ML003719135
| ML003719135 | |
| Person / Time | |
|---|---|
| Site: | PROJ0690 |
| Issue date: | 05/26/2000 |
| From: | Charemagne Grimes NRC/NRR/DRIP/RLSB |
| To: | Lochbaum D, Walters D Nuclear Energy Institute, Union of Concerned Scientists |
| Lee S, NRR/RLSB, 415-3109 | |
| References | |
| Download: ML003719135 (87) | |
Text
May 26, 2000 Mr. Douglas J. Walters Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Mr. David Lochbaum Union of Concerned Scientists 1616 P. Street, NW, Suite 310 Washington, DC 20036-1495
SUBJECT:
DRAFT GENERIC AGING LESSONS LEARNED (GALL) REPORT FOR LICENSE RENEWAL, VOLUME 1 Gentlemen:
By letter dated April 24, 2000, we provided you with an early draft Standard Review Plan for License Renewal (SRP-LR) that is based on the draft Generic Aging Lessons Learned (GALL) report made available at our December 6, 1999, public workshop.
The draft SRP-LR provides guidance for the staff to review a license renewal application. The draft GALL report is an extensive tabulation/catalog of aging effects and evaluation of aging management programs. To facilitate tracing information between these documents, we have prepared a summary which bridges the draft SRP-LR and the GALL tabulation/catalog. We plan on dividing the GALL report into two volumes. Volume 1 would contain this summary and Volume 2 would contain the tabulation/catalog. We are forwarding our draft GALL report, Volume 1, for your information and comment.
We are seeking preliminary feedback on the draft SRP-LR and GALL report from all interested stakeholders, in preparation for issuing the SRP-LR and GALL report for public comments in August 2000, in accordance with the plan described during the workshop. If you have any questions regarding this matter, please contact Sam Lee at (301)415-3109.
Sincerely, IRA/
Christopher I. Grimes, Chief License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Project No. 690
Enclosure:
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PUBLIC R. Zimmerman J. Johnson D. Matthews S. Newberry C. Grimes C. Carpenter B. Zalcman J. Strosnider R. Wessman G. Bagchi K. Manoly W. Bateman J. Calvo M. Tchiltz G. Holahan T. Collins C. Gratton B. Boger J. Peralta J. Moore J. Rutberg R. Weisman B. Poole M. Mayfield S. Bahadur A. Murphy W. McDowell S. Droggitis RLSB Staff N. Dudley, ACRS - T2E26 A. Thadani M. Federline C. Julian R. Gardner D. Chyu M. Modes J. Vora
"UNITED STATES NUCLEAR REGULATORY COMMISSION
- )4 WASHINGTON, D.C. 20555-0001 i
May 26, 2000 Mr. Douglas J. Walters Mr. David Lochbaum Nuclear Energy Institute Union of Concerned Scientists 1776 I Street, NW, Suite 400 1616 P. Street, NW, Suite 310 Washington, DC 20006-3708 Washington, DC 20036-1495
SUBJECT:
DRAFT GENERIC AGING LEGSONS LEARNED (GALL) REPORT FOR LICENSE RENEWAL, VOLUME 1 Gentlemen:
By letter dated April 24, 2000, we provided you with an early draft Standard Review Plan for License Renewal (SRP-LR) that is based on the draft Generic Aging Lessons Learned (GALL) report made available at our December 6, 1999, public workshop.
The draft SRP-LR provides guidance for the staff to review a license renewal application. The draft GALL report is an extensive tabulation/catalog of aging effects and evaluation of aging management programs. To facilitate tracing information between these documents, we have prepared a summary which bridges the draft SRP-LR and the GALL tabulation/catalog. We plan on dividing the GALL report into two volumes. Volume 1 would contain this summary and Volume 2 would contain the tabulation/catalog. We are forwarding our draft GALL report, Volume 1, for your information and comment.
We ar-seeking preliminary -e-.;b&(k on the draft SRP-LR and GALL report from all interested stakeholders, in preparation for issuing the SRP-LR and GALL report for public comments in August 2000, in accordance with the plan described during the workshop. If you have any questions regarding this matter, please contact Sam Lee at (301)415-3109.
Sincerely, Christopher I.
idmes, Chief License Renewal and Standardization Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Project No. 690
Enclosure:
As stated cc w/encl: See next page
NUCLEAR ENERGY INSTITUTE (License Renewal Steering Committee)
Project No. 690 cc:
Mr. Dennis Harrison U.S. Department of Energy NE-42 Washington, D.C. 20585 Mr. Ricard P. Sedano, Commissioner State Liaison Officer Department of Public Service 112 State Street Drawer 20 Montipelier, Vermont 05620-2601 Mr. Douglas J. Walters Nuclear Energy Institute 1776 I Street, N.W.
Washington, DC 20006-3708 DJW@NEI.ORG National Whistleblower Center 3238 P Street, N.W.
Washington, DC 20007-2756 Mr. Garry Young Entergy Operations, Inc.
Arkansas Nuclear One 1448 SR 333 GSB-2E Russellville, Arkansas 72802 Mr. James P. Riccio Public Citizen's Critical Mass Energy Project 211 Pennsylvania Avenue, SE Washington, DC 20003 Mr. Robert Gill Duke Energy Corporation Mail Stop EC-12R P.O. Box 1006 Charlotte, NC 28201-1006 Mr. Charles R. Pierce Southern Nuclear Operating Co.
40 Inverness Center Parkway BIN B064 Birmingham, AL 35242 Carl J. Yoder Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway NEF 1st Floor Lusby, Maryland 20657 Chattooga River Watershed Coalition P. 0. Box 2006 Clayton, GA 30525 Mr. David Lochbaum Union of Concerned Scientists 1616 P. St., NW Suite 310 Washington, DC 20036-1495 Mr. Paul Gunter Director of the Reactor Watchdog Project Nuclear Information & Resource Service 1424 16th Street, NW, Suite 404 Washington, DC 20036
NUREG-xxxx Vol. 1 Generic, Aging.
,,essn Learned (GALL) Report Summary (Draft)
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Draft - May 25, 2000
TABLE OF CONTENTS Paaie No.
VOLUME I (
SUMMARY
)
TABLE O F CO NTENTS..............................................................................................................
i LIST O F TA BLES................................................
- i.
IN T R O D U C T IO N........................................................................................................................
1 GALL REPORT EVALUATION PROCESS.................................................................................
1 APPLICATION OF GALL REPORT........................................................................................
3
SUMMARY
AND RECOMMENDATIONS...............................................................................
3 APPENDIX: DESCRIPTION OF STRUCTURE AND COMPONENTS (ITEM NUMBER) IN THE GALL REPORT........................................................
39 PREFIX OF ITEM NUMBERS IN THE GALL REPORT.....................................
40 VOLUME 2 (TABULATION OF RESULTS)
TA BLE O F CO NTENTS..............................................................................................................
i MAJOR PLANT SECTIONS IN THE GALL REPORT..............................................................
ii APPENDIX: QUALITY ASSURANCE FOR AGING MANAGEMENT PROGRAMS............... A-1 Draft - 5/25/00 i
LIST OF TABLES Page No.
Table 1. NOT USED Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report............................................................
5 Table 3. Summary of-Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL.Report...........................................
17 Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report.......................................................
21 Table 5. Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of the GALL Report.........................
28 Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report...........................
30 Table 7. Summary of Aging Management Programs for the Electrical Components Evaluated in Chapter VI of the GALL Report......................................
38 Draft - 5/25/00 ii
INTRODUCTION By letter dated March 3, 1999, the Nuclear Energy Institute (NEI) documented the industry's views on how existing plant programs and activities should be credited for license renewal. The ucredit" issue was: to what extent should the staff review existing programs relied on for license renewal, to conclude that an applicant has demonstrated reasonable assurance that such programs will be effective in managing effects of aging on the functionality of structures and components in the period of extended operation. In a staff paper, SECY-99-148, "Credit for Existing Programs for License Renewal," dated June 3, 1999, the staff described options and provided a recommendation for credi!ing existing programs to improve the efficiency of the license renewal process.
By staff requirements memorandum (SRM) dated August 27, 1999, the Commission approved the staffs recommendation and directed the staff to focus the staff review guidance in the Standard Review Plan for License Renewal (SRP-LR) on areas where existing programs should be augmented for license renewal. The staff would develop a "Generic Aging Lessons Learned (GALL)" report which evaluates existing programs generically to document the basis for determining when existing programs are adequate without change and when existing programs should be augmented for license renewal.
The GALL report would be referenced in 1he SRP-LR as a basis for determining the adequacy of existing programs.
GALL REPORT EVALUATION PROCESS This report builds on a previous report, NUREG/CR-6490, "Nuclear Power Plant Generic Aging Lessons Learned (GALL)," which is a systematic compilation of plant aging information. NUREG/CR-6490 was based on information in over 500 documents:
Nuclear Plant Aging Research (NPAR) program reports sponsored by the Office of Nuclear Regulatory Research, Nuclear Management and Resources Council (NUMARC, now NEI) industry reports addressing license renewal, licensee event reports (LERs),
information notices, generic letters, and bulletins. The staff has also considered information contained in the reports provided by the Union of Concerned Scientists (UCS) in a May 5, 2000 letter.
Following the format of NUREG-0800 for major plant sections in pressurized and boiling water reactor power plants, the current effort reviews the aging effects on components and structures, identifies the relevant existing programs, and evaluates program attributes to manage aging effects for license renewal. This report is prepared with the technical assistance of Argonne National Laboratory and Brookhaven National Laboratory. As directed in the SRM, this report has the benefit of the experience from the staff members who conducted the review of the initial license renewal applications.
Also, as directed in the SRM, the staff is seeking stakeholders' participation in the development of this report.
The results of the GALL effort are presented in a table format in Volume 2. The table column headings are: Item, Structure and Component, Region of Interest, Material, Environment, Aging Effects, Aging Mechanism, References, Existing Aging Management Program, Evaluation and Technical Basis, and Further Evaluation. The adequacy of the existing aging management programs in managing certain aging effects for particular structures and components are evaluated based on the review of the following 10 program attributes (or elements):
Draft - 5/25/00 1
Description
- 1. Scope of program
- 2. Preventive actions
- 3. Parameters monitored or inspected
- 4. Detection of aging effects
- 5. Monitoring and trending
- 6. Acceptance criteria
- 7. Corrective actions
- 8. Confirmation process
- 9. Administrative controls
- 10. Operating experience Scope of program should include the specific structures and components subject to an aging management review for license renewal.
Preventive actions should mitigate or prevent aging degradation.
Parameters monitored or inspected should be linked to the degradation of the particular structure and component intended function(s).
Detection of aging effects should occur before there is a loss of the structure and component intended function(s).
Monitoring and trending should provide predictability of the extent of degradation and timely corrective or mitigative actions. The monitoring, inspection, testing frequency, and sample size should be appropriate for timely detection of aging effects.
Acceptance criteria, against which the need for corrective action will be evaluated, should ensure that the structure and component intended function(s) are maintained under all CLB design conditions during the period of extended operation.
Corrective actions, including root cause determination and prevention of recurrence, should be timely.
Confirmation process should ensure that preventive actions are adequate and that appropriate corrective actions have been completed and are effective.
Administrative controls should provide a formal review and approval process.
Operating experience of the aging management program, including past corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support that the effects of aging will be adequately managed so that the structure and component intended function(s) will be maintained during the period of extended operation.
If the evaluation determines that a program is adequate to manage certain aging effects for a particular structure and component without change, the "Further Evaluation" entry would indicate no further staff evaluation is recommended for license renewal.
Otherwise, it would recommend area(s) where the staff should focus its review.
Draft - 5/25/00 Element 2
APPLICATION OF GALL REPORT The GALL report is a technical basis document to the SRP-LR that provides staff guidance in reviewing a license renewal application. The GALL report should be treated in the same manner as an approved topical report that is applicable generically. The staff should not repeat its review of the matters described in the GALL report and should find it acceptable when the GALL report is referenced in a license renewal application.
The focus of the staff review should be on augmented programs for license renewal.
When referencing the GALL report, an applicant should briefly describe the system, components, materials, and environment, etc. in the plant, and state that they are bounded by the GALL report. The applicant should also state that the applicable aging effects and industry and plant-specific operating experience have been reviewed, and are bounded by the GALL report. Any outliers should be discussed in the application.
Then, the applicant should state that certain aging management programs and the staff evaluation, as described in the GALL report, are applicable to their plant. If the GALL report indicates that some of these aging management programs should be further evaluated, the applicant should provide the plant-specific proposal to augment these programs. For aging management programs and/or staff evaluation in the GALL report that do not apply or are otherwise different for their plant, the applicant should provide a plant-specific aging management review. Also, for components and/or applicable aging effects that are not addressed in the GALL report, the applicant should provide the plant specific aging management review.
The staff should not repeat its review of the matters described in the GALL report. The staff should ensure that the material presented in the GALL report is applicable to the specific plant under review. The staff should verify that the applicant has identified the appropriate programs as described and evaluated in the GALL report. The focus of the staff review should be on augmented programs for license renewal. The staff should also review information that is not addressed in the GALL report or is otherwise different from that in the GALL report.
The GALL report contains one acceptable way to manage aging effects for license renewal. An applicant may propose alternatives for staff review in its plant-specific license renewal application.
In addition, the GALL report does not address scoping of structures and components for license renewal. Scoping is plant specific and the results depend on the plant design and current licensing basis. The inclusion of a certain structure or component in the GALL report does not mean that this particular structure or component is within the scope of license renewal for all plants. Conversely, the omission of a certain structure or component in the GALL report does not mean that this particular structure or component is not within the scope of license renewal for any plants.
SUMMARY
AND RECOMMENDATIONS The GALL report contains an evaluation of a large number of structures and components in a plant. The evaluation result documented in the GALL report indicates that many of the existing programs are adequate to manage aging effects for license renewal without change. The GALL report also contains recommendations on specific areas where augmented programs should be considered for further evaluation. The GALL report Draft - 5/25/00 3
documents the technical basis for that determination. Tables 2 through 7 are summaries of the aging management review and these tables are the same as Tables 3.2-1 to 3.7-1, respectively, in the SRP-LR, except for an additional 5 t column in Tables 2 to 7 identifying the specific item numbers in the GALL report. Descriptions of the specific item numbers in the various GALL chapters. (I through VIII) are given in the Appendix of Volume 1. The specific item number and associated aging effect provide a pointer to the technical evaluation for the specific structure and component in Volume 2 (Tabulation of Results) of the GALL report.
The Appendix of Volume 2 of the GALL report addresses quality assurance for aging management programs. Safety-related structures and components are subject to 10 CFR Part 50, Appendix B requirements which are adequate to address the corrective actions, confirmation process, and administrative controls elements of an aging management program for license renewal. However, further evaluation is recommended regarding these program elements for non-safety-related structures and components that are subject to an aging management program for license renewal. An applicant has an option to expand the scope of its 10 CFR Part 50, Appendix B program to include the non-safety-related structures and components and address these program elements during the period of extended operation.
The GALL report provides a technical basis for crediting existing aging management programs and recommending area(s) for program augmentation and further evaluation.
The incorporation of the GALL report information into the SRP-LR, as directed by the Commission, should improve the efficiency of the license renewal process and better focus the staff review resources.
