-a, 

IV.B2.5-a, 

IV.B2.5-e, 

IV.B2.5-k, 

IV.B2.6-a, 

IV.B3.1 -a, 

IV.B3.2-a, 

IV.B3.2-b, 

IV.B3.3-a, 

IV.B3.4-a, 

IV.B3.4-e, 

IV.B3.5-a, 

IV.B3.5-b, 

IV.B4.1-a, 

IV. B4.1 -b, 

IV.B4.2-a, 

IV.B4.2-b, 

IV.B4.3-a, 

IV.B4.3-b, 

IV.B4.4-a, 

IV.B4.4-b, 

IV.B4.5-a, 

IV.B4.5-b, 

IV.B4.6-a, 

IV.B4.6-b, 

IV.B4.7-a, 

IV.B4.7-b, 

IN/ PA 0_,

14 April 2001
Table 1. Summary of Aging Management Programs for the Reactor Coolant System 

Evaluated in Chapter IV of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

PWR Reactor Loss of preload Inservice No IV.B2.1 -k, 

internals due to stress inspection; IV.B2.5-h, 

(Westinghouse relaxation loose part IV.B3.2-g, 

upper and lower monitoring IV.B3.4-h. 

internal 

assemblies, 

CE bolts and tie 

I rods)

April 2001 15 NUREG-1 801
Table 2. Summary of Aging Management Programs for the Engineered Safety 

Features Evaluated in Chapter V of the GALL Report 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Piping, fittings, Cumulative TLAA, Yes, TLAA V.D1.1-c, PWR and valves in fatigue damage evaluated in V.D1.4-a, 

emergency core accordance with V.D2.1 -b. 

cooling system 10 CFR 

54.21(c) 

BWR Piping, fittings, Loss of material Water chemistry Yes, detection of V.D2.1 -a, 

pumps, and due to general and one-time aging effects is to V.D2.2-a, valves in corrosion inspection be further V.D2.3-b. 

emergency core evaluated 

cooling system BWR/ Components in Loss of material Plant specific Yes, plant specific V.A.2-a, PWR containment due to general V.A.5-a, 

spray (PWR corrosion V.B.1-a, only), standby V.B.2-a, 

gas treatment V.C.1-a, system (BWR V.D2.1 -e, only), V.D2.5-a. 

containment 

isolation, and 

emergency core 

cooling systems 

BWR Piping, fittings, Loss of material Water chemistry Yes, detection of V.D2.1 -a, 

pumps, and due to pitting and and one-time aging effects is to V.D2.2-a, valves in crevice corrosion inspection be further V.D2.3-b. 

emergency core evaluated 

cooling system BWR/ Components in Loss of material Plant specific Yes, plant specific V.C.1-a, PWR containment due to pitting and V.C.I-b, 

spray (PWR crevice corrosion V.D1.8-c, only), standby V.D2.1 -e. 

gas treatment 

system (BWR 

only), 

containment 

isolation, and 

emergency core 

cooling systems BWR/ Containment Loss of material Plant specific Yes, plant specific V.C.1-a, PWR isolation valves due to V.C.1-b. 

and associated microbiologically 

piping influenced 

corrosion (MIC) BWR Seals in Changes in Plant specific Yes, plant specific V.B.1-b, standby gas properties due to V.B.2-b. 

treatment elastomer 

-system degradation

NUREG-1801 16 April 2001
Table 2. Summary of Aging Management Programs for the Engineered Safety 

Features Evaluated in Chapter V of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

PWR High-pressure Loss of material Plant specific Yes, plant specific V.D1.2-c. 

safety injection due to erosion 

(charging) pump 

miniflow orifice 

BWR Drywell and Plugging of flow Plant specific Yes, plant specific V.D2.5-b. 

suppression orifice and spray 

chamber spray nozzles by 

system nozzles general corrosion 

and flow orifices products 

BWR/ External surface Loss of material Plant specific Yes, plant specific V.E.1-b. 

PWR of carbon steel due to general 

components corrosion 

BWR/ Piping and Loss of fracture Thermal aging No V.D1 .1-b, 

PWR fittings of CASS toughness due to embrittlement of V.D2.1-d. 

in emergency thermal aging CASS 

core cooling embrittlement 

I systems 

BWR/ Components Loss of material Open-cycle No V.A.6-a, 

PWR serviced by due to general, cooling water V.A.6-b, 

open-cycle pitting, and system V.D1.6-b, 

cooling system crevice corrosion, V.D1.6-c, 

MIC, and V.D2.4-a, 

biofouling; buildup V.D2.4-b. 

of deposit due to 

biofouling 

BWR/ Components Loss of material Closed-cycle No V.A.6-c, 

PWR serviced by due to general, cooling water V.D1.5-a, 

closed-cycle pitting, and system V.D1.6-a, 

cooling system crevice corrosion V.D2.4-c. 

BWR Emergency core Wall thinning due Flow- No V.D2.1-f, 

cooling system to flow- accelerated V.D2.3-a. 

valves and lines accelerated corrosion 

to and from corrosion 

high-pressure 

coolant injection 

(HPCI) and 

reactor core 

isolation cooling 

(RCIC) pump 

turbines 

PWR Pumps, valves, Crack initiation Water chemistry No V.A.1-a, 

piping and and growth due to V.A.1 -c, 

fittings, and SCC V.A.3-a, 

tanks in V.A.4-a, 

containment V.D1.1-a, 

spray and V.D1.2-a, 

emergency core V.D1.4-b, 

cooling system V.D1.7-b, 

V.D1.8-a.

April 2001 17 NUREG-1801
Table 2. Summary of Aging Management Programs for the Engineered Safety Features Evaluated in Chapter V of the GALL Report (continued) 

Aging Further Item Aging Effect( Management Evaluation Number in Type Component Mechanism Programs Recommended GALL 

BWR Pumps, valves, Crack initiation Water chemistry No V.D2.1-c, piping and and growth due to and BWR stress V.D2.3-c. 

fittings in SCC and IGSCC corrosion 

emergency core cracking 

cooling system PWR Carbon steel Loss of material Boric acid No V.A.1 -b, components due to boric acid corrosion V.A.3-b, 

corrosion V.A.4-b, 

V.A.5-b, 

V.A.6-d, 

V.D1.1 -d, 

V.D1.2-b, 

V.D1.3-a, 

V.D1.4-c, 

V.D1.5-b, 

V.D1.6-d, 

V.D1.7-a, 

V.D1.8-b, 

V.E.1-a. 

BWR/ Closure bolting Loss of material Bolting integrity No V.E.2-a, PWR in high-pressure due to general V.E.2-b. 

or high- corrosion; crack 

temperature initiation and 

systems growth due to 

cyclic loading and/or SCC

NUREG-1801 April 2001 18
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Components in Loss of material Water chemistry Yes, detection of VII.A3.2-a, 

PWR spent fuel pool due to general, and one-time aging effects is to VII.A3.3-a, 

cooling and pitting, and inspection be further VII.A3.5-a, 

cleanup crevice corrosion evaluated VII.A4.1-a, 

VII.A4.2-a, 

VII.A4.3-a, 

VII.A4.4-b, 

VII.A4.5-a, 

VII.A4.6-a. 

BWR/ Linings in spent Hardening, Plant specific Yes, plant specific VII.A3.2-d, 

PWR fuel pool cooling cracking and loss VII.A3.3-d, 

and cleanup of strength due to VII.A3.5-c, 

system; seals elastomer VII.A4.2-b, 

and collars in degradation; VII.A4.3-b, 

ventilation loss of material VII.A4.5-b, 

systems due to wear VII.F1.1-b, 

VII.FI.1-c, 

VII.F1.4-b, 

VII.F2.1-b, 

VII.F2.1-c, 

VII.F2.4-b, 

VII.F3.1-b, 

VII.F3.1 -c, 

VII.F3.4-b, 

VII.F4.1 -b, 

VII.F4.1 -c. 

BWR/ Components in Cumulative TLAA, Yes, TLAA VII.B.1-a, 

PWR load handling, fatigue damage evaluated in VII.E1 .1-a, 

chemical and accordance with VII.E1.3-a, 

volume control 10 CFR VII.E1.7-a, 

system (PWR), 54.21 (c) VII.E1.8-a, 

and reactor VII.E3.1-b, 

water cleanup VII.E3.2-b, 

and shutdown VII.E3.2-c, 

cooling systems VII.E4.1-b. 

1 (older BWR) 

BWR/ Heat Crack initiation Plant specific Yes, plant specific VII.EI.5-a, 

PWR exchangers in and growth due to VII.E3.3-d, 

reactor water SCC or cracking VII.E3.4-a. 

cleanup system 

(BWR); high 

pressure pumps 

in chemical and 

volume control 

1 system (PWR)

April 2001 19 NUREG-1 801
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report (continued) 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Components in Loss of material Plant specific Yes, plant specific VlI.F1.1-a, 

PWR ventilation due to general, VII.F1.2-a, 

systems, diesel pitting, and VII.F1.4-a, 

fuel oil system, crevice corrosion, VII.F2.1-a, 

and emergency and MIC VII.F2.2-a, 

diesel generator VII.F2.4-a, 

systems; VII.F3.1 -a, 

external VII.F3.2-a, 

surfaces of VII.F3.4-a, 

carbon steel VII.F4.1-a, 

components VII.F4.2-a, 

VII.H1 .1-a, 

VII.H1.2-a, 

VII.H1.3-a, 

VII.H2.2-a, 

VII.H2.3-a, 

VII.H2.4-a, 

VII. Il-b. 

BWR/ Components in Loss of material One-time Yes, detection of VII.G.7-a, 

PWR reactor coolant due to galvanic, inspection aging effects is to VII.G.7-b. 

pump oil collect general, pitting, be further 

system of fire and crevice evaluated 

protection corrosion 

BWR/ Diesel fuel oil Loss of material Fuel oil Yes, detection of VII.H1.4-a, PWR tanks in diesel due to general, chemistry and aging effects is to VII.H2.5-a. 

fuel oil system pitting, and one-time be further 

and emergency crevice corrosion, inspection evaluated 

diesel generator MIC, and 

system biofouling 

BWR Piping, pump Loss of material Water chemistry Yes, detection of VII.E4.1-a, 

casing, and due to pitting and and one-time aging effects is to VII.E4.2-a. 

valve body and crevice corrosion inspection be further 

bonnets in evaluated 

shutdown 

cooling system 

(older BWR) 

PWR Heat Crack initiation Water chemistry Yes, plant specific VII.E1.7-c, exchangers in and growth due to and a plant- VII.E1.8-b. 

chemical and SCC and cyclic specific 

volume control loading verification 

system program 

BWR/ Neutron Reduction of Plant specific Yes, plant specific VII.A2.1-b. 

PWR absorbing neutron absorbing 

sheets in spent capacity and loss 

fuel storage of material due to 

racks general corrosion 

(Boral, boron 

steel)

NUREG-1801 20 April 2001
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report (continued) 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ New fuel rack Loss of material Structures No VII.A1.1-a. 

PWR assembly due to general, monitoring 

pitting, and 

crevice corrosion 

BWR/ Neutron Reduction of Boraflex No VII.A2.1-a. 

PWR absorbing neutron absorbing monitoring 

sheets in spent capacity due to 

fuel storage Boraflex 

racks degradation 

BWR/ Spent fuel Crack initiation Water chemistry No VII.A2.1-c, 

PWR storage racks and growth due to VII.A3.3-b. 

and valves in stress corrosion 

spent fuel pool cracking 

cooling and 

cleanup 

BWR/ Closure bolting Loss of material Boric acid No VII.A3.1-a, 

PWR and external due to boric acid corrosion VII.A3.2-b, 

surfaces of corrosion VII.A3.2-c, 

carbon steel VI .A3.3-c, 

and low-alloy VII.A3.4-b, 

steel VII.A3.5-b, 

components VII.A3.6-a, 

VII.E1.1-b, 

VII.E1.2-a, 

VII.E1.3-b, 

VII.E1.4-a, 

VII.E1.5-b, 

VII.E1.6-a, 

VII.E1.7-brVII.E1.8-d, 

VII.E1.9-a, 

VII.E1.10-a, 

VII.l.1-a. 

BWR/ Components in Loss of material Closed-cycle No VII.A3.4-a, 

PWR or serviced by due to general, cooling water VII.A4.4-a, 

closed-cycle pitting, and system VII.C2.1-a, 

cooling water crevice corrosion, VII.C2.2-a, 

system and MIC VII.C2.3-a, 

VII.C2.4-a, 

VII.C2.5-a, 

VII.E1.8-c, 

VII.E3.4-b, 

VII.F1.3-a, 

VII.F2.3-a, 

VII.F3.3-a, 

VII.F4.3-a, VII.H2.1-a.

