NUREG-1832

Analysis of Public Comments on the 

Revised License Renewal Guidance 

Documents

Manuscript Completed: September 2005

Date Published: September 2005

Division of Regulatory Improvement Programs

Office of Nuclear Reactor Regulation

U.S. Nuclear Regulatory Commission

Washington, DC 20555-0001
NUREG-1832 ii September 2005

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September 2005 iii NUREG-1832

ABSTRACT

This report contains the staff’s analysis of the comments received on the draft license 

renewal guidance (LRG) documents. These LRG documents consist of: 

• Draft Generic Aging Lessons Learned (GALL) Report (NUREG-1801), Revision 1;

• Draft Standard Review Plan for License Renewal (NUREG-1800), Revision 1; and 

• Draft Regulatory Guide DG-1104, "Standard Format and Content for Applications to 

Renew Nuclear Power Plant Operating Licenses."

The staff proposed to update these LRG documents, which were previously published in 

2001 (each of which is referred to as Revision 0). The draft revisions of these LRG 

documents were issued for public comment on February 1, 2005 (70FR 5254). 

The staff’s analysis of these comments is presented in a tabular format and contained in 

the following appendices: 

• Appendix A addresses comments submitted by the Nuclear Energy Institute (NEI); 

• Appendix B addresses comments from the Advisory Committee on Reactor Safety; 

• Appendix C addresses comments from the participants at the license renewal public 

workshop held on March 2, 2005; 

• Appendix D addresses comments submitted by various stakeholders, such as the 

Union of Concerned Scientists (UCS), utilities, and private citizens; and

• Appendix E is a comparison of unique aging management review (AMR) line-items in 

the September 2005 revision of the GALL Report, to that presented in the January 

2005 Draft Revision of the GALL Report issued for public comment.

No comments were received on DG-1140, "Standard Format and Content for 

Applications to Renew Nuclear Power Plant Operating Licenses, dated January 2005.

The September 2005 version of these LRG documents (referred to as Revision 1) 

incorporated changes to the draft revision based on the information contain in this report.
NUREG-1832 iv September 2005

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September 2005 v NUREG-1832

TABLE OF CONTENTS

Page

Abstract.................................................................................................................................. iii

List of Contributors................................................................................................................. vii

Executive Summary............................................................................................................... ES-1

1 Introduction ...................................................................................................................... 1-1

1.1 Background............................................................................................................. 1-1

1.2 Organization of Report............................................................................................ 1-1

APPENDIX A: Disposition of NEI Comments 

A.1. Introduction ............................................................................................................. A-1

A.2. Evaluation and Disposition of Comments............................................................... A-1

APPENDIX B: Disposition of the Comments from the 520th Meeting of 

the NRC Advisory Committee on Reactor Safeguards 

(ACRS)

B.1. Introduction ............................................................................................................. B-1

B.2. Evaluation and Disposition of Comments............................................................... B-1

B.3. References.............................................................................................................. B-1

APPENDIX C: Disposition of Participant Comments from the License 

Renewal Public Workshop 

C.1. Introduction ............................................................................................................. C-1

C.2. Participant Affiliation ............................................................................................... C-1

C.3. Evaluation and Disposition of Comments............................................................... C-3

C.4. References.............................................................................................................. C-4

APPENDIX D: Disposition of Written Public Comments

D.1. Introduction ............................................................................................................. D-1

D.2. Origin of Written Public Comments ........................................................................ D-1

D.3. Evaluation and Disposition of Comments............................................................... D-1

APPENDIX E: Comparison of Unique Aging Management Reviews

(AMR) in the September 2005 revision of the GALL 

Report, to that Presented in the January 2005 Draft 

Revision of the GALL Report Issued for Public Comment

E.1. Purpose and Use of Comparison Table ................................................................. E-1
NUREG-1832 vi September 2005

LIST OF TABLES

 

Page

Table A.2.1 Disposition of NEI Comments on Chapter II of the GALL Report......... A 2.1-1

Table A.2.2 Disposition of NEI Comments on Chapter III of the GALL Report ....... A 2.2-1

Table A.2.3 Disposition of NEI Comments on Chapter IV of the GALL Report ....... A 2.3-1

Table A.2.4 Disposition of NEI Comments on Chapter V of the GALL Report ........ A 2.4-1

Table A.2.5 Disposition of NEI Comments on Chapter VI of the GALL Report ....... A 2.5-1

Table A.2.6 Disposition of NEI Comments on Chapter VII of the GALL Report ..... A 2.6-1

Table A.2.7 Disposition of NEI Comments on Chapter VIII of the GALL Report ..... A 2.7-1

Table A.2.8 Disposition of NEI Comments on Chapter IX of the GALL Report ....... A 2.8-1

Table A.2.9 Disposition of NEI Comments on Chapter X of the GALL Report ........ A 2.9-1

Table A.2.10 Disposition of NEI Electrical Comments on Chapter XI.E 

of the GALL Report ................................................................................ A 2.10-1

Table A.2.11 Disposition of NEI Mechanical Comments on Chapter XI.M 

of the GALL Report ................................................................................ A 2.11-1

Table A.2.12 Disposition of NEI Structural Comments on Chapter XI.S 

of the GALL Report ................................................................................ A 2.12-1

Table A.2.13 Disposition of NEI Comments on Chapter 2 of SRP-LR ...................... A 2.13-1

Table A.2.14 Disposition of NEI Comments on Chapter 3, Section 3.1 

of SRP-LR.............................................................................................. A 2.14-1

Table A.2.15 Disposition of NEI Comments on Chapter 3, Section 3.2, 

of SRP-LR.............................................................................................. A 2.15-1

Table A.2.16 Disposition of NEI Comments on Chapter 3, Section 3.3, 

of SRP-LR.............................................................................................. A 2.16-1

Table A.2.17 Disposition of NEI Comments on Chapter 3, Section 3.4, 

of SRP-LR.............................................................................................. A 2.17-1

Table A.2.18 Disposition of NEI Comments on Chapter 3, Section 3.5, 

of SRP-LR.............................................................................................. A 2.18-1

Table A.2.19 Disposition of NEI Comments on Chapter 3, Section 3.6, 

of SRP-LR.............................................................................................. A 2.19-1

Table A.2.20 Disposition of NEI Comments on Chapter 4, of SRP-LR...................... A 2.20-1

Table B Disposition of Comments from Transcript of 3/4/05 Review by

NRC Advisory Committee on Reactor Safeguards (ACRS) ................. B-3

Table C Disposition of Participant Comments from the

License Renewal Public Workshop....................................................... C-5

Table D Disposition of Written Public Comments............................................... D-3

Table E Aging Management Review Line-item Comparison.............................. E-3
September 2005 vii NUREG-1832

LIST OF CONTRIBUTORS 

License Renewal and Environmental Programs Section of Division of Regulatory 

Improvement Programs, Office of Nuclear Reactor Regulation

P.T. Kuo Program Director

S. Lee Section Chief

S. West Section Chief

J. Zimmerman Section Chief

J. Dozier Team Leader

K. Chang Mechanical Engineering

K. Cozens Materials Engineering 

G. Cranston Reactor Systems Engineering

D. Guha Systems Engineering

M. Heath Mechanical Engineering

S. Hoffman Mechanical Engineering

A. Hull Materials Engineering

K. Hsu Materials Engineering

M. Lintz Mechanical Engineering

K. Naidu Reactor Engineering

J. Rajan Mechanical Engineering

R. Subbaratnam Mechanical Engineering

T. Terry Civil Engineering

L. Tran Electrical Engineering

P. Wen Electrical Engineering

Office of Nuclear Reactor Regulation

T. Chan Section Chief

S. Coffin Section Chief

S. Jones Section Chief

R. Jenkins Section Chief

L. Lund Section Chief

R. Karas Section Chief

K. Manoly Section Chief

M. Mitchell Section Chief

J. Nakoski Section Chief

D. Terao Section Chief

S. Weerakkody Section Chief

H. Ashar Structural Engineering

S. Bailey Mechanical Engineering

T. Cheng Structural Engineering

R. Davis Materials Engineering

B. Elliot Materials Engineering

J. Fair Mechanical Engineering

G. Georgiev Materials Engineering

A. Keim Materials Engineering
NUREG-1832 viii September 2005

LIST OF CONTRIBUTORS (continued)

N. Iqbal Fire Protection Engineering

D. Jeng Structural Engineering

K. Karwoski Materials Engineering

C. Lauron Chemical Engineering

L. Lois Reactor Systems Engineering

Y. Li Mechanical Engineering

R. McNally Mechanical Engineering

J. Medoff Materials Engineering

D. Nguyen Electrical Engineering

A. Pal Electrical Engineering

K. Parczewski Chemical Engineering

J. Strnisha Mechanical Engineering

P. Shemanski Electrical Engineering

Office of Nuclear Regulatory Research

A. Hiser Section Chief

J. Vora Team Leader

J. Davis Materials Engineering

P. Kang Electrical Engineering

Parallax, Inc

A. Baione Team Leader

M. Bowman Mechanical Engineering

K. Larsen Technical Editing

E. Patel Mechanical Engineering

R. Wells License Engineering

Argonne National Laboratory

O. Chopra Team Leader

D. Diercks Materials Engineering

V. Shah Mechanical and Materials Engineering

S. Tam Materials Engineering
September 2005 ES-1 NUREG-1832

EXECUTIVE SUMMARY

OVERVIEW

On February 1, 2005 (70FR 5254), the Nuclear Regulatory Commission (NRC) announced the 

issuance and availability of the following license renewal guidance (LRG) documents for public 

comment:

• Draft Generic Aging Lessons Learned (GALL) Report (NUREG-1801), Revision 1;

• Draft Standard Review Plan for License Renewal (NUREG-1800), Revision 1; and 

• Draft Regulatory Guide DG-1104, "Standard Format and Content for Applications to Renew 

Nuclear Power Plant Operating Licenses."

These LRG documents describe methods acceptable to the staff for implementing the license 

renewal rule (10 CFR Part 54), as well as techniques used by the staff in evaluating applications 

for license renewal. The draft revision incorporated changes that reflected past precedents and 

other lessons learned since Revision 0, which were published in 2001. 

The draft revision of these LRG documents was issued for public comment on January 31, 

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

discuss comments. 

The staff has taken into consideration comments received as a result of the solicitation 

described above and incorporated its dispositions into the September 2005 versions of the LRG 

documents. There were no comments received on DG-1140.

This report provides the evaluation and disposition of public comments received by the NRC on 

the draft revision of license renewal guidance documents.
NUREG-1832 ES-2 September 2005

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September 2005 1-1 NUREG-1832

1. INTRODUCTION

1.1 BACKGROUND

On February 1, 2005 (70FR 5254), the Nuclear Regulatory Commission (NRC) announced the 

issuance and availability of the following license renewal guidance (LRG) documents:

• Draft Generic Aging Lessons Learned (GALL) Report (NUREG-1801), Revision 1;

• Draft Standard Review Plan for License Renewal (NUREG-1800), Revision 1; and 

• Draft Regulatory Guide DG-1104, "Standard Format and Content for Applications to Renew 

Nuclear Power Plant Operating Licenses."

These draft revision of the LRG documents describe methods acceptable to the staff for 

implementing the license renewal rule (10 CFR Part 54), as well as techniques used by the staff 

in evaluating applications for license renewals. These draft revision incorporated changes that 

reflected past precedents and other lessons learned since Revision 0, which were published in 

2001 (70 FR 5254).

The staff had previously made available to the public a draft preliminary version of portions of 

these LRG documents on September 31, 2004. These preliminary draft versions were also 

discussed in public meetings held on October 27, 2004 and December 1, 2004. Subsequently, 

these LRG documents were formally issued for public comment, as discussed above. After the 

documents were issued for public comment, the staff held a public workshop on March 2, 2005, 

to discuss the changes made to these documents and to facilitate gathering of public 

comments. The staff was especially interested in stakeholder comments that address the safety, 

effectiveness, and efficiency of the license renewal process.

1.2 ORGANIZATION OF REPORT

The staff’s analysis of these comments is presented in a tabular format and contained in the 

following appendices: 

• Appendix A addresses the specific written comments submitted by NEI; 

• Appendix B addresses the Advisory Committee on Reactor Safety comments, 

• Appendix C addresses the participant comments from the license renewal public workshop 

on March 2, 2005; 

• Appendix D addresses the written comments submitted by various stakeholders, such as 

the Union of Concerned Scientists, utilities, and private citizens; and

• Appendix E is a comparison of Unique Aging Management Reviews (AMR) in the 

September 2005 revision of the GALL Report, to that presented in the January 2005 Draft 

Revision of the GALL Report issued for public Comment.

No comments were received on DG-1140.
NUREG-1832 1-2 September 2005

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September 2005 A-1 NUREG-1832

APPENDIX A:

Disposition of NEI Comments

A.1. INTRODUCTION

The Nuclear Energy Institute (NEI) provided comments on the SRP-LR and the 

GALL Report during the public comment period. The complete text of the NEI 

comments may be found in ADAMS Accession No. ML050970288. The tables in this 

appendix provide a NEI comment summary, NEI basis, and NRC disposition for the 

comment.

A.2. EVALUATION AND DISPOSITION OF COMMENTS 

Tables in this appendix address each comment and are arranged to correspond to the individual 

section of the updated license renewal guidance documents and are identified uniquely. For 

example, Table A.2.1 contains the NEI comments relating to Chapter II of the GALL Report. The 

Comment Number (i.e., G.II-GC-1) identifies and provides additional information regarding the 

comment. The first digit indicates the document to which the comment pertains. For example 

"G" indicates the GALL Report and an "S" represents the SRP-LR. The next part of the identifier 

indicates the chapter to which the comment applies, such as "II" for chapter II, "III" for chapter 

III, etc. The next part of the identifier indicates the type of comment. For example GC indicates a 

generic comment that applies to several places in the document, and S indicates a specific 

comment to a particular portion of the document. The last part of the identifier is a sequence 

number to make each of the comment numbers unique. 

Additionally, within each table, the second column contains an item number column that 

provides the location in the document where the comment applies. For example, comment 

number G.II-GC-2 applies to GALL AMR line-items C-05 and C-42. The "Comment/Proposed 

Change" column provides a summary of the NEI comment. A summary of the comment is used 

in order to address similar comments that may be made by NEI in multiple places within the 

applicable section of the updated license renewal documents. The NEI basis is provided in the 

"Basis for Comment" column and the final column presents the staff’s disposition and evaluation 

of the comment.
Draft NUREG-1832 A-2 September 2005

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September 2005 A.2.1-1 NUREG-1832

Table A.2.1: Disposition of NEI Comments on Chapter II of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.II-GC-1 Several Composite Component 

Descriptions - The combination 

of some lines to produce generic 

lines resulted in 

structure/component descriptions 

that included all the components 

previously (GALL’01) listed in the 

individual lines. These 

comprehensive lists include 

components that do not apply to 

all system/structure tables. For 

example, in table II.B2.2 for Mark 

II BWR containments, line C-19 

addresses steel elements 

including "Drywell; torus; drywell 

head; embedded shell and sand 

pocket regions; drywell support 

skirt; torus ring girder; 

downcomers; emergency core 

cooling system (ECCS) suction 

header." Some of these 

components (e.g., torus and 

torus ring girder) are not 

applicable to Mark II BWR 

containments and may lead to 

confusion when comparing plant 

AMR results to this AMR lineitem of the GALL Report.

The compound names will 

create confusion because 

specific component types are 

listed in structures that don’t 

contain those components. The 

descriptions in the rolled up 

lines should be split to their 

original configuration so that the 

list of structural component 

types matches the structure

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. The 

line-items in the GALL Report were 

revised so that component type matched 

the containment type. New line-items 

were created in the GALL Report to make 

it consistent with the GALL’01 version.

C-01 becomes C-01, C-28, and C-29.

C-02 becomes C-02, C-30, C-31, and 

C-32.

C-03 becomes C-03, C-25, and C-27.

C-04 becomes C-04, C-38, C-39, and 

C-40.

C-05 becomes C-05, C-41, C-42, and 

C-43.

C-06 becomes C-06, C-36, and C-37.

C-08 becomes C-08, C-33, C-34, and 

C-35.

C-13 becomes C-13 and C-45.

C-14 becomes C-14 and C-44.

C-19 becomes C-19 and C-46.

C-20 becomes C-20 and C-47.

C-21 becomes C-21 and C-48

C-22 becomes C-22 and C-49.

The GALL Report was revised to address 

these proposed changes.

G.II-GC-2 C-05

C-42

NEI recommended in the AMP 

column be changed as follows:

Accessible Areas:

Inspections performed in 

accordance with IWL will indicate 

the presence of increase in 

porosity and permeability, 

cracking, loss of bond, and

NEI stated that incorrect aging 

mechanism listed under the 

AMP for the aging mechanism 

specified in the previous column 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 2).

The staff agreed with this comment. 

This was an error in the GALL Report. 

The GALL Report was revised to address 

the proposed changes for C-05, and the 

new items C-41, C-42, and C-43. These 

new items in the GALL Report were 

revised as follow:
NUREG-1832 A.2.1-2 September 2005

Table A.2.1: Disposition of NEI Comments on Chapter II of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

loss of material (spalling, scaling) 

due to aggressive chemical 

attack corrosion of embedded 

steel. 

"Inspections performed in accordance 

with IWL will indicate the presence of 

surface cracking, loss of bond, and loss of 

material (spalling, scaling) due to 

corrosion of embedded steel."

G.II.C-1 C-02 NEI proposed to eliminate the 

period in the AMP column under 

inaccessible areas.

It is a typo -eliminate "period" (.) 

This comment also applies to 

II.A2-3 (C-02) and II.B2.2-2, 

(C-02), II.B3.1-2 (C-02), II.B3.2-

3 (C-02). 

The staff agreed with this comment.

The GALL Report was revised to correct 

the typo.

G.II-C-2 C-08 NEI proposed delete "concrete 

fill in annulus" from Region of 

interest column.

NEI stated industry does not 

recognize this component in the 

PWRs Concrete Elements 

(Concrete Containments).

The staff agreed with this comment.

The GALL Report was revised to delete 

concrete fill in annulus for the concrete 

containment section. 

However, it is retained in the section 

pertaining to the Mark III containment. 

New line-items were created in the GALL 

Report. C-08 becomes C-08, C-33, C-34, 

and C-35.

G.II-C-3 C-04 NEI recommended the aging 

effect mechanism be changed as 

follows:

Expansion and c Cracking due 

to expansion/ reaction with 

aggregates

In the AMP column delete:

And replace with:

"As described in NUREG-1557, 

investigations, tests, and 

petrographic examinations of 

NEI proposed to change the 

aging effect/mechanism, so it 

will be consistent with previous 

GALL version.

The staff agreed with this comment. 

The staff agreed that the proposed 

changes to the aging effect/aging 

mechanism column and the AMP column 

are acceptable because it is identical to 

the GALL’01 version. 

The GALL Report was revised to address 

the proposed changes for C-04, and the 

new AMR line-items C-38, C-39, and 

C-40.
September 2005 A.2.1-3 NUREG-1832

Table A.2.1: Disposition of NEI Comments on Chapter II of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

aggregates performed in 

accordance with ASTM C295-54 

or ASTM C227-50 can 

demonstrate that those 

aggregates do not react within 

reinforced concrete. For 

potentially reactive aggregates, 

aggregate-reinforced concrete 

reaction is not significant if the 

concrete was constructed in 

accordance with ACI 201.2R-77.

Therefore, if these conditions are 

satisfied, aging management is 

not necessary."

G.II-C-4 C-05 NEI recommended the 

components and materials be 

changed as follows:

Dome; wall; basemat; ring 

girders; buttresses; reinforcing 

steel

Concrete; steel

NEI proposed the aging effect is 

for concrete not steel.

The staff did not agree with this comment. 

The staff did not agree with deleting 

reinforcing steel in component and steel 

in the material because the aging 

mechanism is corrosion of embedded 

steel.

The GALL Report was not revised to 

address these proposed changes.

G.II-C-5 C-09 NEI recommended the 

environment and aging 

effect/mechanism be changed as 

follows:

Air – indoor uncontrolled or air –

outdoor

Loss of material/ general, pitting, 

and crevice corrosion

NEI proposed that liners are 

only exposed to an air-indoor 

uncontrolled environment.

Loss of material due to pitting 

and crevice corrosion is not 

applicable for air – indoor 

uncontrolled environment. Air –

indoor uncontrolled environment 

is defined as a normally dry 

environment and crevice and 

The staff agreed with this comment. The 

GALL Report was revised to address the 

proposed changes since liners are not 

exposed to air-outdoor environment.

The staff did not agree with deleting

pitting and crevice in the aging 

effect/mechanism because it is not 

consistent with the GALL’01 version.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.1-4 September 2005

Table A.2.1: Disposition of NEI Comments on Chapter II of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

pitting occur in a wetted 

environment per GALL Chapter 

IX.

G.II-C-6 C-13

C-14

C-15

NEI recommended the 

environment be changed as 

follows:

Air – indoor uncontrolled or air 

outdoor

NEI stated this item component 

is same as II.A3-1 which lists 

"Air –indoor uncontrolled or air 

outdoor. 

The staff agreed with this comment.

The staff agreed that the comment as 

proposed is acceptable because it is 

identical to the GALL’01 version. 

The GALL Report was revised to address 

this proposed change.

G.II-C-7 C-23 NEI recommended the material 

be changed as follows:

Steel; Graphite plate

NEI proposed that the industry 

experience and EPRI Civil Tools 

indicate this aging effect is not 

applicable to graphite plate 

(Lubrite®). This is consistent 

with past approved applications. 

See NUREG-1759.

The staff agreed with this comment.

The GALL Report was revised to delete 

graphite plate since the aging effect of 

fretting or lockup is not applicable to 

graphite plate (or Lubrite®).

G.II-C-8 C-19 NEI recommended the 

environment be changed as 

follows: 

Air – indoor uncontrolled

or treated water (as applicable)

NEI proposed that add "or 

treated water" to environment 

column to account for the wetted 

portion of the torus and other 

components inside the torus.

The staff agreed with this comment. 

The GALL Report was revised to add or 

treated water since treated water is an 

applicable environment for the torus and 

other components inside the torus.

G.II-C-9 C-22 NEI recommended the 

component, material, 

environment, and aging 

effect/mechanism to be changed 

as follows:

Steel elements:

Vent line bellows

Suppression chamber liner 

(interior surface)

Steel or Stainless steel

Air – indoor uncontrolled

Add steel to account for 

suppression chamber with 

carbon steel liner.

Add treated water to account for 

the wetted portion of the 

suppression pool.

Add loss of material aging 

effect.

Delete cracking due to SCC 

The staff agreed with this comment with 

modifications.

The staff agreed with the change 

proposed by NEI for item II.B2.2.2-b 

(C-22), except that steel is not a material 

used for suppression chamber liner.

Change in component type was 

addressed by comment G.II-GC-1 above. 

A new AMR line-item C-49 was added to 

the GALL Report specifically to address 
September 2005 A.2.1-5 NUREG-1832

Table A.2.1: Disposition of NEI Comments on Chapter II of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

or treated water

Loss of material/ general, pitting, 

and crevice corrosion 

Cracking/ stress corrosion 

cracking

GALL AMP XI.S1 and GALL 

AMP XI.S4

because suppression chamber 

temperature is < 600C (< 1400F)

stainless steel suppression chamber liner 

in treated water with an aging effect for 

loss of material due to general, pitting and 

crevice corrosion. Cracking due to SCC is 

not an aging effect because the treated 

water in suppression chamber is < 600C 

(< 1400F).

The AMPs recommended are GALL AMP

XI.S1, "ASME Section XI, Subsection 

IWE,” and GALL AMP XI.S4, "10 CFR 

Part 50, Appendix J."
NUREG-1832 A.2.1-6 September 2005

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1): Composite Component Descriptions

The combination of some lines to produce generic lines resulted in structure/component descriptions that included the 

components previously (GALL’01) listed in the individual lines. These comprehensive lists include components that do not apply 

to system/structure tables. For example, in table II.B2.2 for Mark II BWR containments, line-itemC-19 addresses steel elements 

including "Drywell; torus; drywell head; embedded shell and sand pocket regions; drywell support skirt; torus ring girder; 

downcomers; ECCS suction header." Some of these components (e.g., torus and torus ring girder) are not applicable to Mark II 

BWR containments and may lead to confusion when comparing plant AMR results to this line-item of GALL.

The compound names will create confusion because specific component types are listed in structures that don’t contain those 

components. The descriptions in the rolled up lines should be split to their original configuration so that the list of structural 

component types matches the structure.

2. General Comment 2 (GC2): Mechanism/Program Mismatch

The aging mechanism in the "Aging Effect/Mechanism" column does not match with description in the "AMP" column for some 

lines. For example, item II.A2-7 calls out "corrosion of embedded steel" in mechanism but describes "aggressive chemical attack"

in AMP. Corrections have been proposed.
September 2005 A.2.2-1 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-1 All Items NEI recommended reducing the 

number of sub-sections from 9 to 3.

The tables of Chapter III for 

the various structures and 

component supports are 

highly repetitive.

To simplify these GALL 

tables, the nine structures 

tables have been 

consolidated into three 

tables. Tables A1, A2, A3, 

A4, A5, and A9 comprise a 

new Group 1 Structures 

Table; Table A6 becomes a 

new Group 2 Structures 

Table; and Tables A7 and A8 

are joined to become a new 

Group 3 Structures Table. 

Similarly, the three ASME 

piping supports tables B1.1, 

B1.2 and B1.3 are combined 

as a table for supports for 

ASME piping and 

components and Class MC 

(BWR Containment 

Supports); and the remaining 

four tables have been 

combined as a table for other 

supports (see also the 

endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff did not agree with this comment 

to reduce the number of sub-sections 

from 9 to 3 because it does not meet the 

requirements of 10 CFR 54.21a (1), and 

it is not consistent with the format of 

GALL Chapter II.

The GALL Report was not revised to 

address these proposed changes.
NUREG-1832 A.2.2-2 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-2a TP-10 NEI recommended the creation of 

new AMR line-items for aging effects 

and mechanisms of loss of 

material/general crevice, pitting 

corrosion of carbon and stainless 

steel supports members, welds, 

bolded connections, support 

anchorage to building structure in a 

treated water environment. The 

aging management program 

recommended by NEI was GALL 

AMP XI.M2 "Water Chemistry 

Program."

NEI stated that this new AMR 

line-item applies to cover 

BWR support components in 

treated water (see also the 

endnotes to this table for 

NEI’s presentation of general

comment 2).

The staff agreed with the proposed 

change. A treated water environment 

could be present in BWR 

torus/suppression pool. A new AMR lineitem TP-10 was added to GALL

Chapter IIIB1.

The staff agreed that the GALL AMP 

XI.M2 in the AMP column for this new 

AMR line-item was appropriate. The 

verification of water chemistry was 

added.

The GALL Report was revised to address 

these proposed changes.

G.III-GC-2b III.B2(1) NEI recommended the creation of 

new AMR line-items for aging effects 

and mechanisms of loss of 

material/general corrosion of 

galvanized steel supports members, 

welds, bolted connections, and 

support anchorage to building 

structure in an outdoor air 

environment. The aging 

management program 

recommended by NEI was GALL 

AMP XI.S6 "Structures Monitoring 

Program."

NEI stated that this past 

precedent was in the RNP

SER (NUREG 1785), where 

this material, environment, 

aging effect/mechanism, and 

aging management program 

(MEAP) combination was 

used. (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 2).

See G.III-C-9 below
September 2005 A.2.2-3 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-2c III.B2(2) NEI recommended the creation of 

new AMR line-items for aging effects 

and mechanisms of loss of material 

due to change in material properties 

of wood. The aging management 

program recommended by NEI was 

GALL AMP XI.S6 "Structures 

Monitoring Program," and GALL 

AMP XI.S7 RG, Inspection of WaterControlled Structures, or Plantspecific AMP."

NEI stated that this new AMR 

line-item was added to 

include component supports 

and water control structures, 

small dams and ponds, and 

power poles. This material is 

not in GALL (see also the 

endnotes to this table for 

NEI’s presentation of general 

comment 2).

The staff reviewed these components 

and did not agree to add this AMR lineitem because wood needs more criteria, 

it is too general, and also this MEAP 

combination would be plant-specific.

The GALL Report was not revised to 

address these proposed changes.

G.III-GC-3a T-05 NEI recommended the AMP be 

changed as follows:

Accessible Areas:

Inspections performed in accordance 

with SMPIWL will indicate the 

presence of increase in porosity and 

permeability, cracking, loss of bond, 

and or loss of material (spalling, 

scaling) due to corrosion of 

embedded steel aggressive 

chemical attack

NEI stated that dissimilar 

aging effects were identified 

in the AMP column and in the 

AE/M column (see also the 

endnotes to this table for 

NEI’s presentation of general 

comment 3).

The staff agreed with this comment. This 

was a typo that needed to be corrected.

The GALL Report was revised to address 

these proposed changes.

G.III-GC-3b T-02

T-05

NEI recommended the AMP be 

changed as follows:

GALL AMP XI.S26, "Structures 

Monitoring Program (SMP) ASME 

Section XI, Subsection IWL."

Accessible areas:

Inspections performed in accordance 

with IWL SMP will indicate the 

presence of increase in porosity, and 

permeability due to leaching of 

calcium hydroxide.

NEI proposed that IWL is for 

inspection of the reinforced 

concrete containment and is 

not used to inspect other 

structures. The SMP is 

utilized for the inspection of 

these other structures in the 

sections listed, which is 

consistent with previous 

versions of GALL (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 3).

The staff agreed that the NEI proposed 

change in AMP column is acceptable 

because it is identical with GALL’01 and 

IWL is used in containment, while 

Section III is associated with other Class 

1 and 2 structures. AMP GALL XI.S6 was 

revised also.

The GALL Report was revised to address 

these proposed changes.
NUREG-1832 A.2.2-4 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-4a T-18

T-19

NEI recommended the AMP be 

changed as follows:

Accessible Areas: Inspections 

performed in accordance with 

"Regulatory Guide 1.127, Inspection 

of Water-Control Structures 

Associated with Nuclear Power 

Plants" or the FERC/US Army Corp 

of Engineers dam inspections and 

maintenance or the Structures 

Monitoring Program will indicate the 

presence of increase in porosity and 

permeability, cracking, or loss of 

material (spalling, scaling) due to 

aggressive chemical attack.

Inaccessible Areas:

Examination of representative 

samples of below-grade concrete, 

when excavated for any reason, is to 

be performed, if the below-grade 

environment is aggressive (pH<5.5, 

chlorides>500ppm, or 

sulphates>1,500 ppm).

Periodic monitoring of below-grade 

water chemistry (including 

consideration of potential seasonal 

variations) is an acceptable 

approach to demonstrate that the 

below-grade environment is 

aggressive or non-aggressive.

NEI recommended the Further 

Evaluation be changed as follows:

NEI stated the text was not 

consistent with other sections 

of GALL because there was 

no discussion of accessible 

and inaccessible concrete. It 

is also not consistent with the 

NRC’s requirement in ISG-3 

and other sections of GALL

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 4).

The staff agreed that the text should be 

consistent with other structural sections 

of GALL and address accessible and 

inaccessible concrete. The staff agreed 

with the accessible concrete change, but 

did not agree with including SMP.

The staff has modified the inaccessible 

area write-up to appropriately address 

non-aggressive and aggressive 

environment as follows:

Inaccessible Areas:

For plants with non-aggressive ground 

water/soil; i.e. pH > 5.5, chlorides < 500 

ppm, or sulfates <1500 ppm, as a 

minimum, consider (1) Examination of 

the exposed portions of the below grade 

concrete, when excavated for any 

reason, and (2) Periodic monitoring of 

below-grade water chemistry, including 

consideration of potential seasonal 

variations. For plants with aggressive 

groundwater/soil, and/or where the 

concrete structural elements have 

experienced degradation, a plant-specific

AMP accounting for the extent of the 

degradation experienced should be 

implemented to manage the concrete 

aging during the period of extended 

operation

The staff agreed with this change 

because a plant-specific AMP is called 

out, and further evaluation is 
September 2005 A.2.2-5 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

Yes, if environment is aggressive recommended.

The GALL Report was revised to address 

these proposed changes.

G.III-GC-4b T-15

T-17

NEI recommended in the AMP 

column be changed as follows:

Inaccessible Areas:

Evaluation is needed for plants that 

are located in moderate to severe 

weathering conditions (weathering 

index > 100 day-inch/yr) (NUREG1557). Documented evidence to 

confirm that existing concrete has air 

content of 3% to 6%, and 

subsequent inspections did not 

exhibit degradation related to freezethaw, should be considered a part of 

the evaluation. The weathering index 

for the continental US are shown in 

ASTM C33-90, Fig.1.

NEI recommended the Further 

Evaluation be changed as follows:

No, if within the scope of the

applicant’s "Regulatory Guide 1.127, 

Inspection of Water-Control 

Structures Associated

with Nuclear Power Plants," the

FERC/US Army Corp of

Engineers dam inspections and

Maintenance or the Structures

Monitoring Program and stated

Conditions are satisfied for

Inaccessible areas

NEI stated the text was not 

consistent with other sections 

of GALL because there was

no discussion of accessible 

and inaccessible concrete. It 

is also not consistent with the 

NRC’s requirement in ISG-3 

and other sections of GALL

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 4).

The staff did not agree with the change 

because, for inaccessible areas, the staff 

prefers to retain entrained air and waterto-cement ratio. 

The GALL Report was not revised to 

address this proposed change.

The staff did not agree with this comment 

because the stated conditions are not 

satisfied. An evaluation is necessary and 

will have to be addressed in the 

application. However, the GALL AMP

XI.S7 was modified to address NEI 

concern. See Appendix A, Table A.2.12.
NUREG-1832 A.2.2-6 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-4c T-16 NEI recommended the AMP column 

be changed as follows:

Inaccessible Areas:

An aging management program is 

not necessary, even if reinforced 

concrete is exposed to flowing water, 

if there is documented evidence that 

confirms the in-place concrete was 

constructed in accordance with the 

recommendations in ACI 201.2R-77.

NEI recommended the Further 

Evaluation be changed as follows:

No, if concrete was constructed

as stated for inaccessible areas

NEI stated the text was not 

consistent with other sections 

of GALL because there was 

no discussion of accessible 

and inaccessible concrete. It 

is also not consistent with the 

NRC’s guidance in ISG-3 and 

other sections of GALL (see 

also the endnotes to this 

table for NEI’s presentation of 

general comment 4).

The staff did not agree with the comment 

because the existing words provide more 

information and a better explanation than 

the words proposed by NEI. The GALL 

Report was not changed as a result of 

this comment.

The staff did not agree with this comment

because the AMP description (above) 

was not changed. The GALL Report was 

not revised to address these proposed 

changes.
September 2005 A.2.2-7 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III-GC-4d T-03 NEI recommended that the AMP 

column be changed as follows:

Inaccessible Areas:

As described in NUREG-1557, 

investigations, tests, and 

petrographic examinations of 

aggregates performed in accordance 

with ASTM C295-54 or ASTM 

C227-50 can demonstrate that those 

aggregates do not react within 

reinforced concrete. For potentially 

reactive aggregates, aggregatereinforced concrete reaction is not 

significant if the concrete was 

constructed in accordance with 

ACI 201.2R-77.

Therefore, if these conditions are 

satisfied, aging management is not 

necessary.

Evaluation is needed if testing and 

petrographic examinations of 

aggregates performed in accordance 

with ASTM C295-54, ASTM C227-

50, or ACI 201.2R-77 (NUREG1557) demonstrate that the 

aggregates are reactive. 

NEI proposed the change in 

the AMP, so it will be 

consistent with previous 

GALL version (see also the 

endnotes to this table for 

NEI’s presentation of general 

comment 4).

The staff agreed that the NEI proposed 

changes in the AMP column are 

acceptable because they are identical to 

the original wording inGALL’01.

The GALL Report was revised to address 

these proposed changes.
NUREG-1832 A.2.2-8 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III.GC-5a T-15

T-16

T-17

T-18

T-19

T-20

T-21

T-22

NEI recommended to add another 

alternative program in the AMP 

column as follows:

GALL AMP XI.S6 "Structures 

Monitoring Program"

NEI proposed that this 

change recognizes that the 

Structures Monitoring 

Program (SMP) is also 

commonly used for aging 

management of concrete in 

the water control structures

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 5).

The staff did not agree with the proposed 

change in GALL AMP XI.S6, because the 

U.S. Army Corps of Engineers (COE) 

guidelines for water-control structures 

are very specific. The SMP is too 

general. However, staff agreed to provide 

this option in the description for GALL 

AMP XI.S7, provided that necessary 

elements of GALL AMP XI.S7 are 

addressed. GALL AMP XI.S7 was 

revised to address this change. See 

Appendix A, Table A.2.12 of this report. 

G.III-GC-5b T-12 NEI recommended the AMP be 

changed as follows: 

Note: May be part of GALL AMP

XI.S6 "Structures Monitoring 

Program"

NEI proposed that many 

plants use SMP for Masonry 

Wall (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 5).

The staff did not agree with adding GALL 

AMP XI.S6 SMP to the GALL AMP 

XI.S5.

The GALL AMP specific criteria are in

GALL AMP XI.S5 "Masonry Wall 

Program" and the existing program 

description in GALL AMP XI.S5 allows 

the use of SMP.

The GALL Report was not revised to 

address these proposed changes.

G.III.C-1 T-21 NEI recommended the environment 

be changed as follows:

Air – indoor uncontrolled or air –

outdoor

Water-flowing, water - standing

NEI proposed to add the 

environment for carbon steel 

in flowing or standing water 

for items such as sheet piles 

and gates.

The staff agreed with the proposed

change in description of environment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.2-9 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III.C-2 T-13 NEI recommended deletion of the 

aging effect/mechanism and aging 

management program, and state 

"None," "None" for both.

NEI stated the industry 

experience and EPRI Civil 

Tools indicates this aging 

effect is not applicable to 

graphite plate (Lubrite®).

The staff did not agree with deleting the 

aging effect/mechanism and AMP. 

Although, Lubrite® bearings are 

characterized as maintenance free, 

because of the differences in installation, 

fineness of the surfaces, and lubricant 

characteristics, they can be subjected to 

mechanical wear and fretting. Therefore, 

the staff recommends that they should be 

subjected to visual examinations to 

assess their condition and ensure that 

they will be able to perform their intended 

functions under normal operating and 

postulated seismic conditions.

The GALL Report was not revised to 

address these proposed changes.

G.III.C-3 T-14 NEI recommended the environment 

be changed as follows:

Treated water or treated borated 

water

NEI stated the treated water 

or treated borated water 

environment is a better 

description of spent fuel pool 

environment.

The staff agreed with the changes in the 

environment because treated water or 

treated borated water is a better 

description of the spent fuel pool 

environment.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.2-10 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III.C-4 T-27 NEI recommended adding another 

aging effect to the aging effect/aging 

mechanism column as follows:

Cracking/stress corrosion cracking

Loss of material/general corrosion

GALL AMP XI.M18, "Bolting 

Integrity" or GALL AMP XI.S3, 

"ASME Section XI, Subsection IWF"

NEI stated loss of material is 

also an applicable aging 

effect for this component, and 

IWF is also an adequate 

program for inspection of 

high strength bolting for the 

identified aging effects.

The staff agreed with the proposed 

changes. This is acceptable because the 

aging effect of cracking exists in 

GALL’01. A new AMR line-item TP-9 was 

created to address loss of material in the 

GALL Report to address this aging effect.

The GALL Report was revised to address 

this first proposed change.

The staff did not agree with the use of 

GALL AMP XI.S3 because the ASME 

program does not look at the shank of 

the bolt. The GALL Report was not 

revised to address this second proposed 

change.

G.III.C-5 T-28 NEI recommended the material be 

changed as follows:

Steel and non-steel materials (e.g., 

lubrite plates, vibration isolators, 

etc.)

NEI stated the industry 

experience and EPRI Civil 

Tools indicates this aging 

effect is not applicable to 

graphite plate (Lubrite®).

The staff did not agree with deleting 

Lubrite® plates. Although, Lubrite®

bearings are characterized as 

maintenance free, because of the 

differences in installation, fineness of the 

surfaces, and lubricant characteristics, 

they can be subjected to mechanical 

wear and fretting. Therefore, the staff

recommends that they should be 

subjected to visual examinations to 

assess their condition and ensure that 

they will be able to perform their intended 

functions under normal operating and 

postulated seismic conditions.

The GALL Report was not revised to 

address these proposed changes.
September 2005 A.2.2-11 NUREG-1832

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III.C-6 T-30 NEI recommended the environment 

be changed as follows:

Air – indoor uncontrolled (External)

or air-outdoor

NEI stated add air-outdoor to 

account for components 

located outdoors such as 

platforms, instrument racks, 

and electrical enclosures.

The staff agreed with the proposed 

change because it would provide for 

proper aging management for 

components for indoor or outdoor

environments.

The GALL Report was revised to address 

these proposed changes.

G.III.C-7 TP-1 NEI recommended the deletion of 

this AMR line-item.

NEI stated the industry 

experience and EPRI Civil 

Tools indicates this aging 

effect is not applicable to 

graphite plate (Lubrite®).

The staff did not agree with deleting this 

AMR line-item. Although, Lubrite®

bearings are characterized as 

maintenance free, because of the 

differences in installation, fineness of the 

surfaces, and lubricant characteristics, 

they can be subjected to mechanical 

wear and fretting. Therefore, the staff 

recommends that they be subjected to 

visual examinations to assess their 

condition and ensure that they will be 

able to perform their intended functions 

under normal operating and postulated 

seismic conditions.

The GALL Report was not revised to 

address these proposed changes.

G.III.C-8 TP-5

See new 

item TP-11

NEI recommended the material 

be changed as follows:

Galvanized steel, Stainless steel

NEI stated this is based on a

past precedent (RNP SER 

NUREG 1785).

The staff agreed that the proposed

changes in the material are acceptable 

because galvanized steel can be used in 

these applications, and no aging effects 

are expected in this indoor environment. 

A new AMR line-item TP-11 was created.
NUREG-1832 A.2.2-12 September 2005

Table A.2.2: Disposition of NEI Comments on Chapter III of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.III.C-9 TP-6 NEI recommended the material and 

aging effect/mechanism 

be changed as follows:

Galvanized steel, Aluminum, 

stainless steel

Loss of material/ pitting and crevice 

corrosion

NEI stated this is based on a

past precedent (RNP SER 

NUREG 1785).

NEI had proposed a new 

AMR line-item be added for 

galvanized steel.

The staff did not agree with this comment 

because galvanized steel in an outdoor 

environment is subject to aging effects. 

Also, pitting and crevice corrosion are 

aging mechanisms associated with these 

materials in an outdoor environment. 

The GALL Report was not revised to 

address these proposed changes.

G.III.C-10 TP-8 NEI recommended the aging 

effect/mechanism and aging 

management program be changed 

as follows:

Loss of material/ galvanic corrosion

None

GALL AMP XI.S6, "Structures 

Monitoring Program"

None

NEI stated the NUREG basis 

document for GALL states 

"Difficult to justify loss of 

materials in this environment. 

All issued SERs have 

accepted no aging effects."

Therefore aging effect and 

AMP should be changed to 

"None."

The staff agreed with this change 

because air - indoor uncontrolled 

environment is defined as "normally dry"

in GALL Chapter IX.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.2-13 NUREG-1832

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1): Consolidation of Chapter III Tables

The tables of Chapter III for the various structures and component supports are highly repetitive. Many of the generic GALL lines 

are the same for each structure table. To simplify these GALL tables, the nine structures tables have been consolidated into three 

tables. Tables A1, A2, A3, A4, A5, and A9 comprise a new Group 1 Structures Table; Table A6 becomes a new Group 2 

Structures Table; and Tables A7 and A8 are joined to become a new Group 3 Structures Table. Similarly, the three ASME piping 

supports tables B1.1, B1.2 and B1.3 are combined as a table for supports for ASME piping and components and Class MC (BWR 

Containment Supports); and the remaining four tables have been combined as a table for other supports.

Because the consolidation changes more than just the tables themselves, the entire chapter is presented below showing how it 

should appear; not all deletions are marked. The bases for consolidation are not discussed for each line. Comments in addition to 

the consolidation maintain the convention of bold italics for additions and strikethrough for deletions and a basis for the change 

are provided.

2. General Comment 2 (GC2): New Line-items

Proposed new lines items are listed at the end of each table. The new lines are designated "New III.X(Y)" where X is the table 

identifier and Y is a sequential number for new lines in that table.

3. General Comment 3 (GC3): Inappropriate AMP

The wrong AMP is designated in the AMP column of some lines. For example Item III.A1-7 for Class I (other than Containment) 

concrete is managed by SMP not IWL. Corrections are suggested.

4. General Comment 4 (GC4): AMP Modifications for Consistency

"Accessible Areas and Inaccessible Areas" were introduced for water control structures concrete AMP to make it consistent with 

rest of the GALL Report. For example see Item III.A2-3.

5. General Comment 4 (GC5): Alternate AMPs

Added "and/or Structures Monitoring Program (SMP)." Section XI mentions SMP as an alternative program; we are adding it in 

GALL so that we can credit it as "consistent with GALL." For example see Item III.A2-3.
NUREG-1832 A.2.2-14 September 2005

This Page Intentionally Left Blank
September 2005 A.2.3-1 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-1a RP-25 Create new AMR line-item to 

address loss of material for 

Stainless Steel (SS) in a treated 

water environment. Specifically, 

add the aging effect of loss of 

material due to pitting and 

crevice corrosion for SS, 

steel with nickel-alloy or 

stainless steel cladding; nickelalloy

Flanges, nozzles; penetrations; 

pressure housings; safe ends; 

vessel shells, heads and welds

in a reactor coolant environment. 

The NEI-recommended AMP 

was GALL AMP XI.M2, "Water 

Chemistry," for BWR water.

NEI suggested the addition of 

this AMR line-item to be 

consistent with new IV.A2 (1) 

as shown in comment 

G-IV-GC - 2.a. NEI 

recommended the water 

chemistry AMP as sufficient 

basis for minimizing the 

dissolved oxygen and ionic 

impurity concentrations and 

thus managing pitting and 

crevice corrosion (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed that the proposed lineitem could be added for consistency with 

the additions for stainless steel 

components in PWR reactor coolant 

environment. The component "pressure 

housing" does not apply to BWRs.

Unlike the PWR reactor coolant 

environment, the BWR treated water 

environment does not contain boron 

(which is a recognized corrosion 

inhibitor). Thus for this AMR line-item 

related to BWRs, it is necessary to have 

the GALL AMP XI.M2, "Water 

Chemistry," augmented by verifying the 

effectiveness of water chemistry control.

The staff determined that the 

appropriate AMP description is GALL 

AMP XI.M2, "Water Chemistry," for 

BWR water. The AMP is to be 

augmented by verifying the 

effectiveness of water chemistry control. 

See GALL AMP XI.M32, "One-Time 

Inspection," for an acceptable

verification program.

A new AMR line-item RP-25 was 

created.
NUREG-1832 A.2.3-2 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-1b RP-26 Create new AMR line-item to 

address loss of material for SS 

in a treated water environment. 

(Same as G-IV-GC-1.a but 

address a different component in 

a different RCS subsystem). 

Create new AMR line-item to 

address the aging effect of loss 

of material due to pitting and 

crevice corrosion for SS; steel 

with nickel-alloy or SS cladding; 

nickel-alloy reactor vessel 

internals components in a 

reactor coolant environment. 

The NEI-recommended AMP 

was GALL AMP XI.M2, "Water 

Chemistry," for BWR water.

NEI suggested the addition of 

this AMR line-item to be 

consistent with new AMR lineitem IV.A2 (1) as shown in 

comment G-IV-GC - 2.a. NEI 

recommended the water 

chemistry AMP as sufficient 

basis for minimizing the 

dissolved oxygen and ionic 

impurity concentrations and 

thus managing pitting and 

crevice corrosion (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed that the proposed lineitem could be added for consistency with 

the additions for SS components in 

PWR reactor coolant environment.

Unlike the PWR reactor coolant 

environment, the BWR treated water 

environment does not contain boron 

(which is a recognized corrosion 

inhibitor). Thus for this AMR line-item 

related to BWRs, it is appropriate to 

have as the GALL AMP XI.M1, "ASME 

Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD," for 

Class 1 components and GALL AMP 

XI.M2, "Water Chemistry," for BWR 

water.

When GALL AMP XI.M1 is associated 

with water chemistry, it is not necessary 

to verify the effectiveness of chemistry 

because ISI periodically checks the 

effectiveness of chemistry which is 

better than one-time verification (GALL 

AMP XI.M32).

A new AMR line-item RP-26 was 

created.
September 2005 A.2.3-3 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-1c RP-27 Create new AMR line-item to 

address loss of material for SS 

in a treated water environment 

(same as G-IV-GC-1.a but 

address a different component in 

a different RCS subsystem). 

Create new AMR line-item to 

address the aging effect of loss 

of material due to pitting and 

crevice corrosion for Steel with 

stainless steel or nickel alloy 

cladding; SS; nickel alloy reactor 

coolant pressure boundary 

components in a reactor coolant 

environment. The NEIrecommended AMP was GALL 

AMP XI.M2, "Water Chemistry,"

for BWR water.

NEI suggested the addition of 

this AMR line-item to be 

consistent with new AMR lineitem IV.A2 (1) as shown in 

comment G-IV-GC - 2.a. NEI 

recommended the water 

chemistry AMP as sufficient 

basis for minimizing the 

dissolved oxygen and ionic 

impurity concentrations and 

thus managing pitting and 

crevice corrosion (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed that the proposed lineitem could be added for consistency with 

the additions for stainless steel 

components in PWR reactor coolant 

environment. Unlike the PWR reactor 

coolant environment, this BWR treated 

water environment does not contain 

boron (which is a recognized corrosion 

inhibitor).

Thus for this AMR line-item related to 

BWRs, it is appropriate to have as the 

AMP description "Chapter XI.M2, "Water 

Chemistry," for BWR water. The AMP is 

to be augmented by verifying the 

effectiveness of water chemistry control. 

See Chapter XI.M32, "One-Time 

Inspection," for an acceptable 

verification program."

A new AMR line-item RP-27 was 

created.
NUREG-1832 A.2.3-4 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC1d1.1No 

corresponding 

AMR line-item

created 

although 

proposed by 

NEI for 

IV.D1(1) 

IV.D2(1)

Same as G-IV-GC-1.a but 

address a different component in 

a different RCS subsystem. 

Create new AMR line-item to 

address the aging effect of loss 

of material due to pitting and 

crevice corrosion for steel with 

SS or nickel alloy cladding; SS; 

nickel alloy Primary side steam 

generator components in a

reactor coolant environment. 

The NEI-recommended AMP 

was GALL AMP XI.M2, "Water 

Chemistry," for PWR primary 

water.

NEI suggested the addition of 

this AMR line-item to address 

the aging effect of loss of 

material in a treated borated 

water environment (PWR 

reactor coolant). NEI 

recommended the water 

chemistry AMP as sufficient 

basis for minimizing the 

dissolved oxygen and ionic 

impurity concentrations (see 

also the endnotes to this table 

for NEI’s presentation of 

general comment 1).

The staff did not agree with this 

comment. The staff decided that the 

proposed line-item potentially conflicted 

with other AMR line-items and the 

assigned AMP (such as R-44 which 

uses GALL AMP XI.M19, "Steam 

Generator Tubing Integrity" together with 

GALL AMP XI.M2, "Water Chemistry,"

for PWR primary water).

The GALL Report was not revised to 

address this proposed change.

G-IV-GC1d1.2No 

corresponding 

AMR line-item

created 

although 

proposed by 

NEI for 

IV.D1(2) 

Create new AMR line-item to 

address the aging effect 

cracking due to SCC for steel

with SS or nickel alloy cladding; 

SS; nickel alloy tubesheet in a

reactor coolant environment. 

The NEI-recommended AMP 

was GALL AMP XI.M2, "Water 

Chemistry," for PWR primary 

water.

NEI wrote that their proposed 

AMR line-item addresses the 

primary side of the tubesheet 

and added that this AMR lineitem is similar to RP-17 with 

added materials (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff did not agree with this 

comment because of concern that the 

proposed AMP may not adequately 

manage cracking due to SCC in the 

additional nickel alloy materials in a 

reactor coolant environment. RP-17 

uses GALL AMP XI.M2, "Water 

Chemistry," for PWR primary water.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.3-5 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC1d1.3No 

corresponding 

AMR line-item

created 

although 

proposed by 

NEI for 

IV.D1(3) 

Create new AMR line-item to 

address the aging effect 

cracking due to SCC for 

steel with SS or nickel alloy 

cladding; SS; nickel alloy 

tubesheet in a secondary 

feedwater/ steam environment. 

The NEI-recommended AMP 

was GALL AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water, and plant-specific

inspection program.

NEI wrote that their proposed 

AMR line-item addresses the 

secondary side of the tubesheet 

and that the AMR line-item is 

similar to lines RP-14 and R-36 

except that a plant-specific

inspection program is used 

since neither ISI nor SG Tube 

Integrity is applicable (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff did not agree with this 

comment. The staff decided that the 

proposed AMR line-item is not needed 

because it is not anticipated that SCC of 

the tubesheet on the secondary side is a 

significant enough issue to warrant 

inclusion. The GALL Report is not 

intended as a scoping and screening 

document. If the AMR line-item were to 

be added, the appropriate AMP would 

have to be ‘plant-specific.’ NEI’s analogy 

of AMR line-item RP-14 addresses SCC 

of Ni or SS antivibration bars in a 

secondary feedwater/ steam 

environment and references ISI and 

SGTI AMPs. NEI’s analogy of AMR lineitem R-36 addresses SCC of Ni SG 

components in a secondary feedwater/ 

steam environment and also references 

ISI and SGTI AMPs. 

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.3-6 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC1d1.4No 

corresponding 

AMR line-item

created 

although 

proposed by 

NEI for 

IV.D1(4) I

V.D2(2)

Create new AMR line-item to 

address the aging effect of loss 

of material due to pitting and 

crevice corrosion for 

steel with SS or nickel alloy 

cladding; SS; nickel alloy Steam 

generator components in a

secondary feedwater/ steam 

environment. The NEIrecommended AMP was GALL 

AMP XI.M2, "Water Chemistry,"

for PWR secondary water, and 

plant-specific inspection 

program.

NEI wrote that this proposed 

AMR line-item addresses SS

and nickel alloy secondary side 

components and that the lineitem is similar to lines SP-16 

and S-22 except that a plantspecific inspection program is 

used and nickel alloy is 

included (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff did not agree with this 

comment. The staff decided that the 

proposed line-item was too broad and 

potentially conflicted with other AMR 

line-items such as those discussing SG 

tubes.

The GALL Report was not revised to 

address this proposed change.

G-IV-GC-1e No 

corresponding 

AMR line-item

created 

although 

proposed by 

NEI for IV.E(1) 

Create new AMR line-item to 

address the situation where 

there is no aging effect found 

(and no recommended AMP) for 

external surfaces of steel piping, 

piping components, and piping 

elements exposed to inert 

containment environment.

NEI wrote that this proposed 

AMR line-item was based on 

the proposed revision to add 

the definition of an inert 

containment environment to 

GALL 

Chapter IX (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff did not agree with the NEI 

proposed AMR line-item because the

staff disagrees that the containment 

environment is inert (it is subjected to 

outages and moisture leakages).

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.3-7 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-2a RP-28 Create new AMR line-item to 

address loss of material in a 

treated borated water 

environment due to pitting and 

crevice corrosion 

for SS; steel with nickel-alloy or 

SS cladding; nickel-alloy 

flanges, nozzles; penetrations; 

pressure housings; safe ends; 

vessel shells, heads and welds

in a reactor coolant environment.

The water chemistry AMP XI.M2 

is the basis for minimizing the 

dissolved oxygen and ionic 

impurity concentrations. 

Pitting and crevice corrosion 

may occur in ASME Code 

Class1 SS or NiCrFe 

components under exposure to 

aggressive, oxidizing 

environments (quoted from 

Farley SER Section 3.1.2.3.1.2, 

and applicant’s response to RAI 

3.1.3.1.1-1). Because the aging 

effect is minor, the water 

chemistry program by itself is 

sufficient to manage this aging 

effect, as evidenced by past 

operating experience (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 2).

The staff agreed with this comment. In 

the context of the PWR borated water 

environment, loss of material due to 

pitting and crevice corrosion is 

effectively managed by 

recommendations in GALL AMP XI.M2, 

"Water Chemistry," for PWR primary 

water. 

The inclusion of boron (even at 25 ppm 

levels) acts as a corrosion inhibitor to 

protect stainless steels in a 

demineralized water environment (Nalco 

Water Handbook, 2nd Edition). Thus it is 

not necessary to have additional 

augmentation for the GALL AMP XI.M2,

as it would be if this AMR line-item 

addressed BWR components (exposed 

to a nonborated water environment).

A new AMR line-item RP-28 was 

created.
NUREG-1832 A.2.3-8 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-2b RP-24 Create new AMR line-items to 

address the aging effect of loss 

of material for stainless steel or 

nickel alloy reactor vessel 

internals components in a 

treated PWR borated water 

environment. (Reactor coolant). 

The water chemistry GALL AMP

XI.M2 is the basis for minimizing 

the dissolved oxygen and ionic 

impurity concentrations. 

Pitting and crevice corrosion 

may occur in ASME Code 

Class1 stainless steel or 

NiCrFe components under 

exposure to aggressive, 

oxidizing environments. 

Because the aging effect is 

minor, the water chemistry 

program by itself is sufficient to 

manage this aging effect, as 

evidenced by past operating 

experience (precedent based 

on Farley SER Section 

3.1.2.3.1.2, and applicant’s 

response to RAI 3.1.3.1.1-1) 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 2).

The staff agreed with this comment. In 

the context of the PWR borated water 

environment, loss of material due to 

pitting and crevice corrosion is 

effectively managed by 

recommendations in GALL AMP XI.M2, 

"Water Chemistry," for PWR primary 

water. 

Consistent revisions were made to 

tables for PWR reactor vessel internals 

for Westinghouse, Combustion 

Engineering, & Babcock & Wilcox. The 

inclusion of boron (even at 25 ppm 

levels) acts as a corrosion inhibitor to 

protect stainless steels in a 

demineralized water environment (Nalco 

Water Handbook, 2nd Edition). Thus it is 

not necessary to have additional 

augmentation for the GALL XI.M2 AMP, 

as it would be if this AMR line-item 

addressed BWR components (exposed 

to a nonborated water environment).

A new AMR line-item RP-24 was 

created.
September 2005 A.2.3-9 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-2c RP-23 Create new AMR line-item to 

address the aging effect of loss 

of material due to pitting and 

crevice corrosion for 

Steel with stainless steel or 

nickel alloy cladding; stainless 

steel; nickel alloy

Piping, piping components, and 

piping elements; flanges; heater 

sheaths and sleeves; 

penetrations; thermal sleeves; 

vessel shell heads and welds in 

a treated PWR borated water 

environment (reactor coolant). 

The water chemistry GALL AMP

XI.M2 is the basis for minimizing 

the dissolved oxygen and ionic 

impurity concentrations.

Delete the following sentence in 

GALL Report ’05 introduction to 

Chapter IV C2 "The effects of 

pitting and crevice corrosion on 

stainless steel components are 

not significant in treated borated 

water and, therefore, are not 

included in this section."

Pitting and crevice corrosion 

may occur in ASME Code 

Class1 stainless steel or 

NiCrFe components under 

exposure to aggressive, 

oxidizing environments. 

Because the aging effect is 

minor, the water chemistry 

program by itself is sufficient to 

manage this aging effect, as 

evidenced by past operating 

experience (precedent based 

on Farley SER Section 

3.1.2.3.1.2, and applicant’s 

response to RAI 3.1.3.1.1-1)

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 2).

The staff agreed with this comment. In 

the context of the PWR borated water 

environment, loss of material due to 

pitting and crevice corrosion is 

effectively managed by 

recommendations in GALL AMP XI.M2, 

"Water Chemistry," for PWR primary 

water. 

Consistent revisions were made to 

tables for PWR reactor vessel internals 

for Westinghouse, Combustion 

Engineering, & Babcock & Wilcox. The 

inclusion of boron (even at 25 ppm 

levels) acts as a corrosion inhibitor to 

protect stainless steels in a 

demineralized water environment (Nalco 

Water Handbook, 2nd Edition). Thus it is 

not necessary to have additional 

augmentation for GALL AMP XI.M2, as it 

would be if this AMR line-item 

addressed BWR components (exposed 

to a nonborated water environment).

The introductory sentence in the 

narrative for IV.C2 was removed. A new 

AMR line-item RP-23 was created.
NUREG-1832 A.2.3-10 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-3a Global change Wherever it is used in AMR lineitems within the AMP column to 

describe GALL AMP XI.M2 for 

PWR water chemistry, delete the 

reference to the specific EPRI 

document TR105714.

The reference to the specific 

EPRI document need not be 

included in the AMP column of

this particular AMR line-item 

because this information is 

provided in GALL AMP XI.M2.

Within the AMR line-item, it is 

adequate and internally 

consistent to more simply 

reference GALL AMP XI.M2, 

"Water Chemistry," for PWR 

primary water in EPRI TR -

105714 as GALL AMP XI.M2, 

"Water Chemistry," for PWR 

primary water" (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 3).

The staff agreed with this comment. In 

the circumstances where previously 

EPRI TR-105714 was referenced in the 

AMP column of the AMR line-item, the 

AMP XI.M2 is now denoted as GALL 

AMP XI.M2, "Water Chemistry," for 

PWR primary water."

The GALL Report was revised to 

address this proposed change.

G-IV-GC-3b Global change Wherever it is used in AMR lineitems within the AMP column to 

describe AMP XI.M2 for BWR 

water chemistry, delete the 

reference to BWRVIP-29 (EPRI 

TR-103515) 

The reference to the specific 

EPRI document need not be 

included in the AMP column of 

this particular AMR line-item 

because this information is 

provided in GALL AMP XI.M2.

Within the AMR line-item, it is 

adequate and internally 

consistent to more simply 

reference GALL AMP XI.M2, 

"Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR103515) as GALL AMP XI.M2, 

"Water Chemistry," for BWR 

water" (see also the endnotes to 

this table for NEI’s presentation 

of general comment 3).

The staff agreed with this comment. 

In the circumstances where previously 

BWRVIP-29 (EPRI TR-103515) was 

referenced in the AMP column of the 

AMR line-item, the AMP XI.M2 is now 

denoted as GALL AMP-XI.M2, "Water 

Chemistry," for BWR water.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-11 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-3c Global change Wherever it is used in AMR lineitems within the AMP column to 

describe GALL AMP XI.M2 for 

PWR secondary water 

chemistry, delete the reference 

to EPRI TR-102134.

The reference to the specific 

EPRI document need not be 

included in the AMP column of 

this particular AMR line-item 

because this information is 

provided in GALL AMP XI.M2 

Within the AMR line-item, it is 

adequate and internally 

consistent to more simply 

reference 

GALL AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water in EPRI TR-102134 as 

GALL AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water" (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 3).

The staff agreed with this comment. In 

the circumstances where previously 

EPRI TR-102134 was referenced in the 

AMP column of the AMR line-item, the 

AMP XI.M2 is now denoted as GALL 

AMP XI.M2, "Water Chemistry," for 

PWR secondary water.

The GALL Report was revised to 

address this proposed change.

G-IV-GC-4 R-01 

R-06

R-75

R-76

R-89

R-90

RP-21

RP-22

Where appropriate, replace term 

"Alloy 600" in the AMP column

for these AMR line-items 

describing the appropriate AMP 

with "nickel alloys."

Aging issues associated with 

Alloy 600 also affect other 

nickel alloys such as Alloy 

690/52/152. The guidance for 

AMP should be applicable to 

nickel alloys (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 4).

The staff agreed with this comment. The 

specificity created by denoting Alloy 600 

in the AMP description within the AMR 

line-item is not desirable when 

considering the aging issues of nickel 

alloys.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-12 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-5 R-01

R-126

R-128

R-130

R-131

RP-21

Add Nickel (Ni) alloys to 

materials for certain items in 

addition to stainless steel (SS).

Materials for certain items may 

include Ni alloys in addition to 

SS. Similarly, some items 

currently listed as nickel alloy 

can also be steel clad with 

nickel alloy, e.g., SG primary 

side components. The added 

materials are subject to the 

same aging effects as those 

currently listed (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 5).

The staff partially agreed with this 

comment. Steel with nickel alloy 

cladding was added to already existing 

Ni alloy in R-01 and RP-21.

Nickel alloy was added to already 

existing stainless steel in R-130 and R131. Nickel alloy was not added to R126 and R-128.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-13 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-6a R-12

R-27

R-73

GIX Table IX.C

Group the term "high strength 

low alloy steel" within the 

category of low alloy steel. 

NEI pointed out that the "high 

strength" modifier refers to 

susceptibility to the cracking 

aging effect and that bolt 

strength does not impact the 

fatigue or wear aging 

mechanisms (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 6).

The staff agreed with this comment. The 

staff agreed that since the high strength 

steels are vulnerable to SCC, this 

descriptor should be retained where 

cracking is stipulated as the aging 

mechanism and simplified to low-alloy 

steel where SCC was not among the 

aging mechanisms. The staff agreed to 

remove any reference to specific 

maximum tensile strength in the material 

column.

As stated in NUREG-1339, pg. 12, 

"high-strength bolts should be those with 

yield strength, Sy , = 150 ksi" and GALL 

Chapter IX was modified to include the 

clarification.

As shown in the second column for AMR 

line-items, a number of AMR line-item 

material designations were changed in 

response to this comment. These are 

the ones that do not reference cracking 

as an aging effect.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-14 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-6b R-11

R-60

R-71

GIX Table IX.C

Group the term "high strength 

low alloy steel" within the 

category of low alloy steel. 

NEI pointed out that the "high 

strength" modifier refers to 

susceptibility to the cracking 

aging effect and that bolt 

strength does not impact the 

fatigue or wear aging 

mechanisms (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 6).

The staff agreed with this comment. The 

staff agreed that since the high strength 

steels are vulnerable to SCC, this 

descriptor should be retained where 

cracking is stipulated as the aging effect 

and simplified to low-alloy steel where 

SCC was not among the aging 

mechanisms. 

As stated in NUREG-1339, pg. 12, 

"high-strength bolts should be those with 

yield strength, Sy , = 150 ksi" and GALL 

IX was modified to include the 

clarification. As shown in the second 

column for AMR line-items, a number of 

AMR line-item material designations 

were not changed in response to this 

comment. These are the ones that 

reference cracking as an aging effect.

The GALL Report was modified to 

address this comment.
September 2005 A.2.3-15 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-6c R-12

R -27

R-32

Delete loss of preload due to 

stress relaxation as an aging 

effect/aging mechanism couplet 

in GALL.

NEI stated that the industry 

does not consider loss of 

preload as an aging effect 

requiring management. Loss of 

preload is a design driven effect 

and not an aging effect 

requiring management (EPRI 

1003056, "Mechanical Tool,"

Appendix F) NEI further wrote 

that the bolting at most facilities 

is standard grade B7 carbon 

steel, or similar material, except 

in rare specialized applications. 

Loss of preload due to stress 

relaxation (creep) for this 

material can only be a concern 

in very high temperature 

applications (> 700°F) as stated 

in the ASME Code Section II 

Part D Table 4 Note 4 (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 6).

The staff agreed with the proposed 

change with modification. The staff 

agreed that ASME Code Section II Part 

D Table 4 Note G14 points out that loss 

of preload due to stress relaxation 

(creep) for B7 (low alloy steel –A193 B7, 

as stated in Appendix F of EPRI 

1003056 and elsewhere) can only be a 

concern in very high temperature 

applications(> 700°F).

The reference (EPRI TR-104213) 

replaces the earlier report EPRI NP5067, Good Bolting Practices, A 

Reference Manual for Nuclear Power 

Plant Maintenance Personnel. In both 

documents, loss of preload due to 

gasket creep, thermal effects (including 

differential expansion and creep or 

stress relaxation), and self-loosening 

(which includes vibration, joint flexing, 

cyclic shear loads, thermal cycles) is 

discussed. The staff determined that this 

combination of aging mechanisms will 

replace ‘stress relaxation.’ Thus the 

replacement aging effect/aging 

mechanism will be loss of preload/ 

thermal effects, gasket creep, and selfloosening.

The GALL Report was revised to 

address this comment.
NUREG-1832 A.2.3-16 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-7a R-04

R-09

R-100

R-109

R-110

R-138

R-139 

R-149

R-151

R-159

R-160

R-166

R-167

R-168

R-180

R-182

R-185

R-20

R-202

R-204

R-24

R-53

R-54

R-76

R-83

GIX Table IX.C

Cast austenitic stainless steel 

(CASS) should be treated as a 

subset of stainless steel 

EXCEPT where CASS and SS 

have different aging 

effects/mechanisms (loss of 

fracture toughness due to 

thermal and neutron irradiation 

embrittlement). List CASS as a 

separate material only when loss 

of fracture toughness is an 

issue.

With the exception of the loss of 

fracture toughness due to 

thermal and neutron irradiation 

embrittlement, CASS and 

stainless steel share the same 

aging effects/mechanisms in 

GALL (see also the endnotes to 

this table for NEI’s presentation 

of general comment 7).

The staff agreed with this comment. 

CASS is generally treated as a subset of 

stainless steel EXCEPT where CASS 

and SS have different aging 

effects/mechanisms. Both CASS and SS 

are subject to 

• cracking/ stress corrosion cracking, 

irradiation-assisted stress corrosion 

cracking, and or intergranular stress 

corrosion cracking,

• cracking/ primary water stress 

corrosion cracking,

• changes in dimensions/void 

swelling, and 

• cumulative fatigue damage/ fatigue.

These aging effect/aging mechanisms 

are generally managed by the same 

AMPs for both CASS and SS.

AMR line-items and the definition of 

stainless steel in Chapter IX are 

changed accordingly. As indicated by 

the AMR line-item numbers, CASS was 

removed from the materials listing and 

stainless steel was added if not already 

present.

Others, such as IV.C2-4 (R-05), retained 

their original identity.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-17 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-7b RP-02 Delete AMR line-items where 

CASS is not subjected to aging 

effect/aging mechanism couplet 

of loss of fracture toughness due 

to thermal and/or neutron 

irradiation embrittlement.

CASS is treated as a subset of 

stainless steel EXCEPT where 

CASS and SS have different 

aging effects/mechanisms (loss 

of fracture toughness due to 

thermal and neutron irradiation 

embrittlement) (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 7).

The staff agreed with this comment. As 

shown in the staff disposition for 

comment G-IV-GC-7a, CASS is treated 

as a subset of SS except where the 

aging effect of fracture toughness is due 

to thermal and neutron irradiation 

embrittlement.

The GALL Report was revised to 

address this proposed change.

G-IV-GC8a1R-04 The composite component 

description is confusing when it 

includes both generic description 

as well as specific component 

names.

Component combination

Piping, piping components, and 

piping elements; Flanges; 

nozzles; heater sheaths and 

sleeves; penetrations; pressure 

housings; pump casing/cover; 

spray head; thermal sleeves; 

safe ends; vessel shells, heads 

and welds

Or

Piping, piping components, and 

piping elements; flanges; heater 

sheaths and sleeves; 

penetrations; pressure housings; 

pump casing/cover; spray head; 

thermal sleeves; vessel shell 

heads and welds

(with GIX definition updated to 

NEI pointed out that the 

composite component 

description is confusing when it 

includes both generic 

descriptions as well as specific 

component names (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 8).

The staff agreed with this comment. The 

staff decided it was appropriate to split 

R-04 into 6 generic items.

• R-04 which includes (for BWRs) the 

IV.A1 links and the components 

defined as, BWR vessel 

components - Flanges; nozzles; 

penetrations; safe ends; thermal 

sleeves, vessel shells, heads and 

welds.

• R-219 which includes (for PWRs) 

the IV.A2 links and the PWR 

Reactor vessel components defined 

as Flanges, nozzles; penetrations; 

pressure housings; safe ends, 

Thermal sleeves, vessel shells,

heads and welds.

• R-220 which includes (for BWRs) 

the IV.C1 links and the components 

defined as 

Piping, piping components, and 

piping elements.

• R-223 which includes (for PWRs) 

the IV.C2 links and the components 

defined as 
NUREG-1832 A.2.3-18 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

include penetrations, pressure 

housings, vessel shells heads 

and welds.)

Piping, piping components, and 

piping elements; flanges; Nozzles 

and safe ends; Pressurizer vessel 

shell heads and welds; Heater 

sheaths and sleeves; Penetrations; 

and Thermal sleeves

• R-221 which includes IV.D1 link and 

the components defined as 

Recirculating steam generator 

components: Flanges; Penetrations; 

Nozzles; Safe ends, lower heads 

and welds.

• R-222 which includes IV.D2 link and 

the components defined as 

Once-through steam generator 

components: Primary side nozzles; 

Safe ends and welds.

G-IV-GC8d1R-33 Replace components definition 

term of "steam generator 

components" with more specific 

identification.

The term "Steam generator 

components" is too broad a 

‘Structure and/or Component’ 

identification for this item. Item 

IV.D1-5 addresses the same 

aging effect for primary side 

steam generator components. 

Rev. 0 structure/component 

description of GALL’01 was 

adequate.

Comment also applies to item 

IV.D2-9 below (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 8).

The staff agreed with this comment. The 

staff decided it was appropriate to keep 

the recirculating and once-through SGs 

together in this case and the listing of 

SSCs was changed to Steam generator 

components 

Top head 

Steam nozzle and safe end; 

Upper and lower shell; 

FW and AFW nozzle and safe end; 

FW impingement plate and support.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-19 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC8d1R-07 The composite component 

description is confusing when it 

includes both generic description 

as well as specific component 

names. Change the components 

to delete Class 1 piping, fittings 

and only retain primary nozzles, 

safe ends, manways, and 

flanges.

Alternatively, identify which 

Class 1 pipe and fittings are this 

item referring to that is not 

already addressed in Section 

IV.C2. Clarify components for 

which this item is applicable.

The draft NUREG-1833 bases

document) does not address 

this change in approach for 

listing component names. 

Manways and flanges are 

reasonable additions for 

recirculating steam generators 

due to being primary side 

forgings, but Class 1 piping and 

fittings create confusion since 

piping and fittings are 

addressed in Section IV.C2 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 8).

The staff did not agree with this 

comment. The staff decided to keep 

Class 1 piping and fittings. The AMR 

line-item R-07 is used for the link to the 

piping and fittings in IV C2 as well as D1 

and references the following GALL’01 

line-items:

C2.2-f 

C2.5-h 

C2.5-m

D1.1-i 

The GALL Report was not revised to 

address this proposed change.

G-IV-GC8d2R-35 Replace the term "Steam 

generator components" with 

more specific identification.

The term "steam generator 

components" is too broad a 

‘Structure and/or Component’

identification for this item (see 

also the endnotes to this table 

for NEI’s presentation of 

general comment 8).

The staff agreed with this comment. The 

staff redefined the S&C term as:

Primary side components

Upper and lower heads

Tube sheets and tube-to-tube sheet 

welds

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-20 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC8d3R-34 Refine the SG components 

definition term. Clarify the 

description of the AMP in the 

AMR line-item.

NEI stated that the existing 

AMP description in the AMR 

line-item does not clearly 

convey the nature of the 

degradation mechanism, which 

is related to a very specific set 

of conditions, not to most SGs. 

IN 90-04 indicates that pitting 

corrosion on the surface served 

as corrosion fatigue crack 

initiation sites, not that pitting 

corrosion resulted in sufficient 

degradation to cause loss of 

component function. Further, 

this degradation mode has 

been limited to isolated cases 

of weld-zone cracking in 

Westinghouse Model 44 and 51 

SGs, where a high stress 

region exists in the area of the 

shell to transition cone weld 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 8).

The staff agreed with this comment. The 

staff determined it was necessary to 

separate the AMR line-item for the 

recirculating SG [D1.1-c] from the AMR 

line-item for the once-through SG [D2.1-

e] which becomes R-224 and is 

discussed below in G-IV-GC-8d4.

The staff redefined the S&C term for R34 as, "Steam generator components, 

Upper and lower shell, and transition 

cone."