Draft - 5/25/00 4
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL BWR vessel Crack Inservice No IV.A1.1.1 components initiation inspection; water IV.A1.1.3, (except closure and growth chemistry IV.A1.3.2 studs, vessel from SCC IV.A1.3.9, flange leak and IGSCC IV.A1.4.1 detection line, IV.A1.4.5, vessel intermed-IV.A1.5.1 iate and lower IV.A1.5.6, shell and beltline IV.C1.2.1, welds, CRD IV.C1.3.1, housing, and IV.C1.3.2 vessel attachment welds); BWR CASS recirculation pump and valve components BWR vessel Crack Inservice No IV.A1.1.4 closure studs initiation inspection; and growth minimization and from SCC control of SCC and IGSCC BWR vessel Crack Plant-specific Yes; plant-IV.A1.1.5 flange leak initiation AMP specific AMP detection line and growth from SCC and IGSCC BWR vessel Crack Inservice Yes; some IV.A1.2.1 intermediate and initiation inspection; applicable IV.A1.2.6, lower shell and and growth water chemistry; BWRVIP IV.A1.7.1, beltline welds from SCC materials guidelines IV.C1.1.5 and control rod and IGSCC selection and under staff IV.C1.1.11 drive (CRD) processing to review mechanism reduce housing; BWR susceptibility to piping and sensitization fittings Draft - 5/25/00 5
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect!
Management Evaluation Number Component Mechanism Programs Recommended in GALL BWR vessel Crack Inservice Yes; IV.A1.2.7 attachment initiation inspection; augmented welds and growth water chemistry inspection from SCC program may and IGSCC be required BWR internals Crack Inservice Yes; some IV.B1.1.2 (except core initiation inspection; applicable IV.B1.1.4, plate access and growth water chemistry BWRVIP IV.B1.1.6 hole cover and from SCC guidelines IV.B1.1.8, core shroud and IASCC under staff IV.B1.2, support review IV.B1.3.1 structure)
IV.B1l.3.3, IV.B1.4.1 IV.B1.4.4, IV.B1.5.1 IV.B1I.5.8, IV.B1.7.1 IV.B1I.7.3 BWR core Crack Inservice Yes; some IV.B1.1.1 shroud head initiation inspection; applicable bolts and growth water chemistry BWRVIP from SCC guidelines under staff review BWR core plate Crack Inservice No IV.B1.1.5 access hole initiation inspection; cover and core and growth water chemistry shroud support from SCC structure and IASCC PWR vessel Crack Inservice No IV.A2.1.1, components initiation inspection; IV.A2.2.1 (except closure and growth water chemistry (except Ni-base studs, vessel from SCC alloys),
flange leak and IGSCC IV.A2.3.1 detection line, IV.A2.3.3, and CRD IV.A2.7.1, housing: Ni-base IV.C2.1.1 alloy com-IV.C2.1.4, ponents); PWR IV.C2.2.1 coolant system IV.C2.2.6, components IV.C2.5.7, (except CASS)
IV.C2.3.1, (con'd on next page Draft - 5/25/00 6
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL No IV.C2.4.1, IV.C2.5.1, IV.C2.5.2, IV.C2.5.3, IV.C2.5.6, IV.C2.5.8, IV.C2.5.10, IV.C2.6.1, IV.C2.6.2 PWR vessel Crack Inservice No IV.A2.1.3 closure studs initiation inspection; and growth minimization and from SCC control of SCC and IGSCC PWR reactor Crack Bolting integrity No IV.C2.3.3, coolant system initiation program; in-IV.C2.4.3, and steam and growth service IV.C2.5.9, generator bolting from SCC inspection IV.D1.1.10 and IGSCC PWR vessel Crack Plant-specific Yes; plant-IV.A2.1.4, flange leak initiation AMP specific AMP IV.C2.5.4 detection line and growth and pressurizer from SCC spray head and IGSCC PWR surge Crack Inservice Yes; plant-IV.C2.1.1 lines, nozzles initiation inspection; water specific AMP IV.C2.1.3, and safe ends and growth chemistry; plant-IV.C2.2.6, from SCC specific AMP IV.C2.5.3 and IGSCC PWR steam Crack Inservice Yes; IV.D2.1.1 generator initiation inspection, augmented IV.D2.1.3 pressure and growth materials inspection boundary from SCC selection program may be and IGSCC required PWR steam Crack Inservice No, provided IV.D1.2.1, generator tubes initiation inspection Plant Tech.
IV.D1.2.4, and mechanical and growth Specs. conform IV.D1I.2.5, plugs from to EPRI IV.D2.2.1
- PWSCC, guidelines and
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL PWR control rod Crack Inservice Yes; Ni-base IVA2.2.1, drive (CRD) initiation inspection; alloys may be IV.A2.4.1 mechanism and growth water chemistry susceptible to IV.A2.4.3, pressure from SCC PWSCC IV.A2.6, housing, nozzle and IGSCC IV.A2.8.1 safe ends, core IV.A2.8.3, support pads, IV.C2.5.6, and vessel "
IV.C2.5.1 0, penetrations (Ni-IV.D1.1.9, base alloys)
IV.D2.1.7 PWR internals (except Westinghouse PWR baffle former bolts)
Crack initiation and growth from SCC and IASCC Inservice inspection; water chemistry Yes; augmented inspection program may be required A.
I J
I IV.B2.1.1 IV.B2.1.7, IV.B2.2.1 IV.B82.2.3, IV.B2.3.1 IV. B2.3.4, IV.B32.4.1, IV.B2.5.1 IV.B2.5.7, IV.B2.6.1, IV.B3.1.1 IV.B3.1.3, IV.B3.2.1, IV.B3.2.2, IV.B3.3.1, IV.B3.3.2, IV.B3.4.1 IV.B3.4.3, IV.B3.5.1 IV.B3.5.6, IV.B4.1, IV.B4.2.1 IV.B4.2.4, IV.B4.3.1 IV.B4.3.3, IV.B4.4.1, IV.B4.4.2, IV.B4.5, IV.B4.6.1 IV.B4.6.3, IV.B4.7.1 IV.B84.7.9, IV.B4.8, IV.B4.9 Draft - 5/25/00 8
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL Westinghouse Crack Plant-specific Yes; plant-IV.1B2.4.2 PWR baffle initiation AMP specific AMP former bolts and growth from SCC and 1ASCC PWR small-bore Crack Inservice Yes; volumetric IV.C2.2.7 reactor coolant initiation inspection; water inspection not system piping and growth chemistry required for from SCC small-bore and IGSCC piping.
BWR isolation Loss of Inservice No IV.C1.4.1 condenser material inspection; water IV.C1.4.4, components; from crevice chemistry IV.D1.4.1 PWR steam and pitting IV.D1.4.3, generator main corrosion IV.D2.3.1 steam piping and IV.D2.3.3 fittings PWR steam Loss of Inservice Yes; IV.D1.1.3, generator (recirc.
material inspection; water supplemental IV.D1.1.4, and once-from crevice chemistry inservice IV.D2.1.4 through) upper and pitting inspection may and lower shell corrosion be required and transition cone PWR steam Loss of Inservice No, provided IV.D1.2.1 generator tubes material inspection Plant Tech.
from Specs. conform general and to EPRI pitting guidelines and corrosion NEI 97-06 PWR steam Deformation Inservice No IV.D1I.2.1 generator tubes (denting) inspection; from water chemistry corrosion at tube support plate inter sections Draft - 5/25/00 9
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL PWR vessel Loss of Inservice No IV.A2.1.1 components, material inspection; boric IV.A2.1.3, piping, and from boric acid corrosion IV.A2.5.3, fittings; acid inspection IV.C2.1.1, pressurizer shell, wastage IV.C2.1.2, heads, and inte-IV.C2.2.4, gral support, IV.C2.2.5, pressurizer relief IV.C2.5.1, tank, steam IV.C2.5.12, generator IV.C2.6.1, pressure IV.DI.1.10, boundary and IV.D2.1.1, structural IV. D2.1.4 IV.D2.1.8 PWR reactor Loss of Bolting integrity No IV.C2.3.3, pump, valve, and material program; IV.C2.4.3, pressurizer from boric inservice IV.C2.5.9 manway and acid inspection flange closure wastage bolting BWR and PWR Loss of Thermal aging No IV.A2.2.1, cast austenitic fracture embrittlement IV.C1.1.5, stainless steel toughness monitoring IV.C1.1.11, (CASS) from program; IV.C1.2.1, components thermal inservice IV.C1.2.2, aging inspection IV.C1.3.1, embrittle-IV.C1.3.2, ment IV.C2.1.1 IV.C2.1.3, IV.C2.2.6, IV.C2.3.1, IV.C2.4.1, IV.C2.5.3, IV.C2.5.4 BWR jet pump Loss of Thermal aging No IV.B1I.5.4, assembly fracture embrittlement IV.B1I.6.1 castings and toughness monitoring orificed fuel from program; support thermal inservice aging inspection embrittle ment Draft - 5/25/00 10
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL Westinghouse Loss of Inservice Yes; IV.B2.3.2 PWR internals fracture inspection augmented IV.B2.3.4, (except support toughness inspection IV.B2.4.1, plate and upper from program may be IV.B2.4.2, and lower neutron required IV.B2.5.1, support plate irradiation IV.B2.5.2, columns) embrittle-IV.B2.5.5, ment BWR vessel Loss of Inservice Yes; TLAA IV.A1.2.4, intermediate fracture inspection; BWR IV.A1.2.6.
(beltline) shell toughness surveillance IV.A1.3.8 and welds and from program to be LPCI nozzles neutron submitted irradiation embrittle ment PWR vessel Loss of Irradiation Yes; TLAA IV.A2.3.1 shell and nozzles fracture embrittlement IV.A2.3.3, toughness monitoring IV.A2.5.1, from program IV.A2.5.2 neutron irradiation embrittle ment PWR pressure Loss of Irradiation No IV.A2.9.2, vessel cantilever/
fracture embrittlement IV.A2.9.3 column support toughness monitoring and shield tank from program neutron irradiation embrittle ment ABB/Combustion Loss of Inservice Yes; IV.B3.3.1, Engineering fracture inspection augmented IV.B3.3.2, PWR internals toughness inspection IV.B3.4.1 (except CEA from program may be IV.B3.4.3, shroud and core neutron required IV.B3.5.1, support column) irradiation IV.B3.5.6, embrittle ment Draft - 5/25/00 11
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL Babcock &
Loss of Inservice Yes; IV.B4.3.1 Wilcox PWR fracture inspection augmented IV.B4.3.3, internals (except toughness inspection IV.B4.4.1 CRA guide tube from program may be IV.B4.4.3, assemblies and neutron required IV.B4.5, CASS vent valve irradiation IV.B4.6.i assembly) embrittle-IV.B4.6.3, ment IV.B4.7.1 IV.1B4.7.9, IV.B4.8, IV.B4.9 Westinghouse Loss of Thermal aging No IV.1B2.1.2, PWR support fracture and irradiation IV.B2.5.3, plate and upper toughness embrittlement IV.B2.5.4 and lower from monitoring support plate thermal programs; columns aging and inservice neutron inspection irradiation embrittle ment ABB/
Loss of Thermal aging No IV.B3.2.1, Combustion fracture and irradiation IV.B3.5.4 Engineering toughness embrittlement PWR CEA from monitoring shroud and core thermal programs; support column aging and inservice neutron inspection irradiation embrittle ment Babcock &
Loss of Thermal aging No IV.B4.2.1 Wilcox PWR fracture and irradiation IV.1B4.2.3, CRA guide tube toughness embrittlement IV.B4.5 assemblies and from monitoring CASS vent valve thermal programs; assembly aging and inservice neutron inspection irradiation embrittle ment Draft - 5/25/00 12
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL PWR internals Changes in dimension from void swelling Control of void swelling Yes; control of void swelling I
BWR Loss of Bolting integrity No IV.C1.2.4, recirculation preload program; IV.C1.3.4 pump and valve from stress inservice closure bolting relaxation inspection PWR reactor Loss of Bolting integrity No IV.C2.3.3, coolant system preload program; IV.C2.4.3, component and from stress inservice IV.C2.5.9, steam generator relaxation inspection IV.D2.1.8, closure bolting I
I I
IV.D2.1.9 Draft - 5/25/00 13 IV.B2.1.1 IV.B2.1.7, IV.B2.2.1 IV.B2.2.3, IV.B2.3.1 iV.B2.3.4, iV.B2.4.1, IV.B2.4.2, IV.B2.5.1 IV.B2.5.7, IV.B2.6.1, IV.B3.1.1 IV.B3.1.3, IV.B3.2.1, IV.B3.2.2, IV.1B3.3.1, IV.B3.3.2, IV.B3.4.1 IV.B3.4.3, IV.1B3.5.1, IV.B3.5.6, IV.B4.1, V.B4.2.1 IV.B4.2.4, IV.B4.3.1 IV.B4.3.3, IV.B4.4.1, IV.B4.4.2, IV.B4.5, IV.B4.6.1 IV.B4.6.3, IV.B4.7.1 IV.B4.7.9, IV.B4.8, IV.B4.9
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL PWR internals BWR piping and fittings; PWR steam generator components Loss of preload from stress relaxation Inservice inspection Yes; augmented inspection program may be required 4
4 t
I Wall thinning from erosion/
corrosion Erosion/
corrosion control program; water chemistry Yes; guidance provided in NSAC-202L-R2 is too general to ensure that applicant's flow accelerated corrosion program will be effective.
.I.
IV.C1.1.1, IV.C1.1.2, IV.C1.1.12, IV.C1.3.1, IV.D1.1.2, IV.D1.1.5, IV.D1.4.1 IV.D1.4.3, IV.D1I.5.1, IV.D2.1.5, IV.D2.1.6, IV.D2.3.1 IV.D2.3.3, IV.D2.4.1 Draft - 5/25/00 14 IV.B2.1.3, IV.B2.1.7, IV. B2.2.2, IV.B2.4.2, IV.B2.5.2, IV.1B2.5.5, IV.B2.5.7, IV.B3.2.2, IV.B3.4.2, IV.B3.4.3, IV.B3.5.2, IV.B3.5.5, IV. B4. 1, IV.B4.2.1 IV.B4.2.4, IV.B4.3.1 IV.B4.3.3, IV.1B4.4.1, IV.B4.4.2, IV.B4.5, IV.B4.6.1 IV.B4.6.3, IV.B4.7.1 IV.1B4.7.9, IV.B4..,
IV.B4.9, IV.1B4.2.4, IV.B4.3.2, IV.E4.6.2, IV.B4.6.3, IV.B4.7.6 IV.E4.7.9
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging "urther Evaluatior Item Effect/
Management Recommended Number Component Mechanism Programs in GALL PWR steam Loss of Plant Tech.
Yes; plant-IV.D1.2.3 generator tube section Specs.
specific AMP support lattice thickness bars from erosion/
corrosion PWR steam Loss of Inservice No IV.D1.3.1 generator material inspection feedwater inlet from ring and erosion/
supports corrosion PWR steam Loss of Inservice No IV.D2.1.9 generator material inspection secondary from manways and erosion/
handholes corrosion PWR pressurizer Wall Plant Tech.