April 2001 21 NUREG-1801
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report (continued) 

Aging Further Item 

Aging Effectl Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Cranes Loss of material Overhead No VII.B.1-b, 

PWR including bridge due to general heavy load and VII.B.2-a. 

and trolleys and corrosion and light load 

rail system in wear handling 

load handling systems 

system 

BWR/ Components in Loss of material Open-cycle No VII.C1 .1-a, 

PWR or serviced by due to general, cooling water VII.C1.2-a, 

open-cycle pitting, crevice, system VII.C1.3-a, 

cooling water and galvanic VII.C1.3-b, 

systems corrosion, MIC, VII.C1.4-a, 

and biofouling; VII.C1.5-a, 

buildup of deposit VII.C1.6-a, 

due to biofouling VII.C3.1-a, 

VII.C3.2-a, 

VII.C3.3-a, 

VII.H2.1-b. 

BWR/ Buried piping Loss of material Buried piping No VII.C1 .1-b, 

PWR and fittings due to general, and tanks VII.H1.1-b. 

pitting, and surveillance 

crevice corrosion, 

and MIC or 

Buried piping Yes, detection of 

and tanks aging effects and 

inspection operating 

experience are to 

be further 

evaluated 

BWR/ Components in Loss of material Compressed air No VII.D.1-a, 

PWR compressed air due to general monitoring VII.D.2-a, 

system and pitting VII.D.3-a, 

corrosion VII.D.4-a, 

VII.D.5-a, 

VII.D.6-a. 

BWR/ Components Loss of material Fire protection No VII.G.1-a, 

PWR (doors and due to wear; VII.G.1-d, 

barrier penetra- hardening and VII.G.2-a, 

tion seals) and shrinkage due to VII.G.2-d, 

concrete weathering VII.G.3-a, 

structures in fire VII.G.3-d, 

protection VII.G.4-a, 

VII.G.4-d, 

VII.G.5-c.

NUREG-1801 22 April 2001
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Components in Loss of material Fire water No VII.G.6-a, 

PWR water-based fire due to general, system VII.G.6-b. 

protection pitting, crevice, 

and galvanic 

corrosion, MIC, 

and biofouling _ 

BWR/ Components in Loss of material Fire protection No VII.G.8-a. 

PWR diesel fire due to galvanic, and fuel oil 

system general, pitting, chemistry 

and crevice 

corrosion 

BWR/ Tanks in diesel Loss of material Aboveground No VII.H1.4-b. 

PWR fuel oil system due to general, carbon steel 

pitting, and tanks 

crevice corrosion 

BWR/ Closure bolting Loss of material Bolting integrity No VII.l.2-a, 

PWR due to general VIl.l.2-b. 

corrosion; crack 

initiation and 

growth due to 

cyclic loading and 

SCC 

BWR Components in Crack initiation Water chemistry No VII.E2.1-a, 

contact with and growth due to VII.E2.2-a, 

sodium penta- SCC VII.E2.3-a, 

borate solution VII.E2.4-a. 

in standby liquid 

control system 

(BWR) 

BWR Components in Crack initiation Reactor water No VII.E3.1-a, 

reactor water and growth due to cleanup system VII.E3.2-a. 

cleanup system SCC and IGSCC inspection 

BWR Components in Crack initiation BWR stress No VII.E4.1-c, 

shutdown and growth due to corrosion VII.E4.3-a. 

cooling system SCC cracking and 

S(older BWR) water chemistry 

BWR Components in Loss of material Closed-cycle No VII.E4.4-a. 

shutdown due to pitting and cooling water 

cooling system crevice corrosion, system 

S(older BWR) and MIC

April 2001 23 NUREG-1 801
Table 3. Summary of Aging Management Programs for the Auxiliary Systems 

Evaluated in Chapter VII of the GALL Report (continued) 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Components Loss of material Selective No VII.C1.1-a, PWR (aluminum due to selective leaching of VII.C1.1-c, bronze, brass, leaching materials VII.C1.2-a, 

cast iron, cast Vll.C1.3-a, steel) in open- Vli.C1.5-a, 

cycle and VII.C2.3-a, closed-cycle VII.C3.1 -a, 

cooling water VII.C3.2-a. 

systems, and 

ultimate heat 

sink 

BWR/ Fire barriers, Concrete cracking Fire protection No VII.G.1-b, 

PWR walls, ceilings, and spalling due and structures VII.G.1-c, and floors in fire to freeze-thaw, monitoring VII.G.2-b, 

protection aggressive VII.G.2-c, 

chemical attack, VII.G.3-b, 

and reaction with VII.G.3-c, 

aggregates; loss VII.G.4-b, 

of material due to VII.G.4-c, corrosion of VII.G.5-a, embedded steel I VII.G.5-b.

NUREG-1801 24 April 2001
Table 4. Summary of Aging Management Programs for the Steam and Power 

Conversion System Evaluated in Chapter VIII of the GALL Report 

Further Item 

Aging Effect/ Aging Effectl Evaluation Number in 

Type Component Mechanism Mechanism Recommended GALL 

PWR/ Piping and Cumulative TLAA, Yes, TLAA VIII.B1 .1-b, 

BWR fittings in main fatigue damage evaluated in VIII.B2.1-c, 

feedwater line, accordance with VIII.D1 .1-b, 

steam line and 10 CFR VIlI.D2.1-c, 

auxiliary 54.21 (c) VIII.G.1-b. 

feedwater (AFW) 

piping (PWR Ionly) 

PWR/ Piping and Loss of material Water chemistry Yes, detection of VIII.A.1-b, 

BWR fittings, valve due to general and one-time aging effects is to VIII.A.2-b, 

bodies and (carbon steel inspection be further VIII.C.1-b, 

bonnets, pump only), pitting, and evaluated VIII.C.2-b, 

casings, tanks, crevice corrosion VIII.D1.1-c, 

tubes, VIII.D1.2-b, 

tubesheets, VIII.D1.3-a, 

channel head, VIII.D2.1-b, 

and shell (except VIII.D2.2-b, 

main steam VIII.D2.3-b, 

system) VIII.E.1 -b, VIII.E.2-b, 

VIII.E.3-a, 

VIII.E.4-a, 

VIII.E.4-d, 

VIII.E.5-a, 

VIII.E.5-b, 

VIII.E.6-a, 

VIII.F.1-b, 

VIII.F.2-b, 

VIII.F.3-a, 

VIII.F.4-a, 

VIII.F.4-d, 

VIIl.G.1-c, 

VIII.G.2-a, 

VIII.G.3-a, 

VIII.G.4-a, 

VIII.G.4-b. 

PWR AFW piping Loss of material Plant specific Yes, plant specific VIII.G.1-d. 

due to general, 

pitting, and 

crevice corrosion, 

MIC, and 

biofouling 

PWR Oil coolers in Loss of material Plant specific Yes, plant specific VIII.G.5-d. 

AFW system due to general 

(lubricating oil (carbon steel 

side possibly only), pitting, and 

contaminated crevice corrosion, 

with water) and MIC

April 2001 25 NUREG-1 801
Table 4. Summary of Aging Management Programs for the Steam and Power 

Conversion System Evaluated in Chapter VIII of the GALL Report (continued) 

Further Item 

Aging Effect/ Aging Effectl Evaluation Number in 

Type Component Mechanism Mechanism Recommended GALL 

BWR/ External surface Loss of material Plant specific Yes, plant specific VIII.H.1-b. 

PWR of carbon steel due to general 

components corrosion 

BWR/ Carbon steel Wall thinning due Flow- No VIII.A.1-a, 

PWR piping and valve to flow- accelerated VIII.A.2-a, 

bodies accelerated corrosion VIII.B1.1-c, 

corrosion VIII.B1.2-b, 

VIII.B2.1 -b, 

VIII.B2.2-a, 

VIII.C.1-a, 

VIII.C.2-a, 

VIII.D1.1-a, 

VIII.D1.2-a, 

VIII.D1.3-b, 

VIII.D2.1-a, 

VIII.D2.2-a, 

VIII.D2.3-a, 

VIII.E.1-a, 

VIII.E.2-a, 

VIII.F.1-a, 

VIII.F.2-a, 

VIII.G.1-a. 

BWR/ Carbon steel Loss of material Water chemistry No VlII.B1.1-a, 

PWR piping and valve due to pitting and VlII.B1 .2-a, 

bodies in main crevice corrosion VIII.B2.1-a, 

steam system VIII.B2.2-b. 

BWR/ Closure bolting in Loss of material Bolting integrity No VIII.H.2-a, 

PWR high-pressure or due to general VIII.H.2-b. 

high-temperature corrosion; crack 

systems initiation and 

growth due to 

cyclic loading 

and/or SCC. 

BWR/ Heat exchangers Loss of material Open-cycle No VIII.E.4-b, 

PWR and coolers/ due to general cooling water VIII.E.4-c, 

condensers (carbon steel system VIII.F.4-b, 

serviced by only), pitting, and VIII.F.4-c, 

open-cycle crevice corrosion, VIII.G.5-a, 

cooling water MIC, and VIII.G.5-b. 

biofouling; buildup 

of deposit due to 

biofouling 

BWR/ Heat exchangers Loss of material Closed-cycle No VIII.E.4-e, 

PWR and coolers/ due to general cooling water VIII.F.4-e, 

condensers (carbon steel system VIII.G.5-c. 

serviced by only), pitting, and 

closed-cycle crevice corrosion 

cooling water

NUREG-1801 26 April 2001
Table 4. Summary of Aging Management Programs for the Steam and Power 

Conversion System Evaluated in Chapter VIII of the GALL Report (continued) 

Further Item 

Aging Effect/ Aging Effect/ Evaluation Number in 

Type Component Mechanism Mechanism Recommended GALL 

BWR/ External surface Loss of material Aboveground No VIII.E.5-c, 

PWR of aboveground due to general carbon steel VIII.G.4-c. 

condensate (carbon steel tanks 

storage tank only), pitting, and 

crevice corrosion 

BWR/ External surface Loss of material Buried piping No VIII.E.5-d, 

PWR of buried due to general, and tanks VIII.G.1-e, 

condensate pitting, and surveillance VIII.G.4-d. 

storage tank and crevice corrosion, 

AFW piping and MIC or 

Buried piping Yes, detection of 

and tanks aging effects and 

inspection operating 

experience are to 

be further 

I_ _ I_ 1_ 1evaluated I 

PWR External surface Loss of material Boric acid No VIII.H.1-a. 

of carbon steel due to boric acid corrosion 

components corrosion I I

April 2001 27 NUREG-1801
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report

Aging Further 

Aging Effect/ Management Evaluation GALL Type Component Mechanism Programs Recommended Item Number 

Common Components of All Types of PWR and BWR Containment 

BWR/ Penetration Cumulative TLAA Yes, TLAA ll.A3.1-b, PWR sleeves, fatigue damage evaluated in 11.B4.1-b. 

penetration (CLB fatigue accordance 

bellows, and analysis exists) with 10 CFR 

dissimilar metal 54.21 (c) 

welds 

BWR/ Penetration Cracking due to Containment Yes, detection of II.A3.1-c, PWR sleeves, cyclic loading; inservice aging effects is to II.A3.1-d, bellows, and crack initiation inspection (ISI) be evaluated II.B4.1-c, 

dissimilar metal and growth due and 

welds to SCC containment II.B4.1-d. 

leak rate test 

BWR/ Penetration Loss of material Containment No II.A3.1-a, PWR sleeves, due to corrosion ISI and II.B4.1-a. 

penetration Containment 

bellows, and leak rate test 

dissimilar metal 

welds 

BWR/ Personnel Loss of material Containment No II.A3.2-a, PWR airlock and due to corrosion ISI and 1I.B4.2-a. 

equipment containment 

hatch leak rate test

Personnel 

airlock and 

equipment 

hatch

Loss ot leak 

tightness in 

closed position 

due to 

mechanical wear 

of locks, hinges, 

and closure 

mechanisms

Containment 

leak rate test 

and plant 

technical 

specifications

No

BWR/ Seals, gaskets, Loss of sealant Containment No 

PWR and moisture and leakage ISI and 

barriers through containment 

containment due leak rate test 

to deterioration of 

joint seals, 

gaskets, and 

moisture barriers

I I.A3.2-b, 

II.B4.2-b.

NUREG-1801 April 2001

DVV I/ 

PWR

28
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report (continued) 

Aging Further 

Aging Effect/ Management Evaluation GALL 

Type Component Mechanism Programs Recommended Item Number 

PWR Concrete (Reinforced and Prestressed) and Steel Containment 

BWR Concrete (Mark II and IIl) and Steel (Mark I, II, and Ill) Containment 

BWR/ Concrete Aging of Containment Yes, if aging ll.A1 .1-b, 

PWR elements: accessible and IS1 mechanism is ll.A1.1-c, 

foundation, inaccessible significant for ll.A1 .1-e, 

dome, and wall concrete areas inaccessible llA22b 

due to leaching areas 

of calcium I1.A2.2-c, 

hydroxide, II.A2.2-e, 

aggressive lo.B2.2.1 -a, 

chemical attack, 11.B2.2.1 -b, 

and corrosion of 11.B2.2.1-d, 

embedded steel II.B3.1.2-a, 

I1.B3.1.2-b, 

I1.B3.1.2-d, 

Il.B3.2.1-b, 

11.B3.2.1 -c, 

11.B3.2.1 -e. 