The reference in the AMR line-item to 

the AMP column is rewritten to state "

Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 2 components 

and Chapter XI.M2, "Water Chemistry,"

for PWR secondary water. As noted in 

NRC Information Notice IN 90-04, if 

general and pitting corrosion of the shell 

is known to exists, the guidelines in 

XI.M1 may not be sufficient to detect 

general and pitting corrosion (and the 

resulting corrosion-fatigue cracking), and 

additional inspection procedures are to 

be developed. This issue is limited to 

Westinghouse Model 44 and 51 Steam 

Generators where a high stress region 

exists at the shell to transition cone 

weld.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-21 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC8d4R-224 As shown in companion 

comment for R-34, refine SG 

components definition term. 

Clarify the reference to the AMP 

in the AMR line-item

NEI stated that the existing 

reference to the AMP in the 

AMR line-item does not clearly 

convey the nature of the 

degradation mechanism, which 

is related to a very specific set 

of conditions, not to most SGs. 

See companion comment for IV 

D1-16 (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 8).

The staff agreed with this comment. The 

staff determined it was necessary to 

separate the AMR line-item for the 

recirculating SG [D1.1-c] from the AMR 

line-item for the once-through SG [D2.1-

e] and a new AMR line-item R-224 was 

created.

The S&C are defined as Steam 

generator components: Shell assembly

The reference to the AMP column is 

rewritten to be, "Chapter XI.M2, "Water 

Chemistry," for PWR secondary water. 

The AMP is to be augmented by 

verifying the effectiveness of water 

chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an 

acceptable verification program."

Further Evaluation: Yes, detection of 

aging effects is to be evaluated.

The GALL Report was revised to 

address this proposed change.

G-IV-GC-9a R-75

R-90

NEI commented that the 4 

different types of commitment 

statements used in lieu of 

specific AMPs are less welldefined than the AMPS they 

replaced. For the first type, NEI 

commented that the 

replacement of a specifically 

defined AMP (referring to GALL 

AMP XI.M11 for Ni-alloy Nozzles 

and Penetrations) with the 

following open-ended 

NRC staff notes that this 

commitment was used 15 times 

in the Jan’05 version of the 

GALL Report and replaces

twice in Chpt. IV where AMP 

XI.M11 was originally used in 

GALL’01 (A2.2-a and A2.7-b) 

and the 3 times where there 

had previously been plantspecific AMPs. This 

commitment was also used in 2 

new AMR line-items. The 

The staff agreed with this comment. As 

mentioned in the basis for comment, 

The staff agreed that the interim staff 

guidance (ISG) process will be used to 

update GALL AMP XI.M11 which will 

again be explicitly mentioned in the AMR 

line-items. The staff points out that this 

AMP was only referenced twice in 

Chapter IV of GALL’01; the affected 

AMR line-item numbers in the 2nd

column will again reference GALL AMP 

XI.M11A. 
NUREG-1832 A.2.3-22 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

commitment reduced clarity.

GALL AMP XI.M1, "ASME 

Section XI Inservice Inspection, 

Subsections IWB, IWC, and 

IWD," for Class 1 components 

and GALL AMP XI.M2, "Water 

Chemistry," for PWR primary 

water in EPRI TR-105714 and, 

for Alloy 600, provide a 

commitment in the FSAR 

supplement to implement 

applicable (1) NRC Orders, 

Bulletins and Generic Letters 

associated with nickel alloys and 

(2) staff-accepted industry 

guidelines.

remaining 8 usages were just 

an expansion on the earlier 

GALL’01 usage of combined. 

XI.M1 and XI.M2,

The former plant-specific and 

GALL AMP XI.M11 references 

were changed to explicitly call 

out GALL AMPs XI.M1 and 

XI.M2, supplemented by the 

actions identified by Orders, 

Bulletins and Generic Letters 

associated with recent 

experience with nickel alloys to 

provide more precise guidance 

on what would constitute an 

acceptable plant-specific AMP. 

The staff position encompasses 

ISGs and branch technical 

positions published in other 

regulatory guidance documents 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 9).

The other 13 AMR line-items using this 

description were changed as follows on 

the basis of comments G-IV-GC-3a and 

G-IV-GC-4:

Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components 

and Chapter XI.M2, "Water Chemistry,"

for PWR primary water for Nickel Alloys, 

provide a commitment in the FSAR 

supplement to implement applicable (1) 

NRC Orders, Bulletins and Generic 

Letters associated with nickel alloys and 

(2) staff-accepted industry guidelines."

The AMR line-items R-75 and R-90 

reference the new GALL AMP XI.M11A

as follows:

"Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components 

and Chapter XI.M2, "Water Chemistry,"

for PWR primary water and Chapter 

XI.M11-A, "Nickel-Alloy Penetration 

Nozzles Welded to the Upper Reactor 

Vessel Closure Heads of Pressurized."

Water Reactors (PWRs Only)"

The GALL Report was revised to 

address this comment.
September 2005 A.2.3-23 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-9b R-24

R-88

NEI commented that the 4 

different types of commitment 

statements used in lieu of 

specific AMPs are less welldefined than the AMPS they 

replaced. For the second type, 

NEI commented that the AMP is 

not clear as written below:

GALL AMP XI.M2, "Water 

Chemistry," and GALL AMP

XI.M32 "One-Time Inspection" or 

GALL AMP XI.M1, "ASME 

Section XI Inservice Inspection, 

Subsections IWB, IWC, and 

IWD," and provide a 

commitment in the FSAR 

supplement to submit a plantspecific AMP delineating 

commitments to Orders, 

Bulletins, or Generic Letters that 

inspect stipulated components 

for cracking of wetted surfaces.

NEI was not clear whether or 

not a plant-specific program 

was required only if there are 

applicable Generic 

Communications.

The staff noted that this 

commitment was used 2 times 

in the Jan’05 version of the 

GALL Report where there had 

previously been plant-specific 

AMPs. This AMP was changed 

from requiring a plant-specific 

program to call out explicitly 

GALL AMPs XI.M2 and XI.M32 

or GALL AMP XI.M1. It also 

allows submittal of a plantspecific AMP which would 

identify commitments to actions 

identified by Orders, Bulletins 

and Generic Letters associated

with recent experience with 

nickel alloys (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 9).

The staff agreed with this comment. The 

reference to the AMP in A2.6-a (R-88) 

was rewritten as:

GALL AMP XI.M2, "Water Chemistry,"

and 

GALL AMP XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," and provide a 

commitment in the FSAR supplement to 

submit a plant-specific AMP to 

implement applicable (1) NRC Orders, 

Bulletins, and Generic Letters 

associated with nickel alloys and 

(2) staff-accepted industry guidelines.

Since the ISI programs do not inspect 

the pressurizer spray head in AMR lineitem C2.5-j (R-24), the AMP is rewritten 

as:

"GALL AMP XI.M2, "Water Chemistry,"

and GALL AMP XI.M32 "One-Time 

Inspection" and for nickel alloy welded 

spray heads provide a commitment in 

the FSAR supplement to submit a plantspecific AMP delineating commitments 

to Orders, Bulletins, or Generic Letters 

that inspect stipulated components for 

cracking of wetted surfaces.

Further Evaluation "No, but licensee 

commitment needs to be confirmed."

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-24 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-9c R-107 R-108

R-110 R-113

R-114 R-117

R-119 R-121

R-122 R-124

R-125 R-126

R-127 R-128

R-129 R-131

R-132 R-134

R-135 R-136

R-137 R-139

R-141 R-144

R-147 R-151

R-154 R-157

R-158 R-160

R-161 R-163

R-164 R-165

R-168 R-169

R-174 R-177

R-178 R-182

R-184 R-187

R-188 R-192

R-195 R-196

R-197 R-199

R-201 R-204

R-205 R-207

R-211 R-212

R-213 R-215

R-216

NEI commented that the 4 

different types of commitment 

statements used in lieu of 

specific AMPs are less welldefined than the AMPS they 

replaced.

For the third type, NEI 

commented that the GALL AMP

XI.M16, "PWR Vessel Internals"

was replaced by unclear 

wording. NEI asked for 

clarification, stating that the 

reason for the change is unclear 

and the proposed commitment is 

also unclear.

NEI asked what is the intent of 

submittal 24 months prior to the 

period of extended operation 

(POEO). NEI asked if submittal 

24 months before any proposed 

inspection be an acceptable 

reword. 

The staff points out the 

following wording was used 58 

times in the Jan’05 GALL 

Report to rewrite 15 of the AMR 

line-items in GALL’01 that 

referenced GALL AMP XI.M16 

(out of 49 total); it was used to 

rewrite 11 AMR line-items that 

referenced GALL AMP XI.M14 

and it was used to more tightly 

focus 32 previously plantspecific AMPs.

No further aging management 

review is necessary if the 

applicant provides a 

commitment in the FSAR 

supplement to (1) participate in 

the industry programs for 

investigating and managing 

aging effects on reactor 

internals; (2) evaluate and 

implement the results of the 

industry programs as applicable 

to the reactor internals; and (3) 

upon completion of these 

programs, but not less than 24

months before entering the 

period of extended operation, 

submit an inspection plan for 

reactor internals to the NRC for 

review and approval (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 9).

The staff did not agree with this 

comment. The existing GALL AMP 

XI.M16, "PWR Vessel Internals" is no 

longer referred to by any GALL AMR line 

item in the Jan’05 GALL Report. Instead, 

each AMR line item refers to an industry 

initiative that will define an appropriate 

aging management program which will 

be implemented prior to the period of 

extended operation.

The GALL Report was not revised to 

address this proposed change. The 

NUREG -1833 was revised to explain 

better the staff’s rationale and changes 

for the listed AMR line-items.
September 2005 A.2.3-25 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-GC-9d R-41 1) Change the components to 

read:

"Steam generator structural

 Tube support lattice bars."

2) Explain why the original 

GALL’01 reference in the AMR 

line-item to a plant-specific AMP 

was changed to something that 

seems more unclear in what is 

to be done.

The wording in the AMP column

in the AMR line-item was 

changed from plant-specific to 

reflect the industry efforts to 

develop a program on 

inspection criteria which will be 

used on a plant-specific basis 

with NRC review and approval 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 9).

The staff agreed with this comment. The 

staff revised the component listing to 

state:

"Steam generator structural

tube support lattice bars"

The wording of the AMP column in the 

AMR line-item is modified to read: GALL 

AMP XI.M19, "Steam Generator Tubing 

Integrity" and GALL AMP XI.M2, "Water 

Chemistry," for PWR secondary water

The GALL Report was revised to 

address this comment.
NUREG-1832 A.2.3-26 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

01

R-185

R-187

R-188

R-189

GIX Table IXC

Grouping of metals. PH stainless 

steel forging should be 

subsumed by the definition of 

"stainless steel."

Precipitation-hardened (PH) 

stainless steel is a subset of 

stainless steel with respect to 

aging. There is nothing distinct 

in the AMR line-items 

associated with this material 

that warrants special treatment.

The staff agreed with this comment. 

Precipitation-hardened (PH) stainless 

steel (SS) is treated as a subset of 

stainless steel in these particular cases 

where the aging effect/aging mechanism 

(AE/M) and management are the same. 

For R-185, the materials listed in the 

Jan’05 GALL Report as "Stainless steel, 

PH stainless steel forging, CASS" are 

restated as "stainless steel." The AE/M 

remains cracking due to SCC, IASCC.

For R-187, the materials listed in the Jan 

’05 GALL Report as "Stainless steel, 

nickel alloy, PH Stainless Steel forging"

are restated as "Stainless steel; 

nickel alloy." The AE/M remains 

"Changes in dimensions/void swelling."

For R-188, the materials listed in the 

Jan ’05 GALL Report as "Stainless steel

nickel alloy, PH Stainless Steel forging 

are restated as "Stainless steel; nickel 

alloy." The AE/M remains "Loss of 

fracture toughness/neutron irradiation 

embrittlement, void swelling."

For R-189, the materials listed in the 

Jan’05 GALL Report as "Stainless steel, 

cast austenitic stainless steel, nickel 

alloy, PH Stainless Steel forging" are 

restated as "Stainless steel; nickel 

alloy." (Part of R-53) the AE/M remains 

"Cumulative fatigue damage/ fatigue."

The AMR line-item R-189 is deleted.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-27 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

02

R-29

GIX Table IXD

Clarification of environment. 

Make the following correction Air 

with metal System temperature 

up to 288°C (550°F)

Environment should be 

"System temperature up to 

288°C (550°F)."

As defined in Chapter IX, 

specified environment is 

synonymous with the 

suggested revision but intended 

to describe the environment 

experienced by a PWR 

Pressurizer support skirt. 

The staff agreed with this comment. The 

environment for the pump and valve seal 

flange closure bolting should be 

described by the expression ‘System 

temperature up to 288°C (550°F).’ This 

is now used consistently through GALL 

Chapter IV to describe an environment 

for bolting or the PWR Pressurizer 

support skirt.

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

03a

R-61

R-74

GIX Table IXD

Clarification of environment. Use 

the following expression "Air with 

reactor coolant leakage 

(Internal)."

GALL Chapter IX defines this 

environment as leakage onto a 

surface, which implies an 

external surface, and germane 

to BWRs. Of the 13 GIV items 

that list this environment, 10 

items are for effects on bolting. 

This item addresses the 

collection of reactor coolant 

leakage inside the component 

(e.g., extending pressure 

boundary).

The staff agreed with this comment. The 

term "Air with reactor coolant leakage 

(Internal)" is used in these AMR lineitems to address the collection of reactor 

coolant leakage inside the component 

(e.g., extending pressure boundary).

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

03b

RP-13

GIX Table IXD

Clarify structural and 

environment parameters. Use 

the following expression "Air with 

reactor coolant leakage 

(Internal) or "reactor coolant"

Section 3.1.2.4.5 of the VCS 

SER more correctly describes 

the environment for this item 

(NEI notes that the 1/05 drafts 

of the Bases document lists an 

incorrect section of the RNP 

SER for the change from Rev. 

0 to this item).

The staff agreed with this comment. The 

staff decided that the appropriate 

environment is "reactor coolant." The 

S&C term was also changed to read:

"Bottom-mounted guide tube."

The GALL Report was revised to 

address this comment.
NUREG-1832 A.2.3-28 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

04

R-145 Replace lengthy AMP 

description with reference to 

new AMP Flux Thimble Tube 

Inspection Program" supplied by 

NEI.

NEI proposed to add this AMP.

Replace existing AMP 

discussion with reference to 

new AMP proposed for flux 

thimble tube inspections. Flux 

thimble tubes are not within the 

scope of ASME Section XI. Flux 

thimble tubes are less than 1"

in diameter. Per sections IWB1220(b), IWC-1222(a) (1), and 

IWD-1220(a), the flux thimble 

tubes are exempt from Section 

XI examination 

recommendations. 

Furthermore, IEB 88-09 stated,

"There are currently no 

inservice inspection or testing 

requirements for thimble tubes."

IEB 88-09 does not include any 

guidelines concerning an 

inspection schedule beyond the 

initial inspections which were 

performed fifteen years ago at 

each utility. What IEB 88-09 

says about schedule is already 

addressed in part (b) of the 

AMP description.

The staff agreed with this comment. The 

staff reviewed, revised, and accepted 

the AMP XI.M37 "Flux Thimble Tube 

Inspection Program."

The GALL Report was revised to 

address this comment.
September 2005 A.2.3-29 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

05

R-54 Delete AMR line-item IV.B4-38 

(R-189). Combine link to 

GALL’01 GALL IV.B4.4-e in 

AMR line-item IV.B4-37 (R-54).

The difference between lineitems IV.B4-37 and IV.B4-38 

include:

"PH Stainless Steel forging" is 

listed as an additional material 

in line-item IV.B4-38, whereas 

both list SS, CASS, and nickel 

alloy.

IV.B4-38 is the only RV 

Internals (IV.B1, B2, B3, and 

B4) item which includes 

environmental effects in the 

AMP discussion.

The staff agreed with this comment. The 

AMR line-item IV.B4-38 (R-189) is 

subsumed by IV.B4-37 (R-54) with a link 

placed to GALL’01 IV.B4.4-e.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-30 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

06a

R-03

R-55

SRP3.1.2.2.4.1

Revise existing line-item IV.C1-1

AMP reference to be consistent 

with reference to AMP in lineitem IV.C1-2. Rewrite GALL 

AMP XI.M1, "ASME Section XI 

Inservice Inspection, 

Subsections IWB, IWC, and 

IWD," for Class 1 components 

and GALL AMP XI.M2, "Water 

Chemistry," for BWR water in 

BWRVIP-29 (EPRI TR-103515).

Inspection in accordance with 

ASME Section XI does not 

require volumetric examination 

of pipes less than NPS 4. A 

plant-specific destructive 

examination or a nondestructive 

examination that permits 

inspection of the inside surfaces 

of the piping is to be conducted 

to ensure that cracking has not 

occurred and the component 

intended function will be 

maintained during the extended 

period of operation. 

As presently listed, GALL 

specifies a plant-specific

destructive or non-destructive 

examination for SCC and a 

separate plant-specific 

inspection (One-time Inspection 

is acceptable) for cracking of 

the same components due to 

thermal and mechanical 

loading.

The staff agreed with this comment. The 

staff decided to combine AMR Lineitems R-03 and R-55 (as had been 

previously in GALL’01 IV C1-1. The new 

AMR line-item R-03 (R-55 deleted from 

use) has changes in 2 columns– AE/M 

becomes cracking/stress corrosion 

cracking, intergranular stress corrosion 

cracking (for stainless steel only), and 

thermal and mechanical loading. 

The entry in the AMP column is rewritten 

as: 

Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components, 

and Chapter XI.M2, "Water Chemistry,"

for BWR water and XI.M35, "One-Time 

Inspection of ASME Code Class 1 

Small-bore Piping."

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-31 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

06b

R-02 Revise existing IV.C2-1 (R-02) 

to reinstate AMP description to 

be consistent with the AE/M 

wording "Loss of material/ 

general (steel only), pitting and 

crevice corrosion" and the GALL 

AMP XI.M32 in combination with 

GALL AMP XI.M1 and GALL 

AMP XI.M2.

See comment G-IV-S.C.-5b

The option for utilizing GALL 

AMP XI.M32 in combination 

with GALL AMP XI.M1 and 

GALL AMP XI.M2 has been 

removed and should be 

reinstated. SRP-LR Section 

3.1.2.2.7.3 also recommends

revision, accordingly, to specify 

that OTI is an acceptable 

verification method.

The staff agreed with this comment that 

the reference to the AMP should be 

improved. The addition of the new AMP 

XI.M35 for small bore piping in GALL’05

provides specific guidance and replaces 

the prior need for a plant-specific AMP. 

R-57 was rolled up into this item.

The entry in the AMP column is rewritten 

as: 

Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components, 

and Chapter XI.M2, "Water Chemistry,"

for PWR water and XI.M35, "One-Time 

Inspection of ASME Code Class 1 

Small-bore Piping."

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-32 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

07a

R-15 

SRP-LR (and 

GALL Vol. 1) 

Item 11, 

Section 

3.1.2.2.4.3

Revise existing IV.C1-5 (R-15) 

AMP description to be consistent 

with the AE/M wording 

"Cracking/ stress corrosion 

cracking and intergranular stress 

corrosion cracking."

AMP discussion is in error since 

cyclic loading is not an aging 

mechanism listed for this item, 

or for BWR items other than for 

jet-pump sensing lines (IV.B1-

12) and Nozzles (IV. A1-3 & 

IV.A1-2) and loss of material for 

this component is addressed in 

Item IV.C1-6.

Item IV.C1-5 corresponds to 

SRP-LR (and GALL Vol. 1) Item 

11 and Section 3.1.2.2.4.3 

whereas Item IV.C1-6 

corresponds to SRP-LR Item 5 

and Section 3.1.2.2.2. 

The staff agreed with this comment. The 

staff revised the AMP column to state, 

"Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components 

and Chapter XI.M2, "Water Chemistry,"

for BWR water."

Chapter XI.M1 is to be augmented to 

detect cracking due to stress corrosion 

cracking and verification of the 

effectiveness of the program is 

necessary to ensure that significant 

degradation is not occurring and the 

component intended function will be 

maintained during the extended period 

of operation. An acceptable verification 

program is to include temperature and 

radioactivity monitoring of the shell side 

water, and eddy current testing of tubes.

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

07b

R-16 

SRP-LR (and 

GALL Vol. 1) 

Item 5, Section 

3.1.2.2.2.2

Revise existing IV.C1-6 (R-16) 

AMP description to be consistent 

with the AE/M wording "Loss of 

material/ general (steel only), 

pitting and crevice corrosion."

See comment G-IV-S.C.-6a. 

Aging effect/mechanism in the 

AMP discussion is not 

consistent with the aging 

effect/aging mechanism listed 

in that column.

The staff agreed with this comment. The 

staff revised the AMP to state GALL 

AMP XI.M2, "Water Chemistry," for 

BWR water.

The AMP is to be augmented by 

verifying the effectiveness of water 

chemistry control. See GALL AMP

XI.M32, "One-Time Inspection," for an 

acceptable verification program.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-33 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

08a

R-05 Since CASS is involved in both 

AMR line-items, simplify the 

AMP and combine with R-07. 

The proposed change to the 

entry assumes the material is 

susceptible, but lists water 

chemistry as the aging 

management program which, 

by the current logic, eliminates 

the need for a plant-specific

program. However, ISI has 

been conservatively added as 

an AMP.

The staff did not agree with this 

comment. The staff decided to retain 

both R-05 and R-07. Monitoring and 

control of primary water chemistry in 

accordance with the guidelines in EPRI 

TR-105714 (Rev. 3 or later revisions or 

updates) minimize the potential of SCC, 

and material selection according to the 

NUREG-0313, Rev. 2 guidelines of 

=0.035% C and =7.5% ferrite reduces 

susceptibility to SCC. For CASS 

components that do not meet either one 

of the above guidelines, a plant-specific 

aging management program is to be 

evaluated. The program is to include 

(a) adequate inspection methods to

ensure detection of cracks, and (b) flaw 

evaluation methodology for CASS 

components that are susceptible to 

thermal aging embrittlement.

The GALL Report was not modified to 

address this comment.

G-IV-S.C.-

08b

R-09 Simplify the AMP description in 

the AMR line-item (see comment 

describing proposed change to 

R-05)

The change to the AMP column 

effectively recommends both 

the first provision (water 

chemistry) of the existing entry, 

and conservatively applies the 

conditional AMP (ISI).

The staff agreed with this comment. The 

revised AMP description in the AMR 

line-item reads 

Chapter XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components 

and Chapter XI.M2, "Water Chemistry,"

for PWR primary water.

The GALL Report was revised to 

address this comment.
NUREG-1832 A.2.3-34 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

09

R-125 Correct the components to read

Baffle/former assembly

Baffle/former bolts and screws

Correct the environment to 

delete reference to fluence and

Correct the AMP to include 

water chemistry.

The GALL Link is for B/F Bolts, 

not Core Barrel Assy. Looks 

like a typo that should be 

returned to the original format.

Environment should be 

"Reactor Coolant" and AMP 

should be ‘Chemistry and 

FSAR commitment’ for 

consistency with the twenty-five 

(25) other items in Chapter IV 

for this EAP. Item R-125 is the 

only one that uses the specified 

environment and the only one 

for this Reactor Internals MEAP 

that does not list Chemistry and 

FSAR commitment as the AMP. 

In GALL Rev. 0, a plant-specific 

AMP was used. 

The staff agreed with this comment. The 

SSCs, environment, and AMP were 

revised. The AMP cell was corrected to 

read:

"Chapter XI.M2, "Water Chemistry," for 

PWR primary water. No further aging 

management review is necessary if the 

applicant provides a commitment in the 

FSAR supplement to (1) participate in 

the industry programs for investigating 

and managing aging effects on reactor 

internals; (2) evaluate and implement 

the results of the industry programs as 

applicable to the reactor internals; and 

(3) upon completion of these programs, 

but not less than 24 months before 

entering the period of extended 

operation, submit an inspection plan for 

reactor internals to the NRC for review 

and approval."

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

10

RP-14 Correct component listing to 

read: Steam generator structural

anti-vibration bars; Correct 

materials listing to read

Chrome plated steel; stainless 

steel; nickel alloy

NEI suggested clarifying 

‘Structure and/or Component’ 

for item grouping purposes and 

suggested alphabetical 

component listing.

Chrome plated nickel alloy is 

incorrect for a material. Chrome 

plated steel is a possible 

material for AV bars. 

The staff agreed with this comment. The 

staff revised the components as:

"Steam generator structural antivibration bars" and revised materials to 

be: "Chrome plated steel; stainless steel; 

nickel alloy"

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-35 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

11a

RP-21 Correct component listing to 

read: primary side divider plate; 

Correct materials listing to read

Nickel alloy; steel with nickel 

alloy cladding. Correct AMP to 

delete ISI and read:

GALL AMP XI.M2, "Water 

Chemistry," for PWR primary 

water and, for Nickel alloys, 

provide a commitment in the 

FSAR supplement to implement 

applicable (1) NRC Orders, 

Bulletins and Generic Letters 

associated with nickel alloys and 

(2) staff-accepted industry 

guidelines.

The primary side divider plate 

component is not an RCPB 

component. The ISI Program 

does not directly examine this 

component. Previous applicants 

have credited only the Water 

Chemistry Program. This is a 

location of lower failure and 

lower consequences.

The staff agreed with this comment. The 

staff revised the components to be:

"primary side divider plate" and revised 

materials to be: "Nickel alloy; steel with 

nickel alloy cladding."

The staff decided that the AMPs for lineitems RP-17 and RP-21 should remain

the same. The primary side divider plate 

component is not an RCPB component; 

it is a location of lower failure and lower 

consequences. Thus, the AMP column 

was revised to state: Chapter XI.M2, 

"Water Chemistry," for PWR primary 

water."

No further validation is needed because 

there is no adverse safety consequence 

should through wall cracking occur on 

this component.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-36 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

11b

RP-17 Correct component listing to 

read: primary side divider plate; 

Correct AMP to delete ISI and 

read:, "GALL AMP XI.M2, 

"Water Chemistry," for PWR 

primary water and, for Nickel 

alloys, provide a commitment in 

the FSAR supplement to 

implement applicable (1) NRC 

Orders, Bulletins and Generic 

Letters associated with nickel 

alloys and (2) staff-accepted 

industry guidelines."

The primary side divider plate 

component is not an RCPB 

component. The ISI Program 

does not directly examine this 

component. Previous applicants 

have credited only the Water 

Chemistry Program. This is a 

location of lower failure and 

lower consequences.

The staff agreed with this comment. The 

staff revised the components to be

"primary side divider plate."

The staff revised the components to be

"primary side divider plate" and 

stipulated materials to be "stainless 

steel."

The staff decided that the AMPs for RP17 and RP-21 should remain the same. 

The primary side divider plate 

component is not an RCPB component; 

this is a location of lower failure and 

lower consequences. Thus, the 

referenced AMP column was revised to 

read: GALL AMP XI.M2, "Water 

Chemistry," for PWR primary water." No 

further validation is needed because 

there is no adverse safety consequence 

should through wall cracking occur on 

this component.

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

12a

R-42 Clarify component listing to read: 

Steam generator structural

Tube support plates;

NEI suggested clarifying 

‘Structure and/or Component’ 

for item grouping purposes and 

suggested alphabetical 

component listing.

It’s not clear whether the aging 

effect for "Ligament cracking/ 

corrosion" is Cracking, LOM, or 

both. Entry should be clarified. 

SRP-LR Table 3.1-1 Item 65 

should also be clarified.

The staff agreed with this comment. The 

staff revised the components to be:

"Steam generator structural

Tube support plates."

The AE/M was not revised because 

Ligament cracking/ corrosion" is a

specific AE/M combination.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.3-37 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

12b

R-38 Clarify component listing to read:

Steam generator components

FW and AFW nozzles and safe 

ends 

Steam nozzles and safe ends

NEI suggested clarifying 

‘Structure and/or Component’ 

for item grouping purposes and 

suggested alphabetical 

component listing.

The staff agreed with this comment. The 

staff revised components to be:

"Steam generator components

FW and AFW nozzles and safe ends 

Steam nozzles and safe ends."

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

12c

R-35 Clarify component listing to read:

Primary side components

Upper and lower heads

Tube sheets

NEI suggested clarifying 

‘Structure and/or Component’ 

for item grouping purposes and 

suggested alphabetical 

component listing.

The staff agreed with this comment. The 

staff revised components to be:

"Primary side components

Upper and lower heads;

Tube sheets and tube-to-tube sheet 

welds."

The GALL Report was revised to 

address this proposed change.

G-IV-S.C.-

13

R-57 Revise materials to remove steel 

with stainless steel cladding. 

Revise AMP description to 

delete specific reference to 

service-induced weld cracking.

Small bore piping is not clad 

with stainless steel, but small 

bore RCS piping is stainless 

steel.

The AMP description still 

includes attributes that are 

specific to SCC (but are not 

applicable to thermal and 

mechanical loading).

The staff agreed with this comment. 

When the S&C was revised, this AMR 

line-item fell into the MEAP combination 

represented by R-02, and thus R-57 was 

deleted. 

The AMR line-item R-02 adequately 

addresses the intent of R-57 and thus 

the GALL Report was modified to 

address this comment.
NUREG-1832 A.2.3-38 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IV-S.C.-

14

R-01

R-218

Consolidate minor component 

and material modifications into 

R-01 and delete R-218.

Add safe ends to components 

listing, Add steel with alloy 

cladding to the materials listing, 

add IV.D1.1-i to the link. 

The differences between R-01 

and R-218 were trivial thus 

logically they should be 

combined. SRP-LR Table 3.1-1 

Item 22 should also be updated 

to remove R-218 from the 

‘Related Item’ field.

The staff agreed with this comment. The 

link for R-01 was revised to be:

IV.D1.1-i

IV.D1.1-j

IV.D2.1-h

The S&C were revised to be instrument 

penetrations and primary side nozzles, 

safe ends, and welds. The materials 

were revised to be Nickel alloy or steel 

with nickel alloy cladding.

The GALL Report was revised to 

address this proposed change.

G-IX-GC-7 IX-Table C Revise the definition of SS to 

include CASS in Table C for 

Definition of Materials in Chapter 

IX.

CASS and stainless steel share 

the same aging effects/ 

mechanisms in GALL except for 

thermal and neutron irradiation 

embrittlement. (also see 

endnotes to this table)

See the staff’s disposition of NEI 

Comment G-IV-GC-7. 

The GALL Report was revised to 

address this proposed change.

NRC G-IV-1 R-102 Delete the AMR line-item 

concerning cracking due to 

cyclic loading of SS jet pump 

sensing line. In GALL’01, the 

AMR line-item pointed to a plantspecific AMP as being the 

management approach.

The staff pointed out a staffapproved precedent stating that 

pressure boundary components 

of active instrumentation may 

be excluded from AMR 

because the functional 

degradation resulting from 

aging effects on active 

functions is readily 

determinable from existing 

programs and requirements (for 

example, NUREG-1705, 1999). 

The jet pump sensing line is an 

instrumentation line that 

measures the flow amount of 

the jet pump, by measuring the 

The staff did not agree with the 

proposed change. The jet pump sensing 

line is within the scope of license 

renewal, and may need an AMR. Thus 

this AMR line-item is retained.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.3-39 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

difference of pressure between 

the upper part and the exit of 

the diffuser.

On the other hand, other staff 

stated that jet pump sensing 

line should be within the scope 

of license renewal, but can 

often be screened out from 

requiring AMR. AMR line-item 

(R-101) [B1.4-c] addresses 

thermal aging and neutron 

embrittlement of jet pump 

assembly castings. AMR lineitem (R-100) [B1.4-a] 

addresses cracking of jet pump 

assembly components. AMR 

line-item (R-69 [A1.5-a] 

addresses cracking of jet pump 

penetrations. Of the four, the 

AMR line-item concerning 

cracking due to cyclic loading of 

SS jet pump sensing line, was 

the only one managed by a 

plant-specific AMP.

NRC G-IV-2 R-98 Although the description of top 

guide program scope had been 

placed in AMP XI.M9, the staff 

also wanted it included in the 

AMP column.

The staff wanted to ensure that 

this guidance was followed by 

licensees during the license 

renewal process.

The staff agreed with this comment. The 

GALL Report (AMP) was revised to 

state: "Chapter XI.M9, "BWR Vessel 

Internals," for top guide and Chapter 

XI.M2, "Water Chemistry," for BWR 

water. Additionally, for top guides with 

neutron fluence exceeding the IASCC 

threshold (5E20, E>lMeV) prior to the 

period of extended operation, inspect 

five percent (5%) of the top guide 

locations using enhanced visual 

inspection technique, EVT-1 within six 
NUREG-1832 A.2.3-40 September 2005

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

years after entering the period of 

extended operation. An additional 5% of 

the top guide locations will be inspected 

within twelve years after entering the 

period of extended operation.

Alternatively, if the neutron fluence for 

the limiting top guide location is 

projected to exceed the threshold for 

IASCC after entering the period of 

extended operation, inspect 5% of the 

top guide locations (EVT-1) within six 

years after the date projected for 

exceeding the threshold. An additional 

5% of the top guide locations will be 

inspected within twelve years after the 

date projected for exceeding the 

threshold.

The top guide inspection locations are 

those that have high neutron fluences 

exceeding the IASCC threshold.

The extent and frequency of 

examination of the top guide is similar to 

the examination of the control rod drive 

housing guide tube in BWRVIP-47."
September 2005 A.2.3-41 NUREG-1832

Table A.2.3: Disposition of NEI Comments on Chapter IV of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

NRC G-IV-3 R-25 Delete the reference to Ni alloys 

or Alloy 600 in the AMP 

description. 

The predominant materials are 

steel or stainless steel. In 

GALL’01, the AMP also stated 

that 

"Cracks in the pressurizer 

cladding could propagate from 

cyclic loading into the ferrite 

base metal and weld metal. 

However, because the weld 

metal between the surge nozzle 

and the vessel lower head is 

subjected to the maximum 

stress cycles and the area is 

periodically inspected as part of 

the ISI program, the existing 

AMP is adequate for managing 

the effect of pressurizer clad 

cracking."

The staff agreed with this comment.

The staff revised the AMP column to 

state, "AMP XI.M1, "ASME Section XI 

Inservice Inspection, Subsections IWB, 

IWC, and IWD," for Class 1 components 

and AMP XI.M2, "Water Chemistry," for 

PWR primary water."

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.3-42 September 2005

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1) for New AMR Line-Items: NEI proposed new AMR line-items are listed are designated "New 

IV.X(Y) where X is the table identifier and Y is a sequential number for new lines in that table. Where the same line-item is 

proposed in multiple tables, the other tables are listed below the designation.

2. General Comment 2 (GC2) for Stainless Steel in Treated Borated Water: Neither the 2001 version of the GALL Report nor 

the January 2005 draft revision address the aging effect of loss of material for stainless steel in a treated borated water 

environment. Some sections of GALL note that the effect is minor and specifically not mentioned in GALL. For example, the 

introductory text to table IV.C2 says: The effects of pitting and crevice corrosion on stainless steel components are not significant 

in treated borated water and, therefore, are not included in this section.

NEI pointed out that operating experience has shown loss of material to be a negligible effect because the water chemistry 

requirements minimize contaminants that would lead to loss of material. In other words, the water chemistry programs for PWRs 

manage the aging effect of loss of material. Although the effect is minor, past applications have listed (and future applications will 

list) loss of material as an aging effect for stainless steel in a treated borated water environment with water chemistry as the aging 

management program. Because the aging effect is minor, the water chemistry program by itself is sufficient to manage this aging 

effect, as evidenced by past operating experience.

This was acknowledged in previous SERs including the following excerpt from Farley SER Section 3.1.2.3.1.2, Pitting corrosion 

and crevice corrosion may occur in ASME Code, Class 1, stainless steel or NiCrFe components under exposure to aggressive, 

oxidizing environments. Normally, the presence of elevated dissolved oxygen and/or aggressive ionic impurity concentrations is 

necessary to create these oxidizing environments in the RCS. The applicant’s response to RAI 3.1.3.1.1-1, Part b, provides an 

acceptable explanation for citing the Water Chemistry Control Program as a basis for minimizing the dissolved oxygen and ionic 

impurity concentrations that could otherwise, if left present in high concentrations, lead to an aggressive, oxidizing RCS coolant 

environment. The GALL Report does not indicate that the loss of material due to pitting corrosion or crevice corrosion is an aging 

effect of concern for stainless steel or NiCrFe ASME Code Class 1 components. Since the applicant has conservatively assumed 

that the loss of material due to pitting corrosion or crevice corrosion is an applicable aging effect for these RV components, the 

staff concludes that the Water Chemistry Control Program provides a sufficient mitigative strategy for managing this aging effect 

relative to the recommendations of the GALL Report.

NEI proposed new lines for systems where this MEAP is appropriate. The introductory text indicating the effect is not addressed 

is deleted.
September 2005 A.2.3-43 NUREG-1832

3. General Comment 3 (GC3) Water Chemistry Reference: NEI pointed out that the reference to the specific EPRI document 

need not be included in the Aging Management Program column. This information is identified in the AMP description in Chapter 

XI of GALL.

4. General Comment 4 (GC4) Alloy 600 to Nickel Alloys: Aging issues commonly associated with Alloy 600 also affect other 

nickel alloys such as Alloy 690/52/152. Where appropriate, the term "Nickel Alloys" should replace Alloy 600 to include the 

broader range of materials (this term is defined in GALL Chapter IX). 

5. General Comment 5 (GC5) Add Nickel Alloys: Materials for certain items may include nickel alloy in addition to stainless steel; 

e.g., PWR RVI baffle former bolts. Similarly, some items currently listed, as nickel alloy can also be steel clad with nickel alloy, 

e.g., SG primary side components. The added materials are subject to the same aging effects as those currently listed.

6. General Comment 6 (GC6) Bolting: NEI suggested that, consistent with its Chapter IX comment, high strength low alloy steel 

should be ‘Low alloy steel.’ Also, bolt strength does not impact the fatigue or wear aging mechanisms.

NEI further said that, although some utilities have conservatively applied loss of preload as aging effect for bolting, the industry 

does not consider loss of preload as an aging effect requiring management. In accordance with EPRI 1003056, "Mechanical 

Tool," Appendix F, loss of preload is a design driven effect and not an aging effect requiring management. The bolting at most 

facilities is standard grade B7 carbon steel, or similar material, except in rare specialized applications. Loss of preload due to 

stress relaxation (creep) for this material can only be a concern in very high temperature applications (> 700°F) as stated in the 

ASME Code Section II Part D Table 4 Note 4. However, there is no bolting used in BWRs and PWRs that operate at 700°F, with 

the exception of unique applications, such as the emergency diesel generator exhaust. Therefore, loss of preload due to stress 

relaxation (creep) is not a valid aging effect. 

In addition, NEI stated that the industry has taken actions to address NUREG –1339, "Resolution to Generic Safety Issue 29: 

Bolting Degradation or Failure in Nuclear Power Plants." Licensees have implemented good bolting practices in accordance with 

those referenced in EPRI NP-5769, EPRI NP-5067, and EPRI TR-104213 in normal maintenance and design activities. Normal 

maintenance and design activities thus address the potential for loss of preload such that it is not a concern for the current or 

extended operating term. Proper joint preparation and make-up in accordance with industry standards precludes loss of preload. 

Even other design factors that could contribute to a loss of preload in closure bolting applications, such as vibration, should not 

result in loosening in a properly designed and assembled bolted joint. 

NEI suggested that the impact to the GALL tables is that, with elimination of loss of preload as an aging effect, closure bolting has 

the same MEAP as external surfaces and the lines could be combined.
NUREG-1832 A.2.3-44 September 2005

7. General Comment 7 (GC7) Integration of CASS with Stainless Steel: NEI pointed out that cast austenitic stainless steel 

(CASS) is currently treated as a separate material in GALL. However, with the exception of the loss of fracture toughness due to 

thermal and neutron irradiation embrittlement, CASS and stainless steel share the same aging effects/mechanisms in GALL.

To simplify GALL, NEI suggested that CASS should be treated as a subset of stainless steel. CASS would only be listed as a 

material when loss of fracture toughness due to thermal (or thermal and irradiation) embrittlement is at issue, or where unique

AMP requirements are given. This would provide consistency with GALL’s treatment of other material groups, e.g., gray cast iron 

as a subset of steel, and copper alloy >15% zinc as a subset of copper alloy. Gray cast iron and copper alloy >15% zinc are both 

susceptible to selective leaching and are only listed as materials when selective leaching is addressed.

NEI summarized that this change will have the added benefit of eliminating the need for new MEAP combinations to address 

CASS in non-Class 1 systems where stainless steel is adequately evaluated but CASS, if it is to be considered a separate 

material, is not. CASS is currently listed in only a few lines in Chapters V and VII and not at all in Chapter VIII. 

8. General Comment 8 (GC8) Composite Component Descriptions: NEI pointed out that the combination of some lines to 

produce generic lines resulted in structure/component descriptions that included the components previously (GALL’01) listed in 

the individual lines. These comprehensive lists include components that do not apply to all system/structure tables. For example, 

in table IV.A1 for BWR vessels,line-itemR-04 addresses fatigue for "Piping, piping components, and piping elements; flanges; 

heater sheaths and sleeves; penetrations; pressure housings; pump casing/cover; spray head; thermal sleeves; vessel shell 

heads and welds." Some of these components are not applicable to BWR vessels and may lead to confusion when comparing 

plant AMR results to this line-item of GALL.

NEI noted that the September 2004 version of GALL used generic descriptions, such as "Piping, piping components, and piping 

elements." The reason for the switch from the generic name used in the September version to the compound name in the 

January version is unclear. The compound names will create confusion because specific component types are listed in systems 

that don’t contain those components.

NEI noted that if it is important to maintain the list of component types, component names in the rolled up lines should be split to 

their original configuration so that the list of component types matches the system. Alternatively, the component names should be 

restored to the generic names used in September. As a general rule, a generic line-item (rolled up line) should not be created 

unless the component description can be simplified to be applicable to the systems that use it.

9. General Comment 9 (GC9) Commitments: NEI pointed out that the Aging Management Program entries for many lines have 

been changed. In many lines, AMPs described in GALL Chapter XI were replaced by commitments to be specified in the FSAR 

supplement. These commitments are less well defined than the programs they replaced. Four different commitment statements 

were used in the GALL lines. They are discussed further below, identified by key phrases in each.
September 2005 A.2.3-45 NUREG-1832

(GC9a) "Provide a commitment to implement applicable. (2) staff-accepted industry guidelines." Most of the lines that now list this 

commitment previously listed a GALL described AMP such as XI.M11 no longer existed, "Ni-alloy Nozzles and Penetrations or 

ISI." The Bases Document does not explain why these programs were replaced by an open-ended commitment. The commitment 

itself is unclear.

(GC9b) "submit plant-specific AMP delineating commitments to Orders, Bulletins, or Generic Letters that inspect stipulated 

components for cracking of wetted surfaces" Clarification is requested regarding the meaning of "submit plant-specific AMP 

delineating commitments to Orders, Bulletins, or Generic Letters that inspect stipulated components for cracking of wetted 

surfaces." Is a plant-specific program required only if there are applicable Generic Communications? 

(GC9c) "upon completion of these programs, but not less than 24 months before entering the period of extended operation, 

submit an inspection plan." This commitment statement appears in a large number of lines associated with PWR internals. The 

AMP XI.M16, "PWR Vessel Internals" was formerly used for these lines. This GALL described program was credited in prior 

approved applications. The reason for the change is unclear and the proposed commitment is also unclear. If the industry 

develops a staff accepted program, then submittal of the program would seem unnecessary. What is the intent of submittal 24 

months prior to the POEO? Would submittal 24 months before any proposed inspection be an acceptable reword? 

(GC9d) "submit, for NRC review and approval, an inspection plan for tube support lattice bars" This commitment occurs in only 

one line. The line-item originally referred to a plant-specific program.
NUREG-1832 A.2.3-46 September 2005

This Page Intentionally Left Blank
September 2005 A.2.4-1 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1a EP-39 NEI recommends the creation of 

a new AMR line-item to address 

the aging effect of reduction of 

heat transfer on copper alloy 

heat exchanger tubes exposed 

to closed cycle cooling water 

environment. The aging 

management program 

recommended by NEI was 

GALL AMP XI.M21, "ClosedCycle Cooling Water System."

NEI stated that the reduction of 

heat transfer due to fouling of 

copper alloy heat exchanger 

tubes was not been addressed 

previously. EP-35 already exists 

to manage fouling of stainless 

steel tubes, and because the 

AMP provides for management of 

surface fouling, this program can 

also be applied here (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. A 

new AMR line-item was added as 

proposed by NEI.

The GALL Report was revised to 

address this proposed change.

G-V-GC-1b EP-40 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

reduction of heat transfer/fouling 

in steel heat exchangers tubes 

subject to lubricating oil 

environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI noted that the D.C. Cook 

SER Section 3.2.2.3.3 

acknowledged the potential for 

fouling of copper alloy 

components in a lubricating oil 

environment. The SER addressed 

components in a PWR ECCS 

system, but these conditions 

would be equally applicable to 

components of other lube oil 

systems. Steel heat exchanger 

tubes would also be subject to 

fouling in a lubricating oil 

environment (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. A 

new AMR line-item was added as 

proposed by NEI. However, the AMP 

and FE columns were revised to refer to 

GALL AMP XI.M39, "Lubricating Oil 

Analysis," which was developed to 

identify an acceptable means of 

managing aging of these components. 

The AMP is to be augmented by 

verifying the effectiveness of the 

lubricating oil analysis program.

GALL AMP XI.M32, "One –Time 

Inspection," is an acceptable verification 

program.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-2 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1c EP-42 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/general, pitting, 

and crevice corrosion in steel 

encapsulated components 

subject to Air – indoor 

uncontrolled (internal) 

environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI stated that encapsulation 

components are not currently 

GALL items, but a precedent 

exists for including these items 

based on the Millstone and Farley 

LRAs and corresponding staff 

reviews. The staff aging 

management programs identified 

by these applicants for these 

material and environment 

combinations for loss of material 

in the SERs, Millstone SER 

Section 2.3A.2.3, and Farley SER 

Section 3.2.2.2.2 (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. A 

new AMR line-item was added as 

proposed by NEI. However, the AMP 

and FE columns were revised to refer to 

GALL AMP XI.M38, "Inspection of 

Internal Surfaces in Miscellaneous 

Piping and Ducting Components."

The GALL Report was revised to 

address this proposed change.

G-V-GC-1d EP-43 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/general, pitting, 

and crevice corrosion in steel 

encapsulated components 

subject to air with borated water 

leakage (internal) environment. 

The aging management 

program recommended by NEI 

was a plant-specific program.

NEI stated that encapsulation 

components are not currently 

GALL items, but a precedent 

exists for including these items 

based on the Millstone and Farley 

LRAs and corresponding staff 

reviews. The staff aging 

management programs identified 

by these applicants for these 

material and environment 

combinations for loss of material 

in the SERs, Millstone SER 

Section 2.3A.2.3, and Farley SER 

Section 3.2.2.2.2 (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. The 

AMP and FE columns were also revised 

to refer to GALL AMP XI.M38, 

"Inspection of Internal Surfaces in 

Miscellaneous Piping and Ducting 

Components."

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.4-3 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1e EP-44 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

cracking/stress corrosion 

cracking of stainless steel 

piping, piping elements exposed 

to closed cycle cooling water > 

60o C (>140o F) environment. 

The aging management 

program recommended by NEI 

was GALL AMP XI.M21, 

"Closed-Cycle Cooling Water 

System."

NEI stated that existing GALL row 

AP-60 is also applicable to 

components in ESF systems 

where closed cooling water 

temperatures exceed 60o C or 

140o F in supporting systems 

such as bearing and lube oil 

coolers (see also the endnotes to 

this table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. The 

staff agreed that existing item AP-60 can 

be extended to cover components in 

ESF systems where closed cooling water 

temperatures exceed 140o F in 

supporting systems such as bearing and 

lube oil coolers and associated piping 

that are considered part of the ESF 

systems. Also, EP-33 addresses a 

different aging mechanism for this same 

group of components. 

The GALL Report was revised to 

address this proposed change.

G-V-GC-1f EP-45 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/pitting and 

crevice corrosion of copper alloy 

piping, piping components and 

piping elements exposed to 

lubricating oil environment. The 

aging management program 

recommended by NEI was a 

plant-specific program.

NEI stated that the bases for AP47 and SP-32 are also applicable 

to components such as pump and 

motor lubricating oil systems that 

are included as ESF systems (see 

also the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment. In 

the FCS SER 3.3.2.4.14, the staff took

the position that copper-alloy in a 

lubricating oil environment exhibits a loss 

of material and therefore recommends

an aging management program. The 

AMP and FE columns were revised to 

refer to GALL AMP XI.M39, "Lubricating 

Oil Analysis," which was developed to 

identify an acceptable means of 

managing aging of these components. 

The AMP is to be augmented by 

verifying the effectiveness of the 

lubricating oil analysis program.

GALL AMP XI.M32, "One –Time 

Inspection," is an acceptable verification 

program.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-4 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1g EP-46 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/general, pitting 

and crevice corrosion of steel 

piping, piping components, and 

piping elements exposed to 

lubricating oil environment. The 

aging management program

recommended by NEI was a 

plant-specific program.

NEI stated that the bases for 

AP-30 and SP- 25 are applicable 

to components such as pump and 

motor lubricating oil systems that 

are included as ESF systems (see 

also the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment. The 

basis for the acceptance of this comment 

is the same disposition as comment 

G-V-GC-1f.

The GALL Report was revised to 

address this proposed change.

G-V-GC-1h EP-47 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

reduction of heat transfer/ 

fouling in copper alloy heat 

exchangers tubes subject to 

lubricating oil environment. The 

aging management program 

recommended by NEI was a 

plant-specific program.

NEI stated that in the D.C. Cook 

SER Section 3.2.2.3.3, the staff 

acknowledged the potential for 

fouling of copper alloy 

components in a lubricating oil 

environment. The SER addressed 

components in a PWR ECCS 

system, but these conditions 

would be equally applicable to 

components of other lube oil 

systems (see also the endnotes to 

this table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. A 

new AMR line-item was added as 

proposed by NEI. The AMP and FE 

columns were revised to refer to GALL

AMP XI.M39, "Lubricating Oil Analysis,"

which was developed to identify an 

acceptable means of managing aging of 

these components. The AMP is to be 

augmented by verifying the effectiveness 

of the lubricating oil analysis program.

GALL AMP XI.M32, "One –Time 

Inspection," is an acceptable verification 

program.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.4-5 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1i EP-48 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/general, pitting 

and crevice corrosion on steel 

piping, and piping components, 

and piping elements, internal 

surfaces exposed to closed 

cycle cooling water 

environment. The aging 

management program 

recommended by NEI was 

Chapter XI.M21, "Closed-Cycle 

Cooling Water System."

NEI stated that This is the same 

as line-items RP-10 and A-25 and 

that this also should be extended 

to the containment isolation 

components (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. A 

similar MEAP combination exists as item 

E-17 and the staff agreed to extend this 

item to the containment isolation 

components. 

The GALL Report was revised to 

address this proposed change.

G-V-GC-1j EP-49 NEI recommends the creation of 

a new AMR line-item to address 

the aging effect of 

cracking/under clad cracking of 

steel with stainless steel clad for 

pump casings exposed to 

treated borated water. The 

aging management program 

recommended by NEI was a 

plant-specific program.

NEI stated that unique problems 

with stainless steel cladding have 

been identified in high head safety 

injection pump as noted in NRC 

IN 94-63, Boric Acid Corrosion of 

Charging Pump Casings caused 

by Cladding Cracks," (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment, but 

changed the aging effect/mechanism to 

"Loss of material/cladding breach."

A new AMR line-item EP-49 was 

created, and due to the use of similar 

pumps in the Auxiliary Systems, a similar

line item was also created as AP-85.
NUREG-1832 A.2.4-6 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1k EP-50 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

reduction of heat transfer/fouling 

in stainless steel heat 

exchanger tubes in a lubricating 

oil environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI stated that this line-item is 

similar to EP-40 and 47 (see G-VGC-1b and G-V-GC-1h, 

respectively) except for a different 

material. Heat exchanger tubes of 

stainless steel would also be 

subject to fouling in a lubricating 

oil environment (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. The 

AMP and FE columns were also revised 

to refer to GALL AMP XI.M39, 

"Lubricating Oil Analysis," which was 

developed to identify an acceptable 

means of managing aging of these 

components. The AMP is to be 

augmented by verifying the effectiveness 

of the lubricating oil analysis program.

GALL AMP XI.M32, "One –Time 

Inspection," is an acceptable verification 

program.

The GALL Report was revised to 

address this proposed change.

G-V-GC-1l EP-51 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/pitting and 

crevice corrosion of stainless 

steel piping, piping components, 

and piping elements when 

exposed to lubricating oil 

environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI stated that GALL assumes 

water pooling for the lubricating oil 

environment; therefore, loss of 

material is a plausible aging effect 

that should be managed (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment. The 

AMP and FE columns were also revised 

to refer to GALL AMP XI.M39, 

"Lubricating Oil Analysis," which was 

developed to identify an acceptable 

means of managing aging of these 

components. The AMP is to be 

augmented by verifying the effectiveness 

of the lubricating oil analysis program.

GALL AMP XI.M32, "One –Time 

Inspection," is an acceptable verification 

program.

A new AMR line-item EP-51 was 

created. The GALL Report was revised 

to address this proposed change.
September 2005 A.2.4-7 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1m EP-52 NEI recommends the creation of 

a new AMR line-item to address 

the aging effect/mechanism of 

loss of material/selective 

leaching for gray cast iron heat 

exchanger components in 

closed cycle cooling water. The 

aging management program 

recommended by NEI was 

Chapter XI.M33, "Selective 

Leaching of Materials."

NEI stated that existing GALL 

rows AP-31 and SP-27 are similar 

to proposed line-item except they 

apply to treated water 

environments. In the closed cycle 

cooling water environment, gray 

cast iron exhibits a loss of 

material due to selective leaching 

and therefore recommends

management by a program (see 

also the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment.

A new AMR line-item EP-52 was 

created. However, to more broadly 

encompass the intent, the 

structure/component was changed from 

heat exchanger components to piping, 

piping components, piping elements. 

Existing line item E-43 addresses the 

specific case of the use of gray cast iron 

in the motor cooler heat exchanger for 

the ECCS system.

G-V-GC-1n EP-53 NEI recommends the creation of 

a new AMR line-item to address 

the aging effect/mechanism of 

loss of material/pitting and 

crevice corrosion for stainless 

steel piping, piping components, 

piping elements, and tanks 

when exposed to internal 

condensation environment. The 

aging management program 

recommended by NEI was a 

plant-specific program.

NEI stated that the RWST vent 

line in the Farley LRA is an 

example of this 

material/environment/aging effect 

combination (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment. The 

addition of this item extends the MEAP 

combination for BWRs contained in E-14 

to PWRs.

The GALL Report was revised to 

address this proposed change. A new 

AMR line-item EP-53 was created.
NUREG-1832 A.2.4-8 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-1o EP-54 NEI recommends the creation of 

a new AMR line-item to address 

the aging effects/mechanism of 

loss of material/selective 

leaching on gray cast iron 

piping, piping components, and 

piping elements exposed to soil. 

The aging management 

program recommended by NEI 

was Chapter XI.M33,"Selective 

Leaching of Materials."

NEI stated that the bases for 

AP-42 and SP-26 are applicable 

for buried gray cast iron 

components of the standby gas 

treatment system. E-42 added 

steel in soil for standby gas 

treatment system components. 

This proposed line-item

addresses gray cast iron as a 

subset of those steel components 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. An 

approved precedent exists for adding 

this material, environment, aging effect 

and program combination item to the 

GALL Report. As shown in the FCS SER 

3.3.2.4.16, the staff has accepted the 

position that gray cast iron in a soil 

environment exhibits a loss of material 

due to selective leaching and therefore 

recommends management by a 

program.

The GALL Report was revised to 

address this proposed change. A new 

AMR line-item EP-54 was created.

G-V-GC-1p EP-55 NEI recommends the creation of 

a new AMR line-item to address 

the aging effect/mechanism of 

loss of material/pitting and 

crevice, and microbiologically 

influenced corrosion in stainless 

steel piping, piping components, 

and piping elements, when 

exposed to raw water 

environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI stated that GALL row E-34 

addresses the same material, 

environment, aging effect, and 

plant-specific program for 

containment isolation piping and 

components. See IN 85-30 for 

evidence of micro-biologically 

influenced corrosion (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

1).

The staff agreed with this comment.

A new AMR line-item EP-55 was 

created.
September 2005 A.2.4-9 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-2 EP-41 NEI recommended the creation of 

a new AMR line-item for the 

aging effects and mechanisms of 

loss of material/ pitting and 

crevice corrosion for stainless 

steel and stainless steel cladding 

piping, piping components, and 

piping elements in a treated 

borated water environment. The 

aging management program 

recommended by NEI was GALL 

AMP XI.M2, "Water Chemistry,"

for PWR primary water.

Pitting and crevice corrosion may 

occur in ASME Code Class 1 

stainless steel components under 

exposure to aggressive, oxidizing 

environments. Because the aging 

effect is minor, the water chemistry 

program by itself is sufficient to 

manage this aging effect, as 

evidenced by past operating 

experience (precedent based on 

Farley SER Section 3.1.2.3.1.2, 

and applicant’s response to RAI 

3.1.3.1.1-1) (see also the endnotes 

to this table for NEI’s presentation 

of general comment 2)

The staff agreed with this comment. 

The GALL Report was revised to 

address this proposed change. A new 

AMR line-item EP-41 was created.

G-V-GC-3a E-08

E-37

EP-32

NEI recommended deletion of 

the reference to EPRI document 

TR103515 from the AMP 

column in the line-items.

NEI stated that the reference to 

this specific EPRI document need 

not be included in the line-item

AMP columns because this 

information is provided in Chapter 

XI.M2. Within the AMR line-items, it 

is adequate and internally 

consistent simply to reference AMP 

XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR103515) as GALL AMP XI.M2, 

"Water Chemistry," for BWR water 

(see also the endnotes to this table 

for NEI’s presentation of general 

comment 3).

The staff agreed with this comment. 

Previously, BWRVIP-29 (EPRI TR103515) was referenced in the AMP 

column of the AMR line-items; The AMP 

column was revised to read: "Chapter 

XI.M2 "Water Chemistry," for BWR 

water."

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-10 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-3b E-12

E-38

NEI recommended deletion of

the reference to EPRI document 

TR105714 from the AMP 

column in the line-items.

NEI stated that the reference to 

this specific EPRI document need 

not be included in the line-item

AMP columns because this 

information is provided in XI.M2, 

the AMP description in Chapter XI 

of GALL. Within the AMR lineitems, it is adequate and internally 

consistent simply to reference AMP 

XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -

105714 as GALL AMP XI.M2, 

"Water Chemistry," for PWR 

secondary water (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

3).

The staff agreed with this comment. 

Previously, EPRI TR-105714 was 

referenced in the AMP column of the 

AMR line-items. The staff revised the 

AMP Column to read: "Chapter XI.M2,"

Water Chemistry "for PWR primary 

water."

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.4-11 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-4 E-02

E-06

E-26

E-28

E-30

E-35

E-40

E-42

E-44

E-45

EP-2

EP-24

EP-31

NEI recommended deletion of 

the line-items that address the 

external surfaces of components 

and bolting from the applicable 

systems table and move them to 

a new external surfaces aging 

management program table.

NEI proposed to add this AMP 

"External Surfaces Monitoring."

NEI stated that the appropriate 

location for line-items that 

address external surfaces is for all 

to be co-located in the new 

external surfaces aging 

management program table rather 

than within their applicable 

system tables, but that line-items 

that refer to a unique aging 

management program, e.g., the 

fire protection program, which 

monitors fire doors, should remain 

with the appropriate systems table 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 4).

The staff did not agree with this 

comment. The staff noted that it was 

important for its reviewers to know to 

what system each line-item belonged; 

this information was important and useful 

in performing its reviews to know which 

specific systems are addressed by which 

line-items. The staff thus decided that it 

was more beneficial to the reviewer to

include each line-item in its appropriate 

system rather than to group these 

components by the surface to be 

examined.

The GALL Report was not revised to 

address this proposed change.

For E-26, E-30, E-35, E-40, E-44, and E45 the AMP Columns were changed to 

GALL XI.M36, "External Surfaces 

Monitoring" program.
NUREG-1832 A.2.4-12 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-5 E-17

E-18

E-19

E-20

EP-13

EP-37

NEI recommended deletion of 

the references to reactor type 

and to heat exchanger shell and 

tube side components, as 

appropriate.

NEI stated that many GALL items 

referring to heat exchanger 

components indicate whether the

line-item applies to the tube side 

or the shell side. However, the 

designation of the tube side or 

shell side of a heat exchanger 

unnecessarily limits the 

applicability of the GALL line-item. 

Small heat exchangers in 

particular can be configured with 

the cooled fluid on either the shell 

or tube side. For heat exchangers 

with a given set of materials and 

environments, the configuration of 

the heat exchanger (tube side vs. 

shell side) will not alter the aging 

effects or the aging management 

programs. Consequently, the 

component descriptions for these 

lines should be changed to delete 

the tube side or shell side 

designation (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

5).

The staff agreed with this comment. The 

staff agreed that the aging effects and 

AMPs are applicable to the component, 

regardless of heat exchanger design, 

(i.e., of either shell or tube side) thus, it 

was appropriate to include both sides,

not just one. (Note: As a result of these 

changes, row A-85 was deleted because 

it was identical to A-71)

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.4-13 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-GC-6 EP-24 NEI recommended the deletion 

of this AMR line-item.

NEI stated that loss of preload is 

not an aging effect (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

6).

The staff agreed with this comment. The 

staff agreed that loss of preload due to 

stress relaxation (creep) can only be a 

concern in very high temperature 

applications (> 700°F).

In EPRI TR-104213 and EPRI NP-5067, 

loss of preload due to gasket creep, 

thermal effects (including differential 

expansion and creep or stress 

relaxation), and self-loosening (which 

includes vibration, joint flexing, cyclic 

shear loads, thermal cycles) is 

discussed. The staff determined that this 

combination of aging mechanisms will 

replace ‘stress relaxation.’ Thus the 

replacement aging effect/aging 

mechanism will be loss of preload/ 

thermal effects, gasket creep, and selfloosening.

The GALL Report was modified to 

address this comment.

G-V-GC-7 EP-8 NEI recommended the deletion 

of these line-items.

NEI stated that cast austenitic 

stainless steel is addressed by 

other GALL rows for stainless 

steel effect (see also the 

endnotes to this table for NEI’s 

presentation of general comment 

7).

The staff agreed with this comment. A101, A-41, and A-42 are enveloped by A61, A-60, and A-62, respectively.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-14 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-C-1 EP-33 NEI recommends adding the 

term "internal surfaces" to the 

structure and/or component 

column for this GALL row.

NEI stated that the addition of 

"internal surfaces" will be 

consistent with the rest of GALL 

AMP XI.M21.

The staff did not agree with this 

comment. There are no other GALL rows 

that credit GALL AMP XI.M21 that 

specify "internal surfaces" in the 

structure and/or component column. The 

term "Piping, piping components, and 

piping elements" assumes the internal 

surfaces since the external surfaces are 

usually managed by a different program.

The environment was changed from "Air 

and Steam" to "Steam" because it is 

steam environment that gives rise to 

potential for flow –accelerated corrosion.

The GALL Report was not revised to 

address this proposed change. 

G-V-C-2 E-07 NEI recommends changing the 

environment addressing the 

aging effect/mechanism of wall 

thinning/flow accelerated 

thinning on steel piping from air 

and steam to steam only.

NEI stated that the change in 

environment from "Air and steam"

to "Steam" is because the steam 

lines to the HPCI and RCIC 

Turbine, for which this NUREG 

1801 line-item was meant for, is 

rarely used since these steam 

lines are used less than 2% of the 

time and are therefore not 

susceptible to flow accelerated 

corrosion. The steam drain lines 

however, see constant steam flow 

and are therefore susceptible to 

flow accelerated corrosion.

The staff agreed with this comment. 

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.4-15 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-C-3 E-01

E-34

NEI recommends changing the 

environment from untreated 

water to raw water.

NEI stated that this change is 

consistent with the conforming 

change in Chapter IX.

The staff agreed with this comment. 

The terminology for this environment 

was changed to remove "Untreated 

Water" and instead use "Raw Water."

Due to the additional roll-up, AMR lineitem E-32 was subsumed by E-22.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-16 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-C-4 E-37 NEI recommends adding GALL 

AMP XI.M32, "One Time 

Inspection," for managing this 

aging mechanism, as an 

alternate choice to verify 

effectiveness of the water 

chemistry to prevent cracking.

NEI stated that GALL AMP XI.M7, 

"BWR Stress Corrosion Cracking"

is essentially the applicant’s 

response to Generic Letter (GL) 

88-01, which required increased 

ISI inspections and piping 

material replacement within the 

reactor coolant pressure 

boundary. The GALL Report 

assigns this AMP for ECCS 

systems, specifically in GALL 

lines V.D2.1-c and V.D2.3-c. 

Typically the ECCS Systems do 

not fall under the guidance of GL 

88-01. The reactor coolant 

pressure boundary of the ECCS 

systems may be covered under 

GL-88-01; however those portions 

of the ECCS systems are 

included under GALL Chapter IV 

(Reactor Coolant Pressure 

Boundary), lines IV.C1.1-f and 

IV.C1.3-c.

Therefore, a One-Time Inspection 

AMP should be available as an 

alternate choice to verify 

effectiveness of the water 

chemistry to prevent cracking.

The staff did not agree with this 

comment. GALL AMP XI.M7 needs to be 

supplemented by GALL AMP XI.M2, 

"Water Chemistry," in order to mitigate 

damage caused by corrosion and stress 

corrosion cracking. As noted in GALL 

AMP XI.M7, the program delineated in 

NUREG-0313 and NRC GL 88 01 does 

not provide specific guidelines for 

controlling reactor water chemistry to 

mitigate intergranular stress corrosion 

cracking. Maintaining high water purity 

reduces susceptibility to stress corrosion 

cracking or intergranular stress corrosion 

cracking. Reactor coolant water 

chemistry is monitored and maintained in 

accordance with the guidelines in 

BWRVIP 29 (Electric Power Research 

Institute [EPRI] TR -103515). The 

program description, and evaluation and 

technical basis of monitoring and 

maintaining reactor water chemistry are 

presented in GALL AMP XI.M2, "Water 

Chemistry." This is consistent with other 

GALL rows (i.e., R-20, R-21, R-68, and 

A-61).

The GALL Report was not revised to 

address this proposed change. 
September 2005 A.2.4-17 NUREG-1832

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-C-5 E-38 NEI recommends deleting the 

line-item which addresses the 

aging effect/mechanism of 

cracking/stress corrosion 

cracking of steel with stainless 

steel cladding in safety injection 

tanks (accumulators) in a 

treated borated water >60o C 

(>140 o F) environment.

NEI stated that this is included in 

line-item E-12, and that GALL 

AMP XI.M2, "Water Chemistry,"

for PWR primary water in EPRI 

TR-105714 addresses this issue.

The staff did not agree with this 

comment. The staff decided to retain this 

item so that the stainless steel cladding 

issue is kept separate and because the 

stainless steel cladded safety injection 

tank should not be generalized as a 

typical tank.

The GALL Report was not revised to 

address this proposed change. 

G-V-C-6 E-43 NEI recommended the use of 

the term heat exchangers 

instead of Motor Coolers.

NEI stated that the term "motor 

cooler" is the same as a heat 

exchanger.

The staff did not agree with this 

comment because a motor cooler is not 

the same as a heat exchanger.

The GALL Report was not revised to 

address this proposed change. 

G-V-C-7 EP-32 NEI recommends using AMP 

GALL AMP XI.M2, "Water 

Chemistry" instead of plantspecific for BWR water to 

manage the aging 

effect/management of loss of 

material/pitting and crevice 

corrosion on stainless steel 

piping, piping components, and 

piping elements exposed to 

treated water environment.

NEI stated that the change will be 

consistent with NUREG 1801

lines VII.E4.1-a (A-35) and 

VIII.E.5.-b (S-13).

The staff agreed with this comment.

The AMP Column was revised to read:

Chapter XI.M2, "Water Chemistry" for 

BWR water. The AMP is to be 

augmented by verifying the effectiveness 

of water chemistry control. See Chapter 

XI.M32, "One-Time Inspection," for an 

acceptable verification program.

The GALL Report was revised to 

address this proposed change.
NUREG-1832 A.2.4-18 September 2005

Table A.2.4: Disposition of NEI Comments on Chapter V of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-V-C-8 EP-21

(deleted as 

result of 

advise 

during public 

comment 

period)

NEI recommends to add, "No 

water pooling" to the lubricating 

oil environment column.

NEI stated that GALL assumes 

water pooling for the lubricating oil 

environment. The industry 

assumes that if water pooling is 

present, loss of material is a 

plausible aging effect that should 

be managed. To support a finding 

of no aging effect, the 

environment should be annotated 

to exclude water pooling.

The staff agreed with NEI that with water 

pooling is present in lubricating oil loss of 

material is a plausible aging effect that 

should be managed, The definition of 

lubricating oil stipulates the possibility of 

moisture or contamination, "Lubricating 

oils are low-to-medium viscosity 

hydrocarbons, with the possibility of 

containing contaminants and/or 

moisture, used for bearing, gear, and 

engine lubrication. The GALL AMP 

XI.M39 "Lubricating Oil Monitoring"

addresses this environment. Piping, 

piping components, and piping elements, 

whether copper, stainless steel, or steel, 

when exposed to lubricating oil that does 

not have water pooling, will have limited 

susceptibility to aging degradation, due 

to general or localized corrosion."

The GALL Report was revised to 

address this proposed change.

G-V-C-9 New V.F(1) NEI recommended the creation 

of a new AMR line-item for the 

external surfaces of steel piping, 

piping components, and piping 

elements in a containment 

(inert) environment. NEI 

recommended no aging effect of 

aging management program for 

this new row.

NEI stated that this comment is 

similar to one they had on GALL 

Chapter IX on Containment 

environment (inert).

The staff did not agree with this 

comment. There are situations where the 

containment is not inerted, for example, 

during outages the environment is not 

inerted, and when inerted, leakage is 

allowed per the Technical Specifications. 

Potential exists for aging effects due to 

these conditions.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.4-19 NUREG-1832

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1) for New AMR Line-Items: NEI proposed new AMR line-items which are listed at the end of each 

table. The new lines are designated "New V.X(Y) where X is the table identifier and Y is a sequential number for lines in that 

table. Where the same line-item is proposed in multiple tables, the other tables are listed below the designation.

2. General Comment 2 (GC2) for Stainless Steel in Treated Borated Water: Neither the 2001 version of the GALL Report nor 

the January 2005 draft revision address the aging effect of loss of material for stainless steel in a treated borated water 

environment. Some sections of GALL note that the effect is minor and specifically not mentioned in GALL. For example, the 

introductory text to table IV.C2 says: The effects of pitting and crevice corrosion on stainless steel components are not 

significant in treated borated water and, therefore, are not included in this section.

NEI pointed out that operating experience has shown loss of material to be a negligible effect because the water chemistry 

requirements minimize contaminants that would lead to loss of material. In other words, the water chemistry programs for 

PWRs manage the aging effect of loss of material. Although the effect is minor, past applications have listed (and future 

applications will list) loss of material as an aging effect for stainless steel in a treated borated water environment with water 

chemistry as the aging management program. Because the aging effect is minor, the water chemistry program by itself is 

sufficient to manage this aging effect, as evidenced by past operating experience.

This was acknowledged in previous SERs including the following excerpt from Farley SER Section 3.1.2.3.1.2, Pitting corrosion 

and crevice corrosion may occur in ASME Code, Class 1, stainless steel or NiCrFe components under exposure to aggressive, 

oxidizing environments. Normally, the presence of elevated dissolved oxygen and/or aggressive ionic impurity concentrations is 

necessary to create these oxidizing environments in the RCS. The applicant’s response to RAI 3.1.3.1.1-1, Part b, provides an 

acceptable explanation for citing the Water Chemistry Control Program as a basis for minimizing the dissolved oxygen and 

ionic impurity concentrations that could otherwise, if left present in high concentrations, lead to an aggressive, oxidizing RCS 

coolant environment. The GALL Report does not indicate that the loss of material due to pitting corrosion or crevice corrosion is 

an aging effect of concern for stainless steel or NiCrFe ASME Code Class 1 components. Since the applicant has 

conservatively assumed that the loss of material due to pitting corrosion or crevice corrosion is an applicable aging effect for 

these RV components, the staff concludes that the Water Chemistry Control Program provides a sufficient mitigative strategy 

for managing this aging effect relative to the recommendations of the GALL Report.

NEI proposed new lines for systems where this MEAP is appropriate. The introductory text indicating the effect is not 

addressed is deleted.
NUREG-1832 A.2.4-20 September 2005

3. General Comment 3 (GC3) Water Chemistry Reference: NEI pointed out that the reference to the specific EPRI document 

need not be included in the Aging Management Program column. This information is identified in the AMP description in 

Chapter XI of GALL.

4. General Comment 4 (GC4) External Environments: NEI commented that the introductory text to Chapter V systems tables 

refers to an external surfaces table H at the end of the chapter for aging management programs for the degradation of external 

surfaces of components and miscellaneous bolting. However, many external surfaces and external bolting entries are still within 

the individual systems tables. NEI proposed to move most external surface and external bolting lines to the external table. Any 

lines which refer to a unique aging management program (e.g., Fire Protection Program to monitor fire doors) would remain 

with the system table.

5. General Comment 5 (GC5) Heat Exchanger Components Description: NEI noted that many GALL items referring to heat 

exchanger components indicate whether the line-item applies to the tube side or the shell side. However, the designation of the 

tube side or shell side of a heat exchanger unnecessarily limits the applicability of the GALL line-item. Small heat exchangers in 

particular can be configured with the cooled fluid on either the shell or tube side. For heat exchangers with a given set of 

materials and environments, the configuration of the heat exchanger (tube side vs. shell side) will not alter the aging effects or 

the aging management programs. Consequently, the component descriptions for these lines should be changed to delete the 

tube side or shell side designation. Similarly, some lines list heat exchanger components including tubes. For aging effects 

other than the reduction of heat transfer, tubes may be considered with other heat exchanger components. Thus, for aging 

effects other than reduction of heat transfer, the component description should be "Heat exchanger components." The 

descriptor "Heat exchanger tubes" should be used when addressing reduction of heat transfer. 

6. General Comment 6 (GC6) Bolting: NEI suggested that, consistent with its Chapter IX comment, high strength low alloy steel 

should be ‘Low alloy steel.’ Also, bolt strength does not impact the fatigue or wear aging mechanisms.

NEI further said that, although some utilities have conservatively applied loss of preload as aging effect for bolting, the industry 

does not consider loss of preload as an aging effect requiring management. In accordance with EPRI 1003056, "Mechanical 

Tool," Appendix F, loss of preload is a design driven effect and not an aging effect requiring management. The bolting at most 

facilities is standard grade B7 carbon steel, or similar material, except in rare specialized applications. Loss of preload due to 

stress relaxation (creep) for this material can only be a concern in very high temperature applications (> 700°F) as stated in the 

ASME Code Section II Part D Table 4 Note 4. However, there is no bolting used in BWRs and PWRs that operate at 700°F, 

with the exception of unique applications, such as the emergency diesel generator exhaust. Therefore, loss of preload due to 

stress relaxation (creep) is not a valid aging effect. 

In addition, NEI stated that the industry has taken actions to address NUREG –1339, "Resolution to Generic Safety Issue 29: 

Bolting Degradation or Failure in Nuclear Power Plants." Licensees have implemented good bolting practices in accordance 
September 2005 A.2.4-21 NUREG-1832

with those referenced in EPRI NP-5769, EPRI NP-5067, and EPRI TR-104213 in normal maintenance and design activities. 

Normal maintenance and design activities thus address the potential for loss of preload such that it is not a concern for the 

current or extended operating term. Proper joint preparation and make-up in accordance with industry standards precludes loss 

of preload. Even other design factors that could contribute to a loss of preload in closure bolting applications, such as vibration, 

should not result in loosening in a properly designed and assembled bolted joint. 