Yes; plant-IV.C2.5.4 spray head thinning Specs.
specific AMP from erosion PWR steam Loss of Plant Tech.
Yes; plant-IVD1.1.6 generator section Specs.
specific AMP feedwater thickness impingement from erosion plate support BWR Loss of Bolting integrity No IV.C1.2.3, recirculation material program; IV.C1.2.4, pump and valve from attrition inservice IV.C1.3.3, seal flange and and wear inspection IV.C1.3.4 closure bolting PWR internals Loss of Inservice No IV.B2.1.5, material inspection IV.B2.1.6, from attrition IV.B2.2.1, and wear IV.B2.3.2, IV.B2.5.2, IV.B2.5.6, IV.B2.6.2, IV.B3.1.1, IV.B3.1.3, IV.B3.1.4 (cont'd on next page)
Draft - 5/25/00 15
Table 2. Summary of Aging Management Programs for Reactor Coolant System Evaluated in Chapter IV of the GALL Report (cont'd.)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in GALL IV.B3.2.3, IV.B3.3.2, IV.B3.3.3, IV.B3.5.2, IV.1B3.5.6, IV. B4.2. 1, IV.1B4.3.3, IV.B4.4.2, IV.B4.7.2, IV.B4.7.5 PWR reactor Loss of Bolting integrity No IV.C2.3.3, coolant system material program; IV.C2.4.3, component from attrition inservice IV.D1.1.7, closure bolting; and wear inspection IV.D1.1.8, steam generator IV.D1.1.10, bolting PWR vessel Loss of Inservice No IV.A2.1.3, closure studs, material inspection; IV.A2.6 and core support from attrition attrition and pads and wear wear control program PWR pressurizer Loss of Plant Tech.
Yes; plant-IV.C2.5.10 heater sheaths material Specs.
specific AMP and sleeves from attrition and wear PWR steam Loss of Inservice No, provided IV.D1.2.1 generator tubes material inspection Plant Tech.
from fretting Specs conform and wear to EPRI guidelines and NEI 97-06 PWR small-bore Crack Inservice Yes; volumetric IV.C2.1.5 reactor coolant initiation inspection; inspection not system piping and growth water chemistry required for from small-bore unanticipate piping d thermal and mechanical loading Draft - 5/25/00 16
Table 3. Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL Report Aging Aging Further Item Effect/
Management Evaluation Number in Component Mechanism Programs Recommended GALL BWR emergency Crack Inservice No V.A.1.1, core cooling sys-initiation inspection; V.A.1.5, tern and contain-and growth materials V.A.3.1, ment isolation from SCC selection and V.A.4.1, components; processing to V.A.5.1, PWR reduce V.C.8.1, containment susceptibility to V.C.8.2, spray and sensitization; V.C.9.1, emergency core water chemistry V.C.9.2, cooling system V.D1.1.1 components in V.D1.1.6, contact with V.D1.2.1, primary coolant V.D1.4.1, V.D2.1.1 V.D2.1.7, V.D2.3.1 PWR Crack Inservice Yes; one-time V.A.3.2, containment initiation inspection; inspection and V.D1.7.3, spray chemical and growth materials appropriate V.D1.8.3 addition storage from SCC selection and follow-up tank; PWR emer-processing to actions recom gency core reduce mended cooling safety susceptibility to injection tank sensitization and refueling water tank penetrations and nozzles BWR standby Crack Plant Technical Yes; plant-V.B.2 gas treatment initiation Specifications specific AMP system electric and growth heater housing from SCC Containment Loss of Inservice No V.C.1.1-V.C.1.3, isolation coated material inspection; V.C.2.1, carbon steel from coatings program V.C.2.2, components general V.C.3.1, corrosion V.C.3.3-V.C.3.5, V.C.4.1, V.C.4.2, V.C.4.4, V.C.5.1-V.C.5.3, V.C.7.1, V.C.7.2 Draft - 5/25/00 17
Table 3. Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL Report (cont'd)
Aging Aging Further Item Effect/
Management Evaluation Number in Component Mechanism Programs Recommended GALL BWR standby Loss of Plant Technical Yes; plant-V.B.1, gas treatment material Specifications; specific AMP V.B.3.1, system carbon from humidity control V.B.4 steel general components corrosion PWR fan cooler Loss of Plant Technical Yes; plant-V.E.1.2 system cooling material Specifications specific AMP V.E.1.6 woils, fan from components, and general piping and corrosion fittings PWR Local loss of Inservice No V.A.7.1 containment material inspection; V.A.7.4, spray heat ex-from pitting inservice testing; V.D1.5.1 changer corn-and crevice water chemistry V.D1.5.4, ponents and corrosion V.D1.6.1 PWR and BWR V.D1.6.3, emergency core V.D2.4.1 cooling system V.D2.4.4, heat exchanger V.D2.6.1 and isolation V.D2.6.4 condenser components PWR Local loss of Inservice Yes; one-time V.A.1.1 containment material inspection; water inspection and V.A.1.3, spray system from pitting chemistry appropriate V.A.1.5, components, and crevice follow-up V.A.4.1, BWR and PWR corrosion actions recom-V.A.5.1, and emergency mended V.C.8.1, core cooling V.C.8.2, system V.C.9.1, components; V.C.9.2, BWR and PWR V.D1.1.1 containment V.D1.1.5, isolation valves V.D1.2.2, V.D1.3.1, V.D1.4.1, V.D1.7.1 V.D1.7.3, V.D1.8.1 V.D1.8.3, V.D2.2.1 V.D2.2.3, V.D2.3.1 Draft - 5/25/00 18
Table 3. Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL Report (cont'd)
Aging Aging Further Item Effect]
Management Evaluation Number in Component Mechanism Programs Recommended GALL PWR Local loss of Plant Technical Yes; plant-V.A.2.1 containment material Specifications specific AMP V.A.2.4, system compon-from V.A.6.1, ents; BWR and
- general, V.C.10.1, PVVR pitting and V.C.10.2, containment crevice V.D2.1.8, isolation com-corrosion V.D2.5.1 ponents;-BWR V.D2.5.4 emergency core cooling system components BWR standby Local loss of Plant Technical Yes; plant-V.B.1, gas treatment material Specifications, specific AMP V.B.3.1, system carbon from pitting humidity control V.B.4 steel and crevice components corrosion PWR Loss of Inservice No V.A.1.4, V.A.4.2 containment material inspection; boric V.A.5.2,
- spray, from boric acid corrosion V.A.7.3-V.A.7.5 containment acid prevention V.C.9.1, V.C.9.2 isolation, and wastage V.D1.1.7, emergency core V.D1.2.1, cooling system V.D1.2.2, bolting and other V.D1.3.2, external surfaces V.D1.4.1, V.D1.4.2, V.D1.5.3 V.D1.5.5, V.D1.6.3, V.D1.6.4, V.D1.7.1, V.D1.8.4 PWR Loss of ma-Service water No V.A.7.1, containment terial from program; water V.A.7.4, spray and BWR general and chemistry V.D2.4.1 emergency core microbiologi V.D2.4.4 cooling system
-cally heat exchanger influenced components corrosion PWR emergency Loss of ma-Plant Technical Yes; plant-V.D1.1.6 core cooling terial from Specifications specific AMP system line to microbiologi emergency sump
-cally influenced corrosion Draft - 5/25/00 19
Table 3. Summary of Aging Management Programs for Engineered Safety Features Evaluated in Chapter V of the GALL Report (cont'd)
Aging Aging Further Item Effect/
Management Evaluation Number Component Mechanism Programs Recommended in V PWR Buildup of Service water No V.A.7.1 containment deposit from program; water V.A.7.4, spray and BWR biofouling chemistry V.D2.4.1 emergency core V.D2.4.4 cooling system heat exchanger components PWR emergency Wall Erosion/
Yes; guidance V.D2.1.9, core cooling thinning corrosion control provided in V.D2.1.10, system lines and from program NSAC-202L-R2 V.D2.3.1 valve erosion/
is too general to components corrosion ensure that applicant's flow accelerated corrosion pro gram will be effective.
Containment Loss of Inservice No V.C.1.1 isolation coated material inspection; V.C.1.3, carbon steel from attrition coatings program V.C.2.1, components and wear V.C.2.2 BWR standby Changes in Plant Technical Yes; plant-V.B.3.3, gas treatment properties Specifications specific AMP V.C.3.2, system filter from V.C.4.3, seals: contain-elastomer V.C.6.1, ment isolation degradation V.C.7.3 penetration seals PWR emergency Loss of Plant Technical Yes; plant-V.D1.8.5 core cooling sys-elasticity Specifications specific AMP tem refueling from water tank weathering perimeter seal BWR standby Loss of Plant Technical Yes; plant-V.B.3.2 gas treatment iodine Specifications specific AMP system charcoal retention absorber filter capacity from absorption of moisture Draft - 5/25/00 20
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report Aging Aging Further Item Effect/
Management Evaluation Number in Component Mechanism Programs Recommended GALL New fuel rack Loss of Plant system
- Yes, VII.A1.1.1, assembly; ducts, material due
- walkdown, the existence VII.FI.1.1 heating/ cooling to general, protective coating of a suitable VII.F1.1.4, coils, and piping pitting, and AMP should be VII.F1.2.1, in heating and crevice evaluated VII.F1.3.1, ventilation corrosion; or VII.F2.1.1 systems; and attrition from VII.F2.1.4, piping, valve wear VII.F2.2.1, bodies, pump VII. F2.3. 1, casing, and VII.F3.1.1 tanks in diesel VII.F3.1.4, fuel oil system VII.F3.2.1, VII.F3.3.1, VII.F4.1.1 VII.F4.1.4, VII.F4.2.1, VII.F4.3.1, VII.H 1.1.1, VII.HI.2.1, VII.H1I.2.2, VII. H1.3.1, VII.H1.3.2, VII.H1.4.2, Neutron Reduction in Neutron No VII.A2.1.1 absorbing neutron absorbing sheets sheets in spent absorbing monitoring fuel storage capacity program racks due to aging degradation Components in Cumulative Components Yes; VII.B1.1.1, load handling fatigue designed for TLAA VII.B1.2.1, and liquid waste damage fatigue in VII.B2.1.1, disposal accordance with VII.B2.2.1,
- systems, ASME or ANSI VII.EI.1.1, chemical and Codes VII.E1.1.2, volume control VII.El.2.1, system (PWR),
VII.El.2.2, and reactor VII.E1.3.1, water cleanup VII.E1.3.2, and shutdown VII.E1.4.1, cooling systems VII.E1.4.2, (BWR)
VII.E1.5.1, VII.E1.5.2, Draft - 5/25/00 21
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd)
Load handling system structures, rails, and wire ropes Components in open-cycle and closed-cycle cooling water systems 7
.7.
7 1
- 4.
4 Loss of material from general corrosion and wear; or cracking and breaking of wire ropes due to degradation Buildup of deposit from biofouling, and/or loss of material from general and microbio logically influenced corrosion Crane inspection program Service waier program No i
t No Carbon steel Loss of Water chemistry, Yes, inspection VII.A3.1.1, piping, valve material corrosion resistant of susceptible VII.A3.4.1, bodies, pump from lining or coating, locations VII.A3.5.1, casing, tanks, general and inservice VII.A3.6.1, and heat microbio-inspection VII.A3.8.1, exchangers logically VII.A4.1.1, influenced VII.A4.2.1, corrosion, VII.A4.3.1, and VII.A4.4.1, selective VII.C3.2.1, Draft - 5/25/00 VII.El.6.1, VII.E1.6.2, VII.E1.7.1 VII.El.7.4, VII.El.8.1 VII.El.8.4, VII.E3.1.1, VII.E3.2.1 VII.E3.2.4, VIi.E3.3.1 VII.E3.3.4, VII.E3.4.1, VII.E3.4.2, VII.E3.5.1, VII.E3.5.2, VII.E5.1.1 VII.B 1.1.1, VII.B1.2.1, VII.B1.2.2, VII.B1.3, VII.B2.1.1, VII.B2.2.1, VII.B2.2.2, VII.B2.3 VI.C1.1.1, VII.Cl.2.1, VII.C1.3.1 VII.C1.3.5, VII.CI.4.1, VII.Cl.5.1, VI.CI.6.1, VII.C2.1.1, VI1. C2.2. 1, VII.C2.3.1, VI1.C2.4.1, VI1.C2.5.1 22
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd) leaching Carbon steel Loss of Air quality Yes, inspection VII.D.1.1, piping, valve material due monitoring of susceptible VII.D.2.1 bodies, and air to general program locations VII.D.2.3, accumulator and and pitting VII.D.3.1, filter corrosion VII.D.4.1 components in VII.D.4.3 compressed air system Bolting and Loss of Boric acid No VII.A3.1.2, external material corrosion program VII.A3.2.1, surfaces of from boric VII.A3.3.1, carbon steel acid VII.A3.4.1, components in wastage VII.A3.4.2, PWRs VII.A3.5.1, VII.A3.5.2, VII.A3.6.1 VII.A3.6.3, VII.A3.7.1, VII.A3.8.1, VII.A3.8.2, VII.A3.9.1, VII.A3.10.1, VIL.E1.1.2, VIi.El.2.2, VII.El.3.2, VII.E1.4.2, Draft - 5/25/00 23 VII.C3.3.1, VII.C3.4.1, VII.E1.1.1, VII.El.2.1, VII.El.3.1, VII.El.4.1, VII.El.5.1, VII.El.6.1, VII.E1.7.5, VII.E1.8.5, VII.E1.10.2 VII.E1.10.4, VII.E4.1.1, VII.E4.2.1, VII.E4.3.1, VII.E4.4.1 VII.E4.4.3, VII.E4.5.1, VII.E4.5.2, VII.E5.1.1, VIi.E5.2.1, VIi.E5.3.1, VII.E5.4.1 VII.E5.4.4
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd)
VII.E1.5.2, VII.E1.6.2, VII.E1.7.2, VII.E1.8.2, VII.El.9.1, VII.El.10.1, VII.E4.2.2, VII.E4.5.5, 1.1.?