BWR/ Concrete Cracks, Structures No, if within the ll.A1 .1-f, 

PWR elements: distortion, and monitoring scope of the ll.A2.2-f, 

foundation increases in applicant's II.B2.2.1-e, 

component structures 11. B3.1.2-e, 

stress level due monitoring II.B3.1.2fe 

to settlement program II.13.2.1-f. 

BWR/ Concrete Reduction in Structures No, if within the ll.A1 .1-g, PWR elements: foundation monitoring scope of the II.A2.2-g, 

foundation strength due to applicant's I1.B2.2.1 -f, erosion of porous structures 11.13.1.2-, 

concrete monitoring I .B3.1.2-f 

subfoundation program II.B3.2.1-g. 

BWR/ Concrete Reduction of Plant specific Yes, for any II.A1 .1-h, 

PWR elements: strength and portions of II.A2.2-h, 

foundation, modulus due to concrete I1.B2.2.1-g, 

dome, and wall elevated containment that ll.11.2-g, 

temperature exceed specified l..13.2-g, 

temperature limits I1.B3.2.1h. 

BWR/ Prestressed Loss of prestress TLAA Yes, TLAA ll.A1.3-b, 

PWR containment: due to relaxation, evaluated in II.B2.2.3-b. 

tendons and shrinkage, creep, accordance 

anchorage and elevated with 10 CFR 

components temperature 54.21 (c)

April 2001 29 NUREG-1801
Table 5. Summary of Aging Management Programs for the Structures and Component Supports Evaluated in Chapters II and III of the GALL Report (continued) 

Aging Further 

Aging Effectl Management Evaluation GALL Type Component Mechanism Programs Recommended Item Number 

BWR/ Steel elements: Loss of material Containment Yes, if corrosion is II.A1.2-a, PWR liner plate and due to corrosion ISI and significant for lI.A2.1-a, containment in accessible and containment inaccessible 11.11.1.1-a, shell inaccessible leak rate test areas ll.B2.1.1-a, 

areas 

11.12.2.2-a, 

lI.B3.1.1-a, 

IL.B3.2.2-a. 

BWR Steel elements: Cumulative TLAA Yes, TLAA 113.1.1.1-c, vent header, fatigue evaluated in 11.B2.1.1-c, drywell head, damage(CLB accordance 

torus, fatigue analysis with 10 CFR II.B2.2.2-d. 

downcomers, exists) 54.21 (c) 

and 

pool shell 

BWR/ Steel elements: Loss of material Protective No ll.A1.2-a, PWR protected by due to corrosion coating II.A2.1-a, coating in accessible monitoring and 11.11.1.1-a, 

areas only maintenance II. B2. 1.1-a, 

II..B2.2.2-a, 

11.83.1.1-a, 

11.B3.2.2-a. 

BWR/ Prestressed Loss of material Containment No ll.A1.3-a, PWR containment: due to corrosion ISI II1.B2.2.3-a. 

tendons and of prestressing 

anchorage tendons and 

components anchorage 

components BWR/ Concrete Scaling, Containment No ll.A1.1-a, PWR elements: cracking, and ISI II.A1 .l-d, foundation, spalling due to ll.A2.2-a, dome, and wall freeze-thaw; II.A2.2-d, 

expansion and 

cracking due to II.B2.2.1-c, 

reaction with 11.B3.1.2-c, 

aggregate 11.833.2.1-a, 

lI.B3.2.1-d. 

BWR Steel elements: Cracking due to Containment Yes, detection of II.B13.1.1-b, vent line cyclic loads; SI and aging effects is to Il.B1.1.1-d, bellows, vent crack initiation Containment be evaluated 11.B2.1 .1-b, headers, and and growth due leak rate test I1.B2.2.2-c. 

downcomers to SCC 

BWR Steel elements: Crack initiation Containment No II.B2.2.2-b, suppression and growth due ISI and 11.13.1.1-b, chamber liner to SCC containment 11.B3.2.2-b. leak rate test

NUREG-1801 April 2001 30
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report (continued)

Aging Further 

Aging Effect/ Management Evaluation GALL 

Type Component Mechanism Programs Recommended Item Number 

BWR Steel elements: Fretting and lock Containment No II.B1.1.1-e, 

drywell head up due to wear IS! II.B2.1 .1-d, 

and I I.B2.2.2-e. 

downcomer 

pipes 

Class I Structures

All Groups 

except Group 6: 

accessible 

interior/exterior 

concrete and 

steel 

components

All types of aging 

effects

Structures 

monitoring

No, if within the 

scope of the 

applicant's 

structures 

monitoring 

program

NUREG-1801

BWR/ 

PWR

IlI.A1.1-a, 

Ill.A1.1-b, 

Ill.A1.1-c, 

Ill.Al .1-f, 

Ill.A1.2-a, 

IIl.A2.1-a, 

IIl.A2.1-b, 

III.A2.1-c, 

II1.A2.1 -d, 

IIl.A2.1-f, 

III.A2.2-a, 

III.A3.1 -a, 

Ill.A3.1-b, 

Ill.A3.1-c, 

III.A3.1-d, 

II1.A3.1 -f, 

IIl.A3.2-a, 

III.A4.1 -a, 

III.A4.1 -b, 

III.A4.1-d, 

IIl.A4.2-a, 

III.A4.2-b, 

III.A5.1 -a, 

III.A5.1-b, 

III.A5.1-c, 

Ill.A5.1-d, 

III.A5.1-f, 

IIl.A5.2-a, 

IIl.A7.1-a, 

III.A7.1-b, 

III.A7.1 -c, 

IIl.A7.1-d, 

IIl.A7.1-f, 

I Il.A7.2-a, 

IIl.A8.1-a,

April 2001 31
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report (continued) 

Aging Further 

Aging Effect/ Management Evaluation GALL Type Component Mechanism Programs Recommended Item Number 

BWR/ All Groups All types of aging Structures No, if within the III.A8.1-b, PWR except Group 6: effects monitoring scope of the III.A8.1-c, accessible applicant's l lI.A8.2-a, interior/exterior structures III.A9.1a, 

concrete and monitoring steel program III.A9.1-b, 

components III.A9.1-c, 

III.A9.1-d, 

III.A9. 1-f. 

BWR/ Groups 1-3, 5, Aging of Plant specific Yes, if an Ill.A1 .1-e, PWR 7-9: inaccessible aggressive below- llI.A1.1-g, inaccessible concrete areas grade IIl.A2.1-e, 

concrete due to environment III.A2.1g, components, aggressive exists such as chemical attack, III.A3.1-e, exterior walls and corrosion of III.A3.1-g, below grade embedded steel III.A5.1-e, and foundation llI.A5.1-g, 

III.A7.1-e, 

llI.A7.1-g, 

IIlI.A8.1 -d, 

III.A8.1-e, 

III.A9.1-e, 

III.A9.1-g. BWR/ Group 6: all All types of aging Inspection of No III.A6.1-a, PWR accessible/ effects, including water-control III.A6.1-b, 

inaccessible loss of material structures or III.A6.1-c, 

concrete, steel, due to abrasion, FERC/US III.A6.1-c, and earthen cavitation, and Army Corp of III.A6.1-d, 

components corrosion Engineers dam IlI.A6.1-e, 

inspection and III.A6.1-f, 

maintenance III.A6.1-h, 

III.A6.2-a, 

III.A6.4-a. 

BWR/ Group 5: Crack initiation Water No III.A5.2-b. 

PWR liners and growth due chemistry and 

to SCC; loss of monitoring of 

material due to spent fuel pool 

crevice corrosion water level 

BWR/ Groups 1-3, Cracking due to Masonry wall No Ill.A1.3-a, PWR 5, 6: restraint, III.A2.3-a, 

all masonry shrinkage, creep, Ill.A3.3-a, block walls and aggressive III.A5.3-a, environment I __ I I IIII.A6.3-a.

NUREG-1801 April 2001 32
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report (continued) 

Aging Further 

Aging Effect/ Management Evaluation GALL 

Type Component Mechanism Programs Recommended Item Number 

BWR/ Groups 1-3, 5, Cracks, Structures No, if within the III.A1.1-h, 

PWR 7-9: distortion, and monitoring scope of the III.A2.1-h, 

foundation increases in applicant's IIl.A3.1-h, 

component structures 

stress level due monitoring Ill.A5.1-h, 

to settlement program III.A7.1-h, 

III.A8.1-f, 

IIl.A9.1-h. 

BWR/ Groups 1-3, Reduction in Structures No, if within the Ill.A1.1-i, 

PWR 5-9: foundation monitoring scope of the IIl.A2.1-i, 

foundation strength due to applicant's IIl.A3.1-i, erosion of porous structures lll.A5.1-i, 

concrete monitoring II1.A5.1.-i, 

subfoundation program III.A6.1-g, 

III.A7.1 -i, 

III.A8.1 -g, 

IIl.A9.1-i. 

BWR/ Groups 1-5: Reduction of Plant specific Yes, for any Ill.A1.1-j, 

PWR concrete strength and portions of III.A2.1-j, 

modulus due to concrete that III.A3.1-j, 

elevated exceed specified 

temperature temperature limits III.A4.1 -c, 

BWR/ Groups 7, 8: Crack Initiation Plant specific Yes III.A7.2-b, 

PWR liners and growth due IIl.A8.2-b. 

to SCC; loss of 

material due to 

crevice corrosion 

Component Supports 

BWR/ All Groups: Aging of Structures No, if within the Ill.B13.1.4-a, 

PWR support component monitoring scope of the Ill.B13.2.3-a, 

members: supports applicant's Ill.B13.3.3-a, 

anchor bolts, concreteIlI.B2.1 structures -a, 

concrete monitoring 

surrounding program IIl.B2.2-a, 

anchor bolts, III.B3.1-a, 

welds, grout III.B3.2-a, 

pad, bolted III.B4.1 -a, 

connections, III.B4.2-a, 

etc. Ill.B4.3-a, 

IIl.B5.1-a, 

I _IIl.B5.2-a.

April 2001 33 NUREG-1801
Table 5. Summary of Aging Management Programs for the Structures and 

Component Supports Evaluated in Chapters II and III of the GALL Report (continued) 

Aging Further 

Aging Effect/ Management Evaluation GALL Type Component Mechanism Programs Recommended Item Number 

BWR/ Groups B1.1, Cumulative TLAA Yes, TLAA Ill.B1.1.1-c, PWR B1.2, and B1.3: fatigue damage evaluated in Il.B1.2.1-c, 

support (CLB fatigue accordance 1ll.B1.3.1-b. 

members: analysis exists) with 10 CFR 

anchor bolts 54.21 (c) 

and welds 

PWR All Groups: Loss of material Boric acid No 1ll.B13.1.1-b, 

support due to boric acid corrosion 1ll.B13.2.1-b, members: corrosion Ill.B2.1-b, 

anchor bolts III.B2.1-b, 

and welds lI.B3.1-b, 

III.B4.1-b, 

Ill.B5.1-b. 

BWR/ Groups B1.1, Loss of material SI No Ill.B1.1.1-a, PWR B1.2, and B1.3: due to lll.B1.1.3-a, support environmental 111.13.2.1 members: corrosion; loss of Ill.B1.2.1-a, anchor bolts, mechanical Ill.B1.2.2-a, welds, spring function due to lll.B1.3.1-a. 

hangers, corrosion, lll.B1.3.2-a. 

guides, stops, distortion, dirt, 

and vibration overload, etc. 

isolators 

BWR/ Group B1.1: Crack initiation Bolting integrity No llI.B1.1.2-a. 

PWR high strength and growth due 

low-alloy bolts to SCC

NUREG-1801 April 2001 34
Table 6. Summary of Aging Management Programs for the Electrical Components 

Evaluated in Chapter VI of the GALL Report 

Aging Further Item 

Aging Effect/ Management Evaluation Number in 

Type Component Mechanism Programs Recommended GALL 

BWR/ Electrical equip- Degradation due Environmental Yes, TLAA VI.B.1-a. 

PWR ment subject to to various aging qualification of 

10 CFR 50.49 mechanisms electric 

environmental components 

qualification 

(EQ) require

ments 

BWR/ Electrical cables Embrittlement, Aging manage- No VI.A.1-a. 

PWR and connections cracking, melting, ment program for 

not subject to discoloration, electrical cables 

10 CFR 50.49 swelling, or loss of and connections 

EQ dielectric strength not subject to 

requirements leading to 10 CFR 50.49 

reduced insulation EQ requirements 

resistance (IR); 

electrical failure 

caused by 

thermal/ 

thermoxidative 

degradation of 

organics; 

radiolysis and 

photolysis 

(ultraviolet [UV] 

sensitive 

materials only) of 

organics; 

radiation-induced 

oxidation; 

moisture intrusion 

BWR/ Electrical cables Embrittlement, Aging manage- No VI.A.1-b. 