NEI suggested that the impact to the GALL tables is that, with elimination of loss of preload as an aging effect, closure bolting 

has the same MEAP as external surfaces and the lines could be combined.

7. General Comment 7 (GC7) Integration of CASS with Stainless Steel: NEI noted that cast austenitic stainless steel (CASS) 

is currently treated as a separate material in GALL. However, with the exception of the loss of fracture toughness due to 

thermal and neutron irradiation embrittlement, CASS and stainless steel share the same aging effects/mechanisms in GALL.

To simplify GALL, NEI recommended that CASS should be treated as a subset of stainless steel. CASS would only be listed as 

a material when loss of fracture toughness due to thermal (or thermal and irradiation) embrittlement is at issue, or where

unique AMP requirements are given. This would provide consistency with GALL’s treatment of other material groups, e.g., gray 

cast iron as a subset of steel, and copper alloy >15% zinc as a subset of copper alloy. Gray cast iron and copper alloy >15% 

zinc are both susceptible to selective leaching and are only listed as materials when selective leaching is addressed.

This change has the added benefit of eliminating the need for new MEAP combinations to address CASS in non-Class 1 

systems where stainless steel is adequately evaluated but CASS, if it is to be considered a separate material, is not. CASS is 

currently listed in only a few lines in Chapters V and V and not at all in Chapter VI.

The changes required in GALL Chapter V are listed below. Each of these lines list CASS alone, and an identical line-item

exists in the system table for stainless steel, so the CASS line-item may be deleted.
NUREG-1832 A.2.4-22 September 2005

This page intentionally left blank.
September 2005 A.2.5-1 NUREG-1832

Table A.2.5: Disposition of NEI Comments on Chapter VI of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.VI-A-1 LP-07 NEI commented for high 

voltage insulators, 

"Degradation of insulation 

quality due to presence of any 

salt deposits and surface 

contamination" is a condition 

that can be caused in a matter 

of hours under the right 

environmental condition rather 

than an aging effect that 

changes the long-term 

physical properties of high 

voltage insulators.

NEI states that the NRC has 

issued 13 SERs covering 26 

reactors with out requiring any one 

of them to have a single program 

for managing aging effects for high 

voltage insulators. NEI states that 

operating experience has not 

reported any adverse conditions.

The staff determined that a large buildup 

of contamination enables the conductor 

voltage to track along the surface more 

easily and can lead to insulator flashover. 

Surface contamination can be a problem 

in areas where greater concentrations of 

airborne particles at facilities that 

discharge soot or near the sea coast 

where salt spray is prevalent. However, 

staff agreed to modify the AMP column of 

the GALL Table VI.A, item LP-07 to state 

as follows:

"A plant-specific aging management 

program is to be evaluated for plants 

located where the potential exists for salt 

deposits or surface contamination (e.g., 

in the vicinity of salt water bodies or 

industrial pollution)."

G.VI-A-2 LP-11 NEI recommends the deletion 

of aging effect/aging 

mechanism as listed for high 

voltage insulators.

NEI states that there has been no 

operating experience to support 

this aging effect. 

The staff did not agree with this comment 

because mechanical wear is an aging 

effect for strain and suspension insulators 

in that they are subject to movement. 

Movement of the insulators can be 

caused by wind blowing the supported 

transmission conductor, causing it to 

swing from side to side. If this swinging is 

frequent enough, it could cause wear in 

the metal contact points of the insulator 

string and between an insulator and the 

supporting hardware.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.5-2 September 2005

Table A.2.5: Disposition of NEI Comments on Chapter VI of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.VI-A-3 LP-04

LP-05

LP-06

LP-10

NEI recommends the use of 

"Metal-Enclosed Bus" instead 

of bus ducts to denote 

electrical bus. 

NEI recommends the change in 

name to differentiate them from out 

side enclosures around the 

electrically conducting bus bar, its 

supports, and insulating 

assemblies

The staff agreed with the definition.

The GALL Report was revised to address 

this proposed change.

G.VI-A-4 LP-08

LP-09

NEI stated that industry has 

not identified any aging effects 

for transmission conductors 

and connections, and for 

switchyard bus and 

connections.

NEI states that the NRC has 

issued 13 SERs covering 26 

reactors with out requiring any one 

of them to have a single program 

for managing aging effects on 

transmission conductors and 

connections, and switchyard bus 

and connections. An aging 

management program is not 

needed for this component based 

on previously approved staff 

positions along with operating 

experience and testing that has

demonstrated greater than an 80-

year service life.

The staff did not agree with this comment 

because transmission conductor vibration 

could be caused by wind loading. Also, 

bolted connections can loosen due to 

thermal cycling. EPRI TR-104213, 

"Bolted Joint Maintenance & Applications 

Guide" recommends inspection of bolted 

joints for evidence of overheating, signs 

of burning or discoloration and indication 

of loose bolts. It recommends checking 

the joint resistance of bolted joints using 

a low range ohm meter. Lastly, the 

applicability of Ontario Hydro’s test of 

ACSR conductor is determined to be 

applicable on a plant-specific basis.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.5-3 NUREG-1832

Table A.2.5: Disposition of NEI Comments on Chapter VI of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.VI-A-5 LP-12 Cable connection metallic 

parts – NEI recommends 

deleting the AMP XI.E6, 

"Electrical Connections Not 

Subject to 10 CFR 50.49 

Environmental Qualification 

Requirements"

This is a proposed AMP that has 

not been published previously, has 

not been proposed in a draft or 

final ISG, and has not been 

required for any previously 

approved license renewal 

application. This AMP should be 

eliminated as these items either 

have no aging effects requiring 

management or are adequately 

covered by other AMPs. Operating 

experience does not indicate a 

need for this proposed program.

The staff did not agree with this comment 

because SAND 96-0344, "Aging 

Management Guidelines For Electrical 

Cable and Terminations," identified 

loosened terminations at several plants. 

Additionally, EPRI TR -104213 

recommends inspection of bolted joints 

for evidence of overheating, signs of 

burning or discoloration and indication of 

loose bolts. It recommends checking the 

joint resistance of bolted joints using a 

low range ohmmeter. GALL AMP XI.E1 

manages the aging of insulating materials 

but not the metallic parts of the electrical 

connections, which is the subject of this 

new AMP.

The GALL Report was not revised to 

address this proposed change.

G.VI-A-6 LP-01 Fuse holders – NEI 

recommends deleting the AMP 

XI.E5, "Fuse Holders."

A new aging management 

program is proposed to monitor 

fuse holders as a special type of 

terminal block. Fuse holders and 

terminal blocks are already 

covered in XI.E1, "Electrical 

Cables and Connections Not 

Subject To 10 CFR 50.49 

Environmental Qualification 

Requirements," and listed in 

NUREG-1800, Table 2.1.5, Item 

77, page 2.1-22 as part of the 

commodity group "Cables and 

Connections, Bus, Electrical 

portions of Electrical and I&C 

Penetration Assemblies." There 

should not need to be a special 

The staff did not agree with this comment 

because GALL AMP XI.E1 covers 

insulation in an adverse environmental 

condition only. ISG-5 included the need 

for an AMR and a new AMP. A new AMR 

row and a new AMP were included in the 

Jan’05 GALL Report. 

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.5-4 September 2005

Table A.2.5: Disposition of NEI Comments on Chapter VI of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

program for a specific type of a 

subcomponent of another AMP, if 

that program adequately covers 

the subcomponent. Most fuse 

holders are a subcomponent of 

active equipment and not subject 

to aging management review. 

Since no fuse holder aging 

management program has 

previously been required for 

nuclear plants with renewed 

licenses, there should be 

provisions for a licensee to show 

that the materials and 

environments for fuse holders do 

not produce stressors that cause 

aging effects requiring 

management and an AMP is 

therefore not required. One 

example of these conditions would 

be a fuse panel installed to the 

manufacturer’s specifications in a 

dry environment without sources of 

water in the vicinity, with both 

normal and peak loadings less 

than the rated amperage for the 

fuse at the design voltage and the 

fuses are not routinely removed for 

circuit isolation purposes.
September 2005 A.2.6-1 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1a AP-73 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of loss of material/ pitting and 

crevice corrosion for stainless 

steel piping, piping components, 

and piping elements in a sodium 

pentaborate solution 

environment. NEI recommended 

by NEI was Chapter XI.M2, 

"Water Chemistry," for PWR 

primary water.

NEI stated that the sodium 

pentaborate solution will 

effectively be treated water. 

Sodium pentaborate solution is 

relatively benign for stainless. 

As for other cases of stainless 

steel in treated water (e.g., A58) loss of material is a possible 

aging effect (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1). 

The staff agreed with this comment. The 

appropriate AMPs to use XI.M2 and 

XI.M32 for this material, environment, 

aging effect, program (MEAP) 

combination based on similar rows in 

GALL (e.g., A-59). GALL AMP XI. M2 can 

be credited for corrosion as well as stress 

corrosion cracking 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-2 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1b AP-74 (a) NEI recommended the 

creation of a new AMR lineitem for the aging effects 

and mechanisms of loss of 

material/ pitting and crevice 

corrosion of aluminum 

piping, piping components, 

and piping elements in a 

condensation environment. 

The aging management 

program recommended by 

NEI was a plant-specific

program.

b) NEI also proposed a similar 

new row for the external 

surfaces of the ventilation 

systems in Chapter VII of 

GALL, and also 

recommended that 

microbiologically influenced 

corrosion be added to the 

aging effect/mechanism 

column and that the AMP 

changed to the External 

Surfaces Monitoring 

Program.

NEI stated that an approved 

precedent exists for this MEAP 

Combination. ANO-2 SER 

Section 3.3.2.3.11 

acknowledges that aluminum 

components in a condensation 

environment are subject to loss 

of material. Aluminum may be 

used in HVAC systems where 

condensation is a possible 

environment. It is typical that the 

condensation would be on the 

outside (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

(a) The staff agreed with this comment. 

This line-item is similar to line-items 

AP-38, EP-26, and SP-24 which 

address loss of material for aluminum 

in a treated water environment, in that 

the condensation environment is 

frequently wetted. The aging 

mechanisms listed in this line-item do 

not include general corrosion, since 

aluminum is not subject to general 

corrosion even in treated water. A 

plant-specific program will manage 

the loss of material for these 

components.

(b) AP-74 does apply to the ventilation 

systems in Chapter VII of GALL. The 

staff did not change the plant-specific

program because this MEAP 

combination applies to more than 

external surfaces.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-3 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1c AP-75

AP-76

NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms 

of hardening and loss of 

strength/elastomer degradation 

and loss of material/ erosion of 

elastomers in a raw water 

environment. The aging 

management program 

recommended by NEI was a 

plant-specific program.

NEI stated that the D.C. Cook 

SER Section 3.3.2.3.2 

acknowledged the potential for a 

change of material properties for 

elastomeric components 

exposed to a raw water 

environment in the open cycle 

cooling water system. Loss of 

elastomer material would be 

addressed by a plant-specific

program (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. 

However, consistent with the D.C. Cook 

SER, the AMP column was revised to

read: Chapter XI.M20, "Open-Cycle 

Cooling Water System." This was

accepted by the staff in the D.C. Cook 

SER Section 3.3.2.1.2.

The GALL Report was revised to address 

this proposed change.

G-VII-GC-1d AP-77 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of reduction of heat 

transfer/fouling for steel heat 

exchanger tubes in a closed 

cycle cooling water environment.

NEI recommended Chapter

XI.M21, "Closed-Cycle Cooling 

Water System."

NEI stated that fouling is an 

aging effect requiring 

management for heat 

exchanger tubes in a closed 

cycle cooling water environment 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. This 

row is similar to other GALL rows (e.g., 

AP-63) except that the material is steel 

versus stainless steel. GALL AMP XI.M21, 

"Closed-Cycle Cooling Water System is 

appropriate for this application."

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-4 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1e AP-78 NEI recommended the creation 

of a new AMR line-items for the 

aging effects and mechanisms 

of loss of material/pitting and 

crevice corrosion for copper 

alloy piping, piping components, 

and piping elements in a 

condensation environment. The

aging management program 

recommended was a plantspecific program.

NEI stated that an approved 

precedent exists for this MEAP 

combination. GALL row A-46 

addresses copper alloy 

components in a condensation 

(external) environment. This 

proposed row is the same as A46 except the condensation is 

on the internal surface of the 

component in the fire protection 

system (see also the endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. 

The staff agrees that an internal 

condensation environment can exist in the 

fire protection system and that this row is 

similar to GALL row A-46 except that the 

condensation is on the internal surface of 

the component. A plant-specific program 

will manage the loss of material for these 

components.

The GALL Report was revised to address 

this proposed change.

G-VII-GC-1f AP-80 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of reduction of heat 

transfer/fouling for copper alloy 

heat exchanger tubes in a

closed cycle cooling water 

environment. NEI recommended 

Chapter XI.M21, "Closed-Cycle 

Cooling Water System."

NEI stated that fouling is an 

aging effect requiring 

management for heat 

exchanger tubes in a closed 

cycle cooling water environment 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 1).

The staff agreed with this comment. This 

row is similar to AP-34 and AP-65 except 

that the aging effect of reduction of heat 

transfer was to account for the internal 

environment of the tubes. GALL AMP is 

XI.M21, "Closed-Cycle Cooling Water 

System, is appropriate for this 

application."

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-5 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1g AP-81 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of loss of material/ pitting and 

crevice corrosion of stainless 

steel piping, piping components, 

and piping elements in a 

condensation environment. The 

aging management program 

recommended by NEI was a 

plant-specific program.

NEI stated that this new row is 

the same as AP-72. It 

addresses stainless steel used 

in compressed air systems (see 

also the endnotes to this table 

for NEI’s presentation of general 

comment 1).

The staff agreed that this row is identical 

to AP-72 with the exception that AP-72 

applies to Non-Safety Related Category 

(A)(2) Systems and was deleted when the 

corresponding section was deleted 

whereas AP-81 applies only to the 

Compressed Air Systems. Thus, the plantspecific AMP for AP-81 was replaced with 

GALL AMP XI.M24, "Compressed Air 

Monitoring." AMR line-item AP-72 was 

deleted when the section (VII K) in which 

it was located, "Non-Safety Related 

Category (A)(2) Systems," was deleted in 

response to advice during the public 

comment period.

The GALL Report was revised to address 

this proposed change.

G-VII-GC-1h AP-82 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of cracking/stress corrosion 

cracking for stainless steel 

piping, piping components, 

piping elements, and tanks in a 

treated water environment. NEI

recommended Chapter XI.M2, 

"Water Chemistry," for PWR 

primary water.

NEI stated that this row is 

identical to E-12 in Chapter V of 

GALL and it should also be 

added to the PWR Chemical 

and Volume Control System 

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 1). 

The staff agreed with this comment. The 

staff agreed that this row is identical to E12 in GALL Chapter V and it should also 

be added to the PWR Chemical and 

Volume Control System. GALL AMP

XI.M2, "Water Chemistry," for PWR 

primary water is appropriate for this 

application.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-6 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1i AP-83 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of loss of material/pitting and 

crevice corrosion for aluminum 

piping, piping components, and 

piping elements in a raw water 

environment. NEI recommended 

Chapter XI.M26, "Fire 

Protection."

NEI stated that the Farley SER 

Section 3.3.2.3.13 for the fire 

protection system 

acknowledges (by reference to 

Table 3.3.2-13 of the Farley 

LRA) that aluminum 

components in a raw water 

environment are subject to loss 

of material which can be 

managed by the fire protection 

program. This line-item is similar 

to lines AP-38, EP-26, and SP24 which address loss of 

material for aluminum in a 

treated water environment. The 

aging mechanisms listed in this

line-item do not include general 

corrosion; since aluminum is not 

subject to general corrosion 

even in treated water (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment. The 

staff agreed that a precedent exists for 

adding this AMR line-item for the fire 

protection system for aluminum 

components in a raw water environment 

that are subject to loss of material, GALL

AMP XI.M26, "Fire Protection" is 

appropriate for this application.

The GALL Report was revised to address 

this proposed change.

G-VII-GC-1j A-35 NEI recommended that VII.E3 

also be added to A-35 for BWR 

reactor water cleanup systems

NEI stated that steel exposed to 

a BWR primary water 

environment is possible in the 

BWR reactor water cleanup 

system. This material and 

environment combination was

approved by the NRC in the 

Dresden/Quad Cities SER 

Section 3.3.2.4.4 (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1)

The staff agreed with this comment. The 

staff agreed that this AMR line-item

should also be extended to the BWR 

reactor water cleanup system.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-7 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1k New 

VII.G(2) and 

H(2)

NEI recommended the creation 

of a new AMR line-items for the 

aging effects and mechanisms 

of loss of material/pitting and 

crevice corrosion for aluminum 

piping, piping components, and 

piping elements in a diesel 

exhaust environment. The aging 

management program 

recommended was a plantspecific program.

NEI stated that ANO-2 SER 

Section 3.3.2.3.4 for the 

alternate AC diesel generator 

system acknowledges (by 

reference to Table 3.3.2-4 of the 

ANO-2 LRA) that aluminum 

components in a diesel exhaust 

environment are subject to loss 

of material. Aluminum would be 

subject to pitting and crevice 

corrosion in this environment. 

This line-item is applied to 

aluminum components in the 

exhaust systems of the fire 

protection diesel generators and 

emergency diesel generators. 

The aging effects for these 

components will be managed by 

a plant-specific program (see 

also the endnotes to this table 

for NEI’s presentation of general 

comment 1).

The staff did not agree with this comment. 

Aluminum is typically not used in a high 

temperature environment. Thus, this 

proposed new AMR line-item appears to 

be plant-specific and not a generic MEAP 

combination.

The GALL Report was not revised to 

address this proposed change.

G-VII-GC-1l New 

VII.G(3)

NEI recommended the creation 

of a new AMR line-items for the 

Fire Protection System for the 

aging effects and mechanisms 

of loss of material/pitting and 

crevice corrosion for steel 

piping, piping components, and 

piping elements in a 

condensation environment. The 

aging management program 

recommended was a plantspecific program.

NEI stated that GALL rows E-27 

and AP-71 already address this 

combination of material, 

environment, aging effect, and 

aging management program for 

other systems. This line-item

addresses the same material 

and environment combination 

which can exist in the fire 

protection system (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 1)

The staff agreed with this comment. Due 

to the changes that were made to A-23 as 

a result of another NEI comment (G-VII-C1), AP-71 was deleted and A-23 was 

revised to extend the applicability of this 

GALL row to the fire protection system.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-8 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-1m New 

VII.H2(1)

NEI recommended the creation 

of a new AMR line-items for the 

aging effects and mechanisms 

of loss of material/pitting and 

crevice corrosion for stainless 

steel piping, piping components, 

and piping elements, and tanks 

in a condensation environment. 

The aging management program 

recommended was a plantspecific program.

NEI stated that starting air 

systems on the diesel engines 

may contain moist (but filtered) 

air. NEI stated that the Farley 

nuclear plant has several 

instances of this condition (see 

also the endnotes to this table 

for NEI’s presentation of general 

comment 1),

The staff did not agree with this comment. 

The staff believes this material in this 

environment is not generically present in 

the emergency diesel generator system. A 

similar row was added to the Compressed 

Air Systems (AP-81, see G-VII-GC-1g) 

where GALL AMP XI.M24 could be used, 

however, this AMP is not applicable to the 

new row that was proposed.

The GALL Report was not revised to 

address this proposed change.

G-VII-GC-2 AP-79 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms 

of loss of material/ pitting and 

crevice corrosion for stainless 

steel and stainless steel 

cladding piping, piping 

components, and piping 

elements in a treated borated 

water environment. NEI 

recommended Chapter XI.M2, 

"Water Chemistry," for PWR 

primary water.

Pitting and crevice corrosion may 

occur in ASME Code Class 1 

stainless steel components under 

exposure to aggressive, oxidizing 

environments. Because the aging 

effect is minor, the water 

chemistry program by itself is 

sufficient to manage this aging 

effect, as evidenced by past 

operating experience (precedent 

based on Farley SER Section 

3.1.2.3.1.2, and applicant’s 

response to RAI 3.1.3.1.1-1)

(see also the endnotes to this 

table for NEI’s presentation of 

general comment 2)

The staff agreed with this comment. Loss 

of material due to pitting and crevice 

corrosion is managed by water chemistry 

requirements. The AMP specification is 

XI.M2, "Water Chemistry," for PWR 

primary water.

A new AMR line-itemAP-79 was created.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-9 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-3a A-35

A-40

A-58

A-59

A-61

A-96

NEI recommended deletion of 

the reference to EPRI document 

TR103515 from the AMP column 

in the line-items.

NEI stated that the reference to 

this specific EPRI document need 

not be included in the line-item

AMP column because this 

information is provided in GALL 

AMP XI.M2. Within the AMR lineitems, it is adequate and 

internally consistent simply to 

reference AMP XI.M2, "Water 

Chemistry," for BWR water in 

BWRVIP-29 (EPRI TR-103515) 

as GALL AMP XI.M2, "Water 

Chemistry," for BWR water (see 

also the endnotes to this table for 

NEI’s presentation of general 

comment 3).

The staff agreed with this comment.

Previously, BWRVIP-29 (EPRI TR103515) was referenced in the AMP 

column of the AMR line-items.

The AMP column was revised to read: 

"Chapter XI.M2, Water Chemistry, for 

BWR water."

The GALL Report was revised to address 

this proposed change.

G-VII-GC-3b A-39

A-56

A-84

A-97

AP-82

NEI recommended deletion of 

the reference to EPRI document 

TR105714 from the AMP column

in the line-items.

NEI stated that the reference to 

this specific EPRI document need 

not be included in the line-item

AMP column because this 

information is provided in AMP 

Chapter XI.M2. Within the AMR 

line-items, it is adequate and 

internally consistent simply to 

reference AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water in EPRI TR-105714 as 

Chapter XI.M2, "Water 

Chemistry," for PWR secondary 

water (see also the endnotes to 

this table for NEI’s presentation 

of general comment 3).

The staff agreed with this comment

Previously, EPRI TR-105714 was 

referenced in the AMP column of the AMR 

line-items; AMP column was revised to 

read: "Chapter XI.M2, Water Chemistry for 

PWR primary water."

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-10 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-4 A-01

A-02

A-05

A-07

A-09

A-10

A-23

A-24

A-46

A-73

A-77

A-79

A-78

A-80

A-94

A-95

A-103

A-104

A-105

AP-01

AP-42

NEI recommended deletion of 

the line-items that address the 

external surfaces of components 

and bolting from the applicable 

systems table and move them to 

a new external surfaces aging 

management program table.

NEI proposed to add this AMP 

"External Surfaces Monitoring."

NEI stated that the appropriate 

location for line-items that 

address external surfaces is for 

all to be co-located in the new 

external surfaces aging 

management program table 

rather than within their 

applicable system tables, but 

that line-items that refer to a 

unique aging management 

program, e.g., the fire protection 

program, which monitors fire 

doors, should remain with the 

appropriate systems table (see 

also the endnotes to this table 

for NEI’s presentation of general 

comment 4).

The staff noted that it was important for its 

reviewers to know to what system each 

line-item belonged; this information was 

important and useful in performing its 

reviews to know which specific systems 

are addressed by which line-items. The 

staff thus decided that it was more 

beneficial to the reviewer to include each 

line-item is in its appropriate system than 

to group these components by the surface 

to be examined.

The GALL Report was not revised to 

address this proposed change.

However, for A-02, general corrosion was 

removed from the AE/M because it is 

already covered under A-01 and the AMP 

in this row (A-02) did not provide for 

general corrosion management. Also, the 

staff extended the applicability to H1 and 

H2, and deleted AP-42 (which was 

duplicative with A-02). 

For A-10, A-24, A-80, A-105 the AMP was 

changed to the new AMP XI.M36, 

"External Surfaces Monitoring" program.
September 2005 A.2.6-11 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-5 A-100

A-63

A-64

A-65

A-66

A-67

A-68

A-69

A-70

A-71

A-84

A-85

AP-34

AP-39

AP-40

AP-41

AP-65

NEI recommended deletion of 

the references to reactor type 

and to heat exchanger shell and 

tube side components, as 

appropriate.

NEI stated that many GALL 

items referring to heat 

exchanger components indicate 

whether the line-item applies to 

the tube side or the shell side.

However, the designation of the 

tube side or shell side of a heat 

exchanger unnecessarily limits 

the applicability of the GALL 

line-item. Small heat 

exchangers in particular can be 

configured with the cooled fluid 

on either the shell or tube side. 

For heat exchangers with a 

given set of materials and 

environments, the configuration 

of the heat exchanger (tube side 

vs. shell side) will not alter the 

aging effects or the aging 

management programs. 

Consequently, the component 

descriptions for these lines 

should be changed to delete the 

tube side or shell side 

designation (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 5).

The staff agreed that the aging effects and 

AMPs are applicable to the component, 

regardless of heat exchanger design, (i.e., 

of either shell or tube side) thus, it was 

appropriate to include both sides, not just 

one. (Note: As a result of these changes, 

row A-85 was deleted because it was 

identical to A-71)

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-12 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-GC-6 AP-26 NEI recommended the deletion 

of this AMR line-item.

NEI stated that loss of preload is 

not an aging effect (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 6).

The staff agreed that loss of preload due 

to stress relaxation (creep) can only be a 

concern in very high temperature 

applications (> 700°F). 

In EPRI TR-104213 and EPRI NP-5067, 

loss of preload due to gasket creep, 

thermal effects (including differential 

expansion and creep or stress relaxation), 

and self-loosening (which includes 

vibration, joint flexing, cyclic shear loads, 

thermal cycles) is discussed. The staff

determined that this combination of aging 

mechanisms will replace ‘stress 

relaxation.’ Thus the replacement aging 

effect/aging mechanism will be loss of 

preload/ thermal effects, gasket creep, 

and self-loosening.

The GALL Report was modified to 

address this comment.

G-VII-GC-7 A-101

A-41

A-42

AP-7

NEI recommended the deletion 

of these line-items.

NEI stated that cast austenitic 

stainless steel is addressed by 

other GALL rows for stainless 

steel

The staff agreed with this comment. A101, A-41, and A-42 are enveloped by A61, A-60, and A-62, respectively.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-13 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-C-1 A-23 NEI recommended changing the 

environment from Moist air to 

Condensation (internal) to reflect 

moisture in the emergency 

diesel starting air system. 

NEI stated that the aging effects 

are the same for both 

environments and the definition 

in Chapter IX says the two 

environments are similar.

The staff agreed with this comment. As a 

result of this change, the staff determined 

that AP-71 was identical to A-23. Thus, 

AP-71 was deleted and the related items 

column of A-23 was revised to make it 

applicable to the same systems as AP-71. 

The AMP column was also revised to 

read: Chapter XI.M38, "Inspection of 

Internal Surfaces in Miscellaneous Piping 

and Ducting Components."

The GALL Report was revised to address 

this proposed change.

G-VII-C-2 A-32

AP-25

NEI recommended the deletion 

of this AMR line-item.

NEI stated that this item is 

addressed under item VII.C1-20 

(A-38).

The staff agreed with this comment. The 

related item rows for A-32 and AP-25 

were transferred to the related items 

column for A-38. The materials column for 

A-38 was also revised to indicate that this 

may be steel with or without lining/coating. 

The aging effect/mechanism column was 

also revised to add "and lining/coating 

degradation" similar to rows A-39 and

 A-40. 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-14 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-C-3 A-50 NEI recommended deleting 

pitting and crevice corrosion 

from the AERM. 

Correspondingly, NEI 

recommended that XI.M21, 

"Closed-Cycle Cooling Water 

System," be deleted from the 

AMP column.

NEI noted that row A-25 

includes general, pitting and 

crevice corrosion for steel which 

includes gray cast iron for these 

mechanisms.

The staff agreed with this comment. The 

staff agreed that this AMR line-item

should only address selective leaching 

since the aging mechanisms of general, 

pitting and crevice corrosion are 

addressed in A-31. 

The GALL Report was revised to address 

this proposed change.

Also, this row is similar to AP-31; thus, F3 

(PWR Steam Generator Blowdown 

System) was added to the related item 

column to address the NEI comment (see 

G-VII-C-9) to change the environment to 

closed cycle cooling water.

G-VII-C-4 AP-57

(deleted 

following the 

public 

comment 

period)

NEI recommended that the 

reference to C2 in the related 

item column be deleted.

NEI stated that closed cycle 

cooling water environment is 

associated with use of GALL 

AMP XI.M.21, "Closed-Cycle 

Cooling Water System"; 

therefore, it is already covered 

by VII.C2-9 (A-52).

The staff agreed with this comment. The 

staff agreed that this AMR line-item

should not apply to VII.C2, "Closed-Cycle 

Cooling Water System," since this 

addressed in A-52. Thus the AMR lineitem AP-57 was deleted following the 

public comment period.

The GALL Report was revised to address 

this proposed change.

G-VII-C-5 A-59 NEI recommended to add 

">60°C (>140°F)" at the end of 

the environment column.

NEI stated that sodium 

pentaborate solution is relatively 

benign for stainless. Water 

chemistry controls will assure 

contaminants are minimized so 

>140 F temperature threshold 

for cracking is applicable.

The staff agreed with this comment. The 

staff agreed that this temperature 

threshold is appropriate for cracking to 

occur.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.6-15 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-C-6 A-90 NEI recommend deleting freezethaw from the aging 

effect/mechanism column.

NEI stated that freeze-thaw is 

not possible in an Air - indoor 

uncontrolled environment.

The staff agreed with this comment. The 

staff agreed that freeze-thaw is not 

possible in an air-indoor uncontrolled 

environment.

The GALL Report was revised to address 

this proposed change.

G-VII-C-7 AP-64 NEI recommended that the 

reference to C2 in the related 

item column be deleted.

NEI noted that that environment 

for VII.C2 should be closed 

cycle cooling water not treated 

water. Therefore, this row is 

duplicative to AP-12.

The staff agreed with this comment.

The staff agreed that the closed cycle 

cooling water AMP be deleted from this

line-item because the environment is 

treated water. Thus, the staff deleted 

VII.C2, "Closed-Cycle Cooling Water 

System"; from the related field because it 

is associated with closed cycle cooling, 

which is covered by AP-12. No change to 

AP-12 was required.

The appropriate AMP description is 

Chapter XI.M2, "Water Chemistry," for 

BWR water. The AMP is to be augmented 

by verifying the effectiveness of water 

chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.6-16 September 2005

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-C-8 AP-29

(deleted 

following the 

public 

comment 

period)

NEI recommended that the 

environment for this row be 

changed from untreated water to 

raw water.

NEI stated that this change is 

consistent with the environment 

for other GALL rows in the fire 

protection system.

The staff agreed with this comment. The 

staff revised the environment from 

untreated water to raw water to be 

consistent with the terminology for this 

fluid system throughout the GALL Report.

The AMR line-item AP-29 was deleted 

since it is now duplicative of A-51.

The GALL Report was revised to address 

this proposed change.

G-VII-C-9 AP-31 NEI recommended that the 

environment for this row be 

changed to closed cycle cooling 

water for related item F3 only 

(Primary Containment Heating 

and Ventilation System).

NEI stated that this environment 

is consistent with other steel 

environments.

The staff agreed with this comment.

Related item F3 was moved to A-50 since 

this row addresses closed cycle cooling 

water for the same material and aging 

effect/mechanism as AP-31.

The GALL Report was revised to address 

this proposed change.

G-VII-C-10 AP-35

AP-44

NEI recommended deleting 

Chapter XI.M32, "One-Time 

Inspection," from the AMP 

column.

NEI stated that if a chemistry 

program is consistent with GALL

then water is not allowed to 

accumulate and aging effect will 

not occur. Thus, NEI believes 

that that there is no need for a 

One-Time Inspection.

The staff did not agree with this comment.

GALL AMP XI.M30 does not contain any 

requirements to verify the absence of 

water; thus this program is required to be 

supplemented by XI.GALL AMP M32 

consistent with other GALL rows. (Note: 

M32 was also added to GALL row AP-54) 

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.6-17 NUREG-1832

Table A.2.6: Disposition of NEI Comments on Chapter VII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VII-C-11 AP-44 NEI recommended deleting 

"(Water as a contaminant)" from 

the fuel oil environment.

NEI stated the use of the phrase 

(water as a contaminant) is 

confusing. NEI stated that it is 

not clear in Chapter IX or by this 

entry what the difference is and 

why this is needed. This phrase 

is rarely used and is not 

consistent.

The staff agreed with this comment. The 

staff agreed that the term "(Water as a 

contaminant)" is not needed since the 

definition of Fuel Oil in GALL Chapter IX 

notes that water contamination is 

possible.

The GALL Report was revised to address 

this proposed change.

G-VII-C-12 AP-60 NEI recommended adding 

Chapter XI.M21, "Closed -Cycle 

Cooling Water System" to the 

AMP column for managing 

cracking.

NEI noted that in the Farley 

LRA, the Water Chemistry 

Control Program satisfies the 

recommendation of GALL AMP 

XI.M21 to manage cracking in 

stainless steel in this 

environment. This was

approved by the NRC in Section 

3.0.3.2.1 of the Farley SER.

The staff agreed with this comment. The 

AMP column was revised to read:

"Chapter XI.M21 "Closed –Cycle Cooling 

Water System." and no further evaluation 

is required. GALL AMP XI.M21 has also 

been revised to allow it to properly 

manage stress corrosion cracking.

The GALL Report was revised to address 

this proposed change.

G-VII-C-13 New VII.J(1) NEI recommended the creation 

of a new AMR line-item for the 

external surfaces of steel piping, 

piping components, and piping 

elements in a containment (inert) 

environment. NEI recommended 

no aging effect of aging 

management program for this 

new row.

NEI stated that this comment is 

similar to one they had on GALL

Chapter IX on Containment 

environment (inert).

The staff did not agree with this comment.

There are situations where the 

containment is not inerted, for example, 

during outages the environment is not 

inerted, and when inerted, leakage is 

allowed per the Technical Specifications.

Potential exists for aging effects due to 

these conditions.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.6-18 September 2005

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1) for New AMR Line-Items: NEI proposed new lines items are listed at the end of each table. The 

new lines are designated "New VII.X(Y) where X is the table identifier and Y is a sequential number for lines in that table.

Where the same line-item is proposed in multiple tables, the other tables are listed below the designation.

2. General Comment 2 (GC2) for Stainless Steel in Treated Borated Water: Neither the 2001 version of the GALL Report nor 

the January 2005 draft revision address the aging effect of loss of material for stainless steel in a treated borated water 

environment. Some sections of GALL note that the effect is minor and specifically not mentioned in GALL. For example, the 

introductory text to table IV.C2 says: The effects of pitting and crevice corrosion on stainless steel components are not 

significant in treated borated water and, therefore, are not included in this section.

NEI pointed out that operating experience has shown loss of material to be a negligible effect because the water chemistry 

requirements minimize contaminants that would lead to loss of material. In other words, the water chemistry programs for 

PWRs manage the aging effect of loss of material. Although the effect is minor, past applications have listed (and future 

applications will list) loss of material as an aging effect for stainless steel in a treated borated water environment with water 

chemistry as the aging management program. Because the aging effect is minor, the water chemistry program by itself is 

sufficient to manage this aging effect, as evidenced by past operating experience.

This was acknowledged in previous SERs including the following excerpt from Farley SER Section 3.1.2.3.1.2, Pitting corrosion 

and crevice corrosion may occur in ASME Code, Class 1, stainless steel or NiCrFe components under exposure to aggressive, 

oxidizing environments. Normally, the presence of elevated dissolved oxygen and/or aggressive ionic impurity concentrations is 

necessary to create these oxidizing environments in the RCS. The applicant’s response to RAI 3.1.3.1.1-1, Part b, provides an 

acceptable explanation for citing the Water Chemistry Control Program as a basis for minimizing the dissolved oxygen and 

ionic impurity concentrations that could otherwise, if left present in high concentrations, lead to an aggressive, oxidizing RCS 

coolant environment. The GALL Report does not indicate that the loss of material due to pitting corrosion or crevice corrosion is 

an aging effect of concern for stainless steel or NiCrFe ASME Code Class 1 components. Since the applicant has 

conservatively assumed that the loss of material due to pitting corrosion or crevice corrosion is an applicable aging effect for 

these RV components, the staff concludes that the Water Chemistry Control Program provides a sufficient mitigative strategy 

for managing this aging effect relative to the recommendations of the GALL Report.

NEI proposed new lines for systems where this MEAP is appropriate. The introductory text indicating the effect is not 

addressed is deleted.
September 2005 A.2.6-19 NUREG-1832

3. General Comment 3 (GC3) Water Chemistry Reference: NEI pointed out that the reference to the specific EPRI document 

need not be included in the Aging Management Program column. This information is identified in the AMP description in 

Chapter XI of GALL.

4. General Comment 4 (GC4) External Environments: NEI commented that the introductory text to Chapter VII systems tables 

refers to an external surfaces table H at the end of the chapter for aging management programs for the degradation of external 

surfaces of components and miscellaneous bolting. However, many external surfaces and external bolting entries are still 

within the individual systems tables. NEI proposed to move most external surface and external bolting lines to the external 

table. Any lines which refer to a unique aging management program (e.g., Fire Protection Program to monitor fire doors) would 

remain with the system table.

5. General Comment 5 (GC5) Heat Exchanger Components Description: NEI noted that many GALL items referring to heat 

exchanger components indicate whether the line-item applies to the tube side or the shell side. However, the designation of the 

tube side or shell side of a heat exchanger unnecessarily limits the applicability of the GALL line-item. Small heat exchangers 

in particular can be configured with the cooled fluid on either the shell or tube side. For heat exchangers with a given set of 

materials and environments, the configuration of the heat exchanger (tube side vs. shell side) will not alter the aging effects or 

the aging management programs. Consequently, the component descriptions for these lines should be changed to delete the 

tube side or shell side designation. Similarly, some lines list heat exchanger components including tubes. For aging effects 

other than the reduction of heat transfer, tubes may be considered with other heat exchanger components. Thus, for aging 

effects other than reduction of heat transfer, the component description should be "Heat exchanger components." The 

descriptor "Heat exchanger tubes" should be used when addressing reduction of heat transfer. 

6. General Comment 6 (GC6) Bolting: NEI suggested that, consistent with its Chapter IX comment, high strength low alloy steel 

should be ‘Low alloy steel.’ Also, bolt strength does not impact the fatigue or wear aging mechanisms.

NEI further said that, although some utilities have conservatively applied loss of preload as aging effect for bolting, the industry 

does not consider loss of preload as an aging effect requiring management. In accordance with EPRI 1003056, "Mechanical 

Tool," Appendix F, loss of preload is a design driven effect and not an aging effect requiring management. The bolting at most 

facilities is standard grade B7 carbon steel, or similar material, except in rare specialized applications. Loss of preload due to 

stress relaxation (creep) for this material can only be a concern in very high temperature applications (> 700°F) as stated in the 

ASME Code Section II Part D Table 4 Note 4. However, there is no bolting used in BWRs and PWRs that operate at 700°F, 

with the exception of unique applications, such as the emergency diesel generator exhaust. Therefore, loss of preload due to 

stress relaxation (creep) is not a valid aging effect. 

In addition, NEI stated that the industry has taken actions to address NUREG –1339, "Resolution to Generic Safety Issue 29: 

Bolting Degradation or Failure in Nuclear Power Plants." Licensees have implemented good bolting practices in accordance 
NUREG-1832 A.2.6-20 September 2005

with those referenced in EPRI NP-5769, EPRI NP-5067, and EPRI TR-104213 in normal maintenance and design activities.

Normal maintenance and design activities thus address the potential for loss of preload such that it is not a concern for the 

current or extended operating term. Proper joint preparation and make-up in accordance with industry standards precludes loss 

of preload. Even other design factors that could contribute to a loss of preload in closure bolting applications, such as vibration, 

should not result in loosening in a properly designed and assembled bolted joint. 

NEI suggested that the impact to the GALL tables is that, with elimination of loss of preload as an aging effect, closure bolting 

has the same MEAP as external surfaces and the lines could be combined.

7. General Comment 7 (GC7) Integration of CASS with Stainless Steel: NEI noted that cast austenitic stainless steel (CASS) 

is currently treated as a separate material in GALL. However, with the exception of the loss of fracture toughness due to 

thermal and neutron irradiation embrittlement, CASS and stainless steel share the same aging effects/mechanisms in GALL.

To simplify GALL, NEI recommended that CASS should be treated as a subset of stainless steel. CASS would only be listed as 

a material when loss of fracture toughness due to thermal (or thermal and irradiation) embrittlement is at issue, or where 

unique AMP requirements are given. This would provide consistency with GALL’s treatment of other material groups, e.g., gray 

cast iron as a subset of steel, and copper alloy >15% zinc as a subset of copper alloy. Gray cast iron and copper alloy >15% 

zinc are both susceptible to selective leaching and are only listed as materials when selective leaching is addressed.

This change has the added benefit of eliminating the need for new MEAP combinations to address CASS in non-Class 1 

systems where stainless steel is adequately evaluated but CASS, if it is to be considered a separate material, is not. CASS is 

currently listed in only a few lines in Chapters V and VII and not at all in Chapter VIII.

The changes required in GALL Chapter VII are listed below. Each of these lines list CASS alone, and an identical line-item 

exists in the system table for stainless steel, so the CASS line-item may be deleted.
September 2005 A.2.7-1 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1a SP-43

SP-44

SP-45

SP-46

NEI recommended the creation 

of a new AMR line-items for the 

aging effects and mechanisms of 

cracking and stress corrosion 

cracking, loss of material/pitting 

and crevice corrosion, of 

stainless steel piping, piping 

components, and piping 

elements in a steam 

environment. NEI recommended 

Chapter XI.M2, "Water 

Chemistry," augmented by 

Chapter XI.M32, "One-Time 

Inspection."

NEI stated that the aging effects 

and mechanisms of cracking 

and stress corrosion cracking of 

stainless steel piping, piping 

components, and piping 

elements in a steam 

environment were already 

included in the main steam 

system, as identified in line-item

SP-45, SP-44, SP-46, and SP43, respectively, and that it was 

appropriate to address 

components of the same MEAP 

combination that existed in the 

steam turbine (also see 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. The 

existing MEAP combinations noted by 

NEI were extended to cover the BWR and 

PWR steam turbine systems. 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.7-2 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1b SP-30

SP-31

NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms of 

loss of material/pitting, crevice 

and microbiologically influenced 

corrosion, and loss of 

material/selective leaching, of 

copper alloy piping, piping 

components, and piping 

elements in a raw water 

environment. NEI recommended 

Chapter XI.M20, "Open-Cycle 

Cooling Water System," for loss 

of material/pitting, crevice and 

microbiologically influenced 

corrosion. This program 

implements the requirements of 

Generic Letter 89-13, "Service 

Water System Problems 

Affecting Safety-Related 

Equipment." For the aging 

effect/mechanism of loss of 

material/selective leaching, the 

recommended program is 

Chapter XI.M33, "Selective 

Leaching of Materials."

NEI stated that components of 

these MEAP combinations 

addressed the exciter and the 

isophase bus coolers of the 

turbines. NEI stated that this 

GALL AMP XI.M20 (Generic 

Letter 89-13), is appropriate for 

both safety-related and nonsafety-related applications, and 

that it also applies to water 

chemistry, as it is normally the 

service water system; the 

service water system aging 

management program is more 

comprehensive than Generic 

Letter 89-13. These new AMR 

line-items are the same as SP31 and SP-30, respectively 

(also see endnotes to this table 

for NEI’s presentation of general 

comment 1).

The staff agreed with this comment. The 

existing MEAP combinations noted by 

NEI were extended to be included in 

VIII.A SPCS Steam Turbine System to 

cover the exciter coolers and the 

isophase bus coolers of the turbines.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-3 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1c SP-27

SP-28

NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms of 

loss of material/selective 

leaching of gray cast iron piping, 

piping components, and piping 

elements in treated and raw 

water environments. NEI

recommended Chapter XI.M33, 

"Selective Leaching of Materials"

for this application.

NEI stated that there is a need 

to address the selective 

leaching of gray cast iron.

These new AMR line-items are 

the same as SP-27 and SP-28, 

respectively (also see endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. The 

existing MEAP combinations noted by 

NEI were extended to cover the BWR and 

PWR steam turbine systems. However, 

the staff regarded the environment of 

"untreated water" to be inconsistent with 

line-items in other chapters. The staff

changed this environment to "raw water,"

to be consistent throughout the GALL 

Report.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1d S-23 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

loss of material/general, pitting, 

and crevice corrosion of steel 

heat exchanger components in a 

closed cycle cooling water 

environment. NEI recommended

Chapter XI.M21, "Closed–Cycle 

Cooling Water System," for this 

application.

NEI stated that this new AMR 

line-item addressed the stator 

coolers, which had not been 

addressed. This line-item was 

the same as S-23 (also see 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. The 

existing MEAP combinations noted by 

NEI were extended to cover the BWR and 

PWR steam turbine systems. 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.7-4 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1e SP-61 NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms of 

loss of material/general, pitting, 

and crevice corrosion of copper 

alloy piping, piping components, 

and piping elements in a treated 

water environment. The NEIrecommended aging 

management program was 

Chapter XI.M2, "Water 

Chemistry."

NEI stated that these new AMR 

line-items complimented the 

new AMR line-item VIII.F1 in 

that they addressed the loss of 

material of general, pitting, and 

crevice corrosion, in addition to 

selective leaching, which is 

already addressed, and which 

can apply to all copper alloys 

(also see endnotes to this table 

for NEI’s presentation of general 

comment 1).

The staff reviewed these components and 

agreed that, while the selective leaching 

of copper alloy piping, piping 

components, and piping elements had 

been addressed, the aging mechanisms 

of general, pitting, and crevice corrosion 

had not been addressed. However, NEI 

had recommended that no further 

evaluation be required. The staff

disagreed with this assessment and 

decided that the detection of aging effects 

was to be evaluated. Further, the staff 

noted that there was no validation 

program. Thus, staff added a verification 

program to read: Chapter XI.M32, "OneTime Inspection," is unacceptable 

verification program.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1f SP-60 NEI recommended a new AMR 

line-item for the aging effects and 

mechanisms of loss of 

material/general, pitting, and 

crevice corrosion of the internals 

of steel piping, piping 

components, and piping 

elements in a condensation 

environment. The NEIrecommended aging 

management program was a 

plant-specific aging management 

program.

NEI stated that this new AMR 

line-item would address such 

components as steam piping 

that remains empty, when it in a 

standby condition. This piping 

would include AFW turbine 

steam lines during normal 

operation. MIC cannot occur 

here, as the water condenses 

from temperatures in excess of 

2120F. (also see endnotes to 

this table for NEI’s presentation 

of general comment 1).

The staff agreed with this comment with 

modification to cover steam piping that is 

empty in standby condition during normal 

operations, such as AFW turbine steam 

lines. The AMP column was revised to 

read: Chapter XI.M38, "Inspection of 

Internal Surfaces in Miscellaneous Piping 

and Ducting Components" which is a new 

AMP developed to apply to manage aging 

on internal piping surfaces.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-5 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1g S-09

S-10

SP-16

SP-17

NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms of 

cracking/stress corrosion 

cracking and loss of 

material/pitting and crevice 

corrosion, loss of material/ 

general, pitting, and crevice 

corrosion, of stainless steel and 

steel piping, piping components, 

and piping elements in a treated 

water environment. NEI 

recommended Chapter XI.M2, 

"Water Chemistry" for PWR 

secondary water, augmented by 

"Chapter XI.M32, "One-Time 

Inspection," for this application.

NEI stated that this new AMR 

line-item was added to include 

the treated water environment 

that exists due to steam 

condensation from drain 

lines/drain pots, etc. This lineitem is the same as SP-17, SP16, S-10, and S-09 (also see 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment. The 

existing MEAP combinations noted by 

NEI were extended to cover the BWR and 

PWR main steam systems.

The GALL Report was revised as 

described above to address this 

comment.

G-VIII-GC-1h S-16 NEI recommended the creation 

of new AMR line-items for the 

aging effect and mechanism of 

wall thinning/flow-accelerated 

corrosion, of steel piping, piping 

components, and piping 

elements in a treated water 

environment. The aging 

management program 

recommended by NEI was 

"Chapter XI.M17, "FlowAccelerated Corrosion," for this 

application

NEI stated that this new AMR 

line-item was added to include 

the treated water environment 

that exists due to steam 

condensation from drain 

lines/drain pots, etc. This lineitem is the same as S-16 (also 

see endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff did not agree with this comment

because the drain lines/pots, etc. are only 

exposed to low flow conditions. Thus, the 

potential for wall thinning/flow 

accelerated-corrosion does not exist.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.7-6 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1i SP-59 NEI recommended the creation 

of new AMR line-items for the 

aging effects and mechanisms of 

loss of material/general, pitting, 

and crevice corrosion of steel 

piping, piping components, and 

piping elements internals in an 

outdoor air environment. NEI 

recommended GALL AMP

XI.M32, "One-Time Inspection,"

for this application.

NEI stated that this new AMR 

line-item was added to include 

the interior surfaces of the main 

steam safety vents to 

atmosphere downstream of the 

safety valves. This line-item is 

similar to other lines with the 

combination of steel, outdoor 

air, and loss of material, such as 

line-item A-24. However, where

line-item A-24 refers to a plantspecific program, this line-item 

uses a one time inspection (also 

see endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff agreed with this comment with 

modification to cover the interior surfaces 

of the main steam safety vents to 

atmosphere downstream of safety valves.

The AMP column was revised to read:

"Chapter XI.M38, "Inspection of Internal 

Surfaces in Miscellaneous Piping and 

Ducting Components." GALL AMP 

XI.M38 was developed to apply to 

manage aging on internal piping surfaces.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1j SP-57 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

reduction of heat transfer/fouling

of copper alloy heat exchanger 

tubes in a closed cycle cooling 

water environment. NEI 

recommended GALL AMP

XI.M21, "Closed Cycle Cooling 

Water System," for this 

application.

NEI stated that this AMR lineitem applies to any heat 

exchanger with closed cycle 

cooling water on either side of 

the heat exchanger tubes. It is 

similar to AP-63, but for a 

different material (also see 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment and 

agreed that the copper alloy heat 

exchanger tubes in a closed cycle cooling 

water environment could result in 

reduction of heat transfer.

A new AMR line-item SP-57 was created

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-7 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1k SP-56 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

reduction of heat transfer/fouling 

of copper alloy heat exchanger 

tubes in a raw water 

environment. NEI recommended 

GALL AMP XI.M20, "Open Cycle 

Cooling Water," for this 

application.

NEI stated that this AMR lineitem applies to any heat 

exchanger with raw water on 

either side of the heat 

exchanger tubes. It is the same 

as A-72 (also see endnotes to 

this table for NEI’s presentation 

of general comment 1).

The staff agreed with this comment and 

agreed that the copper alloy heat 

exchanger tubes in a raw water 

environment could result in reduction of 

heat transfer.

A new AMR line-item SP-56 was created.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1l SP-58 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

reduction of heat transfer/fouling 

of copper alloy heat exchanger 

tubes in a treated water 

environment. NEI recommended 

GALL AMP XI.M2, "Water 

Chemistry," for this application.

NEI stated that this AMR lineitem applies to any heat 

exchanger with treated water on 

either side of the heat 

exchanger tubes. It is similar as 

SP-40, but for a different 

material (also see endnotes to 

this table for NEI’s presentation 

of general comment 1).

The staff agreed that the copper alloy 

heat exchanger tubes in a treated water 

environment could result in reduction of 

heat transfer. However, the staff 

concluded that a validation program was 

necessary, and included in the AMP 

column XI.M32, "One-Time Inspection."

Chapter XI.M32 is an acceptable 

verification program.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1m SP-55 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

loss of material/selective 

leaching of copper alloy >15% 

zinc piping, piping components, 

and piping elements in a treated 

water environment. NEI

recommended GALL AMP

XI.M33, "Selective Leaching of 

Materials," for this application

NEI stated that this AMR lineitem applies to heat exchanger 

items and other supporting 

equipment. It is the same as 

AP-32 (also see endnotes to 

this table for NEI’s presentation 

of general comment 1).

The staff agreed with this comment and 

agreed that the copper alloy piping in a 

treated water environment would result in 

loss of material.

A new AMR line-item SP-55 was created.
NUREG-1832 A.2.7-8 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1n SP-54 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

cracking/stress corrosion 

cracking of stainless steel piping, 

piping components, and piping 

elements in a closed cycle 

cooling water environment. NEI

recommended GALL AMP

XI.M21, "Closed Cycle Cooling 

Water System," for this 

application. 

NEI stated that the basis for AP60 is applicable to components 

in steam and power conversion 

systems where closed cooling 

water temperatures exceed 

140°F in supporting systems, 

such as bearing and lube oil 

coolers and associated piping 

that are considered part of 

these systems. SP-39 

addresses a different aging 

mechanism for this same group 

of components (also see 

endnotes to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed that the stainless steel 

piping in a closed cycle cooling water 

environment would result in cracking. The 

staff also modified GALL AMP XI.M21, 

"Closed Cycle Cooling Water System," to 

address managing the aging effect of 

cracking.

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1o SP-53 NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

reduction of heat transfer/fouling 

of copper alloy heat exchanger 

tubes in a lubricating oil 

environment. The aging 

management program 

recommended by NEI was plantspecific.

NEI stated that Calvert SER 

Section 3.2.2.3.3 acknowledged 

the potential for fouling of 

copper alloy components in a 

lubricating oil environment. The 

SER addressed components in 

a PWR ECCS system, but these 

conditions would be equally 

applicable to components of 

other systems with this 

environment (also see endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment and 

agreed that copper alloy tubing in a 

lubricating oil environment would result in 

the reduction of heat transfer. However, 

the staff revised the AMP column to read: 

Chapter XI.M39, "Lubricating Oil Analysis"

and augmented by XI.M32, "One-Time 

Inspection."

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-9 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-1p SP-62

SP-63

NEI recommended the creation 

of a new AMR line-item for the 

aging effects and mechanisms of 

reduction of heat transfer/fouling 

of steel and stainless steel heat 

exchanger tubes in a lubricating 

oil environment. The aging 

management program 

recommended by NEI was plantspecific.

NEI stated that this is line-item

is similar to new AMR line-item

SP-53 except for a different 

material. Heat exchanger tubes 

of steel would also be subject to 

fouling in a lubricating oil 

environment (also see endnotes 

to this table for NEI’s 

presentation of general 

comment 1).

The staff agreed with this comment and 

agreed that steel piping in a lubricating oil 

environment would result in loss of heat 

transfer. However, the staff revised the 

AMP column to read: "Chapter XI.M39, 

"Lubricating Oil Analysis" and augmented

by Chapter XI.M32, "One-Time 

Inspection."

The GALL Report was revised to address 

this proposed change.

G-VIII-GC-1q VIII.I(1) NEI recommended the creation 

of a new AMR line-item for steel 

piping, piping components, and 

piping elements in an inert 

containment environment. There 

was no aging management 

program recommended by NEI.

NEI stated that, while there 

would be moisture present, 

there would be an inerted 

atmosphere, which would not 

support corrosion. Only thin if 

any surface corrosion would be 

detected. Very little aging is 

expected (also see endnotes to 

this table for NEI’s presentation 

of general comment 1).

The staff did not agree with this comment.

There are situations where the 

containment is not inerted, for example, 

during outages the environment is not 

inerted, and when inerted, leakage is 

allowed per the Technical Specifications.

Potential exists for aging effects due to 

these conditions.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.7-10 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC3aS-06

S-07

S-10

S-14

S-19

S-39

SP-16

SP-17

SP-18

SP-43

SP-44

SP-45

SP-46

NEI recommended deletion of 

the reference to EPRI document 

TR102134 from the AMP column

in the line-items.

NEI stated that the reference to 

this specific EPRI document 

need not be included in the lineitem AMP column because this 

information is provided in GALL 

AMP XI.M2, the AMP description 

in Chapter XI of GALL. Within the 

AMR line-items, it is adequate 

and internally consistent simply 

to reference AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water in EPRI TR-102134. as 

Chapter XI.M2, "Water 

Chemistry," for PWR secondary 

water (see also the endnotes to 

this table for NEI’s presentation 

of general comment 3).

The staff agreed with this comment.

Previously, EPRI TR-102134 was 

referenced in the AMP column of the 

AMR line-items; the AMP column was 

revised to read: "Chapter XI.M2, "Water 

Chemistry," for BWR secondary water."

The GALL Report was revised to address 

this proposed change.

G-VIII-GC3bS-04

S-05

S-09

S-13

S-18

S-21

SP-19

NEI recommended deletion of 

the reference to EPRI document 

TR103515 from the AMP column 

in the line-items.

NEI stated that the reference to 

this specific EPRI document 

need not be included in the lineitem AMP column because this 

information is provided in GALL 

AMP XI.M2. Within the AMR lineitems, it is adequate and 

internally consistent simply to 

reference AMP XI.M2, "Water 

Chemistry," for BWR water in 

BWRVIP-29 (EPRI TR-103515).

Chapter XI.M2, "Water 

Chemistry," for BWR water (see 

also the endnotes to this table for 

NEI’s presentation of general 

comment 3).

The staff agreed with this comment.

Previously, BWRVIP-29 (EPRI TR103515) was referenced in the AMP 

column of the AMR line-items; AMP 

column revised to read: "Chapter XI.M2, 

"Water Chemistry," for BWR water."

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-11 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-3c S-22 NEI recommended deletion of 

the reference to EPRI document 

TR105714 from the AMP column

in the line-items.

NEI stated that the reference to 

this specific EPRI document 

need not be included in the lineitem AMP columns because this 

information is provided in GALL 

AMP XI.M2, Within the AMR lineitems, it is adequate and 

internally consistent simply to 

reference AMP XI.M2, "Water 

Chemistry," for PWR secondary 

water in EPRI TR-105714.

Chapter XI.M2, "Water 

Chemistry," for PWR secondary 

water (see also the endnotes to 

this table for NEI’s presentation 

of general comment 3).

The staff agreed with this comment.

Previously, EPRI TR-105714 was 

referenced in the AMP column of the 

AMR line-items; the AMP column was 

revised to read: "Chapter XI.M2, "Water 

Chemistry," for PWR secondary water."

The GALL Report was revised to address 

this proposed change.

G-VIII-GC4aS-01

S-31

SP-26

SP-37

NEI recommended deletion of 

the line-items that address the 

external surfaces of components 

and bolting from the applicable 

systems table and move them to 

a new external surfaces aging 

management program table.

NEI stated that the appropriate 

location for line-items that 

address external surfaces is for 

all to be co-located in the new 

external surfaces aging 

management program table 

rather than within their 

applicable system tables, but 

that line-items that refer to a 

unique aging management 

program, e.g., the fire protection 

program, which monitors fire 

doors, should remain with the 

appropriate systems table (see 

also the endnotes to this table 

for NEI’s presentation of general 

comment 4).

The staff did not agree with this comment.

The staff noted that it was important for its 

reviewers to know to what system each 

line-item belonged; this information was 

important and useful in performing its 

reviews to know which specific systems 

are addressed by which line-items. The 

staff thus decided that it was more 

beneficial to include each line-item in its

appropriate system than to group these 

components by the surface to be 

examined.

The GALL Report was not revised to 

address this proposed change.

The staff did not agree with this comment.
NUREG-1832 A.2.7-12 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC4bS-02

S-03

S-29

S-32

S-34

S-41

S-42

NEI recommended the 

modification of these line-items 

for the aging effects and 

mechanisms of loss of 

material/general, pitting, and 

crevice corrosion, and cracking/ 

cyclic loading, stress corrosion 

cracking of steel of steel or low 

alloy steel external surfaces, 

including closure bolting, in an 

outdoor air, air with steam or 

water leakage, or uncontrolled 

indoor air environments. NEI 

recommended Chapter XI.M36, 

"External Surface Monitoring."

NEI proposed to add this AMP 

"External Surfaces Monitoring."

NEI stated that these line-items 

should be consolidated under 

the previously external surfaces 

monitoring program, including 

S-41, S-02, and S-29 (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 4).

The staff reviewed these components and 

did not agree to consolidate these lineitems. The staff believes that applicants 

and staff reviewers need to know to what 

system each line-item belongs to. Thus, it 

will be beneficial if each line-item is in its

appropriate system than to group these 

components by the surface to be 

examined. This information enables the 

applicants and staff reviewers to identify 

which specific systems are addressed by 

the corresponding line-items.

The GALL Report was not revised to 

address this proposed change. However, 

for S-29, S-41, and S-42, the staff 

changed the plant-specific AMP to 

Chapter XI.M36, "External Surfaces 

Monitoring."

G-VIII-GC-4c S-30

S-40

NEI recommended the 

modification of these line-items 

for the aging effects and 

mechanisms of loss of material/

boric acid corrosion of steel 

external surfaces, including 

closure bolting, in an air with 

borated water leakage 

environment.

NEI stated that these line-items 

should be consolidated under 

the previously external surfaces 

monitoring program, including 

S-30 (VIII.H-9) (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 4).

The staff did not agree with this comment.

The staff reviewed these components and 

did not agree to consolidate these lineitems. The staff believes that applicants 

and staff reviewers need to know to what 

system each line-item belongs to. Thus, it 

will be beneficial if each line-item is in its

appropriate system than to group these 

components by the surface to be 

examined. This information enables the 

applicants and staff reviewers to identify 

which specific systems are addressed by 

the corresponding line-items.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.7-13 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC4dS-42 NEI recommended the 

modification of this AMR line-item

for the aging effects and 

mechanisms of loss of 

material/general corrosion of 

steel external surfaces in a 

condensation environment. NEI 

recommended Chapter XI.M36, 

External Surfaces Monitoring."

NEI proposed to add this AMP 

"External Surfaces Monitoring."

NEI stated that these line-items 

should be consolidated under 

the previously external surfaces 

monitoring program, including 

S-41 (VIII.H-8) (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 4).

The staff reviewed these components and 

did not agree to consolidate these lineitems. The staff believes that applicants 

and staff reviewers need to know to what 

system each line-item belongs to. Thus, it 

will be beneficial if each line-item is in its

appropriate system than to group these 

components by the surface to be 

examined. This information enables the 

applicants and staff reviewers to identify 

which specific systems are addressed by 

the corresponding line-items.

The staff did agree to change the plantspecific program to Chapter XI.M36, 

"External Surfaces Monitoring."
NUREG-1832 A.2.7-14 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-5 S-17

S-18

S-19

S-20

S-21

S-22

S-23

S-24

S-25

S-26

S-39

NEI recommended deletion of 

the references to reactor type

and to heat exchanger shell and 

tube side components, as 

appropriate.

NEI stated that many GALL 

items referring to heat 

exchanger components indicate 

whether the line-item applies to 

the tube side or the shell side.

However, the designation of the 

tube side or shell side of a heat 

exchanger unnecessarily limits 

the applicability of the GALL 

line-item. Small heat 

exchangers in particular can be 

configured with the cooled fluid 

on either the shell or tube side.

For heat exchangers with a 

given set of materials and 

environments, the configuration 

of the heat exchanger (tube side 

vs. shell side) will not alter the 

aging effects or the aging 

management programs.

Consequently, the component 

descriptions for these lines 

should be changed to delete the 

tube side or shell side 

designation (see also the 

endnotes to this table for NEI’s 

presentation of general 

comment 5).

The staff agreed with this comment. The 

staff agreed that the aging effects and 

aging programs are applicable to the 

component, regardless of heat exchanger 

design, (i.e., of either shell or tube side) 

thus, it was appropriate to include both 

sides, not just one.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.7-15 NUREG-1832

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-GC-6 S-33 NEI recommended the deletion 

of this AMR line-item.

NEI stated that loss of preload 

is not an aging effect (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 6).

The staff agreed with this comment. The 

staff agreed that loss of preload due to 

stress relaxation (creep) can only be a 

concern in very high temperature 

applications (> 700°F).

In EPRI TR-104213 and EPRI NP-5067, 

loss of preload due to gasket creep, 

thermal effects (including differential 

expansion and creep or stress relaxation), 

and self-loosening (which includes 

vibration, joint flexing, cyclic shear loads, 

thermal cycles) is discussed. The staff

determined that this combination of aging 

mechanisms will replace ‘stress 

relaxation.’ Thus the replacement aging 

effect/aging mechanism will be loss of 

preload/ thermal effects, gasket creep, 

and self-loosening.

The GALL Report was modified to 

address this comment.

G-VIII-C-1 S-08 NEI recommended the 

modification of line-items for the 

aging effects and mechanisms of 

cumulative fatigue 

damage/fatigue of steel piping, 

piping components, and piping 

elements in a steam environment 

to include treated water 

environments.

NEI stated that the aging effect 

of fatigue may not be limited to 

only steel piping in a steam 

environment, but that such 

piping in a treated water 

environment was also 

susceptible to fatigue.

The staff agreed with this comment. The 

staff reviewed these components and 

agreed that fatigue is a time-limited aging 

analysis, and that it will have an aging 

effect regardless of the environment in 

which the item is located.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.7-16 September 2005

Table A.2.7: Disposition of NEI Comments on Chapter VIII of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-VIII-C-2 S-13

S-14

SP-42

NEI recommended the deletion 

of these line-items.

NEI stated that these 

components (tanks) are 

included under the definition of 

piping, and that tanks should be 

considered there and not 

separately.

The staff did not agree with this comment.

The staff believes tanks need to be 

addressed separately from the piping 

category, due to their differing 

environments (e.g., stagnant conditions).

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.7-17 NUREG-1832

Endnotes Clarifying General Comments Provided by NEI

1. General Comment 1 (GC1) for New AMR Line-Items: NEI proposed new lines items are listed at the end of each table. The 

new lines are designated "New VIII.X(Y) where X is the table identifier and Y is a sequential number for lines in that table.

Where the same line-item is proposed in multiple tables, the other tables are listed below the designation.

2. General Comment 2 (GC2) for Stainless Steel in Treated Borated Water: This general comment does not apply to this 

GALL chapter.

3. General Comment 3 (GC3) Water Chemistry Reference: NEI pointed out that the reference to the specific EPRI document 

need not be included in the Aging Management Program column. This information is identified in the AMP description in 

Chapter XI of GALL.

4. General Comment 4 (GC4) External Environments: NEI commented that the introductory text to Chapter VIII systems tables 

refers to an external surfaces table H at the end of the chapter for aging management programs for the degradation of external 

surfaces of components and miscellaneous bolting. However, many external surfaces and external bolting entries are still 

within the individual systems tables. NEI proposed to move most external surface and external bolting lines to the external 

table. Any lines which refer to a unique aging management program (e.g., Fire Protection Program to monitor fire doors) would 

remain with the system table.

5. General Comment 5 (GC5) Heat Exchanger Components Description: NEI noted that many GALL items referring to heat 

exchanger components indicate whether the line-item applies to the tube side or the shell side. However, the designation of the 

tube side or shell side of a heat exchanger unnecessarily limits the applicability of the GALL line-item. Small heat exchangers 

in particular can be configured with the cooled fluid on either the shell or tube side. For heat exchangers with a given set of 

materials and environments, the configuration of the heat exchanger (tube side vs. shell side) will not alter the aging effects or 

the aging management programs. Consequently, the component descriptions for these lines should be changed to delete the 

tube side or shell side designation. Similarly, some lines list heat exchanger components including tubes. For aging effects 

other than the reduction of heat transfer, tubes may be considered with other heat exchanger components. Thus, for aging 

effects other than reduction of heat transfer, the component description should be "Heat exchanger components." The 

descriptor "Heat exchanger tubes" should be used when addressing reduction of heat transfer. 

6. General Comment 6 (GC6) Bolting: NEI suggested that, consistent with its Chapter IX comment, high strength low alloy steel 

should be ‘Low alloy steel.’ Also, bolt strength does not impact the fatigue or wear aging mechanisms.

NEI further said that, although some utilities have conservatively applied loss of preload as aging effect for bolting, the industry 

does not consider loss of preload as an aging effect requiring management. In accordance with EPRI 1003056, "Mechanical 
NUREG-1832 A.2.7-18 September 2005

Tool," Appendix F, loss of preload is a design driven effect and not an aging effect requiring management. The bolting at most 

facilities is standard grade B7 carbon steel, or similar material, except in rare specialized applications. Loss of preload due to 

stress relaxation (creep) for this material can only be a concern in very high temperature applications (> 700°F) as stated in the 

ASME Code Section II Part D Table 4 Note 4. However, there is no bolting used in BWRs and PWRs that operate at 700°F, 

with the exception of unique applications, such as the emergency diesel generator exhaust. Therefore, loss of preload due to 

stress relaxation (creep) is not a valid aging effect. 

In addition, NEI stated that the industry has taken actions to address NUREG –1339, "Resolution to Generic Safety Issue 29: 

Bolting Degradation or Failure in Nuclear Power Plants." Licensees have implemented good bolting practices in accordance 

with those referenced in EPRI NP-5769, EPRI NP-5067, and EPRI TR-104213 in normal maintenance and design activities.

Normal maintenance and design activities thus address the potential for loss of preload such that it is not a concern for the 

current or extended operating term. Proper joint preparation and make-up in accordance with industry standards precludes loss 

of preload. Even other design factors that could contribute to a loss of preload in closure bolting applications, such as vibration, 

should not result in loosening in a properly designed and assembled bolted joint. 

NEI suggested that the impact to the GALL tables is that, with elimination of loss of preload as an aging effect, closure bolting 

has the same MEAP as external surfaces and the lines could be combined.
September 2005 A.2.8-1 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-B-1 IX.B, Pg. IX-3, 

6

th line-item

Add ‘tanks’ to the list of various 

features of the piping, piping 

components, and piping 

elements that are within the 

scope of license renewal.

This component category was 

intended to encompass all 

components when evaluating 

material and environment 

combinations where the 

configuration of the component, 

and thus its specific type, has no 

impact on the aging effects. While 

the word "examples" indicates the 

list is only partial, the inclusion of 

at least one larger component 

type would further clarify the 

definition as all inclusive.

The staff did not agree with this 

comment because a tank is not an 

aspect of piping. The staff decided that 

the listing will continue to state, 

"Examples include piping, fittings, 

tubing, flow elements/indicators, 

demineralizer, nozzles, and orifices, flex 

hoses, pump casing and bowl, safe 

ends, spray head, strainers, 

thermowells, and valve body and 

bonnet."

The GALL Report was not revised to 

address this proposed change.

G-IX-B-V.1 IX.B, Pg. IX-3, 

create new 3rd

line-item

Add new component: 

Encapsulation Components/ 

Valve Chambers

Encapsulation components are 

not currently a GALL SSC term, 

but a precedent exists for 

including these items based on 

the Millstone and Farley LRAs 

and corresponding staff reviews.

The staff accepted the aging 

management programs identified 

by these applicants for these 

material and environment 

combinations for loss of material 

in the Millstone SER Section 

2.3A.2.3 and Farley SER Section 

3.2.2.2.2.

The staff agreed with this comment. The 

term "encapsulation components/valve 

chambers" was added to GALL in IX 

and defined as: "These are airtight 

enclosures that function as a secondary 

containment boundary to completely 

enclose containment sump lines and 

isolation valves." A new AMR line-item 

EP-42 was created to the GALL Report 

for this SSC.

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-2 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-B-VI.1 IX.B, Pg. IX-3, 

3

rd line-item

The definition of high-voltage 

insulators for license renewal 

should include the insulator 

used to support the bus bar in 

MEB at low, and mediumvoltages

The existing phrasing of highvoltage insulators only refers to 

"those used to support and 

insulate high voltage electrical 

components in switchyards, 

switching stations, and 

transmission lines."

The staff did not agree with this 

comment. The staff notes that high

voltage insulators are defined as those 

that handle voltage >34.9 kV. Low and 

medium-voltage insulators are covered 

under the GALL AMP XI.E4 "Metalenclosed Buses."

The GALL Report was not revised to 

address this proposed change.

G-IX-C-1 IX.C, Pg. IX5, 3

rd line-item

Add the sentence:

CASS is susceptible to loss of 

fracture toughness due to 

thermal and neutron irradiation 

embrittlement.

Within the context of license 

renewal, CASS should be 

considered to be a category of 

stainless steel except where 

thermal and neutron irradiation 

embrittlement is considered as an 

aging effect.

The staff agreed with this comment. The 

staff agreed that the additional sentence 

did clarify the behavior of CASS so the 

sentence was added. However, in 

certain cases, CASS will still retain its 

identity in AMR line-items in GALL, Rev. 

1, even when the aging mechanism is 

SCC (as in the case of R-05).

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-3 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-C-2a IX.C, Pg. IX7, 6

th line-item

Change the definition of 

stainless steel so that CASS 

becomes part of it unless the 

aging effect/mechanism is: 

loss of fracture toughness due 

to thermal and neutron 

irradiation embrittlement.

CASS aging effects should be 

managed the same as stainless 

steel other than thermal and 

neutron irradiation embrittlement.

This permits CASS to be treated 

as a subset of stainless steel.

CASS is then only listed as a 

material when loss of fracture 

toughness due to thermal (or 

thermal and irradiation) 

embrittlement is at issue, or where 

unique AMP requirements are 

given. This provides consistency 

with GALL’s treatment of other 

material groups, e.g., gray cast 

iron as a subset of steel, and 

copper alloy >15% zinc as a 

subset of copper alloy. Gray cast 

iron and copper alloy >15% zinc 

are both susceptible to selective 

leaching and are only listed as 

materials when selective leaching 

is addressed.

The staff agreed with this comment with 

modification.

The staff incorporated some of the 

suggested changes in the new 

description of stainless steel. However, 

in certain cases, CASS will still retain its 

identity in AMR line-items in GALL, Rev. 

1, even when the aging mechanism is 

SCC (as in the case of R-05) because 

the AMP is unique. For R-05, the AMP 

states "Monitoring and control of 

primary water chemistry in accordance 

with the guidelines in EPRI TR -105714 

(Rev. 3 or later revisions or updates) 

minimize the potential of SCC, and 

material selection according to the 

NUREG-0313, Rev. 2 guidelines of 

=0.035% C and =7.5% ferrite reduces 

susceptibility to SCC. For CASS 

components that do not meet either one 

of the above guidelines, a plant-specific 

AMP is to be evaluated. The program is 

to include (a) adequate inspection 

methods to ensure detection of cracks, 

and (b) flaw evaluation methodology for 

CASS components that are susceptible 

to thermal aging embrittlement."

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-4 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-C-2b IX.C, Pg. IX7, 6

th line-item

Change the definition of 

stainless steel so that:

Steel with stainless steel 

cladding may also be 

considered stainless steel when 

the aging effect is associated 

with the stainless steel surface 

of the material rather than the 

composite volume of the 

material.

The stainless steel surface of 

cladding on steel can be 

considered to be the same as 

stainless steel for most common 

aging effects. For volumetric 

aging effect such as fatigue, steel 

with stainless steel cladding 

should be listed as a separate 

material.

The staff agreed with this comment. The 

staff agreed that this change provides 

added clarity to the license renewal 

guidance documents. In certain cases in 

AMR line-items reference to 

components fabricated from steel with 

stainless steel cladding was retained.

The GALL Report was revised to 

address this proposed change.

G-IX-C-IV-1 IX.C, Pg. IX6, 3

rd line-item

Change the description of high 

strength low alloy steel to "lowalloy steel" and rewrite to

simply describe typical bolting 

used in nuclear applications.

Clarify that high strength bolting 

are those with actual measured 

yield strength, Sy , = 150 ksi.

The "High strength" modifier 

refers to susceptibility to the 

cracking aging effect. SA193 

Grade B7 bolting is not "high 

strength" per the definition 

provided on page 12 of NUREG1339. The categorization should 

be based on the actual measured 

yield strength, Sy , and not on the 

specified minimum yield strength.

The staff agreed with this comment. The 

staff agreed that this change provides 

added clarity to the license renewal 

guidance documents. Since not all lowalloy steel is subject to SCC, this 

suggestion was revised to retain 

reference to high-strength low-alloy 

steel.

The GALL Report was revised to 

address this proposed change.

G-IX-C-IV-2 IX.C, Pg. IX6, 7th line-itemPH stainless steel forging 

should be subsumed by the 

definition of "stainless steel."

There is nothing distinct in the 

AMR line-items associated with 

this material that warrants special 

treatment. 