Perimeter seal Loss of No generic AMP Yes, new VII.E4.5.6, for tanks elasticity program VII.1H 1.4.3 from should be weathering implemented Valve bodies Loss of Assessment of
- Yes, VII.E3.2.1, and pump fracture embrittlement the existence VII.E3.3.1 casing in reactor toughness susceptibility and of a suitable water cleanup from supplemental AMP should be system (BWR) thermal inservice evaluated aging inspection embrittle ment Stainless steel Crack Inservice Yes, visual VII.A3.1.1, piping and tank initiation inspection, examination VII.A4.1.1, penetrations in and growth material selection, can not detect VII.E4.1.1, spent fuel pool from SCC water chemistry cracks VII.E4.5.3 cooling and cleanup system and refueling water tank heating system Stainless steel Crack inservice No VII.E5.1.1, components in initiation inspection, VII.E5.3.1, shutdown and growth material selection, VII.E2.1 cooling and from SCC water chemistry VII.E2.1 0 standby liquid control systems (BWR)
External Crack Monitoring of Yes; VII.E1.2.1, surfaces of low-initiation heat-traced the existence VII.E1.4.1 pressure and growth components of a suitable stainless steel from SCC AMP should be piping and due to evaluated valves in electrical chemical and heat tracing volume control system (PWR)
Stainless steel Crack IGSCC program Yes, inspection VII.E3.1.1, piping, valve initiation of susceptible VII.E3.2.1, bodies, and and growth locations VII.E3.2.2, pump casing in I
I
_I_._VII.E3.3.1, Draft - 5/25/00 24
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd) reactor water from SCC VII.E3.3.2, cleanup system VII.E3.4.1, (BWR)
VII.E3.4.2, VII.E3.5.1, VII.E3.5.2, VII.E3.6.1 Closure bolting Attrition Bolting integrity No VII.E3.2.4, of reactor water from wear, program VII.E5.1.2, cleanup and or loss of VII.E5.2.2, shutdown preload VII.E5.3.2, cooling system from stress VII.E5.4.5 components relaxation (BWR)
Fire rated doors Attrition Fire protection No VII.G.1.3, from wear program VII.G.2.3, VII.G.3.3, VII.G.4.3, VII.G.5.2 Concrete fire Concrete Fire protection No VII.G.1.2, barrier walls, cracking program VII.G.2.2, ceilings, and and spalling VII.G.3.2, floors due to VII.G.5.1 freeze thaw, aggressive chemical attack, and reaction with aggregates, or loss of material due to corrosion of embedded steel Piping, filter, fire Buildup of Periodic No VII.G.6.1,
- hydrants, deposit from performance and VII.G.6.2 mulsifier, pump biofouling flush test of fire casing, sprinkler, protection system strainer, and valve bodies in high-pressure service water system for fire protection Piping, filter, fire Loss of Fire protection No VII.G.6.1,
- hydrants, material due program VII.G.6.2 mulsifier, pump to general, casing, sprinkler, microbio-_
__II
_I___I Draft - 5/25/00 25
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd) strainer, and logically valve bodies in influenced, high-pressure pitting, and service water crevice system for fire corrosion protection Components in Loss of No generic AMP
- Yes, VII.G.6.1, fire protection material due one-time VII.G.6.2, high-pressure to galvanic, inspection VII.G.7.1, service water pitting, and VII.G.7.2 system and crevice reactor coolant corrosion pump oil collect system Diesel-driven fire Loss of Fire protection No VII.G.8.1 pump and fuel material due program oil supply lines to general,
- galvanic, pitting, and crevice corrosion Diesel fuel oil Loss of Corrosion No VII.H1.1.2 buried piping material protection of from buried piping
- general, galvanic, microbio logically Influenced, pitting, and crevice corrosion Diesel fuel oil Loss of Fuel oil
- Yes, VII.H1.4.1, strainer and tank material surveillance and inspection of VII.H2.5.1 internal surfaces from maintenance tank internal VII.H2.5.3
- general, program surfaces microbio logically Influenced, pitting, and crevice corrosion, or buildup of deposit from biofouling Piping, valves, Loss of Diesel generator Yes; VII.H2.2.1 drain trap, air material starting air and the existence VII.H2.2.5, accumulator, from combustion air of a suitable VII.H2.3.1 filter, and muffler
- general, system monitoring AMP should be VII.H2.3.3, in diesel pitting, and I
VII.H2.4.1, Draft - 5/25/00 26
Table 4. Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of the GALL Report (cont'd) generator crevice evaluated VII. H2.4.2 starting air and corrosion combustion air systems Diesel engine Wall No generic AMP
- Yes, VII.H2.4.2 combustion air thinning due review plant exhaust muffler to erosion specific AMP Draft - 5/25/00 27
Table 5. Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of the GALL Report Aging Further Item Aging Effectl Management Evaluation Number in Component Mechanism Programs Recommended GALL Piping, valve bodies, and pump casings (carbon steel)
Wall thinning from erosion/
corrosion Erosion/
corrosion control program No BWR Loss of Inservice No VIIL.B2.1.1, components in material from inspection VIII.B2.2.1 main steam
- general, lines to steam crevice, and turbine pitting corrosion Buried piping Loss of Corrosion No VIII.G.1.2 material from protection of
- general, buried piping galvanic, &
microbio logically influenced corrosion Draft - 5/25/00 28 VIII.A.1.1, VIII.A.1.2, VilI.BI.I.1 VIII.B1.1.5, VIII.B13.2.1, VIII.B2.1.1 VIII.B2.1.6, VIII.B2.2.1, VIII.C.1.1, VIII.C.1.2, VIII.C.2.1, VIII.D1.1.1, VIII.D1.2.1, VIII.D1.3.1, VIII.D1.3.2, VIII.D2.1.1, VIII.D2.2.1, VIII.D2.3.1, VIII.D2.3.2, VIII.E.1.1, VIII.E.2.1, VIII.E.3.1, VlII.F.I.1, VIII.F.1.2, VIII.F.2.1, VIII.F.3.1, VIII.G.1.1, VIII.G.2.1, VIII.G.2.2, VIII.G.3.1
Table 5. Summary of Aging Management Programs for Steam and Power Conversion System Evaluated in Chapter VIII of the GALL Report (cont'd)
PWR auxiliary Loss of Inservice No VIII.G.2.1, feedwater material from inspection; VIII.G.2.2, system pumps
- general, water chemistry; VIII.G.3.1 and valves crevice, and inservice testing pitting corrosion Carbon steel Loss of Water chemistry Yes, inspection VIII.D1.1.1, piping, valve material from of select VIII.D1.2.1, bodies, pump
- general, components VIII.D1.3.1, casing, and crevice, and may be needed VIII.D1.3.2, tanks, except pitting VIII.E.5.1, for the steam corrosion VIII.E.6.1 system and VIII.E.6.4, BWR VIII.F.1.1, feedwater VIII.F.1.2, system VIII.F.2.1, components VIII.F.3.1, VIII.G.1.1, VIII.G.1.2 Heat Loss of Service water No VIII.E.4.1 exchanger material from program; VIII.E.4.4, general and water chemistry VIII.F.4.1 microbio-VIII.F.4.3 logically influenced corrosion, and buildup of deposit from biofouling Oil coolers Loss of Service water No VIII.G.5.1 material from program; VIII.G.5.3 general and monitoring oil microbio-contamination logically influenced corrosion, and buildup of deposit from biofouling Closure bolting Attrition from Bolting integrity No VIII.B2.2.2, wear program VIII.D2.1.2, I
I_
VIII.G.2.3 Draft - 5/25/00 29
Draft - 5/25/00 Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report Aging Further Item Aging Effect/
Management Evaluation Number in Component Mechanism Programs Recommended GALL Common Components of All Types of PWR and BWR Containment Penetration Loss of ASME IWE Yes, for Il.A3.1
- sleeves, material from inservice inaccessible I1.B4.1 penetration corrosion inspection in areas.
bellows, and accordance with dissimilar 10 CFR 50.55a metal welds and Appendix J containment leak rate tests.
Penetration Cumulative TLAA Yes, TLAA II.A3.1
- sleeves, fatigue I1.1B4.1 penetration damage from bellows, and cyclic loading dissimilar metal welds Penetration Crack ASME IWE No, except for II.A3.1
- sleeves, initiation and inservice bellows. Plant-I1.B4.1 penetration growth from inspection specific operat bellows, and stress ing experience dissimilar corrosion with cracking of metal welds cracking containment bellows should be evaluated.
Subfoundation Reduction in Plant-specific Yes, for.
I1.A3.3 layer foundation monitoring and containment 11.134.3 strength from preventive structures that erosion of program of have a porous porous subfoundation concrete concrete settlement subfoundation, subfounda-plant-specific tion evaluation is required.
Personnel Loss of ASME IWE No II.A3.2 airlock and material from inservice II.B4.2 equipment corrosion; inspection in hatch fretting/lock-accordance with up from wear 10 CFR 50.55a of locks, and Appendix J hinges, and containment leak closures rate tests.
mechanisms I
I 30
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
Seals and Loss of seal-ASME IWE No I1.A3.4 gaskets ant and leak-inservice I1..B4.4 age through inspection in containment accordance with from deterio-10 CFR 50.55a ration of joint and Appendix J sealants and containment leak gaskets rate tests PWR Containment Concrete (Reinforced and Prestressed) and Steel BWR Containment (Mark 1, If and IlI) Concrete and Steel Inaccessible Aging of ASME IWL Yes, for I1.A1.1 concrete areas inaccessible inservice inaccessible II.A2.2 such as concrete Inspection in areas II.B1.2.1
- basemat, areas:
accordance with II.B2.2.1 exterior walls Increase in 10 CFR 50.55a I1.B3.2.1 below grade
- porosity, II.B3.1.2 permeability,
- scaling, cracking, and spalling from leaching of calcium hydroxide and aggressive chemical attack; crack ing, spalling, loss of bond, and loss of material from corrosion of embedded steel Containment
- Cracks, Plant-specific Yes, for a II.A1.1 structure and distortion, structure containment I1.A2.2 basemat and settlement resting on soil I1.B2.2.1 increases in monitoring or piles, or for I1.B3.2.1 components program sites which I1.B3.1.2 stress level experience from significant settlement changes in ground water conditions PWR: Dome, Loss of No mandated Yes, for any II.A1.1 wall, basemat, strength and aging portions of I!.A2.2 ring girder, and modulus from management concrete I1.B13.2.1 buttresses elevated program exists containment I1.B2.2.1 Draft - 5/25/00 31
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
BWR:
temperature that exceed 11.13.2.1 Drywell, torus specified lI.B3.1.2 dome, wall, temperature
- basemat, limits concrete fill in annulus PWR:
Loss of ASME IWE Yes, for II.A1.2 Liners, liner material from inservice inaccessible II.A2.1 anchors, and corrosion in inspection in areas II.B1.2.2 structural steel, inaccessible accordance with 11.12.2.2 containmenlt areas of liner 10 CFR 50.55a 11.B3.2.2 shell, etc.
plates & steel and Appendix J 11.B1.1.1 BWR:
structures containment leak II.B2.1.1
- Drywell, rate tests II.B3.1.1 suppression chamber liners, downcomer bracing, saddle support, etc.
PWR; Degradation Plant-specific Yes, plant-II.A1.2 Concrete:
of protective coating monitor-specific coating II.A2.1 Liners, liner coating ing and mainten-monitoring and II.B13.2.2 anchors, and ance program maintenance
!1.B2.2.2 structural steel.
program 11.B3.2.2 BWR:
II.B1.1.1
- Drywell, lI.B2.1.1 suppression 11.B3.1.1 chamber liners, downcomrer bracing, saddle support, etc.
PWR & BWR Loss of ASME IWL Yes, plant II.A1.3 Mark II material from inservice specific II.B2.2.3 prestressed corrosion of Inspection in conditions of containment:
prestressing accordance with tendon gallery.
Tendons and tendons 10 CFR 50.55a anchorage anchorage components components PWR & BWR Loss of pre-ASME IWL Yes, TLAA II.A1.3 Mark II stress from inservice II..B2.2.3 prestressed relaxation, inspection in containment:
shrinkage, accordance with Tendons and creep, and 10 CFR 50.55a anchorage elevated and Regulatory components temperature Guide 1.35.1 PWR:
- Scaling, ASME IWVL No II.A1.1 Dome, wall, cracking, and inservice II.A2.2 basemat, etc.
spalling from Inspection in 11.B3.2.1 freeze-thaw; accordance with 11.B1.2.1 11.B2.2.1 Draft - 5/25/00 32
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
BWR:
expansion 10 CFR 50.55a 11.B3.2.1 Drywell, tows, and cracking 11.B3.1.2 basemat, etc.
from reaction with aggregate BWR:
Cumulative TLAA Yes, TLAA II.B1.2.2 Concrete and fatigue 11.11.1.1 steel Mark I:
damage from Vent line cyclic loading bellows,.
BWR:
Crack ASME IWE Yes, plant-I1.B13.2.2 Concrete and initiation and inservice specific 11.B1.1.1 steel Mark 1:
growth from inspection in operating Vent line stress accordance with experience with
Crack ASME IWE No II.B2.2.2 Suppression initiation and inservice
!1.B3.2.2 chamber liner growth from inspection in II.B3.1.1 (interior stress accordance with surface) corrosion 10 CFR 50.55a cracking and Appendix J containment leak rate tests BWR:
Fretting and ASME IWE No l1.B13.2.2 Drywell head, lock up from inservice 11.B2.2.2 downcomers, weir of locks, inspection in and bracing hinges and accordance with II.B13.1.1 system.
closures 10 CFR 50.55a 11.B2.1.1 mechanisms Class I Structures All Groups Aging of Maintenance No, if within the Ill.A1.1 except structures not Rule (MR) scope of the III.A1.2 Group 6:
covered by structure applicant's MR II1.A2.1 Accessible Maintenance monitoring structure moni-III.A2.2 interior/exterior Rule:
program in toring program.
III.A3.1 concrete &
- Scaling, accordance with Otherwise, the II1.A3.2 steel cracking, and IOCFR50.65 or aging II1.A4.1 components:
spalling from plant-specific management II1.A4.2 such as freeze-thaw; structure program should II1.A4.3 exterior increase in monitoring be evaluated for II1.A5.1 concrete above
- porosity, program structure/aging III.A5.2
- grade, permeability, effect II1.A7.1 structural steel
- scaling, combinations II1.A7.2 components, cracking &
not within the II1.A8.1 steel liner of spalling from scope of the II1.A8.2 concrete and leaching of I
applicant's II1.A9.1 Draft - 5/25/00 33
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd) steel tanks f
1 structure monitoring program.
Draft - 5/25/00 calcium hydroxide and aggre ssive chemical attack; expansion and cracking from reaction with aggregate,;
- cracking, spalling, loss of bond, and loss of material from corrosion of embedded steel; loss of material from corrosion;
- cracks, distortion, and increases in components stress level from settlement; reduction in foundation strength from erosion of porous concrete subfounda tion; crack initiation &
growth from SCC; loss of material from crevice corrosion; loss of material from corrosion of prestressing tendons anchorage components 34
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
All Groups except Group 6:
Inaccessible concrete &
steel components such as exterior walls below grade and foundation Aging management of inaccessi ble areas:
Increase in
- porosity, permeability,
- scaling, cracking, and spalling from aggressive chemical.
attack; crack ing, spalling, loss of bond, and loss of material from corrosion of embedded steel; loss of material from corrosion Plant-specific aging management program Yes, evaluation should be performed on a case-by-case basis.
Group 4:
Loss of TLAA Yes, TLAA III.A4.3 Tendons of prestress prestressed from system relaxation, shrinkage, and creep.