PWR used in cracking, melting, ment program for 

instrumentation discoloration, electrical cables 

circuits not swelling, or loss of used in 

subject to dielectric strength instrumentation 

10 CFR 50.49 leading to circuits not 

EQ reduced IR; subject to 

requirements electrical failure 10 CFR 50.49 

that are caused by EQ requirements 

sensitive to thermaV 

reduction in thermoxidative 

conductor degradation of 

insulation organics; 

resistance radiation-induced 

oxidation; 

moisture intrusion I

April 35 NUREG-1801 2001
Table 6. Summary of Aging Management Programs for Electrical Components 

Evaluated in Chapter VI of the GALL Report (continued) 

Aging Further Item 

Aging Effectl Management Evaluation Number In 

Type Component Mechanism Programs Recommended GALL 

BWR/ Inaccessible Formation of Aging No VI.A.1-c. 

PWR medium-voltage water trees; management (2kV to 15kV) localized damage program for 

cables leading to inaccessible 

(e.g., installed in electrical failure medium-voltage conduit or direct (breakdown of cables not 

buried) not insulation) caused subject to 

subject to by moisture 10 CFR 50.49 

10 CFR 50.49 intrusion and EQ requirements 

EQ water trees 

1 requirements 

PWR Electrical Corrosion of Boric acid No VI.A.2-a. 

connectors not connector contact corrosion 

subject to surfaces caused 

10 CFR 50.49 by intrusion of 

EQ borated water 

requirements 

that are 

exposed to 

borated water 

I ___ lleakage I

NUREG-1801 36 April 2001
APPENDIX

PLANT SYSTEMS EVALUATED IN THE GALL REPORT 

(VOLUME 2) 

LISTS OF ITEM NUMBERS IN THE GALL REPORT 

(VOLUME 2)

April 2001 A-i NUREG-1801
This Page Intentionally Left Blank

NUREG-1801 A-ii April 2001
TABLE OF CONTENTS 

Page 

PLANT SYSTEMS EVALUATED IN THE GALL REPORT (VOLUME 2) ............................ A-1 

LISTS OF ITEM NUMBERS IN THE GALL REPORT (VOLUME 2) 

II. Containment Structures ..................................................................................... A-4 

Ill. Class 1 Structures and Component Supports .................................................. A-5 

IV.A1. Reactor Vessel (BW R) ...................................................................................... A-7 

IV.A2. Reactor Vessel (PW R) .................................................................................... A-8 

IV.B1. Reactor Vessel Internals (BW R) ........................................................................ A-9 

IV.B2. Reactor Vessel Internals (PW R) - W estinghouse ........................................... A-1 0 

IV.B3. Reactor Vessel Internals (PWR) - Combustion Engineering ......................... A-i 1 

IV.B4. Reactor Vessel Internals (PW R) - Babcock & W ilcox ........................................ A-12 

IV.C1. Reactor Coolant Pressure Boundary (BW R) ...................................................... A-14 

IV.C2. Reactor Coolant System and Connected Lines (PW R) .................................. A-1 5 

IV.D1. Steam Generator (Recirculating) ................................................................... A-1 6 

IV.D2. Steam Generator (Once-Through) ..................................................................... A-17 

V.A. Containment Spray System (PW R) .............................................................. A-1 8 

V.B. Standby Gas Treatment System (BW R) ........................................................ A-1 9 

V.C. Containment Isolation Components ............................................................... A-1 9 

V.D1. Emergency Core Cooling System (PW R) .......................................................... A-20 

V.D2. Emergency Core Cooling System (BW R) .......................................................... A-21 

V.E. Carbon Steel Components ................................................................................ A-21 

VI.A. Electrical Cables and Connections Not Subject to 10 CFR 50.49 

Environmental Qualification Requirements ....................................................... -A-22 

VI.B. Equipment Subject to 10 CFR 50.49 Environmental 

Qualification Requirements ............................................................................... A-22 

VII.A1. New Fuel Storage .............................................................................................. A-23 

VII.A2. Spent Fuel Storage ........................................................................................... A-23 

VII.A3. Spent Fuel Pool Cooling and Cleanup (PW R) ................................................... A-23 

VII.A4. Spent Fuel Pool Cooling and Cleanup (BW R) ................................................... A-24 

VII.A5. Suppression Pool Cleanup System (BW R) ........................................................ A-24 

VII.B. Overhead Heavy Load and Light Load (Related to Refueling) 

Handling Systems ............................................................................................. A-24 

VII.C1. Open-Cycle Cooling W ater System (Service W ater System) ............................. A-25 

VII.C2. Closed-Cycle Cooling W ater System ................................................................. A-25 

VII.C3. Ultimate Heat Sink ............................................................................................. A-26 

VII.D. Compressed Air System .................................................................................... A-26 

VII.El. Chemical and Volume Control System (PW R) ................................................... A-27 

VII.E2. Standby Liquid Control System (BW R) .............................................................. A-28 

VII.E3. Reactor W ater Cleanup System ........................................................................ A-28 

VII.E4. Shutdown Cooling System (Older BW R) ........................................................... A-29

April 2001 A-iii NUREG-1801
LISTS OF TABLES OF ITEM NUMBERS IN THE GALL REPORT (VOLUME 2) (Cont.) 

Page 

VII.F1. Control Room Area Ventilation System ............................................................. A-29 

VII.F2. Auxiliary and Radwaste Area Ventilation System .............................................. A-30 

VII.F3. Primary Containment Area Ventilation System .................................................. A-30 

VII.F4. Diesel Generator Building Ventilation System ................................................... A-31 

VII.G. Fire Protection ................................................................................................... A-31 

VII.H1. Diesel Fuel Oil System ...................................................................................... A-32 

VII.H2. Emergency Diesel Generator System ................................................................ A-32 

VII.L Carbon Steel Components ................................................................................ A-33 

VIII.A. Steam Turbine System ...................................................................................... A-33 

VIII.B1. Main Steam System (PW R) ............................................................................... A-33 

VIII.B2. Main Steam System (BW R) ............................................................................... A-34 

VIII.C. Extraction Steam System .................................................................................. A-34 

VIII.D1. Feedwater Systems (PW R) ............................................................................... A-34 

VIII.D2. Feedwater Systems (BW R) ............................................................................... A-35 

VIII.E. Condensate System .......................................................................................... A-35 

VIII.F. Steam Generator Blowdown System (PW R) ..................................................... A-36 

VIII.G. Auxiliary Feedwater (AFW ) System (PW R) ....................................................... A-36 

VIII.H. Carbon Steel Components ................................................................................ A-36

NUREG-1801 A-iv April 2001
Plant Systems 

Evaluated in the GALL Report (Volume 2)

Section in GALL 

Type System (Vol. 2) 

BWR Automatic depressurization system V.D2 

BWR Containment structures: 

Mark I steel containments Il.B1 

Mark I1 concrete and steel containments II.B2 

Mark III concrete and steel containments 1I.B3 

Common components Il.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 Ill.A1 

BWR Reactor building with steel superstructure Ill.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 IV.C1 

Feedwater IV.C1 

High-pressure core spray IV.C1 

High-pressure coolant injection IV.C1 

Isolation condenser IV.C1 

Low-pressure coolant injection IV.C1 

Low-pressure core spray IV.C1 

Main steam IV.C1 

Reactor core isolation cooling IV.C1 

Reactor water cleanup IV.C1 

Recirculation system IV.C1 

Residual heat removal IV.C1 

Shutdown cooling IV.C1 

Standby liquid control 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 Ill.A9 

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

BWR/PWR Auxiliary building, diesel generator building, radwaste Ill.A3 

building, turbine building, switchgear room, auxiliary 

feedwater pump house, and utility/piping tunnels 

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

BWR/PWR Closed-cycle cooling water system (reactor auxiliary cooling VII.C2 

water)

April 2001 A-1 NUREG-1801
Plant Systems 

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

Section in GALL 

Type System (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 IIl.A4 

BWR/PWR Containment isolation components (containment isolation V.C 

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

VII, and VIII) 

BWR/PWR Control room/building IllI.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 

BWRPPWR Fire protection VII.G 

BWR/PWR Fuel storage facility and refueling canal Ill.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) VII.B 

handling systems 

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 Ill.A5 

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

BWR/PWR Steam turbine system VIII.A 

BWRIPWR Steel tanks Ill.A8 

BWR/PWR Ultimate heat sink VII.C3 

BWR/PWR Water-control structures (e.g., intake structure, cooling tower, IllI.A6 _and spray pond) 

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 II.A1 

Steel containments II.A2 

_R Common components II.A3 

PWR Coolant storage/refueling water system V.D1

NUREG-1801 A-2 April 2001
Plant Systems 

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

Section in GALL 

Type System (Vol. 2) 

PWR Core flood system (see accumulators or safety injection V.D1 

tanks) 

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 Ill.A1 

PWR Reactor coolant system and connected lines (up to and 

including the second isolation valve): 

Chemical and volume control system IV.C2 

Core flood system IV.C2 

Drains and instrumentation lines IV.C2 

High-pressure injection system IV.C2 

Low-pressure injection IV.C2 

Residual heat removal or shutdown cooling IV.C2 

Safety injection IV.C2 

Sampling system lV.C2 

PWR Reactor coolant system, pressurizer, pressurizer relief tank, IV.C2 

and other Class 1 components 

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

April 2001 A-3 NUREG-1801
List of Item Numbers in the GALL Report 

II. Containment Structures

NUREG-1801

Item Number 

in GALL Description 

II.A Pressurized water reactor (PWR) containments 

II.A1 Concrete containments (reinforced and prestressed) 

IL.A1.1 Concrete elements 

Il.A1.2 Steel elements 

ll.A1.3 Prestressing system 

Ih.A2 Steel containments 

Il.A2.1 Steel elements 

i1.A2.2 Concrete elements 

II.A3 Common components 

Il.A3.1 Penetration sleeves, penetration bellows, and dissimilar metal welds 

II.A3.2 Personnel airlock and equipment hatch 

II.A3.3 Seals, gaskets, and moisture barriers (caulking, flashing, and other sealants) 

II.B Boiling water reactor (BWR) containments 

Ih.B1 Mark I containments 

II.B1.1 Steel containments 

II.B1.1.1 Steel elements 

Ih.B2 Mark II containments 

II.B2.1 Steel containments 

11.B2.1.1 Steel elements 

I1.B2.2 Concrete containments 

II.B2.2.1 Concrete elements 

1I.B2.2.2 Steel elements 

11.B2.2.3 Prestressing system 

I.hB3 Mark III containments 

II.B3.1 Steel containments 

I1.B3.1.1 Steel elements 

II.B3.1.2 Concrete elements 

11.B3.2 Concrete containments 

II.B3.2.1 Concrete elements 

II.B3.2.2 Steel elements 

Ih.B4 Common components 

II.B4.1 Penetration sleeves, penetration bellows, and dissimilar metal welds 

I1.B4.2 Personnel airlock, equipment hatch, and control rod drive (CRD) hatch 

11.B4.3 Seals, gaskets, and moisture barriers (caulking, flashing, and other sealants)

A-4 April 2001
List of Item Numbers in the GALL Report 

Ill. Class 1 Structures and Component Supports

Item Number 

in GALL Description 

III.A Class 1 structures 

Ill.A1 Group 1 structures (BWR reactor building, PWR shield building, and control 

room/building) 

Ill.A1.1 Concrete elements 

Ill.A1.2 Steel elements 

Ill.A1.3 Masonry walls 

Ill.A2 Group 2 structures (BWR reactor building with steel superstructure) 

III.A2.1 Concrete elements 

1II.A2.2 Steel elements 

II.A2.3 Masonry walls 

Ill.A3 Group 3 structures (auxiliary building, diesel generator building, radwaste 

building, turbine building, switchgear room, auxiliary feedwater (AFW) 

pumphouse, and utility/piping tunnels) 

III.A3.1 Concrete elements 

Ill.A3.2 Steel elements 

lll.A3.3 Masonry walls 

Ill.A4 Group 4 structures (containment internal structures, excluding refueling canal) 

Ill.A4.1 Concrete elements 

1II.A4.2 Steel elements 

Ill.A5 Group 5 structures (fuel storage facility, refueling canal) 

lll.A5.1 Concrete elements 

Ill.A5.2 Steel elements 

1II.A5.3 Masonry walls 

Ill.A6 Group 6 structures (water control structures) 

III.A6.1 Concrete elements 

III.A6.2 Steel elements 

Ill.A6.3 Masonry walls 

III.A6.4 Earthen water control structures 

Ill.A7 Group 7 structures (concrete tanks) 

Ii.A7.1 Concrete elements 

III.A7.2 Steel elements 

Ill.A8 Group 8 structures (steel tanks) 

III.A8.1 Concrete elements 

III.A8.2 Steel elements 

UhI.A9 Group 9 structures (BWR unit vent stack) 