The staff agreed with this comment.

Precipitation hardened (pH) martensitic 

stainless steel is subject to the same 

aging effects and aging mechanisms as 

other stainless steels and thus is no 

longer specially defined. The 2005 

counterparts of the GALL’01 AMR lineitems that specified PH stainless steel 

forgings (IV B4.4-d, IV B4.4-c, IV B4.4-

a, IV B4.4-e) now simply reference 

stainless steel.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-5 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-C-VI.1 IX.C, Pg. IX7, 3rd line-itemAdd the term "Malleable iron"

under the description of steel.

Malleable iron is defined nowhere 

else in the LRG documents.

The staff agreed with this comment. The 

definition for steel in Table IX.C was 

revised to state "For a given 

environment, carbon steel, alloy steel, 

cast iron, gray cast iron, malleable iron, 

and high strength low alloy steel are 

vulnerable to general, pitting, and 

crevice corrosion even though the rates 

of aging may vary. 

Another line-item was created in Table

IX.C, for malleable iron that states - -

Malleable iron usually means malleable 

cast iron, characterized by exhibiting 

some elongation and reduction in area 

in tensile test. Malleable iron is one of 

the materials in the suite of "Porcelain, 

Malleable iron, aluminum, galvanized 

steel, cement" used to define the high 

voltage insulators subject to degradation 

of insulator quality/presence of any salt 

deposits or surface contamination (AMR 

line-item LP-07) or loss of material/ 

mechanical wear due to wind blowing 

on transmission conductors (AMR lineitem LP-11).

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-6 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-C-VI.2 IX.C, Pg. IX5, 3rd line-itemAdd the term "porcelain "under 

the description of steel.

Porcelain is defined nowhere else 

in the LRG documents.

The staff agreed with this comment.

Porcelain and glass are quite different 

materials. The definition of glass was 

enhanced to state that "Glass is a hard, 

amorphous, brittle substance made by 

fusing together one or more of the 

oxides of silicon, boron, or 

phosphorous, with certain basic oxides 

(e.g., Na, Mg, Ca, K), and cooling the 

product rapidly to prevent crystallization 

or devitrification."

Another line-item was created in Table 

IX.C, for porcelain that states: "Hardquality porcelain is used as an insulator 

for supporting high-voltage electrical 

insulators. Porcelain is a hard, finegrained ceramic that essentially consists 

of kaolin, quartz, and feldspar that is 

fired at high temperatures. Porcelain is 

one of the materials in the category of 

’Porcelain, Malleable iron, aluminum, 

galvanized steel, cement’ used to define 

the high voltage insulators subject to 

degradation of insulator quality/

presence of any salt deposits or surface 

contamination (AMR line-item LP-07) or 

loss of material/mechanical wear due to 

wind blowing on transmission

conductors (AMR line-item LP-11)."

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-7 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-D-1 Table IX.D, 

Page IX-10, 

no 

corresponding 

line-item

Replace the term "air" with "Air 

– indoor 

controlled/uncontrolled, Air -

outdoor."

Have consistency between terms 

in AMR line-items and Chapter IX.

The term "air" is undefined in 

Chapter IX although it is 

associated with AMR line-items 

AP-48 and SP-33 for Glass in 

Chapters VII and VIII.

The staff agreed with this comment.

The term "air" was replaced with "Air –

indoor controlled/uncontrolled, Air -

outdoor."

The GALL Report was revised to 

address this proposed change.

G-IX-D-2 Table IX.D, 

Page IX-10, 

no 

corresponding 

line-item

Replace the term "air - indoor"

(found in LP-01) with "Air –

indoor controlled/uncontrolled, 

Air - outdoor."

Have consistency between terms 

in AMR line-items and Chapter IX

The term "air - indoor" is 

undefined in Chapter IX although 

it is associated with AMR lineitems LP-01.

The staff agreed with this comment. Air 

- indoor was added as an environment. 

The GALL Report was revised to 

address this proposed change.

G-IX-D-3 Table IX.D, 

Page IX-12, 

7

th line-item

Delete the examples of closed 

cycle cooling water. The 

suggested rewording is as 

follows: Treated water subject 

to the closed cycle cooling 

water chemistry program.

Closed cycle cooling water 

>60°C (>140°F) allows the 

possibility of stainless steel 

SCC.

The examples should be removed 

as it may be viewed as limiting in 

terms of consistency.

The staff agreed with this comment. The 

description was rewritten. The examples 

were retained because they clarify 

rather than limit the definition provided.

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-8 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-D-4 Table IX.D, 

Page IX-12, 

7

th line-item

Simplify the definition of 

condensation as follows, "The 

environment to which the 

internal or external surface of 

the component or structure is 

exposed. Condensation on the 

surfaces of systems with 

temperatures below the dew 

point is considered raw"

NEI simplified the definition so 

that condensation can be 

considered anywhere it occurs.

The staff agreed with this comment. The 

description was rewritten for clarity to 

read: "The environment to which the 

internal or external surface of the 

component or structure is exposed.

Condensation on the surfaces of 

systems with temperatures below the 

dew point is considered raw water due 

to potential for surface contamination.

For the purposes of NUREG-1801, Rev. 

1, under certain circumstances the 

GALL Rev. 0, terms "moist air" or "warm 

moist air" are enveloped by 

condensation to describe an 

environment where there is enough 

moisture for corrosion to occur."

The GALL Report was revised to 

address this proposed change.

G-IX-D-5 IX.D, Pg. IX11, no 

corresponding 

AMR lineitem.

Create a new definition for 

Containment environment 

(inert). 

"The drywell is made inert with 

nitrogen to render the primary 

containment atmosphere nonflammable by maintaining the 

oxygen content below 4% by 

volume during normal 

operation."

Create conforming line-items in 

Chapters IV, V, VII, and VII. For 

example:

Piping, piping components, and 

piping 

elements/Steel/Containment 

environment/None/None

There currently is not an 

environment defined for inside the 

containment of BWRs, where the 

normal environment is inerted with 

nitrogen to less than 4% oxygen, 

as required by plant technical 

specifications. The environments 

"Air – indoor uncontrolled" and 

"Air – indoor uncontrolled or air –

outdoor" as defined in GALL, and 

as explained in the basis 

document, include both "inside 

and outside containment", but 

make no reference to the low 

oxygen content inside the 

containment of BWRs.

The staff did not agree with this 

comment. The staff expressed concern 

about what would happen during 

outages and decided it was not an 

appropriate new environment for the 

mechanical system AMR line-items in 

the GALL Report.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.8-9 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

When the environment of the 

external surface of a component 

is containment atmosphere, and 

the oxygen content is <4%, then 

loss of material will not be an 

aging effect for steel, carbon 

steel, and other metals that would 

be susceptible to loss of material 

in an air environment. The NRC 

staff agreed to this position in the 

SER for the Dresden Quad Cities 

license renewal application 

(NUREG 1796). The following is 

taken from NUREG 1796, section 

3.1.2.4.5 on page 3-160, "NRC 

staff agreed with the applicant that 

there are no applicable aging 

effects for external surfaces of 

carbon components exposed to a 

containment nitrogen environment 

because the low oxygen level 

present in the primary 

containment atmosphere 

precludes loss of material due to 

corrosion as a credible aging 

effect for the external surface of 

carbon steel components exposed 

to the containment environment."
NUREG-183

2 A.2.8-10 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-D-6 IX.D, Pg. IX13, 10th lineitemSimplify the definition for 

sodium pentaborate solution to 

simply say Treated water that 

contains a mixture of borax and 

boric acid

Delete the following words.

BWR operators are required to 

upgrade their standby liquid 

control systems with sodium 

pentaborate solution. The use 

of higher fuel enrichments and 

the popularity of MOX fuels tax 

reactivity controls at BWRs and 

enriched sodium pentaborate 

provides an excellent solution 

for these new requirements

The original definition did not 

describe the solution.

The staff agreed with this comment. The 

description was rewritten exactly as 

suggested by NEI.

The GALL Report was revised to 

address this proposed change.

G-IX-D-7 IX.D, Pg. IX12, 13th lineitemDelete the environmental term 

of steam (dry).

The BWR main steam system is 

considered dry (usually ~99.9% 

dry) but the PWR main steam 

system can contain moisture and 

thus not fall into this category.

The staff agreed with this comment. The 

environmental description was deleted 

from AMR line-items and deleted from 

GALL Chapter IX.

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-11 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-D-8 IX.D, Pg. IX12, 21st lineitemDelete the environmental term 

of untreated water. 

Define raw water as: Raw 

untreated fresh, salt, or ground 

water. Floor drains and reactor 

buildings and auxiliary building 

sumps may be exposed to a 

variety of untreated water that 

is thus classified as raw water 

for the determination of aging 

effects. Raw water that may 

contain contaminants including 

oil and boric acid depending on 

the location and including 

originally treated water that is 

not monitored by a chemistry 

program.

NEI suggested that untreated 

water and raw water are 

redundant environments and 

should be consolidated. NEI 

stated further that the 

consolidation of environments will 

add to the consistency in the 

usage of the GALL.

The staff agreed with this comment. The 

staff agreed that consolidating these

environmental terms is more productive.

The GALL Report was revised to 

address this proposed change.

G-IX-D-VI.1 IX.D, Pg. IX8, 3rd

paragraph

Add a second sentence that 

states "When applied to the 

elastomers used in cable 

insulation, it should be noted 

that most cable insulation is 

manufactured as either 75°C 

(167°F) or 90°C (194°F) rated 

material."

The added sentence provides 

clarification that an aging effect is 

not expected for electrical cable 

insulation.

The staff agreed with this comment. The 

paragraph has been revised to state 

"Temperature threshold of 95°F (35°C)

for thermal stresses in elastomers: In 

general, if the ambient temperature is 

less than about 95°F (35°C), then 

thermal aging may be considered not 

significant for rubber, butyl rubber, 

neoprene, nitrile rubber, silicone 

elastomer, fluoroelastomer, EPR, and 

EPDM [1]. When applied to the 

elastomers used in electrical cable 

insulation, it should be noted that most 

cable insulation is manufactured as 

either 75oC (167oF) or 90oC (194oF) 

rated material.

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-12 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-D-VII.1 Table IX.D, 

Page IX-11, 

5

th line-item

Delete the term "Air, moist"

which is duplicative" of 

"Condensation."

Removing duplicate environments 

removes confusion; this affects VII 

A-23.

The staff agreed with this comment.

Both the definitions for moist air and 

condensation were modified to clarify 

the relationship. Moist air in the absence 

of condensation is also potentially 

aggressive, e.g., under conditions 

where hygroscopic surface 

contaminants are present. The AMR 

line-item VII A-23 was rewritten to state 

that the environment was moist air or 

condensation.

The GALL Report was revised to 

address this proposed change.

G-IX-E-VI.1 IX.E, Pg. IX14, 3rd

paragraph

Qualify the description of 

degradation of insulator quality 

to note the transience of 

environmental conditions. 

The presence of salt deposits or 

surface contamination results 

from temporary, transient 

environmental conditions, and 

therefore is not an aging 

mechanism or aging effect.

The staff agreed with this comment. The 

staff notes that although a natural 

phenomenon may be transient, the 

presence of salt deposits or surface 

contamination may be long-lasting and 

cumulative.

The description was rewritten to state, 

"The decrease in insulating capacity can 

result from the presence of salt deposits 

or surface contamination. Although this 

derives from an aging mechanism 

(presence of salt deposits or surface 

contamination as noted in LP-07) that 

may be due to temporary, transient 

environmental conditions, the net result 

may be long-lasting and cumulative."

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-13 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-E-VI.2 Table IX.E, 

Page IX-15, 

first line-item

Revise the description of 

fatigue in copper fuse holder 

clamps to note that electrical 

transients beyond the rating of 

the fuse holder are events or 

design-driven issues and are 

not part of the normal 

environment evaluated in 

AMRs.

NEI states that if a transient is 

within the rating of the fuse 

holder, then it does not contribute 

to degradation of the fuse holder.

The designs of fuse holders to 

meet the ANSI/UL 512 standard 

require them to have the ability to 

withstand thousands of fuse 

insertions and removals without 

failure. Therefore, when a fuse 

and fuse holder are used solely 

for circuit protection, there is no 

credible aging mechanism due to 

infrequent fuse manipulation.

The staff agreed with this comment. The 

staff notes that high temperature can 

result from electrical transients (NUREG 

1760 page 9) The entry for fatigue 

remains: "Fatigue in copper fuse holder 

clamps can result from ohmic heating, 

thermal cycling, electrical transients, 

frequent manipulation, vibration, 

chemical contamination, corrosion, 

oxidation."

The GALL Report was revised to 

address this comment.

G-IX-E-VI.3 Table IX.E, 

Page IX-15, 

8

th line-item

Revise the description of 

loosening of bolted connections 

to note that thermal cycling 

during service up to the rated 

loading is not an aging 

mechanism.

NEI points out that bolted 

connections for bus bar in metalenclosed bus are designed for 

thermal cycling caused by ohmic 

heating up to the rated loading of 

the bus. NEI further states that 

ohmic heating due to bus 

overload beyond the design rating 

is a beyond design basis event 

rather than a normal stressor 

evaluated in the aging 

management review.

The staff agreed, in part, with this 

comment. The staff notes that loosened 

terminations were identified in several 

plants (SAND 96-0344). Additionally, 

EPRI TR-104213 recommends 

inspection of bolted joints for indication 

of loose bolts and recommends 

checking joint resistance of bolted joints 

using a low range ohm meter.

The entry for loosening of bolted 

connections remains: "The loosening of 

bolted bus duct connections due to 

thermal cycling can result from ohmic 

heating" with markers to these 

references.

The GALL Report was revised to 

address this comment.
NUREG-183

2 A.2.8-14 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-E-VI.4 Table IX.E, 

Page IX-16, 

1

st line-item

Revise the description of Loss 

of Material to not include highvoltage insulators, loss of 

material attributed to 

mechanical wear or windinduced abrasion and fatigue 

due to wind blowing on 

transmission conductors.

NEI points out that there are 

neither high-voltage insulator 

failures attributed to this effect nor 

operating experience to support 

loss of material from high-voltage 

insulators.

The staff agreed with this comment with 

modification. The staff noted that there 

are instances of concern (SAND-96-

0344) The last sentence in the entry will 

remain "For high voltage insulators, loss 

of material can be attributed to 

mechanical wear or wind-induced 

abrasion and fatigue due to wind 

blowing on transmission conductors" but 

a reference will be added to support 

NRC’s statement.

The GALL Report was revised to 

address this comment.

G-IX-F-1 Table IX.F, 

Page IX-19, 

6

th line-item

Delete the aging mechanism 

"Corrosion of embedded steel"

and replace with "corrosion."

The definition of "corrosion" is 

adequate to encompass this 

combination of aging mechanism 

and location.

The staff did not agree with this 

comment. The staff noted that this 

expression, used a total of 9 times in 

GALL Rev. 1 Chapters II, III, and VII, 

provides clarification about particular 

form of corrosion that is of significant 

concern. Thus the expression 

"Corrosion of embedded steel" is 

retained.

The GALL Report was not revised to 

address this proposed change.
September 2005 A.2.8-15 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-F-2 Table IX.F, 

Page IX-21, 

4

th line-item

Add the following sentence to 

the existing definition of Flowaccelerated corrosion (FAC).

Susceptibility may be 

determined using the review 

process outlined in Section 4.2 

of NSAC-202L-R2.

The definition should be tied to 

the susceptibility reviews that can 

be performed per Section 4.2 of 

NSAC-202L-R2.

NSAC-202L-R2 is used as a basis 

for AMP XI.M17 Flow-Accelerated 

Corrosion.

The staff agreed with this comment. The 

staff revised the description to state, 

"Also termed erosion-corrosion. A cojoint activity involving corrosion and 

erosion in the presence of a moving 

corrosive fluid, leading to the 

accelerated loss of material.

Susceptibility may be determined using 

the review process outlined in Section 

4.2 of the NSAC-202L-R2."

The GALL Report was revised to 

address this proposed change.

G-IX-F-3 Table IX.F, 

Page IX-24, 

10th line-item

The standardized expression 

"relaxation" should be deleted.

The description can be added 

to the "stress relaxation."

Loss of prestress due to 

relaxation is redundant to loss of 

preload due to stress relaxation.

The staff agreed with this comment. The 

sentence "Relaxation in structural steel 

anchorage components can be an aging 

mechanism contributing to the aging 

effect of loss of prestress" was 

relocated to the description of stress 

relaxation.

The GALL Report was revised to 

address this proposed change.

G-IX-F-IV.1 Table IX.F, 

Page IX-19, 

5

th line-item

Delete entry for "Corrosion of 

carbon steel tube support plate"

This standardized expression 

should be deleted. The definition 

of "corrosion" is adequate to 

encompass this combination of 

aging mechanism and location.

The staff did not agree with this 

comment. The staff noted that this 

expression, only used for R-43, provides 

clarification about particular form of 

corrosion that is of significant concern 

for nickel alloy tubes and sleeves. Thus 

the expression "Corrosion of carbon 

steel tube support plate" is retained.

The GALL Report was not revised to 

address this proposed change.
NUREG-183

2 A.2.8-16 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-F-IV.2 Table IX.F, 

Page IX-23,

8

th line-item

Delete entry for "Outer 

Diameter Stress Corrosion 

Cracking (ODSCC)"

This standardized expression 

should be deleted. The definition 

of "corrosion" is adequate to 

encompass this combination of 

aging mechanism and location.

The staff did not agree with this 

comment. The staff noted that this 

expression, only used for R-47, provides 

clarification about particular form of 

corrosion that is of significant concern 

for nickel alloy tubes and sleeves. Thus 

the expression "Outer Diameter Stress 

Corrosion Cracking (ODSCC)" is 

retained.

The GALL Report was not revised to 

address this proposed change.

G-IX-F-VI.1 Table IX.F, 

Page IX-20, 

6

th line-item

Revise the description of 

electrical transients to quantify 

the transient or provide a 

threshold for this as an aging 

mechanism.

NEI points out that if the transient 

does not result in sufficient ohmic 

heating to affect the physical 

properties of the fuse clamp 

metal, no aging effect will occur

The staff agreed with this comment with 

modification. The staff notes that 

electrical transients will cause 

overheating (NUREG-1760 page 9) The 

entry for electrical transients is rewritten 

to state: "An electrical transient is a 

stressor caused by a voltage spike that 

can contribute to aging degradation. 

Certain types of high-energy electrical 

transients can contribute to 

electromechanical forces ultimately 

resulting in fatigue or loosening of 

bolted connections. Transient voltage 

surges are a major contributor to the 

early failure of sensitive electrical 

components."

The GALL Report was revised to 

address this comment.
September 2005 A.2.8-17 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-F-VI.2 Table IX.F, 

Page IX-23, 

3

rd line-item

Revise the description of 

mechanical wear so that fatigue 

is no longer the lead-in word for 

the description.

Fatigue is not a subset of 

Mechanical Wear in any practical 

or theoretical manner. Wear is the

physical removal of material at the 

surface of a metal and fatigue is a 

change in the internal physical 

properties of the metal at the grain 

boundary level. This is not a 

proper description of an aging 

mechanism for fuse holders or 

electrical lines due to wind 

blowing on transmission 

conductors.

The staff agreed with this comment. The 

entry was rewritten so it no longer 

begins by naming the stipulated aging 

effect (fatigue) caused by the defined 

aging mechanism. The entry was 

revised to state, "Degradation of copper 

clamps in fuse holders can be partially 

attributed to frequent manipulation, 

which is really a subset of mechanical 

wear (as referenced in LP-01). Other 

examples include mechanical wear of 

electrical lines due to wind blowing on 

transmission conductors as referenced 

in LP-11)..."

The GALL Report was revised to 

address this comment.

G-IX-F-VI.3 Table IX.F, 

Page IX-23, 

7

th line-item

Revise entry for ohmic heating 

to be more general.

Ohmic heating is induced by 

current flow through a conductor 

and can be calculated using first 

principles of electricity and heat 

transfer. Ohmic heating is not 

restricted only to conductors 

passing through electrical 

penetrations.

The staff agreed with this comment. The

entry was rewritten to state "Ohmic 

heating is induced by current flow 

through a conductor and can be 

calculated using first principles of 

electricity and heat transfer. Ohmic 

heating is a thermal stressor; and can 

be induced in situations such as 

conductors passing through electrical 

penetrations. Ohmic heating is 

especially significant for power circuit 

penetrations.

The GALL Report was revised to 

address this proposed change.
NUREG-183

2 A.2.8-18 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-F-VI.4 Table IX.F, 

Page IX-24, 

4

th line-item

Revise entry for "Presence of 

any Salt Deposits" to be more 

general.

NEI notes that the description of 

presence of any Salt Deposits 

should not include degradation of 

insulator quality since surface 

contamination is a short-term 

transient condition that does not 

change the material properties of 

an insulator. The effects of such 

deposits are relevant to the 

current license term and as such, 

should be addressed under 10 

CFR 50.

The staff agreed with this comment. The 

staff notes that although a natural 

phenomenon may be transient, the 

presence of salt deposits or surface 

contamination may be long-lasting and 

cumulative.

The entry was rewritten to state that the 

surface contamination resulting from the 

aggressive environment associated with 

the presence of any salt deposits can be 

an aging mechanism causing the aging 

effect of degradation of insulator quality.

"Although this aging mechanism may be 

due to temporary, transient 

environmental conditions, the net result 

may be long-lasting and cumulative."

The GALL Report was revised to 

address this comment.

G-IX-F-VI.6 Table IX.F, 

Page IX-26, 

4

th line-item

Revise entry for "Water trees"

to be more general.

Based on analysis of mediumvoltage underground cable 

failures, electric trees that may 

result from water trees that 

penetrate the insulation are not 

the predominant cause of failures 

in underground polymericjacketed cables. This issue is 

being addressed by an NEI task 

force on medium-voltage 

underground cables as a separate 

concern under 10 CFR 50 in 

response to the February 5, 2004, 

letter from Jose Calvo (NRC).

The staff agreed with this comment. The 

definition was rewritten to state "Water 

trees occur when the insulating 

materials are exposed to long-term, 

continuous electrical stress and 

moisture; these trees eventually result in 

breakdown of the dielectric and ultimate 

failure. The growth and propagation of 

water trees is somewhat unpredictable.

Water treeing is a degradation and 

long-term failure phenomenon."

85

The GALL Report was revised to 

address this proposed change.
September 2005 A.2.8-19 NUREG-1832

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

G-IX-F-VII.1 Table IX.F, 

Page IX-19, 

3

rd line-item

Revise entry for "Cladding 

degradation" to be more 

general.

NEI suggested rewording: 

This refers to the degradation 

of the stainless steel cladding 

(via any applicable degradation 

process for stainless 

steel/applicable environment 

described in NUREG 1801).

NEI pointed out that the definition 

needs revision so that it conforms 

to the usage in the SRP-LR and 

the GALL Report. The definition in 

Chapter IX is not consistent with 

the usage of this term in Chapter 

VII. AMR line-item A-40 refers to 

the lining of piping and piping 

elements. The lining is a design 

feature and is not credited as part 

of the pressure boundary.

Therefore, the definition provided 

is not accurate. The SRP-LR 

refers to the cracking of cladding.

The staff agreed with this comment. The 

aging mechanism description was 

rewritten exactly as suggested by NEI.

The GALL Report was revised to 

address this proposed change.

G-IX-E/F1 Table IX.F, E 

– AMR lineitems.

Restrict the use of the aging 

effect/mechanism for bolting 

"loss of preload/stress 

relaxation" to situations where 

there are very high temperature 

applications (>700°F).

Loss of preload due to stress 

relaxation (creep) is not a valid 

aging effect. 

The staff agreed with this comment. A 

new aging mechanism of "Thermal 

effects, gasket creep, and selfloosening" was added in GALL Rev. 1 

to be used as a substitute for stress 

relaxation in lower temperature 

conditions.

The staff agree that ASME Code 

Section II Part D Table 4 Note G14 

points out that loss of preload due to 

stress relaxation (creep) for B7 (low 

alloy steel –A193 B7, as stated in 

Appendix F of EPRI 1003056 and 

elsewhere) can only be a concern in 

very high temperature applications 

(> 700°F).

The reference (EPRI TR-104213) 

replaces the earlier report EPRI NP5067, Good Bolting Practices, A 

Reference Manual for Nuclear Power 
NUREG-183

2 A.2.8-20 September 2005

Table A.2.8: Disposition of NEI Comments on Chapter IX of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

Plant Maintenance Personnel. In both 

documents, loss of preload due to 

gasket creep, thermal effects (including 

differential expansion and creep or 

stress relaxation), and self-loosening 

(which includes vibration, joint flexing, 

cyclic shear loads, thermal cycles) is 

discussed. The staff determined that 

this combination of aging mechanisms 

will replace ‘stress relaxation.’

Thus the replacement AE/AM will be 

loss of preload/ thermal effects, gasket 

creep, and self-loosening.

The GALL Report was revised to 

address this comment.
September 2005 A.2.9-1 NUREG-1832

Table A.2.9: Disposition of NEI Comments on Chapter X of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-X.M1-1 Program 

Description

Eliminate change which added 

"and the severity" to the first 

paragraph of the program 

description as follows. In order 

not to exceed the design limit on 

fatigue usage, the aging 

management program (AMP)

monitors and tracks the number 

and the severity of critical 

thermal and pressure transients 

for the selected reactor coolant 

system components.

This is adequately covered by 

the existing wording under the

"Parameters Monitored/

Inspected" element, and could 

be viewed as requiring the 

program to monitor severity of 

transients (which is not done for 

those programs that only count 

cycles). 

The staff agreed with this comment.

The sentence in the program description 

was rewritten to state, "In order not to 

exceed the design limit on fatigue usage, 

the aging management program (AMP) 

monitors and tracks the number of critical 

thermal and pressure transients for the 

selected reactor coolant system 

components."

The GALL Report was revised to address 

this proposed change.

G-X.M1-2 Program 

Description

Restore original text regarding 

critical components.

Changes to the "Program

Description" and "Monitoring 

and Trending" elements of the 

AMP suggest scope of critical

components goes beyond 

those identified in NUREG/CR6260.

The Bases Document does not

provide a technical justification 

for this change.

Suggest leaving the original

wording.

The staff did not agree with this comment 

because there may be locations which 

could more limiting than those identified 

in NUREG-6260 and should be 

addressed.

The GALL Report was not revised to 

address this proposed change.

G-X.M1-3 Monitoring 

and Trending

Restore original text

regarding critical

components.

Changes to the "Program

Description" and "Monitoring 

and Trending" elements of the 

AMP suggest scope of critical

components goes beyond 

those identified in NUREG/CR6260. The Bases Document 

does not provide a technical 

justification for this change.

Suggest leaving the original

wording.

The staff did not agree with this comment 

because there may be locations which 

could more limiting than those identified 

in NUREG-6260 and should be 

addressed.

The GALL Report was not revised to 

address this proposed change.
NUREG-1832 A.2.9-2 September 2005

Table A.2.9: Disposition of NEI Comments on Chapter X of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G-X.M1-4 Corrective 

Actions

Restructure sentence to

make original meaning

clear.

Original (GALL’01) sentence

Structure was awkward. 

Addition

of word "during" attempted to

make sentence read better, but

completely changed original

meaning. Proposed change

resolves original problem.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.10-1 NUREG-1832

Table A.2.10: Disposition of NEI Comments on Chapter XI.E of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.E-4-1 XI.E4, Aging 

Management 

Program for 

Metal 

Enclosed Bus 

(MEB)

Since no MEB aging 

management program has 

previously been required for 

nuclear plants with renewed 

licenses, there should be 

provisions for a licensee to show 

that the materials and 

environment for MEB do not 

produce the stressors that cause

aging effects requiring 

management and an AMP is 

therefore not required.

The staff’s proposed program 

was issued as ISG-17 in the 

Federal Register on December 

23, 2004, and also as XI.E4 in 

GALL, each with a different 

comment period. An alternate to 

the proposed GALL AMP is 

provided with this document.

The staff did not agree with this 

comment because each applicant needs 

to provide in its application the rationale 

why an AMP is not required. The staff

can then determine if they concur with 

the applicant rationale.

The GALL Report was not revised to 

address this proposed change.

XI.E-4-2 XI.E4, Aging 

Management 

Program for 

Metal 

Enclosed Bus 

(MEB)

NEI recommends the use of 

"Metal Enclosed Bus" instead of 

"bus ducts" to denote electrical 

bus.

NEI recommends the change in 

name to differentiate the metal 

enclosed bus from out side 

enclosures around the 

electrically conducting bus bar, 

its supports, and insulating 

assemblies.

The staff agreed with this change in 

terminology.

The GALL Report was revised to 

address this proposed change. The AMP 

is now titled, "Metal Enclosed Bus"

XI.E-4-3 XI.E4, Aging 

Management 

Program for 

Metal 

Enclosed Bus 

(MEB)

elements 3, 4, 

and 6

Delete measuring for proper 

torque of bolted connections

Based on industry 

recommendations in EPRI TR -

104213, bolted connections will 

not and should not be checked 

for proper torque unless 

guidance is provided by the bus 

manufacturer, since 

overtorquing can cause loose 

connections resulting in 

increased connection 

resistance.

The staff agreed with this comment.

The GALL Report was revised to delete 

measuring for bolted connection torque.

Additionally, as an alternative, a visual 

inspection can be performed.
NUREG-1832 A.2.10-2 September 2005

Table A.2.10: Disposition of NEI Comments on Chapter XI.E of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.E-5-1 XI.E5, Aging 

Management 

Program for 

Fuse Holders

NEI recommends deleting the 

AMP XI.E5, "Fuse Holders."

Also, NEI stated that visual 

inspection of fuse holders is 

sufficient to manage the effects 

of aging on fuse holders that are 

not subject to mechanical abuse.

Testing should not be needed for 

fuse holders designed and 

constructed to UL standards that 

do not show signs of excessive 

temperature (discoloration, 

scorching, burned surfaces).

There is no technical or 

operating experience basis for 

the statement that "... failures of 

a deteriorated cable system 

(cables, connections including 

fuse holders, and penetrations) 

might be induced during event 

conditions." In addition, fuse 

holders are included in the EQ 

programs of many plants, 

similar to terminal blocks and 

other non-cable electrical 

components within the scope of 

10 CFR 50.49. Operating 

experience has not shown 

significant failures due to fuse 

holder aging, but rather failures 

due to removal and reinsertion 

of fuses for circuit isolation 

purposes. This use of fuses is a 

design, procedural, or 

operational deficiency, for fuse 

holders that are not designed 

for this type of use.

The staff did not agree with this 

comment because operating experience 

documenting the failures of fuse holders 

has been provided in NRC Information 

Notices (INs).

These NRC INs are referenced in ISG-5.

Additionally, after receiving an industry 

comment (as summarized in this line

XI.E-5-1) by a letter dated March 2, 

2004, the staff revised the AMP on 

March 30, 2004. This new AMP is 

included in the GALL’05 revision.
September 2005 A.2.10-3 NUREG-1832

Table A.2.10: Disposition of NEI Comments on Chapter XI.E of the GALL Report

Comment 

Number Item Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.E-6-1 XI.E6, 

Electrical 

Connections 

Not Subject to 

10 CFR 50.49 

Environmental 

Qualification 

Requirements

Cable connection metallic parts 

– NEI recommends deleting the 

AMP XI.E6, "Electrical 

Connections Not Subject to 10 

CFR 50.49 Environmental 

Qualification Requirements"

This is a proposed AMP that 

has not been published 

previously, has not been 

proposed in a draft or final ISG, 

and has not been required for 

any previously approved license 

renewal application. This AMP 

should be eliminated as these 

items either have no aging 

effects requiring management 

or are adequately covered by 

other AMPs. Operating 

experience does not indicate a 

need for this proposed program.

The staff did not agree with this 

comment because SAND 96-0344, 

"Aging Management Guidelines For 

Electrical Cable and Terminations,"

identified loosened terminations at 

several plants. Additionally, EPRI TR104213 recommends inspection of 

bolted joints for evidence of overheating, 

signs of burning or discoloration and 

indication of loose bolts. It recommends 

checking the joint resistance of bolted 

joints using a low range ohmmeter. AMP

XI.E1 manages the aging of insulating 

materials but not the metallic parts of the 

electrical connections, which is the 

subject of this new AMP. The GALL 

Report was not revised to address this 

proposed change.
NUREG-1832 A.2.10-4 September 2005

This page intentionally left blank.
September 2005 A.2.11-1 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M1.1 XI.M1 ASME 

Section XI 

Inservice 

Inspection, 

Subsections 

IWB, IWC, 

AND IWD

The footnote is based on ASME 

Section XI. The note discusses 

that the NRC adopts the use of 

updated versions of ASME XI in 

10 CFR 50.55a but does not 

state that an applicant may credit 

the updated versions. The Bases 

Document for the revision to the 

GALL Report states that the 

addition of the code used in the 

plant’s ISI program, which is 

based on 10 CFR 50.55a, can be 

used as an AMP in a LRA.

Revise footnote wording as 

shown for XI.M1 in each AMP 

using the footnote (XI.M3 

through M9).

The footnote added to several 

AMP program descriptions 

acknowledges that the ASME 

code required under 10 CFR

50.55a changes periodically but 

it does not clearly state the 

applicant can credit whatever 

code version is applicable 

during the period of extended 

operation. 

The rewording proposed 

corrects the discrepancy and 

will eliminate exceptions that 

applicants must take given the 

current wording.

The proposed wording in the 

footnote will allow applicants to 

credit the revision of ASME XI 

that is credited in their current 

ISI plan as an acceptable aging 

management program for 

license renewal.

The staff did not agree with the exact 

language as proposed by NEI. GALL’01 

evaluated specific editions and addenda 

of the ASME Code to determine if the 

aging management achieved by the ISI 

programs is sufficient to satisfy the 

license renewal rule. GALL’01concluded 

that the specific edition and addenda 

augmented by certain inspections was 

sufficient to manage the aging effects 

listed in GALL. In recent 10 CFR 50.55a 

rulemakings, the associated Statement of 

Considerations authorize use of the 

editions and addenda of the ASME Code 

approved in the rulemaking, if augmented 

by the additional inspections defined in 

the GALL Report, without the need for the 

license renewal applicant to submit these 

alternatives for NRC review in its plantspecific license renewal application.

Thus, the footnote was revised as follows: 

“An applicant may rely on a different 

version of the ASME Code, but should 

justify such use. An applicant may wish to 

refer to the SOC for an update of 10 CFR 

§ 50.55a to justify use of a more recent 

edition of the Code.”
NUREG-1832 A.2.11-2 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M2.1 XI.M2 Water 

Chemistry

Program 

Description 

Add the following words to the 

Program description, "Later 

versions of these chemistry 

program guidelines are 

developed from collective 

operating experience using 

sound technical judgment, and 

are approved by the electric 

utility industry in an effort to 

constantly improve water 

chemistry and thereby manage 

or prevent aging effects. The 

later versions of these guidelines 

when reviewed and approved for 

implementation by the staff in 

applicant Safety Evaluation 

Reports may be used in lieu of 

the revisions or versions 

specified above."

EPRI guidelines change with 

experience. Plant chemistry 

programs generally adopt new 

guidance. Because later 

editions than listed in GALL will 

be used in future, the licenses 

to not want to tie themselves to 

a specific edition. GALL water 

chemistry program description 

already permits use of "later 

revisions or updates of these 

reports as approved by the 

staff."

The staff did not agree with this comment.

It is necessary to specify the edition of 

the EPRI document reviewed by the staff

for license renewal because new 

revisions have not been reviewed for 

generic acceptance for use in license 

renewal.

The GALL Report was not revised to 

address this proposed change.

XI.M2.2. XI.M2 Water 

Chemistry

Scope of the 

Program, 

Preventive 

Actions, and 

Detection of 

Aging 

Effects.

Wherever "crack initiation and 

growth" is mentioned replace the 

words with "cracking"

The change will be consistent 

with current terminology used in 

the GALL Report.

The staff agreed with this comment.

This change is consistent with the 

definitions provided in new Chapter IX in 

the GALL Report.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-3 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M7.1 XI.M7 BWR 

Stress 

Corrosion

Cracking 

Program 

Description 

The program description limits 

the scope to stainless steel. This 

program should also manage 

nickel-based alloys.

Nickel-based alloys are used for 

joint welds as well as for weld 

overlays in BWR reactor 

coolant pressure boundary 

piping. Nickel-based alloys are 

susceptible to IGSCC per 

Chapter IV of NUREG-1801.

Specific discussions of 

inspection frequencies for 

nickel-based alloy materials are 

contained in applicable 

BWRVIP guidelines. In addition, 

Items R-68 and R-21 

specifically align this program 

and material.

The staff agreed with this comment based 

on the fact that item R-21 is for nickel 

alloy and it references XI.M7. 

The GALL Report was revised to address 

this proposed change.

XI.M7.2 XI.M7 BWR 

Stress 

Corrosion

Cracking 

Program 

Description

This program should also 

manage cast austenitic stainless 

steel.

No change is required; if CASS 

is included in the definition of 

stainless steel.

Cast austenitic stainless steel is 

used pumps, valves, and fittings 

in BWR reactor coolant 

pressure boundary piping. Cast 

austenitic stainless steel is 

susceptible to IGSCC per 

Chapter IV of NUREG-1801.

Items R-20 and A-101 

specifically align this program 

and material.

The definition of stainless steel in 

Chapter IX of GALL has been revised to 

include CASS. Thus, no change was 

required to this GALL program to address 

this comment.

XI.M7.3 XI.M7 BWR 

Stress 

Corrosion 

Cracking

Program 

Description

There is a typographical error in 

the last sentence. The close 

parenthesis should be after "75":

Editorial correction, no 

justification is required.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-4 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M7.4 XI.M7 BWR 

Stress 

Corrosion 

Cracking

Scope of 

Program

The program description limits 

the scope to stainless steel. This 

program should also manage 

nickel-based alloys and cast 

austenitic stainless steel.

See Justifications to Comments 

XI.M7.1 and XI.M7.2

This is the same as XI.M7.1 and XI.M7.2. 

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-5 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M7.5 XI.M7 BWR 

Stress 

Corrosion 

Cracking

Preventive 

Action

The last paragraph states:

"Reactor coolant water chemistry 

is monitored and maintained in 

accordance with the guidelines in 

BWRVIP-29 (Electric Power 

Research Institute [EPRI] TR -

103515). The program 

description, and evaluation and 

technical basis of monitoring and 

maintaining reactor water 

chemistry are presented in 

Section XI.M2, "Water 

Chemistry."

The EPRI Water Chemistry 

Guidelines and their 

corresponding BWRVIP 

documents are living documents 

that capture industry operating 

experience and best practices.

The reference to a specific 

version of the water chemistry 

guidelines would require each 

applicant to compare its water 

chemistry program to an old 

version of the guidelines with 

little chance of having a program 

that is consistent.

The BWR SCC Program should 

only reference Section XI.M2, 

Water Chemistry.

Recent applicants have 

received approval of their water 

chemistry programs based on 

later versions of the water 

chemistry guidelines.

For example, NUREG-1769, 

Safety Evaluation Report 

Related to the License Renewal 

of Peach Bottom Atomic Power 

Station, Units 2 and 3, stated in 

Section 3.0.3.2.2 on page 3-9 

that:

"The staff finds the provisions of 

the 2000 revision of EPRI 

TR-103515 acceptable because 

the program is based on 

updated industry experience."

In conclusion, it is important to 

maintain the flexibility to modify 

plant chemistry control 

procedures based on the best 

industry guidance developed 

from the collective operating 

experience of similar reactors

The staff agreed with this comment with 

respect to deleting the reference to 

BWRVIP-29 and replacing it with the 

reference to XI.M2.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-6 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M7.6 XI.M7 BWR 

Stress 

Corrosion 

Cracking

Acceptance 

Criteria

The first paragraph states:

"As recommended in NRC GL 

88-01, any indication detected is 

evaluated in accordance with the 

ASME Section XI, Subsection 

IWB-3640 (2001 edition6

including the 2002 and 2003 

Addenda) and the guidelines of 

NUREG-0313."

NRC GL 88-01 does not state 

that any indication detected is 

evaluated in accordance with the 

ASME Section XI, Subsection 

IWB-3640.

This paragraph should be 

revised as follows:

"As recommended in NRC GL 

88-01, any indication detected is 

evaluated in accordance with the 

ASME Section XI, Subsection 

IWB-3600 (1986 edition) and the 

guidelines of NUREG-0313."

For inspections performed per 

Generic Letter 88-01 the 

following acceptance criterion is 

applicable.

The original Generic Letter, 

when discussing the staff 

position on crack evaluations, 

states the following:

"Methods and criteria for crack 

evaluation and repair should be 

in conformance with IWB-3600 

of Section XI of the 1986 

Edition of the ASME Boiler and 

Pressure Vessel Code."

Supplement 1 to Generic Letter 

88-01 did not revise this 

requirement.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M7.7 XI.M7 BWR 

Stress 

Corrosion 

Cracking

Acceptance 

Criteria

Since Note 6 is not required, the 

note description at the bottom of 

page XI M-26 should be deleted.

See the Justification for 

Comment XI.M7.6

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-7 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M7.8 XI.M7 BWR 

Stress 

Corrosion 

Cracking

References

The 1986 Edition of ASME 

Section XI is not in the list of 

references. It should be added 

as follows: 

"ASME Section XI, Rules for 

Inservice Inspection of Nuclear 

Power Plant Components, ASME 

Boiler and Pressure Vessel 

Code, 1986 edition, American 

Society of Mechanical Engineers, 

New York, NY."

See the Justification for 

Comment XI.7.6

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M7.9 XI.M7 BWR 

Stress 

Corrosion 

Cracking

References

Make conforming change to the 

reference.

See the Justification for 

Comment XI.M7.5

The staff agreed with this comment, see 

XI.M7.5.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-8 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M17.1 XI.M17

FlowAccelerated 

Corrosion

Monitoring 

and Trending

Modified criteria for sample 

expansion.

Plant FAC programs typically 

use a threshold limit for sample 

expansion. Some plants use 

125% of time to next outage, 

some use 70% min wall 

thickness, some use minimum 

allowable, some use 50%, or 

less than 1 operating cycle, or 

significant unexpected wall 

thinning. Some plants use a 

combination of the above. But a 

strict threshold based on 

measured degradation being 

more than predicted would 

require sample expansion 

where it is unnecessary.

In a real world application, if the 

FAC program owner predicts 

the wear to be 5 mils over an 

18-month period and the actual 

as found wear is 6 mils then, 

per the current GALL, sample 

expansion is necessary.

Clearly, the wear is one 

element, but the minimum wall 

thickness is a critical input to 

the need for sample expansion.

In this particular example, if the 

pipe wall is 0.25 inches and has 

a min allowable wall thickness 

of 0.15 inches, then the pipe will 

last 16 refueling cycles. Sample 

expansion in this case is really 

not necessary.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-9 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M18.1 XI.M18 

Bolting 

Integrity

Entire 

Description

The Bolting Integrity Program 

should be extensively revised to 

focus on non-ASME bolting.

Basis for most changes 

explained in the revisions to the 

Program Description section.

The staff agreed with this comment. The 

entire Bolting Integrity Program has been 

rewritten. While the revised program does 

not implement all of the proposed NEI 

changes, it has been rewritten to better 

define the aging management strategies 

for the various classifications of bolting.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-10 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M18.2 XI.M18 

Bolting 

Integrity

Parameters 

Monitored/ 

Inspected

Explain that loss of preload is not 

an aging effect requiring 

management for non Class 1

bolting

Loss of preload is not an aging 

effect requiring management for 

non-Class 1 bolting. In 

accordance with EPRI 1003056 

Appendix F, loss of preload is a 

design driven effect and not an 

aging effect requiring 

management. Loss of preload 

due to stress relaxation (creep) 

for standard grade B7 carbon 

steel bolting is only a concern in 

very high temperatures (> 

700°F) as stated in the ASME 

Code Section II Part D Table 4 

Note 4. Non-Class 1 systems 

never exceed this temperature.

The majority of non-Class 1

bolting at most facilities is this 

same grade or very similar 

except in rare specialized 

applications. As a result stress 

relaxation should not occur for 

any of the non-Class 1 systems.

In addition, the resolution to 

GSI-29 for licensees would 

have taken actions to address 

the potential for this effect such 

that it is not a concern for the 

current or extended operating 

term. This position has been 

previously approved by the staff 

in the VC Summer SER 

NUREG 1787 section 3.0.3.7.2.

The staff acknowledges the NEI comment 

but concludes that additional 

mechanisms could lead to loss of 

preload/loss of prestress in addition to 

thermal effects. The AMP has been 

rewritten to refine the aging mechanisms 

that can lead to loss of preload/loss of 

prestress. Loss of preload/loss of 

prestress has been defined further in 

Chapter IX of GALL.
September 2005 A.2.11-11 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M21.1 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Program 

Description

Clarify intent of guidance 

reference in EPRI TR-107396.

There are no specific standards 

for testing and inspections in 

the guideline. The EPRI 

document merely mentions 

testing and inspections that are 

commonly applied.

The staff agreed with this comment. 

Additionally, the program discussion was 

changed to add cracking/stress corrosion 

cracking in addition to corrosion as aging 

mechanisms managed by this AMP. The 

EPRI guidelines referenced by this AMP 

include management of this aging effect.

This change (the inclusion of stress 

corrosion cracking as an aging effect 

managed by the AMP) was also included 

in other sections of the AMP, where 

appropriate.

The GALL Report was revised to address 

this proposed change.

XI.M21.2 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Program 

Description

Acknowledge acceptability of 

later versions of EPRI document.

The proposed wording will 

permit an applicant to credit a 

revision of the EPRI guidelines 

that has been reviewed and as 

part of a previous application.

The staff did not agree with this comment

(see XI.M2.1).

The GALL Report was not revised to 

address this proposed change.

XI.M21.3 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Parameters 

Monitored/ 

Inspected

Clarify intent of guidance 

reference in EPRI TR-107396.

There are no specific standards 

for testing and inspections in 

the guideline. The EPRI 

document merely mentions 

testing and inspections that are 

commonly applied.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-12 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M21.4 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Detection of 

Aging Effects

Clarify intent of guidance 

reference in EPRI TR-107396.

EPRI does not provide details 

on extent and schedule of 

inspections. It is a guidance 

document not a standard.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M21.5 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Detection of 

Aging Effects

Eliminate "pump wear 

characteristics"

Pump wear characteristics is an 

active function that is not in the 

scope of license renewal.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M21.6 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Monitoring 

and Trending

Clarify intent of guidance 

reference in EPRI TR-107396.

There is no testing interval 

specification in the EPRI 

guideline

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M21.7 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Acceptance 

Criteria

Clarify intent of guidance 

reference in EPRI TR-107396.

EPRI does not provide 

guidance on performance test 

results 

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M21.8 XI.M21 

Closed-Cycle 

Cooling 

Water 

System

Corrective 

Actions

Clarify intent of guidance 

reference in EPRI TR-107396.

EPRI does not provide 

corrective actions for 

performance failures.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-13 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M23.1 XI.M23 

Inspection of 

Overhead

Heavy Load 

and

Light Load 

(Related To 

Refueling) 

Handling 

Systems

Parameters 

Monitored/ 

Inspected

Delete sentence related to 

number of lifts.

It has been proven in previous 

applications that this is not a 

parameter that is monitored.

Calculated number of lifts is 

significantly lower than crane is 

designed for.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M23.2 XI.M23 

Inspection of 

Overhead

Heavy Load 

and

Light Load 

(Related To 

Refueling) 

Handling 

Systems 

Detection of 

Aging Effect

Delete sentence related to 

functional testing.

Functional tests do not detect 

aging effects.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M26.1 XI.M26 Fire 

Protection

Detection of 

Aging Effect

Replace prescriptive inspection 

requirements with general 

requirement that inspectors are 

qualified.

There are no regulatory 

requirements or any other type 

of requirements specifying that 

these inspections be performed 

to VT-1 or VT-3 standards.

The staff agreed with this comment. The

sentence was modified to state qualified 

fire protection inspectors.

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-14 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M26.2 XI.M26 Fire 

Protection

Acceptance 

Criteria

Add words to recognize 

allowable defect indications.

As currently worded, no 

indications of defects are 

acceptable. The criteria need to 

recognize variations from these 

strict limits that have been 

approved for the seal 

configuration.

The staff agreed with this comment

because inspection is performed by fire 

protection qualified inspectors.

The GALL Report is revised to address 

this comment.

XI.M27.1 XI.M27 Fire 

Water 

System

Program 

Description

Modify code references. The proposed changes 

recognize a second acceptable 

version of the NFPA Code.

The staff agreed with this comment 

because the 2002 version of the NFPA 

Code is acceptable.

The GALL Report was revised to address 

this proposed change.

XI.M27.2 XI.M27 Fire 

Water 

System

Program 

Description 

and 

Parameters 

Monitored/ 

Inspected

Modify sprinkler flow test 

requirements.

The proposed change 

recognizes practical flow test 

limitations.

The staff did not agree with this comment.

Maximum flow is part of CLB, thus must 

be demonstrated to for license renewal.

The GALL Report was not revised to 

address this proposed change.

XI.M27.3 XI.M27 Fire 

Water 

System

Parameters 

Monitored/ 

Inspected

Delete specific code reference. References do not correspond 

to the 2002 edition.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.

XI.M27.4 XI.M27 Fire 

Water 

System

Monitoring 

and Trending

Link requirements to plant 

commitments to code.

Existing plant commitments to 

code should determine 

monitoring and trending 

requirements.

The staff agreed with this comment.

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-15 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M31.1 XI.M31 

Reactor 

Vessel 

Surveillance

Program 

Description

Modify sentences delineating 

storage requirements for 

capsules.

The proposed revisions define a 

more appropriate set of storage 

guidelines that are consistent 

with vessel surveillance 

requirements.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32 .1 XIM32 OneTime 

Inspection

Program 

Description

Move sentences related to timing 

of OTI to section 4.0

These sentences add no value 

since the timing is specified in 

section 4.0 and is neither 

appropriate nor fit for the 

description.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32 .2 XIM32 OneTime 

Inspection

Program 

Description

Editorial comments Editorial correction, no 

justification is required.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32 .3 XIM32 OneTime 

Inspection

Scope of 

Program

Editorial comments Editorial correction, no 

justification is required.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32 .4 XIM32 OneTime 

Inspection 

Parameters 

Monitored/ 

Inspected

Clarify relevance of ASME Code 

to inspection requirements.

Most of the components 

included in this program are not 

ASME Code components and 

as such should not be 

subjected to Code 

requirements. This new wording 

is consistent with wording in 

section 4.0.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32.5 XIM32 OneTime 

Inspection

Detection of 

Aging Effects

Editorial comments Editorial correction, no 

justification is required.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-16 September 2005

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M32.6 XIM32 OneTime 

Inspection

Detection of 

Aging Effects

Remove table of example 

parameters/inspections

The addition of this table is 

unnecessary and overly 

prescriptive. In the prior 

paragraph wording is provided 

that the program will rely on 

established NDE techniques 

consistent with the Code that is 

sufficient for determining 

techniques. The techniques 

specified in the proposed table 

are Code requirements that 

should not be applied to noncode components. This will tie 

applicant’s hands in the ability 

to use various approaches and 

other techniques that may be 

developed in the future and 

have to justify deviations.

The staff did not agree with this comment. 

The table provides examples of 

parameters monitored or inspected and 

aging effects and mechanisms for specific 

structures or components; these 

examples may not be appropriate for all 

relevant situations. If the applicant 

chooses to use an alternative to the 

recommendations in this table, a 

technical justification should be provided 

as an exception to this AMP. This 

exception should list the AMR line-item

component, examination technique, 

acceptance criteria, evaluation standard,

and a description of the justification.

The GALL Report was not revised to 

address this proposed change.

XI.M32.7 XIM32 OneTime 

Inspection

Detection of 

Aging Effects

Move sentences related to timing 

of OTI to section 4.0

See comment XI.M32.1. The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M32 .8 XIM32 OneTime 

Inspection 

Operating 

Experience

Editorial comments Editorial correction, no 

justification is required.

The staff agreed with this comment. 

The GALL Report was revised to address 

this proposed change.

XI.M36 XIM36 

External 

Surfaces 

Monitoring 

Program

This is a new program; NEI 

proposed to add this AMP.

This program entails 

inspections of external surfaces 

of components in systems

The staff agreed with this comment with 

some modification. 

The GALL Report was revised to address 

this proposed change.
September 2005 A.2.11-17 NUREG-1832

Table A.2.11: Disposition of NEI Comments on Chapter XI.M of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

XI.M37 XIM37 Flux 

Thimble 

Tube 

Inspection 

Program

This is a new program; NEI 

proposed to add this AMP.

NEI recommends a new 

inspection program to monitor 

for the thinning of the flux 

thimble tube walls, which 

provide a path for the incore 

sensors to travel from the seal 

table, through the bottom of the 

reactor vessel, and into 

selected fuel assemblies. The 

thimble tubes over most of the 

length serve as the RCS 

pressure boundary and are 

experiencing thinning as a 

result of flow-induced vibration.

It appears that the only effective 

method for determining thimble 

tube integrity is through plantspecific inspections and 

periodic monitoring. 

An NDE methodology, such as 

eddy current testing (ECT), is 

used to monitor for wear of the 

flux thimble tubes. This program 

implements the 

recommendations of NRC IE 

Bulletin 88-09,

The staff agreed with this comment with 

some modification. 

The GALL Report was revised to address 

this proposed change.
NUREG-1832 A.2.11-18 September 2005

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September 2005 A.2.12-1 NUREG-1832

Table A.2.12: Disposition of NEI Comments on Chapter XI.S of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.XI-S-1 XI.S1, ASME 

Section XI, 

Subsection 

IWE;

XI.S2, ASME

Section XI, 

Subsection 

IWL;

XI.S3, ASME

Section XI, 

Subsection 

IWF

Revise footnote wording as 

shown:

10 CFR 50.55a is revised 

periodically to adopt, by 

reference, new editions, and 

addenda of the ASME Code. For 

each successive 120-month (10 

year) inspection interval, 

applicants are required to revise 

the nuclear plant’s ISI program 

to incorporate the requirements 

specified in the version of the 

ASME Code incorporated into 

10 CFR 50.55a 12 months 

before the start of the inspection 

interval. Because a plant’s 10 

year ISI programs is based on 

the edition of the ASME Code 

when the ISI program is 

prepared, the ISI program based 

on any edition and addenda of 

the ASME Code adopted by the 

NRC in 10 CFR 50.55a is an 

acceptable aging management 

program that can be credited in 

a license renewal application as 

consistent with NUREG 1801 

without justifying exceptions.

The footnote is based on ASME 

Section XI. The note discusses 

that the NRC adopts the use of 

updated versions of ASME XI in 

10 CFR 50.55a but does not 

state that an applicant may 

credit the updated versions.

The Bases Document for the 

revision to the GALL Report 

states that the addition of the 

code used in the plant’s ISI 

program, which is based on 10 

CFR 50.55a, can be used as an 

AMP in a LRA.

See the response to comment XI.M1.1 in 

Table A.2.11.
NUREG-1832 A.2.12-2 September 2005

Table A.2.12: Disposition of NEI Comments on Chapter XI.S of the GALL Report

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

G.XI-S-2 XI.S7, RG 

1.127, 

Inspection of 

WaterControl 

Structures 

Associated 

with Nuclear 

Power Plants

Add conditional statement 

acknowledging use of structures 

monitoring program for certain 

structures for plants committed 

to RG 1.127.

Some plants committed to RG 

1.127 already use structures 

monitoring program for certain 

structures (e.g., Intake 

Structure Concrete). The 

change will reduce the 

likelihood of exceptions to the 

program.

The staff agreed with this comment. The 

GALL AMP XI.S7 program description was 

revised to add the following:

Even if plant is committed to RG 1.127, 

Revision 1, aging management of certain 

structures and components may be included 

in the Structures Monitoring Program (XI.S6).
September 2005 A.2.13-1 NUREG-1832

Table A.2.13: Disposition of NEI Comments on Chapter 2 of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S.2-1 2.1.2.1 In this and other paragraphs, 

Revision 3 of NEI 95-10 is 

referenced. Draft Regulatory 

Guide (RG) DG-1140 (RG 1.188) 

references NEI 95-10, Rev. 5.

This is a generic comment as 

Revision 3 is referenced in 

several sections of the SRP-LR.

Editorial The staff agrees with this comment that 

Rev. 3 of NEI 95-10 is not the correct 

reference. As of June 2005, the RG 1.188 

references NEI 95-10, Rev. 6

The SRP-LR was revised to address 

these proposed changes.

S.2-2 2.1.2.2 Change Regulatory Guide 1.1888 

to Regulatory Guide 1.188.

Editorial The staff agreed with this editorial 

comment.

The SRP-LR was revised to address 

these proposed changes.

S.2-3 Table 2.1-

4(a) and (b)

Table needs to be changed to 

match NEI 95-10 Rev.5 Table 

4.1-1

Consistency The staff agreed with this comment 

because NEI 95-10, Rev. 6 is the correct 

version and the SRP-LR Table should 

match this revision.

The SRP-LR was revised to address 

these proposed changes.

S.2-4 Table 2.1-

4(b)

In the Intended Function column, 

Electrical Continuity should not 

be bold type.

Editorial The staff agreed with this editorial 

change.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.13-2 September 2005

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September 2005 A.2.14-1 NUREG-1832

Table A.2.14: Disposition of NEI Comments on Chapter 3, Section 3.1, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S.3.1-1 3.1.2.2.2.1 Clarify intent of NRC Information 

Notice (IN) 90-04 

Refer to comments for NUREG1801 Vol. 2 Items IV.D1-16 and 

IV.D2-10.

Discussion does not clearly 

convey the nature of the 

degradation mechanism, which 

is related to a very specific set 

of conditions, not to most SGs.

IN 90-04 indicates that pitting 

corrosion on the surface served 

as corrosion fatigue crack 

initiation sites, not that pitting 

corrosion resulted in sufficient 

degradation to cause loss of 

component function.

Further, this degradation mode 

has been limited to isolated 

cases of weld-zone cracking in 

Westinghouse Model 44 and 51 

SGs, where a high stress region 

exists in the area of the shell to 

transition cone weld.

The staff agreed with this comment 

because this aging degradation is limited 

to a specific type of Westinghouse steam 

generators.

The SRP-LR was revised to address 

these proposed changes.

S3.1-2 3.1.2.2.4.2 Delete redundant text Editorial The staff agreed with this editorial 

comment.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.14-2 September 2005

Table A.2.14: Disposition of NEI Comments on Chapter 3, Section 3.1, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S3.1-3 3.1.2.2.4.3 Delete mention of cyclic loading 

and loss of material

The subject of this item is 

cracking due to SCC and 

IGSCC. As such, requirements 

to augment AMP for cracking 

due to cyclic loading or for loss 

of material due to pitting and 

crevice corrosion do not belong 

or are addressed elsewhere.

Firstly, cyclic loading of isolation 

condenser components is not 

an aging effect identified in 

NUREG-1801 Volume 2.

Secondly, NUREG-1801 Vol. 2 

Item IV.C1-6 (R-16) addresses 

LOM. Table 3.1.1, Item 5 (R-16) 

lists 3.1.2.2.2.2 as the 

applicable SRP-LR section and 

not 3.1.2.2.4.3.

The staff agreed with this comment

because the information for cyclic loading 

and loss of material is included in other 

subsections as identified in Table 3.1-1.

The SRP-LR was revised to address 

these proposed changes.

S3.1-4 3.1.2.2.8 Delete "due to line" to correct 

sentence.

Editorial correction. Either 

delete words or determine what 

is missing from the 2nd

sentence.

The staff agreed with this editorial 

comment. The extra words were delet ed.

The SRP-LR was revised to address 

these proposed changes.

S3.1-5 3.1.2.2.18 Eliminate specific fluence level Editorial – fluence level is not 

required part of the description, 

neutron flux would be adequate 

terminology.

The staff agreed with this comment. 

The GALL Report was revised to address 

these proposed changes.

S3.1-6 Table 3.1-1 Odd page footers are for 

NUREG-1801.

Editorial The staff agreed with this editorial 

comment

The SRP-LR was revised to address 

these proposed changes.
September 2005 A.2.14-3 NUREG-1832

Table A.2.14: Disposition of NEI Comments on Chapter 3, Section 3.1, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S3.1-7 Table 3.1-1,

Table 3.2-1,

Table 3.3-1,

Table 3.4-1

Note: This 

comment 

actually 

applies to 

the rollup 

Tables of 

GALL 

Volume 1., 

which then 

become the 

tables in the 

SRP

When addressing Further 

Evaluation Recommended 

issues, avoid mixing internal and 

external environments for the 

same component.

For example, Table 3.2-1, ID 2 

addresses "Steel components 

(including piping and ducting) 

exposed to external 

condensation or outside air, 

internally or externally to indoor 

uncontrolled air." Table 3.2-1, ID 

11 addresses "Steel piping, 

piping components, and piping 

elements (internal surfaces) and 

ducting closure bolting exposed 

to condensation (internal, treated 

water, or air –indoor uncontrolled 

(external)." In this case, the 

words "internally or" should be 

deleted from ID 1 and the word 

"external" should be replaced 

with "internal." Of course the 

related items from NUREG-1801, 

Volume 2, that deal with external 

surfaces should point to ID 1; 

while those dealing with internal 

surfaces should point to ID 11. If 

the NUREG-1801, Volume 2, 

related items are unclear about 

which surface is being 

addressed, those items should 

be clarified.

Typically the plant-specific 

program applied to internal 

surfaces is not the same 

program as applied to external 

surfaces. Addressing the plantspecific programs to be used 

would be simplified if separate 

LRA discussions were 

permitted for external and 

internal surfaces. The 

suggested changes would also 

eliminate a source of confusion 

regarding which surfaces are 

being addressed in GALL rollup line-items.

The staff agreed with this comment for 

those tables where it applies. This 

comment is not applicable for Table 3.1-

1. Each SRP-LR line-item should only 

address one type of environment, internal 

or external and the associated AMP 

recommended managing the aging 

effects.

See Appendix A.2.16 for applicability to 

Table 3.2-1; Appendix A.2.17 for Table 

3.3-1.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.14-4 September 2005

Table A.2.14: Disposition of NEI Comments on Chapter 3, Section 3.1, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S.3.1-8 Table 3.1-1 Delete Loose Parts Monitoring 

and Neutron Noise rows from

table.

These programs are not 

credited in GALL.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.
September 2005 A.2.15-1 NUREG-1832

Table A.2.15: Disposition of NEI Comments on Chapter 3, Section 3.2, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S3.2-1 Table 3.2-1,

ID 2, 11

This is a 

generic 

comment 

applicable to 

Tables 3.2-

1, 3.3-1, and 

3.4-1, 

various IDs

When addressing Further 

Evaluation Recommended 

issues, avoid mixing internal and 

external environments for the 

same component.

For example, Table 3.2-1, ID 2 

addresses "Steel components 

(including piping and ducting) 

exposed to external 

condensation or outside air, 

internally or externally to indoor 

uncontrolled air." Table 3.2-1, ID 

11 addresses "Steel piping, 

piping components, and piping 

elements (internal surfaces) and 

ducting closure bolting exposed 

to condensation (internal, treated 

water, or air –indoor uncontrolled 

(external)." In this case, the 

words "internally or" should be 

deleted from ID 1 and the word 

"external" should be replaced 

with "internal." Of course the 

related items from NUREG-1801, 

Volume 2, that deal with external 

surfaces should point to ID 1; 

while those dealing with internal 

surfaces should point to ID 11. If

the NUREG-1801, Volume 2, 

related items are unclear about 

which surface is being 

addressed, those items should 

be clarified.

Typically the plant-specific 

program applied to internal 

surfaces is not the same 

program as applied to external 

surfaces. Addressing the plantspecific programs to be used 

would be simplified if separate 

LRA discussions were 

permitted for external and 

internal surfaces. The 

suggested changes would also 

eliminate a source of confusion 

regarding which surfaces are 

being addressed in GALL rollup line-items.

The staff agreed with this comment for 

those tables where it applies. Each SRPLR line-item should only address one type 

of environment, internal or external and 

the associated AMP recommended 

managing the aging effects.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.15-2 September 2005

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September 2005 A.2.16-1 NUREG-1832

Table A.2.16: Disposition of NEI Comments on Chapter 3, Section 3.3, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S3.3-1 Table 3.3-1,

IDs 10, 16, 

17, 23, 28, 

46, 47, 49, 

50 

This is a 

generic 

comment 

applicable to 

Tables 3.2-1,

3.3-1, and 

3.4-1, 

various IDs

When addressing Further 

Evaluation Recommended issues, 

avoid mixing internal and external 

environments for the same 

component.

For example, Table 3.2-1, ID 2 

addresses "Steel components 

(including piping and ducting) 

exposed to external condensation 

or outside air, internally or 

externally to indoor uncontrolled 

air." Table 3.2-1, ID 11 addresses 

"Steel piping, piping components, 

and piping elements (internal 

surfaces) and ducting closure 

bolting exposed to condensation 

(internal, treated water, or air –

indoor uncontrolled (external)." In 

this case, the words "internally or"

should be deleted from ID 1 and 

the word "external" should be 

replaced with "internal." Of course 

the related items from NUREG1801, Volume 2, that deal with 

external surfaces should point to 

ID 1; while those dealing with 

internal surfaces should point to ID 

11. If the NUREG-1801, Volume 2, 

related items are unclear about 

which surface is being addressed, 

those items should be clarified.

Typically the plant-specific 

program applied to internal 

surfaces is not the same 

program as applied to 

external surfaces. Addressing 

the plant-specific programs to 

be used would be simplified if 

separate LRA discussions 

were permitted for external 

and internal surfaces. The 

suggested changes would 

also eliminate a source of 

confusion regarding which 

surfaces are being addressed 

in GALL roll-up line-items.

The staff agreed with this comment for 

those tables where it applies. Each SRPLR line-item should only address one type 

of environment, internal or external and 

the associated AMP recommended 

managing the aging effects.

Appendix A.2.16 addresses Table 3.2-1 

IDs, and A.2.18 addresses Table 3.4-1 

IDs.

The SRP-LR was revised to address these 

proposed changes.
NUREG-1832 A.2.16-2 September 2005

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September 2005 A.2.17-1 NUREG-1832

Table A.2.17: Disposition of NEI Comments on Chapter 3, Section 3.4, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S3.4-1 Table 3.4-1,

IDs 3,5,11

This is a 

generic 

comment 

applicable to 

Tables 3.2-1,

3.3-1, and 

3.4-1, 

various IDs

When addressing Further 

Evaluation Recommended 

issues, avoid mixing internal and 

external environments for the 

same component.

For example, Table 3.2-1, ID 2 

addresses "Steel components 

(including piping and ducting) 

exposed to external 

condensation or outside air, 

internally or externally to indoor 

uncontrolled air." Table 3.2-1, ID 

11 addresses "Steel piping, 

piping components, and piping 

elements (internal surfaces) and 

ducting closure bolting exposed 

to condensation (internal, 

treated water, or air –indoor 

uncontrolled (external)." In this 

case, the words "internally or"

should be deleted from ID 1 and 

the word "external" should be 

replaced with "internal." Of 

course the related items from 

NUREG-1801, Volume 2, that 

deal with external surfaces 

should point to ID 1; while those 

dealing with internal surfaces 

should point to ID 11. If the 

NUREG-1801, Volume 2, 

related items are unclear about 

which surface is being 

addressed, those items should 

be clarified.

Typically the plant-specific 

program applied to internal 

surfaces is not the same 

program as applied to external 

surfaces. Addressing the plantspecific programs to be used 

would be simplified if separate 

LRA discussions were 

permitted for external and 

internal surfaces. The 

suggested changes would also 

eliminate a source of confusion 

regarding which surfaces are 

being addressed in GALL rollup line-items.

The staff agreed with this comment for 

those tables where it applies. Each SRPLR line-item should only address one type 

of environment, internal or external and 

the associated AMP recommended 

managing the aging effects.

Appendix A.2.16 addresses Table 3.2-1 

IDs, and A.2.17 addresses Table 3.3-1 

IDs.

The SRP-LR was revised to address these 

proposed changes.
NUREG-1832 A.2.17-2 September 2005

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September 2005 A.2.18-1 NUREG-1832

Table A.2.18: Disposition of NEI Comments on Chapter 3, Section 3.5, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S.3.5-1 SRP-LR 3.5 The changes marked in this 

section support the 

consolidation of tables in GALL 

Chapter III. NEI recommended 

reducing the number of subsections from 9 to 3.

The tables of Chapter III for the 

various structures and 

component supports are highly 

repetitive.

To simplify these GALL tables, 

the nine structures tables have 

been consolidated into three 

tables. Tables A1, A2, A3, A4, 

A5, and A9 comprise a new 

Group 1 Structures Table; Table 

A6 becomes a new Group 2 

Structures Table; and Tables A7 

and A8 are joined to become a 

new Group 3 Structures Table.

Similarly, the three ASME piping 

supports tables B1.1, B1.2 and 

B1.3 are combined as a table 

for supports for ASME piping 

and components and Class MC 

(BWR Containment Supports); 

and the remaining four tables 

have been combined as a table 

for all other supports (see also 

the endnotes to this table for 

NEI’s presentation of general 

comment 1).

The staff did not agree with this comment 

to reduce the number of sub-sections from 

9 to 3 because it does not meet the 

requirements of 10 CFR 54.21a (1), and it 

is not consistent with the format of GALL 

Chapter II.

The SRP-LR was not revised to address 

these proposed changes.

S.3.5-2 Table 3.5-1, 

ID 24

 NEI recommended the AMP 

column add on another 

alternative program as follow:

Chapter XI.S6 "Structures 

Monitoring Program"

NEI proposed that change 

recognizes that the Structures 

Monitoring Program (SMP) is 

also commonly used for aging 

management of concrete in the 

water control structures.

The staff did not agree with this comment 

because the Army Core of Engineers

guidelines for water-control structures are 

very specific. SMP is too general.

However, staff agreed to provide this 

option in the description for AMP XI.S7, 

provided the necessary elements of XI.S7 

are addressed. AMP XI.S7 was revised to 

address this change. See Appendix 

A.2.12 in NUREG-1832.
NUREG-1832 A.2.18-2 September 2005

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September 2005 A.2.19-1 NUREG-1832

Table A.2.19: Disposition of NEI Comments on Chapter 3, Section 3.6, of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S.3.6-1 Sections 

3.6.2.2.2, 

3.6.2.2.3, 

and 

3.6.2.2.4, 

and Sections 

3.6.3.2.2, 

3.6.3.2.3, 

and 

3.6.3.2.4

These sections are noted as 

"Deleted." Rather than include 

these sections as they are 

presently annotated, delete 

them entirely.

Some applicants prefer to align 

the LRA section numbers of 

Further Evaluation 

Recommended items so that 

they correspond to the 

paragraphs in NUREG-1800.

Including these deleted sections 

would make it more difficult and 

awkward to achieve one-to-one 

correspondence.

The staff agreed with this comment.

The SRP-LR sections are revised.
NUREG-1832 A.2.19-2 September 2005

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September 2005 A.2.20-1 NUREG-1832

Table A.2.20: Disposition of NEI Comments on Chapter 4 of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S4.1-1 Table 4.1-3 Split up the multiple TLAAs 

listed in rows one and five of 

the table, i.e., Make "Lowtemperature overpressure 

protection (LTOP) analyses,"

"Flow induced vibration 

endurance limit," transient cycle 

count assumptions," and 

"ductility reduction of fracture 

toughness for the reactor vessel 

internals" separate lines on the 

table.

These TLAAs will be easier to 

address on a one-by-one basis, 

for example, by reference to a 

specific section of the LRA.

Grouping them together has 

necessitated referencing multiple 

LRA sections for one line-item.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.

S4.2-1 Section 

4.2.2.1.2

Correct typographical error in 

last sentence.

Editorial The staff agreed with this editorial 

comment.

The SRP-LR was revised to address 

these proposed changes.

S4.2-2 Section 

4.2.3.1.1.2.2

Provide flexibility in information 

provided for equivalent margins 

analysis

Many Applicants will not have 

fluence predictions at 1-inch, but 

rather at 3⁄4-T. The applicant 

should provide the 1⁄4-T and 3⁄4-T 

data at the time of submittal. This 

is based upon the NRC’s request 

in an RAI for Farley.

The staff did not agree with this 

comment. The 3⁄4-T is not used in the 

equivalent margin analysis.

The SRP-LR was not revised to address 

these proposed changes.

S4.3-1 Sections 

4.3.1.1.1,

4.3.2.1.1.2,

4.3.3.1.1.2

Correct stated Code limit for 

CUF from "less than one" to 

"less than or equal to one."

The Code, and many applicants 

CLB, allow for a CUF equal to 

unity over the service life.

The staff agreed with this comment. 

The SRP-LR was revised to address 

these proposed changes.

S4.3-2 Sections 

4.3.2.1.2.2, 

4.3.3.1.2.2

Allow for stress reduction 

factors that may differ from 

those in Table 4.3-1

The applicant’s code of record is 

bounding in their CLB. Table 4.3-

1 appears to be appropriate for 

most cases, but it may not be for 

all cases.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.20-2 September 2005

Table A.2.20: Disposition of NEI Comments on Chapter 4 of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S4.3-3 Section 

4.3.3.2.3

Provide flexibility for future 

references for environmental 

life correction factors by adding 

the phrase "or an approved 

technical equivalent."

Leaves room for improvement in 

the research into the 

phenomenon and improvements 

in calculational methods.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.

S4.5-1 Section 4.5.1 Clarify requirements for 

evaluating existing TLAA

10CFR54 does not require 

TLAAs to be created to address 

this aging effect; however 

analyses/calculations to address 

the aging effect of loss of 

prestress in containment tendons 

generally exist and generally 

meet the definition of a TLAA as 

given by 10CFR54.3.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.

S4.5-2 Sections 

4.5.2.1.1, 

4.5.2.1.2, 

4.5.3.1.2, 

Table 4.5-1

Update acceptance criteria –

replace "predicted lower limit 

(PLL)" with "minimum required 

prestress force specified at 

anchorage"

The update meets the 

requirement per ASME Section 

XI, Sub-section IWL Acceptance 

criteria

The staff agreed with this comment. 

The SRP-LR was revised to address 

these proposed changes.

S4.5-3 Section 

4.5.2.1.3

Acknowledge GALL as 

guidance rather than 

requirement.

ISG-1 was approved to 

implement this change

The staff agreed with this change 

because other sections of SRP-LR 

implemented ISG-1.

The SRP-LR was revised to address 

these proposed changes.

S4.5-4 Section 

4.5.3.1.3

Address evaluations outside 

GALL guidance

ISG 1 The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.

S4.5-5 Section 4.5.6 Change Reference 4, NUREG1801 July 2001, to NUREG1801, Revision 1, September 

2005

Editorial The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.
September 2005 A.2.20-3 NUREG-1832

Table A.2.20: Disposition of NEI Comments on Chapter 4 of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S4.5-6 Table 4.5-1 10 CFR 54.21(1)(i) and 10 CFR 

54.21(1)(ii) Examples are 

repeat information, so it should 

be consolidated in one item.

Updated to meet the requirement 

per ASME Section XI, Subsection IWL Acceptance criteria

The staff agreed with this change 

because the information is duplicated in 

two different rows, and could be 

combined.

The SRP-LR was revised to address 

these proposed changes.

S4.6-1 Sections 

4.6.1.1.1,

4.6.2.1.1.3,

4.6.3.1.1.3,

Table 4.6-1

Correct stated Code limit for 

CUF from "less than one" to 

"less than or equal to one."

Code allows CUF to be equal to 

1.0 for the entire service life of 

the bellows. Many calculations 

on bellows are done to show that 

an extremely large number of the 

design cycles may be 

experienced without CUF = 1.0.

In this case, there is no TLAA as 

the assumption is not based 

upon the original license term.

The staff agreed with this comment.

The SRP-LR was revised to address 

these proposed changes.
NUREG-1832 A.2.20-4 September 2005

Table A.2.20: Disposition of NEI Comments on Chapter 4 of SRP-LR

Comment 

Number

Item 

Number Comment/Proposed Change Basis for Comment NRC Disposition

S4.7-1 Section 4.7.3 Replace the existing first 

paragraph with the following 

words:

For certain applicants, plantspecific analyses may meet the 

definition of a TLAA as given in 

10CFR54.3. The concern for 

License Renewal is that these 

analyses may not have 

properly considered the length 

of the extended period of 

operation, the consideration of 

which may change conclusions 

with regard to safety and the 

capability of SSCs within the 

scope of the Rule to perform of 

one or more safety functions. 