Group 6:
All types of; Regulatoýy No III.A.6.1 All accessible/
aging effects Guide 1.127 II1.A.6.2 inaccessible including loss II1.A.6.3 concrete &
of material steel from abrasion components and Cavitation Group 5:
Crack Periodic No III.A5.2 Liners initiation and monitoring of the growth from leak chase stress corro-system drain sion cracking lines and the and loss of leak detection material from sump crevice corrosion Groups 1-3, Cracking Implementation No II1.A1.3 5-6:
from restraint, of IE Bulletin 80-II!.A2.3 All masonry shrinkage, 11 and IIi.A3.3 block walls creep, and Information I!1.A5.3 I aggressive Notice 87-67 for I!1.A6.3 Draft - 5/25/00 35 IIl.A1.1 III.A1.2 Iii.A2.1 Iii.A2.2 III.A3.1 III.A3.2 III.A4.1 III.A4.2 II1.A5.1 II1.A5.2 IlI.A7.1 III.A7.2 III.A8.1 II1.A8.2 II1.A9.1
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
Component SuDports:
All Groups::
Support
- members, anchor bolts, and welds, concrete surrounding anchor bolts, grout pad, Bolted friction connections etc.
Copnn Supots Aging of component supports not covered by Maintenance Rule:
Loss of material from environmen tal corrosion; reduction/
loss of isolation function from sustained vibration loading
_I_
i 4 All Groups:
Support
- members, anchor bolts, and welds Loss of material from boric acid corrosion Maintenance Rule (MR) structure monitoring program lmp~erra.tation of Generic Letter 88-05.
No, if within the scope of the applicant's MR structure monitoring program.
Otherwise, the aging management program should be evaluated for component support/aging effect combinations not within the scope of the applicant's structure monitoring program.
No, provided that visual inspection of adjacent areas is included in the applicant's boric acid AMP of reactor cool ant pressure boundary.
Otherwise plant specific evaluation is required.
Groups B1.1, Cumulative TLAA Yes, TLAA 1111.1.1.1 B1.2, B2, and fatigue 111.B1.2.1 B4:
damage from 111.B2.1 Support mem-cyclic loading III.B4.1 bers, anchor bolts, and welds Draft - 5/25/00 111.B1.1.4 111.B1.2.3 111.B2.1 Ill.B2.2 Il1.1B2.3 IlI.B3.1 II1.B3.2
!11.B4.1 II1.B4.2 II.B4.3 111.B5.1 III.B5.2 lll.B13.1.1 Ill.B1.2.1 II.B2.1 I1l.B3.1 II.B4.1 111.B5.1 36
Table 6. Summary of Aging Management Programs for Structures and Structural Components Evaluated in Chapters II and III of the GALL Report (cont'd)
Groups 81.1, 81.2, B2, and B4:
Support
- members, anchor bolts, welds, Spring
- hangers, guides, stops, and vibration isolators Loss of material from environmen tal corrosion; loss of mechanical function from corrosion, distortion, dirt, overload; cracking initiation and growth from stress corrosion crackina ASME IWF inservice inspec tion in accordance with 10 CFR 50.55a T
T No I1.B13.1.1 111.B1.1.3 Ill.B13.2.1 111.B1.2.2 II1.12.1 111.B4.1 Group B1.1:
Crack Implementation No I1l.B1.1.2 High strength initiation and of Generic Letter low-alloy bolts growth from 91-17 stress corrosion cracking Draft - 5/25/00 37
Table 7. Summary of Aging Management Programs for the Electrical Components Evaluated in Chapter VI of the GALL Report Aging Further Aging Effect/
Management Evaluation it Nubr Component Mechanisms Programs Recommended Electrical Degradation EQ program Yes, if TLAA is VI.A.1.1, VI.A.1.2, equipment due to various to be projected VI.A.1.3, VI.A.1.4; subject to 10 aging to the end of VI.A.1.3, V1.1.I.2, CFR 50.49 mechanisms the period of VI.B.1.1, VI.B.I.2, VI.B.1.3, VI.B.2.1, environmental extended VI.B.3.1; qualification operation by re-VI.C..1, VI.C.1.2, (EQ) analysis, the re-VI.C.1.3, VI.C.1.4 requirements analysis should be evaluated.
Non-EQ Degradation Aging Yes VI.A.1.1, VI.A.1.2, electrical due to various inspection and VI.A.1.3, VI.A.1.4;
- cables, aging instrument VI.B.1.1, VI.B.1.2, connectors, mechanisms calibration VI.B.1.3, VI.B.2.1, and VI.B.3.1; penetrations VI.C.1.1, VI.C.1.2, VI.C.1.3, VI.C.1.4 Electrical Degradation Electrical bun-,
No V1.D.1.1, VI.D.1.2,
- buses, due to various insulator, VI.D.1.3, VI.D.1.4, insulators, aging transmission VI.D.2.1, VI.D.2.2, transmission mechanisms conductor, and VI.D.2.3, VI.D.2.4, conductors, ground VI.D.3.1, VI.D.3.2, and ground conductor VI.D.3.3, VI.D.4.1; conductors inspection VI.E.1.1, VI.E.2.1; program VI.F.1.1; VI.G.1.1 Draft - 5/25/00 38
APPENDIX DESCRIPTION OF STRUCTURE AND (ITEM NUMBER) IN THE GALL COMPONENTS REPORT Draft - 5/25/00 39
Prefix of Item Numbers in the GALL Report Page No.
II.
Containment Structure I1A PWR Containments.............................................................................................................
43 II.A1 Concrete Containments (Reinforced and Prestressed)....................................
43 II.A2 Steel Containments...........................................................................................
43 II.A3 Common Components.............................................................................................
43 Il.B BWR Containments........................................................................................................
43 Il.B1 Mark I Containments...........................................................................................
43 11.132 Mark II Containments.........................................................................................
43 II.B3 Mark III Containments........................................................................................
43 11.14 Common Components.........................................................................................
43 Ill.
Structures & Component Supports lIlA Class I Structures..........................................................................................................
44 IItA1 Group 1 Structures (BWR Reactor Bldg, PWR Shield Bldg, Control Rm/Bldg)....... 44 IIlA2 Group 2 Structures (BWR Reactor Bldg with Steel Superstructure)...............
44 IIIA3 Group 3 Structures (Auxiliary Bldg, Diesel Generator Bldg, Radwaste Bldg, Turbine Bldg, Switchgear Rm, AFW Pumphouse, Utility/Piping Tunnels).......... 44 Ill.A4 Group 4 Structures (Containment Interior Structures, excluding Refueling Canal)................................................................................................
44 IIlA5 Group 5 Structures (Fuel Storage Facility, Refueling Canal)............................
44 III *6 Group 6 Structures (Water-Control Structures)...............................................
44 Ill.A7 Group 7 Structures (Concrete Tanks)..............................................................
44 IIl.AB Group 8 Structures (Steel Tanks)....................................................................
44 IIIA9 Group 9 Structures (BWR Unit Vent Stack)....................................................
44 111.B Component Support.....................................................................................................
45 1Il.B1 Supports for ASME Class Piping and Components..........................................
45 Ill.B2 Supports for Cable Trays, Conduit, HVAC Ducts, TubeTrack, Instrument Tubing, Non-ASME Piping and Components....................................................
45 ll.B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electrical Equipment and Instrumentation.........................................................................
45 111.134 Supports for Miscellaneous Mechanical Equipment (e.g., Cranes, EDG, HVAC System Components)........................................................................................
45 1111.5 Supports for Miscellaneous Steel Structures (e.g., Platforms, Pipe Whip Restraints, Jet Impingement Shields).................................................................
45 IV.
Reactor Vessel, Internals, and Reactor Coolant System IV.A1 Reactor Vessel (BWR)...............................................................................................
46 IV.A2 Reactor Vessel (PWR)..................................................................................................
48 IV.B1 Reactor Vessel Intemals (BWR)...................................................................................
49 40 Draft-5/25/00 I
IV.B2 Reactor Vessel Internals (PW R) - W estinghouse..........................................................
50 IV.B3 Reactor Vessel Internals (PW R) - Combustion Engineering..........................................
51 IV.B4 Reactor Vessel Internals (PW R) - Babcock & W ilcox..................................................
52 IV.C1 Reactor Coolant Pressure Boundary (BW R)..................................................................
53 IV.C2 Reactor Coolant System & Connected Lines (PW R)....................................................
54 IV.D1 Steam Generator (Recirculating)....................................................................................
55 IV.D2 Steam Generator (Once-Through)................................................................................
56 V.
Engineered Safety Features V.A Containment Spray System (PW R).............................................................................
57 V.B Standby Gas Treatment Systems (Secondary Containment) (BWR)..........................
58 V.C Containment Isolation Components..............................................................................
59 V.D1 Emergency Core Cooling System (PW R).......................................................................
61 V.D2 Emergency Core Cooling System (BW R)......................................................................
63 V.E Fan Cooler System.......................................................................................................
64 VI.
Electrical Components VI.A Electric Cables....................................................................................................................
65 VI.B Electrical Connectors.....................................................................................................
65 VI.C Electrical Penetration Assemblies................................................................................
65 VI.D Electrical Buses..................................................................................................................
66 Vl.E Electrical Insulators.......................................................................................................
66 VIF Transmission Conductors.............................................................................................
66 VI.G Ground Conductors.....................................................................................................
66 VII.
Auxiliary Systems VII.AI New Fuel Storage..........................................................................................................
67 VII.A2 Spent Fuel Storage........................................................................................................
67 VII.A3 Spent Fuel Pool Cooling and Cleanup (PW R).................................................................
67 VII.A4 Spent Fuel Pool Cooling and Cleanup (BWR)..............................................................
68 VII.A5 Suppression Pool Cleanup System (BW R)....................................................................
68 VII.B1 Light Load Handling Systems (Related to Refueling)....................................................
68 VII.B2 Overhead Heavy Load Handling Systems..................................................................
68 VII.C1 Open Cycle Cooling W ater System (Service W ater System)........................................
69 VII.C2 Closed Cycle Cooling W ater System............................................................................
69 VII.C3 Ultimate Heat Sink..........................................................................................................
69 VI.D Compressed Air System................................................................................................
70 VII.EI Chemical and Volume Control System (PW R)..............................................................
70 VII.E2 Standby Liquid Control System (BW R)........................................................................
71 VII.E3 Reactor W ater Cleanup System (BWR)...........................................................................
72 VII.E4 Coolant Storage/Refueling W ater System (PW R).......................................................
72 VII.E5 Shut-down Cooling System (Older BW R)...................................................................
73 Draft - 5/25/00 41
VII.F1 Control Room Area Ventilation System.........................................................................
73 VII.F2 Auxiliary and Radwaste Area Ventilation System.......................................................
74 VII.F3 Primary Containment Heating & Ventilation System.......................................................
74 VII.F4 Diesel Generator Building Ventilation System.............................................................
74 VII.G Fire Protection..............................................................................................................
75 VII.H1 Diesel Fuel Oil System..................................................................................................
75 VII.H2 Em ergency Diesel Generator System..........................................................................
76 V.1 Liquid W aste Disposal System......................................................................................
76 VIII.
Steam and Power Conversion System VIII.A Steam Turbine System s...............................................................................................
77 VIII.B1 M ain Steam System s (PW R)........................................................................................
77 VIII.B2 M ain Steam System (BW R)..........................................................................................
77 VIII.C Extraction Steam System.............................................................................................
78 VIII.D1 Feedwater System (PW R)................................................................................................
78 VIII.D2 Feedwater System (BW R)...........................................................................................
78 VIII.E Condensate System.....................................................................................................
79 VIII.F Steam Generator Blowdown System (PW R)..............................................................
79 VIII.G Auxiliary Feedwater (AFW ) System (PW R).................................................................
80 Draft - 5/25/00 42 I
Chapter II. Containments Item Number in GALL Description II.A PWR Containments II.AI Concrete Containments (Reinforced or Prestressed)
II.A1.1 Concrete elements I.A1.2 Steel elements ILA1.3 Prestressing systems II.A2 Steel Containments Ii.A2.1 Steel elements II.A2.2 Concrete elements II.A3 Common Components II.A3.1 Penetration sleeves, penetration bellows, dissimilar metal welds I1.A3.2 Personal air lock, equipment hatch II.A3.3 Subfoundation layer i1.A3.4 Seals and gaskets 11.B BWR Containments II.B1 Mark I Containments II.BI.1 Steel Containments II.B1.1.1 Steel elements II.B13.2 Concrete Containments II.B13.2.1 Concrete elements II.B13.2.2 Steel elements II.B2 Mark II Containments I1.B2.1 Steel Containments I1.B2.1.1 Steel elements 11.B2.2 Concrete Containments 11.B2.2.1 Concrete elements 11.12.2.2 Steel elements 1I.B2.2.3 Prestressing systems II.B3 Mark III Containments I1.B3.1 Steel Containments 11.B3.1.1 Steel elements 11.B3.1.2 Concrete elements 11.B3.2 Concrete Containments 11.B3.2.1 Concrete elements 11.B3.2.2 Steel elements II.B4 Common Components 11.B4.1 Penetration sleeves, penetration bellows, dissimilar metal welds 11.B4.2 Personal air lock, equipment hatch, CRD hatch 11.B4.3 Subfoundation layer 11.B4.4 Seals and gaskets Draft - 5/25/00 43
Chapter III. Class I Structures and Component Supports Item Number in GALL Description III.A Class I Structures IILA!