Ill.A9.1 Concrete elements 

I11.B Component supports 

Uh1.B1 Supports for ASME piping and components 

1113.1.1 Supports for ASME Class 1 piping and components 

lll.B1.1.1 Support members; welds, bolted connections; support anchorage to building structure 

lll.B1.1.2 High-strength bolts for NSSS component supports 

lll.B1.1.3 Constant/variable load spring hangers; guides; stops; sliding surfaces; design 

clearances; vibration isolators 

lll.B1.1.4 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates 

ll.B13.2 Supports for ASME Class 2 and 3 piping and components 

Ill.B1.2.1 Support members; welds, bolted connections; support anchorage to building structure

April 2001 A-5 NUREG-1801
List of Item Numbers in the GALL Report Ill. Class I Structures and Component Supports (continued) 

Item Number 

in GALL Description lll.B1.2.2 Constant/variable load spring hangers; guides; stops; sliding surfaces; design clearances; vibration isolators 

lll.B1.2.3 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates IIl.B1.3 Supports for ASME Class MC components (BWR containment supports) lII.B1.3.1 Support members; welds, bolted connections; support anchorage to building structure 

Ill.B1.3.2 Guides; stops; sliding surfaces; design clearances 

lll.B1.3.3 Building concrete at locations of expansion and grouted anchors; grout pads for 

suppor base plates 

Ill.B2 Supports for cable trays, conduits, HVAC ducts, tube track, instrument tubing, and non-ASME piping and components III.B2.1 Support members; welds; bolted connections; support anchorage to building structure 

II.B2.2 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates Ill.B3 Anchorage of racks, panels, cabinets, and enclosures for electric equipment 

and instrumentation 

II.B3.1 Support members; welds; bolted connections; support anchorage to building structure I1.B3.2 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates Ill.B4 Supports for emergency diesel generator (EDG), HVAC system components, and other miscellaneous mechanical equipment 1Il.B4.1 Support members; welds; bolted connections; support anchorage to building structure 

III.B4.2 Vibration isolation elements 

II.B4.3 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates Ill.B5 Supports for platforms, pipe whip restraints, jet impingement shields, masonry walls, and other miscellaneous steel structures 

II1.B5.1 Support members; welds; bolted connections; support anchorage to building structure 

lll.B5.2 Building concrete at locations of expansion and grouted anchors; grout pads for 

support base plates

NUREG-1801 A-6 April 2001
List of Item Numbers in the GALL Report IV.A1. Reactor Vessel (BWR) 

Item Number 

in GALL Description 

IV.A1.1 Top head enclosure 

IV.A1.1.1 Top head 

IV.A1.1.2 Nozzles [vent, top head spray or reactor core isolation cooling (RCIC), and spare] IV.A1.1.3 Head flange 

IV.A1.1.4 Closure studs and nuts 

lV.A1.1.5 Vessel flange leak detection line 

IV.A1.2 Vessel shell 

IV.A1.2.1 Vessel flange 

IV.A1.2.2 Upper shell 

IV.A1.2.3 Intermediate nozzle shell 

IV.A1.2.4 Intermediate beltline shell 

IV.A1.2.5 Lower shell 

IV.A1.2.6 Beltline welds 

IV.A1.2.7 Attachment welds 

IV.A1.3 Nozzles 

IV.A1.3.1 Main steam 

IV.A1.3.2 Feedwater 

IV.A1.3.3 CRD return line 

IV.A1.3.4 Low-pressure coolant injection (LPCI) or residual heat removal (RHR) injection mode 

IV.A1.4 Nozzles safe ends 

IV.A1.4.1 High-pressure core spray (HPCS) 

IV.A1.4.2 Low-pressure core spray (LPCS) 

IV.A1.4.3 CRD return line 

IV.A1.4.4 Recirculating water (inlet and outlet) 

IV.A1.4.5 LPCI or RHR injection mode 

IV.A1.5 Penetrations 

IV.A1.5.1 CRD stub tubes 

IV.A1.5.2 Instrumentation 

IV.A1.5.3 Jet pump instrument 

IV.A1.5.4 Standby liquid control 

IV.A1.5.5 Flux monitor 

IV.A1.5.6 Drain line 

IV.A1.6 Bottom head 

IV.A1.7 Support skirt and attachment welds

April 2001 A-7 NUREG-1801
List of Item Numbers in the GALL Report 

IV.A2. Reactor Vessel (PWR) 

Item Number 

in GALL Description 

IV.A2.1 Closure head IV.A2.1.1 Dome 

IV.A2.1.2 Head flange 

IV.A2.1.3 Stud assembly 

IV.A2.1.4 Vessel flange leak detection line 

IV.A2.2 Control rod drive (CRD) head penetration 

IV.A2.2.1 Nozzle 

IV.A2.2.2 Pressure housing 

IV.A2.2.3 Flange bolting 

IV.A2.3 Nozzles 

IV.A2.3.1 Inlet 

IV.A2.3.2 Outlet 

IV.A2.3.3 Safety injection (on some) 

IV.A2.4 Nozzle safe ends 

IV.A2.4.1 Inlet 

IV.A2.4.2 Outlet 

IV.A2.4.3 Safety injection (on some) 

IV.A2.5 Shell 

IV.A2.5.1 Upper (nozzle) shell 

IV.A2.5.2 Intermediate and lower shell 

IV.A2.5.3 Vessel flange 

IV.A2.5.4 Bottom head 

IV.A2.6 Core support pads/core guide lugs 

IV.A2.7 Penetrations 

IV.A2.7.1 Instrumentation tubes (bottom head) 

IV.A2.7.2 Head vent pipe (top head) 

IV.A2.7.3 Instrument tubes (top head) 

IV.A2.8 Pressure vessel support 

IV.A2.8.1 Skirt support 

IV.A2.8.2 Cantilever/column support 

IV.A2.8.3 Neutron shield tank

NUREG-1801 A-8 April 2001
List of Item Numbers in the GALL Report 

IV.B1. Reactor Vessel Internals (BWR)

Item Number in 

GALL Description 

IV.B1 .1 Core shroud, shroud head, and core plate 

IV.B1 .1.1 Core shroud (upper, central, and lower) 

IV.B1 .1.2 Core plate 

IV.B1 .1.3 Core plate bolts 

IV.B1 .1.4 Access hole cover 

IV.B1 .1.5 Shroud support structure 

IV.B1 .1.6 LPCI coupling 

IV.B1.2 Top guide 

IV.B1.3 Core spray lines and spargers 

IV.B1 .3.1 Core spray lines (headers) 

IV.B1 .3.2 Spray ring 

IV.B1 .3.3 Spray nozzles 

IV.B1 .3.4 Thermal sleeve 

IV.B1 .4 Jet pump assemblies 

IV.B1 .4.1 Thermal sleeve 

IV.B1 .4.2 Inlet header 

IV.B1 .4.3 Riser brace arm 

IV.B1 .4.4 Holddown beams 

IV.B1 .4.5 Inlet elbow 

IV.B1 .4.6 Mixing assembly 

IV.B1 .4.7 Diffuser 

IV.B1 .4.8 Castings 

IV.B1 .4.9 Jet pump sensing line 

IV.B1.5 Fuel support and CRD assemblies 

IV.B1 .5.1 Orif iced fuel support 

IV.B1 .5.2 CRD housing 

IV.B1.6 Instrumentation 

IV.B1 .6.1 Intermediate range monitor (IRM) dry tubes 

IV.B1 .6.2 Low-power range monitor (LPRM) dry tubes 

IV.B1 .6.3 Source range monitor (SRM) dry tubes 

IV.B1 .6.4 Incore neutron flux monitor guide tubes

April 2001 A-9 NUREG-1801
List of Item Numbers in the GALL Report 

IV.B2. Reactor Vessel Internals (PWR) - Westinghouse 

Item Number in 

GALL Description IV.B2.1 Upper internals assembly 

IV.B2.1.1 Upper support plate 

IV.B2.1.2 Upper support column 

IV.B2.1.3 Upper support column bolts 

IV.B2.1.4 Upper core plate 

IV.B2.1.5 Upper core plate alignment pins 

IV.B2.1.6 Fuel alignment pins 

IV.B2.1.7 Hold-down spring 

IV.B2.2 RCCA guide tube assemblies 

IV.B2.2.1 RCCA guide tubes 

IV.B2.2.2 RCCA guide tube bolts 

IV.B2.2.3 RCCA guide tube support pins 

IV.B2.3 Core barrel 

IV.B2.3.1 Core barrel 

IV. B2.3.2 Core barrel flange 

IV.B2.3.3 Core barrel outlet nozzles 

IV.1B2.3.4 Thermal shield 

IV.B2.4 Baffle/former assembly 

IV.B2.4.1 Baffle/former plates 

IV.B2.4.2 Baffle/former bolts 

IV.B2.5 Lower internal assembly 

IV.B2.5.1 Lower core plate 

IV.B2.5.2 Fuel alignment pins 

IV.B2.5.3 Lower support forging or casting 

IV.B2.5.4 Lower support plate columns 

IV.B2.5.5 Lower support plate column bolts 

IV.B2.5.6 Radial support keys and clevis inserts 

IV.B2.5.7 Clevis insert bolts 

IV.B2.6 Instrumentation support structure 

IV.B2.6.1 Flux thimble guide tubes 

IV.1B2.6.2 Flux th im bles

NUREG-1801 A-1 0 April 2001
List of Item Numbers in the GALL Report 

IV.B3. Reactor Vessel Internals (PWR) - Combustion Engineering

Item Number in 

GALL Description 

IV.B3.1 Upper internals assembly 

IV.B3.1 .1 Upper guide structure support plate 

IV.B3.1.2 Fuel alignment plate 

IV.B3.1.3 Fuel alignment plate guide lugs and guide lug inserts 

IV.B3.1.4 Hold-down ring 

IV.B3.2 Control-core element assembly (CEA) shroud assemblies 

IV.B3.2.1 CEA shrouds 

IV.B3.2.2 CEA shrouds bolts 

IV.B3.2.3 CEA shrouds extension shaft guides 

IV.1B3.3 Core support barrel 

IV.B3.3.1 Core support barrel 

IV.B3.3.2 Core support barrel upper flange 

IV.B3.3.3 Core support barrel alignment keys 

IV.B3.4 Core shroud assembly 

IV.B3.4.1 Core shroud assembly 

IV.B3.4.2 Core shroud assembly bolts 

IV.B3.4.3 Core shroud tie rods 

IV.B3.5 Lower internal assembly 

IV.B3.5.1 Core support plate 

IV.B3.5.2 Fuel alignment pins 

IV.B3.5.3 Lower support structure beam assemblies 

IV.B3.5.4 Core support column 

IV.B3.5.5 Core support column bolts 

IV.B3.5.6 Core support barrel snubber assemblies

April 2001 A-1 1 NUREG-1801
List of Item Numbers in the GALL Report 

IV.B4. Reactor Vessel Internals (PWR) - Babcock & Wilcox (B&W) 

Item Number 

in GALL Description IV.B4.1 Plenum cover and plenum cylinder 

IV.B4.1.1 Plenum cover assembly 

IV.B4.1.2 Plenum cylinder 

IV.B4.1.3 Reinforcing plates 

IV.B4.1.4 Top flange-to-cover bolts 

IV.B4.11.5 Bottom flange-to-upper grid screws 

IV.B4.2 Upper grid assembly 

IV.B4.2.1 Upper grid rib section 

IV.B4.2.2 Upper grid ring forging 

IV.B4.2.3 Fuel assembly support pads 

IV.B4.2.4 Plenum rib pads 

IV.B4.2.5 Rib-to-ring screws 

IV.B4.3 Control rod guide tube (CRGT) assembly 

IV.1B4.3.1 CRGT pipe and flange 

IV.B4.3.2 CRGT spacer casting 

IV.B4.3.3 CRGT spacer screws 

IV.B4.3.4 Flange-to-upper grid screws 

IV.B4.3.5 CRGT rod guide tubes 

IV.B4.3.6 CRGT rod guide sectors 

IV.B4.4 Core support shield assembly 

IV.B4.4.1 Core support shield cylinder (top and bottom flange) IV.B4.4.2 Core support shield-to-core barrel bolts 

IV.B4.4.3 Outlet and vent valve nozzles 

IV.B4.4.4 Vent valve body and retaining ring 

IV.1B4.4.5 Vent valve assembly locking device 

IV.B4.5 Core barrel assembly 

IV.B4.5.1 Core barrel cylinder (top and bottom flange) 

IV.B4.5.2 Lower intemals assembly-to-core barrel bolts 

IV.B4.5.3 Core barrel-to-thermal shield bolts 

IV.B4.5.4 Baffle plates and formers 

IV.B4.5.5 Baffle/former bolts and screws 

IV.B4.6 Lower grid (LG) assembly 

IV.B4.6.1 Lower grid rib section 

IV.B4.6.2 Fuel assembly support pads 

IV.B4.6.3 Lower grid rib-to-shell forging screws 

IV.B4.6.4 Lower grid flow distributor plate 

IV.B4.6.5 Orifice plugs 

IV.B4.6.6 Lower grid and shell forgings 

IV.B4.6.7 Lower internals assembly-to-thermal shield bolts 

IV.B4.6.8 Guide blocks and bolts 

IV.B4.6.9 Shock pads and bolts 

IV.B4.6.10 Support post pipes 

IV.B4.6.1 1 Incore guide tube spider castings

NUREG-1801 A-12 April 2001
List of Item Numbers in the GALL Report 

IV.B4. Reactor Vessel Internals (PWR) - Babcock & Wilcox (B&W) (continued) 