The review of these TLAAs will 

provide the assurance that the 

aging effect is properly 

addressed through the period 

of extended operation."

NEI stated that this paragraph 

appears to present the 

information in an awkward 

manner. The alternative 

paragraph was proposed with the 

intent to focus on the Rule and

its requirements.

The staff agrees with this comment. 

The SRP-LR was revised to address this 

proposed change.
September 2005 B-1 NUREG-1832

APPENDIX B:

Disposition of Comments from the 520th Meeting of the

NRC Advisory Committee on Reactor Safeguards (ACRS)

held on March 4, 2005

B.1 INTRODUCTION

The NRC Advisory Committee on Reactor Safeguards (ACRS) held its 520th meeting on March 

4, 2005 which included a presentation from staff addressing the planned changes to LRG 

documents.On April 6, 2005 the ACRS provided additional comments during its review of a 

draft SER for Millstone’s License Renewal Application (LRA). Each of these comments has 

been evaluated, and the LRG documents have been revised, as needed, based on the staff’s 

disposition of these comments.

B.2. EVALUATION AND DISPOSITION OF COMMENTS 

Table B provides the evaluation and disposition for each of the ACRS comments. 

The column heading "Comment Number" is primarily intended to provide the source of the 

comment, meaning the individual that made the comment. For example, ACRS-SHACK-1 

indicates that the comment was made by Dr. Shack and the "1" segregates this comment from 

all other comments he made.

B.3 REFERENCES

Official Transcript of the 520th Meeting of the Advisory Committee on Reactor Safeguards 

Proceeding, March 4, 2005. (ADAMs Accession No. ML05070048)

Official Transcript of Proceedings ACRST-3309, Advisory Committee on Reactor Safeguards 

Plant License Renewal Subcommittee, Wednesday, April 6, 2005. (ADAMS Accession # 

ML051110405)
NUREG-1832 B-2 September 2005

This Page Intentionally Left Blank
September 2005

B-3 NUREG-1832

Table B: Disposition of Comments from Transcript of 3/4/05 Review by NRC Advisory Committee on Reactor Safeguards (ACRS) 

Comment 

Number

TpgComment/Proposed 

Change Basis for Comment NRC Disposition

ACRSShack-0153 Is there a link from the GALL 

Report programs to a related 

ISG (Interim Staff 

Guidance)?

Concern for traceability of the 

ISGs as they become 

incorporated into the LRG 

documents.

When incorporation of an ISG is made in the LRG 

documents it will be reflected in the basis document.

The basis document will provide the link between the 

revised LRG documents and the original ISG.

ACRSWallace-0272 Throughout this discussion 

and throughout the tables 

that have been presented, 

"criteria," the plural form of 

"criterion," is used 

incorrectly, will that be 

corrected?

Concern over proper grammar. The staff reviewed the updated LRG documents to

ensure that this term is used correctly.

ACRS -

Rosen-01

110 

and 

157

As stated on p.110 of the 

transcript from the 4/6/05 

ACRS Subcommittee review 

of the draft LR-SER for an 

applicant, the NRC staff was 

asked whether or not aging 

effects for halon and carbon 

dioxide fire suppression 

systems should be included.

Later, to paraphrase the 

discussion on p.157 of the 

transcript from the 4/6/05 

ACRS Subcommittee review 

of the draft LR-SER for this 

applicant, the staff was 

requested to clarify under 

what circumstances aging 

effects would be expected

from halon/carbon dioxide in 

the fire suppression system 

and to make appropriate 

revisions to GALL.

The wording in the LR-SER 

(3.0.3.2.7 Fire Protection 

Program) about aging effects 

associated with the 

halon/carbon dioxide fire 

suppression system can lead to 

questions about clarity in the 

GALL AMPXI.M26 for fire 

protection.

The staff reviewed the LR-SER of concern and 

determined that it was not necessary to change any of 

the LRG documents on the basis of this comment.

The guidance in GALL AMPXI.M26 is based on 

standards from the National Fire Protection 

Association (NFPA) for halon and carbon dioxide fire 

suppression systems. NFPA 12A: Standard on Halon 

1301 Fire Extinguishing Systems, (last updated in 

2004) provides safety requirements for designing, 

installing, testing, inspecting, approving, listing, 

operating, maintaining, decommissioning, and 

removing halon systems. NFPA 12: Standard on 

Carbon Dioxide Extinguishing Systems, (last updated 

in 2000) provides minimum requirements for 

installation and maintenance of carbon dioxide 

extinguishing systems and covers total flooding 

systems, local application systems, hand hose line 

systems, standpipe systems, and mobile supplies.

The LRG documents were not revised to address this 

proposed change.
NUREG-1832

B-4 September 2005

Table B: Disposition of Comments from Transcript of 3/4/05 Review by NRC Advisory Committee on Reactor Safeguards (ACRS) 

Comment 

Number

TpgComment/Proposed 

Change Basis for Comment NRC Disposition

ACRSRosen-02153 As stated on p. 153 of the 

transcript from the 4/6/05 

ACRS Subcommittee review 

of the draft LR-SER for an 

applicant, the staff was 

requested to clarify why riskinformed ISI was not 

credited. Rosen said the staff 

needs to take that to heart 

and have another look at the 

GALL Report and maybe

consider an ISG at some 

point.

It is not clear why the riskinformed in-service inspection 

programs are not being credited 

as acceptable alternatives to

conventional programs.

The GALL Report contains acceptable approaches for 

managing aging effects for various SSCs within the 

scope of the license renewal rule. Provisions for the 

use of risk-informed ISI programs are being 

incorporated in the current licensing basis of existing 

plants, but similar application of risk-informed 

programs for license renewal were not included as part 

of 10 CFR 54. Should a licensee choose to utilize a 

risk-informed approach for ISI for license renewal, it 

will be required to provide the technical basis for its 

acceptability in order to satisfy the requirements of 10 

CFR 54(a)(3).

Available staff and other resource constraints currently 

prevent the development of an ISG to guide the use of 

risk-informed ISI, should license renewal applicants 

choose to apply such programs that are part of their 

current licensing basis. Risk-informed inservice 

inspection is an area of active interest at NRC. The 

staff will consider development of an ISG for the use of 

risk-informed ISI in license renewal applications as 

resources and other priorities allow.
September 2005 C-1 NUREG-1832

APPENDIX C:

Disposition of Participant Comments from the

License Renewal Public Workshop

C.1. INTRODUCTION

On March 2, 2005, the staff held a license renewal public workshop to obtain feedback and 

comments on the updated LRG documents which were issued for public comment on February 

1, 2005 (70FR5254).

At this meeting, key staff members responsible for updating these LRG documents made 

presentations describing the process that was used to make changes to the LRG documents.

Mr. David Lochbaum from the Union of Concerned Scientists made a presentation expressing 

his organization’s concerns with the license renewal process, and representatives from the 

Nuclear Energy Institute presented information describing the comments they were making on 

the updated LRG documents. Additionally, county legislators from Westchester and Ulster 

Counties in New York made presentations identifying their concerns regarding the staff’s review 

of a future license renewal application.

C.2. PARTICIPANT AFFILIATION

The participant list for the March 2, 2005 License Renewal Public Workshop is provided below.

This is sorted alphabetically first by organizational affiliation and then by the first name of the 

attendee. Individuals who participated and whose comments are included in this appendix are 

noted by an asterisk (*) next to their name.

Participant Affiliation

Wayne Lunsford Alliance

Bob Kalinowski American Electric Power – D.C. Cook

Massoud Tafazzoli AREVA

Paul Crawley Arizona Public Service – Palo Verde

Charles Willbanks ATL Intl

David Wootten Dominion Resources

Alan Cox Entergy Nuclear

Garry Young Entergy Nuclear

Jacque Lingenfelter Entergy Nuclear

Reza Ahrabis Entergy Nuclear

Roger Rucker Entergy Nuclear

Fred Polaski Exelon

Farideh Saba ISL

Jon Woodfield ISL

Kirayaku Kyn JEPIC
NUREG-1832 C-2 September 2005

Participant Affiliation

Deann Raleigh LIS Scientech

Kathryn Sutton Morgan, Lewis & Bockius LLP

Fred Emerson * NEI

Paul Genoa NEI

Dennis Zannoni The State of New Jersey

Brian Wohlers NMC

Patrick Burke NMC

Steven Schellin NMC- PB

Darrel Turner NMC - Palisades

Aida Rivera-Varina NRC

Allision Black NRC

Amar Pal NRC

Amy Hull NRC

Barry Elliot NRC

Carolyn Lauron NRC

Cayatano Santos NRC

Chang Li NRC

Chip Cameron NRC

Daniel Merzke NRC

David Jeng NRC

Duc Nguyen NRC

Frank Gillespie NRC

Greg Cranston NRC

Jake Zimmerman NRC

Jerry Dozier NRC

Johnny Eads NRC

Jonathan Rowley NRC

Juan Ayala NRC

Kaihwa Hsu NRC

Kamalakar Naidu NRC

Ken Chang NRC

Kimberley Corp NRC

Kurt Cozens NRC

Makuteswara Srinivasan NRC

Mario Bonaca NRC

Mark Lintz NRC

Melissa Jenkins NRC

Michael Waterman NRC
September 2005 C-3 NUREG-1832

Participant Affiliation

Naeem Iqbal NRC

Pao- Tsin Kuo NRC

Peter Kang NRC

Ram Subbaratnam NRC

Samson Lee NRC

Steve Hoffman NRC

Steve West NRC

Tomeka Terry NRC

Zahira Cruz NRC

Dan Naus ORNL

Al Baione Parallax

Russell Wells Parallax

Eric Blocher Parsons Energy & Chemical :

John Oddo PPL

Michael B. Detamore PPL

Roger Stewart Progress Energy

Chalmer Myer Southern Nuclear

Mike Macfarlane Southern Nuclear

Partha Ghosal Southern Nuclear

Tom Greene Southern Nuclear

David Lochbaum * UCS

Brian Shapiro * Ulster County Legislature

Susan Zimet * Ulster County Legislature

Michael Kaplowitz * Westchester County Legislature, NY

Tara Bernard * Westchester County Legislature, NY

Todd Anselmi Wolf Creek Nuclear Operating Corp.

John Bowen WPI

C.3. EVALUATION AND DISPOSITION OF COMMENTS

Table C contains comments provided by the participants at the workshops. The column heading 

"Commenter and Affiliation" is primarily intended to provide the source of the comment, 

meaning the individual and his/her affiliated organization that submitted the comment. For 

example, Emerson -1, NEI, indicates that the comment was made by Mr. Emerson of NEI and 

the "1" segregates this comment from other comments made by that individual. 

This table is sorted by the page number where the comment appeared in the meeting’s 

transcript.
NUREG-1832 C-4 September 2005

C.4. REFERENCES

Official Transcript of the Workshop on Revised License Renewal Guidance Documents, March 2, 2005.

(ADAM Accession No. ML050750296)
September 2005

C-5 NUREG-1832

Table C: Disposition of Comments from License Renewal Public Workshop

Comment 

Number

Tpg

Comment/Proposed Change Basis for Comment NRC Disposition

Lochbaum1, UCS43 We will be probably providing 

some written comments very 

similar to this effect by the 

end of the month for the 

process.

To supplement the 

presentations made at the 

public workshop, formal 

comments will be provided.

Mr. Lochbaum has written a book that identifies, in 

detail, the concerns he expressed at the meeting. The 

topics presented in this book were identified and 

responded to in Appendix D, Table D.2. These topics 

are identified by the number eight (8) following the 

comment identifier.

Emerson-1, 

NEI

47 At the end of the comment 

period, at the end of March, 

we’ll provide more detailed 

comments which are going to 

be provided in a manner that 

will help the staff address the 

issues that we think need to 

be addressed to improve the 

process.

In addition to the comments 

provided during this public 

workshop, formal comments will 

be provided.

Appendix A to this NUREG contains the NEI 

comments and corresponding staff dispositions.

Legislators 

from 

Westchester 

and Ulster 

Counties, 

NY.-1

201 Expressed concern with the 

prospect of NRC approving 

the future license renewal 

applications of the Indian 

Point commercial nuclear 

power plant licenses.

Legislators provided positions 

that are contained in the 

workshop transcript.

The purpose of this public workshop was to solicit 

specific comments on the draft changes to the LRG 

documents provided on January 31, 2005. The 

comments provided by these legislators were broader 

license renewal issues and outside the scope of the 

proposed updated LRG documents.
NUREG-1832

C-6 September 2005

This Page Left Intentionally Blank
September 2005 D-1 NUREG-1832

APPENDIX D:

Disposition of Written Public Comments

D.1. INTRODUCTION

On February 1, 2005, the updated LRG documents were made available for public comment on 

the NRC web site. The public was requested to submit comments on Draft Regulatory Guide 

DG-1104, the draft SRP-LR, and the draft GALL Report by March 31, 2005. 

D.2. ORIGIN OF WRITTEN PUBLIC COMMENTS 

As provided in the following listing, eight written public comments were submitted during the 

public comment period. This listing below provides the name of the person providing the

comment, his/her affiliation, and the location of the complete text of the comment. An identifier is 

also provided to associate the particular comment with the more detailed comment evaluation 

contained in Table D.

Identifier Commenter Affiliation ADAMS Accession No.

(1) Malherek, J. P. Public Citizen ML050880209

(2) Boyd, J California Energy 

Commission

ML050900222

(3) Becker, R

Blanch, P

Epstein, E

Huang, A

Lampert, M

May, D

Alliance for Nuclear 

Responsibility, TMI-Alert, 

Environmental Health 

Coalition, Pilgrim Watch, 

California Earth Corps

ML050960394

(4) Van Suntum –

Rainwater, L

Riverkeeper ML050960340

(5) Swanson, J San Luis Obispo Mothers for 

Peace

ML050960341

(6) Adams, M

Schumann, K

Public ML050960343

(7) Spano, A Westchester County ML051510238

(8) Lochbaum, D Union of Concerned 

Scientists*

ML050540351

*The Union of Concerned Scientists comments are extracted from the publication, "U.S. Nuclear 

Plants in the 21st Century, The Risk of a Lifetime."

D.3. EVALUATION AND DISPOSITION OF COMMENTS

Table D contains a summary of the comments received from the stakeholders identified in the 

above table, along with the staff’s disposition of these comments. The column labeled 
NUREG-1832 D-2 September 2005

"Comment Number," is primarily intended to identify the source of the comment (i.e., the 

organization or individual that submitted the comment).

Comments are summarized according to general topics. If the comment is outside the scope of 

project to update the LRG documents, the comment is acknowledged, but a detailed evaluation 

is not performed. Comments with similar specific objectives are also combined to capture the 

common essential issues that had been raised, and the identifier of the commenter (provided in 

the above table) is placed in parenthesis. If more than one commenter made a similar comment 

on the topic, then there will be several identifiers for each of the commenters following the 

comment number.
September 2005

D-3 NUREG-1832

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-1 (1) Regarding institutional 

independence, Safety Review 

information is based on information 

provided by the applicant. The 

commenter stated that "unless the 

NRC has the capacity to conduct its 

own safety reviews and develop its 

own guidelines for considering

license applications, citizens cannot 

be assured that the NRC is serving 

the interest of the public and not that 

of industry."

The NRC adheres to the principles of good regulations as provided on the NRC Website 

at http:/www.nrc.gov/who-we-are/values.html. The following provides the NRC values 

regarding independence:

"Nothing but the highest possible standards of ethical performance and professionalisms 

should influence regulation. However, independence does not imply isolation. All 

available facts and opinions must be sought openly from licensees and other interested

members of the public. The many and possibly conflicting public interests involved must 

be considered. Final decisions must be based on objective, unbiased assessments of all 

information, and must be documented with reasons explicitly stated."

NEI and public comments were considered and used in the initial and subsequent 

development of the license renewal guidance documents, including this revision to the 

LRG documents. However, the NRC staff independently developed its own technical 

information and research for the license renewal guidance documents. As identified in 

the background to the GALL Report, the technical information was derived primarily from 

independent NRC documents and reports developed by the staff, government 

laboratories under contract to NRC, and other contractors to the NRC. Specifically, the 

GALL Report (NUREG-1801) was first published in 2001 and was based on a previous 

report, NUREG/CR-6490, "Nuclear Power Plant Generic Aging Lessons Learned 

(GALL)." NUREG/CR-6490 represents a systematic compilation of plant aging 

information.

The NUREG/CR-6490 report was based on information gathered from over 500 

documents: 

• Nuclear Plant Aging Research (NPAR) program reports sponsored by the NRC 

Office of Nuclear Regulatory Research, 

• Licensee Event Reports (LERs) submitted to the NRC, 

• NRC generic letters,

• NRC bulletins, 

• NRC information notices, and

• Nuclear Management and Resources Council (NUMARC, now NEI) industry 

reports addressing license renewal for major structures and components. 

The staff also considered information contained in the reports provided by the Union of 

Concerned Scientists (UCS). Many of these reports are available in ADAMS and the 
NUREG-1832

D-4 September 2005

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

NRC website at: http://www.nrc.gov/reactors/operating/licensing/renewal/guidance.html.

The GALL Report expands upon the information in NUREG/CR-6490 to provide an 

evaluation of the adequacy of aging management programs for license renewal.

P-G-2 

(1)(3)(5)(6)

Concern that NRC might conduct 

review of license renewal application

on a generic rather than plantspecific basis

A plant-specific evaluation is performed by the applicant, submitted to, and reviewed by 

the staff. The staff conducts plant-specific audits and reviews of the applicant’s license 

renewal application. This plant-specific process is described in 10 CFR Part 54 and on

the NRC website at http://www.nrc.gov/reactors/operating/licensing/renewal.html.

P-G-3 (2) The guidance documents do not 

focus sufficiently on the equally 

important human factors, for 

example, the "safety culture" of a 

plant

The NRC is proactive in this area and is not waiting until the period of extended 

operation before addressing these topics. The Commission has provided guidance to the 

staff in SECY-04-0111, "Recommended Staff Actions Regarding Agency Guidance in the 

Areas of Safety Conscious Work Environment and Safety Culture" and the SRM -SECY04-0111, "NRC Staff Requirements - SECY-04-0111 - Recommended NRC Staff Actions 

Regarding Agency Guidance in the Areas of Safety Conscious Work Environment and 

Safety Culture." These documents are available in ADAMS Accession numbers 

ML041750238 and ML042430661, respectively. More information in this area is available 

on the Human Factors web page at http://www.nrc.gov/reactors/operating/opsexperience/human-factors.html

P-G-4 (2) The NRC should review the 

Columbia Accident Investigation 

Board’s conclusions and 

recommendations 

The staff has reviewed and taken into consideration the Columbia Accident Investigation 

Board’s conclusions and recommendations that are relevant to the NRC. For example, 

the NRC’s Inspection Program Branch developed a web-based training course (provided 

in ADAMS at Accession Number ML040440475) based on the Columbia Space Shuttle

accident to: 

(1) illustrate the importance of maintaining a questioning attitude toward safety and the 

potential negative consequences that can occur when such a questioning attitude is lost 

or compromised; 

(2) provide examples of how issues concerning an organization’s safety culture can lead 

to technological failures; 

(3) provide insights into investigation techniques that can be used to assess safety 

significant issues or events; and 

(4) illustrate the importance of a robust corrective action program and highlight the 

corrective action program weaknesses that contributed to the shuttle accident.

P-G-5 (2) NRC should: (1) revise how it 

assesses plant performance and 

The staff acknowledges this comment. However, it is a recommendation related to 

current plant operations, which the NRC inspects as part of the ongoing Reactor 
September 2005

D-5 NUREG-1832

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

early indications of deteriorating 

safety at a plant, (2) establish a more 

specific methodology for deciding to 

shut down a plant, (3) establish 

management controls for 

systematically tracking actions that a 

plant has taken in response to 

incidents, and (4) encourage 

programs to air differing professional 

opinions and advice about plant 

safety and security.

Oversight Process (ROP). Accordingly, the comment does not relate to the license 

renewal guidance documents being revised, and is not appropriately addressed in this 

context. More Information on the reactor oversight process is available on the NRC 

Website at http://www.nrc.gov/reactors/operating/oversight.html#power

P-G-6(8) Specific operating experience should 

be considered when updating the 

GALL Report.

In general, the operating experience was considered in the update of the GALL Report. 

In particular, the AMR line-items were verified to be in the GALL Report for the specific 

operating experience identified in the UCS report relating to the Oconee, Quad Cities, 

Summer, and Indian Point facilities.

P-G-7(2) Safety and environmental issues 

should be reviewed, evaluated and 

an opportunity provided for state and 

local comment during the license 

renewal review process, if and when 

these licensees apply for license 

renewal.

The NRC license renewal process does provide the opportunity for formal public 

participation with respect to both safety and environmental matters. In addition, the staff 

affords the public opportunities to comment on the scope of the environmental review for 

individual applications and on the staffs draft supplemental environmental impact 

statements on those applications. More information regarding the license renewal 

process is available at the NRC Website at

http://www.nrc.gov/reactors/operating/licensing/renewal/overview.html
NUREG-1832

D-6 September 2005

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-8(3) 

(4)(6)(7)(8)

Criteria for license renewal process 

should be equivalent to regulations 

for a new reactor

The current licensing bases of each operating plant are maintained for the period of 

extended operation. Specifically, as provided in the Statements of Consideration for the 

License Renewal Rule:

"Reasonable assurance that the function of important systems, structures, and 

components will be maintained throughout the renewal period, combined with the 

rule’s stipulation that all aspects of a plant’s CLB (e.g., technical specifications) and 

the NRC’s regulatory process carry forward into the renewal period, are viewed as 

sufficient to conclude that the CLB (which represents an acceptable level of safety) 

will be maintained."

License renewal requirements, established as part of the 10 CFR Part 54 license 

renewal rulemaking, contain the requirements for the NRC to issue license 

amendments which allow the extension of a plant’s life by up to 20 years.
September 2005

D-7 NUREG-1832

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G9(2)(3)(5)(7)Security issues have not changed 

since existing nuclear plants were 

licensed – most over 20 years ago

The NRC promulgated regulations and guidance on plant security well before September 

11, 2001, and has moved quickly and aggressively to further enhance security in light of 

the increased threat since then. These enhancements will be implemented well before 

the license renewal period.

Nuclear facility structures are designed to withstand extreme events such as hurricanes, 

tornadoes, and earthquakes. Nevertheless, the events of September 11 have resulted in 

additional protections at nuclear power plants and enhanced coordination with Federal, 

State and local organizations responsible for protecting critical national infrastructure to 

ensure that these commercial facilities remain secure.

Following the September 2001 terrorist attacks, the NRC immediately advised nuclear 

facilities to go to the highest level of security in accordance with the system in place at 

the time. Since then, a series of Advisories, Orders, and Regulatory Issue Summaries 

have been issued to further strengthen security at NRC-licensed facilities including

power reactors, decommissioned reactors, independent spent fuel storage installations, 

research and test reactors, uranium conversion facilities, gaseous diffusion plants, fuel 

fabrication facilities, and certain sites at which radioactive materials are used and in the 

transportation of spent fuel and radioactive materials.

Details of the specific actions are sensitive, but for facilities such as power reactors, they 

generally include: 

ß increased patrols, 

ß augmented security forces and capabilities,

ß additional security posts,

ß installation of additional physical barriers,

ß vehicle checks at greater stand-off distances,

ß enhanced coordination with law enforcement and military authorities;

ß more restrictive site access controls for personnel; and

ß expanded, expedited, and more thorough employee background checks.

For power reactors and fuel fabrication facilities having significant quantities of nuclear 

material, facility owners were required in April 2003 to revise the physical security plans, 

guard training and qualification plans, and contingency plans. The NRC reviewed these 

plans and the owners implemented them by October 2004.?
NUREG-1832

D-8 September 2005

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-10(2) 

(3) (4)(5) 

(6)(7)

License Renewal will increase 

Radioactive Waste

The safety and environmental effects of long-term storage of spent fuel onsite have been 

evaluated by the NRC, and as set forth in the Waste Confidence Rule, the NRC 

generically determined that such storage could be accomplished without significant 

environmental impact. In the Waste Confidence Rule, the Commission determined that 

spent fuel can be stored onsite for at least 30 years beyond facility licensed operating 

life, which may include the term of a renewed license. At or before the end of that period, 

the fuel would be moved to a permanent repository. The Generic Environmental Impact 

Statement (GEIS) for License Renewal of Nuclear Plants (NUREG -1437) is based upon 

the assumption that storage of the spent fuel onsite is not permanent in accordance with 

the Waste Confidence Rule.

P-G-11 (3) 

(6)(7)(8)

Safety problems in the current 

license renewal term are not 

considered in the license renewal 

period

The NRC monitors safety performance in the current operating license term through the 

reactor oversight process (ROP). The NRC will not delay addressing current safety 

issues until the period of extended operation. The ROP will continue into the license 

renewal period to ensure appropriate corrective actions, root cause analyses, and 

actions to prevent recurrence are implemented, as required. Appropriate action for 

violations of NRC requirements, such as findings, fines, and/or shutdown by the NRC will 

continue in the current term as well as the license renewal period.

P-G-12 

(2)(3) (4) 

(6)(7)

Emergency Planning needs to be 

considered for license renewal

Emergency Preparedness (EP) is a current operating issue that is aggressively being 

addressed by the NRC during the current operating license term. The oversight of EP will 

also be carried out into the period of extended operation. In accordance with the 

response to Comment P-G-8, the NRC’s regulatory process is sufficient to conclude that 

the EP portion of the current licensing basis, among other things, will be maintained 

during the period of extended operation.

The NRC performs oversight of EP through performance indicators and through 

inspection. NRC inspectors dedicate thousands of hours to routine inspections, 

observations of drill and exercises, review of licensee corrective actions, as well as 

emergency plan changes. In addition, licensees are required to conduct a full-scale 

exercise involving Federal, State, and local agencies every two years. These exercises 

are evaluated by the NRC and FEMA. The results and, if necessary, enforcement of 

these emergency preparedness oversight activities are available for public review and 

can be found on the NRC Operating Reactor Oversight Web page.
September 2005

D-9 NUREG-1832

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-13 

(2)(3) (4) (6)

Extending the reactor operating 

license impacts the environment

Each license renewal applicant must include a supplement to the environmental report 

that contains an analysis of the plant’s impact on the environment if allowed to continue 

operation beyond the initial license. The NRC performs plant-specific reviews of 

environmental impacts of operating life extension in accordance with the National 

Environmental Policy Act (NEPA) and the requirements of 10 CFR Part 51 

"Environmental Protection Regulations for Domestic Licensing and Related Regulatory 

Functions." This review continues on a separate "track" from the safety reviews of the 

technical information. Environmental requirements for the renewal of power reactor 

operating licenses are contained in the NRC regulations in 10 CFR Part 51.

P-G-14 

(2)(3) (6) 

Workshops and public meetings on 

license renewal are not held in the 

vicinity of the plants to allow public 

participation and comment

Public Meetings have occurred in the vicinity of license renewal applicant’s power plants 

to allow convenient public participation in the license renewal process. The public also 

participates by written comments during the formal public comment period on the draft 

environmental impact statement. This license renewal process is described on the NRC 

license renewal Website at http://www.nrc.gov/reactors/operating/licensing/renewal.html.

P-G-15(4) NRC should evaluate Moving Parts 

for License renewal

As provided in the statements of consideration for the License Renewal Rule:

"In June 1993, the NRC issued Regulatory Guide 1.160 'Monitoring the Effectiveness of 

Maintenance at Nuclear Power Plants.' The regulatory guide provides an acceptable 

method for complying with the requirements of the maintenance rule and states that a 

licensee can use alternative methods if the licensee can demonstrate that these 

alternative methods satisfy the requirements of the rule. Because aging is a continuous 

process, the Commission has concluded that existing programs and regulatory 

requirements that continue to be applicable in the period of extended operation and 

provide adequate aging management for systems, structures, and components should 

be credited for license renewal. Accordingly, the amendment to the license renewal rule 

focuses the renewal review on plant systems, structures, and components for which 

current activities and requirements may not be sufficient to manage the effects of aging 

in the period of extended operation."

The Commission determined that, at this time, there was not an adequate basis to 

generically exclude passive, long-lived structures and components from an aging 

management review. Thus, the license renewal process focuses on passive long-lived 

structures and components.
NUREG-1832

D-10 September 2005

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G16(5) There is a severe shortage of trained 

workers available to replace the 

aging workforce

The nuclear industry and the NRC are aware of the problems associated with an aging 

workforce and are acting upon it to ensure staff resources are adequate through hiring 

and training processes. For example, as provided in SECY-01-0196, the Electric Power 

Research Institute (EPRI) is pursuing research on methods for enhancing knowledge 

management as a tool for capturing and accessing the knowledge of experts who are 

leaving the industry. However, since this comment is not directed to plant systems, 

structures, and components covered by 10 CFR Part 54 and the guidance in the GALL 

Report, it is not within the scope of the license renewal guidance update.

P-G-17(6) Instead of license Renewal, focus on 

Renewable Resources

Consideration of other generation technologies are typically discussed in the NRC staff’s

Environmental Impact Statement (EIS). For example, in chapter 8 of Ginna’s 

Supplemental EIS (SEIS) regarding the Ginna Nuclear Power Plant (NUREG-1437, 

supplement 14), the staff describes the environmental impact associated with alternative 

sources of electric power to replace the power generated by Ginna, assuming that the 

OL is not renewed. The Ginna SEIS states that, "Alternative technologies are not 

considered feasible at this time for replacement of the Ginna base-load power and it is 

very unlikely that the environmental impacts of any reasonable combination of generation 

and conservation options could be reduced to the level of impacts associated with 

renewal of the Ginna operating licenses." This EIS is provided on the NRC Website at 

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

collections/nuregs/staff/sr1437/supplement14/sr1437s14.pdf

P-G-18(7) Plant-specific Comments regarding 

individual plants

Specific comments regarding individual licensees license renewal applications have 

been or will be addressed when the applicant applied or applies for license renewal
September 2005

D-11 NUREG-1832

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-19(2) 

(7)

The NRC must broaden the issues it 

considers in its license extension 

decisions (security, emergency

planning, etc.)

The purpose of the public comment period was to comment on the update of the license 

renewal guidance documents. These documents are based on current regulations 

provided in 10 CFR Part 54. Some of the comments received in response to the January 

31, 2005, Federal Register notice solicitation (65FR53047) on license renewal 

misinterpreted the purpose of the comment period by interpreting it as an opportunity to 

comment on relicensing requirements for nuclear power reactors beyond the current

regulations found in 10 CFR Part 54. The public comments included a wide range of 

topics such as "Terrorism," and a suggestion to make requirements for relicensing 

comparable to those for licensing new reactors.

These issues are not directly related to the update of the license renewal guidance 

document and many would involve a change in NRC regulations. The process of 

developing or modifying NRC regulations is called rulemaking. Rulemaking is most often 

initiated by the staff, although any member of the public may also petition the NRC to 

develop, change, or rescind one of its regulations. More information is available on public 

involvement in rulemaking on the NRC website at: http://www.nrc.gov/what-weo/regulatory/rulemaking.html

Since these comments are not directly related to the update of the license renewal 

guidance documents, they do not warrant any further response.
NUREG-1832

D-12 September 2005

Table D: Disposition of Written Public Comments 

Comment 

Number Comment/Proposed Change NRC Disposition

P-G-20(8) Perform inspections of areas 

considered less vulnerable to aging 

degradation

The staff agreed with this comment. This is the purpose of the one-time inspection AMP.

As provided in the introduction to this AMP, the One-time Inspection program includes 

measures to verify the effectiveness of an AMP and confirm the absence of an aging 

effect. As a plant will have accumulated at least 30 years of use before inspections under 

this program begin, sufficient time will have elapsed for aging effects, if any, to be 

manifested.

There are situations in which additional confirmation is appropriate. These include 

(a) an aging effect is not expected to occur but the data is insufficient to rule it out with 

reasonable confidence; 

(b) an aging effect is expected to progress very slowly in the specified environment, but 

the local environment may be more adverse than that generally expected; or 

(c) the characteristics of the aging effect include a long incubation period.

For these cases, a holder of a renewed license will confirm that either the aging effect is 

indeed not occurring, or the aging effect is occurring very slowly so as not to affect the 

component or structure intended function during the period of extended operation.

A one-time inspection may be used to provide additional assurance that aging that has 

not yet manifested itself is not occurring, or that the evidence of aging shows that the 

aging is so insignificant that an aging management program is not warranted. A one time 

inspection may also trigger development of a program necessary to assure component 

intended functions through the period of extended operation.

The AMP XI.M32 and several AMR line-items have been enhanced to address this 

comment.

P-G-20(8) Perform the right inspection 

technique for the appropriate 

degradation mechanism

The staff agrees with this comment. AMP XI.M32 was enhanced with a table providing a 

table of mechanisms with acceptable inspection techniques to provide guidance to the 

applicants.

The AMP XI.M32 was enhanced to address this comment.
September 2005 E-1 NUREG-1832

APPENDIX E:

Aging Management Review Line-item Comparison

E.1. Purpose and Use of the Comparison Table

The Aging Management Reviews (AMRs) defined in Volume 2 of NUREG-1801, "Generic Aging 

Lessons Learned (GALL) Report," present acceptable methods of managing aging effects. Each 

AMR line-item from NUREG-1801 identifies the component, material, environment, and aging 

effect, along with the corresponding aging management program. A unique AMR line-item may 

be used multiple times.

This Appendix is intended to facilitate identification of the changes made to the AMR line-items 

in NUREG-1801 in response to comments from the public and the industry. In this Appendix, 

each unique AMR line-item from the January 2005 GALL Report is presented above the 

corresponding line-item from September 2005 GALL Report, where possible. If the January 

2005 line-item was not retained, or if a new item was added to the September 2005 GALL 

Report, this is noted in the table. Shading has also been added to the September 2005 lineitems to facilitate the comparison.

Each unique September 2005 AMR line-item in Table E has a unique coded identifier, such as 

C-01 or R-152. Tables 1A, 2A, 3A, 4A, 5A and 6A of Volume 1 of NUREG-1801 identify where 

each of these unique line-items are used in Volume 2 of NUREG 1801.

To facilitate the presentation of the unique AMR line-items, an ID column not shown in the GALL 

AMR tables has been added to Table E, and two other column headings were shortened due to 

table spacing considerations. The ID column was added to identify which GALL Report Chapter 

contains the AMR line-item. The two column heading changes are as follows:

AMR Line-item Heading Table E Heading

Structure and/or Component S/C

Environment Environ

Additionally, the unique AMR line-items presented in Table E were obtained from a Microsoft 

Excel spreadsheet that was used to develop the AMR tables in NUREG-1801 in Microsoft Word.

The special codes are included in the spreadsheet to represent carriage returns, which provide 

proper vertical alignment of the text within each row once the text is transferred from the 

spreadsheet into Word. The carriage returns are also used to designate paragraph returns. In 

Table E, these special characters were removed and not replaced with carriage returns in order 

to facilitate the presentation of the unique AMR line-item information for comparison.

Consequently, some cells in Table E do not include the vertical alignment that exists in the 

NUREG-1801 AMR line-items. For example, the following sample AMR "Further Evaluation"

column text illustrates this alignment difference:

NUREG-1801 AMR Table Table E

Yes, if corrosion is significant for inaccessible 

areas

No

No

Yes, if corrosion is significant for 

inaccessible areas No No
NUREG-1832 E-2 September 2005

This Page Intentionally Left Blank
September 2005

E-3 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-01 A1.1-a 

A2.2-a 

B3.2.1-

a 

Concrete 

Dome; 

wall; 

basemat; 

ring 

girder; 

buttresse

s

Concrete Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S2, "ASME Section XI, Subsection 

IWL" Accessible areas: Inspections performed in 

accordance with IWL will indicate the presence of 

loss of material (spalling, scaling) and cracking 

due to freeze-thaw. Inaccessible Areas: 

Evaluation is needed for plants that are located in 

moderate to severe weathering conditions 

(weathering index >100 day-inch/yr) (NUREG1557). Documented evidence confirms that where 

the existing concrete had air content of 3% to 6%, 

subsequent inspection did not exhibit degradation 

related to freeze-thaw. Such inspections should be 

considered a part of the evaluation. The

weathering index for the continental US is shown 

in ASTM C33-90, Fig. 1.

No, if stated 

conditions 

are satisfied 

for 

inaccessible 

areas

II C-01 A1.1-a Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas: Inspections performed in 

accordance with IWL will indicate the presence of 

loss of material (spalling, scaling) and surface 

cracking due to freeze-thaw. Inaccessible Areas: 

Evaluation is needed for plants that are located in 

moderate to severe weathering conditions 

(weathering index >100 day-inch/yr) (NUREG1557). Documented evidence confirms that where 

the existing concrete had air content of 3% to 6%, 

subsequent inspection did not exhibit degradation 

related to freeze-thaw. Such inspections should be 

considered a part of the evaluation. The

weathering index for the continental US is shown 

in ASTM C33-90, Fig. 1.

Yes, for 

inaccessible 

areas of 

plants 

located in 

moderate to 

severe 

weathering 

conditions
NUREG-1832

E-4 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-02 A1.1-b 

A2.2-b 

B2.2.1-

a 

B3.1.2-

a 

B3.2.1-

b

Concrete 

Dome; 

wall; 

basemat; 

ring 

girder; 

buttresse

s

Concrete Water –

flowing

Increase in 

porosity, 

permeability/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL" Accessible areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide. Inaccessible Areas: 

An aging management program is not necessary, 

even if reinforced concrete is exposed to flowing 

water, if there is documented evidence that 

confirms the in-place concrete was constructed in 

accordance with the recommendations in ACI 

201.2R-77.

No, if 

concrete was 

constructed 

as stated for 

inaccessible 

areas

II C-02 A1.1-b Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Water –

flowing

Increase in 

porosity, 

permeability/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL" Accessible areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide. Inaccessible Areas: 

An aging management program is not necessary, 

even if reinforced concrete is exposed to flowing 

water, if there is documented evidence that 

confirms the in-place concrete was constructed in 

accordance with the recommendations in ACI 

201.2R.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
September 2005

E-5 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-03 A1.1-c 

A2.2-c 

B2.2.1-

b 

B3.1.2-

b 

B3.2.1-c

Concrete 

Dome; 

wall; 

basemat; 

ring 

girder; 

buttresse

s

Concrete Aggressi

ve 

environm

ent

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S2, "ASME Section XI, Subsection 

IWL" Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, cracking, or 

loss of material (spalling, scaling) due to 

aggressive chemical attack. Inaccessible Areas: 

Examination of representative samples of belowgrade concrete, when excavated for any reason, is 

to be performed, if the below-grade environment is 

aggressive (pH < 5.5, chlorides > 500ppm, or 

sulfates > 1,500 ppm). Periodic monitoring of 

below-grade water chemistry (including 

consideration of potential seasonal variations) is 

an acceptable approach to demonstrate that the 

below-grade environment is aggressive or nonaggressive.

Yes, if 

environment 

is aggressive

II C-03 A1.1-c Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Ground 

water/soil 

or air –

indoor 

uncontroll

ed or air -

outdoor

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S2, "ASME Section XI, Subsection 

IWL" Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, surface 

cracking, or loss of material (spalling, scaling) due 

to aggressive chemical attack. Inaccessible Areas: 

For plants with non-aggressive ground water/soil; 

i.e., pH > 5.5, chlorides < 500 ppm, or sulfates 

<1500 ppm, as a minimum, consider (1) 

Examination of the exposed portions of the below 

grade concrete, when excavated for any reason, 

and(2) Periodic monitoring of below-grade water 

chemistry, including consideration of potential 

seasonal variations. For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

Yes, plantspecific if 

environment 

is aggressive
NUREG-1832

E-6 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

during the period of extended operation.

II C-04 A1.1-d 

A2.2-d 

B2.2.1-c 

B3.1.2-c 

B3.2.1-

d

Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Any Expansion 

and cracking/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

cracking due to reaction with aggregates. 

Inaccessible Areas: Evaluation is needed if testing 

and petrographic examinations of aggregates 

performed in accordance with ASTM C295-54, 

ASTM C227-50, or ACI 201.2R-77 (NUREG-1557) 

demonstrate that the aggregates are reactive.

No, if stated 

conditions 

are satisfied 

for 

inaccessible 

areas
September 2005

E-7 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-04 A1.1-d Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking due to reaction with aggregates. 

Inaccessible Areas: As described in NUREG1557, investigations, tests, and petrographic 

examinations of aggregates performed in 

accordance with ASTM C295-54 or ASTM C227-

50 can demonstrate that those aggregates do not 

react within reinforced concrete. For potentially 

reactive aggregates, aggregate-reinforced 

concrete reaction is not significant if the concrete 

was constructed in accordance with ACI 

201.2R.Therefore, if these conditions are satisfied, 

aging management is not necessary.

Yes, if

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas

II C-05 A1.1-e 

A2.2-e 

B2.2.1-

d 

B3.1.2-

d 

B3.2.1-

e

Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s; 

reinforcin

g steel

Concrete; 

steel

Air –

indoor 

uncontroll

ed or air -

outdoor

Cracking,

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, cracking, or 

loss of material (spalling, scaling) due to 

aggressive chemical attack. Inaccessible Areas: 

Examination of representative samples of belowgrade concrete, when excavated for any reason, is 

to be performed, if the below-grade environment is 

aggressive (pH < 5.5, chlorides > 500ppm, or 

sulfates > 1,500 ppm). Periodic monitoring of 

below-grade water chemistry (including 

consideration of potential seasonal variations) is 

an acceptable approach to demonstrate that the 

below-grade environment is aggressive or nonaggressive.

Yes, if 

environment 

is aggressive
NUREG-1832

E-8 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-05 A1.1-e Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s; 

reinforcin

g steel

Concrete; 

steel

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking, 

loss of bond, 

and loss of

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking, loss of bond, and loss of 

material (spalling, scaling) due to corrosion of 

embedded steel. Inaccessible Areas: For plants 

with non-aggressive ground water/soil; i.e., pH > 

5.5, chlorides < 500 ppm, or sulfates <1500 ppm, 

as a minimum, consider (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations. For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-06 A1.1-f 

A2.2-f 

B2.2.1-

e 

B3.1.2-

e 

B3.2.1-f

Concrete 

elements; 

All

Concrete Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring Program” 

The initial licensing basis for some plants included 

a program to monitor settlement. If no settlement 

was evident during the first decade or so, the NRC 

may have given the licensee approval to 

discontinue the program. However, if a dewatering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
September 2005

E-9 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-06 B2.2.1-

e 

B3.2.1-f 

B1.2. 

Concrete 

elements; 

All

Concrete Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring Program” If

a de-watering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the

period of extended operation. 

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon

II C-07 A1.1-g 

A2.2-g 

B2.2.1-f 

B3.1.2-f 

B3.2.1-

g

Concrete: 

Foundati

on; 

subfound

ation

Concrete; 

porous 

concrete

Water –

flowing

Reduction in 

foundation 

strength, 

cracking, 

differential 

settlement/ 

erosion of 

porous 

concrete 

subfoundatio

n

Chapter XI.S6, "Structures Monitoring Program” 

Erosion of cement from porous concrete 

subfoundations beneath containment basemats is 

described in IN 97-11. IN 98-26 proposes 

Maintenance Rule Structures Monitoring for 

managing this aging effect, if applicable. If a dewatering system is relied upon for control of 

erosion of cement from porous concrete 

subfoundations, then the licensee is to ensure 

proper functioning of the de-watering system 

through the period of extended operation.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
NUREG-1832

E-10 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-07 A1.1-g 

A2.2-g 

B2.2.1-f 

B3.1.2-f 

B3.2.1-

g B1.2.

Concrete: 

Foundati

on;

subfound

ation

Concrete; 

porous 

concrete

Water –

flowing

Reduction in 

foundation 

strength, 

cracking, 

differential 

settlement/ 

erosion of 

porous 

concrete 

subfoundatio

n

Chapter XI.S6, "Structures Monitoring Program” 

Erosion of cement from porous concrete 

subfoundations beneath containment basemats is 

described in IN 97-11. IN 98-26 proposes 

Maintenance Rule Structures Monitoring for 

managing this aging effect, if applicable. If a dewatering system is relied upon for control of 

erosion of cement from porous concrete 

subfoundations, then the licensee is to ensure 

proper functioning of the de-watering system 

through the period of extended operation.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon

II C-08 A1.1-h 

A2.2-h 

B2.2.1-

g 

B3.1.2-

g 

B3.2.1-

h

Concrete 

Dome; 

wall; 

concrete 

fill-in 

annulus, 

basemat; 

ring 

girder; 

buttresse

s

Concrete Air –

indoor 

uncontroll

ed or air -

outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management program The

implementation of 10 CFR 50.55a and IWL would 

not be able to identify the reduction of strength 

and modulus due to elevated temperature. Thus, 

for any portions of concrete containment that 

exceed specified temperature limits, further 

evaluations are warranted. Subsection CC-3400 of 

ASME Section III, Division 2, specifies the 

concrete temperature limits for normal operation 

or any other long-term period. The temperatures 

shall not exceed 150°F except for local areas, 

such as around penetrations, which are not 

allowed to exceed 200°F. If significant equipment 

loads are supported by concrete at temperatures 

exceeding 150°F, an evaluation of the ability to 

withstand the postulated design loads is to be 

made. Higher temperatures than given above may 

be allowed in the concrete if tests and/or 

calculations are provided to evaluate the reduction 

in strength and this reduction is applied to the 

design allowables.

Yes, if 

applicable
September 2005

E-11 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-08 A1.1-h Concrete: 

Dome; 

wall; 

basemat; 

ring 

girder; 

buttresse

s

Concrete Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management program The

implementation of 10 CFR 50.55a and ASME 

Section XI, Subsection IWL would not be able to 

identify the reduction of strength and modulus of 

elasticity due to elevated temperature. Thus, for 

any portions of concrete containment that exceed 

specified temperature limits, further evaluations 

are warranted. Subsection CC-3400 of ASME 

Section III, Division 2, specifies the concrete 

temperature limits for normal operation or any 

other long-term period. The temperatures shall not 

exceed 150°F except for local areas, such as 

around penetrations, which are not allowed to 

exceed 200°F. If significant equipment loads are 

supported by concrete at temperatures exceeding 

150°F, an evaluation of the ability to withstand the 

postulated design loads is to be made. Higher

temperatures than given above may be allowed in 

the concrete if tests and/or calculations are 

provided to evaluate the reduction in strength and 

this reduction is applied to the design allowables.

Yes, if 

temperature 

limits are 

exceeded
NUREG-1832

E-12 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-09 A1.2-a 

A2.1-a 

B3.2.2-

a

Steel 

elements: 

Liner; 

liner 

anchors; 

integral 

attachme

nts

Steel Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE” For inaccessible areas (embedded 

containment steel shell or liner), loss of material 

due to corrosion is not significant if the following 

conditions are satisfied: Concrete meeting the 

requirements of ACI 318 or 349 and the guidance 

of 201.2R was used for the containment concrete 

in contact with the embedded containment shell or 

liner. The concrete is monitored to ensure that it is 

free of penetrating cracks that provide a path for 

water seepage to the surface of the containment 

shell or liner. The moisture barrier, at the junction 

where the shell or liner becomes embedded, is 

subject to aging management activities in 

accordance with IWE requirements. Borated water 

spills and water ponding on the containment 

concrete floor are not common and when detected 

are cleaned up in a timely manner. If any of the 

above conditions cannot be satisfied, then a plantspecific aging management program for corrosion 

is necessary. Chapter XI.S4, "10 CFR Part 50, 

Appendix J" and If a coatings program is credited 

for managing loss of material due to corrosion 

during the current licensing term (e.g., relief 

request from IWE), then it is to be continued 

during the period of extended operation. See 

Chapter XI.S8, "Protective Coating Monitoring and 

Maintenance Program."

Yes, if 

corrosion is 

significant for 

inaccessible

areas

No

No
September 2005

E-13 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-09 A1.2-a 

A2.1-a 

B3.2.2-

a

Steel 

elements:

Liner;

Liner

anchors; 

Integral

attachme

nts

Steel Air –

indoor 

uncontroll

ed

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, “ASME Section XI, Subsection 

IWE” For inaccessible areas (embedded 

containment steel shell or liner), loss of material 

due to corrosion is not significant if the following 

conditions are satisfied: 1. Concrete meeting the 

requirements of ACI 318 or 349 and the guidance 

of 201.2R was used for the containment concrete 

in contact with the embedded containment shell or 

liner. 2. The concrete is monitored to ensure that it 

is free of penetrating cracks that provide a path for 

water seepage to the surface of the containment 

shell or liner. 3. The moisture barrier, at the 

junction where the shell or liner becomes 

embedded, is subject to aging management 

activities in accordance with ASME Section XI, 

Subsection IWE requirements. 4. Borated water 

spills and water ponding on the containment 

concrete floor are not common and when detected 

are cleaned up in a timely manner. If any of the 

above conditions cannot be satisfied, then a plantspecific aging management program for corrosion 

is necessary. Chapter XI.S4, “10 CFR Part 50, 

Appendix J”

Yes, if 

corrosion is 

significant for 

inaccessible 

areas No

II C-10 A1.3-a 

B2.2.3-

a

Prestress

ing 

system: 

Tendons; 

anchorag

e 

compone

nts

Steel Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

material/ 

corrosion

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"

No
NUREG-1832

E-14 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-10 A1.3-a 

B2.2.3-

a

Prestress

ing 

system: 

Tendons; 

anchorag

e 

compone

nts

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

material/ 

corrosion

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"

No

II C-11 A1.3-b 

B2.2.3-

b

Prestress

ing 

system: 

Tendons; 

anchorag

e 

compone

nts

Steel Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

prestress/ 

relaxation; 

shrinkage; 

creep; 

elevated 

temperature

Loss of tendon prestress is a time-limited aging 

analysis (TLAA) to be evaluated for the period of 

extended operation. See the Standard Review 

Plan, Section 4.5, "Concrete Containment Tendon 

Prestress" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1)(i) and (ii). See 

Chapter X.S1 of this report for meeting the 

requirements of 10 CFR 54.21(c)(1)(iii).For 

periodic monitoring of prestress, see Chapter 

XI.S2.

Yes,TLAA

II C-11 A1.3-b 

B2.2.3-

b

Prestress

ing 

system: 

Tendons

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

prestress/ 

relaxation; 

shrinkage; 

creep; 

elevated 

temperature

Loss of tendon prestress is a time-limited aging 

analysis (TLAA) to be evaluated for the period of 

extended operation. See the Standard Review 

Plan, Section 4.5, "Concrete Containment Tendon 

Prestress" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1)(i) and (ii). See 

Chapter X.S1 of this report for meeting the 

requirements of 10 CFR 54.21(c)(1)(iii).For 

periodic monitoring of prestress, see Chapter 

XI.S2.

Yes,TLAA
September 2005

E-15 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-12 A3.1-a 

B4.1-a

Penetrati

on 

sleeves

Steel; 

Dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE,"(Note: IWE examination category E-F, 

surface examination of dissimilar metal welds, is 

recommended)Chapter XI.S4, "10 CFR Part 50, 

Appendix J," and If a coatings program is credited 

for managing loss of material due to corrosion 

during the current licensing term (e.g., relief 

request from IWE), then it is to be continued 

during the period of extended operation. See 

Chapter XI.S8, "Protective Coating Monitoring and 

Maintenance Program"

NoNoNo

II C-12 A3.1-a 

B4.1-a

Penetrati

on 

sleeves

Steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE,"(Note: IWE examination category E-F, 

surface examination of dissimilar metal welds, is 

recommended)Chapter XI.S4, "10 CFR Part 50, 

Appendix J"

NoNo 

II C-13 A3.1-b 

B2.1.1-c 

B4.1-b 

Penetrati

on 

sleeves; 

penetrati

on

bellows

Steel; 

Stainless 

steel; 

Dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

II C-13 A3.1-b 

B4.1-b 

Penetrati

on 

sleeves; 

Penetrati

on

bellows

Steel; 

stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
NUREG-1832

E-16 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-14 A3.1-c 

B2.1.1-

b B4.1-c 

Penetrati

on 

sleeves; 

penetrati

on

bellows

Steel; 

Stainless 

steel; 

Dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J" Evaluation of 10 CFR 50.55a/IWE is 

augmented as follows:(4) Detection of Aging 

Effects: VT-3 visual inspection may not detect fine 

cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-14 A3.1-c 

B4.1-c 

Penetrati

on 

sleeves; 

Penetrati

on

bellows

Steel; 

stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ASME 

Section XI, Subsection IWE is to be supplemented 

to consider the following:(4) Detection of Aging 

Effects: VT-3 visual inspection may not detect fine 

cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-15 A3.1-d 

B4.1-d

Penetrati

on 

sleeves; 

penetrati

on

bellows

Stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, "ASME Section XI, Subsection 

IWE" and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/IWE is 

augmented as follows:(4) Detection of Aging 

Effects: Transgranular Stress corrosion cracking 

(TGSCC) is a concern for dissimilar metal welds. 

In the case of bellows assemblies, SCC may 

cause aging effects particularly if the material is 

not shielded from a corrosive environment. 

Subsection IWE covers inspection of these items 

under examination categories E-B, E-F, and E-P 

(10 CFR Part 50, Appendix J pressure tests). 

10 CFR 50.55a identifies examination categories 

E-B and E-F as optional during the current term of 

operation. For the extended period of operation, 

Examination Categories E-B & E-F, and additional 

appropriate examinations to detect SCC in bellows 

assemblies and dissimilar metal welds are 

warranted to address this issue.(10) Operating 

Experience: IN 92-20 describes an instance of 

containment bellows cracking, resulting in loss of 

leak tightness.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-17 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-15 A3.1-d 

B4.1-d

Penetrati

on 

sleeves; 

Penetrati

on

bellows

Stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air

– outdoor

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, “ASME Section XI, Subsection 

IWE” and Chapter XI.S4, “10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ASME 

Section XI, Subsection IWE is augmented as 

follows:(4) Detection of Aging Effects: 

Transgranular Stress corrosion cracking (TGSCC) 

is a concern for dissimilar metal welds. In the case 

of bellows assemblies, SCC may cause aging 

effects particularly if the material is not shielded 

from a corrosive environment. ASME Section XI, 

Subsection IWE covers inspection of these items 

under examination categories E-B, E-F, and E-P 

(10 CFR Part 50, Appendix J pressure tests). 

10 CFR 50.55a identifies examination categories 

E-B and E-F as optional during the current term of 

operation. For the extended period of operation, 

Examination Categories E-B & E-F, and additional 

appropriate examinations to detect SCC in bellows 

assemblies and dissimilar metal welds are 

warranted to address this issue.(10) Operating 

Experience: IN 92-20 describes an instance of 

containment bellows cracking, resulting in loss of 

leak tightness.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-16 A3.2-a 

B4.2-a

Personne

l airlock; 

equipme

nt hatch, 

CRD 

hatch

Steel Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

material/

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE,"Chapter XI.S4, "10 CFR Part 50, 

Appendix J," andIf a coatings program is credited 

for managing loss of material due to corrosion 

during the current licensing term (e.g., relief 

request from IWE), then it is to be continued 

during the period of extended operation. See 

Chapter XI.S8, "Protective Coating Monitoring and 

Maintenance Program."

NoNoNo
NUREG-1832

E-18 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-16 A3.2-a 

B4.2-a

Personne

l airlock, 

equipme

nt hatch, 

CRD 

hatch

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE,"Chapter XI.S4, "10 CFR Part 50, 

Appendix J"

NoNo

II C-17 A3.2-b 

B4.2-b

Personne

l airlock; 

equipme

nt hatch: 

CRD 

hatchLoc

ks, 

hinges, 

and 

closure 

mechanis

ms

Steel Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of leak 

tightness/ 

mechanical 

wear of locks, 

hinges and 

closure 

mechanisms

Chapter XI.S4, "10 CFR Part 50, Appendix J"

andPlant Technical Specifications

No

II C-17 A3.2-b 

B4.2-b

Personne

l airlock, 

equipme

nt hatch, 

CRD 

hatch:Loc

ks, 

hinges, 

and 

closure 

mechanis

ms

Steel Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of leak 

tightness/ 

mechanical 

wear of locks, 

hinges and 

closure 

mechanisms

Chapter XI.S4, "10 CFR Part 50, Appendix J"

andPlant Technical Specifications

No
September 2005

E-19 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-18 A3.3-a 

B4.3-a

Seals, 

gaskets, 

and 

moisture 

barriers 

(caulking, 

flashing, 

and other 

sealants)

Elastome

rs, rubber 

and other 

similar 

materials

Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of 

sealing; 

Leakage 

through 

containment/ 

deterioration 

of seals, 

gaskets, and 

moisture 

barriers 

(caulking, 

flashing, and 

other 

sealants)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE"Leak tightness will be monitored by 10 CFR 

Part 50, Appendix J Leak Rate Tests for pressure 

boundary, seals and gaskets (including O-rings).

No

II C-18 A3.3-a 

B4.3-a

Seals, 

gaskets, 

and 

moisture 

barriers 

(caulking, 

flashing, 

and other 

sealants)

Elastome

rs, rubber 

and other 

similar 

materials

Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

sealing; 

Leakage 

through 

containment/ 

deterioration 

of seals, 

gaskets, and 

moisture 

barriers 

(caulking, 

flashing, and 

other 

sealants)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE"Leak tightness will be monitored by 10 CFR 

Part 50, Appendix J Leak Rate Tests for pressure 

boundary, seals and gaskets (including O-rings).

No
NUREG-1832

E-20 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-19 B1.1.1-

a 

B2.1.1-

a 

B2.2.2-

a 

B3.1.1-

a

Steel 

elements:

Drywell; 

torus; 

drywellhe

ad; 

embedde

d 

shelland 

sand 

pocket 

regions;d

rywell 

support 

skirt;torus 

ring 

girder;do

wncomer

s; 

ECCSsuc

tion 

headerN

OTE: 

Inspectio

n of 

containm

ent 

supports 

is 

addresse

d by 

ASME 

Section X

I, 

Subsecti

Steel Air –

indoor 

uncontroll

ed

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE” For inaccessible areas (embedded 

containment steel shell or liner), loss of material 

due to corrosion is not significant if the following 

conditions are satisfied:Concrete meeting the 

specifications of ACI 318 or 349 and the guidance 

of 201.2R was used for the containment concrete 

in contact with the embedded containment shell or 

liner. The concrete is monitored to ensure that it is 

free of penetrating cracks that provide a path for 

water seepage to the surface of the containment 

shell or liner. The moisture barrier, at the junction 

where the shell or liner becomes embedded, is 

subject to aging management activities in 

accordance with IWE requirements. Borated water 

spills and water ponding on the containment 

concrete floor are not common and when detected 

are cleaned up in a timely manner.If any of the 

above conditions cannot be satisfied, then a plantspecific aging management program for corrosion 

is necessary.Chapter XI.S4, "10 CFR Part 50, 

Appendix J" andIf a coatings program is credited 

for managing loss of material due to corrosion 

during the current licensing term (e.g., relief 

request from IWE), then it is to be continued 

during the period of extended operation. See 

Chapter XI.S8, "Protective Coating Monitoring and 

Maintenance Program."

Yes, if 

corrosion is 

significant for 

inaccessible 

areas NoNo
September 2005

E-21 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

on IWF 

(see 

III.B1.3) 
NUREG-1832

E-22 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-19 B1.1.1-

a 

B3.1.1-

a

Steel 

elements:

Drywell; 

torus; 

drywellhe

ad; 

embedde

d 

shelland 

sand 

pocket 

regions;d

rywell 

support 

skirt;torus 

ring 

girder;do

wncomer

s; 

ECCSsuc

tion 

headerN

OTE: 

Inspectio

n of 

containm

ent 

supports 

is 

addresse

d by 

ASME 

Section X

I, 

Subsecti

Steel Air –

indoor 

uncontroll

ed or 

treated 

water (as 

applicabl

e)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, “ASME Section XI, Subsection 

IWE” For inaccessible areas (embedded 

containment steel shell or liner), loss of material 

due to corrosion is not significant if the following 

conditions are satisfied:Concrete meeting the 

specifications of ACI 318 or 349 and the guidance 

of 201.2R was used for the containment concrete 

in contact with the embedded containment shell or 

liner. The concrete is monitored to ensure that it is 

free of penetrating cracks that provide a path for 

water seepage to the surface of the containment 

shell or liner. The moisture barrier, at the junction 

where the shell or liner becomes embedded, is 

subject to aging management activities in 

accordance with ASME Section XI, Subsection 

IWE requirements. Water ponding on the 

containment concrete floor are not common and 

when detected are cleaned up in a timely 

manner.If any of the above conditions cannot be 

satisfied, then a plant-specific aging management 

program for corrosion is necessary.Chapter XI.S4, 

“10 CFR Part 50, Appendix J” 

Yes, if 

corrosion is 

significant for 

inaccessible 

areas No
September 2005

E-23 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

on IWF 

(see 

III.B1.3) 

II C-20 B1.1.1-

b 

B2.2.2-c

Steel 

elements:

Torus; 

vent line; 

vent 

header; 

vent line 

bellows; 

downcom

ers 

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/IWE is 

augmented as follows:(4) Detection of Aging 

Effects: VT-3 visual inspection may not detect fine 

cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-24 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-20 B1.1.1-

b 

Steel 

elements:

Torus;Ve

nt 

line;Vent 

header;V

ent line 

bellows;D

owncome

rs 

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ ASME 

Section XI, Subsection IWE is augmented as 

follows:(4) Detection of Aging Effects: VT-3 visual 

inspection may not detect fine cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-21 B1.1.1-c 

B2.2.2-

d

Steel 

elements:

Torus; 

vent line; 

vent 

header; 

vent line 

bellows; 

downcom

ers

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

II C-21 B1.1.1-c Steel 

elements:

Torus;Ve

nt 

line;Vent 

header;V

ent line 

bellows;D

owncome

rs 

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-25 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-22 B1.1.1-

d 

B2.2.2-

b

Steel 

elements:

Vent line 

bellows

Stainless 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/IWE is 

augmented as follows:(4) Detection of Aging 

Effects: Stress corrosion cracking (SCC) is a 

concern for dissimilar metal welds. In the case of 

bellows assemblies, SCC may cause aging effects 

particularly if the material is not shielded from a 

corrosive environment. Subsection IWE covers 

inspection of these items under examination 

categories E-B, E-F, and E-P (10 CFR Part 50, 

Appendix J pressure tests). 10 CFR 50.55a 

identifies examination categories E-B and E-F as 

optional during the current term of operation. For 

the extended period of operation, Examination 

Categories E-B and E-F, and additional 

appropriate examinations to detect SCC in bellows 

assemblies and dissimilar metal welds are 

warranted to address this issue.(10) Operating 

Experience: IN 92-20 describes an instance of 

containment bellows cracking, resulting in loss of 

leak tightness.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-26 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-22 B1.1.1-

d

Steel 

elements:

Vent line 

bellows

Stainless 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ASME 

Section XI, Subsection IWE is augmented as 

follows:(4) Detection of Aging Effects: Stress 

corrosion cracking (SCC) is a concern for 

dissimilar metal welds. In the case of bellows 

assemblies, SCC may cause aging effects 

particularly if the material is not shielded from a 

corrosive environment. ASME Code 1995 edition, 

with addenda through 1996, ASME Section XI, 

Subsection IWE covers inspection of these items 

under Examination Categories E-B, E-F, and E-P 

(10 CFR Part 50, Appendix J pressure tests). 

10 CFR 50.55a identifies examination categories 

E-B and E-F as optional during the current term of 

operation. For the extended period of operation, 

Examination Categories E-B and E-F, and 

additional appropriate examinations to detect SCC 

in bellows assemblies and dissimilar metal welds 

are warranted to address this issue.(10) Operating 

Experience: IN 92-20 describes an instance of 

containment bellows cracking, resulting in loss of 

leak tightness.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-23 B1.1.1-

e 

B2.2.2-

e 

B2.1.1-

d

Steel 

elements:

Drywell 

head; 

downcom

ers

Steel; 

Graphite 

plate

Air –

indoor

uncontroll

ed

Fretting or 

lockup/ 

mechanical 

wear

Chapter XI.S1, "ASME Section XI, Subsection 

IWE"

No

II C-23 B1.1.1-

e 

B2.2.2-

e 

B2.1.1-

Steel 

elements:

Drywell 

head;Do

wncomer

Steel Air –

indoor 

uncontroll

ed

Fretting or 

lockup/ 

mechanical 

wear

Chapter XI.S1, "ASME Section XI, Subsection 

IWE"

No
September 2005

E-27 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

d B1.2. s

II C-24 B3.1.1-

b 

B3.2.2-

b

Steel 

elements:

Suppress

ion 

chamber 

shell 

(interior 

surface)

Stainless 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, "ASME Section XI, Subsection 

IWE" and Chapter XI.S4, "10 CFR Part 50, 

Appendix J"

No

II C-24 B3.1.1-

b 

B3.2.2-

b

Steel 

elements:

Suppress

ion 

chamber 

shell 

(interior 

surface)

Stainless 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.S1, "ASME Section XI, Subsection 

IWE" and Chapter XI.S4, "10 CFR Part 50, 

Appendix J"

No

II C-25 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-28 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-25 A2.2-c 

B.3.1.2-

b

Concrete:

Basemat

Concrete Ground 

water/soil

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, surface 

cracking, or loss of mat erial (spalling, scaling) due 

to aggressive chemical attack.Inaccessible 

Areas:For plants with non-aggressive ground 

water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or 

sulfates <1500 ppm, as a minimum, consider (1) 

Examination of the exposed portions of the below 

grade concrete, when excavated for any reason, 

and(2) Periodic monitoring of below-grade water 

chemistry, including consideration of potential 

seasonal variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-26 Did not exist in Shuffle Master 1-28.
September 2005

E-29 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-26 B2.2.1-

b

B1.2.

Concrete:

Containm

ent; wall; 

basemat

Concrete Ground 

water/soil

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, surface 

cracking, or loss of material (spalling, scaling) due 

to aggressive chemical attack.Inaccessible 

Areas:For plants with non-aggressive ground 

water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or 

sulfates <1500 ppm, as a minimum, consider (1) 

Examination of the exposed portions of the below 

grade concrete, when excavated for any reason, 

and(2) Periodic monitoring of below-grade water 

chemistry, including consideration of potential 

seasonal variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-27 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-30 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-27 B3.2.1-c Concrete: 

Dome; 

wall; 

basemat

Concrete Ground 

water/soil

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, surface 

cracking, or loss of material (spalling, scaling) due 

to aggressive chemical attack.Inaccessible 

Areas:For plants with non-aggressive ground 

water/soil; i.e., pH > 5.5, chlorides < 500 ppm, or 

sulfates <1500 ppm, as a minimum, consider (1) 

Examination of the exposed portions of the below 

grade concrete, when excavated for any reason, 

and(2) Periodic monitoring of below-grade water 

chemistry, including consideration of potential 

seasonal variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-28 Did not exist in Shuffle Master 1-28.
September 2005

E-31 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-28 A2.2-a Concrete:

Basemat

Concrete Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

loss of material (spalling, scaling) and surface 

cracking due to freeze-thaw.Inaccessible 

Areas:Evaluation is needed for plants that are 

located in moderate to severe weathering 

conditions (weathering index >100 day-inch/yr) 

(NUREG-1557). Documented evidence confirms 

that where the existing concrete had air content of 

3% to 6%, subsequent inspection did not exhibit 

degradation related to freeze-thaw. Such 

inspections should be considered a part of the 

evaluation.The weathering index for the 

continental US is shown in ASTM C33-90, Fig. 1.

Yes, for 

inaccessible 

areas of 

plants 

located in 

moderate to 

severe 

weathering 

conditions

II C-29 Did not exist in Shuffle Master 1-28.

II C-29 B3.2.1-

a 

Concrete: 

Dome; 

wall; 

basemat

Concrete Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

loss of material (spalling, scaling) and surface 

cracking due to freeze-thaw.Inaccessible 

Areas:Evaluation is needed for plants that are 

located in moderate to severe weathering 

conditions (weathering index >100 day-inch/yr) 

(NUREG-1557). Documented evidence confirms 

that where the existing concrete had air content of 

3% to 6%, subsequent inspection did not exhibit 

degradation related to freeze-thaw. Such 

inspections should be considered a part of the 

evaluation.The weathering index for the 

continental US is shown in ASTM C33-90, Fig. 1.

Yes, for 

inaccessible 

areas of 

plants 

located in 

moderate to 

severe 

weathering 

conditions

II C-30 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-32 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-30 A2.2-b 

B3.1.2-

a

Concrete:

Basemat

Concrete Water –

flowing

Increase in 

porosity, 

permeability/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide.Inaccessible Areas: 

An aging management program is not necessary, 

even if reinforced concrete is exposed to flowing 

water, if there is documented evidence that 

confirms the in-place concrete was constructed in 

accordance with the recommendations in ACI 

201.2R.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas

II C-31 Did not exist in Shuffle Master 1-28.

II C-31 B2.2.1-

a B1.2. 

Concrete:

Containm

ent; wall; 

basemat

Concrete Water –

flowing

Increase in 

porosity, 

permeability/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide.Inaccessible 

Areas:An aging management program is not 

necessary, even if reinforced concrete is exposed 

to flowing water, if there is documented evidence 

that confirms the in-place concrete was 

constructed in accordance with the 

recommendations in ACI 201.2R.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas

II C-32 Did not exist in Shuffle Master 1-28.

II C-32 B3.2.1-

b

Concrete: 

Dome; 

wall; 

basemat

Concrete Water –

flowing

Increase in 

porosity, 

permeability/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide.Inaccessible 

Areas:An aging management program is not 

necessary, even if reinforced concrete is exposed 

to flowing water, if there is documented evidence 

that confirms the in-place concrete was 

constructed in accordance with the 

recommendations in ACI 201.2R.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
September 2005

E-33 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-33 Did not exist in Shuffle Master 1-28.

II C-33 B3.2.1-

h

Concrete: 

Dome; 

wall;

basemat

Concrete Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management programThe 

implementation of 10 CFR 50.55a and ASME 

Section XI, Subsection IWL would not be able to 

identify the reduction of strength and modulus due 

to elevated temperature. Thus, for any portions of 

concrete containment that exceed specified 

temperature limits, further evaluations are 

warranted. Subsection CC-3400 of ASME 

Section III, Division 2, specifies the concrete 

temperature limits for normal operation or any 

other long-term period. The temperatures shall not 

exceed 150°F except for local areas, such as 

around penetrations, which are not allowed to 

exceed 200°F. If significant equipment loads are 

supported by concrete at temperatures exceeding 

150°F, an evaluation of the ability to withstand the 

postulated design loads is to be made.Higher 

temperatures than given above may be allowed in 

the concrete if tests and/or calculations are 

provided to evaluate the reduction in strength and 

this reduction is applied to the design allowables.

Yes, if 

temperature 

limits are 

exceeded

II C-34 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-34 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-34 A2.2-h Concrete:

Basemat

Concrete Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management programThe 

implementation of 10 CFR 50.55a and ASME 

Section XI, Subsection IWL would not be able to 

identify the reduction of strength and modulus due 

to elevated temperature. Thus, for any portions of 

concrete containment that exceed specified 

temperature limits, further evaluations are 

warranted. Subsection CC-3400 of ASME 

Section III, Division 2, specifies the concrete 

temperature limits for normal operation or any 

other long-term period. The temperatures shall not 

exceed 150°F except for local areas, such as 

around penetrations, which are not allowed to 

exceed 200°F. If significant equipment loads are 

supported by concrete at temperatures exceeding 

150°F, an evaluation of the ability to withstand the 

postulated design loads is to be made.Higher 

temperatures than given above may be allowed in 

the concrete if tests and/or calculations are 

provided to evaluate the reduction in strength and 

this reduction is applied to the design allowables.

Yes, if 

temperature 

limits are 

exceeded

II C-35 Did not exist in Shuffle Master 1-28.
September 2005

E-35 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-35 B2.2.1-

g B1.2.

Concrete:

Containm

ent; wall; 

basemat

Concrete Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management programThe 

implementation of 10 CFR 50.55a and ASME 

Section XI, Subsection IWL would not be able to 

identify the reduction of strength and modulus due 

to elevated temperature. Thus, for any portions of 

concrete containment that exceed specified 

temperature limits, further evaluations are 

warranted. Subsection CC-3400 of ASME 

Section III, Division 2, specifies the concrete 

temperature limits for normal operation or any 

other long-term period. The temperatures shall not 

exceed 150°F except for local areas, such as 

around penetrations, which are not allowed to 

exceed 200°F. If significant equipment loads are 

supported by concrete at temperatures exceeding 

150°F, an evaluation of the ability to withstand the 

postulated design loads is to be made.Higher 

temperatures than given above may be allowed in 

the concrete if tests and/or calculations are 

provided to evaluate the reduction in strength and 

this reduction is applied to the design allowables.

Yes, if 

temperature 

limits are 

exceeded

II C-36 Did not exist in Shuffle Master 1-28.

II C-36 A2.2-f 

B3.1.2-

e 

Concrete:

Basemat

Concrete Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring Program"If 

a de-watering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation. 

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon
NUREG-1832

E-36 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-37 Did not exist in Shuffle Master 1-28.

II C-37 A1.1-f Concrete: 

Dome; 

wall; 

basemat; 

ring 

girders; 

buttresse

s

Concrete Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring Program"If 

a de-watering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation. 

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon

II C-38 Did not exist in Shuffle Master 1-28.

II C-38 A2.2-d Concrete:

Basemat

Concrete Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking due to reaction with 

aggregates.Inaccessible Areas: As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

significant if the concrete was constructed in 

accordance with ACI 201.2R.Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

Yes, if 

concrete was

not 

constructed 

as stated for 

inaccessible 

areas

II C-39 Did not exist in Shuffle Master 1-28.
September 2005

E-37 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-39 B2.2.1-c 

B1.2.

Concrete:

Containm

ent; wall; 

basemat

Concrete Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking due to reaction with 

aggregates.Inaccessible Areas: As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

significant if the concrete was constructed in 

accordance with ACI 201.2R. Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas

II C-40 Did not exist in Shuffle Master 1-28.

II C-40 B3.2.1-

d

Concrete: 

Dome; 

wall; 

basemat

Concrete Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking due to reaction with 

aggregates.Inaccessible Areas: As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

significant if the concrete was constructed in 

accordance with ACI 201.2R.Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas

II C-41 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-38 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-41 B2.2.1-

d B1.2. 

Concrete:

Basemat; 

reinforcin

g steel

Concrete; 

steel

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking, loss of bond, and loss of 

material (spalling, scaling) due to corrosion of 

embedded steel.Inaccessible Areas:For plants 

with non-aggressive ground water/soil; i.e., pH > 

5.5, chlorides < 500 ppm, or sulfates <1500 ppm, 

as a minimum, consider (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-42 Did not exist in Shuffle Master 1-28.
September 2005

E-39 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-42 B3.2.1-

e

Concrete: 

Dome; 

wall; 

basemat; 

reinforcin

g steel

Concrete; 

steel

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking, loss of bond, and loss of 

material (spalling, scaling) due to corrosion of 

embedded steel.Inaccessible Areas:For plants 

with non-aggressive ground water/soil; i.e., pH > 

5.5, chlorides < 500 ppm, or sulfates <1500 ppm, 

as a minimum, consider (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-43 Did not exist in Shuffle Master 1-28.
NUREG-1832

E-40 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-43 A2.2-e 

B3.1.2-

d 

Concrete:

Basemat; 

reinforcin

g steel

Concrete; 

steel

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking, loss of bond, and loss of 

material (spalling, scaling) due to corrosion of 

embedded steel.Inaccessible Areas:For plants 

with non-aggressive ground water/soil; i.e., pH > 

5.5, chlorides < 500 ppm, or sulfates <1500 ppm, 

as a minimum, consider (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

II C-44 Did not exist in Shuffle Master 1-28.