BWR Reactor Building, PWR Shield Building, Control Room/Building IIi.A1.1 Concrete elements Ill.A1.2 Steel elements ilI.A1.3 Masonry walls Ill.A2 BWR Reactor Building with Steel Superstructure II1.A2.1 Concrete elements II1.A2.2 Steel elements III.A2.3 Masonry walls Ill.A3 Auxiliary Building, Diesel Generator Building, Radwaste Building, Turbine building, Switchgear Room, AFW Pumphouse, Utility/Piping Tunnels Ill.A3.1 Concrete elements II1.A3.2 Steel elements II1.A3.3 Masonry walls Ill.A4 Containment Interior, excluding Refueling Canal III.A4.1 Concrete elements III.A4.2 Steel elements III.A4.3 Prestressing systems Ill.A5 Fuel Storage Facility, Refueling Canal lil.A5.1 Concrete elements II1.A5.2 Steel elements IIi.A5.3 Masonry walls Ill.A6 Water Control Structures (intake structure, cooling tower, spray pond)
Ill.A6.1 Concrete elements IIL.A6.2 Steel elements II1.A6.3 Masonry walls Ill.A7 Concrete Tanks II1.A7.1 Concrete elements i11.A7.2 Steel elements Ill.A8 Steel Tanks II1.A8.1 Concrete elements II1.A8.2 Steel elements llI.A9 BWR Unit Vent Stack II1.A9.1 Concrete elements Draft - 5/25/00 44
III.B Component Supports 111.B1.1 Supports for ASME Class I Piping and Components Ill.B1.1.1 Support members, anchor bolts, welds Ill.B13.1.2 High strength bolts for major NSSS components III.B1.1.3 Constantlvariable load spring hangers, guides, stops, sliding surfaces, design clearances Ill.B1.1.4 Building concrete surrounding anchor bolts, grout pads Iii.B1.2 Supports for ASME Class 2,3 and MC Piping and Components III.B1.2.1 Support members, anchor bolts, welds III.B1.2.2 Constant/variable load spring hangers, guides, stops, sliding surfaces, design clearances Ill.B13.2.3 Building concrete surrounding anchor bolts, grout pads Ill.B2 Supports for Cable Tray, HVAC Ducts, Tube Track, Instrument Tubing, Non-ASME Piping and Components III.B2.1 Support members, anchor bolts, welds
!11.B2.2 Bolted friction connections (e.g. struts)
I11.B2.3 Building concrete surrounding anchor bolts, grout pads Ill.B3 Anchorage of Racks, Panels, Cabinets, and Enclosures for Electric Equipment and Instrumentation III.B3.1 Support members, anchor bolts, welds II1.B3.2 Building concrete surrounding anchor bolts, grout pads Ill.B4 Supports for Misc. Equipment (e.g., Cranes, EDG, HVAC Components)
II1.B4.1 Support members, anchor bolts, welds III.B4.2 Vibration isolation elements Ill.B4.3 Building concrete surrounding anchor bolts, grout pads 111.B5 Supports for Misc. Steel Structures(e.g., Platforms, Pipe Whip restraints, Jet Impingement Shields)
II.B5.1 Support members, anchor bolts, welds II1.B5.2 Building concrete surrounding anchor bolts, grout pads Draft - 5/25/00 45
Chapter IV.A1. Reactor Vessel (Boiling Water Reactor)
Item Number in GALL Description IV.A1.1 Top Head Enclosure IV.A1.1.1 Top head IV.A1.1.2 Nozzles (vent, top head spray or RCIC, and spare)
IV.A1.1.3 Head flange IV.A1.1.4 Closure studs and nuts IV.A1.1.5 Vessel flange leak detection line IV.A1.2 Vessel Shell IV.A1.2.1 Vessel flange IV.A1.2.2 Upper shell IV.A1.2.3 Intermediate (nozzle) shell IV.A1.2.4 Intermediate (beltline) shell IV.A1.2.5 Lower shell IV.A1.2.6 Beltline welds IV.A1.2.7 Attachment welds IV.A1.3 Nozzles IV.A1.3.1 Main steam IV.A1.3.2 Feedwater IV.A1.3.3 High-pressure coolant injection (HPCI)
IV.A1.3.4 High-pressure core spray (HPCS)
IV.A1.3.5 Low-pressure core spray (LPCS)
IV.A1.3.6 CRD return line IV.A1.3.7 Recirculating water (inlet and outlet)
IV.A1.3.8 Low-pressure coolant injection (LPCI) or RHR injection mode IV.A1.3.9 Isolation condenser supply IV.A1.4 Nozzles safe ends IV.A1.4.1 High-pressure core spray (HPCS)
IV.A1.4.2 Low-pressure core spray (LPCS)
IV.A1.4.3 CRD return line IV.A1.4.4 Recirculating water (inlet and outlet)
IV.A1.4.5 Low-pressure coolant injection (LPCI) or RHR injection mode IV.A1.5 Penetrations IV.AI.5.1 CRD stub tubes IV.A1.5.2 Instrumentation IV.A1.5.3 Jet pump instrument IV.A1.5.4 Standby liquid control IV.A1.5.5 Flux monitor IV. A1.5.6 Drain line IV.A1.6 Bottom head Draft - 5/25/00 46
IV.A1.7 Control rod drive mechanism IV.A1.7.1 Housing IV.A1.8 Support skirt and attachment welds Draft - 5/25/00 47
Chapter IV.A2. Reactor Vessel (Pressurized Water Reactor)
Item Number in GALL Description IV.A2.1 Closure head IV.A2.1.1 Dome IV.A2.1.2 Head flange IV.A2.1.3 Stud assembly IV.A2.1.4 Vessel flange leak detection line IV.A2.2 Control rod drive mechanism IV.A2.2.1 Pressure housing IV.A2.3 Nozzles IV.A2.3.1 Inlet IV.A2.3.2 Outlet IV.A2.3.3 Safety injection (on some)
IV.A2.4 Nozzle safe ends IV.A2.4.1 Inlet IV.A2.4.2 Outlet IV.A2.4.3 Safety injection (on some)
IV.A2.5 Shell IV.A2.5.1 Upper (nozzle) shell IV.A2.5.2 Intermediate and lower shell IV.A2.5.3 Vessel flange IV.A2.6 Core support pads IV.A2.7 Bottom head IV.A2.7.1 Dome IV.A2.8 Penetrations IV.A2.8.1 CRD mechanism IV.A2.8.2 Instrumentation IV.A2.8.3 Leakage monitoring tubes IV.A2.9 Pressure vessel skirt IV.A2.9.1 Skirt support IV.A2.9.2 Cantilever/column support IV.A2.9.3 Neutron shield tank Draft - 5/25/00 48
Chapter IV.B1. Reactor Vessel Internals (Boiling Water Reactor)
Item Number in GALL Description IV.B1.1 Core shroud, shroud head, and core plate IV.B1.1.1 Core shroud head bolts IV.B1.1.2 Core shroud (upper, central, lower)
IV.B1.1.3 Core plate IV.B1.1.4 Core plate bolts IV.BI.1.5 Access hole cover IV.B1.1.6 Shroud support structure IV.B1.1.7 Standby liquid control line IV.B1.1.8 LPCI coupling IV.B1.2 Top guide IV.B1.3 Feedwater spargers IV.B1I.3.1 Thermal sleeve IV.B13.3.2 Distribution header IV.B1.3.3 Discharge nozzles IV.B1.4 Core spray lines and spargers IV.B 1.4.1 Core spray lines (headers)
IV.B1I.4.2 Spray ring IV.B1.4.3 Spray nozzles IV. 1.4.4 Thermal sleeve IV.B1.5 Jet pump assemblies IV.B1.5.1 Thermal sleeve IV.B1.5.2 Inlet header IV.B1.5.3 Riser brace arm IV.B1I.5.4 Holddown beams IV. 1.5.5 Inlet elbow IV.B1.5.6 Mixing assembly IV.B1.5.7 Diffuser IV.B1I.5.8 Castings IV.B1.6 Fuel support and CRD assemblies IV.B1.6.1 Orificed fuel support IV.B1.7 Instrument housings IV.B1.7.1 Intermediate range monitor (IRM) dry tubes IV.B1I.7.2 Low power range monitor (LPRM) dry tubes IV.B1I.7.3 Source range monitor (SRM) dry tubes Draft - 5/25/00 49
Chapter IV.B2. Reactor Vessel Internals (PWR) - Westinghouse Item Number in GALL Description IV.B2.1 Upper internals assembi IV.B2.1.1 Upper support plate IV.B2.1.2 Upper support column IV.B2.1.3 Upper support column bolts IV.B2.1.4 Upper core plate IV.B2.1.5 Upper core plate alignment pins IV.B2.1.6 Fuel pins IV.B2.1.7 Hold-down spring IV.B2.2 RCCA guide tube assemblies IV.B2.2.1 RCCA guide tubes IV.B2.2.2 RCCA guide tube bolts IV.B2.2.3 RCCA guide tube support pins IV.B2.3 Core barrel IV.B2.3.1 Core barrel IV.B2.3.2 Upper core barrel flange IV.B2.3.3 Core barrel nozzles IV. B2.3.4 Thermal shield IV.B2.4 Bafflelformer assembly IV.B2.4.1 Baffle/former plates IV.B2.4.2 Baffle/former bolts IV.B2.5 Lower internal assembly IV.B2.5.1 Lower core plate IV.B2.5.2 Fuel pins IV.B2.5.3 Lower support plate IV.B2.5.4 Lower support plate column IV.B2.5.5 Lower support plate column bolts IV.B2.5.6 Radial keys and clevis inserts IV.B2.5.7 Clevis insert bolts IV.B2.6 Instrumentation support structure IV.B2.6.1 Flux thimble guide tubes IV.B2.6.2 Flux thimbles Draft - 5/25/00 50
Chapter IV.B3. Reactor Vessel Internals (PWR) - Combustion Engineering Item Number in GALL Description IV.B3.1 Upper internals assembly IV.B3.1.1 Upper guide structure support plate IV.B3.1.2 Fuel alignment plate IV.B3.1.3 Fuel alignment plate guide lugs IV.1B3.1.4 Hold-down rings IV.B3.2 CEA shroud assemblies IV.B3.2.1 CEA shrouds IV.B3.2.2 CEA shroud bolts IV.B3.2.3 CEA shrouds extension shaft guides IV.B3.3 Core support barrel IV.B3.3.1 Core support barrel IV.B3.3.2 Core support barrel upper flange IV.B3.3.3 Core support barrel alignment keys IV.B3.4 Core shroud assembly IV.B3.4.1 Core shroud assembly IV.B3.4.2 Core shroud assembly bolts IV.B3.4.3 Core shroud tie rods IV.B3.5 Lower internal assembly IV.B3.5.1 Core support plate IV.B3.5.2 Fuel alignment pins IV.B3.5.3 Lower support structure beam assemblies IV.B3.5.4 Core support column IV.B3.5.5 Core support column bolts IV.B3.5.6 Core support barrel snubber assemblies Draft - 5125/00 51
Chapter IV.B4. Reactor Vessel Internals (PWR) - Babcock & Wilcox Item Number in GALL Description IV.B4.1 Plenum cover and plenum cylinder IV.B4.2 CRA guide tube assemblies IV.B4.2.1 Tubes IV.B4.2.2 Spacer casting IV.B34.2.3 Spider casting IV.B4.2.4 Bolts IV.B4.3 Upper grid assembly IV.1B4.3.1 Upper grid rib section IV.B4.3.2 Upper grid assembly bolts IV.B4.3.3 Plenum rib pads IV.B4.4 Core support assembly IV.B4.4.1 Core support shield IV.B4.4.2 Core support shield flange IV.B4.4.3 Core support shield to core barrel bolts IV.B4.5 Vent valve assembly IV.B4.6 Core barrel assembly IV.B4.6.1 Core barrel IV.B4.6.2 Core barrel bolts IV.B4.6.3 Core barrel to thermal shield bolts IV.B4.7 Lower grid assembly (LGA)
IV.B4.7.1 Upper grid IV.B4.7.2 Fuel guide pads IV.1B4.7.3 Lower grid IV.B4.7.4 Support columns IV.B4.7.5 Cylinder guide blocks IV.B4.7.6 LGA bolts IV.B4.7.7 Core barrel bolts IV.B4.7.8 Flow distributor bolts IV.B4.7.9 Thermal shield bolts IV.B4.8 Flow distributor IV.B4.9 Thermal Shield Draft - 5/25/00 52
Chapter IV.C1. Reactor Coolant Pressure Boundary (Boiling Water Reactor)
Item Number in GALL Description IV.C1.1 Piping and fittings IV.C1.1.1 Main steam IV.C1.1.2 Feedwater IV.C1.1.3 High-pressure coolant injection (HPCI) system IV.C1.1.4 Reactor core isolation cooling (RCIC) system IV.C1.1.5 Recirculation IV.C1.1.6 Residual heat removal (RHR) system IV.C1.1.7 Low-pressure coolant injection (LPCI) system IV.C1.1.8 Low-pressure core spray (LPCS) system IV.C1.1.9 High-pressure core spray (HPCS) system IV.C1.1.10 Isolation condenser IV.C1.1.11 Lines to reactor water cleanup (RWC) and standby liquid control (SLC) systems IV.C1.1.12 Steam line to HPCI and RCIC pump turbine IV.Cl.2 Recirculation pump IV.C1.2.1 Bowl/casing IV.C1.2.2 Cover IV.C1.2.3 Seal flange IV.C1.2.4 Closure bolting IV.CI.3 Safety and relief valves IV.C1.3.1 Valve body IV.C1.3.2 Bonnet IV.C1.3.3 Seal flange IV.C1.3.4 Closure bolting IV.Cl.4 Isolation condenser IV.C1.4.1 Tubing IV. C1.4.2 Tubesheet IV.C1.4.3 Channel head IV.C1.4.4 Shell Draft - 5/25/00 53
Chapter IV.C2. Reactor Coolant System and Connected Lines (Pressurized Water Reactor)
Item Number in GALL Description IV.C2.1 Reactor coolant system piping and fittings IV.C2.1.1 Cold leg IV.C2.1.2 Hot leg IV.C2.1.3 Surge line IV.C2.1.4 Spray line IV.C2.1.5 Small-bore RCS piping IV.C2.2 Connected systems piping and fittings IV.C2.2.1 Residual heat removal (RHR) or low-pressure injection system (Decay heat removal (DHR)/shutdown system)
IV.C2.2.2 Core flood system (CFS)
IV.C2.2.3 Chemical and volume control system or high-pressure injection system (makeup and letdown functions)