Item Number 

in GALL Description 

IV.B4.7 Flow distributor 

IV.B4.7.1 Flow distributor head and flange 

IV.B4.7.2 Shell forging-to-flow distributor bolts 

IV.B4.7.3 Incore guide support plate 

IV.B4.7.4 Clamping ring 

IV.1B4.8 Thermal shield

April 2001 A-1 3 NUREG-1801
List of Item Numbers in the GALL Report 

IV.C1. Reactor Coolant Pressure Boundary (BWR) 

Item Number 

in GALL Description 

IV.C1.1 Piping and fittings 

IV.C1.1.1 Main steam 

IV.C1.1.2 Feedwater 

IV.C1.1.3 High-pressure coolant injection (HPCI) system IV.C1.1.4 Reactor core isolation cooling (RCIC) system IV.C1.1.5 Recirculation 

IV.C1.1.6 Residual heat removal (RHR) system IV.C1.1.7 Low pressure coolant injection (LPCI) system IV.C1.1.8 Low pressure core spray (LPCS) system IV.C1.1.9 High pressure core spray (HPCS) system IV.C1.1.10 Lines to isolation condenser 

IV.C1.1.11 Lines to reactor water cleanup (RWC) and standby liquid control (SLC) systems IV.C1.1.12 Steam line to HPCI and RCIC pump turbine 

IV.C1.1.13 Small bore piping less than NPS 4 

IV.C1.2 Recirculation pump 

IV.C1.2.1 Casing 

IV.C1.2.2 Cover 

IV.C1.2.3 Seal flange 

IV.C1.2.4 Closure bolting 

IV.C1.3 Valves 

IV.C1.3.1 Body 

IV.C1.3.2 Bonnet 

IV.C1.3.3 Seal flange 

IV.C1.3.4 Closure bolting 

IV.C1.4 Isolation condenser 

IV.C1.4.1 Tubing 

IV.C1.4.2 Tubesheet 

IV.C1.4.3 Channel head 

IV.C1.4.4 Shell

NUREG-1801 A-1 4 April 2001
List of Item Numbers in the GALL Report 

IV.C2. Reactor Coolant System and Connected Lines (PWR)

Item Number in 

GALL Description 

IV.C2.1 Reactor coolant system piping and fittings 

IV.C2.1.1 Cold-leg 

IV.C2.1.2 Hot-leg 

IV.C2.1.3 Surge line 

IV.C2.1.4 Spray line 

IV.C2.1.5 Small-bore reactor coolant system (RCS) piping, fittings, and branch connections 

less than NPS 4 

IV.C2.2 Connected systems piping and fittings 

IV.C2.2.1 RHR or low-pressure injection system 

(decay heat removal [DHR]/shutdown system) 

IV.C2.2.2 Core flood system (CFS) 

IV.C2.2.3 High-pressure injection system (makeup and letdown functions) 

IV.C2.2.4 Chemical and volume control system 

IV.C2.2.5 Sampling system 

IV.C2.2.6 Drains and instrument lines 

IV.C2.2.7 Nozzles and safe ends 

IV.C2.2.8 Small-bore piping, fittings, and branch connections less than NPS 4 in connected 

systems 

IV.C2.3 Reactor coolant pump 

IV.C2.3.1 Casing 

IV.C2.3.2 Cover 

IV.C2.3.3 Closure bolting 

IV.C2.4 Safety and relief valves 

IV.C2.4.1 Body 

IV.C2.4.2 Bonnet 

IV.C2.4.3 Closure bolting 

IV.C2.5 Pressurizer 

IV.C2.5.1 Shell/heads 

IV.C2.5.2 Spray line nozzle 

IV.C2.5.3 Surge line nozzle 

IV.C2.5.4 Spray head 

IV.C2.5.5 Thermal sleeves 

IV.C2.5.6 Instrument penetrations 

IV.C2.5.7 Safe ends 

IV.C2.5.8 Manway and flanges 

IV.C2.5.9 Manway and flange bolting 

IV.C2.5.10 Heater sheaths and sleeves 

IV.C2.5.11 Support keys, skirt, and shear lugs 

IV.C2.5.12 Integral support 

IV.C2.6 Pressurizer relief tank 

IV.C2.6.1 Tank shell and heads 

IV.C2.6.2 Flanges and nozzles

April 2001 A-1 5 NUREG-1801
List of Item Numbers in the GALL Report 

IV.D1. Steam Generator (Recirculating)

Item Number in 

GALL Description 

IV.D1.1 Pressure boundary and structural 

IV.D1.1.1 Top head 

IV.D1.1.2 Steam nozzle and safe end 

IV.D1.1.3 Upper and lower shell 

IV.D1.1.4 Transition cone 

IV.D1.1.5 Feedwater nozzle and safe end 

IV.D1.1.6 Feedwater impingement plate and support 

IV.D1.1.7 Secondary manway and handhole bolting 

IV.D1.1.8 Lower head 

IV.D1.1.9 Primary nozzles and safe ends 

IV.D1.1.10 Instrument nozzles 

IV.D1.1.11 Primary manway (cover and bolting) 

IV.D1.2 Tube bundle 

IV.D1 .2.1 Tubes and sleeves 

IV.D1.2.2 Tube support lattice bars (combustion engineering [CE]) 

IV.D1.2.3 Tube plugs 

IV.D1.2.4 Tube support plates 

IV.D1.3 Upper assembly and separators 

IV.D1.3.1 Feedwater inlet ring and support

NUREG-1801 A-1 6 April 2001
List of Item Numbers in the GALL Report 

IV.D2. Steam Generator (Once-Through)

Item Number in 

GALL Description 

IV.D2.1 Pressure boundary and structural 

IV.D2.1.1 Upper and lower heads 

IV.D2.1.2 Tube sheets 

IV.D2.1.3 Primary nozzles and safe ends 

IV.D2.1.4 Shell assembly 

IV.D2.1.5 Feedwater and auxiliary feedwater nozzles and safe ends 

IV.D2.1.6 Steam nozzles and safe ends 

IV.D2.1.7 Primary side drain nozzles 

IV.D2.1.8 Secondary side nozzles (vent, drain, and instrumentation) 

IV.D2.1.9 Primary manways (cover and bolting) 

IV.D2.1.1 0 Secondary manways and handholes (cover and bolting) 

IV.D2.2 Tube bundle 

IV.D2.2.1 Tubes and sleeves 

IV.D2.2.2 Tube plugs

April 2001 A-17 NUREG-1801
List of Item Numbers in the GALL Report 

V.A. Containment Spray System (PWR) 

Item Number in 

GALL Description 

V.A.1 Piping, fittings and miscellaneous items 

V.A.1.1 Piping and fittings up to isolation valve 

V.A.1.2 Flow orifice/elements 

V.A. 1.3 Temperature elements/indicators 

V.A.1.4 Bolting 

V.A.1.5 Eductors 

V.A.2 Headers and spray nozzles 

V.A.2.1 Piping and fittings 

V.A.2.2 Flow orifice 

V.A.2.3 Headers 

V.A.2.4 Spray nozzles 

V.A.3 Pumps 

V.A.3.1 Bowl/casing 

V.A.3.2 Bolting 

V.A.4 Valves (hand, control, check, motor-operated, and containment isolation) in 

containment spray system 

V.A.4.1 Body and bonnet 

V.A.4.2 Bolting V.A.5 Valves (hand, control, and containment isolation) in headers and spray nozzles 

V.A.5.1 Body and bonnet 

V.A.5.2 Bolting 

V.A.6 Containment spray heat exchanger 

V.A.6.1 Bonnet/cover 

V.A.6.2 Tubing 

V.A.6.3 Shell 

V.A.6.4 Case/cover 

V.A.6.5 Bolting

NUREG-1801 A-1 8 April 2001
List of Item Numbers in the GALL Report 

V.B. Standby Gas Treatment System (BWR)

Item Number 

in GALL Description 

V.B1 Ductwork 

V.B.1.1 Duct fittings, access doors, and closure bolts 

V.B.1.2 Equipment frames and housing 

V.B.1.3 Seals between ducts and fan 

V.B.1.4 Seals in dampers and doors 

V.B.2 Filters 

V.B.2.1 Housing and supports 

V.B.2.2 Elastomer seals 

List of Item Numbers in the GALL Report 

V.C. Containment Isolation Components 

Item Number in 

GALL Description 

V.C.1 Isolation barriers 

V.C.1.1 Valve body and bonnet 

V.C.1.2 Pipe penetrations

April 2001 A-1 9 NUREG-1801
List of Item Numbers in the GALL Report 

V.D1. Emergency Core Cooling System (PWR)

Item Number 

in GALL Description 

V.Dl.1 Piping and fittings 

V.D1.1.1 Core flood system (CFS) 

V.D1.1.2 Residual heat removal (RHR) or shutdown cooling (SDC) 

V.D1.1.3 High-pressure safety injection (HPSI) 

V.D1.1.4 Low-pressure safety injection (LPSI) 

V.D1.1.5 Connecting lines to chemical and volume control system (CVCS) and spent fuel pool (SFP) cooling 

V.D1.1.6 Lines to emergency sump 

V.D1.1.7 Bolting for flange connections 

V.D1.2 HPSI and LPSI pumps 

V.D1.2.1 Bowl/casing 

V.D1.2.2 Bolting 

V.D1.2.3 Orifice 

V.D1.3 Refueling water tank (RWT) circulation pump 

V.D1.3.1 Bolting 

V.D1.4 Valves 

V.D1.4.1 Body and bonnet 

V.D1.4.2 Bolting 

V.D1.5 Heat exchangers (RCP, HPSI and LPSI pump seals, and RHR or SDC) 

V.D1.5.1 Bonnet/cover 

V.D1.5.2 Tubing 

V.D1.5.3 Shell 

V.D1.5.4 Case/cover 

V.D1.5.5 Bolting 

V.D1.6 Heat exchangers (RWT heating) 

V.D1.6.1 Bonnet/cover 

V.D1.6.2 Tubing 

V.D1.6.3 Shell 

V.D1.6.4 Bolting 

V.D1.7 Safety injection tank (accumulator) 

V.D1.7.1 Shell 

V.D1.7.2 Manway 

V.D1.7.3 Penetrations/nozzles 

V.D1.8 Refueling water tank (RWT) 

V.D1.8.1 Shell 

V.D1.8.2 Manhole 

V.D1.8.3 Penetrations/nozzles 

V.D1.8.4 Bolting 

V.D1.8.5 Buried portion of tank

NUREG-1801 A-20 April 2001
List of Item Numbers in the GALL Report 

V.D2. Emergency Core Cooling System (BWR)

Item Number in 

GALL Description 

V.D2.1 Piping and Fittings 

V.02.1.1 High pressure coolant injection (HPCI) 

V.D2.1.2 Reactor core isolation cooling (RCIC) 

V.12.1.3 High-pressure core spray (HPCS) 

V.D2.1.4 Low-pressure core spray (LPCS) 

V.D2.1.5 Low-pressure coolant injection (LPCI) and residual heat removal (RHR) 

V.02.1.6 Lines to suppression chamber (SC) 

V.D2.1.7 Lines to drywell and suppression chamber spray system (DSCSS) 

V.D2.1.8 Automatic depressurization system (ADS) 

V.D2.1.9 Lines to HPCI and RCIC pump turbine 

V.D2.1.10 Lines from HPCI and RCIC pump turbines to condenser 

V.D2.2 Pumps (HPCS or HPCI main and booster, LPCS, LPCI or RHR, and RCIC) 

V.D2.2.1 Bowl/casing 

V.D2.2.2 Suction head 

V.D2.2.3 Discharge head 

V.D2.3 Valves (check, control, hand, motor operated, and relief valves) 

V.D2.3.1 Body and bonnet 

V.D2.4 Heat exchangers (RHR and LPCI) 

V.D2.4.1 Tubes 

V.D2.4.2 Tubesheet 

V.D2.4.3 Channel head 

V.D2.4.4 Shell 

V.D2.5 Drywell and suppression chamber spray system (DSCSS) 

V.12.5.1 Piping and fittings 

V.12.5.2 Flow orifice 

V.02.5.3 Headers 

V.D2.5.4 Spray nozzles 

List of Item Numbers in the GALL Report 

V.E. Carbon Steel Components 

Item Number 

in GALL Description 

V.E.1 Carbon steel components 

V.E.11.1 External surfaces 

V.E.2 Closure bolting 

V.E.2.1 In high-pressure or high-temperature systems

April 2001 A-21 NUREG-1801
List of Item Numbers in the GALL Report VI.A. Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements 