II C-44 B2.1.1-

b 

Suppress

ion pool 

shell; 

unbraced 

downcom

ers

Steel; 

stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ASME 

Section XI, Subsection IWE is to be supplemented 

to consider the following:(4) Detection of Aging 

Effects: VT-3 visual inspection may not detect fine 

cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-45 Did not exist in Shuffle Master 1-28.
September 2005

E-41 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-45 B2.1.1-c Suppress

ion pool 

shell; 

unbraced 

downcom

ers

Steel; 

stainless 

steel; 

dissimilar 

metal 

welds

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

II C-46 Did not exist in Shuffle Master 1-28.

II C-46 B2.1.1-

a 

B2.2.2-

a B1.2.

Steel 

elements: 

Suppress

ion 

chamber; 

drywell 

liner; 

drywell 

head; 

embedde

d shell; 

sand 

pocket 

region; 

support 

skirt; 

downcom

er pipes; 

region 

shielded 

by 

diaphrag

m 

floorNOT

E: 

Inspectio

n of 

Steel Air –

indoor 

uncontroll

ed or 

treated 

water (as 

applicabl

e)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE” For inaccessible areas (embedded 

containment steel shell or liner), loss of material 

due to corrosion is not significant if the following 

conditions are satisfied:Concrete meeting the 

specifications of ACI 318 or 349 and the guidance 

of 201.2R was used for the containment concrete 

in contact with the embedded containment shell or 

liner. The concrete is monitored to ensure that it is 

free of penetrating cracks that provide a path for 

water seepage to the surface of the containment 

shell or liner. The moisture barrier, at the junction 

where the shell or liner becomes embedded, is 

subject to aging management activities in 

accordance with ASME Section XI, Subsection 

IWE requirements. Water ponding on the 

containment concrete floor are not common and 

when detected are cleaned up in a timely 

manner.If any of the above conditions cannot be 

satisfied, then a plant-specific aging management 

program for corrosion is necessary.Chapter XI.S4, 

"10 CFR Part 50, Appendix J"

Yes, if 

corrosion is 

significant for 

inaccessible 

areasNo
NUREG-1832

E-42 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

containm

ent 

supports 

is 

addresse

d by 

ASME 

Section X

I, 

Subsecti

on IWF 

(see 

III.B1.3) 

II C-47 Did not exist in Shuffle Master 1-28.

II C-47 B2.2.2-c Steel 

elements:

Vent 

header;D

owncome

rs 

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed

Cracking/ 

cyclic 

loading(CLB 

fatigue 

analysis does 

not exist)

Chapter XI.S1, "ASME Section XI, Subsection 

IWE " and Chapter XI.S4, "10 CFR Part 50, 

Appendix J” Evaluation of 10 CFR 50.55a/ASME 

Section XI, Subsection IWE is augmented as 

follows:(4) Detection of Aging Effects: VT-3 visual 

inspection may not detect fine cracks.

Yes, 

detection of 

aging effects 

is to be 

evaluated

II C-48 Did not exist in Shuffle Master 1-28.
September 2005

E-43 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

II C-48 B2.2.2-

d

Steel 

elements:

Vent 

header;D

owncome

rs 

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed or 

treated 

water (as 

applicabl

e)

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.6, 

"Containment Liner Plate and Penetration Fatigue 

Analysis" for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

II C-49 Did not exist in Shuffle Master 1-28.

II C-49 B2.2.2-

b B1.2.

Steel 

elements:

Suppress

ion 

chamber 

liner 

(interior 

surface)

Stainless 

steel; 

steel

Air –

indoor 

uncontroll

ed or 

treated 

water (as 

applicabl

e)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S1, "ASME Section XI, Subsection 

IWE" and Chapter XI.S4, "10 CFR Part 50, 

Appendix J"

No

II C-50 Did not exist in Shuffle Master 1-28.

II C-50 B3.1.2-

g

Concrete:

Basemat, 

concrete 

fill-in 

annulus

Concrete Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management programThe 

implementation of 10 CFR 50.55a and ASME 

Section XI, Subsection IWL would not be able to 

identify the reduction of strength and modulus due 

to elevated temperature. Thus, for any portions of 

concrete cont ainment that exceed specified 

temperature limits, further evaluations are 

warranted. Subsection CC-3400 of ASME 

Section III, Division 2, specifies the concrete 

temperature limits for normal operation or any 

other long-term period. The temperatures shall not 

exceed 150°F except for local areas, such as 

around penetrations, which are not allowed to 

exceed 200°F. If significant equipment loads are 

supported by concrete at temperatures exceeding 

150°F, an evaluation of the ability to withstand the 

postulated design loads is to be made.Higher 

Yes, if 

temperature 

limits are 

exceeded
NUREG-1832

E-44 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

temperatures than given above may be allowed in 

the concrete if tests and/or calculations are 

provided to evaluate the reduction in strength and 

this reduction is applied to the design allowables.

II C-51 Did not exist in Shuffle Master 1-28.

II C-51 B3.1.2-c Concrete:

Basemat, 

concrete 

fill-in 

annulus

Concrete Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

surface cracking due to reaction with 

aggregates.Inaccessible Areas: As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

significant if the concrete was constructed in 

accordance with ACI 201.2R.Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
September 2005

E-45 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-01 A1.1-a 

A2.1-a 

A3.1-a 

A5.1-a 

A7.1-a 

A8.1-a 

A9.1-a

Concrete:

Exterior 

above 

and 

below 

grade; 

foundatio

n

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S6, "StructuresMonitoring 

Program"Accessible Areas:Inspections performed 

in accordance with "Structures Monitoring 

Program" will indicate the presence of loss of 

material (spalling, scaling) and cracking due to 

freeze-thaw.Inaccessible Areas:Evaluation is 

needed for plants that are located in moderate to 

severe weathering conditions (weathering index > 

100 day-inch/yr) (NUREG-1557). Documented 

evidence to confirm that existing concrete has air 

content of 3% to 6% and subsequent inspections 

did not exhibit degradation related to freeze-thaw, 

should be considered a part of the evaluation.The 

weathering index for the continental US is shown 

in ASTM C33-90, Fig.1.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program and 

stated 

conditions 

are satisfied 

for 

inaccessible 

areas

III T-01 A1.1-a 

A2.1-a 

A3.1-a 

A5.1-a 

A7.1-a 

A8.1-a 

A9.1-a

Concrete:

Exterior 

aboveand

belowgrade; 

foundatio

n

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S6, "Structures Monitoring 

Program"Accessible Areas:Inspections performed 

in accordance with the Structures Monitoring 

Program will indicate the presence of loss of 

material (spalling, scaling) and cracking due to 

freeze-thaw.Inaccessible Areas:Evaluation is 

needed for plants that are located in moderate to 

severe weathering conditions (weathering index > 

100 day-inch/yr) (NUREG-1557). Documented 

evidence to confirm that existing concrete has air 

content of 3% to 6% and water-to-cement ratio of 

0.35-0.45, and subsequent inspections did not 

exhibit degradation related to freeze-thaw, should 

be considered a part of the evaluation.The 

weathering index for the continental US is shown 

in ASTM C33-90, Fig.1.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or 

for plants 

located in 

moderate to 

severe 

weathering 

conditions
NUREG-1832

E-46 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-02 A1.1-b 

A2.1-b 

A3.1-b 

A5.1-b 

A7.1-b 

A8.1-b 

A9.1-b

Concrete:

Exterior 

above 

and 

below 

grade; 

foundatio

n

Reinforce

d 

concrete

Water –

flowing

Increase in 

porosity and 

permeability, 

loss of 

strength/ 

leaching of 

calcium 

hydroxide

Chapter XI.S2, "ASME Section XI, Subsection 

IWL"Accessible areas:Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity, and permeability due to 

leaching of calcium hydroxide.Inaccessible Areas:. 

An aging management program is not necessary, 

even if reinforced concrete is exposed to flowing 

water, if there is documented evidence that 

confirms the in-place concrete was constructed in 

accordance with the recommendations in ACI 

201.2R-77.

No,if 

concrete was 

constructed 

as stated for 

inaccessible 

areas

III T-02 A1.1-b 

A2.1-b 

A3.1-b 

A5.1-b 

A7.1-b 

A8.1-b 

A9.1-b

Concrete:

Exterior 

aboveand 

belowgrade; 

foundatio

n

Reinforce

d 

concrete

Water –

flowing

Increase in 

porosity and 

permeability, 

loss of 

strength/ 

leaching of 

calcium 

hydroxide

Chapter XI.S6, "Structures Monitoring 

Program"Accessible areas:Inspections performed 

in accordance with the Structures Monitoring 

Program will indicate the presence of increase in 

porosity, and permeability due to leaching of 

calcium hydroxide.Inaccessible Areas:An aging 

management program is not necessary, even if 

reinforced concrete is exposed to flowing water, if 

there is documented evidence that confirms the inplace concrete was constructed in accordance 

with the recommendations in ACI 201.2R.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
September 2005

E-47 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-03 A1.1-c 

A2.1-c 

A3.1-c 

A4.1-b 

A5.1-c 

A7.1-c 

A8.1-c 

A9.1-c

Concrete:

All

Reinforce

d 

concrete

Any Expansion 

and cracking/ 

reaction with 

aggregates

Chapter XI.S6, "Structures Monitoring 

Program"Accessible 

Areas:Inspections/evaluations performed in 

accordance with "Structures Monitoring Program"

will indicate the presence of expansion and 

cracking due to reaction with 

aggregates.Inaccessible Areas:Evaluation is 

needed if testing and petrographic examinations of 

aggregates performed in accordance with ASTM 

C295-54, ASTM C227-50, or ACI 201.2R-77 

(NUREG-1557) demonstrate that the aggregates 

are reactive.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program and 

stated 

conditions 

are satisfied 

for 

inaccessible 

areas

III T-03 A1.1-c 

A2.1-c 

A3.1-c 

A4.1-b 

A5.1-c 

A7.1-c 

A8.1-c 

A9.1-c

Concrete:

All

Reinforce

d 

concrete

Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S6, "Structures Monitoring 

Program"Accessible 

Areas:Inspections/evaluations performed in 

accordance with the Structures Monitoring 

Program will indicate the presence of expansion 

and cracking due to reaction with 

aggregates.Inaccessible Areas: As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

significant if the concrete was constructed in 

accordance with ACI 201.2R. Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas.
NUREG-1832

E-48 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-04 A1.1-d 

A2.1-d 

A3.1-d 

A4.1-d 

A5.1-d 

A7.1-d 

A9.1-d

Concrete:

Interior 

and 

abovegrade 

exterior

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed or air -

outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S6, "Structures Monitoring 

Program"Accessible areas:Inspections performed 

in accordance with "Structures Monitoring 

Program" will indicate the presence of cracking, 

loss of bond, and loss of material (spalling, 

scaling) due to corrosion of embedded steel.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program

III T-04 A1.1-d 

A2.1-d 

A3.1-d 

A4.1-d 

A5.1-d 

A7.1-d 

A9.1-d

Concrete:

Interior 

and 

abovegrade 

exterior

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking,

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S6, "Structures Monitoring 

Program"Accessible areas:Inspections performed 

in accordance with the Structures Monitoring 

Program will indicate the presence of cracking, 

loss of bond, and loss of material (spalling, 

scaling) due to corrosion of embedded steel.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-05 A1.1-e 

A2.1-e 

A3.1-e 

A5.1-e 

A7.1-e 

A8.1-d 

A9.1-e

Concrete:

Belowgrade 

exterior; 

foundatio

n

Reinforce

d 

concrete

Aggressi

ve 

environm

ent

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S2, "ASME Section XI, Subsection 

IWL” Accessible Areas: Inspections performed in 

accordance with IWL will indicate the presence of 

increase in porosity and permeability, cracking, or 

loss of material (spalling, scaling) due to 

aggressive chemical attack.Inaccessible 

Areas:Examination of representative samples of 

below-grade concrete, when excavated for any 

reason, is to be performed, if the below-grade 

environment is aggressive (pH < 5.5, chlorides > 

500ppm, or sulfates > 1,500 ppm). Periodic 

monitoring of below-grade water chemistry 

(including consideration of potential seasonal 

variations) is an acceptable approach to 

demonstrate that the below-grade environment is 

aggressive or non-aggressive.

Yes, if 

environment 

is aggressive
September 2005

E-49 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-05 A1.1-e 

A2.1-e 

A3.1-e 

A5.1-e 

A7.1-e 

A8.1-d 

A9.1-e

Concrete:

Belowgrade 

exterior; 

foundatio

n

Reinforce

d 

concrete

Ground 

water/soil

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S6, "Structures Monitoring 

Program"Accessible Areas:Inspections performed 

in accordance with the Structures Monitoring 

Program will indicate the cracking, loss of bond, or 

loss of material (spalling, scaling) due to corrosion 

of embedded steel.Inaccessible Areas:For plants 

with non-aggressive ground water/soil; i.e., pH > 

5.5, chlorides < 500 ppm, or sulfates <1500 ppm, 

as a minimum, consider(1) Examination of the 

exposed portions of the below-grade concrete, 

when excavated for any reason, and (2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations. For plants with aggressive

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive

III T-06 A1.1-f 

A2.1-f 

A3.1-f 

A4.1-a 

A5.1-f 

A7.1-f 

A9.1-f

Concrete:

Interior 

and 

abovegrade 

exterior

Reinforce

d 

concrete

Aggressi

ve 

environm

ent

Increase in 

porosity and 

permeability, 

cracking, loss

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S6, "Structures Monitoring 

Program"Accessible Areas:Inspections performed 

in accordance with "Structures Monitoring 

Program" will indicate the presence of increase in 

porosity and permeability, cracking, or loss of 

material (spalling, scaling) due to aggressive 

chemical attack.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
NUREG-1832

E-50 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-06 A1.1-f 

A2.1-f 

A3.1-f 

A4.1-a 

A5.1-f 

A7.1-f 

A9.1-f

Concrete:

Interior 

and 

abovegrade 

exterior

Reinforce

d 

concrete

Air-indoor 

uncontroll

ed or airoutdoor

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S6, "Structures Monitoring 

Program"Accessible Areas:Inspections performed 

in accordance with Structures Monitoring Program 

will indicate the presence of increase in porosity 

and permeability, cracking, or loss of material 

(spalling, scaling) due to aggressive chemical 

attack.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-07 A1.1-g 

A2.1-g 

A3.1-g 

A5.1-g 

A7.1-g 

A8.1-e 

A9.1-g

Concrete:

Belowgrade 

exterior; 

foundatio

n

Reinforce

d 

concrete

Aggressi

ve 

environm

ent

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Inaccessible Areas:Examination of representative 

samples of below-grade concrete, when 

excavated for any reason, is to be performed, if 

the below-grade environment is aggressive (pH < 

5.5, chlorides > 500ppm, or sulfates > 1,500 ppm). 

Periodic monitoring of below-grade water 

chemistry (including consideration of potential 

seasonal variations) is an acceptable approach to 

demonstrate that the below-grade environment is 

aggressive or non-aggressive.

Yes, if 

environment 

is aggressive

III T-07 A1.1-g 

A2.1-g 

A3.1-g 

A5.1-g 

A7.1-g 

A8.1-e 

A9.1-g

Concrete:

Belowgrade 

exterior; 

foundatio

n

Reinforce

d 

concrete

Ground 

water/soil

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Inaccessible Areas:For plants with non-aggressive 

ground water/soil; i.e., pH > 5.5, chlorides < 500 

ppm, or sulfates <1500 ppm, as a minimum, 

consider(1) Examination of the exposed portions 

of the below-grade concrete, when excavated for 

any reason, and (2) Periodic monitoring of belowgrade water chemistry, including consideration of 

potential seasonal variations. For plants with 

aggressive groundwater/soil, and/or where the 

concrete structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive
September 2005

E-51 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-08 A1.1-h 

A2.1-h 

A3.1-h 

A5.1-h 

A7.1-h 

A8.1-f 

A9.1-h 

A6.1-f

Concrete:

All

Reinforce

d 

concrete

Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring 

Program"The initial licensing basis for some plants 

included a program to monitor settlement. If no 

settlement was evident during the first decade or 

so, the NRC may have given the licensee 

approval to discontinue the program. However, if a 

de-watering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program

III T-08 A1.1-h 

A2.1-h 

A3.1-h 

A5.1-h 

A6.1-f 

A7.1-h 

A8.1-f 

A9.1-h 

Concrete:

All

Reinforce

d 

concrete

Soil Cracks and 

distortion due 

to increased 

stress levels 

from 

settlement

Chapter XI.S6, "Structures Monitoring Program"If 

a de-watering system is relied upon for control of 

settlement, then the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation. 

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon

III T-09 A1.1-I 

A2.1-I 

A3.1-I 

A5.1-I 

A6.1-g 

A7.1-I 

A8.1-g 

A9.1-i

Concrete:

Foundati

on;subfo

undation

Reinforce

d 

concrete;

porous 

concrete

Water -

flowing 

under 

foundatio

n

Reduction in 

foundation 

strength, 

cracking, 

differential 

settlement/ 

erosion of 

porous 

concrete 

subfoundatio

n

Chapter XI.S6, "Structures Monitoring 

Program"Erosion of cement from porous concrete 

subfoundations beneath containment basemats is 

described in IN 97-11. IN 98-26 proposes 

Maintenance Rule Structures Monitoring for 

managing this aging effect, if applicable. If a dewatering system is relied upon for control of 

erosion of cement from porous concrete 

subfoundations, then the licensee is to ensure 

proper functioning of the de-watering system 

through the period of extended operation.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
NUREG-1832

E-52 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-09 A1.1-i 

A2.1-i 

A3.1-i 

A5.1-i 

A6.1-g 

A7.1-i 

A8.1-g 

A9.1-i

Concrete:

Foundati

on; 

subfound

ation

Reinforce

d 

concrete;

Porous 

concrete

Water –

flowing 

under 

foundatio

n

Reduction in 

foundation 

strength, 

cracking, 

differential 

settlement/ 

erosion of 

porous 

concrete 

subfoundatio

n

Chapter XI.S6, "Structures Monitoring 

Program"Erosion of cement from porous concrete 

subfoundations beneath containment basemats is 

described in NRC IN 97-11. NRC IN 98-26 

proposes Maintenance Rule Structures Monitoring 

for managing this aging effect, if applicable. If a 

de-watering system is relied upon for control of 

erosion of cement from porous concrete 

subfoundations, the licensee is to ensure proper 

functioning of the de-watering system through the 

period of extended operation.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program or a 

de-watering 

system is 

relied upon

III T-10 A1.1-j 

A2.1-j 

A3.1-j 

A4.1-c 

A5.1-j

Concrete:

All

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F

general; 

>200°F local)

Plant-specific aging management programFor any 

concrete elements that exceed specified 

temperature limits, further evaluations are 

warranted. Appendix A of ACI 349-85 specifies the 

concrete temperature limits for normal operation 

or any other long-term period. The temperatures 

shall not exceed 150°F except for local areas 

which are allowed to have increased temperatures 

not to exceed 200°F.

Yes, if 

applicable

III T-10 A1.1-j 

A2.1-j 

A3.1-j 

A4.1-c 

A5.1-j

Concrete:

All

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Reduction of 

strength and 

modulus/ 

elevated 

temperature 

(>150°F 

general; 

>200°F local)

Plant-specific aging management programFor any 

concrete elements that exceed specified 

temperature limits, further evaluations are 

warranted. Appendix A of ACI 349-85 specifies the 

concrete temperature limits for normal operation 

or any other long-term period. The temperatures 

shall not exceed 150°F except for local areas 

which are allowed to have increased temperatures 

not to exceed 200°F.

Yes, if 

temperature 

limits are 

exceeded
September 2005

E-53 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-11 A1.2-a 

A2.2-a 

A3.2-a 

A4.2-a 

A5.2-a 

A7.2-a 

A8.2-a

Steel 

compone

nts:All 

structural 

steel

Steel Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

material/ 

corrosion

Chapter XI.S6, "Structures Monitoring Program"If 

protective coatings are relied upon to manage the 

effects of aging, the structures monitoring program 

is to include provisions to address protective 

coating monitoring and maintenance.

No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program

III T-11 A1.2-a 

A2.2-a 

A3.2-a 

A4.2-a 

A5.2-a 

A7.2-a 

A8.2-a

Steel 

compone

nts:All 

structural 

steel

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

material/ 

corrosion

Chapter XI.S6, "Structures Monitoring Program"If 

protective coatings are relied upon to manage the 

effects of aging, the structures monitoring program 

is to include provisions to address protective 

coating monitoring and maintenance.

Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-12 A1.3-a 

A2.3-a 

A3.3-a 

A5.3-a 

A6.3-a

Masonry 

walls:All

Concrete 

block

Air –

indoor 

uncontroll

ed or air -

outdoor

Cracking due 

to restraint 

shrinkage, 

creep, and 

aggressive 

environment

Chapter XI.S5, "Masonry Wall Program" No

III T-12 A1.3-a 

A2.3-a 

A3.3-a 

A5.3-a 

A6.3-a

Masonry 

walls:All

Concrete 

block

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking due 

to restraint 

shrinkage, 

creep, and 

aggressive 

environment

Chapter XI.S5, "Masonry Wall Program" No
NUREG-1832

E-54 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-13 A4.2-b Steel 

compone

nts:Radia

l beam 

seats in 

BWR 

drywell;R

PV 

support 

shoes for 

PWR 

with 

nozzle 

supports;

Steam 

generator 

supports

Lubrite Air –

indoor 

uncontroll

ed

Lock-up/ 

wear

Chapter XI.S3, "ASME Section XI, Subsection 

IWF" orChapter XI.S6, "Structures Monitoring 

Program"

No, if within 

the scope of 

Section XI, 

IWF or 

structures 

monitoring 

program

III T-13 A4.2-b Steel 

compone

nts:Radia

l beam 

seats in 

BWR 

drywell;R

PV 

support 

shoes for 

PWR 

with 

nozzle 

supports;

Steam 

generator 

supports

Lubrite® Air –

indoor 

uncontroll

ed

Lock-up/ 

wear

Chapter XI.S3, "ASME Section XI, Subsection 

IWF" orChapter XI.S6, "Structures Monitoring 

Program"

Yes, if not 

within the 

scope of 

Section XI, 

IWF or 

structures 

monitoring 

program
September 2005

E-55 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-14 A5.2-b Steel 

compone

nts:Fuel 

pool liner

Stainless 

steel

Water –

standing

Cracking/ 

stress 

corrosion 

crackingLoss 

of 

material/pittin

g and crevice 

corrosion

Chapter XI.M2, "Water Chemistry Program" and 

monitoring of the spent fuel pool water level

No

III T-14 A5.2-b Steel 

compone

nts:Fuel 

pool liner

Stainless 

steel

Treated 

water or 

treated 

borated 

water

Cracking/ 

stress 

corrosion 

crackingLoss 

of 

material/pittin

g and crevice 

corrosion

Chapter XI.M2, "Water Chemistry" and,Monitoring 

of the spent fuel pool water level in accordance 

with technical specifications and leakage from the 

leak chase channels.

No

III T-15 A6.1-a Concrete:

Exterior 

above 

and 

below 

grade; 

foundatio

n; interior 

slab

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenanceAs described in NUREG-1557, 

freeze-thaw does not cause loss of material from 

reinforced concrete in foundations, and in aboveand below-grade exterior concrete, for plants 

located in a geographic region of negligible 

weathering conditions (weathering index <100 

day-inch/yr). Loss of material from such concrete 

is not significant at plants located in areas in which 

weathering conditions are severe (weathering 

index >500 day-inch/yr) or moderate (100-500 

day-inch/yr), provided that the concrete mix design 

meets the air content (entrained air3-6%) and 

water-to-cement ratio(0.35-0.45) specified in ACI 

318-63 or ACI 349-85. Therefore, if these 

conditions are satisfied, aging management is not 

No
NUREG-1832

E-56 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

necessary.The weathering index is defined in 

ASTM C33-90, Table 3, Footnote E. Fig. 1 of 

ASTM C33-90 illustrates the various weathering 

index regions throughout the U.S.

III T-15 A6.1-a Concrete:

Exterior 

aboveand 

belowgrade; 

foundatio

n

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material 

(spalling, 

scaling) and 

cracking/ 

freeze-thaw

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.Accessible 

Areas:Inspections performed in accordance with 

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs will indicate the presence 

of loss of material (spalling, scaling) and cracking 

due to freeze-thaw.Inaccessible Areas: As

described in NUREG-1557, freeze-thaw does not 

cause loss of material from reinforced concrete in 

foundations, or in above- and below-grade exterior 

concrete, for plants located in a geographic region 

of negligible weathering conditions (weathering 

index <100 day-inch/yr). Loss of material from 

such concrete is not significant at plants located in 

areas in which weathering conditions are severe 

(weathering index >500 day-inch/yr) or moderate 

(100-500 day-inch/yr), provided that the concrete 

mix design meets the air content (entrained air 3-

6%) and water-to-cement ratio (0.35-0.45) 

specified in ACI 318-63 or ACI 349-85. Therefore, 

if these conditions are satisfied, aging 

management is not necessary.The weathering 

index is defined in ASTM C33-90, Table 3, 

Footnote E. Fig. 1 of ASTM C33-90 illustrates the 

various weathering index regions throughout the 

Yes, for 

inaccessible 

areas of 

plants 

located in 

moderate to 

severe 

weathering 

conditions
September 2005

E-57 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

U.S.
NUREG-1832

E-58 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-16 A6.1-b Concrete:

Exterior 

above 

and 

below 

grade; 

foundatio

n; interior 

slab

Reinforce

d 

concrete

Water –

flowing

Increase in 

porosity and 

permeability, 

loss of 

strength/ 

leaching of 

calcium 

hydroxide

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenanceAs described in NUREG-1557, 

leaching of calcium hydroxide from reinforced 

concrete becomes significant only if the concrete 

is exposed to flowing water. Even if reinforced 

concrete is exposed to flowing water, such 

leaching is not significant if the concrete is 

constructed to ensure that it is dense, well-cured, 

has low permeability, and that cracking is well 

controlled. Cracking is controlled through proper 

arrangement and distribution of reinforcing bars. 

All of the above characteristics are assured if the 

concrete was constructed with the guidance of 

ACI 201.2R-77. Therefore, if these conditions are 

satisfied, aging management is not necessary.

No
September 2005

E-59 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-16 A6.1-b Concrete:

Exterior 

aboveand 

belowgrade; 

foundatio

n; interior 

slab

Reinforce

d 

concrete

Water –

flowing

Increase in 

porosity and 

permeability, 

loss of 

strength/ 

leaching of 

calcium 

hydroxide

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programsAccessible 

Areas:Inspections performed in accordance with 

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs will indicate the presence 

of increase in porosity and permeability, loss of 

strength/ leaching of calcium 

hydroxideInaccessible Areas: As described in 

NUREG-1557, leaching of calcium hydroxide from 

reinforced concrete becomes significant only if the 

concrete is exposed to flowing water. Even if 

reinforced concrete is exposed to flowing water, 

such leaching is not significant if the concrete is 

constructed to ensure that it is dense, well-cured, 

has low permeability, and that cracking is well 

controlled. Cracking is controlled through proper 

arrangement and distribution of reinforcing bars. 

All of the above characteristics are assured if the 

concrete was constructed with the guidance of 

ACI 201.2R. Therefore, if these conditions are 

satisfied, aging management is not necessary.

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
NUREG-1832

E-60 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-17 A6.1-c Concrete:

All

Reinforce

d 

concrete

Any Expansion 

and cracking/ 

reaction with 

aggregates

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenanceAs described in NUREG-1557, 

investigations, tests, and petrographic 

examinations of aggregates performed in 

accordance with ASTM C295-54 or ASTM C227-

50 can demonstrate that those aggregates do not 

react within reinforced concrete. For potentially 

reactive aggregates, aggregate-reinforced 

concrete reaction is not significant if the concrete 

was constructed in accordance with ACI 201.2R77.Therefore, if these conditions are satisfied, 

aging management is not necessary.

No

III T-17 A6.1-c Concrete:

All

Reinforce

d 

concrete

Any Cracking due 

to expansion/ 

reaction with 

aggregates

Chapter XI.S7, “Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants” or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.Accessible 

Areas:Inspections/evaluations performed in 

accordance with “Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants” or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs will indicate the presence 

of expansion and cracking due to reaction with 

aggregates.Inaccessible areas:As described in 

NUREG-1557, investigations, tests, and 

petrographic examinations of aggregates 

performed in accordance with ASTM C295-54 or 

ASTM C227-50 can demonstrate that those 

aggregates do not react within reinforced 

concrete. For potentially reactive aggregates, 

aggregate-reinforced concrete reaction is not 

Yes, if 

concrete was 

not 

constructed 

as stated for 

inaccessible 

areas
September 2005

E-61 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

significant if the concrete was constructed in 

accordance with ACI 201.2R. Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

III T-18 A6.1-d Concrete:

All

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed or air -

outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance.As described in NUREG-1557, 

corrosion of exterior above-grade and interior 

embedded steel is not significant if the steel is not 

exposed to an aggressive environment (concrete 

pH <11.5 or chlorides >500 ppm). If such steel is 

exposed to an aggressive environment, corrosion 

is not significant if the concrete in which the steel 

is embedded has a low water-to-cement ratio 

(0.35-0.45), adequate air entrainment (3-6%), low 

permeability, and is designed in accordance 

withACI 318-63 or ACI 349-85. Therefore, if these 

conditions are satisfied, aging management is not 

necessary.

No
NUREG-1832

E-62 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-18 A6.1-d Concrete:

All

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed or air 

– outdoor

Cracking, 

loss of bond, 

and loss of 

material 

(spalling, 

scaling)/ 

corrosion of 

embedded 

steel

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.Accessible areas:As 

described in NUREG-1557, corrosion of exterior 

above-grade and interior embedded steel is not 

significant if the steel is not exposed to an 

aggressive environment (concrete pH <11.5 or 

chlorides >500 ppm). If such steel is exposed to 

an aggressive environment, corrosion is not 

significant if the concrete in which the steel is 

embedded has a low water-to-cement ratio (0. 35-

0.45), adequate air entrainment (3-6%), low 

permeability, and is designed in accordance with 

ACI 318-63 or ACI 349-85. Therefore, if these 

conditions are satisfied, aging management is not 

necessary.Inaccessible areas:For plants with nonaggressive ground water/soil; i.e., pH > 5.5, 

chlorides < 500 ppm, or sulfates <1500 ppm, as a 

minimum, consider (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry,

including consideration of potential seasonal 

variations.For plants with aggressive 

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

Yes, plantspecific if 

environment 

is aggressive
September 2005

E-63 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-19 A6.1-e Concrete:

All

Reinforce

d 

concrete

Aggressi

ve 

environm

ent

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance.As described in NUREG-1557, 

aggressive chemical attack on interior and abovegrade exterior reinforced concrete is not significant 

if the concrete is not exposed to an aggressive 

environment (pH <5.5), or to chloride or sulfate 

solutions beyond defined limits (>500 ppm 

chloride, or >1500 ppm sulfate). Therefore, if 

these conditions are satisfied, aging management 

is not necessary.

No

III T-19 A6.1-e Concrete:

All

Reinforce

d 

concrete

Ground 

water/soil

Increase in 

porosity and 

permeability, 

cracking, loss 

of material 

(spalling, 

scaling)/ 

aggressive 

chemical 

attack

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.Accessible 

Areas:Inspections performed in accordance with 

"Regulatory Guide 1.127, Inspection of WaterControl Structures Associated with Nuclear Power 

Plants" or the FERC / US Army Corp of Engineers 

dam inspections and maintenance programs will 

indicate the presence of increase in porosity and 

permeability, cracking, or loss of material (spalling, 

scaling) due to aggressive chemical 

attack.Inaccessible areas:For plants with nonaggressive ground water/soil; i.e. pH > 5.5, 

chlorides < 500 ppm, or sulfates <1500 ppm, as a 

minimum, consider: (1) Examination of the 

exposed portions of the below grade concrete, 

when excavated for any reason, and(2) Periodic 

monitoring of below-grade water chemistry, 

including consideration of potential seasonal 

variations.For plants with aggressive 

Yes, plantspecific if 

environment 

is aggressive
NUREG-1832

E-64 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

groundwater/soil, and/or where the concrete 

structural elements have experienced 

degradation, a plant specific AMP accounting for 

the extent of the degradation experienced should 

be implemented to manage the concrete aging 

during the period of extended operation.

III T-20 A6.1-h Concrete:

Exterior 

above 

and 

below 

grade; 

foundatio

n; interior 

slab

Reinforce

d 

concrete

Water –

flowing

Loss of 

material/ 

abrasion; 

cavitation

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance.

No
September 2005

E-65 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-20 A6.1-h Concrete:

Exterior 

aboveand 

belowgrade; 

foundatio

n; interior 

slab

Reinforce

d 

concrete

Water –

flowing

Loss of 

material/ 

abrasion; 

cavitation

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.

No

III T-21 A6.2-a Metal 

compone

nts:All 

structural 

members

Steel; 

Copper 

alloys

Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

material/ 

General 

(steel only), 

pitting and 

crevice 

corrosion

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenanceIf protective coatings are relied upon 

to manage the effects of aging, this AMP is to 

include provisions to address protective coating 

monitoring and maintenance.

No

III T-21 A6.2-a Metal 

compone

nts:All 

structural 

members

Steel; 

copper 

alloys

Air –

indoor 

uncontroll

ed or air -

outdoor; 

Water –

flowing or 

water –

standing

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.If protective coatings are 

relied upon to manage the effects of aging, this 

AMP is to include provisions to address protective 

coating monitoring and maintenance.

No

III T-22 A6.4-a Earthen 

watercontrolstr

uctures:D

ams, 

embank

ments,re

servoirs, 

channels,

Various Water –

flowingW

ater –

standing

Loss of 

material, loss 

of form/ 

erosion, 

settlement, 

sedimentatio

n, frost 

action, 

waves, 

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance.

No
NUREG-1832

E-66 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

canals 

and 

ponds

currents, 

surface 

runoff, 

seepage

III T-22 A6.4-a Earthen 

watercontrol 

structure

s:Dams,E

mbankm

ents,Res

ervoirs,C

hannels,

Canals 

and 

ponds

Various Water –

flowingW

ater –

standing

Loss of 

material, loss 

of form/ 

erosion, 

settlement, 

sedimentatio

n, frost 

action, 

waves, 

currents, 

surface 

runoff, 

seepage

Chapter XI.S7, "Regulatory Guide 1.127, 

Inspection of Water-Control Structures Associated 

with Nuclear Power Plants" or the FERC / US 

Army Corp of Engineers dam inspections and 

maintenance programs.

No

III T-23 A7.2-b 

A8.2-b

Steel 

compone

nts:Tank 

liner

Stainless 

steel

Water –

standing

Cracking/ 

stress 

corrosion 

crackingLoss 

of 

material/pittin

g and crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes
September 2005

E-67 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-23 A7.2-b 

A8.2-b

Steel 

compone

nts:Tank 

liner

Stainless 

steel

Water –

standing

Cracking/ 

stress 

corrosion 

crackingLoss 

of 

material/pittin

g and crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

III T-24 B1.1.1-

a 

B1.2.1-

a 

B1.3.1-

a

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air –

indoor 

uncontroll

ed or air 

outdoor

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.S3, "ASME Section XI, Subsection 

IWF"

No

III T-24 B1.1.1-

a 

B1.2.1-

a 

B1.3.1-

a

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.S3, "ASME Section XI, Subsection 

IWF"

No
NUREG-1832

E-68 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-25 B1.1.1-

b 

B1.2.1-

b B2.1-

b B3.1-

b B4.1-

b B5.1-

b

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

III T-25 B1.1.1-

b 

B1.2.1-

b B2.1-

b B3.1-

b B4.1-

b B5.1-

b

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

III T-26 B1.1.1-c 

B1.2.1-c 

B1.3.1-

b

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-69 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-26 B1.1.1-c 

B1.2.1-c 

B1.3.1-

b

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue(Only 

if CLB fatigue 

analysis 

exists)

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

III T-27 B1.1.2-

a

High 

strength 

bolting 

for NSSS 

compone

nt 

supports

Low alloy 

steel, 

yield 

strength 

>150 ksi

Air –

indoor 

uncontroll

ed 

(External)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

III T-27 B1.1.2-

a

High 

strength 

bolting 

for NSSS 

compone

nt 

supports

Low alloy 

steel, 

yield 

strength 

>150 ksi

Air –

indoor 

uncontroll

ed 

(External)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-70 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-28 B1.1.3-

a 

B1.2.2-

a 

B1.3.2-

a

Constant 

and 

variable 

load 

spring 

hangers; 

guides; 

stops; 

sliding 

surfaces; 

design 

clearance

s; 

vibration 

isolators

Steel and 

non-steel 

materials 

(e.g., 

lubrite 

plates, 

vibration 

isolators, 

etc.)

Air –

indoor 

uncontroll

ed or air -

outdoor

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads; 

elastomer 

hardening

Chapter XI.S3, "ASME Section XI, Subsection 

IWF"

No

III T-28 B1.1.3-

a 

B1.2.2-

a 

B1.3.2-

a

Constant 

and 

variable 

load 

spring 

hangers; 

guides; 

stops; 

sliding 

surfaces; 

design 

clearance

s; 

vibration 

isolators

Steel and 

non-steel 

materials 

(e.g., 

Lubrite® 

plates, 

vibration 

isolators, 

etc.)

Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads; 

elastomer 

hardening

Chapter XI.S3, "ASME Section XI, Subsection 

IWF"

No
September 2005

E-71 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-29 B1.1.4-

a 

B1.2.3-

a 

B1.3.3-

a B2.2-

a B3.2-

a B4.3-

a B5.2-

a

Building 

concrete 

at 

locations 

of 

expansio

n and 

grouted 

anchors; 

grout 

pads for 

support 

base 

plates

Reinforce

d 

concrete; 

grout

Air –

indoor 

uncontroll

ed or air -

outdoor

Reduction in 

concrete 

anchor 

capacity due 

to local 

concrete 

degradation/ 

serviceinduced 

cracking or 

other 

concrete 

aging 

mechanisms

Chapter XI.S6, "Structures Monitoring Program" No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program

III T-29 B1.1.4-

a 

B1.2.3-

a 

B1.3.3-

a B2.2-

a B3.2-

a B4.3-

a B5.2-

a

Building 

concrete 

at 

locations 

of 

expansio

n and 

grouted 

anchors; 

grout 

pads for 

support 

base 

plates

Reinforce

d 

concrete;

Grout

Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction in 

concrete 

anchor 

capacity due 

to local 

concrete 

degradation/ 

serviceinduced 

cracking or 

other 

concrete 

aging 

mechanisms

Chapter XI.S6, "Structures Monitoring Program" Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-30 B2.1-a 

B3.1-a 

B4.1-a 

B5.1-a

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
NUREG-1832

E-72 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

anchorag

e to 

building 

structure

III T-30 B2.1-a 

B3.1-a 

B4.1-a 

B5.1-a

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Steel Air –

indoor 

uncontroll

ed or air 

– outdoor

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.S6, "Structures Monitoring Program" Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-31 B4.2-a Vibration 

isolation 

elements

Nonmetallic 

(e.g.,Rub

ber)

Air –

indoor 

uncontroll

ed or air -

outdoor

Reduction or 

loss of 

isolation 

function/ 

radiation 

hardening, 

temperature, 

humidity, 

sustained 

vibratory 

loading

Chapter XI.S6, "Structures Monitoring Program" No, if within 

the scope of 

the 

applicant’s 

structures 

monitoring 

program
September 2005

E-73 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III T-31 B4.2-a Vibration 

isolation 

elements

Nonmetallic 

(e.g.,Rub

ber)

Air –

indoor 

uncontroll

ed or air 

– outdoor

Reduction or 

loss of 

isolation 

function/ 

radiation 

hardening, 

temperature, 

humidity, 

sustained 

vibratory 

loading

Chapter XI.S6, "Structures Monitoring Program" Yes, if not 

within the 

scope of the 

applicant’s 

structures 

monitoring 

program

III T-32 Did not exist in Shuffle Master 1-28.

III T-32 B1.1.3-

a 

B1.2.2-

a 

B1.3.2-

a 

Sliding 

surfaces

Lubrite®Air–

indoor 

uncontroll

ed or air–

outdoor

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads

Chapter XI.S3, “ASME Section XI, Subsection 

IWF”

No

III T-33 Did not exist in Shuffle Master 1-28.

III T-33 B1.1.3-

a 

B1.2.2-

B1.3.2-

a 

Vibration 

isolation 

elements

Nonmetallic 

(e.g., 

Rubber)

Air–

indoor 

uncontroll

ed or air–

outdoor

Reduction or 

loss of 

isolation 

function/ 

radiation 

hardening, 

temperature, 

humidity, 

sustained 

vibratory 

loading

Chapter XI.S3, “ASME Section XI, Subsection 

IWF”

No
NUREG-1832

E-74 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-1 B2. B4. Steel 

compone

nts:Radia

l beam 

seats in 

BWR 

drywell; 

RPV 

support 

shoes for 

PWR 

with 

nozzle 

supports; 

other 

supports

Lubrite Air –

indoor 

uncontroll

ed

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads; 

elastomer 

hardening

Chapter XI.S6, "Structures Monitoring Program" No

III TP-1 B2. B4. Sliding 

support 

bearings 

and 

sliding 

support 

surfaces

Lubrite®, 

graphitic 

tool steel

Air –

indoor 

uncontroll

ed

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads

Chapter XI.S6, "Structures Monitoring Program" No

III TP10Did not exist in Shuffle Master 1-28.
September 2005

E-75 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP10B1.1 Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Stainless 

steel; 

steel

Treated 

Water < 

60C 

(<140 F)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

water, andChapter XI.S3, "ASME Section XI, 

Subsection IWF"

No

III TP11Did not exist in Shuffle Master 1-28.

III TP11B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Galvaniz

ed steel

Air –

indoor 

uncontroll

ed

None None No
NUREG-1832

E-76 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-2 B2. B4. Sliding 

support 

bearings 

and 

sliding 

support 

surfaces

Lubrite Air –

outdoor

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads; 

elastomer 

hardening

Chapter XI.S6, "Structures Monitoring Program" No

III TP-2 B2. B4. Sliding 

support 

bearings 

and 

sliding 

support 

surfaces

Lubrite®, 

graphitic 

tool steel

Air –

outdoor

Loss of 

mechanical 

function/ 

corrosion, 

distortion, 

dirt, overload, 

fatigue due to 

vibratory and 

cyclic thermal 

loads

Chapter XI.S6, "Structures Monitoring Program" No

III TP-3 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Galvaniz

ed steel, 

aluminum

Air with 

borated 

water 

leakage

Loss of 

material/

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-77 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-3 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Galvaniz

ed steel, 

aluminum

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

III TP-4 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

III TP-4 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Stainless 

steel

Air with 

borated 

water 

leakage

None None No
NUREG-1832

E-78 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-5 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Stainless 

steel

Air –

indoor 

uncontroll

ed

None None No

III TP-5 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Stainless 

steel

Air –

indoor 

uncontroll

ed

None None No

III TP-6 B2. B4. Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Galvaniz

ed steel, 

aluminum

, 

stainless 

steel

Air –

outdoor

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No
September 2005

E-79 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-6 B2. B4. Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Galvaniz

ed steel, 

aluminum

, 

stainless 

steel

Air –

outdoor

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No

III TP-7 A6.5. Seals, 

gaskets, 

and 

moisture 

barriers 

(caulking, 

flashing, 

and other 

sealants)

Elastome

rssuch as 

EPDM 

rubber

Various Loss of 

sealing/ 

deterioration 

of seals, 

gaskets, and 

moisture 

barriers 

(caulking, 

flashing, and 

other 

sealants)

Chapter XI.S6, "Structures Monitoring Program" No

III TP-7 A6. Seals, 

gaskets, 

and 

moisture 

barriers 

(caulking, 

flashing, 

and other 

sealants)

Elastome

rssuch as 

EPDM 

rubber

Various Loss of 

sealing/ 

deterioration 

of seals, 

gaskets, and 

moisture 

barriers 

(caulking, 

flashing, and 

other 

sealants)

Chapter XI.S6, "Structures Monitoring Program" No
NUREG-1832

E-80 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

III TP-8 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building

structure

Galvaniz

ed steel, 

aluminum

Air –

indoor 

uncontroll

ed

Loss of 

material/ 

galvanic 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No

III TP-8 B1.1. 

B1.2. 

B1.3. 

B2. B3. 

B4. B5. 

Support 

members

; welds; 

bolted 

connectio

ns; 

support 

anchorag

e to 

building 

structure

Aluminu

m

Air –

indoor 

uncontroll

ed

None None No

III TP-9 Did not exist in Shuffle Master 1-28.

III TP-9 B1.1 High 

strength 

bolting 

for NSSS 

compone

nt 

supports

Low alloy 

steel, 

yield 

strength 

>150 ksi

Air –

indoor 

uncontroll

ed

Loss of 

material/ 

general 

corrosion

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-81 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-01 D1.1-j 

D2.1-h 

Instrume

nt 

penetrati

ons and 

primary 

side 

nozzles 

and 

welds

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV R-01 D1.1-i 

D1.1-j 

D2.1-h 

Instrume

nt 

penetrati

ons and 

primary 

side 

nozzles, 

safe 

ends, 

and 

welds

Nickel 

alloy; 

steel with 

nickelalloy 

cladding

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water andFor nickel 

alloy, comply with applicable NRC Orders and 

provide a commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-02 C2.1-g 

C2.2-h 

Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714Inspection in accordance with ASME 

Section XI does not require volumetric 

examination of pipes less than NPS 4. A plantspecific destructive examination or a 

nondestructive examination (NDE) that permits 

inspection of the inside surfaces of the piping is to 

be conducted to ensure that cracking has not 

occurred and the component intended function will 

be maintained during the extended period of 

operation.

Yes,paramet

ers 

monitored/ 

inspected 

and detection 

of aging 

effects are to 

be evaluated
NUREG-1832

E-82 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-02 C2.1-g 

C2.2-h 

Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

thermal and 

mechanical 

loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR water andXI.M35, "One-Time 

Inspection of ASME Code Class 1 Small-bore 

Piping"

No

IV R-03 C1.1-i Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel; 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 (EPRI 

TR-103515)Inspection in accordance with ASME 

Section XI does not require volumetric 

examination of pipes less than NPS 4. A plantspecific destructive examination or a 

nondestructive examination (NDE) that permits 

inspection of the inside surfaces of the piping is to 

be conducted to ensure that cracking has not 

occurred and the component intended function will 

be maintained during the extended period of 

operation.

Yes,paramet

ers 

monitored/ 

inspected 

and detection 

of aging 

effects are to 

be evaluated

IV R-03 C1.1-i Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel; 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking (for 

stainless 

steel only), 

and thermal 

and 

mechanical 

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for BWR water andXI.M35, "One-Time 

Inspection of ASME Code Class 1 Small-bore 

Piping"

No
September 2005

E-83 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

loading
NUREG-1832

E-84 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-04 A1.1-b 

A1.2-a 

A1.2-b 

A1.3-a 

A1.3-d 

A1.4-b 

A1.5-b 

A1.6-a 

A2.1-b 

A2.2-c 

A2.3-c 

A2.4-a 

A2.5-d 

C1.1-b 

C1.1-d 

C1.1-e 

C1.1-h 

C1.2-a 

C1.3-d 

C2.1-a 

C2.1-b 

C2.2-a 

C2.2-b 

C2.2-c 

C2.3-a 

C2.4-a 

C2.5-a 

C2.5-d 

C2.5-e 

C2.5-f 

C2.5-q 

D1.1-h 

D2.1-c 

Piping, 

piping 

compone

nts, and 

piping 

elements; 

flanges; 

heater 

sheaths 

and 

sleeves; 

penetrati

ons; 

pressure 

housings; 

pump 

casing/co

ver; 

spray 

head; 

thermal 

sleeves; 

vessel 

shell 

heads 

and 

welds

Steel, 

stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

carbon 

steel with 

nickelalloy or 

stainless 

steel 

cladding, 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-85 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-04 A1.1-b 

A1.2-a 

A1.2-a 

A1.2-b 

A1.2-b 

A1.2-b 

A1.2-b 

A1.3-a 

A1.3-d 

A1.3-d 

A1.4-b 

A1.5-b 

A1.5-b 

A1.5-b 

A1.5-b 

A1.5-b 

A1.5-b 

A1.6-a

Reactor 

vessel 

compone

nts:Flang

es;Nozzl

es;Penetr

ations;Sa

fe 

ends;The

rmal 

sleeves;V

essel 

shells, 

heads 

and 

welds 

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-05 C2.1-e 

C2.2-g 

C2.5-i 

Class 1 

piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Monitoring and control of primary water chemistry 

in accordance with the guidelines in EPRI TR105714 (Rev. 3 or later revisions or update) 

minimize the potential of SCC, and material 

selection according to the NUREG-0313, Rev. 2 

guidelines of =0.035% C and =7.5% ferrite 

reduces susceptibility to SCC.For CASS 

components that do not meet either one of the 

above guidelines, a plant-specific aging 

management program is to be evaluated. The 

program is to include (a) adequate inspection 

methods to ensure detection of cracks, and 

(b) flaw evaluation methodology for CASS 

components that are susceptible to thermal aging 

embrittlement.

Yes, plantspecific
NUREG-1832

E-86 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-05 C2.1-e 

C2.2-g 

C2.5-i 

Class 1 

piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Monitoring and control of primary water chemistry 

in accordance with the guidelines in EPRI TR105714 (Rev. 3 or later) minimize the potential of 

SCC, and material selection according to NUREG0313, Rev. 2 guidelines of =0.035% C and =7.5% 

ferrite reduces susceptibility to SCC.For CASS 

components that do not meet either one of the 

above guidelines, a plant-specific aging 

management program is to be evaluated. The 

program is to include (a) adequate inspection 

methods to ensure detection of cracks, and 

(b) flaw evaluation methodology for CASS 

components that are susceptible to thermal aging 

embrittlement.

Yes, plantspecific

IV R-06 C2.5-k 

C2.5-s 

C2.5-m 

Pressuriz

er 

instrume

ntation 

penetrati

ons, 

heater 

sheaths 

and 

sleeves, 

heater 

bundle 

diaphram 

plate, 

and 

manways 

and 

flanges

Nickel 

alloy or 

nickel 

alloy 

cladding

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed
September 2005

E-87 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-06 C2.5-k 

C2.5-s 

C2.5-m 

Pressuriz

er 

instrume

ntation 

penetrati

ons, 

heater 

sheaths 

and 

sleeves, 

heater 

bundle 

diaphram 

plate, 

and 

manways 

and 

flanges

Nickel 

alloy or 

nickel 

alloy 

cladding

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD" for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water andFor nickel 

alloy, comply with applicable NRC Orders and 

provide a commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-07 C2.2-f 

C2.5-h 

D1.1-i 

C2.5-m 

Class 1 

piping, 

fittings 

and 

primary 

nozzles, 

safe 

ends, 

manways

, and 

flanges

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714

No

IV R-07 C2.2-f 

C2.5-h 

D1.1-i 

C2.5-m 

Class 1 

piping, 

fittings, 

primary 

nozzles, 

safe 

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No
NUREG-1832

E-88 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

ends, 

manways

, and 

flanges

IV R-08 C1.2-c 

C1.3-b 

C2.3-c 

C2.4-c 

Class 1 

pump 

casings, 

and valve 

bodies 

and 

bonnets

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components. For pump casings and valve 

bodies, screening for susceptibility to thermal 

aging is not necessary. The ASME Section XI 

inspection requirements are sufficient for 

managing the effects of loss of fracture toughness 

due to thermal aging embrittlement of CASS pump 

casings and valve bodies.Alternatively, the 

requirements of ASME Code Case N-481 for 

pump casings are sufficient for managing the 

effects of loss of fracture toughness due to 

thermal aging embrittlement of CASS pump 

casings.

No

IV R-08 C1.2-c 

C1.3-b 

C2.3-c 

C2.4-c 

Class 1 

pump 

casings, 

and valve 

bodies 

and 

bonnets

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components. For pump casings and valve 

bodies, screening for susceptibility to thermal 

aging is not necessary. The ASME Section XI 

inspection requirements are sufficient for 

managing the effects of loss of fracture toughness 

due to thermal aging embrittlement of CASS pump 

casings and valve bodies. Alternatively, the 

requirements of ASME Code Case N-481 for 

pump casings are sufficient for managing the 

effects of loss of fracture toughness due to 

thermal aging embrittlement of CASS pump 

casings.

No
September 2005

E-89 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-09 C2.3-b 

C2.4-b 

Class 1 

pump 

casings 

and valve 

bodies

CASS, 

carbon 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Monitoring and control of primary water chemistry 

in accordance with the guidelines in EPRI TR105714 (Rev. 3 or later revisions or update) 

minimize the potential of SCC, and material 

selection according to the NUREG-0313, Rev. 2 

guidelines of =0.035% C and =7.5% ferrite 

reduces susceptibility to SCC.For CASS 

components that do not meet either one of the 

above guidelines, an aging management program 

should conform to Chapter XI.M1, "ASME Section 

XI, Subsections IWB, IWC, and IWD."

No

IV R-09 C2.3-b 

C2.4-b 

Class 1 

pump 

casings 

and valve 

bodies

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No

IV R-10 D1.1-l Closure 

bolting

Steel Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

IV R-10 D1.1-l Closure 

bolting

Steel Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-90 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R100B1.4-a Jet pump 

assembli

esTherm

al 

sleeveInl

et 

headerRi

ser brace 

armHoldd

own 

beamsInl

et 

elbowMix

ing 

assembly

DiffuserC

astings

Nickel 

alloy, 

cast 

austenitic 

stainless 

steel, 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for jet 

pump assembly andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)

No

IV R100B1.4-a Jet pump 

assembli

esTherm

al 

sleeveInl

et 

headerRi

ser brace 

armHoldd

own 

beamsInl

et 

elbowMix

ing 

assembly

DiffuserC

astings

Nickel 

alloy; 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for jet 

pump assembly andChapter XI.M2, "Water 

Chemistry," for BWR water

No
September 2005

E-91 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R101B1.4-c Jet pump 

assembli

esCastin

gs

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R101B1.4-c Jet pump 

assembli

esCastin

gs

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R102B1.4-d Jet pump 

assembli

esJet 

pump 

sensing 

line

Stainless 

steel

Reactor 

coolant

Cracking/ 

cyclic loading

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

IV R102B1.4-d Jet pump 

assembli

esJet 

pump 

sensing 

line

Stainless 

steel

Reactor 

coolant

Cracking/ 

cyclic loading

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

IV R103B1.5-a Fuel 

supports 

and 

control 

rod drive 

assembli

esOrifice

d fuel 

support

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
NUREG-1832

E-92 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R103B1.5-a Fuel 

supports 

and 

control 

rod drive 

assembli

esOrifice

d fuel 

support

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R104B1.5-c Fuel 

supports 

and 

control 

rod drive 

assembli

esControl 

rod drive 

housing

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for lower 

plenum andChapter XI.M2, "Water Chemistry," for 

BWR water in BWRVIP-29 (EPRITR-103515)

No

IV R104B1.5-c Fuel 

supports 

and 

control 

rod drive 

assembli

esControl 

rod drive 

housing

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for lower 

plenum andChapter XI.M2, "Water Chemistry," for 

BWR water

No
September 2005

E-93 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R105B1.6-a Instrume

ntationInt

ermediat

e range 

monitor 

(IRM) dry 

tubesSou

rce range 

monitor

(SRM) 

dry 

tubesInco

re 

neutron 

flux 

monitor 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for lower 

plenum andChapter XI.M2, "Water Chemistry," for 

BWR water in BWRVIP-29 (EPRITR-103515)

No

IV R105B1.6-a Instrume

ntationInt

ermediat

e range 

monitor 

(IRM) dry 

tubesSou

rce range 

monitor 

(SRM) 

dry 

tubesInco

re 

neutron 

flux 

monitor 

guide 

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for lower 

plenum andChapter XI.M2, "Water Chemistry," for 

BWR water

No
NUREG-1832

E-94 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

tubes

IV R106B2.1-a Upper 

internals 

assembly

Upper 

support 

plateUpp

er core 

plateHold

-down 

spring

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-95 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R106B2.1-a Upper 

internals 

assembly

Upper 

support 

plateUpp

er core 

plateHold

-down 

spring

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R107B2.1-b Upper 

internals 

assembly

Upper 

support 

plateUpp

er core 

plateHold

-down 

spring

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R107B2.1-b Upper 

internals 

assembly

Upper 

support 

plateUpp

er core 

plateHold

-down 

spring

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-96 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R108B2.1-d Upper 

internals 

assembly

Holddown 

spring

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R108B2.1-d Upper 

internals 

assembly

Holddown 

spring

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R109B2.1-e Upper 

internals 

assembly

Upper 

support 

column

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-97 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R109B2.1-e Upper 

internals 

assembly

Upper 

support 

column

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-11 C2.3-e 

C2.4-e 

C2.5-n 

Closure 

bolting

Highstrength 

low-alloy 

steel, 

stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

IV R-11 C2.3-e 

C2.4-e 

C2.5-n 

Closure 

bolting

Highstrength 

low-alloy 

steel, 

stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-98 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R110B2.1-f Upper 

internals 

assembly

Upper 

support 

column

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R110B2.1-f Upper 

internals 

assembly

Upper 

support 

column

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R111B2.1-g Upper 

internals 

assembly

Upper 

support 

column(o

nly cast 

austenitic 

stainless 

steel 

portions)

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
September 2005

E-99 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R111B2.1-g Upper 

internals 

assembly

Upper 

support 

column(o

nly cast 

austenitic 

stainless 

steel 

portions)

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R112B2.1-i Upper 

internals 

assembly

Upper 

support 

column 

bolts 

Upper 

core 

plate 

alignment 

pinsFuel 

alignment 

pins

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-100 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R112B2.1-i Upper 

internals 

assembly

Upper 

support 

column 

bolts 

Upper 

core 

plate 

alignment 

pinsFuel 

alignment 

pins

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R113B2.1-j Upper 

internals 

assembly

Upper 

support 

column 

bolts 

Upper 

core 

plate 

alignment 

pinsFuel 

alignment 

pins

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-101 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R113B2.1-j Upper 

internals 

assembly

Upper 

support 

column 

bolts 

Upper 

core 

plate 

alignment 

pinsFuel 

alignment 

pins

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R114B2.1-k Upper 

internals 

assembly

Upper 

support 

column 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R114B2.1-k Upper 

internals 

assembly

Upper 

support 

column 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-102 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

internals to the NRC for review and approval.

IV R115B2.1-l Upper 

internals 

assembly

Upper 

core 

plate 

alignment 

pins

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R115B2.1-l Upper 

internals 

assembly

Upper 

core 

plate 

alignment 

pins

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-103 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R116B2.2-a RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management revi ew is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R116B2.2-a RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-104 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R117B2.2-b RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R117B2.2-b RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R118B2.2-d RCCA 

guide 

tube 

assembli

esRCCA 

guide

tube 

boltsRCC

A guide 

tube 

support 

pins

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-105 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R118B2.2-d RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tube 

boltsRCC

A guide 

tube 

support 

pins

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R119B2.2-e RCCA

guide 

tube 

assembli

esRCCA 

guide 

tube 

boltsRCC

A guide 

tube 

support 

pins

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R119B2.2-e RCCA 

guide 

tube 

assembli

esRCCA 

guide 

tube 

boltsRCC

A guide 

tube 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-106 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

support 

pins

internals to the NRC for review and approval.

IV R-12 C2.3-g 

C2.4-g 

C2.5-p 

Closure 

bolting

Highstrength 

low-alloy 

steel, 

stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No

IV R-12 C2.3-g 

C2.4-g 

C2.5-p 

Closure 

bolting

Low-alloy 

steel, 

stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-107 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R120B2.3-a Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R120B2.3-a Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee

commitment 

needs to be 

confirmed
NUREG-1832

E-108 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R121B2.3-b Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor int ernals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R121B2.3-b Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R122B2.3-c Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-109 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R122B2.3-c Core 

barrelCor

e barrel 

(CB)CB 

flange 

(upper)C

B outlet 

nozzlesT

hermal 

shield

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R123B2.4-a Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-110 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R123B2.4-a Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R124B2.4-b Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R124B2.4-b Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee

commitment 

needs to be 

confirmed
September 2005

E-111 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R125B2.4-c, 

B4.5-g

Core 

barrel 

assembly

Baffle/for

mer 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant 

and high 

fluence 

(>1 x 102

1 

n/cm2,E 

>0.1 MeV

)

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R125B2.4-c, 

B4.5-g

Core 

barrel 

assembly

Baffle/for

mer 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R126B2.4-d Baffle/for

mer 

assembly

Baffle/for

mer bolts

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-112 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R126B2.4-d Baffle/for

mer 

assembly

Baffle/for

mer bolts

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R127B2.4-e Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R127B2.4-e Baffle/for

mer 

assembly

Baffle 

and 

former 

plates

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-113 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R128B2.4-f Baffle/for

mer 

assembly

Baffle/for

mer bolts

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee

commitment 

to be 

confirmed

IV R128B2.4-f 

B4.5-i

Baffle/for

mer 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R129B2.4-h Baffle/for

mer 

assembly

Baffle/for

mer bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-114 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R129B2.4-h Baffle/for

mer 

assembly

Baffle/for

mer bolts

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-13 C2.6-a Pressuriz

er relief 

tankTank 

shell and 

headsFla

nges and 

nozzlesS

ame as 

above

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-13 C2.6-a Pressuriz

er relief 

tankTank 

shell and 

headsFla

nges and 

nozzles

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-115 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R130B2.5-a Lower 

internal 

assembly

Lower 

core 

plateRadi

al keys 

and 

clevis 

inserts

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R130B2.5-a Lower 

internal 

assembly

Lower 

core 

plateRadi

al keys 

and 

clevis 

inserts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-116 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R131B2.5-b Lower 

internal 

assembly

Lower 

core 

plateRadi

al keys 

and 

clevis 

inserts

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R131B2.5-b Lower 

internal 

assembly

Lower 

core 

plateRadi

al keys 

and 

clevis 

inserts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R132B2.5-c Lower 

internal 

assembly

Lower 

core 

plate

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-117 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R132B2.5-c Lower 

internal 

assembly

Lower 

core 

plate

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R133B2.5-e Lower 

internal 

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

s insert 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR-105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-118 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R133B2.5-e Lower 

internal 

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

s insert 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R134B2.5-f Lower 

internal

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

s insert 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R134B2.5-f Lower 

internal 

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-119 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

s insert 

bolts

internals to the NRC for review and approval.

IV R135B2.5-g Lower 

internal 

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

s insert 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R135B2.5-g Lower 

internal 

assembly

Fuel 

alignment 

pinsLowe

r support 

plate 

column 

boltsClevi

s insert 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-120 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R136B2.5-h Lower 

internal 

assembly

Lower 

support 

plate 

column 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R136B2.5-h Lower 

internal 

assembly

Lower 

support 

plate 

column 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R137B2.5-i Lower 

internal 

assembly

Clevis 

insert 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-121 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R137B2.5-i Lower 

internal 

assembly

Clevis 

insert 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R138B2.5-k Lower 

internal 

assembly

Lower 

support 

forging or 

castingLo

wer 

support 

plate 

columns

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714.

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-122 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R138B2.5-k Lower 

internal 

assembly

Lower 

support 

forging or 

castingLo

wer 

support 

plate 

columns

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R139B2.5-l Lower 

internal 

assembly

Lower 

support 

forging or 

castingLo

wer 

support 

plate 

columns

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R139B2.5-l Lower 

internal 

assembly

Lower 

support 

forging or 

castingLo

wer 

support 

plate 

columns

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-123 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-14 C2.6-c Pressuriz

er relief 

tankTank 

shell and 

headsFla

nges and 

nozzles

Stainless 

steel; 

steel with 

stainless 

steel

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 2 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR105714

No

IV R-14 C2.6-c Pressuriz

er relief 

tankTank 

shell and 

headsFla

nges and 

nozzles

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No

IV R140B2.5-m Lower 

internal 

assembly

Lower 

support 

castingLo

wer 

support 

plate 

columns

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R140B2.5-m Lower 

internal 

assembly

Lower 

support 

castingLo

wer 

support 

plate 

columns

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
NUREG-1832

E-124 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R141B2.5-n Lower 

internal 

assembly

Lower 

support 

forgingLo

wer 

support 

plate 

columns

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R141B2.5-n Lower 

internal 

assembly

Lower 

support 

forgingLo

wer 

support 

plate 

columns

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R142B2.5-o Lower 

internal 

assembly

Radial 

keys and 

clevis 

Inserts

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R142B2.5-o Lower 

internal 

assembly

Radial 

keys and 

clevis 

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-125 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

Inserts

IV R143B2.6-a Instrume

ntation 

support 

structure

sFlux 

thimble 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R143B2.6-a Instrume

ntation 

support 

structure

sFlux 

thimble 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-126 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R144B2.6-b Instrume

ntation 

support 

structure

sFlux 

thimble 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R144B2.6-b Instrume

ntation 

support 

structure

sFlux 

thimble 

guide 

tubes

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-127 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R145B2.6-c Instrume

ntation 

support 

structure

sFlux 

thimble 

tubes

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and recommendations of 

NRC I&E Bulletin 88-09 "Thimble Tube Thinning in 

Westinghouse Reactors," described below: In

response to I&E Bulletin 88-09, an inspection 

program, with technical justification, is to be 

established and is to include (a) an appropriate 

thimble tube wear acceptance criterion, e.g., 

percent through-wall loss, and includes 

allowances for inspection methodology and wear 

scar geometry uncertainty, (b) an appropriate 

inspection frequency, e.g., every refueling outage, 

and (c) inspection methodology such as eddy 

current technique that is capable of adequately 

detecting wear of the thimble tubes. In addition, 

corrective actions include isolation or replacement 

if a thimble tube fails to meet the above 

acceptance criteria. Inspection schedule is in 

accordance with the guidelines of I&E Bulletin 88-

09.

No

IV R145B2.6-c Instrume

ntation 

support 

structure

sFlux 

thimble 

tubes

Stainless 

steel with 

or without 

chrome 

plating

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M37, "Flux Thimble Tube Inspection" No
NUREG-1832

E-128 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R146B3.1-a Upper 

Internals 

Assembly

Upper 

guide 

structure 

support 

plateFuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

guide lug 

inserts

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R146B3.1-a Upper 

internals 

assembly

Upper 

guide 

structure 

support 

plateFuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

guide lug 

inserts

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-129 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R147B3.1-b Upper 

Internals 

Assembly

Upper 

guide 

structure 

support 

plateFuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

guide lug 

inserts

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R147B3.1-b Upper 

internals 

assembly

Upper 

guide 

structure 

support 

plateFuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

guide lug 

inserts

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-130 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R148B3.1-c Upper 

Internals 

Assembly

Fuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

their 

lugsHolddown ring

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R148B3.1-c Upper 

internals 

assembly

Fuel 

alignment 

plateFuel 

alignment 

plate 

guide 

lugs and 

their 

lugsHolddown ring

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-131 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R149B3.2-a CEA 

shroud 

assembli

es

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R149B3.2-a CEA 

shroud 

assembli

es

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-132 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-15 C1.4-a Isolation 

condense

r tube 

side 

compone

nts

Stainless 

steel; 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)The AMP in Chapter XI.M1 is to 

be augmented to detect cracking due to stress 

corrosion cracking and cyclic loading or loss of 

material due to pitting and crevice corrosion, and 

verification of the effectiveness of the program is 

necessary to ensure that significant degradation is 

not occurring and the component intended 

function will be maintained during the extended 

period of operation. An acceptable verification 

program is to include temperature and 

radioactivity monitoring of the shell side water, and 

eddy current testing of tubes.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R-15 C1.4-a Isolation 

condense

r 

compone

nts

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 componentsand Chapter XI.M2, "Water 

Chemistry," for BWR water. The AMP in Chapter 

XI.M1 is to be augmented to detect cracking due 

to stress corrosion cracking and verification of the 

program's effectiveness is necessary to ensure 

that significant degradation is not occurring and 

the component intended function will be 

maintained during the extended period of 

operation. An acceptable verification program is to 

include temperature and radioactivity monitoring of 

the shell side water, and eddy current testing of 

tubes.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-133 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R150B3.2-b CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R150B3.2-b CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary water. No further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-134 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R151B3.2-c CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R151B3.2-c CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R152B3.2-d CEA 

shroud 

assembli

esCEA 

shroud 

extension 

shaft 

guides

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R152B3.2-d CEA 

shroud 

assembli

esCEA 

shroud 

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-135 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

extension 

shaft 

guides

IV R153B3.2-e CEA 

shroud 

assembli

es

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R153B3.2-e CEA 

shroud 

assembli

es

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R154B3.2-g CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-136 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R154B3.2-g CEA 

shroud 

assembli

esCEA 

shrouds 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R155B3.3-a Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-137 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R155B3.3-a Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R156B3.3-b Core 

support 

barrelCor

e support 

barrel 

upper 

flangeCor

e support 

barrel 

alignment 

keys

Stainless

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R156B3.3-b Core 

support 

barrelCor

e support 

barrel 

upper 

flangeCor

e support 

barrel 

alignment 

keys

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
NUREG-1832

E-138 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R157B3.3-a Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R157B3.3-a Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R158B3.3-b Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-139 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R158B3.3-b Core 

support 

barrelCor

e support 

barrel 

upper 

flange

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R159B3.4-a Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core 

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-140 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R159B3.4-a Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core 

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-16 C1.4-b Isolation 

condense

r tube 

side 

compone

nts

Stainless 

steel; 

steel

Reactor 

coolant

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)The AMP in Chapter XI.M1 is to 

be augmented to detect cracking due to stress 

corrosion cracking and cyclic loading or loss of 

material due to pitting and crevice corrosion, and 

verification of the effectiveness of the program is 

necessary to ensure that significant degradation is 

not occurring and the component intended 

function will be maintained during the extended 

period of operation. An acceptable verification 

program is to include temperature and 

radioactivity monitoring of the shell side water, and 

eddy current testing of tubes.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R-16 C1.4-b Isolation 

condense

r 

compone

nts

Stainless 

steel; 

steel

Reactor 

coolant

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-141 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R160B3.4-b Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core 

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R160B3.4-b Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-142 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R161B3.4-c Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core 

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R161B3.4-c Core 

shroud 

assembly

Core 

shroud 

tie rods 

(core 

support 

plate 

attached 

by welds 

in later 

plants)

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-143 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R162B3.4-e Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R162B3.4-e Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-144 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R163B3.4-f Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R163B3.4-f Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R164B3.4-g Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-145 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R164B3.4-g Core 

shroud 

assembly

Core 

shroud 

assembly 

bolts 

(later 

plants 

are 

welded)

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R165B3.4-h Core 

shroud 

assembly

Core 

shroud 

assembly 

boltsCore 

shroud 

tie rods

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R165B3.4-h Core 

shroud 

assembly

Core 

shroud 

assembly 

boltsCore 

shroud 

tie rods

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-146 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R166B3.5-a Lower 

internal 

assembly

Core 

support 

plateLow

er 

support 

structure 

beam 

assembli

esCore 

support 

columnC

ore 

support 

barrel 

snubber 

assembli

es

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R166B3.5-a Lower 

internal 

assembly

Core 

support 

plateLow

er 

support 

structure 

beam 

assembli

esCore 

support 

columnC

ore 

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-147 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

support 

barrel 

snubber 

assembli

es

IV R167B3.5-b Lower 

internal 

Assembly

Fuel 

alignment 

pinsCore 

support 

column 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-148 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R167B3.5-b Lower 

internal 

Assembly

Fuel 

alignment 

pinsCore 

support 

column 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R168B3.5-c Lower 

internal 

assembly

Core 

support 

plateFuel 

alignment 

pinsLowe

r support 

structure 

beam 

assembli

esCore 

support 

column 

bolts 

Core 

support 

barrel 

snubber 

assembli

es

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-149 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R168B3.5-c Lower 

internal 

assembly

Core 

support 

plateFuel 

alignment 

pinsLowe

r support 

structure 

beam 

assembli

esCore 

support 

column 

bolts 

Core 

support 

barrel 

snubber 

assembli

es

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-150 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R169B3.5-d Lower 

internal 

assembly

Core 

support 

plateFuel 

alignment 

pinsLowe

r support 

structure 

beam 

assembli

esCore 

support 

column 

bolts 

Core 

support 

barrel 

snubber 

assembli

es

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-151 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R169B3.5-d Lower 

internal 

assembly

Core 

support 

plateFuel 

alignment 

pinsLowe

r support 

structure 

beam 

assembli

esCore 

support 

column 

bolts 

Core 

support 

barrel 

snubber 

assembli

es

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-152 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-17 A2.1-a 

A2.5-e 

A2.8-b 

C2.1-d 

C2.2-d 

C2.3-f 

C2.4-f 

C2.5-b 

C2.5-o 

C2.5-u 

C2.6-b 

D1.1-g 

D1.1-k 

D2.1-b 

D2.1-j 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

IV R-17 A2.1-a 

A2.5-e 

A2.8-b 

C2.1-d 

C2.2-d 

C2.3-f 

C2.4-f 

C2.5-b 

C2.5-o 

C2.5-u 

C2.6-b 

D1.1-g 

D1.1-k 

D2.1-b 

D2.1-j 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-153 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R170B3.5-e Lower 

internal 

assembly

Fuel 

alignment 

pinsCore 

support 

barrel 

snubber 

assembli

es

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R170B3.5-e Lower 

internal 

assembly

Fuel 

alignment 

pinsCore 

support 

barrel 

snubber 

assembli

es

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R171B3.5-f Lower 

internal 

assembly

Core 

support 

column

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R171B3.5-f Lower 

internal 

assembly

Core 

support 

column

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
NUREG-1832

E-154 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

flux embrittlement

IV R172B4.1-a Plenum 

cover 

and 

plenum 

cylinderPl

enum 

cover 

assembly

Plenum 

cylinderR

einforcing 

plates

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R172B4.1-a Plenum 

cover 

and 

plenum 

cylinderPl

enum 

cover 

assembly

Plenum 

cylinderR

einforcing 

plates

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-155 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R173B4.1-b Plenum 

cover 

and 

plenum 

cylinderT

op 

flange-tocover 

bolts 

Bottom 

flange-toupper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R173B4.1-b Plenum 

cover 

and 

plenum 

cylinderT

op 

flange-tocover 

bolts 

Bottom 

flange-toupper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-156 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R174B4.1-c Plenum 

cover 

and 

plenum 

cylinderPl

enum 

cover 

assembly 

Plenum 

cylinderR

einforcing 

platesTo

p flangeto-cover 

bolts 

Bottom 

flange-toupper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R174B4.1-c Plenum 

cover 

and 

plenum 

cylinderPl

enum 

cover 

assembly 

Plenum

cylinderR

einforcing 

platesTo

p flangeto-cover 

bolts 

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-157 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

Bottom 

flange-toupper 

grid 

screws

IV R175B4.2-a Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

pads

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-158 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R175B4.2-a Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

pads

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R176B4.2-b Upper 

grid 

assembly

Rib- toring 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment

to be 

confirmed
September 2005

E-159 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R176B4.2-b Upper 

grid 

assembly

Rib- toring 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R177B4.2-c Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

padsRibto-ring 

screws

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-160 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R177B4.2-c Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

padsRibto-ring 

screws

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R178B4.2-e Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

padsRibto-ring 

screws

Stainless 

steel

Reactor

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-161 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R178B4.2-e Upper 

grid 

assembly

Upper 

grid rib 

sectionU

pper grid 

ring 

forgingFu

el 

assembly 

support 

padsPlen

um rib 

padsRibto-ring 

screws

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R179B4.2-f Upper 

grid 

assembly

Fuel 

assembly 

support 

pads 

Plenum 

rib pads

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R179B4.2-f Upper

grid 

assembly

Fuel 

assembly 

support 

pads 

Plenum 

rib pads

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
NUREG-1832

E-162 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-18 C2.3-d 

C2.4-d 

C2.5-t 

C2.5-w 

Piping 

and 

compone

nts 

external 

surfaces 

and 

bolting

Stainless 

steel; 

steel

System 

temperat

ure up to 

340°C 

(644°F)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation.