IV.C2.2.4 Sampling system IV.C2.2.5 Drains and instrument lines IV.C2.2.6 Nozzles and safe ends IV.C2.2.7 Small-bore piping in connected systems IV.C2.3 Reactor coolant pump IV.C2.3.1 Bowl/casing IV.C2.3.2 Cover IV.C2.3.3 Closure bolting IV.C2.4 Safety and relief valves IV.C2.4.1 Valve body IV.C2.4.2 Bonnet IV.C2.4.3 Closure bolting IV.C2.5 Pressurizer IV.C2.5.1 Shell/heads IV.C2.5.2 Spray line nozzles IV.C2.5.3 Surge line nozzle IV.C2.5.4 Spray head IV.C2.5.5 Thermal sleeves IV.C2.5.6 Instrument nozzle IV.C2.5.7 Safe ends IV.C2.5.8 Manway and flanges IV.C2.5.9 Manway and flange bolting IV.C2.5.10 Heater sheaths and sleeves IV.C2.5.11 Support keys, skirt, and shear lugs IV.C2.5.12 Integral support IV.C2.6 Pressurizer relief tank IV.C2.6.1 Tank shell and heads IV.C2.6.2 Flanges and nozzles Draft - 5/25/00 54
Chapter IV.D1. Steam Generator (Recirculating)
Item Number in GALL Description IV.D1.1 Pressure boundary and structural IV.D1.1.1 Top head IV.D1.1.2 Steam Nozzle and safe end IV.D1.1,3 Upper and lower shell IV.D1.1.4 Transition cone IV.D1.1.5 Feedwater nozzle and safe end IV.D1.1.6 Feedwater impingement plate and support IV.D1.1.7 Secondary manways and bolting IV.D1.1.8 Secondary handholes and bolting IV.D1.1.9 Instrument nozzles IV.D1.1.10 Primary manways and bolting IV.D1.2 Tube bundle IV.D1.2.1 Tubes IV.D1.2.2 Tube support plates IV.D1.2.3 Tube support lattice bars (Combustion Engineering)
IV.D1.2.4 Tube plugs IV.D1.2.5 Tube repair sleeves IV.D1.3 Upper assembly and separators IV.D1.3.1 Feedwater inlet ring IV.D1.4 Piping and fittings IV.D1.4.1 Main steam IV.D1.4.2 Feedwater IV.D1.4.3 Auxiliary feedwater IV.D1.5 Safety and relief valves IV.D1.5.1 Body Draft - 5/25/00 55
Chapter IV.D2. Steam Generator (Once-Through)
Item Number in GALL Description IV.D2.1 Pressure boundary and structural IV.D2.1.1 Upper and lower heads IV.D2.1.2 Tube sheets IV.D2.1.3 Primary nozzles and safe ends iV.D2.1.4 Shell IV.D2.1.5 Feedwater and auxiliary feedwater nozzles and safe ends IV.D2.1.6 Steam nozzles and safe ends IV.D2.1.7 Instrument and drain nozzles IV.D2.1.8 Primary manways and bolting IV.D2.1.9 Secondary manways and bolting IV.D2.2 Tube bundle IV.D2.2.1 Tubes IV.1D2.3 Piping and fittings IV.D2.3.1 Main steam IV.D2.3.2 Feedwater IV.D2.3.3 Auxiliary feedwater IV.D2.4 Safety and relief valves IV.D2.4.1 Body Draft - 5/25/00 56
Chapter V.A. Containment Spray System Item Number in GALL Description V.A.1 Containment Spray System V.A.1.1 Piping and fittings up to isolation valve V.A. 1.2 Flow orifice/elements V.A.1.3 Temperature elements/indicators V.A.1.4 Bolting V.A.1.5 Eductors V.A.2 Header and Spray Nozzles System V.A.2.1 Piping and fittings V.A.2.2 Flow orifice V.A.2.3 Headers V.A.2.4 Spray Nozzles V.A.3 Chemical Addition System V.A.3.1 Piping and fittings V.A.3.2 Storage tank V.A.4 Pumps V.A.4.1 Bowl/casing V.A.4.2 Bolting V.A.5 Valves (hand, control, check, motor-operated) (in containment spray system V.A.5.1 Body and bonnet V.A.5.2 Bolting V.A.6 Valves (hand, control) (in header and spray nozzle system)
V.A.6.1 Body and bonnet V.A.6.2 Bolting V.A.7 Containment Spray Heat Exchanger V.A.7.1 Bonnet/cover V.A.7.2 Tubing V.A.7.3 Shell V.A.7.4 Case/cover V.A.7.5 Bolting Draft - 5/25/00 57
Chapter V.B. Standby Gas Treatment System (Boiling Water Reactor)
Item Number in GALL Description V.B1 Ductwork and Dampers V.B.2 Electric Heater V.B.3 Filters V.B.3.1 Filter housing and supports V.B.3.2 Charcoal absorber filter V.B.3.3 Elastomer seals V.B.4 Fan Draft - 5/25/00 58
Chapter V.C. Containment Isolation Components Item Number in GALL Description V.C.1 Personnel Hatch V.C.1.1 Hatchway V.C.1.2 Inner door V.C.1.3 Outer door V.C.2 Equipment Hatch V.C.2.1 Hatchway V.C.2.2 Cover Plate V.C.3 Mechanical (Pipe) Penetrations V.C.3.1 Sleeve V.C.3.2 Seal V.C.3.3 Closure plate V.C.3.4 Anchors V.C.3.5 Fasteners V.C.4 Electrical Penetrations V.C.4.1 Sleeve V.C.4.2 Header plate V.C.4.3 Seal V.C.4.4 Anchors V.C.5 Fuel Transfe'r Penetrations V.C.5.1 Sleeve V.C.5.2 Closure V.C.5.3 Anchors V.C.6 PurgeNent V.C.6.1 Seal V.C.7 Leak Testing (Penetration, Integrated, & Isolation Valve Leak Test Systems V.C.7.1 Mechanical penetrations V.C.7.2 Sleeves V.C.7.3 Seal V.C.8 Isolation Barriers - Valves (BWR, In Lines for Emergency Core Cooling Systems, Feedwater, Main Steam V.C.8.1 Body V.C.8.2 Bonnet
_____________________ I Draft - 5/25/00 59
V.C.9 Isolation Barriers - Valves (PWR, in Lines for Emergency Core Cooling Systems, Feedwater, Auxiliary Feedwater, Main Steam, and Blowdown Piping V.C.9.1 Body V.C.9.2 Bonnet V.C.10 Isolation Barriers - Valves (BWR and PWR, in Lines for Fire Protection, Plant Heating, Waster Gas, Plant Drain, Liquid Waste, & Cooling V.C.10.1 Body V.C.10.2 Bonnet Draft - 5/25/00 60
Chapter V.D1. Emergency Core Cooling (Pressurized Water Reactor)
Item Number in GALL Description V.DI.1 Piping & Fittings V.D1.1.1 Core flood system (CFS)
V.D1.1.2 Residual heat removal (RHR) or shutdown cooling (SDC)
V.D1.1.3 High pressure safety injection (HPSI)
V.D1. 1.4 Low pressure safety injection (LPSI)
V.DI.1.5 Connecting lines to chemical and volume control (CVCS) & spent fuel storage pool (SFP) cooling V.D1.1.6 Lines to emergency sump V.D1.1.7 Bolting for flange connections V.D1.2 HPSI & LPSl Pumps V.D1.2.1 Bowl/casing V.D1.2.2 Bolting V.D1.3 RWT Circulation Pump V.D1.3.1 Bowl/casing V.D1.3.2 Bolting V.11.4 Valves V.D1.4.1 Body and bonnet V.D1.4.2 Bolting V.D1.5 Heat Exchangers (RCP, HPS & LPSI Pump Seals, & RHR)
V.D1.5.1 Bonnet/cover V.D1.5.2 Tubing V.D1.5.3 Shell V.D1.5.4 Case/cover V.D1.5.5 Bolting V.D1.6 Heat Exchangers (RWT Heating)
V.D1.6.1 Bonnet/cover V.D1.6.2 Tubing V.D1.6.3 Shell V.D1.6.4 Bolting V.D1.7 Safety Injection Tank (Accumulator)
V.D1.7.1 Shell V.D1.7.2 Manway V.D1.7.3 Penetrations/nozzles V.D1.8 Refueling Water Tank (RWT)
V.D1.8.1 Shell V.D1.8.2 Manhole V.D1.8.3 Penetrations/nozzles Draft - 5/25/00 61
I V.D1.8.4 IBolting V.D1.8.5 Perimeter seal Draft - 5/25/00 62
Chapter V.D2. Emergency Core Cooling System (BWR)
Item Number in GALL Description V.D2.1 Piping & Fittings V.D2.1.1 High pressure coolant injection (HPCI)
V.D2.1.2 Reactor core isolation (RCIC)
V.D2.1.3 High pressure core spray (HPCS)
V.D2.1.4 Low pressure core spray (LPCS)
V.D2.1.5 Low pressure coolant injection (LPCI) or residual heat removal (RHR)
V.D2.1.6 Lines to spent fuel pool (SFP) and suppression chamber (SC)
V. D2.1.7 Lines to containment spray system (CSS)
V.D2.1.8 Automatic depressurization system (ADS)
V.D2.1.9 Lines to HPCI and RCIC pump turbine V.D2.1.10 Lines from HPCI and RCIC pump turbines to condenser V.D2.2 Pumps (HPCS or HPCI Main & Booster, LPCS, LPCI or RHR, & RCIC)
V.D2.2.1 Bowl/casing V.D2.2.2 Suction head V.D2.2.3 Discharge head V.D2.3 Valves (check, control, hand, motor operated, & relief valves)
V.D2.3.1 Body and bonnet V.D2.4 Heat exchangers (RHR & LPCl)
V.D2.4.1 Tubes V.D2.4.2 Tubesheet V.D2.4.3 Channel head V.D2.4.4 Shell V.D2.5 Header and Spray Nozzles System V.D2.5.1 Piping and fittings V.D2.5.2 Flow orifice V.D2.5.3 Headers V.D2.5.4 Spray nozzles V.D2.6 Isolation Condenser V.D2.6.1 Tubing V.D2.6.2 Tubesheet V.D2.6.3 Channel head V.D2.6.4 Shell Draft - 5/25/00 63
Chapter V.E. Fan Cooler System Item Number in GALL Description V.E.1 Fan Cooler System V.E.1.1 Cooling coils V.E.1.2 Fan housing V.E.1.3 Blades V.E.1.4 Fasteners V.E.1.5 Piping V.E.1.6 Fittings Draft - 5/25/00 64
Chapter VI.A. Electric Cables Item numbers in GALL Description VI.A.1 Power, control, & instrument cables VI.A.1.1 Conductor VI.A. 1.2 Shield wire VI.A.1.3 Insulation VI.A. 1.4 Jacket Chapter VI.B. Electrical Connectors Item numbers in GALL Description VI.B.1 Splices VI.B.1.1 Jackets VI.B.1.2 Seals VI.B.1.3 Insulators VI.B.2 Mechanical connectors VI.B.2.1 Terminal lugs, compression fittings, fusion connectors, contact pins VI.B.3.
Terminal blocks VI.B.3.1 Block assembly Chapter VI.C. Electrical Penetration Assemblies (EPA)
Item numbers in GALL Description VI.C.1 Modular EPA VI.C.1.1 O-ring seals VI.C.1.2 Conductor-to-insulator seals VI.C.1.3 Cable lead wires VI.C.1.4 Interface connectors Draft - 5/25/00 65
Chapter VI.D. Electrical Buses Item numbers in GALL Description VI.D.1 Isolated phase bus VI.D. 1.1 Bus assembly VI.D.1.2 Bus support assembly VI.D.1.3 Bus enclosure assembly VI.D.1.4 Bus bushing assembly VI.D.2 Non-segregated phase bus VI.D.2.1 Bus assembly VI.D.2.2 Bus support assembly VI.D.2.3 Bus enclosure assembly VI.D.2.4 Bus bushing assembly VI.D.3 Segregated phase bus VI.D.3.1 Bus assembly VI.D.3.2 Bus support assembly VI.D.3.3 Bus enclosure assembly VI.D.4 Switchyard bus VI.D.4.1 Bus enclosure Chapter VI.E. Electrical Insulators Item numbers in GALL Description VI.E.1 Station post insulators VI.E.1.1 Assembly VI.E.2 Strain/suspension insulators VI.E.2.1 Assembly Chapter VI.F. Transmission Conductors Item numbers in GALL Description VI.F.1 Conductor VI.F.1.1 Assembly Chapter VI.G. Ground Conductors Item numbers in GALL Description VI.G.1 Conductor VI.G.1.1 Assembly Draft - 5/25/00 66
Chapter VII.AI. New Fuel Storage Item Number in GALL Description VII.A1 New Fuel Storage VII.A.11 New Fuel Rack VIII. A1.1.1 New Fuel Rack Assembly Chapter VII.A2 Spent Fuel Storage Item Number in GALL Description, VII.A2.
Spent Fuel Storage VII.A2.1 Spent Fuel Storage Rack V1I.A2.1.1 Neutron-Absorbing Sheets Chapter VII.A3. Spent Fuel Pool Cooling and Cleanup (PWR)
Item Number in GALL Description VII.A3.1 Piping VII.A3.1.1 Pipe, Fittings and Flanges VII.A3.1.2 Studs and Nuts VII.A3.2 Filter VII.A3.2.1 Studs and Nuts VII.A3.3 Strainer VII.A3.3.1 Studs and Nuts VII.A3.4 Check Valve VII.A3.4.1 Body and Bonnet VII.A3.4.2 Studs and Nuts VII.A3.5 Hand Valve VII.A3.5.1 Body and Bonnet VII.A3.5.2 Studs and Nuts VII.A3.5.3 Linings VII.A3.6 Heat Exchanger VII.A3.6.1 Shell VII.A3.6.2 Nozzles VII.A3.6.3 Studs and Nuts VII.A3.7 Ion Exchanger VII.A3.7.1 Studs and Nuts VII.A3.8 Pump VII.A3.8.1 Casing VII.A3.8.2 Studs and Nuts VII.A3.9 Flow Orifice Draft - 5/25/00 67
VII.A3.9.1 Studs and Nuts VII.A3.10 Spent Fuel Transfer Tube VIL.A3.10.1 Studs and Nuts Chapter VII.A4. Spent Fuel Pool Cooling and Cleanup (BWR)
Item Number in GALL Description VII.A.4.1 Piping VII.A.4.1.1 Pipe, Fittings and Flanges VII.A.4.2 Valves VII.A.4.2.1 Body and Bonnet VII.A.4.3 Heat Exchanger VII.A.4.3.1 Shell VII.A.4.4 Pump VII.A.4.4.1 Casing VII.A5. Suppression Pool Cleanup System (BWR)
See Evaluation Summary, Page VII A5-1 of the draft GALL report (12/06/99)
Chapter VII.B1.
Light Load Handling Systems (Related to Refueling)
Item Number in GALL Description VII.B1.1 Bridge and Trolley (for cranes that fall within the scope of 10 CFR 54)
VII.B1.1.1 Structural Girders VII.B1.2 Rail System VII.B1.2.1 Frame Cut Holes VII.B1.2.2 Rail Chapter VII.B2. Overhead Heavy Load Handling System Item Number in GALL Description VII.B2.1 Bridge and Trolley (for cranes that fall within the scope of 10 CFR 54)
VIi.B2.1.1 Structural Girders VII.B2.2 Rail System VII.B2.2.1 Frame Cut Holes VIi.B2.2.2 Rail Draft - 5125/00 I
I 68
Chapter VII.C1. Open Cycle Cooling Water System (Service Water system)
VII.C1.1 Piping VII.CI.1.1 Piping and Fittings VII.C1.1.2 Underground Piping and Fittings VI1C1.?