Item Number 

in GALL Description 

VI.A.1 Conductor insulation 

VI.A.1.1 Electrical cables and connections exposed to an adverse localized environment 

caused by heat, radiation, or moisture 

VI.A.1.2 Electrical cables used in instrumentation circuits that are sensitive to reduction in 

conductor insulation resistance (IR) exposed to an adverse localized environment 

caused by heat, radiation, or moisture 

VI.A.1.3 Inaccessible medium-voltage (2 kV to 15 kV) cables (e.g., installed in conduit or direct 

buried) exposed to an adverse localized environment caused by exposure to 

I moisture and voltage 

VI.A.2 Connector contacts 

VI.A.2.1 Electrical connectors exposed to borated water leakage 

List of Item Numbers in the GALL Report 

VI.B. Equipment Subject to 10 CFR 50.49 

Environmental Qualification Requirements 

Item Number 

in GALL Description 

VI.B.1 Equipment subject to 10 CFR 50.49 environmental qualification requirements 

VI.B.1.1 Electrical equipment subject to 10 CFR 50.49 environmental qualification (EQ) 

requirements

NUREG-1801 A-22 April 2001
List of Item Numbers in the GALL Report 

VII.A1. New Fuel Storage

Item Number in 

GALL Description 

VII.A1.1 New fuel rack 

VII.A1.1.1 New fuel rack assembly 

List of Item Numbers in the GALL Report 

VII.A2. Spent Fuel Storage 

Item Number in 

GALL Description 

VII.A2.1 Spent fuel storage rack 

VIL.A2.1.1 Neutron-absorbing sheets 

VII.A2.11.2 Storage rack 

List of Item Numbers in the GALL Report 

VII.A3. Spent Fuel Pool Cooling and Cleanup (PWR) 

Item Number in 

GALL Description 

VII.A3.1 Piping 

VII.A3.1.1 Closure bolting 

VILA3.2 Filter 

VII.A3.2.1 Housing 

VII.A3.2.2 Closure bolting 

VII.A3.2.3 Elastomer lining 

VII.A3.3 Valves (check and hand valves) 

VII.A3.3.1 Body and bonnet 

VII.A3.3.2 Closure bolting 

VII.A3.3.3 Elastomer lining (hand valves only) 

VII.A3.4 Heat exchanger 

VII.A3.4.1 Shell and access cover 

VII.A3.4.2 Channel head and access cover 

VII.A3.4.3 Closure bolting 

VII.A3.5 Ion exchanger 

VII.A3.5.1 Shell 

VILA3.5.2 Nozzles 

VILA3.5.3 Closure bolting 

VII.A3.5.4 Elastomer lining 

VILA3.6 Pump 

VII.A3.6.1 Closure bolting

April 2001 A-23 NUREG-1801
List of Item Numbers in the GALL Report 

VILA4. Spent Fuel Pool Cooling and Cleanup (BWR)

List of Item Numbers in the GALL Report 

VII.A5. Suppression Pool Cleanup System (BWR) 

See Evaluation Summary, page VII A5- 1, in Volume 2 of the GALL report (NUREG- 1801, 

March 2001). 

List of Item Numbers in the GALL Report 

VII.B. Overhead Heavy Load and 

Light Load (Related to Refueling) Handling Systems 

Item Number in 

GALL Description VII.B.1 Cranes including bridge and trolley (for cranes that fall within the scope of 10 

CFR 54) 

VII.B.1.1 Structural girders 

VII.B.2 Rail system 

VlI.B.2.1 Rail

NUREG-1801

Item Number in 

GALL Description 

VII.A4.1 Piping 

VII.A4.1.1 Piping, fittings, and flanges 

VII.A4.2 Filter 

VII.A4.2.1 Housing 

VII.A4.2.2 Elastomer lining 

VII.A4.3 Valves (check and hand valves) 

VII.A4.3.1 Body and bonnet 

VII.A4.3.2 Elastomer lining (hand valves only) 

VII.A4.4 Heat exchanger 

VII.A4.4.1 Shell and access cover 

VII.A4.4.2 Channel head and access cover 

VII.A4.4.3 Tubes 

VII.A4.4.4 Tubesheet 

VII.A4.5 Ion exchanger 

VII.A4.5.1 Shell 

VII.A4.5.2 Nozzles 

VII.A4.5.3 Elastomer lining 

VII.A4.6 Pump 

VII.A4.6.1 Casing

A-24 April 2001
List of Item Numbers in the GALL Report 

VII.C1. Open-Cycle Cooling Water System (Service Water System)

Item Number in 

GALL Description 

VII.C1.1 Piping 

VII.C1.1.1 Piping and fittings 

VII.C1.1.2 Underground piping and fittings 

VII.C1.2 Valves 

VII.C1.2.1 Body and bonnet 

VII.C1.3 Heat exchanger 

VII.C1.3.1 Shell 

VII.C1.3.2 Channel 

VII.C1.3.3 Channel head and access cover 

VII.C1.3.4 Tubesheet 

VII.C1.3.5 Tubes 

VII.C1.4 Flow orifice 

VII.C1.4.1 Body 

VII.C1.5 Pump 

VII.C1.5.1 Casing 

VII.C1.6 Basket strainer 

VII.C1.6.1 Body 

List of Item Numbers in the GALL Report 

VII.C2. Closed-Cycle Cooling Water System 

Item Number in 

GALL Description 

VII.C2.1 Piping 

VII.C2.1.1 Pipe, fittings, and flanges 

VII.C2.2 Valves (check, hand, control, relief, solenoid, and containment isolation 

valves) 

VII.C2.2.1 Body and bonnet 

VII.C2.3 Pump 

VII.C2.3.1 Casing 

VII.C2.4 Tank 

VII.C2.4.1 Shell 

VII.C2.5 Flow orifice 

VII.C2.5.1 Body

April 2001 A-25 NUREG-1801
List of Item Numbers in the GALL Report 

VII.C3. Ultimate Heat Sink

Item Number in 

GALL Description 

VII.C3.1 Piping 

VII.C3.1.1 Piping and fittings 

VII.C3.2 Valves (check, hand, and control valves) 

VII.C3.2.1 Body and bonnet 

VII.C3.3 Pump 

VII.C3.3.1 Casing 

List of Item Numbers in the GALL Report 

VII.D. Compressed Air System 

Item Number in 

GALL Description 

VII.D.1 Piping 

VII.D.1.1 Piping and fittings 

VII.D.1.2 Closure bolting 

VII.D.2 Valves (including check valves and containment isolation valves) 

VII.D.2.1 Body and bonnet 

VII.D.2.2 Closure bolting 

VII.D.3 Air receiver 

VII.D.3.1 Shell and access cover 

VII.D.3.2 Closure bolting 

VII.D.4 Pressure regulators 

VII.D.4.1 Body and bonnet 

VII.D.5 Filter 

VlI.D.5.1 Shell and access cover 

VII.D.5.2 Closure bolting 

VII.D.6 Dryer 

VII.D.6.1 Shell and access cover 

VII.D.6.2 Closure bolting

NUREG-1801 A-26 April 2001
List of Item Numbers in the GALL Report 

VII.El. Chemical and Volume Control System (PWR)

Item Number in 

GALL Description 

VII.El.1 High-pressure piping (1,500 psig rating) 

VII.E1 .1.1 Pipe, fittings, and flanges 

VII.E1.1.2 Closure bolting 

VII.E1.2 Low-pressure piping (150 psig rating) 

VII.E1.2.1 Closure bolting 

VII.E1.3 High-pressure valves (check, control, hand, motor-operated, pressure 

control, and relief valves) 

VII.E1.3.1 Body and bonnet 

VII.E1.3.2 Closure bolting 

VII.E1.4 Low-pressure valves (check, control, hand, motor-operated, pressure 

control, and relief valves) 

VII.E1.4.1 Closure bolting 

VII.E1.5 High-pressure pump 

VII.E1.5.1 Casing 

VII.E1.5.2 Closure bolting 

VII.E1.6 Low-pressure pump 

VII.E1.6.1 Closure bolting 

VII.E1.7 Regenerative heat exchanger 

VII.E1.7.1 Channel head and access cover 

VII.E1.7.2 Tubesheet 

VII.E1.7.3 Tubes 

VII.E1.7.4 Shell and access cover 

VII.E1.7.5 Closure bolting 

VII.E1.8 Letdown heat exchanger 

VII.E1.8.1 Channel head and access cover 

VII.E1.8.2 Tubesheet 

VII.E1.8.3 Tubes 

VII.E1.8.4 Shell and access cover 

VII.E1.8.5 Closure bolting 

VII.E1.9 Basket strainers 

VII.E1.9.1 Closure bolting 

VII.E1.10 Volume control tank 

VII.E1.1 0.1 Closure bolting

April A-27 NUREG-1801 2001
List of Item Numbers in the GALL Report 

VII.E2. Standby Liquid Control System (BWR)

Item Number in 

GALL Description 

VII.E2.1 Piping 

VII.E2.1.1 Piping and fittings 

VII.E2.2 Solution storage 

VIL.E2.2.1 Tank 

VII.E2.2.2 Tank heaters 

VII.E2.3 Valves (pump suction, relief, injection, containment isolation, and explosive 

actuated discharge valves) 

VII.E2.3.1 Body and bonnet 

VII.E2.4 Injection pumps 

VII.E2.4.1 Casing 

List of Item Numbers in the GALL Report 

VII.E3. Reactor Water Cleanup System (BWR) 

Item Number in 

GALL Description 

VILE3.1 Piping 

VII.E3.1.1 Piping and fittings (beyond second isolation valves) 

VII.E3.2 Reactor water cleanup (RWCU) pump 

VIL.E3.2.1 Casing 

VII.E3.3 Regenerative heat exchanger 

VII.E3.3.1 Channel head and access cover 

VII.E3.3.2 Tubesheet 

VII.E3.3.3 Tubes 

VII.E3.3.4 Shell and access cover 

VII.E3.4 Nonregenerative heat exchanger 

VII.E3.4.1 Channel head and access cover 

VII.E3.4.2 Tubesheet 

VII.E3.4.3 Tubes 

VII.E3.4.4 Shell and access cover

NUREG-1801 A-28 April 2001
List of Item Numbers in the GALL Report 

VII.E4. Shutdown Cooling System (Older BWR)

Item Number in 

GALL Description 

VII.E4.1 Piping 

VII.E4.1.1 Piping and fittings 

VII.E4.2 Pump 

VII.E4.2.1 Casing 

VII.E4.3 Valves (check, control, hand, motor-operated, and relief valves) 

VII.E4.3.1 Body and bonnet 

VII.E4.4 Heat Exchanger 

VII.E4.4.1 Channel head and access cover 

VII.E4.4.2 Tubesheet 

VII.E4.4.3 Tubes 

VII.E4.4.4 Shell and access cover 

List of Item Numbers in the GALL Report 

VII.1F1. Control Room Area Ventilation System 

Item Number in 

GALL Description 

VII.F1.1 Duct 

VII.F1.1.1 Duct fittings, access doors, and closure bolts 

VII.F1.1.2 Equipment frames and housing 

VII.F1.1.3 Flexible collars between ducts and fans 

VII.F17.1.4 Seals in dampers and doors 

VII.F1.2 Air handler heatingicooling 

VII.F1.2.1 Heating/cooling coils 

VII.F1.3 Piping 

VII.F1.3.1 Piping and fittings 

VII.F1.4 Filters 

VII.F17.4.1 Housing and supports 

VII.F17.4.2 Elastomer seals

April 2001 A-29 NUREG-1801
List of Item Numbers in the GALL Report 

VII.F2. Auxiliary and Radwaste Area Ventilation System

Item Number in 

GALL Description 

VII.F2.1 Duct 

VII.F2.1.1 Duct fittings, access doors, and closure bolts 

VII.F2.1.2 Equipment frames and housing 

VII.F2.1.3 Flexible collars between ducts and fans 

VII.F2.1.4 Seals in dampers and doors 

VII.F2.2 Air handler heating/cooling 

VII.F2.2.1 Heating/cooling coils 

VII.F2.3 Piping 

VII.F2.3.1 Piping and fittings 

VII.F2.4 Filters 

VII.F2.4.1 Housing and supports 

VII.F2.4.2 Elastomer seals 

List of Item Numbers in the GALL Report 

VII. F3. Primary Containment Area Ventilation System 

Item Number in 

GALL Description 

VII.F3.1 Duct 

VII.F3.1.1 Duct fittings, access doors, and closure bolts 

VII.F3.1.2 Equipment frames and housing 

VII.F3.1.3 Flexible collars between ducts and fans 

VII.F3.1.4 Seals in dampers and doors 

VII.F3.2 Air handler heating/cooling 

VII.F3.2.1 Heating/cooling coils 

VII.F3.3 Piping 

VII.F3.3.1 Piping and fittings 

VII.F3.4 Filters 

VII.F3.4.1 Housing and supports 

VII.F3.4.2 Elastomer seals

NUREG-1801 A-30 April 2001
List of Item Numbers in the GALL Report 

VII.F4. Diesel Generator Building Ventilation System

Item Number in 

GALL Description 

VII.F4.1 Duct 

VII.F4.1.1 Duct fittings, access doors, and closure bolts 

VII.F4.1.2 Equipment frames and housing 

VII.F4.1.3 Flexible collars between ducts and fans 

VII.F4.1.4 Seals in dampers and doors 

VII.F4.2 Air handler heating/cooling 

VII.F4.2.1 Heating/cooling coils 

VII.F4.3 Piping 

VII.F4.3.1 Piping and fittings 

List of Item Numbers in the GALL Report 

VII.G. Fire Protection 

Item Number in 

GALL Description 

VII.G.1 Intake structure 

VII.G.1.1 Fire barrier penetration seals 

VII.G.1.2 Fire barrier walls, ceilings, and floors 

VII.G.1.3 Fire rated doors 

VII.G.2 Turbine building 

VII.G.2.1 Fire barrier penetration seals 

VII.G.2.2 Fire barrier walls, ceilings, and floors 

VII.G.2.3 Fire rated doors 

VII.G.3 Auxiliary building 

VII.G.3.1 Fire barrier penetration seals 

VII.G.3.2 Fire barrier walls, ceilings, and floors 

VII.G.3.3 Fire rated doors 

VII.G.4 Diesel generator building 

VII.G.4.1 Fire barrier penetration seals 

VII.G.4.2 Fire barrier walls, ceilings, and floors 

VII.G.4.3 Fire rated doors 

VII.G.5 Primary containment 

VII.G.5.1 Fire barrier walls, ceilings, and floors 

VII.G.5.2 Fire rated doors 

VII.G.6 Water-based fire protection system 

VII.G.6.1 Piping and fittings 

VII.G.6.2 Filter, fire hydrants, mulsifier, pump casing, sprinkler, strainer, and valve bodies 