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-18 C2.3-d 

C2.4-d 

C2.5-t 

C2.5-w 

Piping 

and 

compone

nts 

external 

surfaces 

and 

bolting

Stainless 

steel; 

steel

System 

temperat

ure up to 

340°C 

(644°F)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R180B4.3-a Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

pipe and 

flangeCR

GT 

spacer 

castingC

RGT rod 

guide 

tubesCR

GT rod 

guide 

sectors

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-163 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R180B4.3-a Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

pipe and 

flangeCR

GT 

spacer 

castingC

RGT rod 

guide 

tubesCR

GT rod 

guide 

sectors

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R181B4.3-b Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

spacer 

screwsFl

ange-toupper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-164 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R181B4.3-b Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

spacer 

screwsFl

ange-toupper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R182B4.3-c Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

pipe and 

flangeCR

GT 

spacer 

castingC

RGT 

spacer 

screwsFl

ange-toupper 

grid 

screwsC

RGT rod 

guide 

tubesCR

GT rod 

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-165 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

guide 

sectors

IV R182B4.3-c Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

pipe and 

flangeCR

GT 

spacer 

castingC

RGT 

spacer 

screwsFl

ange-toupper 

grid 

screwsC

RGT rod 

guide 

tubesCR

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-166 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

GT rod 

guide 

sectors

IV R183B4.3-d Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT

spacer 

casting

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R183B4.3-d Control 

rod guide 

tube 

(CRGT) 

assembly

CRGT 

spacer 

casting

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
September 2005

E-167 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R184B4.3-e Control 

rod guide 

tube 

(CRGT) 

assembly

Flangeto-upper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R184B4.3-e Control 

rod guide 

tube 

(CRGT) 

assembly

Flangeto-upper 

grid 

screws

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R185B4.4-a Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)O

utlet and 

vent 

Stainless 

steel, PH 

stainless 

steel 

forging, 

CASS

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-168 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

valve 

(VV) 

nozzlesV

V body 

and 

retaining 

ring

IV R185B4.4-a Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)O

utlet and 

vent 

valve 

(VV) 

nozzlesV

V body 

and 

retaining 

ring

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation,

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-169 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R186B4.4-b Core 

support 

shield 

assembly

Core 

support 

shield-tocore 

barrel 

boltsVV 

assembly 

locking 

device

Stainless

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R186B4.4-b Core 

support 

shield 

assembly

Core 

support 

shield-tocore 

barrel 

boltsVV 

assembly 

locking 

device

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-170 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R187B4.4-c Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)Co

re 

support 

shield-tocore 

barrel 

boltsVV 

retaining 

ringVV 

assembly 

locking 

device

Stainless 

steel, 

nickel 

alloy, PH 

Stainless 

Steel 

forging

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R187B4.4-c Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)Co

re 

support 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-171 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

shield-tocore 

barrel 

boltsVV 

retaining 

ringVV 

assembly 

locking 

device

IV R188B4.4-d Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)Co

re 

support 

shield-tocore 

barrel 

boltsOutl

et and 

vent 

valve 

(VV) 

nozzles 

Stainless 

steel, 

nickel 

alloy, PH 

Stainless 

Steel 

forging

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-172 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VV 

assembly 

locking 

device

IV R188B4.4-d Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder 

(top and 

bottom 

flange)Co

re 

support 

shield-tocore 

barrel 

boltsOutl

et and 

vent 

valve 

(VV) 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-173 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nozzles 

VV 

assembly 

locking 

device

IV R189B4.4-e Reactor 

vessel 

internals 

compone

nts

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy, PH 

Stainless 

Steel 

forging

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R189Row was deleted since Shuffle Master 1-28.

IV R-19 C2.5-v Pressuriz

erIntegral 

support

Stainless 

steel; 

steel

Air with 

metal 

temperat

ure up to 

288°C 

(550°F)

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
NUREG-1832

E-174 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-19 C2.5-v Pressuriz

erIntegral 

support

Stainless 

steel; 

steel

Air with 

metal 

temperat

ure up to 

288°C 

(550°F)

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R190B4.4-f Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder(t

op 

flange)V

V 

assembly 

locking 

device

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R190B4.4-f Core 

support 

shield 

assembly

Core 

support 

shield 

cylinder(t

op 

flange)V

V 

assembly 

locking 

device

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-175 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R191B4.4-g Core 

support 

shield 

assembly

Outlet 

and vent 

valve 

nozzlesV

V body 

and 

retaining 

ring

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R191B4.4-g Core 

support 

shield 

assembly

Outlet 

and vent 

valve 

nozzlesV

V body 

and 

retaining 

ring

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R192B4.4-h Core 

support 

shield 

assembly

Core 

support 

shield-tocore 

barrel 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-176 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R192B4.4-h Core 

support 

shield 

assembly

Core 

support 

shield-tocore 

barrel 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R193B4.5-a Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Ba

ffle plates 

and 

formers

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-177 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R193B4.5-a Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Ba

ffle plates 

and 

formers

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R194B4.5-b Core 

barrel 

assembly

Lower 

internals 

assembly

-to-core 

barrel 

boltsCore 

barrel-tothermal 

shield 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-178 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R194B4.5-b Core 

barrel 

assembly

Lower 

internals 

assembly

-to-core 

barrel 

boltsCore 

barrel-tothermal 

shield 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R195B4.5-c Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Lo

wer 

internals 

assembly

-to- core 

barrel 

boltsCore 

barrel-tothermal 

shield 

boltsBaffl

e plates 

and 

formers

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-179 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R195B4.5-c Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Lo

wer 

internals 

assembly

-to- core 

barrel 

boltsCore 

barrel-tothermal 

shield 

boltsBaffl

e plates 

and 

formers

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R196B4.5-d Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Lo

wer 

internals 

assembly

-to- core 

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-180 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

barrel 

boltsCore 

barrel-tothermal 

shield 

boltsBaffl

e plates 

and 

formers

IV R196B4.5-d Core 

barrel 

assembly

Core 

barrel 

cylinder 

(top and 

bottom 

flange)Lo

wer 

internals 

assembly

-to- core 

barrel 

boltsCore 

barrel-tothermal 

shield 

boltsBaffl

e plates 

and 

formers

Stainless 

steel; 

nickel

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-181 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R197B4.5-e Core 

barrel 

assembly

Lower 

internals 

assembly

-to-core 

barrel 

boltsCore 

barrel-tothermal 

shield 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R197B4.5-e Core 

barrel 

assembly

Lower 

internals 

assembly

-to-core 

barrel 

boltsCore 

barrel-tothermal 

shield 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-182 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R199B4.5-h Core 

barrel 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R199B4.5-h Core 

barrel 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-20 C1.1-f 

C1.2-b 

C1.3-c 

Piping, 

piping 

compone

nts, and 

piping 

elements 

greater 

than or 

equal to 

4 NPS

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No
September 2005

E-183 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-20 C1.1-f 

C1.2-b 

C1.3-c 

Piping, 

piping 

compone

nts, and 

piping 

elements 

greater 

than or 

equal to 

4 NPS

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water

No

IV R200B4.5-i Core 

barrel 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R200Row was deleted since Shuffle Master 1-28.

IV R201B4.5-j Core 

barrel 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-184 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R201B4.5-j Core 

barrel 

assembly

Baffle/for

mer bolts 

and 

screws

Stainless 

steel

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R202B4.6-a Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

flow dist. 

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsG

uide 

blocksSh

ock 

padsSup

port post 

pipesInco

Stainless 

steel, 

cast 

austenitic 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-185 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

re guide 

tube 

spider 

castings

IV R202B4.6-a Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

flow dist. 

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsG

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-186 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

uide 

blocksSh

ock 

padsSup

port post 

pipesInco

re guide 

tube 

spider 

castings

IV R203B4.6-b Lower 

grid 

assembly

Lower 

grid ribto-shell 

forging 

screwsLo

wer 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

and 

boltsSho

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-187 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

ck pads 

and bolts

IV R203B4.6-b Lower 

grid 

assembly

Lower 

grid ribto-shell 

forging 

screwsLo

wer 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

boltsSho

ck pads 

bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
NUREG-1832

E-188 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R204B4.6-c Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

rib-toshell 

forging 

screwsLo

wer grid 

flow dist.

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsL

ower 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

and 

boltsSho

ck pads 

and 

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-189 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

boltsSup

port post 

pipesInco

re guide 

tube 

spider 

castings
NUREG-1832

E-190 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R204B4.6-c Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

rib-toshell 

forging 

screwsLo

wer grid 

flow dist. 

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsL

ower 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

and 

boltsSho

ck pads 

and 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-191 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

boltsSup

port post 

pipesInco

re guide 

tube 

spider 

castings
NUREG-1832

E-192 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R205B4.6-d Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

rib-toshell 

forging 

screwsLo

wer grid 

flow dist. 

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsL

ower 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

and 

boltsSho

ck pads 

and 

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-193 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

boltsSup

port post 

pipes
NUREG-1832

E-194 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R205B4.6-d Lower 

grid 

assembly

Lower 

grid rib 

sectionFu

el 

assembly 

support 

padsLow

er grid 

rib-toshell 

forging 

screwsLo

wer grid 

flow dist. 

plateOrifi

ce 

plugsLow

er grid 

and shell 

forgingsL

ower 

internals 

assembly

-tothermal 

shield 

boltsGuid

e blocks 

and 

boltsSho

ck pads 

and 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-195 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

boltsSup

port post 

pipes

IV R206B4.6-e Lower 

grid 

assembly

Incore 

guide 

tube 

spider 

castings

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No
NUREG-1832

E-196 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R206B4.6-e Lower 

grid 

assembly

Incore 

guide 

tube 

spider 

castings

Cast 

austenitic 

stainless

steel

Reactor 

coolant 

>250°C 

(>482°F) 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

thermal aging 

and neutron 

irradiation 

embrittlement

Chapter XI.M13, "Thermal Aging and Neutron 

Irradiation Embrittlement of Cast Austenitic 

Stainless Steel (CASS)"

No

IV R207B4.6-g Lower 

grid 

assembly

Lower 

grid ribto-shell 

forging 

screwsLo

wer 

internals 

assembly

-tothermal 

shield 

bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R207B4.6-g Lower 

grid 

assembly

Lower 

grid ribto-shell 

forging 

screwsLo

wer 

internals 

assembly

-toStainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-197 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

thermal 

shield 

bolts

IV R208B4.6-h Lower 

grid 

assembly

Fuel 

assembly 

support 

pads 

Guide 

blocks

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R208B4.6-h Lower 

grid 

assembly

Fuel 

assembly 

support 

pads 

Guide 

blocks

Stainless 

steel

Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
NUREG-1832

E-198 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R209B4.7-a Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeInc

ore guide 

support 

plateCla

mping 

ring

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R209B4.7-a Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeInc

ore guide 

support 

plateCla

mping 

ring

Stainless 

steel

Reactor

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-21 C1.1-f Piping, 

piping 

compone

nts, and 

piping 

elements 

greater 

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No
September 2005

E-199 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

than or 

equal to 

4 NPS

cracking

IV R-21 C1.1-f Piping, 

piping 

compone

nts, and 

piping 

elements 

greater 

than or 

equal to 

4 NPS

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water

No

IV R210B4.7-b Flow 

distributo

r 

assembly

Shell 

forgingto-flow 

distributo

r bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-200 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R210B4.7-b Flow 

distributo

r 

assembly

Shell 

forgingto-flow 

distributo

r bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R211B4.7-c Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeSh

ell 

forgingto-flow 

distributo

r 

boltsIncor

e guide 

support 

plateCla

mping 

ring

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
September 2005

E-201 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R211B4.7-c Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeSh

ell 

forgingto-flow 

distributo

r 

boltsIncor

e guide 

support 

plateCla

mping 

ring

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R212B4.7-d Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeSh

ell 

forgingto-flow 

distributo

r 

boltsIncor

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-202 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

e guide 

support 

plateCla

mping 

ring

IV R212B4.7-d Flow 

distributo

r 

assembly

Flow 

distributo

r head 

and 

flangeSh

ell 

forgingto-flow 

distributo

r 

boltsIncor

e guide 

support 

plateCla

mping 

ring

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-203 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R213B4.7-e Flow 

distributo

r 

assembly

Shell 

forgingto-flow 

distributo

r bolts

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R213B4.7-e Flow 

distributo

r 

assembly

Shell 

forgingto-flow 

distributo

r bolts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

preload/ 

stress 

relaxation

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R214B4.8-a Thermal 

shield

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water chemistry" for PWR 

primary water, as described in EPRI TR -105714. 

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed
NUREG-1832

E-204 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R214B4.8-a Thermal 

shield

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" for PWR 

primary waterNo further aging management 

review is necessary if the applicant provides a 

commitment in the FSAR supplement to (1) 

participate in the industry programs for 

investigating and managing aging effects on 

reactor internals; (2) evaluate and implement the 

results of the industry programs as applicable to 

the reactor internals; and (3) upon completion of 

these programs, but not less than 24 months 

before entering the period of extended operation, 

submit an inspection plan for reactor internals to 

the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R215B4.8-b Thermal 

shield

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/V

oid swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R215B4.8-b Thermal 

shield

Stainless 

steel

Reactor 

coolant

Changes in 

dimensions/ 

void swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed
September 2005

E-205 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R216B4.8-c Thermal 

shield

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

to be 

confirmed

IV R216B4.8-c Thermal 

shield

Stainless 

steel

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

, void 

swelling

No further aging management review is necessary 

if the applicant provides a commitment in the 

FSAR supplement to (1) participate in the industry 

programs for investigating and managing aging 

effects on reactor internals; (2) evaluate and 

implement the results of the industry programs as 

applicable to the reactor internals; and (3) upon 

completion of these programs, but not less than 

24 months before entering the period of extended 

operation, submit an inspection plan for reactor 

internals to the NRC for review and approval.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R217C2.5-r Pressuriz

er heater 

sheaths 

and 

sleeves, 

and 

heater 

bundle 

diaphrag

m plate

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714

No
NUREG-1832

E-206 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R217C2.5-r Pressuriz

er heater 

sheaths 

and 

sleeves, 

and 

heater 

bundle 

diaphrag

m plate

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No

IV R218D1.1-i Pressure 

boundary 

and 

structural

Primary 

nozzles, 

safe 

ends, 

and 

welds

Nickel 

alloy or 

nickel 

alloy 

cladding

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV R218Row was deleted since Shuffle Master 1-28.

IV R219Did not exist in Shuffle Master 1-28.
September 2005

E-207 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R219A2.1-b 

A2.2-c 

A2.2-c 

A2.3-c 

A2.3-c 

A2.3-c 

A2.4-a 

A2.4-a 

A2.4-a 

A2.5-d 

A2.5-d 

A2.5-d 

A2.5-d 

Reactor 

vessel 

compone

nts:Flang

es;Nozzl

es;Penetr

ations;Pr

essure 

housings;

Safe 

ends;The

rmal 

sleeves;V

essel 

shells, 

heads 

and 

welds

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-22 C1.1-f 

C1.3-c 

Piping, 

piping 

compone

nts, and 

piping 

elements 

greater 

than or 

equal to 

4 NPS

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No

IV R-22 Row was deleted since Shuffle Master 1-28.

IV R220Did not exist in Shuffle Master 1-28.
NUREG-1832

E-208 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R220C1.1-b 

C1.1-d 

C1.1-e 

C1.1-e 

C1.1-h 

C1.1-h 

C1.1-h 

C1.1-h 

C1.1-h 

C1.1-h 

C1.1-h 

C1.2-a 

C1.2-a 

C1.2-a 

C1.3-d 

C1.3-d 

C1.3-d 

Reactor 

coolant 

pressure 

boundary 

compone

nts:Pipin

g, piping 

compone

nts, and 

piping 

elements

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R221Did not exist in Shuffle Master 1-28.

IV R221D1.1-h Recircula

ting 

steam 

generator 

compone

nts:Flang

es; 

Penetrati

ons; 

Nozzles;

Safe 

ends, 

lower 

heads 

and 

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-209 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

welds

IV R222Did not exist in Shuffle Master 1-28.

IV R222D2.1-c Oncethrough 

steam 

generator 

compone

nts:Prima

ry side 

nozzlesS

afe ends 

and 

welds

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R223Did not exist in Shuffle Master 1-28.
NUREG-1832

E-210 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R223C2.1-a 

C2.1-a 

C2.1-b 

C2.1-b 

C2.2-a 

C2.2-a 

C2.2-a 

C2.2-a 

C2.2-b 

C2.2-b 

C2.2-c 

C2.3-a 

C2.3-a 

C2.4-a 

C2.4-a 

C2.5-a 

C2.5-d 

C2.5-d 

C2.5-e 

C2.5-f 

C2.5-f 

C2.5-f 

C2.5-q 

Reactor 

coolant 

pressure 

boundary 

compone

nts:Pipin

g, piping 

compone

nts, and 

piping 

elements;

Flanges;

Nozzles 

and safe 

ends;Pre

ssurizer 

vessel 

shell 

heads 

and 

welds;He

ater 

sheaths 

and 

sleeves;P

enetratio

ns; 

andTher

mal 

sleeves

Steel; 

stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R224Did not exist in Shuffle Master 1-28.
September 2005

E-211 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R224D2.1-e Steam 

generator 

compone

ntsShell 

assembly

Steel Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R225Did not exist in Shuffle Master 1-28.

IV R225C1.4-a Isolation 

condense

r 

compone

nts

Stainless 

steel; 

steel

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 componentsThe AMP in Chapter XI.M1 is 

to be augmented to detect cracking due to cyclic 

loading and verification of the program's 

effectiveness is necessary to ensure that 

significant degradation is not occurring and the 

component intended function will be maintained 

during the extended period of operation. An 

acceptable verification program is to include 

temperature and radioactivity monitoring of the 

shell side water, and eddy current testing of tubes.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R226Did not exist in Shuffle Master 1-28.

IV R226D2. Tubes Nickel

alloy

Secondar

y 

feedwate

r/ steam

Denting/ 

corrosion of 

carbon steel 

tube support 

plate

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water. 

No

IV R-23 C1.1-a 

C1.1-c 

C1.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Reactor 

coolant

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No
NUREG-1832

E-212 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-23 C1.1-a 

C1.1-c 

C1.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Reactor 

coolant

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

IV R-24 C2.5-j Pressuriz

erSpray 

head

Nickel 

alloy, 

cast 

austenitic 

stainless 

steel, 

stainless 

steel

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," andChapter 

XI.M32 "One-Time Inspection" or Chapter XI.M1, 

"ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD," andprovide a 

commitment in the FSAR supplement to submit a 

plant-specific AMP delineating commitments to 

Orders, Bulletins, or Generic Letters that inspect 

stipulated components for cracking of wetted 

surfaces. 

No, unless 

licensee 

commitments 

need to be 

confirmed

IV R-24 C2.5-j Pressuriz

erSpray 

head

Nickel 

alloy; 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," and Chapter 

XI.M32 "One-Time Inspection" andFor nickel alloy 

welded spray heads, comply with applicable NRC 

Orders and provide a commitment in the FSAR 

supplement to implement applicable (1) Bulletins 

and Generic Letters and (2) staff-accepted 

industry guidelines. 

No, unless 

licensee 

commitment 

needs to be 

confirmed

IV R-25 C2.5-c 

C2.5-g 

Pressuriz

er 

compone

nts

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

or 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed
September 2005

E-213 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-25 C2.5-c 

C2.5-g 

Pressuriz

er 

compone

nts

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

or 

stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD" for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water 

No

IV R-26 C1.2-d 

C1.3-e 

Pump 

and valve 

closure 

bolting

Steel System 

temperat

ure up to 

288°C 

(550°F)

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-26 C1.2-d 

C1.3-e 

Pump 

and valve 

closure 

bolting

Steel System 

temperat

ure up to 

288°C 

(550°F)

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-27 C1.2-e 

C1.3-f 

Pump 

and valve 

closure 

bolting

Highstrength 

low-alloy 

steel SA 

193 Gr. 

B7

System 

temperat

ure up to 

288°C 

(550°F)

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No

IV R-27 C1.2-e 

C1.3-f 

Pump 

and valve 

closure 

bolting

Low-alloy 

steel SA 

193 Gr. 

B7

System 

temperat

ure up to 

288°C 

(550°F)

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-214 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-28 C1.2-f 

C1.3-g 

Pump 

and valve 

closure 

bolting

Steel System 

temperat

ure up to 

288°C 

(550°F)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation; 

check Code limits for allowable cycles (less than 

7000 cycles) of thermal stress range. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-28 C1.2-f 

C1.3-g 

Pump 

and valve 

closure 

bolting

Steel System 

temperat

ure up to 

288°C 

(550°F)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation; 

check ASME Code limits for allowable cycles (less 

than 7000 cycles) of thermal stress range. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-29 C1.2-d 

C1.3-e 

Pump 

and valve 

seal 

flange 

closure 

bolting

Stainless 

steel; 

steel

Air with 

metal 

temperat

ure up to 

288°C 

(550°F)

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-29 C1.2-d 

C1.3-e 

Pump 

and valve 

seal 

flange 

closure 

bolting

Stainless 

steel; 

steel

System 

temperat

ure up to 

288°C 

(550°F)

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-30 C2.1-c Reactor 

coolant 

system 

piping 

and 

fittingsCo

ld legHot 

legSurge 

lineSpray 

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714

No
September 2005

E-215 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

line

IV R-30 C2.1-c Reactor 

coolant 

system 

piping 

and 

fittingsCo

ld legHot 

legSurge 

lineSpray 

line

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No

IV R-31 D2.1-l Secondar

y 

manways 

and 

handhole

s (cover 

only)

Steel Air with 

leaking 

secondar

y-side 

water 

and/or 

steam

Loss of 

material/ 

erosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 2 components

No

IV R-31 D2.1-l Secondar

y 

manways 

and 

handhole

s (cover 

only)

Steel Air with 

leaking 

secondar

y-side 

water 

and/or 

steam

Loss of 

material/ 

erosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 2 components

No

IV R-32 D1.1-f 

D2.1-k 

Steam 

generator 

closure 

bolting

Steel System 

temperat

ure up to 

340°C 

(644°F)

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-216 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-32 D1.1-f 

D2.1-k 

Steam 

generator 

closure 

bolting

Steel System 

temperat

ure up to 

340°C 

(644°F)

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening

Chapter XI.M18, "Bolting Integrity" No

IV R-33 D1.1-a 

D1.1-b 

D2.1-d 

D2.1-g 

Steam 

generator 

compone

nts

Steel Secondar

y 

feedwate

r/ steam

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-33 D1.1-a 

D1.1-b 

D2.1-d 

D2.1-g 

Steam 

generator 

compone

ntsTop 

head;Ste

am 

nozzle 

and safe 

end;Uppe

r and 

lower 

shell;FW 

and AFW 

nozzle 

and safe 

end;FW 

impingem

ent plate 

and

support

Steel Secondar

y 

feedwate

r/ steam

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-217 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-34 D1.1-c 

D2.1-e 

Steam 

generator 

shell 

assembly 

(for 

OTSG), 

upper 

and lower 

shell, and 

transition 

cone (for 

recirculati

ng steam 

generator

)

Steel Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 2 components andChapter XI.M2, "Water 

Chemistry," for PWR secondary water in EPRI TR102134As noted in NRC Information Notice IN 90-

04, general and pitting corrosion of the shell 

exists, the AMP guidelines in Chapter XI.M1 may 

not be sufficient to detect general and pitting 

corrosion, and additional inspection procedures 

are to be developed.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R-34 D1.1-c Steam 

generator 

compone

ntsUpper 

and lower 

shell, and 

transition 

cone

Steel Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 2 components andChapter XI.M2, "Water 

Chemistry," for PWR secondary water. As noted in 

NRC IN 90-04, if general and pitting corrosion of 

the shell is known to exist, the AMP guidelines in 

Chapter XI.M1 may not be sufficient to detect 

general and pitting corrosion (and the resulting 

corrosion-fatigue cracking), and additional 

inspection procedures are to be developed. This 

issue is limited to Westinghouse Model 44 and 51 

Steam Generators where a high stress region 

exists at the shell to transition cone weld.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-218 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-35 D2.1-a Steam 

generator 

compone

ntsUpper 

and lower 

headsTu

be sheets

Steel with 

stainless 

steel or 

nickelalloy 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV R-35 D2.1-a Primary 

side 

compone

ntsUpper 

and lower 

headsTu

be sheets 

and tubeto-tube 

sheet 

welds

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water andFor nickel 

alloy, comply with applicable NRC Orders and 

provide a commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-36 D2.1-i Steam 

generator 

compone

ntsSuch 

as, 

secondar

y side 

nozzles 

(vent, 

drain, 

and 

instrume

ntation)

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," andChapter 

XI.M32 "One-Time Inspection" or Chapter XI.M1, 

"ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD." 

No
September 2005

E-219 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-36 D2.1-i Steam 

generator 

compone

ntsSuch 

as 

secondar

y side 

nozzles 

(vent, 

drain, 

and 

instrume

ntation)

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry" andChapter 

XI.M32 "One-Time Inspection" or Chapter XI.M1, 

"ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD." 

No

IV R-37 D1.1-d Pressure 

boundary 

and 

structural

Steam 

nozzle 

and safe 

endFW 

nozzle 

and safe 

end

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

IV R-37 D1.1-d Pressure 

boundary 

and 

structural

Steam 

nozzle 

and safe 

endFW 

nozzle 

and safe 

end

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No
NUREG-1832

E-220 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-38 D2.1-f Pressure 

boundary 

and 

structural

FW and 

AFW 

nozzles 

and safe 

endsStea

m 

nozzles 

and safe 

ends

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

IV R-38 D2.1-f Steam 

generator 

compone

ntsFW 

and AFW 

nozzles 

and safe 

endsStea

m 

nozzles 

and safe 

ends

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

IV R-39 D1.1-e Steam 

generator 

feedwate

r 

impingem

ent plate 

and 

support

Steel Secondar

y 

feedwate

r

Loss of 

material/ 

erosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-221 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-39 D1.1-e Steam 

generator 

feedwate

r 

impingem

ent plate 

and 

support

Steel Secondar

y 

feedwate

r

Loss of 

material/ 

erosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

IV R-40 D1.2-i 

D1.2-j 

D2.2-f 

D2.2-g 

Tube 

plugs

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR primary water in EPRI TR -105714.

No

IV R-40 D1.2-i 

D1.2-j 

D2.2-f 

D2.2-g 

Tube 

plugs

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR primary water

No

IV R-41 D1.2-h Tube 

support 

lattice 

bars

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Applicant must provide a commitment in the FSAR 

supplement to submit, for NRC review and 

approval, an inspection plan for tube support 

lattice bars as based upon staff approved NEI 97-

06 guidelines, or other alternative regulatory basis 

for steam generator degradation management, at 

least 24 months prior to the extended period.

No, but 

licensee 

commitment 

to be 

confirmed

IV R-41 D1.2-h Steam 

generator 

structural

Tube 

support 

lattice 

bars

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No
NUREG-1832

E-222 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-42 D1.2-k Tube 

support 

plates

Steel Secondar

y 

feedwate

r/ steam

Ligament 

cracking/ 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV R-42 D1.2-k 

D2. 

Steam 

generator 

structural

Tube 

support 

plates

Steel Secondar

y 

feedwate

r/ steam

Ligament 

cracking/ 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV R-43 D1.2-g Tubes Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Denting/ 

corrosion of 

carbon steel 

tube support 

plate

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134.For 

plants that could experience denting at the upper 

support plates, the applicant should evaluate 

potential for rapidly propagating cracks and then 

develop and take corrective actions consistent 

with Bulletin 88-02, "Rapidly Propagating Cracks 

in SG Tubes."

No

IV R-43 D1.2-g Tubes Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Denting/ 

corrosion of 

carbon steel 

tube support 

plate

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water.For plants that could 

experience denting at the upper support plates, 

the applicant should evaluate potential for rapidly 

propagating cracks and then develop and take 

corrective actions consistent with Bulletin 88-02, 

"Rapidly Propagating Cracks in SG Tubes."

No

IV R-44 D1.2-a 

D2.2-a 

Tubes 

and 

sleeves

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR primary water in EPRI TR -105714.

No
September 2005

E-223 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-44 D1.2-a 

D2.2-a 

Tubes 

and 

sleeves

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR primary water

No

IV R-45 D1.2-d Tubes 

and 

sleeves

Nickel 

alloy

Reactor 

coolant 

and 

secondar

y 

feedwate

r/steam

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be performed for the period of extended operation, 

and, for Class 1 components, environmental 

effects on fatigue are to be addressed. See the 

Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of10 CFR 54.21(c)(1).

Yes,TLAA

IV R-45 Row was deleted since Shuffle Master 1-28.

IV R-46 D2.2-e Tubes 

and 

sleeves

Nickel 

alloy

Reactor 

coolant 

and 

secondar

y 

feedwate

r/steam

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Revi ew Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-46 D1.2-d 

D2.2-e 

Tubes 

and 

sleeves

Nickel 

alloy

Reactor 

coolant 

and 

secondar

y 

feedwate

r/steam

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-47 D1.2-b 

D2.2-b 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

outer 

diameter 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No
NUREG-1832

E-224 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-47 D1.2-b 

D2.2-b 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

outer 

diameter 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV R-48 D1.2-c 

D2.2-c 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

intergranular 

attack

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV R-48 D1.2-c 

D2.2-c 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

intergranular 

attack

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV R-49 D1.2-e 

D2.2-d 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

fretting and 

wear

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV R-49 D1.2-e 

D2.2-d 

Tubes 

and 

sleeves

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

fretting and 

wear

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV R-50 D1.2-f Tubes 

and 

sleeves 

(exposed 

to 

phosphat

e 

chemistry

)

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

wastage and 

pitting 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV R-50 D1.2-f Tubes 

and 

sleeves 

(exposed 

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

wastage and 

pitting 

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No
September 2005

E-225 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

to 

phosphat

e 

chemistry

)

corrosion

IV R-51 D1.3-a Upper 

assembly 

and 

separator

sFeedwat

er inlet 

ring and 

support

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

A plant-specific aging management program is to 

be evaluated. As noted in Combustion 

Engineering (CE) Information Notice (IN) 90-04 

and NRC IN 91-19 and LER 50-362/90-05-01, this 

form of degradation has been detected only in 

certain CE System 80 steam generators.

Yes, plantspecific

IV R-51 D1.3-a Upper 

assembly 

and 

separator

sFeedwat

er inlet 

ring and 

support

Steel Secondar

y 

feedwate

r/ steam

Wall thinning/ 

flowaccelerated 

corrosion

A plant-specific aging management program is to 

be evaluated. Reference NRC IN 91-19, "Steam 

Generator Feedwater Distribution Piping 

Damage." 

Yes, plantspecific

IV R-52 C1.1-g 

C2.1-f 

C2.2-e 

C2.5-l 

Class 1 

piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

IV R-52 C1.1-g 

C2.1-f 

C2.2-e 

C2.5-l 

Class 1 

piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No
NUREG-1832

E-226 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-53 B1.1-c 

B1.2-b 

B1.3-b 

B1.4-b 

B1.5-b 

B1.6-b 

B2.1-c 

B2.1-h 

B2.1-m 

B2.2-c 

B2.2-f 

B2.3-d 

B2.4-g 

B2.5-d 

B2.5-j 

B2.5-p 

Reactor 

vessel 

internals 

compone

nts

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-227 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-53 B1.1-c 

B1.2-b 

B1.3-b 

B1.4-b 

B1.5-b 

B1.6-b 

B2.1-c 

B2.1-h 

B2.1-m 

B2.2-c 

B2.2-f 

B2.3-d 

B2.4-g 

B2.5-d 

B2.5-j 

B2.5-p 

B3.2-f 

B3.4-d 

B3.5-g 

B4.1-d 

B4.2-d 

B4.3-f 

B4.4-e 

B4.5-f 

B4.6-f 

Reactor 

vessel 

internals 

compone

nts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-54 B3.2-f 

B3.4-d 

B3.5-g 

B4.1-d 

B4.2-d 

B4.3-f 

B4.5-f 

B4.6-f 

Reactor 

vessel 

internals 

compone

nts

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel

alloy

Reactor 

coolant

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-54 Row was deleted since Shuffle Master 1-28.
NUREG-1832

E-228 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-55 C1.1-i Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel; 

steel

Reactor 

coolant

Cracking/ 

thermal and 

mechanical 

loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 componentsInspection in accordance with 

ASME Section XI does not require volumetric 

examination of pipes less than NPS 4. A plantspecific destructive examination or a 

nondestructive examination (NDE) that permits 

inspection of the inside surfaces of the piping is to 

be conducted to ensure that cracking has not 

occurred and the component intended function will 

be maintained during the extended period of 

operation.The AMPs are to be augmented by 

verifying that service-induced weld cracking is not 

occurring in the small-bore piping less than NPS 

4, including pipe, fittings, and branch connections. 

See Chapter XI.M32, "One-Time Inspection" for an 

acceptable verification method.

Yes,paramet

ers 

monitored/ 

inspected 

and detection 

of aging 

effects are to 

be evaluated

IV R-55 Row was deleted since Shuffle Master 1-28.

IV R-56 C2.1-c Reactor 

coolant 

system 

piping 

and 

fittingsCo

ld legHot 

legSurge 

lineSpray 

line

Stainless

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R-56 C2.1-c Reactor 

coolant 

system 

piping 

and 

fittingsCo

ld legHot 

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No
September 2005

E-229 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

legSurge 

lineSpray 

line

IV R-57 C2.1-g 

C2.2-h 

Class 1 

piping, 

fittings 

and 

branch 

connectio

ns < NPS 

4

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Reactor 

coolant

Cracking/ 

thermal and 

mechanical 

loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 componentsInspection in accordance with 

ASME Section XI does not require volumetric 

examination of pipes less than NPS 4. A plantspecific destructive examination or a 

nondestructive examination (NDE) that permits 

inspection of the inside surfaces of the piping is to 

be conducted to ensure that cracking has not 

occurred and the component intended function will 

be maintained during the extended period of 

operation.The AMPs are to be augmented by 

verifying that service-induced weld cracking is not 

occurring in the small-bore piping less than NPS 

4, including pipe, fittings, and branch connections. 

See Chapter XI.M32, "One-Time Inspection" for an 

acceptable verification method.

Yes,paramet

ers 

monitored/ 

inspected 

and detection 

of aging 

effects are to 

be evaluated

IV R-57 Row was deleted since Shuffle Master 1-28.
NUREG-1832

E-230 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-58 C2.5-c 

C2.5-g 

Pressuriz

er 

compone

nts

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

or 

stainless 

steel

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714Cracks in the pressurizer cladding could 

propagate from cyclic loading into the ferrite base

metal and weld metal. However, because the weld 

metal between the surge nozzle and the vessel 

lower head is subjected to the maximum stress 

cycles and the area is periodically inspected as 

part of the ISI program, the existing AMP is 

adequate for managing the effect of pressurizer 

clad cracking.

No

IV R-58 C2.5-c 

C2.5-g 

Pressuriz

er 

compone

nts

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

or 

stainless 

steel

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary waterCracks in the 

pressurizer cladding could propagate from cyclic 

loading into the ferrite base metal and weld metal. 

However, because the weld metal between the 

surge nozzle and the vessel lower head is 

subjected to the maximum stress cycles and the 

area is periodically inspected as part of the ISI 

program, the existing AMP is adequate for 

managing the effect of pressurizer clad cracking.

No

IV R-59 A1.1-a Top head 

enclosure 

(without 

cladding)

Top 

headNoz

zles 

(vent, top 

head 

spray or 

Steel Reactor 

coolant

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 (EPRI 

TR-103515)

No
September 2005

E-231 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

RCIC, 

and 

spare)

IV R-59 A1.1-a Top head 

enclosure 

(without 

cladding)

Top 

headNoz

zles 

(vent, top 

head 

spray or 

RCIC, 

and 

spare)

Steel Reactor 

coolant

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

The AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV R-60 A1.1-c Top head 

enclosure

Closure 

studs and 

nuts

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

Ksi)

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M3, "Reactor Head Closure Studs" No
NUREG-1832

E-232 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-60 A1.1-c Top head 

enclosure

Closure 

studs and 

nuts

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

ksi)

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M3, "Reactor Head Closure Studs" No

IV R-61 A1.1-d Top head 

enclosure

Vessel 

flange 

leak 

detection 

line

Stainless 

steel, 

nickel 

alloy

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated because existing programs may not 

be capable of mitigating or detecting crack 

initiation and growth due to SCC in the vessel 

flange leak detection line.

Yes, plantspecific

IV R-61 A1.1-d Top head 

enclosure

Vessel 

flange 

leak 

detection 

line

Stainless 

steel; 

nickel 

alloy

Air with 

reactor 

coolant 

leakage 

(Internal)

orReacto

r Coolant 

Cracking/ 

stress

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated because existing programs may not 

be capable of mitigating or detecting crack 

initiation and growth due to SCC in the vessel 

flange leak detection line.

Yes, plantspecific
September 2005

E-233 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-62 A1.2-c Vessel 

shellInter

mediate 

beltline 

shellBeltli

ne welds

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time 

dependent aging mechanism to be evaluated for 

the period of extended operation for all ferritic 

materials that have a neutron fluence exceeding 

1017 n/cm2 (E >1 MeV) at the end of the license 

renewal term. Aspects of this evaluation may 

involve a TLAA. In accordance with approved 

BWRVIP-74, the TLAA is to evaluate the impact of 

neutron embrittlement on: (a) the adjusted 

reference temperature, the plant’s pressuretemperature limits, (b) the need for inservice 

inspection of circumferential welds, and (c) the 

Charpy upper shelf energy or the equivalent 

margins analyses performed in accordance with 

10 CFR Part 50, Appendix G. Additionally, the 

applicant is to monitor axial beltline weld 

embrittlement. One acceptable method is to 

determine that the mean RTNDT of the axial 

beltline welds at the end of the extended period of 

operation is less than the value specified by the 

staff in its May 7, 2000 letter. See the Standard 

Review Plan, Section 4.2 "Reactor Vessel Neutron 

Embrittlement" for acceptable methods for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA
NUREG-1832

E-234 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-62 A1.2-c Vessel 

shellInter

mediate 

beltline 

shellBeltli

ne welds

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time 

dependent aging mechanism to be evaluated for 

the period of extended operation for all ferritic 

materials that have a neutron fluence greater than 

1017 n/cm2 (E >1 MeV) at the end of the license 

renewal term. Aspects of this evaluation may 

involve a TLAA. In accordance with approved 

BWRVIP-74, the TLAA is to evaluate the impact of 

neutron embrittlement on: (a) the adjusted 

reference temperature values used for calculation 

of the plant’s pressure-temperature limits, (b) the 

need for inservice inspection of circumferential 

welds, and (c) the Charpy upper shelf energy 

or the equivalent margins analyses performed in 

accordance with 10 CFR Part 50, Appendix G. 

Additionally, the applicant is to monitor axial 

beltline weld embrittlement. One acceptable 

method is to determine that the mean RTNDT of 

the axial beltline welds at the end of the extended 

period of operation is less than the value specified 

by the staff in its March 7, 2000 letter (ADAMS 

ML031430372). See the Standard Review Plan, 

Section 4.2 "Reactor Vessel Neutron 

Embrittlement" for acceptable methods for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA

IV R-63 A1.2-d Vessel 

shellInter

mediate 

beltline 

shellBeltli

ne welds

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No
September 2005

E-235 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-63 A1.2-d Vessel 

shellInter

mediate 

beltline 

shellBeltli

ne welds

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No

IV R-64 A1.2-e Vessel 

shellAttac

hment 

welds

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M4, "BWR Vessel ID Attachment 

Welds," andChapter XI.M2, "Water Chemistry,"for 

BWR water in BWRVIP-29 (EPRI TR-103515)

No

IV R-64 A1.2-e Vessel 

shellAttac

hment 

welds

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M4, "BWR Vessel ID Attachment 

Welds," andChapter XI.M2, "Water Chemistry," for 

BWR water

No

IV R-65 A1.3-b NozzlesF

eedwater

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M5, "BWR Feedwater Nozzle" No

IV R-65 A1.3-b NozzlesF

eedwater

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M5, "BWR Feedwater Nozzle" No
NUREG-1832

E-236 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-66 A1.3-c NozzlesC

ontrol rod 

drive 

return 

line

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M6, "BWR Control Rod Drive Return 

Line Nozzle"

No

IV R-66 A1.3-c NozzlesC

ontrol rod 

drive 

return 

line

Steel 

(with or 

without 

stainless 

steel 

cladding)

Reactor 

coolant

Cracking/ 

cyclic loading

Chapter XI.M6, "BWR Control Rod Drive Return 

Line Nozzle"

No

IV R-67 A1.3-e NozzlesL

ow 

pressure 

coolant 

injection 

or RHR 

injection 

mode

Steel Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of extended operation for all ferritic 

materials that have a neutron fluence greater than 

1017 n/cm2 (E >1 MeV) at the end of the license 

renewal term. In accordance with approved 

BWRVIP-74, the TLAA is to evaluate the impact of 

neutron embrittlement on: (a) the adjusted 

reference temperature, the plant’s pressuretemperature limits, (b) the Charpy upper shelf 

energy, and (c) the equivalent margins analyses 

performed in accordance with 10 CFR Part 50, 

Appendix G. The applicant may choose to 

demonstrate that the materials of the nozzles are 

not controlling for the TLAA evaluations. See the 

Standard Review Plan, Section 4.2 "Reactor 

Vessel Neutron Embrittlement" for acceptable 

methods for meeting the requirements of 10 CFR 

54.21(c).

Yes,TLAA
September 2005

E-237 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-67 A1.3-e NozzlesL

ow 

pressure 

coolant 

injection 

or RHR 

injection 

mode

Steel Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of extended operation for all ferritic 

materials that have a neutron fluence greater than 

1E17 n/cm2 (E >1 MeV) at the end of the license 

renewal term. In accordance with approved 

BWRVIP-74, the TLAA is to evaluate the impact of 

neutron embrittlement on: (a) the adjusted 

reference temperature values used for calculation 

of the plant’s pressure-temperature limits, and (b) 

the need for inservice inspection of circumferential 

welds, and (c) the Charpy upper shelf energy 

or the equivalent margins analyses performed in 

accordance with 10 CFR Part 50, Appendix G 

The applicant may choose to demonstrate that the 

materials of the nozzles are not controlling for the 

TLAA evaluations. See the Standard Review Plan, 

Section 4.2 "Reactor Vessel Neutron 

Embrittlement" for acceptable methods for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA

IV R-68 A1.4-a Nozzle 

safe ends 

(and 

associate

d 

welds)Hi

gh 

pressure 

core 

sprayLow 

pressure 

core 

sprayCon

trol rod 

drive 

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No
NUREG-1832

E-238 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

return 

lineRecir

culating

waterLow 

pressure 

coolant 

injection 

or RHR 

injection 

mode

IV R-68 A1.4-a Nozzle 

safe ends 

(and 

associate

d 

welds)Hi

gh 

pressure 

core 

sprayLow 

pressure 

core 

sprayCon

trol rod 

drive 

return 

lineRecir

culating 

waterLow 

pressure 

coolant 

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water

No
September 2005

E-239 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

injection 

or RHR 

injection 

mode

IV R-69 A1.5-a Penetrati

onsContr

ol rod 

drive stub 

tubes 

Instrume

ntationJet 

pump 

instrume

ntStandb

y liquid 

controlFl

ux 

monitorD

rain line

Stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M8, "BWR Penetrations," andChapter 

XI.M2, "Water Chemistry," for BWR water in 

BWRVIP-29 (EPRI TR-103515)

No
NUREG-1832

E-240 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-69 A1.5-a Penetrati

onsContr

ol rod 

drive stub 

tubes 

Instrume

ntationJet 

pump 

instrume

ntStandb

y liquid 

controlFl

ux 

monitorD

rain line

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M8, "BWR Penetrations," andChapter 

XI.M2, "Water Chemistry," for BWR water

No

IV R-70 A1.7-a Support 

skirt and 

attachme

nt welds

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-70 A1.7-a 

A2.8-a

Pressure 

vessel 

support 

skirt and 

attachme

nt welds

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-241 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-71 A2.1-c Closure 

headStud 

assembly

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

Ksi)

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M3, "Reactor Head Closure Studs" No

IV R-71 A2.1-c Closure 

headStud 

assembly

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

ksi)

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M3, "Reactor Head Closure Studs" No

IV R-72 A2.1-d Closure 

headStud 

assembly

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

Ksi)

Air with 

reactor 

coolant 

leakage

Loss of 

material/ 

wear

Chapter XI.M3, "Reactor Head Closure Studs" No
NUREG-1832

E-242 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-72 A2.1-d Closure 

headStud 

assembly

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

ksi)

Air with 

reactor 

coolant 

leakage

Loss of 

material/ 

wear

Chapter XI.M3, "Reactor Head Closure Studs" No

IV R-73 A2.1-e Closure 

headStud 

assembly

Highstrength 

low alloy 

steelMaxi

mum 

tensile 

strength 

< 1172 

MPa 

(<170 

Ksi)

Air with 

reactor 

coolant 

leakage

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-73 A2.1-e Closure 

headStud 

assembly

Low alloy 

steel

Air with 

reactor 

coolant 

leakage

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-74 A2.1-f Closure 

headVes

sel flange 

leak 

detection 

line

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated because existing programs may not 

be capable of mitigating or detecting crack 

initiation and growth due to SCC in the vessel 

flange leak detection line.

Yes, plantspecific
September 2005

E-243 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-74 A2.1-f Closure 

headVes

sel flange 

leak 

detection 

line

Stainless 

steel

Air with 

reactor 

coolant 

leakage 

(Internal)

orReacto

r Coolant 

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated because existing programs may not 

be capable of mitigating or detecting crack 

initiation and growth due to SCC in the vessel 

flange leak detection line.

Yes, plantspecific

IV R-75 A2.2-a Control 

rod drive 

head 

penetrati

onNozzle 

and 

welds

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV R-75 A2.2-a Control 

rod drive 

head 

penetrati

onNozzle 

and 

welds

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water and Chapter 

XI.M11-A, "Nickel-Alloy Penetration Nozzles 

Welded to the Upper Reactor Vessel Closure 

Heads of Pressurized Water Reactors (PWRs 

Only)"

No

IV R-76 A2.2-b Control 

rod drive 

head 

penetrati

onPressu

re 

housing

Stainless 

steel, 

cast 

austenitic 

stainless 

steel, 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed
NUREG-1832

E-244 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-76 A2.2-b Control 

rod drive 

head 

penetrati

onPressu

re 

housing

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," andChapter 

XI.M1, "ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD" and,For nickel 

alloy, comply with applicable NRC Orders and 

provide a commitment in the FSAR supplement to 

submit a plant-specific AMP to implement 

applicable (1) Bulletins and Generic Letters and 

(2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-77 A2.2-d Control 

rod drive 

head 

penetrati

onPressu

re 

housing

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

IV R-77 A2.2-d Control 

rod drive 

head 

penetrati

onPressu

re 

housing

Cast 

austenitic 

stainless 

steel

Reactor 

coolant 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

IV R-78 A2.2-e Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

IV R-78 A2.2-e Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-245 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-79 A2.2-f Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-79 A2.2-f Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

material/ 

wear

Chapter XI.M18, "Bolting Integrity" No

IV R-80 A2.2-g Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No

IV R-80 A2.2-g Control 

rod drive 

head 

penetrati

onFlange 

bolting

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening 

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-246 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-81 A2.3-a NozzlesI

nletOutlet

Safety 

injection

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of license renewal for all ferritic materials 

that have a neutron fluence greater than 

1017 n/cm2 (E >1 MeV) at the end of the license 

renewal term. The TLAA is to evaluate the impact 

of neutron embrittlement on: (a) the RTPTS value 

based on the requirements in10 CFR 50.61, 

(b) the adjusted reference temperature, the plant’s 

pressure-temperature limits, (c) the Charpy upper 

shelf energy, and (d) the equivalent margins 

analyses performed in accordance with 10 CFR 

Part 50, Appendix G. The applicant may choose to 

demonstrate that the materials in the inlet, outlet, 

and safety injection nozzles are not controlling for 

the TLAA evaluations.

Yes,TLAA

IV R-81 A2.3-a NozzlesI

nletOutlet

Safety 

injection

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of extended operation for all ferritic 

materials that have a neutron fluence greater than 

1E17 n/cm2 (E >1 MeV) at the end of the license 

renewal term. The TLAA is to evaluate the impact 

of neutron embrittlement on: (a) the RTPTS value 

based on the requirements in 10 CFR 50.61, 

(b) the adjusted reference temperature values 

used for calculation of the plant’s pressuretemperature limits, and (c) the Charpy upper shelf 

energy or the equivalent margins analyses 

performed in accordance with 10 CFR Part 50, 

Appendix G requirements. The applicant may 

choose to demonstrate that the materials in the 

inlet, outlet, and safety injection nozzles are not 

controlling for the TLAA evaluations.

Yes,TLAA
September 2005

E-247 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-82 A2.3-b NozzlesI

nletOutlet

Safety 

injection

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No

IV R-82 A2.3-b NozzlesI

nletOutlet

Safety 

injection

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No

IV R-83 A2.4-b Nozzle 

safe ends 

and 

weldsInle

tOutletSa

fety 

injection

Stainless 

steel, 

cast 

austenitic 

stainless 

steel 

(nickel 

alloy 

welds 

and/or 

buttering)

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714.

No

IV R-83 A2.4-b Nozzle 

safe ends 

and 

welds:Inl

etOutletS

afety 

injection

Stainless 

steel; 

nickel 

alloy 

welds 

and/or 

buttering

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water

No
NUREG-1832

E-248 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-84 A2.5-a Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

uding 

beltline 

welds)

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of license renewal for all ferritic materials 

that have a neutron fluence of greater than 

1017 n/cm2 (E >1 MeV) at the end of the license 

renewal term. The TLAA is to evaluate the impact 

of neutron embrittlement on: (a) the RTPTS value 

based on the requirements in10 CFR 50.61, 

(b) the adjusted reference temperature, the plant’s 

pressure temperature limits, (c) the Charpy upper 

shelf energy, and (d) the equivalent margins 

analyses performed in accordance with 10 CFR 

Part 50, Appendix G. See the Standard Review 

Plan, Section 4.2 "Reactor Vessel Neutron 

Embrittlement" for acceptable methods for 

meeting the requirements of10 CFR 54.21(c).

Yes,TLAA

IV R-84 A2.5-a Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

uding 

beltline 

welds)

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Neutron irradiation embrittlement is a time-limited 

aging analysis (TLAA) to be evaluated for the 

period of extended operation for all ferritic 

materials that have a neutron fluence greater than 

1E17 n/cm2 (E >1 MeV) at the end of the license 

renewal term. The TLAA is to evaluate the impact 

of neutron embrittlement on: (a) the RTPTS value 

based on the requirements in 10 CFR 50.61, 

(b) the adjusted reference temperature values 

used for calculation of the plant’s pressuretemperature limits, and (c) the Charpy upper shelf 

energy or the equivalent margins analyses 

performed in accordance with 10 CFR Part 50, 

Appendix G requirements. See the Standard 

Review Plan, Section 4.2 "Reactor Vessel Neutron 

Embrittlement" for acceptable methods for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA
September 2005

E-249 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-85 A2.5-b Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

uding 

beltline 

welds)

SA508-

Cl 2 

forgings 

clad with 

stainless 

steel 

using a 

highheatinput 

welding 

process

Reactor 

coolant

Crack 

growth/ cyclic 

loading

Growth of intergranular separations (underclad 

cracks) in low-alloy steel forging heat affected 

zone under austenitic stainless steel cladding is a 

time-limited aging analysis (TLAA) to be evaluated 

for the period of extended operation for all the SA 

508-Cl 2 forgings where the cladding was 

deposited with a high heat input welding process. 

The methodology for evaluating an underclad flaw 

is in accordance with the current well-established 

flaw evaluation procedure and criterion in the 

ASME Section XI Code. See the Standard Review 

Plan, Section 4.7, "Other Plant-Specific TimeLimited Aging Analysis," for generic guidance for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA

IV R-85 A2.5-b Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

uding 

beltline 

welds)

SA508-

Cl 2 

forgings 

clad with 

stainless 

steel 

using a 

highheatinput 

welding 

process

Reactor 

coolant

Crack 

growth/ cyclic 

loading

Growth of intergranular separations (underclad 

cracks) in low-alloy steel forging heat affected 

zone under austenitic stainless steel cladding is a 

time-limited aging analysis (TLAA) to be evaluated 

for the period of extended operation for all the SA 

508-Cl 2 forgings where the cladding was 

deposited with a high heat input welding process. 

The methodology for evaluating an underclad flaw 

is in accordance with the current well-established 

flaw evaluation procedure and criterion in the 

ASME Section XI Code. See the Standard Review 

Plan, Section 4.7, "Other Plant-Specific TimeLimited Aging Analysis," for generic guidance for 

meeting the requirements of 10 CFR 54.21(c).

Yes,TLAA

IV R-86 A2.5-c Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No
NUREG-1832

E-250 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

uding 

beltline 

welds)

IV R-86 A2.5-c Vessel 

shellUpp

er 

shellInter

mediate 

and lower 

shell(incl

uding 

beltline 

welds)

Steel with 

stainless 

steel 

cladding

Reactor 

coolant 

and 

neutron 

flux

Loss of 

fracture 

toughness/ 

neutron 

irradiation 

embrittlement

Chapter XI.M31, "Reactor Vessel Surveillance" No

IV R-87 A2.5-f Vessel 

shellVess

el flange

Steel Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R-87 A2.5-f Vessel 

shellVess

el flange

Steel Reactor 

coolant

Loss of 

material/ 

wear

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components

No

IV R-88 A2.6-a Core 

support 

pads/cor

e guide 

lugs

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," andChapter 

XI.M32 "One-Time Inspection" or Chapter XI.M1, 

"ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD," andprovide a 

commitment in the FSAR supplement to submit a 

plant-specific AMP delineating commitments to

Orders, Bulletins, or Generic Letters that inspect 

stipulated components for cracking of wetted 

surfaces. 

No, unless 

licensee 

commitments 

need to be 

confirmed
September 2005

E-251 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-88 A2.6-a Core 

support 

pads/ 

core 

guide 

lugs

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," andChapter 

XI.M1, "ASME Section XI Inservice Inspection, 

Subsections IWB, IWC, and IWD" and,Comply 

with applicable NRC Orders and provide a 

commitment in the FSAR supplement to submit a 

plant-specific AMP to implement applicable (1) 

Bulletins and Generic Letters and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-89 A2.7-a Penetrati

onsInstru

ment 

tubes 

(bottom 

head)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV R-89 A2.7-a Penetrati

onsInstru

ment 

tubes 

(bottom 

head)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD" for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water andComply 

with applicable NRC Orders and provide a 

commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV R-90 A2.7-b Penetrati

onsHead 

vent pipe 

(top 

head)Inst

rument 

tubes 

(top 

head)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed
NUREG-1832

E-252 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-90 A2.7-b Penetrati

onsHead 

vent pipe 

(top 

head)Inst

rument 

tubes 

(top 

head)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water and Chapter 

XI.M11-A, "Nickel-Alloy Penetration Nozzles 

Welded to the Upper Reactor Vessel Closure 

Heads of Pressurized Water Reactors (PWRs 

Only)"

No

IV R-91 A2.8-a Pressure 

vessel 

supportS

kirt 

support

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

IV R-91 Row was deleted since Shuffle Master 1-28.

IV R-92 B1.1-a Core 

shroud 

(including 

repairs) 

and core 

plateCore 

shroud 

(upper, 

central, 

lower)

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core 

shroud andChapter XI.M2, "Water Chemistry" for 

BWR water in BWRVIP-29 (EPRITR-103515)

No
September 2005

E-253 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-92 B1.1-a Core 

shroud 

(including 

repairs) 

and core 

plateCore 

shroud 

(upper, 

central, 

lower)

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core 

shroud andChapter XI.M2, "Water Chemistry" for 

BWR water

No

IV R-93 B1.1-b Core 

shroud 

and core 

plateCore 

plateCore 

plate 

bolts 

(used in 

early 

BWRs)

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core 

plate andChapter XI.M2, "Water Chemistry" for 

BWR water in BWRVIP-29 (EPRITR-103515)

No
NUREG-1832

E-254 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-93 B1.1-b Core 

shroud 

and core 

plateCore 

plateCore 

plate 

bolts 

(used in 

early 

BWRs)

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core

plate andChapter XI.M2, "Water Chemistry" for 

BWR water

No

IV R-94 B1.1-d Core 

shroud 

and core 

plateAcc

ess hole 

cover(wel

ded 

covers)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 (EPRI 

TR-103515)Because cracking initiated in crevice 

regions is not amenable to visual inspection, for 

BWRs with a crevice in the access hole covers, an 

augmented inspection is to include ultrasonic 

testing (UT) or other demonstrated acceptable 

inspection of the access hole cover welds.

No
September 2005

E-255 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-94 B1.1-d Core 

shroud 

and core 

plateAcc

ess hole 

cover(wel

ded 

covers)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for BWR waterBecause cracking 

initiated in crevice regions is not amenable to 

visual inspection, for BWRs with a crevice in the 

access hole covers, an augmented inspection is to 

include ultrasonic testing (UT) or other 

demonstrated acceptable inspection of the access 

hole cover welds.

No

IV R-95 B1.1-e Core 

shroud 

and core 

plateAcc

ess hole 

cover(me

chanical 

covers)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)

No
NUREG-1832

E-256 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-95 B1.1-e Core 

shroud 

and core 

plateAcc

ess hole 

cover(me

chanical 

covers)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for BWR water

No

IV R-96 B1.1-f Core 

shroud 

(including 

repairs) 

and core 

plateShro

ud 

support 

structure 

(shroud 

support 

cylinder, 

shroud 

support 

plate, 

shroud 

support 

legs)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for 

shroud support andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)

No
September 2005

E-257 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-96 B1.1-f Core 

shroud 

(including 

repairs) 

and core 

plateShro

ud 

support 

structure 

(shroud 

support 

cylinder, 

shroud 

support 

plate, 

shroud 

support 

legs)

Nickel 

alloy

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for 

shroud support andChapter XI.M2, "Water 

Chemistry," for BWR water

No

IV R-97 B1.1-g Core 

shroud 

and core 

plate 

LPCI 

coupling

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for the 

LPCI coupling andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)

No
NUREG-1832

E-258 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-97 B1.1-g Core 

shroud 

and core 

plate 

LPCI 

coupling

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for the 

LPCI coupling andChapter XI.M2, "Water 

Chemistry," for BWR water

No

IV R-98 B1.2-a Top 

guide

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for top 

guide and Chapter XI.M2, "Water Chemistry," for 

BWR water in BWRVIP-29 (EPRI TR-103515)

No

IV R-98 B1.2-a Top 

guide

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationChapter XI.M9, "BWR Vessel Internals," for top 

guide and Chapter XI.M2, "Water Chemistry," for 

BWR water. Additionally, for top guides with 

neutron fluence exceeding the IASCC threshold 

(5E20, E>lMeV) prior to the period of extended 

operation, inspect five percent (5%) of the top 

guide locations using enhanced visual inspection 

technique, EVT-1 within six years after entering 

the period of extended operation. An additional 

No
September 2005

E-259 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

assisted 

stress 

corrosion 

cracking

5% of the top guide locations will be inspected 

within twelve years after entering the period of 

extended operation.Alternatively, if the neutron 

fluence for the limiting top guide location is 

projected to exceed the threshold for IASCC after 

entering the period of extended operation, inspect 

5% of the top guide locations (EVT-1) within six 

years after the date projected for exceeding the 

threshold. An additional 5% of the top guide 

locations will be inspected within twelve years 

after the date projected for exceeding the 

threshold.The top guide inspection locations are 

those that have high neutron fluences exceeding 

the IASCC threshold.The extent and frequency of 

examination of the top guide is similar to the 

examination of the control rod drive housing guide 

tube in BWRVIP-47.

IV R-99 B1.3-a Core 

spray 

lines and 

spargers

Core 

spray 

lines 

(headers)

Spray 

ringsSpra

y 

nozzlesT

hermal 

sleeves

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core 

spray internals andChapter XI.M2, "Water 

Chemistry," for BWR water in BWRVIP-29 

(EPRITR-103515)

No
NUREG-1832

E-260 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV R-99 B1.3-a Core 

spray 

lines and 

spargers

Core 

spray 

lines 

(headers)

Spray 

ringsSpra

y 

nozzlesT

hermal 

sleeves

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking, 

irradiationassisted 

stress 

corrosion 

cracking

Chapter XI.M9, "BWR Vessel Internals," for core 

spray internals andChapter XI.M2, "Water 

Chemistry," for BWR water

No

IV RP01E. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

IV RP01E. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

IV RP02E. Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

IV RP02Row was deleted since Shuffle Master 1-28.
September 2005

E-261 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP03E. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

IV RP03E. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

IV RP04E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

IV RP04E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

IV RP05E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

IV RP05E. Piping, 

piping 

compone

nts, and 

piping 

Stainless 

steel

Air with 

borated 

water 

leakage

None None No
NUREG-1832

E-262 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

IV RP06E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

IV RP06E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

IV RP07E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

IV RP07E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

IV RP10C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed Cycle Cooling Water 

System"

No
September 2005

E-263 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP10C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

IV RP11C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

IV RP11C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

IV RP12C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

IV RP12C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

IV RP13A2. Instrume

nt 

penetrati

onBottom

-mounted 

Stainless 

steel

Air with 

reactor 

coolant 

leakage

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-264 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

guide 

tube

IV RP13A2. Bottommounted 

guide 

tube

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

IV RP14D1. Steam 

generator

antivibration 

bars

Chrome 

plated 

Nickel 

alloy, 

stainless 

steel, 

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV RP14D1. Steam 

generator 

structural

Antivibration 

bars

Chrome 

plated 

steel; 

stainless 

steel; 

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV RP15D1. Steam 

generator

antivibration 

bars

Chrome 

plated 

Nickel 

alloy, 

stainless 

steel, 

Nickel 

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

crevice 

corrosion and 

fretting

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No
September 2005

E-265 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP15D1. Steam 

generator 

structural

Antivibration 

bars

Chrome 

plated 

steel; 

stainless 

steel; 

Nickel

alloy

Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

crevice 

corrosion and 

fretting

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV RP16D1. Steam 

generator 

tube 

bundle 

wrapper

Steel Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

erosion, 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water in EPRI TR -102134

No

IV RP16D1. Steam 

generator

Tube 

bundle 

wrapper

Steel Secondar

y 

feedwate

r/ steam

Loss of 

material/ 

erosion, 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M19, "Steam Generator Tubing 

Integrity" andChapter XI.M2, "Water Chemistry," 

for PWR secondary water

No

IV RP17D1. Steam 

Generato

rDivider 

Plate

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components andChapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR105714

No

IV RP17D1. Primary 

sideDivid

er Plate

Stainless 

steel

Reactor 

coolant

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

IV RP18B1. Steam 

Dryers

Stainless 

steel

Reactor 

coolant

Cracking/

flow-induced 

vibration

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-266 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP18B1. Steam 

Dryers

Stainless 

steel

Reactor 

coolant

Cracking/ 

flow-induced 

vibration

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

IV RP21D1. Steam 

Generato

rDivider 

Plate

Nickel 

alloy

Reactor 

coolant

Cracking/ 

Primary 

water stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed

IV RP21D1. Primary 

sideDivid

er Plate

Nickel 

alloy; 

steel with 

nickelalloy 

cladding

Reactor 

coolant

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

IV RP22C2. Pressuriz

er steam 

space 

nozzles 

and 

welds

Nickel 

alloy

Reactor 

coolant/ 

steam

Cracking/ 

Primary 

water stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry," for PWR primary water in EPRI TR -

105714 and, for Alloy 600, provide a commitment 

in the FSAR supplement to implement applicable 

(1) NRC Orders, Bulletins and Generic Letters 

associated with nickel alloys and (2) staffaccepted industry guidelines.

No, but 

licensee 

commitments 

to be 

confirmed
September 2005

E-267 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP22C2. Pressuriz

er surge 

and 

steam 

space 

nozzles, 

and 

welds

Nickel 

alloy

Reactor 

coolant/ 

steam

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD" for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry," for PWR primary water andComply 

with applicable NRC Orders and provide a 

commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

IV RP23Did not exist in Shuffle Master 1-28.

IV RP23C2. Piping, 

piping 

compone

nts, and 

piping 

elements; 

flanges; 

heater 

sheaths 

and 

sleeves; 

penetrati

ons; 

thermal 

sleeves; 

vessel 

shell 

heads 

and 

welds

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

IV RP24Did not exist in Shuffle Master 1-28.
NUREG-1832

E-268 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP24B2. B3. 

B4.

Reactor 

vessel 

internals 

compone

nts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

IV RP25Did not exist in Shuffle Master 1-28.

IV RP25A1. Reactor 

Vessel:Fl

anges, 

nozzles; 

penetrati

ons; safe 

ends; 

vessel 

shells, 

heads 

and 

welds

Stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

Coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV RP26Did not exist in Shuffle Master 1-28.

IV RP26B1. Reactor 

vessel 

internals 

compone

nts

Stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD," for 

Class 1 components and Chapter XI.M2, "Water 

Chemistry" for BWR water

No

IV RP27Did not exist in Shuffle Master 1-28.
September 2005

E-269 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP27C1. Reactor 

coolant 

pressure 

boundary 

compone

nts

Steel with 

stainless 

steel or 

nickel 

alloy 

cladding; 

stainless 

steel; 

nickel 

alloy

Reactor 

coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

IV RP28Did not exist in Shuffle Master 1-28.

IV RP28A2. Flanges; 

nozzles; 

penetrati

ons; 

pressure 

housings; 

safe 

ends; 

vessel 

shells, 

heads 

and 

welds

Stainless 

steel; 

steel with 

nickelalloy or 

stainless 

steel 

cladding; 

nickelalloy

Reactor 

Coolant

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

IV RP31Did not exist in Shuffle Master 1-28.
NUREG-1832

E-270 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

IV RP31C2. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Reactor 

coolant/ 

steam

Cracking/ 

primary water 

stress 

corrosion 

cracking

Chapter XI.M1, "ASME Section XI Inservice 

Inspection, Subsections IWB, IWC, and IWD" for 

Class 1 components, andChapter XI.M2, "Water 

Chemistry" for PWR primary water andComply 

with applicable NRC Orders and provide a 

commitment in the FSAR supplement to 

implement applicable (1) Bulletins and Generic 

Letters and (2) staff-accepted industry guidelines.

No, but 

licensee 

commitment 

needs to be 

confirmed

V E-01 D1.8-c Partially 

encased 

tanks 

with 

breached 

moisture 

barrier

Stainless 

steel

Untreate

d water 

or raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated for pitting and crevice corrosion of 

tank bottom because moisture and water can 

egress under the tank due to cracking of the 

perimeter seal from weathering.

Yes, plantspecific

V E-01 D1.8-c Partially 

encased 

tanks 

with 

breached 

moisture 

barrier

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated for pitting and crevice corrosion of 

tank bottom because moisture and water can 

egress under the tank due to cracking of the 

perimeter seal from weathering.

Yes, plantspecific

V E-02 E.2-a Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

V E-02 E.2-a Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general 

corrosion

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-271 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-03 E.2-b Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

V E-03 E.2-b Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

V E-04 D2.5-b Drywell 

and 

suppressi

on 

chamber 

spray 

system 

(internal 

surfaces)

:Flow 

orifice 

Spray 

nozzles

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general

corrosion and 

fouling

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-04 D2.5-b Drywell 

and 

suppressi

on 

chamber 

spray 

system 

(internal 

surfaces)

:Flow 

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general 

corrosion and 

fouling

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-272 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

orifice 

Spray 

nozzles

V E-06 B.1-b 

B.2-b 

Elastome

r seals

Elastome

rs

Air –

indoor 

uncontroll

ed

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-06 B.1-b 

B.2-b 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-07 D2.1-f Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air and 

steam

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

V E-07 D2.1-f Piping, 

piping

compone

nts, and 

piping 

elements

Steel Steam Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No
September 2005

E-273 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-08 D2.1-a 

D2.2-a 

D2.3-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V E-08 D2.1-a 

D2.2-a 

D2.3-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V E-09 D2.3-a Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

V E-09 D2.3-a Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Wall thinning/

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

V E-10 D2.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
NUREG-1832

E-274 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-10 D2.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

V E-11 D2.1-d Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

water 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

V E-11 D2.1-d Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

water 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

V E-12 A.1-a 

A.1-c 

A.3-a 

A.4-a 

D1.1-a 

D1.2-a 

D1.4-b 

D1.7-b 

D1.8-a 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714

No

V E-12 A.1-a 

A.1-c 

A.3-a 

A.4-a 

D1.1-a 

D1.2-a 

D1.4-b 

D1.7-b 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No
September 2005

E-275 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

D1.8-a 

V E-13 D1.1-c 

D1.4-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

V E-13 D1.1-c 

D1.4-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

V E-14 D2.1-e Piping, 

piping 

compone

nts, and 

piping 

elements 

internal 

surfaces

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-14 D2.1-e Piping, 

piping 

compone

nts, and 

piping 

elements 

internal 

surfaces

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-276 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-16 D2.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

V E-16 Row was deleted since Shuffle Master 1-28.

V E-17 A.6-c 

D1.5-a 

D1.6-a 

D2.4-c 

Heat 

exchange

r shell 

side 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V E-17 A.6-c

D1.5-a 

D1.6-a 

D2.4-c 

Heat 

exchange

r 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V E-18 A.6-a 

D1.6-b 

D2.4-a 

Heat 

exchange

r shell 

side 

compone

nts 

including 

tubes

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
September 2005

E-277 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-18 A.6-a 

D1.6-b 

D2.4-a 

Heat 

exchange

r 

compone

nts

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, 

galvanic, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-19 A.6-c 

D1.5-a 

D1.6-a 

D2.4-c 

Heat 

exchange

r shell 

side 

compone

nts 

including 

tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V E-19 A.6-c 

D1.5-a 

D1.6-a 

D2.4-c 

Heat 

exchange

r 

compone

nts

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V E-20 A.6-a 

D1.6-b 

D2.4-a 

Heat 

exchange

r shell 

side 

compone

nts 

including 

tubes

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
NUREG-1832

E-278 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-20 A.6-a 

D1.6-b 

D2.4-a 

Heat 

exchange

r 

compone

nts

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-21 A.6-b 

D1.6-c 

D2.4-b 

Heat 

exchange

r tubes 

(serviced 

by opencycle 

cooling 

water)

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-21 A.6-b 

D1.6-c 

D2.4-b 

Heat 

exchange

r tubes

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-22 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated. See IN 85-30 for evidence of 

microbiologically influenced corrosion.

Yes, plantspecific
September 2005

E-279 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-22 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-23 D2.4-b Heat 

exchange

r tubes 

(serviced 

by opencycle 

cooling 

water)

Steel Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-23 D2.4-b Heat 

exchange

r tubes

Steel Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-24 D1.2-c Orifice 

(miniflow 

recirculati

on)

Stainless 

steel

Treated 

borated 

water

Loss of 

material/ 

erosion

A plant-specific aging management program is to 

be evaluated for erosion of the orifice due to 

extended use of the centrifugal HPSI pump for 

normal charging. See LER 50-275/94-023 for 

evidence of erosion.

Yes, plantspecific

V E-24 D1.2-c Orifice 

(miniflow 

recirculati

on)

Stainless 

steel

Treated 

borated 

water

Loss of

material/ 

erosion

A plant-specific aging management program is to 

be evaluated for erosion of the orifice due to 

extended use of the centrifugal HPSI pump for 

normal charging. See LER 50-275/94-023 for 

evidence of erosion.

Yes, plantspecific

V E-25 B.2-a Ducting, 

piping 

and 

compone

Steel Air –

indoor 

uncontroll

ed 

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-280 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts 

internal 

surfaces

(Internal)

V E-25 B.2-a Ducting 

and 

compone

nts 

internal 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

V E-26 A.2-a 

A.5-a 

B.1-a 

B.2-a 

D2.1-e 

D2.5-a 

Ducting, 

piping 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-26 A.2-a 

A.5-a 

B.1-a 

B.2-a 

D2.1-e 

D2.5-a 

Ducting, 

piping 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-27 D2.1-e Piping 

and 

compone

nts 

internal 

surfaces

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-27 D2.1-e Piping 

and 

compone

nts 

internal 

surfaces

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No
September 2005

E-281 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-28 A.1-b 

A.3-b 

A.4-b 

A.5-b 

A.6-d 

D1.1-d 

D1.2-b 

D1.3-a 

D1.4-c 

D1.5-b 

D1.6-d 

D1.7-a 

D1.8-b 

E.1-a 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V E-28 A.1-b 

A.3-b 

A.4-b 

A.5-b 

A.6-d 

D1.1-d 

D1.2-b 

D1.3-a 

D1.4-c 

D1.5-b 

D1.6-d 

D1.7-a 

D1.8-b 

E.1-a 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V E-29 A.2-a 

A.5-a 

D2.5-a 

Piping 

and 

compone

nts 

internal 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-282 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-29 A.2-a 

A.5-a 

D2.5-a 

Piping 

and 

compone

nts 

internal 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

V E-30 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

external 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-30 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

external 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-31 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-283 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-31 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

internal

surfaces

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V E-32 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Steel Untreate

d water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated. See IN 85-30 for evidence of 

microbiologically influenced corrosion.

Yes, plantspecific

V E-32 Row was deleted since Shuffle Master 1-28.

V E-33 C.1-b Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-33 C.1-b Containm

ent 

isolation 

piping 

and 

compone

nts 

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-284 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

internal 

surfaces

V E-34 C.1-b Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Stainless 

steel

Untreate

d water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated. See IN 85-30 for evidence of 

microbiologically influenced corrosion.

Yes, plantspecific

V E-34 C.1-b Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V E-35 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-285 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-35 C.1-a Containm

ent 

isolation 

piping 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-36 C.1-b Containm

ent 

isolation 

piping 

and 

compone

nts 

internal 

surfaces

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated. See IN 85-30 for evidence of 

microbiologically influenced corrosion.

Yes, plantspecific

V E-36 Row was deleted since Shuffle Master 1-28.

V E-37 D2.1-c 

D2.3-c

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No

V E-37 D2.1-c 

D2.3-c

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking and 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water

No
NUREG-1832

E-286 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-38 D1.7-b Safety 

injection 

tank 

(accumul

ator)

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714

No

V E-38 D1.7-b Safety 

injection 

tank 

(accumul

ator)

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

V E-40 B.1-a Ducting 

closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-40 B.1-a Ducting 

closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-41 E. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V E-41 E. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-287 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-42 B. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Soil Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

V E-42 B. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel 

(with or 

without 

coating 

or 

wrapping

)

Soil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

V E-43 A. D1. Motor 

Cooler

Gray cast 

iron

Treated 

water

Loss of 

material/ 

Selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V E-43 A. D1. Motor 

Cooler

Gray cast 

iron

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V E-44 E. External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-288 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V E-44 E. External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-45 E. External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-45 E. External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-46 E. External 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V E-46 E.1-b External 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

V E-47 D1.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

borated 

water 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No

V E-47 D1.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

borated 

water 

>250°C 

(>482°F)

Loss of 

fracture 

toughness/ 

thermal aging 

embrittlement

Chapter XI.M12, "Thermal Aging Embrittlement of 

Cast Austenitic Stainless Steel (CASS)"

No
September 2005

E-289 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP-1 E. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

V EP-1 E. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

V EP10F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP10F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP11F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil (no 

water 

pooling)

None None No

V EP11Row was deleted since Shuffle Master 1-28.

V EP12F. Piping, 

piping 

compone

Copper 

alloy 

<15% Zn

Air with 

borated 

water 

None None No
NUREG-1832

E-290 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

leakage

V EP12F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

<15% Zn

Air with 

borated 

water 

leakage

None None No

V EP13A. D1. 

D2.

Heat 

exchange

r tubes

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP13A. D1. 

D2.

Heat 

exchange

r 

compone

nts

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP14F. Ducting Galvaniz

ed steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP14F. Ducting Galvaniz

ed steel

Air –

indoor 

controlled 

(External)

None None No

V EP15F. Piping, 

piping 

compone

nts, and 

piping 

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No
September 2005

E-291 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

V EP15F. Piping 

elements

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP16F. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Lubricatin

g oil

None None No

V EP16F. Piping 

elements

Glass Lubricatin

g oil

None None No

V EP17F. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP17F. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP18F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No
NUREG-1832

E-292 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP18F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP19F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

V EP19F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

V EP-2 D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V EP-2 D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V EP20F. Piping, 

piping 

compone

nts, and 

piping 

Stainless 

steel

Concrete None None No
September 2005

E-293 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

V EP20F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

V EP21F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

None None No

V EP21Row was deleted since Shuffle Master 1-28.