Valves VI1.C1.2.1 Body and Bonnet VP.C1.3 Heat Exchanger VII.C1.3.'1 Shell VII.C1.3.2 Channel VII.C1.3.3 Channel Head VII.C1.3.4 Tube Sheets VII.C1.3.5 Tubes VIl.CI.4 Flow Orifice VIL.C1.4.1 Body VI1.CI.5 Pump Vll.C1.5.1 Casing VI1.Cl.6 Basket Strainer VII.C1.6.1 Body Chapter VII.C2. Closed Cycle Cooling Water System Item Number in GALL Description VII.C2.1 Piping VI1.C2.1.1 Pipe, Fittings, and Flanges VII.C2.2 Valves (Check, Hand, Control, Relief, and Solenoid Valves)
VIi.C2.3.1 Body and Bonnet VII.C2.3 Pump VII.C2.3.1 Casing VII.C2.4 Tank VII.C2.4.1 Shell VII.C2.5 Flow Orifice VII.C2.5.1 Body Chapter VII.C3. Ultimate Heat Sink Item Number in GALL Description VII.C3.1 Cooling Tower VII.C3.1.1 Foundation Draft - 5/25/00 69
VII.C3.1.2 Exterior Concrete Above Grade VII.C3.1.3 Exterior Concrete Below Grade VII.C3.1.4 Interior Slabs VII.C3.1.5 Masonry Block Wall VII.C3.1.6 Concrete Surfaces Exposed to Flowing Water VII.C3.1.7 Columns VII.C3.1.8 Base Plates VII.C3.1.9 Beams VII.C3.1.10 Trusses VII.C3.1.11 Bracings VILC3.2 Piping VIL.C3.2.1 Piping and Fittings VII.C3.3 Valves (Check, Hand, and Control Valves)
VII.C3.3.1 Body and Bonnet VII.C3.4 Pump VII.C3.4.1 Casing Chapter VII.D. Compressed Air System Item Number in GALL Description VII.D.1 Piping VII.D.1.1 Piping and Fittings VII.D.2 Air Accumulator ViI.D.2.1 Shell VII.D.2.2 Manway ViI.D.2.3 Manway Bolting VII.D.3 Valves VII.D.3.1 Body and Bonnet VII.D.4 Filter VII.D.4.1 Shell VII.D.4.2 Manway VII.D.4.3 Manway Bolting Chapter VII.EI, Chemical and Volume Control System (PWR)
Item Number in GALL Description VII.E1.1 Piping (1500 psig rating)
VII.E1.1.1 Pipe, Fittings and Flanges VII.E1.1.2 Stud and Nuts VII.E1.2 Piping (150 psig rating)
VII.El.2.1 Pipe, Fittings and Flanges VII.El.2.2 Studs and Nuts Draft - 5/25/00 70
VII.E1.3 High-Pressure Valve VII.El.3.1 Body and Bonnet VII.E1.3.2 Studs and Nuts VII.E1.4 Low-Pressure Valve Vii.El.4.1 Body and Bonnet VII.E1.4.2 Studs and Nuts VII.E1.5 High-Pressure Pump VII.E1.5.1 Casing VII.E1.5.2 Closure Bolting VII.E1.6 Low-Pressure Pump VII.EI.6.1 Casing VII.E1.6.2 Closure Bolting VII.E1.7 Letdown Heat Exchanger Vii.E1.7.1 Tube/Tubesheet VII.El.7.2 Studs and Nuts VII.El.7.3 Channel/Cover VIi.E 1.7.4 Channel/Welds VII.E1.7.5 Shell VII.E1.8 Regenerator Heat Exchanger VII.EI.8.1 Tube/Tubesheet VII.EI.8.2 Studs and Nuts VIl.E 1.8.3 Channel/Cover VII.E1.8.4 Channel/Welds Vii.EI.8.5 Shell VII.E1.9 Basket Strainers VII.El.9.1 Studs and Nuts VII.EI.10 Tank VII.E1.10.1 Studs and Nuts VII.E1.10.2 Shell VII.E1.10.3 Manway VII.El.10.4 Penetrations/Nozzles Chapter VII.E2. Standby Liquid Control System (BWR)
Item Number in GALL Description VII.E2.1 Piping VII.E2.2 Solution Storage Tank VII.E2.3 Solution Storage Tank Heaters VII.E2.4 Pump Suction Valves VII.E2.5 Injection Pumps VII.E2.6 Relief Valves VII.E2.7 Injection Valves VII.E2.8 Containment Isolation Valves VII.E2.9 Injection Sparger VII.E2.10 Pump Suction Valves Draft - 5/25/00 71
Chapter VII.E3. Reactor Water Cleanup System Item Number in GALL Description VII.E3.1 Piping VII.E3.1.1 Pipe and Fittings (beyond isolation valves)
VII.E3.2 Reactor water cleanup (RWCI1) Pump VIL.E3.2.1 Bowl/Casing VIL.E3.2.2 Cover VI.E3.2.3 Seal Flange VII.E3.2.4 Closure Bolting VIi.E3.3 Valves (Quality Group D)
VII.E3.3.1 Body VII.E3.3.2 Bonnet VII.E3.3.3 Seal Flange VII.E3.3.4 Closure Bolting VIi.E3.4 Regenerative Heat Exchanger VII.E3.4.1 Tubing VII.E3.4.2 Shell VII.E3.5 Non-Regenerative Heat Exchanger VII.E3.5.1 Tubing VII.E3.5.2 Shell VII.E3.6 Filter/Demineralizer VIi.E3.6.1 Internals Chapter VII.E4. Coolant StoragelRefueling Water Cleanup System Item Number in GALL Description VII.E4.1 Refueling Water Tank (RWT) Heating VII.E4.1.1 Piping and Fittings VIL.E4.2 RWT Circulation Pump VII.E4.2.1 Bowl/Casing VII.E4.2.2 Bolting VII.E4.3 Valves VII.E4.3.1 Body VII.E4.4 Heat Exchanger (RWT Heating)
VII.E4.4.1 Bonnet or Cover VII.E4.4.2 Tubing
- VII.E4.4.3 Shell VII.E4.5 Refueling Water Tank VII.E4.5.1 Shell VII.E4.5.2 Manhole Draft - 5/25/00 72
VII.E4.5.3 Penetrations/Nozzles VII.E4.5.4 Tank Heating Coil VII.E4.5.5 Manhole Bolting VII.E4.5.6 Perimeter Seal Chapter VIIE5.
Shutdown Cooling System (Older BWR)
Item Number in GALL Description VII.E5.1 Piping VII.E5.1.1 Piping and Fittings VII.E5.1.2 Bolting VII.ES.2 Pump VII.E5.2.1 Bowl/Casing VII.E5.2.2 Bolting VIi.E5.3 Valves VII.E5.3.1 Body and Bonnet VII.E5.3.2 Bolting VII.E5.4 Heat Exchanger VII.E5.4.1 Tubes VII.E5.4.2 Tubesheet VII.E5.4.3 Channel and Head VII.E5.4.4 Shell VII.E5.4.5 Bolting Chapter VIIFI. Control Room Area Ventilation System Item Number in GALL Description VII.F1.1 Duct VII.F1.1.1 Duct, Fittings, and Access Doors VII.F1.1.2 Equipment Frames and Housing VII.F1.1.3 Flexible Collars between Ducts and Fans VII.F1.1.4 Seals in Dampers and Doors VII.F1.2 Air Handler HeatinglCooling VII.F1.2.1 Heating/Cooling Coils VII.F1.3 Piping VIIF1.3.1 Piping and Fittings Draft - 5/25/00 73
Auxiliary and Radwaste Area Ventilation System Item Number in GALL Description VILF2.1 Duct VII.F2.1.1 Duct, Fittings, and Access Doors VII.F2.1.2 Equipment Frames and Housing VII.F2.1.3 Flexible Collars between Ducts and Fans VII.F2.1.4 Seals in Dampers and Doors VII.F2.2 Air Handler HeatinglCooling VIi.F2.2.1 Heating/Cooling Coils VII.F2.3 Piping VII.F2.3.1 Piping and Fittings Chapter VII. F3. Engineered Safety Feature Ventilation System (Primary Containment Area)
Item Number in GALL Description VII.F3.1 Duct VII.F3.1.1 Duct, Fittings, and Access Doors VII.F3.1.2 Equipment Frames and Housing VII.F3.1.3 Flexible Collars between Ducts and Fans VIL.F3.1.4 Seals in Dampers and Doors VII.F3.2 Air Handler HeatinglCooling VII.F3.2.1 Heating/Cooling Coils VII.F3.3 Piping VII.F3.3.1 Piping and Fittings Chapter VII.F4. Diesel Generator Building Ventilation System Item Number in GALL Description VII.F4.1 Duct VII.F4.1.1 Duct, Fittings, and Access Doors VII.F4.1.2-Equipment Frames and Housing VII.F4.1.3 Flexible Collars between Ducts and Fans VII.F4.1.4 Seals in Dampers and Doors VII.F4.2 Air Handler Heating/Cooling VII.F4.2.1 Heating/Cooling Coils VII.F4.3 Piping VII.F4.3.1 Piping and Fittings Draft - 5/25/00 Chapter VII.F2.
74
Chapter VII.G. Fire Protection Item Number in GALL Description VIIG.1 Intake Structure VII.G.1.1 Fire Barrier Penetration Seals VII.G.1.2 Fire Barrier Walls, Ceiling, and Floors VII.G.1.3 Fire Rated Doors VII.G.2 Turbine Building VII.G.2.1 Fire Barrier Penetration Seals VII.G.2.2 Fire Barrier Walls, Ceiling, and Floors VII.G.2.3 Fire Rated Doors VII.G.3 Auxiliary Building VII.G.3.1 Fire Barrier Penetration Seals VII.G.3.2 Fire Barrier Walls, Ceiling, and Floors VII.G.3.3 Fire Rated Doors VII.G.4 Diesel Generator Building VII.G.4.1 Fire Barrier Penetration Seals VII.G.4.2 Fire Barrier Walls, Ceiling, and Floors VII.G.4.3 Fire Rated Doors VII.G.5 Primary Containment VII.G.5.1 Fire Barrier Walls, Ceiling, and Floors VII.G.5.2 Fire Rated Doors VII.G.6 High-Pressure Service Water System VII.G.6.1 Piping and Fittings VII.G.6.2 Filter, Fire Hydrants, Mulsifier, Pump Casing, Sprinkler, Strainer, and Valve Bodies VII.G.7 Reactor Coolant Pump Oil Collect System VII.G.7.1 Tank VII.G.7.2 Piping, Tubing, Valve Bodies VII.G.8 Diesel Fire System VII.G.8.1 Diesel-Driven Fire Pump and Fuel Supply Line Chapter VII.HI Diesel Fuel Oil System Item Number in GALL Description VII.H1.1 Piping VII.H1.1.1 Aboveground Pipe and Fittings VII.H1-.1.2 Underground Pipe and Fittings VII.H1.2 Valves VII.H1-.2.1 Body and Bonnet VII.H1-.2.2 Closure Bolting VII.H1.3 Pump VII.H1.3.1 Casing VII.H1.3.2 Closure Bolting Draft - 5125/00 75
VII.H1.4 Tank VII.H1.4.1 Tank Internal Surfaces VII.H1.4.2 Tank External Surfaces VII.H1.4.3 Caulking and Sealant Chapter VII.H2. Emergency Diesel Generator System Item Number in GALL Description VII.H2.1 Diesel Engine Cooling Water.Subsystem VII.H2.1.1 Pipe and Fittings VII.H2.2 Diesel Generator Air Starting Subsystem VII.H2.2.1 Pipe and Fittings VII.H2.2.2 Hand Valve VII.H2.2.3 Check Valve VII.H2.2.4 Drain Trap VII.H2.2.5 Air Accumulator Vessel VII.H2.3 Diesel Generator Combustion Air Intake Subsystem VII.H2.3.1 Piping and Fittings VII.H2.3.2 Filter VII.H2.3.3 Muffler VII.H2.4 Diesel Generator Combustion Exhaust Air Subsystem VII.H2.4.1 Piping and Fittings VII.H2.4.2 Muffler VII.H2.5 Diesel Generator Fuel Oil Subsystem VII.H2.5.1 Day Tank VII.H2.5.2 Dip Tank VII.H2.5.3 Strainer Chapter VII.I. Liquid Waste Disposal System Item Number in GALL Description VII.I.1 Piping VII.I.2 Pumps VII.I.3 Valves VII.I.4 Tanks VII.I.5 Evaporators VII.I.6 Demineralizers VII.I.7 Gas Strippers Draft - 5/25/00 76
Chapter VIII.A. Steam Turbine System Item Number in GALL Description VIII.A.1 Piping and Fittings VIII.A.1.1 HP Turbine to MSR VIII.A.1.2 MSR to LP Turbine Chapter VIIIB1. Main Steam System (PWR)
Item Number in GALL Description VIII.B1.1 Piping and Fittings VIII.B13.1.1 Steam Lines to Main Turbine VIIIB1.1.2 Lines to FW and AFW Pump Turbines VIII.B1.1.3 Lines to Moisture Separator/Reheater VIII.B1.1.4 Turbine Bypass VIII.B1.1.5 Steam Drains VIII.B1.2 Valves (Check, Control, Hand, Motor Operated Valves)
VIII.B1.2.1 Body Chapter VIII.B2. Main Steam System (BWR)
Item Number in GALL Description VIII.B2.1 Piping and Fittings VIII.B2.1.1 Steam Lines to Main Turbine (Group B)
VIII.B2.1.2 Steam Lines to Main Turbine (Group D)
VIII.B2.1.3 Lines to FW Pump Turbines VIII.B2.1.4 Lines to Moisture Separator/Reheater VIII.B2.1.5 Turbine Bypass VIII.B2.1.6 Steam Drains VIII.B2.2 Valves (Check, Control, Hand, Motor-Operated Valves)
VIII.B2.2.1 Body VIII.B2.2.2 Bolting Draft - 5/25/00 77
Chapter VIII.C. Extraction Steam System Item Number in GALL Description VIII.C.1 Piping and Fittings VIII.C.1.1 Lines to Feedwater Heaters VIII.C.1.2 Steam Drains VIII.C.2 Valves VIII.C.2.1 Body Chapter VIII.D1. Feedwater Systems (PWR)
Item Number in GALL Description VIII.D1.1 Main Feedwater Line ViII.D1.1.1 Pipe and Fittings VIII.D1.2 Valves (Control, Check, and Hand Valves)
V1II.D1.2.1 Body VIII.D1.3 Feedwater Pump (Steam Turbine-and Motor-Driven)
VIII.D1.3.1 Casing VIII.D1.3.2 Suction and Discharge Lines Chapter VIII.D2. Feedwater Systems (BWR)
Item Number in GALL Description VIII.D2.1 Main Feedwater Line VIII.D2.1.1 Pipe and Fittings VIIl.D2.1.2 Bolting for Flange Connections VIII.D2.2 Valves (Control, Check, and Hand Valves)
VIII.D2.2.1 Body VIII.D2.3 Feedwater Pump (Steam Turbine-and Motor-Driven)
VIII.D2.3.1 Casing VIII.D2.3.2 Suction and Discharge Lines Draft - 5/25/00 78
Chapter VIII.E. Condensate System VIII.E.1 Condensate Lines VIII.E.4.1 Piping and FiTbings VIII.E.2 Valves VIII.E.2.1 Body VIII.E.3 Condensate Pumps (Main and Booster Pumps)
VIII.E.3.1 Casing VIII.E.4 Condensate CoolersyCondensers VIII.E.4.1 Tubes VIII.E.4.2 Tubesheet VIII.E.4.3 ChannelHead VIII.E.4.4 Shell VIII.E.C Condensate Storage VIII.E.5.1 Tank VIII.E.6 Condensate Cleanup System VIII.E.6.1 Piping and Fittings VIII.E.6.2 Demineralizer VIII.E6.3 Strainer VIII.E.6.4 Filter Chapter VIII.F. Steam Generator Blowdown System (PWR)
Item Number in GALL Description VIII.F.1 Blowdown Lines VIII.F.I.1 Pipe and Fittings (Group B)
VIII.F.1.2 Pipe and Fittings (Group D)
VIII.F.2 Valves VIII.F.2.1 Body VilI.F.3 Blowdown Pump VIII.F.3.1 Casing VIII.F.4 Blowdown Heat Exchanger VIII.F.4.1 Tubes VIII.F.4.2 Tubesheet VIII.F.4.3 Channel Head VIII.F.4.4 Shell Draft - 5/25/00 79
Chapter VIII.G. Auxiliary Feedwater (AFW) System (PWR)
Item Number in GALL Description VIII.G.1 Auxiliary Feedwater Piping VIII.G.1.1 Pipe and Fittings (Above Ground)
VIII.G.1.2 Pipe and Fittings (Buried)
VIII.G.2 AFW Pumps (Steam Turbine-and Motor-Driven)
VIII.G.2.1 Casing VIII.G.2.2 Suction and Discharge Lines VIII.G.2.3 Bolting VIII.G.3 Valves (Control, Check, Hand Valves)
VIII.G.3.1 Body VIII.G.4 Condensate Storage (Emergency)
VIII.G.4.1 Tank VIII.G.5 Bearing Oil Coolers VIII.G.5.1 Shell VIII.G.5.2 Tubes VIII.G.5.3 Tubesheet Draft - 5/25/00 80