(including containment isolation valves) 

VII.G.7 Reactor coolant pump oil collection system 

VII.G.7.1 Tank 

VII.G.7.2 Piping, tubing, and valve bodies 

VII.G.8 Diesel fire system 

VII.G.8.1 Diesel-driven fire pump and fuel supply line

April 2001 A-31 NUREG-1801
List of Item Numbers in the GALL Report 

VII.H1. Diesel Fuel Oil System 

Item Number in 

GALL Description VII.H1.1 Piping 

VII.H1-.1.1 Aboveground pipe and fittings VlI.H1-.1.2 Underground pipe and fittings 

VII.H1.2 Valves 

VII.H1-.2.1 Body and bonnet 

VIL.H1.2.2 Closure bolting 

VII.H1.3 Pump 

VII.H1.3.1 Casing 

VII.H1.3.2 Closure bolting 

VII.H1.4 Tank 

VII.H1-.4.1 Internal surfaces 

Vll.H1.4.2 External surfaces 

List of Item Numbers in the GALL Report 

VII.H2. Emergency Diesel Generator System 

Item Number in 

GALL Description VII.H2.1 Diesel engine cooling water subsystem 

VII.H2.1.1 Pipe and fittings 

VII.H2.2 Diesel engine starting air subsystem VII.H2.2.1 Pipe and fittings VII.H2.2.2 Valves (hand and check) 

VII.H2.2.3 Drain trap VII.H2.2.4 Air accumulator vessel 

VII.H2.3 Diesel engine combustion air intake subsystem 

VII.H2.3.1 Piping and fittings 

VII.H2.3.2 Filter VII.H2.3.3 Muffler 

VII.H2.4 Diesel engine combustion air exhaust subsystem VII.H2.4.1 Piping and fittings 

VII.H2.4.2 Muffler 

VII.H2.5 Diesel engine fuel oil subsystem 

VII.H2.5.1 Tanks (day and drip)

NUREG-1 801 April 2001 A-32
List of Item Numbers in the GALL Report 

VIl.L Carbon Steel Components

Item Number in 

GALL Description 

VII.I.1 Carbon steel components 

VIl.l.1.1 External surfaces 

VII.I.2 Closure bolting 

VII.I.2.1 In high-pressure or high-temperature systems 

List of Item Numbers in the GALL Report 

VIII.A. Steam Turbine System 

Item Number in 

GALL Description 

VIII.A.1 Piping and fittings 

VIII.A.1.1 High-pressure (HP) turbine to moisture separator/reheater (MSR) 

VIII.A.1.2 MSR to low-pressure (LP) turbine 

VIII.A.2 Valves (stop, control or governor, intermediate stop and control or combined 

intermediate, bypass or steam dumps, atmospheric dumps, main steam 

safety, or safety/relief) 

VIII.A.2.1 Body and bonnet 

List of Item Numbers in the GALL Report 

VIII.B1. Main Steam System (PWR) 

Item Number in 

GALL Description 

VIII.B1.1 Piping and fittings 

VIII.B13.1.1 Steam lines from steam generator to isolation valves (Group B or C) 

VIII.B13.1.2 Steam lines from isolation valves to main turbine (Group D) 

VIII.B1 .1.3 Lines to feedwater (FW) and auxiliary feedwater (AFW) pump turbines 

VIII.B1 .1.4 Lines to moisture separator/reheater (MSR) 

VIII.B13.1.5 Turbine bypass 

VVIII.B1.1.6 Steam drains 

VIII.B1.2 Valves (check, control, hand, motor operated, safety, and containment 

isolation valves) 

ViII.B1.2.1 Body and bonnet

April 2001 A-33 NUREG-1801
List of Item Numbers in the GALL Report 

VIII.B2. Main Steam System (BWR) 

Item Number in 

GALL Description 

VIII.B2.1 Piping and fittings 

VIII.B2.1.1 Steam lines to main turbine (Group B) 

VIII.B2.1.2 Steam lines to main turbine (Group D) 

VIII.B2.1.3 Lines to FW pump turbines 

VIII.B2.1.4 Turbine bypass 

VIII.B2.1.5 Steam drains 

VIII.B2.1.6 Steam line to HPCI turbine 

VIII.B2.1.7 Steam line to RCIC turbine 

VIII.B2.2 Valves (check, control, hand, motor-operated, and safety valves) 

VIII.B2.2.1 Body and bonnet 

List of Item Numbers in the GALL Report 

VIII.C. Extraction Steam System 

Item Number in 

GALL Description 

VIII.C.1 Piping and fittings 

VIII.C.1.1 Lines to feedwater heaters 

VIII.C.1.2 Steam drains 

VIII.C.2 Valves 

VIII.C.2.1 Body and bonnet 

List of Item Numbers in the GALL Report 

VIII.D1. Feedwater Systems (PWR) 

Item Number in 

GALL Description 

VIII.D1.1 Main feedwater line 

VIII.D1.1.1 Pipe and fittings (Group B, C, or D) VIII.D1.2 Valves (control, check, hand, safety, and containment isolation valves) 

VIII.D1.2.1 Body and bonnet 

VIII.D1.3 Feedwater pump (steam turbine and motor driven) 

VIII.D1.3.1 Casing 

VIII.D1.3.2 Suction and discharge lines

NUREG-1801 A-34 April 2001
List of Item Numbers in the GALL Report 

VIII.D2. Feedwater Systems (BWR)

Item Number in 

GALL Description 

VIII.D2.1 Main feedwater line 

VIII.D2.1.1 Pipe and fittings (Group B or D) 

VIII.D2.2 Valves (control, check, and hand valves) 

VIII.D2.2.1 Body and bonnet 

VIII.D2.3 Feedwater pump (steam turbine and motor driven) 

VIII.D2.3.1 Casing 

VIII.D2.3.2 Suction and discharge lines 

List of Item Numbers in the GALL Report 

VIII.E. Condensate System 

Item Number in 

GALL Description 

VIII.E.1 Condensate lines 

VIII.E.1.1 Piping and fittings 

VIII.E.2 Valves 

VIII.E.2.1 Body and bonnet 

VIII.E.3 Condensate pumps (main and booster pumps) VIII.E.3.1 Casing 

VIII.E.4 Condensate coolers/condensers 

VIII.E.4.1 Tubes 

VIII.E.4.2 Tubesheet 

VIII.E.4.3 Channel head 

VIII.E.4.4 Shell 

VIII.E.5 Condensate storage 

VIII.E.5.1 Tank 

VIII.E.6 Condensate cleanup system 

VIII.E.6.1 Piping and fittings 

VIII.E.6.2 Demineralizer 

VIII.E.6.3 Strainer

April 2001 A-35 NUREG-1801
List of Item Numbers in the GALL Report 

VIII.F. Steam Generator Blowdown System (PWR)

Item Number in 

GALL Description 

VIII.F.1 Blowdown lines 

VIII.F.1.1 Pipe and fittings (Group B) 

VII.F.1.2 Pipe and fittings (Group D) 

VIII.F.2 Valves (including containment isolation valves) 

VIII.F.2.1 Body and bonnet 

VIII.F.3 Blowdown pump 

VIII.F.3.1 Casing 

VIII.F.4 Blowdown heat exchanger 

VIII.F.4.1 Tubes 

VIII.F.4.2 Tubesheet 

VIII.F.4.3 Channel head and access cover 

VIII.F.4.4 Shell and access cover 

List of Item Numbers in the GALL Report 

VIII.G. Auxiliary Feedwater (AFW) System (PWR) 

Item Number in 

GALL Description 

VIII.G.1 Auxiliary feedwater piping 

VIII.G.1.1 Pipe and fittings (above ground) 

VIII.G.1.2 Pipe and fittings (buried) 

VIII.G.2 AFW pumps (steam turbine and motor driven) 

VIII.G.2.1 Casing 

VIII.G.2.2 Suction and discharge lines 

VIII.G.3 Valves (control, check, hand, and containment isolation valves) 

VIII.G.3.1 Body and bonnet 

VIII.G.4 Condensate storage (emergency) 

VIII.G.4.1 Tank 

VIII.G.5 Bearing oil coolers (for steam turbine pump) 

VIII.G.5.1 Shell 

VIII.G.5.2 Tubes 

VIII.G.5.3 Tubesheet 

List of Item Numbers in the GALL Report 

VIII.H. Carbon Steel Components 

Item Number in 

GALL Description 

VIII.H.1 Carbon steel components 

VIII.H.1.1 External surfaces 

VIII.H.2 Closure bolting 

VIII.H.2.1 In high-pressure or high-temperature systems

NUREG-1801 A-36 April 2001
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1. REPORT NUMBER 

(2-89) NRCM (Assigned by NRC, Add Vol, Supp. Rev. 1102, and Addendum Nwftr, Nf any.) W01.3202 BIBLIOGRAPHIC DATA SHEET 

(See h7st s o t rs) NUREG-1801 

2. TITLE AND SUBTITLE Vol. 1 

Generic Aging Lessons Learned (GALL) Report S3. DATE REPORT PUBLISHED 

Summary M YEAR 

Jul y 2001 

4. FIN OR GRANT NUMBER 

5. AUTHOR(S) 6. TYPE OF REPORT 

Technical Guidance 

7. PERIOD COVERED (xtusive Dates) 

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region. U.S. NuclearRegulatory Commission, and mailing address; if Wrrtractor 

provide name and mailing address.) 

Division of Regulatory Improvement Programs 

Office of Nuclear Reactor Regulation 

U.S. Nuclear Regulatory Commission 

Washington D.C. 20555-0001

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC. type Same as abovel; if ontraco, provide NRC Dision. Office orRegion, U.S Nuclear Regulatory Commision, 

ard mailhng address.)

Same as above

10. SUPPLEMENTARY NOTES

11. ABSTRACT (Oo uao's or less) 

The Generic Aging Lessons Learned (GALL) report contains the staff's generic evaluation of the existing 

plant programs and documents the technical basis for determining where existing programs are adequate 

without modification and where existing programs should be augmented for the extended period of 

operation. The evaluation results documented in the GALL report indicate that many of the existing 

programs are adequate to manage the aging effects for particular structures or components for license 

renewal without change. The GALL report also contains recommendations on specific areas for which 

existing programs should be augmented for license renewal. 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 and that no further staff review is required. The focus of 

the staff review is on the augmented existing programs for license renewal. The incorporation of the GALL 

report information into the NUREG-1 800, "Standard Review Plan for Review of License Renewal 

Applications for Nuclear Power Plants," as directed by the Commission, should improve the efficiency of 

the license renewal process.

12. KEY WORDS/DESCRIPTORS a wors or re pras that wm assist researwers in ketiog owref m) 13. AVAILABIUTY STATEMENT 

License Renewal unlimited 

Ucense Renewal Applicant 14. SECURITY CLASSIFICATION 

License Renewal Application o Ppag) 

Aging Management Programs unclassified 

Time-limited Aging Analyses (,is Repor't) Aging Effects unclassified *Existing Programs 15. NUMBER OF PAGES 

16. PRICE

NRC FORM 335 (2-89)
Federal Recycling Program