V EP22F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

V EP22F. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

V EP24E. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-294 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP24E. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening 

Chapter XI.M18, "Bolting Integrity" No

V EP25E. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

V EP25E. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

V EP26D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry" The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP26D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry" for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP27A. B. 

D1. D2.

Piping, 

piping 

compone

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

Loss of 

material/ 

selective 

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-295 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

water leaching

V EP27A. B. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V EP28F. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Raw 

water

None None No

V EP28F. Piping 

elements

Glass Raw 

water

None None No

V EP29F. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Treated 

water

None None No

V EP29F. Piping 

elements

Glass Treated 

water

None None No

V EP-3 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air –

indoor 

uncontroll

ed 

(Internal/

External)

None None No
NUREG-1832

E-296 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP-3 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air –

indoor 

uncontroll

ed 

(Internal/

External)

None None No

V EP30F. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Treated 

borated 

water

None None No

V EP30F. Piping 

elements

Glass Treated 

borated 

water

None None No

V EP31D1. D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V EP31D1. D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V EP32D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-297 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP32D2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry" for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP33A. C. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP33A. C. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP34A. D2. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry" No

V EP34A. D2. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP35A. D1. 

D2.

Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP35A. D1. 

D2.

Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-298 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

water

V EP36A. B. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP36A. B. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP37A. B. 

D1. D2.

Heat 

exchange

r tubes

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V EP37A. B. 

D1. D2.

Heat 

exchange

r 

compone

nts

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V EP38E. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

V EP38E. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

>15% Zn

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-299 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP39Did not exist in Shuffle Master 1-28.

V EP39A. Heat 

exchange

r tubes

Copper 

alloy

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP-4 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

controlled 

(External)

None None No

V EP-4 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

controlled 

(External)

None None No

V EP40Did not exist in Shuffle Master 1-28.

V EP40A. D1. 

D2. 

Heat 

exchange

r tubes

Steel Lubricatin

g oil

Reduction of 

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP41Did not exist in Shuffle Master 1-28.

V EP41A. D1. Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Stainless 

steel

Treated 

borated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No
NUREG-1832

E-300 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP42Did not exist in Shuffle Master 1-28.

V EP42A. Encapsul

ation 

Compone

nts

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

V EP43Did not exist in Shuffle Master 1-28.

V EP43A. Encapsul

ation 

Compone

nts

Steel Air with 

borated 

water 

leakage 

(Internal)

Loss of 

material/ 

general, 

pitting, 

crevice and 

boric acid 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

V EP44Did not exist in Shuffle Master 1-28.

V EP44A. C. 

D1. D2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP45Did not exist in Shuffle Master 1-28.

V EP45A. D1. 

D2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP- Did not exist in Shuffle Master 1-28.
September 2005

E-301 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

46

V EP46A. D1. 

D2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP47Did not exist in Shuffle Master 1-28.

V EP47A. D1. 

D2. 

Heat 

exchange

r tubes

Copper 

alloy

Lubricatin

g oil

Reduction of 

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP48Did not exist in Shuffle Master 1-28.

V EP48C. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

V EP49Did not exist in Shuffle Master 1-28.

V EP49D1. Pump 

Casings

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water

Loss of 

material/ 

cladding 

breach

A plant-specific aging management program is to 

be evaluated.Reference NRC Information Notice 

94-63, "Boric Acid Corrosion of Charging Pump 

Casings Caused by Cladding Cracks."

Yes, verify 

that plantspecific 

program 

addresses 

cladding 

breach
NUREG-1832

E-302 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

V EP-5 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

V EP-5 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

V EP50Did not exist in Shuffle Master 1-28.

V EP50A. D1. 

D2. 

Heat 

exchange

r tubes

Stainless 

steel

Lubricatin

g oil

Reduction of 

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP51Did not exist in Shuffle Master 1-28.

V EP51D1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

V EP52Did not exist in Shuffle Master 1-28.

V EP52D1. Piping, 

piping 

compone

nts, and 

Gray cast 

iron

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-303 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

V EP53Did not exist in Shuffle Master 1-28.

V EP53A. D1. Piping, 

piping 

compone

nts, 

piping 

elements 

internal 

surfaces, 

and tanks 

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

V EP54Did not exist in Shuffle Master 1-28.

V EP54B. D1. 

D2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

V EP55Did not exist in Shuffle Master 1-28.

V EP55D1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

V EP-6 F. Piping, 

piping 

compone

Steel Lubricatin

g oil (no 

water 

None None No
NUREG-1832

E-304 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

pooling)

V EP-6 Row was deleted since Shuffle Master 1-28.

V EP-7 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

V EP-7 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

V EP-8 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

V EP-8 Row was deleted since Shuffle Master 1-28.

V EP-9 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No

V EP-9 F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No
September 2005

E-305 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-01 A.1-a Conducto

r 

insulation 

for 

electrical 

cables 

and 

connectio

ns

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

of organics 

(Thermal/ 

thermoxidativ

e), radiolysis 

and 

photolysis

(UV sensitive 

materials 

only) of 

organics; 

radiationinduced 

oxidation, 

and moisture 

intrusion

Chapter XI.E1, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements" 

No
NUREG-1832

E-306 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-01 A.1-a Conducto

r 

insulation 

for 

electrical 

cables 

and 

connectio

ns

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

of organics 

(Thermal/ 

thermoxidativ

e), radiolysis 

and 

photolysis 

(UV sensitive 

materials 

only) of 

organics; 

radiationinduced 

oxidation, 

and moisture 

intrusion

Chapter XI.E1, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements" 

No
September 2005

E-307 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-02 A.1-b Conducto

r 

insulation 

for 

electrical 

cables 

and 

connectio

ns used 

in 

instrume

ntation 

circuits 

that are 

sensitive 

to 

reduction 

in 

conducto

r 

insulation 

resistanc

e (IR)

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

of organics 

(Thermal/ 

thermoxidativ

e), radiolysis 

and 

photolysis 

(UV sensitive 

materials 

only) of 

organics; 

radiationinduced 

oxidation, 

and moisture 

intrusion

Chapter XI.E2, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements Used in 

Instrumentation Circuits"

No
NUREG-1832

E-308 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-02 A.1-b Conducto

r 

insulation 

for 

electrical 

cables 

and 

connectio

ns used 

in 

instrume

ntation 

circuits 

that are 

sensitive 

to 

reduction 

in 

conducto

r 

insulation 

resistanc

e (IR)

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

of organics 

(Thermal/ 

thermoxidativ

e), radiolysis 

and 

photolysis 

(UV sensitive 

materials 

only) of 

organics; 

radiationinduced 

oxidation, 

and moisture 

intrusion

Chapter XI.E2, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements Used in 

Instrumentation Circuits"

No
September 2005

E-309 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-03 A.1-c Conducto

r 

insulation 

for 

inaccessi

ble 

mediumvoltage 

(2kV to 

15kV) 

cables 

(e.g., inst

alled in 

conduit 

or direct 

buried)

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by 

exposure 

to 

moisture 

and 

voltage

Localized 

damage and 

breakdown of 

insulation 

leading to 

electrical 

failure/ 

moisture 

intrusion, 

water trees

Chapter XI.E3, "Inaccessible Medium Voltage 

Cables Not Subject to 10 CFR 50.49 

Environmental Qualification Requirements"

No

VI L-03 A.1-c Conducto

r 

insulation 

for 

inaccessi

ble 

mediumvoltage 

(2kV to 

35kV) 

cables 

(e.g., inst

alled in 

conduit 

or direct 

buried)

Various 

organic 

polymers 

(e.g., 

EPR, SR, 

EPDM, 

XLPE)

Adverse 

localized 

environm

ent 

caused 

by 

exposure 

to 

moisture 

and 

voltage

Localized 

damage and 

breakdown of 

insulation 

leading to

electrical 

failure/ 

moisture 

intrusion, 

water trees

Chapter XI.E3, "Inaccessible Medium Voltage 

Cables Not Subject to 10 CFR 50.49 

Environmental Qualification Requirements"

No
NUREG-1832

E-310 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-04 A.2-a Connecto

r contacts 

for 

electrical 

connecto

rs 

exposed 

to 

borated 

water 

leakage

Various 

metals 

used for 

electrical 

contacts

Air with 

borated 

water 

leakage

Corrosion of 

connector 

contact 

surfaces/ 

intrusion of 

borated water

Chapter XI.M10, "Boric Acid Corrosion" No

VI L-04 A.2-a Connecto

r contacts 

for 

electrical 

connecto

rs 

exposed 

to 

borated 

water 

leakage

Various 

metals 

used for 

electrical 

contacts

Air with 

borated 

water 

leakage

Corrosion of 

connector 

contact 

surfaces/ 

intrusion of 

borated water

Chapter XI.M10, "Boric Acid Corrosion" No

VI L-05 B.1-a Electrical 

equipme

nt subject 

to 

10 CFR 5

0.49 EQ 

requirem

ents

Various 

polymeric 

and 

metallic 

materials

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

oxygen, 

moisture, 

or 

voltage

Various 

degradation/ 

various 

mechanisms

EQ is a time-limited aging analysis (TLAA) to be

evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.4, 

"Environmental Qualification (EQ) of Electrical 

Equipment," for acceptable methods for meeting 

the requirements of 10 CFR 54.21(c)(1)(i) and 

(ii).See Chapter X.E1, "Environmental 

Qualification (EQ) of Electric Components," of this 

report for meeting the requirements of 10 CFR 

54.21(c)(1)(iii).

Yes,TLAA
September 2005

E-311 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI L-05 B.1-a Electrical 

equipme

nt subject 

to 

10 CFR 5

0.49 EQ 

requirem

ents

Various 

polymeric 

and 

metallic 

materials

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

oxygen, 

moisture, 

or 

voltage

Various 

degradation/ 

various 

mechanisms

EQ is a time-limited aging analysis (TLAA) to be 

evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.4, 

"Environmental Qualification (EQ) of Electrical 

Equipment," for acceptable methods for meeting 

the requirements of 10 CFR 54.21(c)(1)(i) and 

(ii).See Chapter X.E1, "Environmental 

Qualification (EQ) of Electric Components," of this 

report for meeting the requirements of 10 CFR 

54.21(c)(1)(iii).

Yes,TLAA

VI LP01A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

) Metallic 

Clamp

Copper 

alloy

Air –

indoor

Fatigue/ 

ohmic 

heating, 

thermal 

cycling, 

electrical 

transients, 

frequent 

manipulation, 

vibration, 

chemical 

contaminatio

n, corrosion, 

and oxidation

Chapter XI.E5, "Aging Management Program for 

Fuse Holders"

No
NUREG-1832

E-312 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP01A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

);Metallic 

Clamp

Copper 

alloy

Air –

indoor

Fatigue/ohmi

c heating, 

thermal 

cycling, 

electrical 

transients, 

frequent 

manipulation, 

vibration, 

chemical 

contaminatio

n, corrosion, 

and oxidation

Chapter XI.E5, "Fuse Holders" No

VI LP02A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

)

Insulation 

material 

–

bakelite, 

phenolic 

melamine 

or 

ceramic, 

molded 

polycarbo

nate and 

other

Air –

indoor 

uncontroll

ed 

(Internal/

External)

None None No
September 2005

E-313 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP02A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

);Insulatio

n

Insulation 

material 

–

bakelite, 

phenolic 

melamine 

or 

ceramic, 

molded 

polycarbo

nate and 

other

Air –

indoor 

uncontroll

ed 

(Internal/

External)

None None No

VI LP03A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

)

Insulation 

material 

–

bakelite, 

phenolic 

melamine 

or 

ceramic, 

molded 

polycarbo

nate and 

other

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen 

or > 60-

year 

service 

limiting 

temperat

ure

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

(Thermal/ 

thermoxidativ

e) of 

organics/ther

moplastics, 

radiationinduced 

Chapter XI.E1, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements" 

No
NUREG-1832

E-314 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

oxidation, 

moisture 

intrusion and 

ohmic 

heating
September 2005

E-315 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP03A. Fuse 

Holders 

(Not Part 

of a 

Larger 

Assembly

);Insulatio

n

Insulation 

material 

–

bakelite, 

phenolic 

melamine 

or 

ceramic, 

molded 

polycarbo

nate and 

other

Adverse 

localized 

environm

ent 

caused 

by heat, 

radiation, 

or 

moisture 

in the 

presence 

of oxygen 

or > 60-

year 

service 

limiting 

temperat

ure

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

degradation 

(Thermal/ 

thermoxidativ

e) of 

organics/ther

moplastics, 

radiationinduced 

oxidation, 

moisture 

intrusion and 

ohmic 

heating

Chapter XI.E1, "Electrical Cables and Connections 

Not Subject to 10 CFR 50.49 Environmental 

Qualification Requirements" 

No
NUREG-1832

E-316 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP04A. Phase 

bus 

Bus/conn

ections

Aluminu

m / Silver 

Plated 

Aluminu

m 

Copper / 

Silver 

Plated 

Copper; 

Stainless 

steel, 

steel

Air –

indoor 

and 

outdoor

Loosening of 

bolted 

connections/ 

thermal 

cycling and 

ohmic 

heating

Chapter XI.E4, "Aging Management Program for 

Bus Ducts"

No

VI LP04A. Metal 

enclosed 

busBus/c

onnection

s

Aluminu

m/ Silver 

Plated 

Aluminu

m 

Copper/ 

Silver 

Plated 

Copper; 

Stainless 

steel, 

steel

Air –

indoor 

and 

outdoor

Loosening of 

bolted 

connections/ 

thermal 

cycling and 

ohmic 

heating

Chapter XI.E4, "Metal Enclosed Bus" No
September 2005

E-317 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP05A. Phase 

bus 

Insulation

/insulator

s

Porcelain

,xenoy, 

thermoplastic 

organic 

polymers

Air –

indoor 

and 

outdoor

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

thermal/ther

moxidative 

degradation 

of 

organics/ther

moplastics, 

radiationinduced 

oxidation; 

moisture/debr

is intrusion, 

and ohmic 

heating

Chapter XI.E4, "Aging Management Program for 

Bus Ducts"

No
NUREG-1832

E-318 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP05A. Metal 

enclosed 

busInsula

tion/insul

ators

Porcelain

,xenoy, 

thermoplastic 

organic 

polymers

Air –

indoor 

and 

outdoor

Embrittlemen

t, cracking, 

melting, 

discoloration, 

swelling, or 

loss of 

dielectric 

strength 

leading to 

reduced 

insulation 

resistance 

(IR); 

electrical 

failure/ 

thermal/ther

moxidative 

degradation 

of 

organics/ther

moplastics, 

radiationinduced 

oxidation; 

moisture/debr

is intrusion, 

and ohmic 

heating

Chapter XI.E4, "Metal Enclosed Bus" No

VI LP06A. Phase 

bus 

Enclosur

e 

assembli

es

Steel, 

galvanize

d steel

Air –

indoor 

and 

outdoor

Loss of 

material/ 

general 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No
September 2005

E-319 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP06A. Metal 

enclosed 

busEnclo

sure 

assembli

es

Steel; 

galvanize

d steel

Air –

indoor 

and 

outdoor

Loss of 

material/ 

general 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No

VI LP07A. High 

voltage 

insulators

Porcelain

,Malleabl

e iron, 

aluminum

, 

galvanize

d steel, 

cement

Air –

outdoor

Degradation 

of insulator 

quality/ 

presence of 

any salt 

deposits and 

surface 

contaminatio

n

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP07A. High 

voltage 

insulators

Porcelain

,Malleabl

e iron, 

aluminum

, 

galvanize

d steel, 

cement

Air –

outdoor

Degradation 

of insulator 

quality/prese

nce of any 

salt deposits 

or surface 

contaminatio

n

A plant-specific aging management program is to 

be evaluated for plants located such that the 

potential exists for salt deposits or surface 

contamination (e.g., in the vicinity of salt water 

bodies or industrial pollution). 

Yes, plantspecific
NUREG-1832

E-320 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP08A. Transmis

sion 

conducto

rs and 

connectio

ns

Aluminu

m, steel

Air –

outdoor

Loss of 

material/ 

wind induced 

abrasion and 

fatigueLoss 

of conductor 

strength/ 

corrosionIncr

eased 

resistance of 

connection/ 

oxidation or 

loss of preload

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP08A. Transmis

sion 

conducto

rs and 

connectio

ns

Aluminu

m, steel

Air –

outdoor

Loss of 

material/ 

wind induced 

abrasion and 

fatigueLoss 

of conductor 

strength/ 

corrosionIncr

eased 

resistance of 

connection/ 

oxidation or 

loss of preload

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-321 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP09A. Switchyar

d bus 

and 

connectio

ns

Aluminu

m, 

copper, 

bronze, 

stainless 

steel, 

galvanize

d steel

Air –

outdoor

Loss of 

material/ 

wind induced 

abrasion and 

fatigueLoss 

of conductor 

strength/ 

corrosionIncr

eased 

resistance of 

connection/ 

oxidation or 

loss of preload

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP09A. Switchyar

d bus 

and 

connectio

ns

Aluminu

m, 

copper, 

bronze, 

stainless 

steel, 

galvanize

d steel

Air –

outdoor

Loss of 

material/ 

wind induced 

abrasion and 

fatigueLoss 

of conductor 

strength/ 

corrosionIncr

eased 

resistance of 

connection/ 

oxidation or 

loss of preload

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP10A. Phase 

bus 

Enclosur

e 

assembli

es

Elastome

rs

Air –

indoor 

and 

outdoor

Hardening 

and loss of 

strength/ 

elastomer 

degradation

Chapter XI.S6, "Structures Monitoring Program" No
NUREG-1832

E-322 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VI LP10A. Metal 

enclosed 

busEnclo

sure 

assembli

es

Elastome

rs

Air –

indoor 

and 

outdoor

Hardening 

and loss of 

strength/ 

elastomer 

degradation

Chapter XI.S6, "Structures Monitoring Program" No

VI LP11A. High 

voltage 

insulators

Porcelain

,Malleabl

e iron, 

aluminum

, 

galvanize

d steel, 

cement

Air –

outdoor

Loss of 

material/ 

mechanical 

wear due to 

wind blowing 

on 

transmission 

conductors

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP11A. High 

voltage 

insulators

Porcelain

,Malleabl

e iron, 

aluminum

, 

galvanize

d steel, 

cement

Air –

outdoor

Loss of 

material/ 

mechanical 

wear due to 

wind blowing 

on 

transmission 

conductors

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VI LP12A. Cable 

Connecti

ons 

(Metallic 

Parts)

Various 

metals 

used for 

electrical 

contacts

Air –

indoor 

and 

outdoor

Loosening of 

bolted 

connections 

due to 

thermal 

cycling, 

ohmic 

heating, 

electrical 

transients, 

vibration, 

chemical 

contaminatio

Chapter XI.E6, "Electrical Connections Not 

Subject to 10 CFR 50.49 Environmental 

Qualification Requirements"

No
September 2005

E-323 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

n, corrosion, 

and oxidation

VI LP12A. Cable 

Connecti

ons 

(Metallic 

Parts)

Various 

metals 

used for 

electrical 

contacts

Air –

indoor 

and 

outdoor

Loosening of 

bolted 

connections 

due to 

thermal 

cycling, 

ohmic 

heating, 

electrical 

transients, 

vibration, 

chemical 

contaminatio

n, corrosion, 

and oxidation

Chapter XI.E6, "Electrical Connections Not 

Subject to 10 CFR 50.49 Environmental 

Qualification Requirements"

No
NUREG-1832

E-324 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-01 H1.1-b 

C1.1-b 

C3. G. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel 

(with or 

without 

coating 

or 

wrapping

)

Soil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

VII A-01 H1.1-b 

C1.1-b 

C3. G. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel 

(with or 

without 

coating 

or 

wrapping

)

Soil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

VII A-02 C1.1-c 

C3. G. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching and 

general 

corrosion

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-02 C1.1-c 

C3. G. 

H1. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-325 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-03 I. Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII A-03 I.2-a Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII A-04 I. Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

VII A-04 I.2-b Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

VII A-05 B.2-a Cranes -

rails

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

wear

Chapter XI.M23, "Inspection of Overhead Heavy 

Load and Light Load (Related to Refueling) 

Handling Systems"

No

VII A-05 B.2-a Cranes -

rails

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

wear

Chapter XI.M23, "Inspection of Overhead Heavy 

Load and Light Load (Related to Refueling) 

Handling Systems"

No
NUREG-1832

E-326 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-06 B.1-a Cranes -

Structural 

girders

Steel Air –

indoor 

uncontroll

ed 

(External)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation 

for structural girders of cranes that fall within the 

scope of 10 CFR 54. See the Standard Review 

Plan, Section 4.7, "Other Plant-Specific TimeLimited Aging Analyses," for generic guidance for 

meeting the requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-06 B.1-a Cranes -

Structural 

girders

Steel Air –

indoor 

uncontroll

ed 

(External)

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation 

for structural girders of cranes that fall within the 

scope of 10 CFR 54. See the Standard Review 

Plan, Section 4.7, "Other Plant-Specific TimeLimited Aging Analyses," for generic guidance for 

meeting the requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-07 B.1-b Cranes -

Structural 

girders

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

General 

corrosion

Chapter XI.M23, "Inspection of Overhead Heavy 

Load and Light Load (Related to Refueling) 

Handling Systems"

No

VII A-07 B.1-b Cranes -

Structural 

girders

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

General 

corrosion

Chapter XI.M23, "Inspection of Overhead Heavy 

Load and Light Load (Related to Refueling) 

Handling Systems"

No

VII A-08 F1.1-a 

F2.1-a 

F3.1-a 

F4.1-a 

Ducting 

and 

compone

nts 

internal 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-327 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-08 F1.1-a 

F2.1-a 

F3.1-a 

F4.1-a 

F1.4-a 

F2.4-a 

F3.4-a 

Ducting 

and 

compone

nts 

internal 

surfaces

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, 

crevice, and 

(for drip pans 

and drain 

lines) 

microbiologic

ally 

influenced 

corrosion 

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

VII A-09 F1.4-a 

F2.4-a 

F3.4-a 

Ducting, 

piping 

and 

compone

nts 

external 

surfaces

Stainless 

steel

Condens

ation 

(External)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-09 F1.4-a 

F2.4-a 

F3.4-a 

Ducting 

and 

compone

nts

Stainless 

steel

Condens

ation

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-10 F1.1-a 

F1.4-a 

F2.1-a 

F2.4-a 

F3.1-a 

F3.4-a 

F4.1-a 

Ducting 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-328 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-10 F1.1-a 

F1.4-a 

F2.1-a 

F2.4-a 

F3.1-a 

F3.4-a 

F4.1-a 

Ducting 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A100E1.8-a Heat 

exchange

r shell 

side 

compone

nts 

including 

tubes

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A100E1.8-a Heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A101E4.3-a Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No

VII A101Row was deleted since Shuffle Master 1-28.

VII A102I. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-329 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A102I. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VII A103D.2-a Closure 

bolting

Steel Condens

ation

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M24, "Compressed Air Monitoring" No

VII A103D.2-a Closure 

bolting

Steel Condens

ation

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII A104E1. Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A104E1.5-a Highpressure 

pumpClo

sure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity."The AMP is to 

be augmented by appropriate inspection to detect 

cracking if the bolts are not otherwise replaced 

during maintenance.

Yes, if the 

bolts are not 

replaced 

during 

maintenance

VII A105F1. Ducting 

closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-330 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A105F1.1-a 

F2.1-a 

F3.1-a 

F4.1-a I.

Ducting 

closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A-11 F1.4-a 

F2.4-a 

F3.4-a 

Ducting, 

piping 

and 

compone

nts 

internal 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-11 Row was deleted since Shuffle Master 1-28.

VII A-12 F1.4-a 

F2.4-a 

F3.4-a 

Ducting, 

piping 

and 

compone

nts 

internal 

surfaces

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-12 Row was deleted since Shuffle Master 1-28.

VII A-13 F1.1-a 

F2.1-a 

F3.1-a 

F4.1-a 

Ducting 

and 

compone

nts 

internal 

surfaces

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-13 Row was deleted since Shuffle Master 1-28.
September 2005

E-331 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-15 A3.2-a 

A3.2-d 

A3.3-a 

A3.3-d 

A3.5-a 

A3.5-c 

Elastome

r lining

Elastome

rs

Treated 

borated 

water

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program that 

determines and assesses the qualified life of the 

linings in the environment is to be evaluated.

Yes, plantspecific

VII A-15 A3.2-a 

A3.2-d 

A3.3-a 

A3.3-d 

A3.5-a 

A3.5-c 

Elastome

r lining

Elastome

rs

Treated 

borated 

water

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program that 

determines and assesses the qualified life of the 

linings in the environment is to be evaluated.

Yes, plantspecific

VII A-16 A4.2-a 

A4.2-b 

A4.3-a 

A4.3-b 

A4.5-a 

A4.5-b 

Elastome

r lining

Elastome

rs

Treated 

water

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program that 

determines and assesses the qualified life of the 

linings in the environment is to be evaluated.

Yes, plantspecific

VII A-16 A4.2-a 

A4.2-b 

A4.3-a 

A4.3-b 

A4.5-a 

A4.5-b 

Elastome

r lining

Elastome

rs

Treated 

water

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program that 

determines and assesses the qualified life of the 

linings in the environment is to be evaluated.

Yes, plantspecific

VII A-17 F1.1-b 

F1.4-b 

F2.1-b 

F2.4-b 

F3.1-b 

F3.4-b 

F4.1-b 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed >35°C 

(>95°F) 

(Internal)

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-332 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-17 F1.1-b 

F1.4-b 

F2.1-b 

F2.4-b 

F3.1-b 

F3.4-b 

F4.1-b 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(Internal/ 

External)

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-18 F1.1-c 

F2.1-c 

F3.1-c 

F4.1-c 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

wear

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-18 F1.1-c 

F2.1-c 

F3.1-c 

F4.1-c 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(Internal)

Loss of 

material/ 

wear

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-19 G.1-a 

G.2-a 

G.3-a 

G.4-a 

Fire 

barrier 

penetrati

on seals

Elastome

rs

Air –

indoor 

uncontroll

ed

Increased 

hardness, 

shrinkage 

and loss of 

strength/ 

weathering

Chapter XI.M26, "Fire Protection" No

VII A-19 G.1-a 

G.2-a 

G.3-a 

G.4-a 

Fire 

barrier 

penetrati

on seals

Elastome

rs

Air –

indoor 

uncontroll

ed

Increased 

hardness, 

shrinkage 

and loss of 

strength/ 

weathering

Chapter XI.M26, "Fire Protection" No

VII A-20 G.1-a 

G.2-a 

G.3-a 

G.4-a 

Fire 

barrier 

penetrati

on seals

Elastome

rs

Air –

outdoor

Increased 

hardness, 

shrinkage 

and loss of 

strength/ 

weathering

Chapter XI.M26, "Fire Protection" No
September 2005

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-20 G.1-a 

G.2-a 

G.3-a 

G.4-a 

Fire 

barrier 

penetrati

on seals

Elastome

rs

Air –

outdoor

Increased 

hardness, 

shrinkage 

and loss of 

strength/ 

weathering

Chapter XI.M26, "Fire Protection" No

VII A-21 G.1-d 

G.2-d 

G.3-d 

G.4-d 

G.5-c 

Fire rated 

doors

Steel Air –

indoor 

uncontroll

ed

Loss of 

material/ 

wear

Chapter XI.M26, "Fire Protection" No

VII A-21 G.1-d 

G.2-d 

G.3-d 

G.4-d 

G.5-c 

Fire rated 

doors

Steel Air –

indoor 

uncontroll

ed

Loss of 

material/ 

wear

Chapter XI.M26, "Fire Protection" No

VII A-22 G.1-d 

G.2-d 

G.3-d 

G.4-d 

Fire rated 

doors

Steel Air –

outdoor

Loss of 

material/ 

wear

Chapter XI.M26, "Fire Protection" No

VII A-22 G.1-d 

G.2-d 

G.3-d 

G.4-d 

Fire rated 

doors

Steel Air –

outdoor

Loss of 

material/ 

wear

Chapter XI.M26, "Fire Protection" No

VII A-23 H2.2-a 

H2.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Moist air Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-23 H2.2-a 

H2.3-a 

G. 

Piping, 

piping 

compone

nts, and 

piping 

Steel Moist air 

or 

condensa

tion 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No
NUREG-1832

E-334 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements corrosion

VII A-24 H1.1-a 

H1.2-a 

H1.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-24 H1.1-a 

H1.2-a 

H1.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A-25 C2.1-a 

C2.2-a 

C2.3-a 

C2.4-a 

C2.5-a 

F1.3-a 

F2.3-a 

F3.3-a 

F4.3-a 

H2.1-a 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
September 2005

E-335 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-25 C2.1-a 

C2.2-a 

C2.3-a 

C2.4-a 

C2.5-a 

F1.3-a 

F2.3-a 

F3.3-a 

F4.3-a 

H2.1-a 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-26 D.1-a 

D.2-a 

D.3-a 

D.4-a 

D.5-a 

D.6-a 

Compres

sed air 

systemPi

ping, 

piping 

compone

nts, and 

piping 

elements

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.M24, "Compressed Air Monitoring" No

VII A-26 D.1-a 

D.2-a 

D.3-a 

D.4-a 

D.5-a 

D.6-a 

Compres

sed air 

systemPi

ping, 

piping 

compone

nts, and 

piping 

elements

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general and 

pitting 

corrosion

Chapter XI.M24, "Compressed Air Monitoring" No

VII A-27 H2.4-a Diesel 

engine 

exhaust 

Piping, 

piping 

compone

nts, and 

Steel; 

Stainless 

steel

Diesel 

exhaust

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-336 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

VII A-27 H2.4-a Diesel 

engine 

exhaustP

iping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel; 

steel

Diesel 

exhaust

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-28 G.8-a Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Fuel oil Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M26, "Fire Protection," and Chapter 

XI.M30, "Fuel Oil Chemistry"

No

VII A-28 G.8-a Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Fuel oil Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M26, "Fire Protection," and Chapter 

XI.M30, "Fuel Oil Chemistry" 

No

VII A-30 H1.4-a 

H2.5-a 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel Fuel oil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

Chapter XI.M30, "Fuel Oil Chemistry" The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-337 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

and fouling

VII A-30 H1.4-a 

H2.5-a 

Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel Fuel oil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M30, "Fuel Oil Chemistry"The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects

is to be 

evaluated

VII A-31 C3.1-a 

C3.2-a 

C3.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-31 Row was deleted since Shuffle Master 1-28.

VII A-32 C1.2-a 

C1.5-a 

C1.6-a 

H2.1-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
NUREG-1832

E-338 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

corrosion, 

and fouling

VII A-32 Row was deleted since Shuffle Master 1-28.

VII A-33 G.6-a 

G.6-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No

VII A-33 G.6-a 

G.6-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No

VII A-34 E1.1-a 

E1.3-a 

E1.7-a 

E1.8-a 

E3.2-c 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-339 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-34 E1.1-a 

E1.3-a 

E1.7-a 

E1.8-a 

E3.2-c 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

uncontroll

ed

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-35 E4.1-a 

E4.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-35 E3. 

E4.1-a 

E4.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-36 F1.1-b 

F1.4-b 

F2.1-b 

F2.4-b 

F3.1-b 

F3.4-b 

F4.1-b

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(External)

Hardening 

and loss of 

strength/ 

elastomer 

degradation

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-36 Row was deleted since Shuffle Master 1-28.

VII A-37 E4.1-b Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-37 Row was deleted since Shuffle Master 1-28.
NUREG-1832

E-340 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-38 C1.1-a Piping, 

piping 

compone

nts, and 

piping 

elements

Steel 

(without 

lining/coa

ting or 

with 

degraded 

lining/coa

ting)

Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-38 C1.1-a 

C1.2-a 

C1.5-a 

C1.6-a 

H2.1-b 

C3.1-a 

C3.2-a 

C3.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel 

(with or 

without 

lining/coa

ting or 

with 

degraded 

lining/coa

ting)

Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

fouling, and 

lining/coating 

degradation

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-39 A3.2-a 

A3.3-a 

A3.5-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

elastome

r lining

Treated 

borated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion 

(only for steel 

after lining 

degradation)

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-341 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-39 A3.2-a 

A3.3-a 

A3.5-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

elastome

r lining

Treated 

borated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion 

(only for steel 

after lining 

degradation)

Chapter XI.M2, "Water Chemistry," for PWR 

primary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-40 A4.2-a 

A4.3-a 

A4.5-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

elastome

r lining or 

stainless 

steel 

cladding

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion 

(only for steel 

after 

lining/claddin

g 

degradation)

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-40 A4.2-a 

A4.3-a 

A4.5-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

elastome

r lining or 

stainless 

steel 

cladding

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion 

(only for steel 

after 

lining/claddin

g 

degradation)

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-41 E3.2-a Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

Chapter XI.M25, "BWR Reactor Water Cleanup 

System"

No
NUREG-1832

E-342 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

cracking

VII A-41 Row was deleted since Shuffle Master 1-28.

VII A-42 E3.2-b Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-42 Row was deleted since Shuffle Master 1-28.

VII A-43 C3.1-a 

C3.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-43 C3.1-a 

C3.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-44 C1.1-a 

C1.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
September 2005

E-343 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

and fouling

VII A-44 C1.1-a 

C1.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-45 G.6-b Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No

VII A-45 G.6-b Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No
NUREG-1832

E-344 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-46 F1.2-a 

F2.2-a 

F3.2-a 

F4.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Condens

ation 

(External)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-46 F1.2-a 

F2.2-a 

F3.2-a 

F4.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Condens

ation 

(External)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-47 C1.1-a 

C1.2-a 

C3.1-a 

C3.2-a 

G.6-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-47 C1.1-a 

C1.2-a 

C3.1-a 

C3.2-a 

G.6-b 

H2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-50 C2.3-a Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion, 

and selective 

leaching

Chapter XI.M21, "Closed-Cycle Cooling Water 

System," and Chapter XI.M33, "Selective 

Leaching of Materials"

No

VII A-50 C2.3-a 

F3. 

Piping, 

piping 

compone

nts, and 

Gray cast 

iron

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-345 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

VII A-51 C1.5-a Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-51 C1.5-a 

C3. G. 

H2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-52 C2.2-a Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-52 C2.2-a Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-53 C3.2-a Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
NUREG-1832

E-346 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-53 C3.2-a Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-54 C1.1-a 

C1.2-a 

C1.4-a 

C1.6-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-54 C1.1-a 

C1.2-a 

C1.4-a 

C1.6-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-55 G.6-a 

G.6-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No

VII A-55 G.6-a 

G.6-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion, 

and fouling

Chapter XI.M27, "Fire Water System" No

VII A-56 A3.3-b Piping, 

piping 

compone

nts, and 

piping 

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714

No
September 2005

E-347 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

VII A-56 A3.3-b Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

VII A-57 E1.1-a 

E1.3-a 

E1.7-a 

E1.8-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-57 E1.1-a 

E1.3-a 

E1.7-a 

E1.8-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

borated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-58 A4.1-a 

A4.6-a 

E4.1-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-58 A4.1-a 

A4.6-a 

E4.1-a 

E3. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-348 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-59 E2.1-a 

E2.2-a 

E2.3-a 

E2.4-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Sodium 

pentabor

ate 

solution

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-59 E2.1-a 

E2.2-a 

E2.3-a 

E2.4-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Sodium 

pentabor

ate 

solution 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-60 E3.1-a Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M25, "BWR Reactor Water Cleanup 

System"

No

VII A-60 E3.1-a 

E3.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

intergranular 

stress 

corrosion 

cracking

Chapter XI.M25, "BWR Reactor Water Cleanup 

System"

No

VII A-61 E4.1-c 

E4.3-a 

Piping,

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water in BWRVIP-29 (EPRI TR-103515)

No
September 2005

E-349 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-61 E4.1-c 

E4.3-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M7, "BWR Stress Corrosion Cracking," 

andChapter XI.M2, "Water Chemistry," for BWR 

water

No

VII A-62 E3.1-b 

E3.2-b 

E4.1-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-62 E3.1-b 

E3.2-b 

E4.1-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Cumulative 

fatigue

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VII A-63 A3.4-a 

A4.4-a 

E1.8-c 

E4.4-a 

C2. E3. 

F1. F2. 

F3. F4.

Heat 

exchange

r shell 

side 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-63 A3.4-a 

A4.4-a 

E1.8-c 

E4.4-a 

C2. E3. 

F1. F2. 

F3. F4.

Heat 

exchange

r 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-35

0 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-64 C1.3-a Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-64 C1.3-a Heat 

exchange

r 

compone

nts

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, 

galvanic, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-65 C1.3-a Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
September 2005

E-351 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-65 C1.3-a Heat 

exchange

r 

compone

nts

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, 

galvanic, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-66 C1.3-a Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-66 C1.3-a Heat 

exchange

r 

compone

nts

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII A-67 E3.4-b 

E4.4-a

Heat 

exchange

r shell 

side 

compone

nts 

including 

tubes

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Closed 

cycle 

cooling 

water

Loss of 

material/ 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-352 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-67 E3.4-b 

E4.4-a 

Heat 

exchange

r 

compone

nts

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Closed 

cycle 

cooling 

water

Loss of 

material/ 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-68 E3.4-a Heat

exchange

r shell 

side 

compone

nts 

including 

tubes

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-68 E3.4-a Heat 

exchange

r 

compone

nts

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII A-69 E1.8-b Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M2, "Water Chemistry,"for PWR 

primary water in EPRI TR- 105714The AMP is to 

be augmented by verifying the absence of 

cracking due to stress corrosion cracking and 

cyclic loading, or loss of material due to pitting and 

crevice corrosion. An acceptable verification 

program is to include temperature and 

radioactivity monitoring of the shell side water, and 

eddy current testing of tubes.

Yes, plantspecific
September 2005

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-69 E1.8-b Nonregenerat

ive heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M2, "Water Chemistry," for PWR 

primary water.The AMP is to be augmented by 

verifying the absence of cracking due to stress 

corrosion cracking and cyclic loading, or loss of 

material due to pitting and crevice corrosion. An 

acceptable verification program is to include 

temperature and radioactivity monitoring of the 

shell side water, and eddy current testing of tubes.

Yes, plantspecific

VII A-70 A4.4-b Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Treated 

water

Loss of 

material/ 

Pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-70 A4.4-b Heat 

exchange

r 

compone

nts

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Treated 

water

Loss of 

material/ 

Pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-71 E3.4-a Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-354 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-71 E3.4-a Heat 

exchange

r 

compone

nts

Stainless 

steel; 

steel with 

stainless 

steel 

cladding

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-72 C1.3-b Heat 

exchange

r tubes

Copper 

alloy

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-72 C1.3-b Heat 

exchange

r tubes

Copper 

alloy

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII A-73 F1.1-c 

F2.1-c 

F3.1-c 

F4.1-c 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

wear

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-73 F1.1-c 

F2.1-c 

F3.1-c 

F4.1-c 

Elastome

r seals 

and 

compone

nts

Elastome

rs

Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

wear

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-76 E1.5-a Highpressure 

pumpCas

ing and 

closure 

bolting

Stainless 

steel; 

steel

Treated 

borated 

water

Cracking/ 

cyclic loading

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-76 E1.5-a Highpressure 

pumpCas

ing

Stainless 

steel

Treated 

borated 

water

Cracking/ 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M2, "Water Chemistry," for PWR 

primary waterThe AMP is to be augmented by 

verifying the absence of cracking due to stress 

corrosion cracking and cyclic loading. A plant 

specific aging management program is to be 

evaluated.

Yes, plantspecific
September 2005

E-355 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-77 I.1-b External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-77 I.1-b External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A-78 I.1-b External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-78 I.1-b External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No
NUREG-1832

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-79 A3.1-a 

A3.2-b 

A3.2-c 

A3.3-c 

A3.4-b 

A3.5-b 

A3.6-a 

E1.1-b 

E1.2-a 

E1.3-b 

E1.4-a 

E1.5-b 

E1.6-a 

E1.7-b 

E1.8-d 

E1.9-a 

E1.10-a 

I.1-a 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
September 2005

E-357 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-79 A3.1-a 

A3.2-b 

A3.2-c 

A3.3-c 

A3.4-b 

A3.5-b 

A3.6-a 

E1.1-b 

E1.2-a 

E1.3-b 

E1.4-a 

E1.5-b 

E1.6-a 

E1.7-b 

E1.8-d 

E1.9-a 

E1.10-a 

I.1-a 

External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VII A-80 D.1-a 

D.2-a 

D.3-a 

D.4-a 

D.5-a 

D.6-a 

Piping 

and 

compone

nts 

external 

surfaces 

and 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-80 D.1-a 

D.2-a 

D.3-a 

D.4-a 

D.5-a 

D.6-a 

Piping 

and 

compone

nts 

external 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A-81 I.1-b External 

surfaces

Steel Condens

ation 

Loss of 

material/ 

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-358 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

(External) General 

corrosion

VII A-81 I.1-b External 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII A-82 G.7-a Reactor 

coolant 

pump oil 

collection 

systemTa

nk

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant specific aging management program that 

determines the thickness of the lower portion of 

the tank is to be evaluated. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-82 G.7-a Reactor 

coolant 

pump oil 

collection 

systemTa

nk

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented to evaluate the thickness 

of the lower portion of the tank. See Chapter 

XI.M32, "One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-83 G.7-b Reactor 

coolant 

pump oil 

collection 

systemPi

ping, 

tubing, 

valve 

bodies

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant specific aging management program that 

monitors the degradation of the components is to 

be evaluated. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII A-83 G.7-b Reactor 

coolant 

pump oil 

collection 

systemPi

ping, 

tubing, 

Steel Lubricatin

g oil

Loss of 

material/ 

general,

pitting, and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

valve 

bodies

VII A-84 E1.7-c Regener

ative heat 

exchange

r tube 

and shell 

side 

compone

nts 

including 

tubes

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M2, "Water Chemistry,"for PWR 

primary water in EPRI TR- 105714The AMP is to 

be augmented by verifying the absence of 

cracking due to stress corrosion cracking and 

cyclic loading. A plant specific aging management 

program is to be evaluated.

Yes, plantspecific

VII A-84 E1.7-c Heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking, 

cyclic loading

Chapter XI.M2, "Water Chemistry," for PWR 

primary waterThe AMP is to be augmented by 

verifying the absence of cracking due to stress 

corrosion cracking and cyclic loading. A plant 

specific aging management program is to be 

evaluated.

Yes, plantspecific

VII A-85 E3.3-d Regener

ative heat 

exchange

r tube 

and shell 

side 

compone

nts 

including 

tubes

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-360 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-85 E3.3-d Regener

ative heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-86 A2.1-a Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- PWR

Boraflex Treated 

borated 

water

Reduction of 

neutronabsorbing 

capacity/ 

boraflex 

degradation

Chapter XI.M22, "Boraflex Monitoring" No

VII A-86 A2.1-a Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- PWR

Boraflex Treated 

borated 

water

Reduction of 

neutronabsorbing 

capacity/ 

boraflex 

degradation

Chapter XI.M22, "Boraflex Monitoring" No

VII A-87 A2.1-a Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- BWR

Boraflex Treated 

water

Reduction of 

neutronabsorbing 

capacity/ 

boraflex 

degradation

Chapter XI.M22, "Boraflex Monitoring" No

VII A-87 A2.1-a Spent 

fuel 

storage 

racksNeu

tronBoraflex Treated 

water

Reduction of 

neutronabsorbing 

capacity/ 

boraflex 

Chapter XI.M22, "Boraflex Monitoring" No
September 2005

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

absorbin

g sheets 

- BWR

degradation

VII A-88 A2.1-b Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- PWR

Boral,bor

on steel

Treated 

borated 

water

Reduction of 

neutronabsorbing 

capacity and 

loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-88 A2.1-b Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- PWR

Boral,bor

on steel

Treated 

borated 

water

Reduction of 

neutronabsorbing 

capacity and 

loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-89 A2.1-b Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- BWR

Boral,bor

on steel

Treated 

water

Reduction of 

neutronabsorbing 

capacity and 

loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-362 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-89 A2.1-b Spent 

fuel 

storage 

racksNeu

tronabsorbin

g sheets 

- BWR

Boral,bor

on steel

Treated 

water

Reduction of 

neutronabsorbing 

capacity and 

loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII A-90 G.1-b 

G.2-b 

G.3-b 

G.4-b 

G.5-a 

Structural 

fire 

barriers –

walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Concrete 

cracking and 

spalling/ 

freeze-thaw, 

aggressive 

chemical 

attack, and 

reaction with 

aggregates

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-90 G.1-b 

G.2-b 

G.3-b 

G.4-b 

G.5-a 

Structural 

fire 

barriers:

Walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Concrete 

cracking and 

spalling/ 

aggressive 

chemical 

attack, and 

reaction with 

aggregates

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-91 G.1-c 

G.2-c 

G.3-c 

G.4-c 

G.5-b 

Structural 

fire 

barriers –

walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Loss of 

material/ 

corrosion of 

embedded 

steel

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No
September 2005

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Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-91 G.1-c 

G.2-c 

G.3-c 

G.4-c 

G.5-b 

Structural 

fire 

barriers:

Walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

indoor 

uncontroll

ed

Loss of 

material/ 

corrosion of 

embedded 

steel

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-92 G.1-b 

G.2-b 

G.3-b 

G.4-b 

Structural 

fire 

barriers –

walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

outdoor

Concrete 

cracking and 

spalling/ 

freeze-thaw, 

aggressive 

chemical 

attack, and 

reaction with 

aggregates

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-92 G.1-b 

G.2-b 

G.3-b 

G.4-b 

Structural 

fire 

barriers:

Walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

outdoor

Concrete 

cracking and 

spalling/ 

freeze-thaw, 

aggressive 

chemical 

attack, and 

reaction with 

aggregates

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-93 G.1-c 

G.2-c 

G.3-c 

G.4-c 

Structural 

fire 

barriers –

walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material/ 

corrosion of 

embedded 

steel

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No
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E-364 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII A-93 G.1-c 

G.2-c 

G.3-c 

G.4-c 

Structural 

fire 

barriers:

Walls, 

ceilings 

and 

floors

Reinforce

d 

concrete

Air –

outdoor

Loss of 

material/ 

corrosion of 

embedded 

steel

Chapter XI.M26, "Fire Protection" and Chapter 

XI.S6, "Structures Monitoring Program"

No

VII A-94 A1.1-a Structural 

Steel

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No

VII A-94 A1.1-a Structural 

Steel

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.S6, "Structures Monitoring Program" No

VII A-95 H1.4-b Tanks Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M29, "Aboveground Carbon Steel 

Tanks"

No

VII A-95 H1.4-b Tanks Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M29, "Aboveground Steel Tanks" No

VII A-96 A2.1-c Spent 

fuel 

storage 

racksStor

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515). 

No
September 2005

E-365 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

age racks 

- BWR

VII A-96 A2.1-c Spent 

fuel 

storage 

racksStor

age racks 

- BWR

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR water No

VII A-97 A2.1-c Spent 

fuel 

storage 

racksStor

age racks 

- PWR

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714

No

VII A-97 A2.1-c Spent 

fuel 

storage 

racksStor

age racks 

- PWR

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

VII AP-1 A3. E1. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VII AP-1 A3. E1. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No
NUREG-1832

E-366 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP10J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil (no 

water 

pooling)

None None No

VII AP10Row was deleted since Shuffle Master 1-28.

VII AP11J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

<15% Zn

Air with 

borated 

water 

leakage

None None No

VII AP11J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

<15% Zn

Air with 

borated 

water 

leakage

None None No

VII AP12A3. A4. 

C2. E1. 

E3. E4. 

F1. F2. 

F3. F4. 

H1. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP12A3. A4. 

C2. E1. 

E3. E4. 

F1. F2. 

F3. F4. 

H1. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP13J. Piping, 

piping 

compone

Galvaniz

ed steel

Air –

indoor 

uncontroll

None None No
September 2005

E-367 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

ed

VII AP13J. Piping, 

piping 

compone

nts, and 

piping 

elements

Galvaniz

ed steel

Air –

indoor 

uncontroll

ed

None None No

VII AP14J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP14J. Piping 

elements

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP15J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Lubricatin

g oil

None None No

VII AP15J. Piping 

elements

Glass Lubricatin

g oil

None None No

VII AP16J. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No
NUREG-1832

E-368 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP16J. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP17J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP17J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP18J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

VII AP18J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air with 

borated 

water 

leakage

None None No

VII AP19J. Piping, 

piping 

compone

nts, and 

piping 

Stainless 

steel

Concrete None None No
September 2005

E-369 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

VII AP19J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

VII AP-2 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

controlled 

(External)

None None No

VII AP-2 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

controlled 

(External)

None None No

VII AP20J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Dried Air None None No

VII AP20J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Dried Air None None No
NUREG-1832

E-370 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP21J. Piping, 

piping

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil (no 

water 

pooling)

None None No

VII AP21Row was deleted since Shuffle Master 1-28.

VII AP22J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

VII AP22J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

VII AP25C1. C3. 

H2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel with 

internal 

lining or 

coating

Raw 

water

Loss of 

material/ 

lining or 

coating 

degradation

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP25Row was deleted since Shuffle Master 1-28.

VII AP26I. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-371 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP26I. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening 

Chapter XI.M18, "Bolting Integrity" No

VII AP27I. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII AP27I. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII AP28I. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII AP28I. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VII AP29C1. C3. 

G. H2.

Piping, 

piping 

compone

nts, and 

Gray cast 

iron

Untreate

d water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
NUREG-1832

E-372 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

VII AP29Row was deleted since Shuffle Master 1-28.

VII AP-3 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

VII AP-3 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

VII AP30C1. C2. 

E1. E4. 

F1. F2. 

F3. F4. 

G. H2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP30C1. C2. 

E1. E4. 

F1. F2.

F3. F4. 

G. H2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP31A3. A4. 

C2. E1. 

E3. E4. 

F1. F2. 

F3. F4. 

Piping, 

piping 

compone

nts, and 

piping 

Gray cast 

iron

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-373 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

G. elements

VII AP31A3. A4. 

C2. E1. 

E3. E4. 

F1. F2. 

F4. G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP32A4. C2. 

E3. E4. 

K.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP32A4. C2. 

E3. E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP33H2. Diesel 

engine 

exhaust 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Diesel 

exhaust

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-374 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP33H2. Diesel 

engine 

exhaustP

iping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Diesel 

exhaust

Cracking/ 

stress 

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP34E1. F1. 

F3. 

Heat 

exchange

r tubes

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP34E1. F1. 

F3. 

Heat 

exchange

r 

compone

nts

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP35H1. H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Fuel oil Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M30, "Fuel Oil Chemistry" The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP35H1. H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Fuel oil Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

Chapter XI.M30, "Fuel Oil Chemistry"The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-375 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

influenced 

corrosion

VII AP36J. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air –

indoor 

controlled 

(External)

None None No

VII AP36J. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Air –

indoor 

controlled 

(External)

None None No

VII AP37J. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Gas None None No

VII AP37J. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Gas None None No
NUREG-1832

E-376 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP38A4. E3. 

E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry" The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP38A4. E3. 

E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP39H2. Heat 

exchange

r shell 

side 

compone

nts

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP39H2. Heat 

exchange

r 

compone

nts

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-377 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP-4 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Dried Air None None No

VII AP-4 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Dried Air None None No

VII AP40G. H2. Heat 

exchange

r tubes

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP40G. H2. Heat 

exchange

r 

compone

nts

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII AP41F1. F2. 

F3. F4. 

G. H2.

Heat 

exchange

r tubes

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-378 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP41F1. F2. 

F3. F4. 

G. H2.

Heat 

exchange

r 

compone

nts

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VII AP42C1. C3. 

G. H1. 

H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP42Row was deleted since Shuffle Master 1-28.

VII AP43A3. A4. 

C2.E1. 

E3. E4. 

F1. F2. 

F3. F4. 

H1. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP43A3. A4. 

C2. E1. 

E3. E4. 

F1. F2. 

F3. F4. 

H1. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP44H1. H2. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Fuel oil 

(Water as 

a 

contamin

ant)

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M30, "Fuel Oil Chemistry" The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-379 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP44H1. H2. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Fuel oil Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M30, "Fuel Oil Chemistry"The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP45H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP45H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP46H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP46Row was deleted since Shuffle Master 1-28.
NUREG-1832

E-380 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP47C1. C2. 

E1. E4. 

G. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP47C1. C2. 

E1. E4. 

G. H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP48J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Air None None No

VII AP48J. Piping 

elements

Glass Air None None No

VII AP49J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Fuel oil None None No

VII AP49J. Piping 

elements

Glass Fuel oil None None No

VII AP-5 J. Piping, 

piping 

compone

nts, and 

Steel Lubricatin

g oil (no 

water 

pooling)

None None No
September 2005

E-381 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

VII AP-5 Row was deleted since Shuffle Master 1-28.

VII AP50J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Raw 

water

None None No

VII AP50J. Piping 

elements

Glass Raw 

water

None None No

VII AP51J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Treated 

water

None None No

VII AP51J. Piping 

elements

Glass Treated 

water

None None No

VII AP52J. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Treated 

borated 

water

None None No

VII AP52J. Piping 

elements

Glass Treated 

borated 

water

None None No

VII AP53C1. C3. Piping, 

piping 

compone

Nickel 

alloy

Raw 

water

Loss of 

material/ 

pitting and 

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
NUREG-1832

E-382 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

crevice 

corrosion

VII AP53C1. C3. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP54G. H1. 

H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Fuel oil Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M30, "Fuel Oil Chemistry" No

VII AP54G. H1. 

H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Fuel oil Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M30, "Fuel Oil Chemistry"The AMP is 

to be augmented by verifying the effectiveness of 

fuel oil chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP55H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
September 2005

E-383 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP55H2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP56C1. C3. 

G. H1. 

H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP56C1. C3. 

G. H1. 

H2.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP57C2. E3. 

K.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP57Row was deleted since Shuffle Master 1-28.

VII AP59C1. C2. 

E1. E4. 

H2. G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-384 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

corrosion

VII AP59C1. C2. 

E1. E4. 

H2. G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP-6 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

VII AP-6 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

VII AP60C2. E3. 

E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress

corrosion 

cracking

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-385 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP60C2. E3. 

E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion

cracking

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP61C1. C3. 

G. H2.

Heat 

exchange

r tubes

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP61C1. C3. 

G. H2.

Heat 

exchange

r tubes

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP62A4. E3. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry" No

VII AP62A4. E3. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP63C2. E3. 

E4. 

Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP63C2. E3. 

E4. 

Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP64A4. C2. 

E3. E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Treated 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-386 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP64A4. E3. 

E4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Treated 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP65E1. F1. 

F3. 

Heat 

exchange

r tubes

Copper 

alloy 

>15% Zn

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP65E1. F1. 

F3. 

Heat 

exchange

r 

compone

nts

Copper 

alloy 

>15% Zn

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VII AP66I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VII AP66I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VII AP67K. Piping, 

piping 

compone

nts and 

piping 

elements

Stainless 

steel

Waste 

water 

(untreate

d or 

treated 

water)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP67Row was deleted since Shuffle Master 1-28.
September 2005

E-387 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP69K. Piping, 

piping 

compone

nts and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP69Row was deleted since Shuffle Master 1-28.

VII AP-7 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Cast 

austenitic 

stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

VII AP-7 Row was deleted since Shuffle Master 1-28.

VII AP70K. Piping, 

piping 

compone

nts and 

piping 

elements

Copper 

alloy

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP70Row was deleted since Shuffle Master 1-28.

VII AP71K. Piping, 

piping 

compone

nts and 

piping 

elements

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP71Row was deleted since Shuffle Master 1-28.

VII AP72K. Piping, 

piping 

compone

nts and 

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-388 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

corrosion

VII AP72Row was deleted since Shuffle Master 1-28.

VII AP73Did not exist in Shuffle Master 1-28.

VII AP73E2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Sodium 

pentabor

ate 

solution

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VII AP74Did not exist in Shuffle Master 1-28.

VII AP74F1. F2. 

F3. F4.

Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Condens

ation

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VII AP75Did not exist in Shuffle Master 1-28.

VII AP75C1. Elastome

r seals 

and 

compone

nts

Elastome

rs

Raw 

water

Hardening 

and loss of 

strength/ 

elastomer 

degradation

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP76Did not exist in Shuffle Master 1-28.
September 2005

E-389 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP76C1. Elastome

r seals 

and 

compone

nts

Elastome

rs

Raw 

water

Loss of 

material/ 

erosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VII AP77Did not exist in Shuffle Master 1-28.

VII AP77F1. F2. 

F3. F4.

Heat 

exchange

r tubes

Steel Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP78Did not exist in Shuffle Master 1-28.

VII AP78G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to

be evaluated.

Yes, plantspecific

VII AP79Did not exist in Shuffle Master 1-28.

VII AP79E1. A2. 

A3. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

Steel; 

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

VII AP-8 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Dried Air None None No
NUREG-1832

E-390 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VII AP-8 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Dried Air None None No

VII AP80Did not exist in Shuffle Master 1-28.

VII AP80C2. F1. 

F2. F3.

Heat 

exchange

r tubes

Copper 

Alloy

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VII AP81Did not exist in Shuffle Master 1-28.

VII AP81D. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Condens

ation 

(Internal)

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M24, "Compressed Air Monitoring" No

VII AP82Did not exist in Shuffle Master 1-28.

VII AP82E1. Piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Stainless 

steel

Treated 

borated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

primary water

No

VII AP83Did not exist in Shuffle Master 1-28.

VII AP83G. Piping, 

piping 

compone

nts, and 

Aluminu

m

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

Chapter XI.M26, "Fire Protection" No
September 2005

E-391 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

corrosion

VII AP85Did not exist in Shuffle Master 1-28.

VII AP85E1. Pump 

Casings

Steel with 

stainless 

steel 

cladding

Treated 

borated 

water

Loss of 

material/ 

cladding 

breach

A plant-specific aging management program is to 

be evaluated.Reference NRC Information Notice 

94-63, "Boric Acid Corrosion of Charging Pump 

Casings Caused by Cladding Cracks."

Yes, verify 

plant-specific 

program 

addresses 

cladding 

breach

VII AP-9 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No

VII AP-9 J. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No
NUREG-1832

E-392 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-01 E.5-d 

G.1-e 

G.4-d 

Buried 

piping, 

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel 

(with or 

without 

coating 

or 

wrapping

)

Soil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

VIII S-01 E.5-d 

G.1-e 

G.4-d 

Buried 

piping,

piping 

compone

nts, 

piping 

elements, 

and tanks

Steel 

(with or 

without 

coating 

or 

wrapping

)

Soil Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M28, "Buried Piping and Tanks 

Surveillance," orChapter XI.M34, "Buried Piping 

and Tanks Inspection"

No Yes, 

detection of 

aging effects 

and operating 

experience 

are to be 

further 

evaluated

VIII S-02 H.2-a Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VIII S-02 H.2-a Closure 

bolting

Steel Air with 

steam or 

water 

leakage

Loss of 

material/ 

general 

corrosion

Chapter XI.M18, "Bolting Integrity" No
September 2005

E-393 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-03 H.2-b Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

VIII S-03 H.2-b Closure 

bolting

Highstrength 

steel

Air with 

steam or 

water 

leakage

Cracking/ 

cyclic 

loading, 

stress 

corrosion 

cracking

Chapter XI.M18, "Bolting Integrity" No

VIII S-04 A.1-b 

A.2-b 

C.1-b 

C.2-b J.

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-04 A.1-b 

A.2-b 

C.1-b 

C.2-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-05 B2.1-a 

B2.2-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

pitting and 

crevice

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515). 

No

VIII S-05 B2.1-a 

B2.2-b 

Piping, 

piping 

compone

nts, and 

Steel Steam Loss of 

material/ 

pitting and 

crevice 

Chapter XI.M2, "Water Chemistry," for BWR water No
NUREG-1832

E-394 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

corrosion

VIII S-06 A.1-b 

A.2-b 

C.1-b 

C.2-b J. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-06 A.1-b 

A.2-b 

C.1-b 

C.2-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-07 B1.1-a 

B1.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134

No

VIII S-07 B1.1-a 

B1.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water

No

VIII S-08 B1.1-b 

B2.1-c 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-395 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-08 B1.1-b 

B2.1-c 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam or 

treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VIII S-09 D2.1-b 

D2.2-b 

D2.3-b 

E.1-b 

E.2-b 

E.3-a 

E.5-a 

E.6-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-09 B2. C. 

D2.1-b 

D2.2-b 

D2.3-b 

E.1-b 

E.2-b 

E.3-a 

E.5-a 

E.6-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-10 D1.1-c 

D1.2-b 

D1.3-a 

E.1-b 

E.2-b 

E.3-a 

E.5-a 

E.6-a 

F.1-b 

F.2-b 

F.3-a 

G.1-c 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-396 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

G.2-a 

G.3-a 

G.4-a 

VIII S-10 B1. C. 

D1.1-c 

D1.2-b 

D1.3-a 

E.1-b 

E.2-b 

E.3-a 

E.5-a 

E.6-a 

F.1-b 

F.2-b 

F.3-a 

G.1-c 

G.2-a 

G.3-a 

G.4-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-11 D1.1-b 

D2.1-c 

G.1-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA
September 2005

E-397 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-11 D1.1-b 

D2.1-c 

G.1-b 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Cumulative 

fatigue 

damage/ 

fatigue

Fatigue is a time-limited aging analysis (TLAA) to 

be evaluated for the period of extended operation. 

See the Standard Review Plan, Section 4.3 "Metal 

Fatigue," for acceptable methods for meeting the 

requirements of 10 CFR 54.21(c)(1).

Yes,TLAA

VIII S-12 G.1-d Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Untreate

d water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII S-12 G.1-d Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII S-13 E.5-b Tanks Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-398 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-13 E.5-a 

E.5-b 

G.4-a 

G.4-b 

Tanks Steel, 

Stainless 

steel

Treated 

water

Loss of 

material/ 

general (steel 

only), pitting 

and crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-14 E.5-b 

G.4-b 

Tanks Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-14 Row was deleted since Shuffle Master 1-28.

VIII S-15 A.1-a 

A.2-a 

B1.1-c 

B1.2-b 

B2.1-b 

B2.2-a 

C.1-a 

C.2-a J.

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

VIII S-15 A.1-a 

A.2-a 

B1.1-c 

B1.2-b 

B2.1-b 

B2.2-a 

C.1-a 

C.2-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No
September 2005

E-399 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-16 D1.1-a 

D1.2-a 

D1.3-b 

D2.1-a 

D2.2-a 

D2.3-a 

E.1-a 

E.2-a 

F.1-a 

F.2-a 

G.1-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

VIII S-16 D1.1-a 

D1.2-a 

D1.3-b 

D2.1-a 

D2.2-a 

D2.3-a 

E.1-a 

E.2-a 

F.1-a 

F.2-a 

G.1-a 

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Treated 

water

Wall thinning/ 

flowaccelerated 

corrosion

Chapter XI.M17, "Flow-Accelerated Corrosion" No

VIII S-17 G.5-d Heat 

exchange

r shell 

side 

compone

nts

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-400 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-17 G.5-d Heat 

exchange

r 

compone

nts

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-18 E.4-a 

E.4-d 

BWR 

heat 

exchange

r shell 

side 

compone

nts

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-18 E.4-a 

E.4-d 

Heat 

exchange

r 

compone

nts

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-19 E.4-a 

E.4-d 

F.4-a 

F.4-d 

PWR 

heat 

exchange

r shell 

side 

compone

nts

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-401 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-19 E.4-a 

E.4-d 

F.4-a 

F.4-d 

PWR 

heat 

exchange

r 

compone

nts

Steel Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-20 G.5-d Heat 

exchange

r shell 

side 

compone

nts

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII S-20 G.5-d Heat 

exchange

r 

compone

nts

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-21 E.4-a 

E.4-d 

BWR 

heat 

exchange

r shell 

side 

compone

nts

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-402 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-21 E.4-a 

E.4-d 

Heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-22 E.4-a 

E.4-d 

F.4-a 

F.4-d 

PWR 

heat 

exchange

r shell 

side 

compone

nts

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary water in EPRI TR -105714The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-22 E.4-a 

E.4-d 

F.4-a 

F.4-d 

PWR 

heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

primary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-23 E.4-e 

F.4-e 

G.5-c 

Heat 

exchange

r tube 

side 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII S-23 A. E.4-e 

F.4-e 

G.5-c 

Heat 

exchange

r 

compone

nts

Steel Closed 

cycle 

cooling 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
September 2005

E-403 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-24 E.4-b 

F.4-b 

G.5-a 

Heat 

exchange

r tube 

side 

compone

nts

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-24 E.4-b 

F.4-b 

G.5-a 

Heat 

exchange

r 

compone

nts

Steel Raw 

water

Loss of 

material/ 

general, 

pitting, 

crevice, 

galvanic, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-25 E.4-e 

F.4-e 

G.5-c 

Heat 

exchange

r tube 

side 

compone

nts

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII S-25 E.4-e 

F.4-e 

G.5-c 

Heat 

exchange

r 

compone

nts

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-404 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-26 E.4-b 

F.4-b 

G.5-a 

Heat 

exchange

r tube 

side 

compone

nts

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-26 E.4-b 

F.4-b 

G.5-a 

Heat 

exchange

r 

compone

nts

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion, 

and fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-27 G.5-b Heat 

exchange

r tubes

Steel Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-27 G.5-b Heat 

exchange

r tubes

Steel Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-28 E.4-c 

F.4-c 

G.5-b 

Heat 

exchange

r tubes

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-28 E.4-c 

F.4-c 

G.5-b 

Heat 

exchange

r tubes

Stainless 

steel

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII S-29 H.1-b External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-405 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-29 H.1-b External 

surfaces

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VIII S-30 H.1-a External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VIII S-30 H.1-a External 

surfaces

Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VIII S-31 E.5-c 

G.4-c 

Tanks Steel Air –

outdoor 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M29, "Aboveground Carbon Steel 

Tanks"

No

VIII S-31 E.5-c 

G.4-c 

Tanks Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M29, "Aboveground Steel Tanks" No

VIII S-32 H. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VIII S-32 H. Bolting Steel Air –

outdoor 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No
NUREG-1832

E-406 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-33 H. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

stress 

relaxation

Chapter XI.M18, "Bolting Integrity" No

VIII S-33 H. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

preload/ 

thermal 

effects, 

gasket creep, 

and selfloosening 

Chapter XI.M18, "Bolting Integrity" No

VIII S-34 H. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VIII S-34 H. Closure 

bolting

Steel Air –

indoor 

uncontroll

ed 

(External)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M18, "Bolting Integrity" No

VIII S-39 F.4-a Heat 

exchange

r tube 

side 

compone

nts 

including 

tubes

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
September 2005

E-407 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII S-39 F.4-a Heat 

exchange

r 

compone

nts

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII S-40 H. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VIII S-40 H. Bolting Steel Air with 

borated 

water 

leakage

Loss of 

material/ 

boric acid 

corrosion

Chapter XI.M10, "Boric Acid Corrosion" No

VIII S-41 H.1-b External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII S-41 H.1-b External 

surfaces

Steel Air –

outdoor 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VIII S-42 H.1-b External 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

General 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII S-42 H.1-b External 

surfaces

Steel Condens

ation 

(External)

Loss of 

material/ 

general 

corrosion

Chapter XI.M36, "External Surfaces Monitoring" No

VIII SP-1 I. Piping, 

piping 

compone

nts, and 

piping 

Steel Air –

indoor 

controlled 

(External)

None None No
NUREG-1832

E-408 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

VIII SP-1 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Air –

indoor 

controlled 

(External)

None None No

VIII SP10I. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Lubricatin

g oil

None None No

VIII SP10I. Piping 

elements

Glass Lubricatin

g oil

None None No

VIII SP11I. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP11I. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickel 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP12I. Piping, 

piping 

compone

nts, and 

piping 

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No
September 2005

E-409 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

VIII SP12I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP13I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

VIII SP13I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Concrete None None No

VIII SP14I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil (no 

water 

pooling)

None None No

VIII SP14Row was deleted since Shuffle Master 1-28.

VIII SP15I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No
NUREG-1832

E-410 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP15I. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Gas None None No

VIII SP16D1. F. 

G. E. 

D2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP16B1. C. 

D1. F. 

G. E. 

D2. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP17E. D1. 

F. G. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134The AMP is 

to be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP17B1. C. 

E. D1. 

F. G. 

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary waterThe AMP is to be augmented by 

verifying the effectiveness of water chemistry 

control. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP18B1. Piping, 

piping 

compone

Nickelbased 

alloys

Steam Loss of 

material/ 

pitting and 

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134

No
September 2005

E-411 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

nts, and 

piping 

elements

crevice 

corrosion

VIII SP18B1. Piping, 

piping 

compone

nts, and 

piping 

elements

Nickelbased 

alloys

Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water

No

VIII SP19E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP19E. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP-2 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No

VIII SP-2 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Concrete None None No
NUREG-1832

E-412 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP23I. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Gas None None No

VIII SP23I. Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Gas None None No

VIII SP24D1. D2. 

E. F. G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP24D1. D2. 

E. F. G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Aluminu

m

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP25A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
September 2005

E-413 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP25A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP26E. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP26E. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Soil Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP27E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP27A. E. F. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP28G. Piping, 

piping 

compone

nts, and 

piping 

Gray cast 

iron

Untreate

d water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
NUREG-1832

E-414 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements

VIII SP28A. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Gray cast 

iron

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP29E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP29E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper

alloy 

>15% Zn

Closed 

cycle 

cooling 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP-3 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Lubricatin

g oil (no 

water 

pooling)

None None No

VIII SP-3 Row was deleted since Shuffle Master 1-28.

VIII SP30E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No
September 2005

E-415 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP30A. E. F.

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Raw 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP31E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII SP31A. E. F. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII SP32A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP32A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Lubricatin

g oil

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated
NUREG-1832

E-416 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP33I. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Air None None No

VIII SP33I. Piping 

elements

Glass Air None None No

VIII SP34I. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Raw 

water

None None No

VIII SP34I. Piping 

elements

Glass Raw 

water

None None No

VIII SP35I. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Treated 

water

None None No

VIII SP35I. Piping 

elements

Glass Treated 

water

None None No

VIII SP36E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No
September 2005

E-417 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

corrosion

VIII SP36E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII SP37E. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP37E. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Soil Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP38A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific
NUREG-1832

E-418 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP38A. D1. 

D2. E. 

G.

Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Lubricatin

g oil

Loss of 

material/ 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP39E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP39E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP-4 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

VIII SP-4 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Gas None None No

VIII SP40E. F. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry" No
September 2005

E-419 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP40E. F. Heat 

exchange

r tubes

Stainless 

steel

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP41E. F. G. Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP41E. F. G. Heat 

exchange

r tubes

Stainless 

steel

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP42E. Tanks Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M21, "Closed Cycle Cooling Water 

System"The AMP is to be augmented by verifying 

the effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP42E. Tanks Stainless 

steel

Treated 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP43B1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134

No
NUREG-1832

E-420 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP43A. B1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water

No

VIII SP44B1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water in EPRI TR -102134

No

VIII SP44A. B1. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for PWR 

secondary water

No

VIII SP45B2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515).The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP45A. B2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M2, "Water Chemistry," for BWR 

waterThe AMP is to be augmented by verifying the 

effectiveness of water chemistry control. See 

Chapter XI.M32, "One-Time Inspection," for an 

acceptable verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP46B2. Piping, 

piping 

compone

nts, and 

Stainless 

steel

Steam Loss of 

material/ 

pitting and 

crevice 

Chapter XI.M2, "Water Chemistry," for BWR water 

in BWRVIP-29 (EPRI TR-103515). 

No
September 2005

E-421 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

piping 

elements

corrosion

VIII SP46A. B2. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Steam Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry," for BWR water No

VIII SP48J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Steam Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP48Row was deleted since Shuffle Master 1-28.

VIII SP-5 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No

VIII SP-5 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Gas None None No
NUREG-1832

E-422 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP51J. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Raw 

water

Loss of 

material/ 

general 

pitting, 

crevice, and 

microbiologic

ally 

influenced 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP51Row was deleted since Shuffle Master 1-28.

VIII SP52J. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Raw 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

A plant-specific aging management program is to 

be evaluated.

Yes, plantspecific

VIII SP52Row was deleted since Shuffle Master 1-28.

VIII SP53Did not exist in Shuffle Master 1-28.

VIII SP53G. Heat 

exchange

r tubes

Copper 

alloy

Lubricatin

g oil

Reduction of

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP54Did not exist in Shuffle Master 1-28.

VIII SP54E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Stainless 

steel

Closed 

cycle 

cooling 

water 

>60°C 

(>140°F)

Cracking/ 

stress 

corrosion 

cracking

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
September 2005

E-423 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP55Did not exist in Shuffle Master 1-28.

VIII SP55E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy 

>15% Zn

Treated 

water

Loss of 

material/ 

selective 

leaching

Chapter XI.M33, "Selective Leaching of Materials" No

VIII SP56Did not exist in Shuffle Master 1-28.

VIII SP56E. F. G. Heat 

exchange

r tubes

Copper 

alloy

Raw 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M20, "Open-Cycle Cooling Water 

System"

No

VIII SP57Did not exist in Shuffle Master 1-28.

VIII SP57E. Heat 

exchange

r tubes

Copper 

alloy

Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP58Did not exist in Shuffle Master 1-28.

VIII SP58E. F. G. Heat 

exchange

r tubes

Copper 

alloy

Treated 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP59Did not exist in Shuffle Master 1-28.

VIII SP59B1. Piping, 

piping 

compone

nts, and 

piping 

Steel Air –

outdoor 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No
NUREG-1832

E-424 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

elements corrosion

VIII SP-6 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP-6 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP60Did not exist in Shuffle Master 1-28.

VIII SP60B1. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Steel Condens

ation 

(Internal)

Loss of 

material/ 

general, 

pitting, and 

crevice 

corrosion

Chapter XI.M38, "Inspection of Internal Surfaces 

in Miscellaneous Piping and Ducting Components"

No

VIII SP61Did not exist in Shuffle Master 1-28.

VIII SP61A. F. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Treated 

water

Loss of 

material/ 

pitting and 

crevice 

corrosion

Chapter XI.M2, "Water Chemistry"The AMP is to 

be augmented by verifying the effectiveness of 

water chemistry control. See Chapter XI.M32, 

"One-Time Inspection," for an acceptable 

verification program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP62Did not exist in Shuffle Master 1-28.
September 2005

E-425 NUREG-1832

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP62G. Heat 

exchange

r tubes

Stainless 

steel

Lubricatin

g oil

Reduction of 

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP63Did not exist in Shuffle Master 1-28.

VIII SP63G. Heat 

exchange

r tubes

Steel Lubricatin

g oil

Reduction of 

heat transfer/ 

fouling

Chapter XI.M39, "Lubricating Oil Analysis"The 

AMP is to be augmented by verifying the 

effectiveness of the lubricating oil analysis 

program. See Chapter XI.M32, "One-Time 

Inspection," for an acceptable verification 

program.

Yes, 

detection of 

aging effects 

is to be 

evaluated

VIII SP64Did not exist in Shuffle Master 1-28.

VIII SP64A. E.4-e 

F.4-e 

G.5-c 

Heat 

exchange

r tubes

Steel Closed 

cycle 

cooling 

water

Reduction of 

heat transfer/ 

fouling

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP-7 I. Piping, 

piping 

compone

nts, and 

piping

elements

Copper 

alloy

Lubricatin

g oil (no 

water 

pooling)

None None No

VIII SP-7 Row was deleted since Shuffle Master 1-28.

VIII SP-8 E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No
NUREG-1832

E-426 September 2005

Table E: Aging Management Review Line -item Comparison

ID Item Related S/C Material Environ Aging 

Effect/ 

Mechanism

Aging Management Program (AMP) Further 

Evaluation

VIII SP-8 E. F. G. Piping, 

piping 

compone

nts, and 

piping 

elements

Copper 

alloy

Closed 

cycle 

cooling 

water

Loss of 

material/ 

pitting, 

crevice, and 

galvanic 

corrosion

Chapter XI.M21, "Closed-Cycle Cooling Water 

System"

No

VIII SP-9 I. Piping, 

piping 

compone

nts, and 

piping 

elements

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No

VIII SP-9 I. Piping 

elements

Glass Air –

indoor 

uncontroll

ed 

(External)

None None No