ML20057A360
| ML20057A360 | |
| Person / Time | |
|---|---|
| Issue date: | 08/27/1993 |
| From: | Hoffman S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9309140079 | |
| Download: ML20057A360 (79) | |
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/gesi stic UNITED STATES l
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August 27, 1993 1
j ORGANIZATION: Westinghouse Owners Group j
SUBJECT:
SUMMARY
OF MEETING REGARDING THE WESTINGHOUSE OWNERS GROUP LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM j
On August 18, 1993, representatives of the Westinghouse Owners Group (WOG)l and
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the Nuclear Regulatory Commission (NRC) staff met in Rockville, Maryland, to discuss the WOG life cycle management / license renewal-(LCM /LR) program.
' is a list of meeting attendees. contains the presentation materials discussed at the meeting.
After a brief discussion of the WOG organization, the WOG representatives provided an overview of their LCM /LR program and. industry interactions. The basic objectives of the program are to (1) assist plants with life cycle 3
management, (2) recognize and utilize maintenance rule activities'that-are j
similar to license renewal activities, and (3) develop a cost-effective approach to license renewal. A copy of the WOG LCM /LR Program Plan was provided at the meeting and is contained in Enclosure 3.
The WOG intends to coordinate with_the Nuclear Management and Resources Council (NUMARC) and--
other industry groups-working in the LCM /LR area to resolve policy issues and to develop consistent industry approaches where possible. The goal is to take advantage of previous and ongoing industry work on LCM /LR and to share WOG results.
A fundamental aspect of the W0G's approach is the development of generic technical reports on specific LCM /LR topics that would be submitted for NRC approval. Once approved, the WOG's intent is that utilities would reference the reports, reducing the amount of NRC review of individual applications. An estimated 30 to 40 reports will be submitted over the 5 year duration'of.the N11C HLE CEnHERBOPY ga wc2p-J y is t, t - % p/g m e d j m
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e August 18, 1993, Meeting Summary t program.
The WOG stated that the first report on its integrated plant assessment (IPA) process is scheduled for submittal in October 1993.
The WOG IPA process is intentionally being developed to be identical to the IPA process being established by NUMARC industry activities.
Stephen T. Hoffman, Senior Project Manager License Renewal and Environmental Review Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
l 1.
List of Attendees l
2.
WOG Presentation Material l
3.
WOG LCM /LR Program Plan, I
Revision 0 cc w/ enclosures:
See next page
August 27, 1993 0
i August 18, 1993, Meeting Summary program. The WOG stated that the first report on its integrated plant assessment (IPA) process is scheduled for submittal in October 1993.
The WOG IPA process is intentionally being developed to be identical to the IPA process being established by NUMARC industry activities.
Original signed by:
Stephen T. Hoffman, Senior Project Manager License Renewal and Environmental Review Project Directorate t
i As:.ociate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation i
Enclosures:
1.
List of Attendees l
2.
WDC Presentation Material l
3.
WOG LCM /LR Program Plan, l
Revision 0 l
cc w/ enclosures:
See next page l
l DISTRIBUTION w/ enclosures:
Central Files PDR PDLR R/F TMurley/FMiraglia, 12G18 JPartlow, 12G18 DCrutchfield, llH21 i
WTravers, llH21 SNewberry, llF23 FAkstulewicz, 11F23 SHoffman, llF23 LLuther, 11F23 OGC EJordan, MNBB3701 ACRS (10)
PTKuo, 11F23 NRC Participants j
PDLR:LA PDLR:SP L J-PDGc66 /_
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DOCUMENT NAME:
HOFFMAN 8/13 MEETING
SUMMARY
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Westinghouse Owners Group Life Cycle Management / License Renewal Program cc:
Lawrence A. Walsh Derek Batchlor North Atlantic Energy Service Wisconsin Electric Power Company Corporation 231 West Michigan P.O. Box 300 Milwaukee, Wisconsin 53201 Seabrook, New Hampshire 03874 George Roulett Ted A. Meyer American Electric Power Westinghouse Electric Corporation Service Corporation P. O. Box 355 One Riverside Plaza Pittsburgh, Pennsylvania 15230 Columbus, Ohio 43215 Grant Chappel Carolina Power and Light Company l
P.O. Box 1551 Raleigh, North Carolina 27602 Don Eggett Commonwealth Edison 1400 Opus Place Suite 300 l
Downers Grove, Illinois 60515 Greg Robison Duke Power Company P.O. Box 1006 Charlotte, North Carolina 28201-1006 Robert J. McDevitt Pacific Gas and Electric Company Nuclear Engineering Services P.O. Box 770000 San Francisco, California 94177 l
John R. Jorgensen i
Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 John M. Giddens Southern Nuclear Operating Co.
P.O. Box 1295 Birmingham, Alabama 35201 l
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i AUGUST 18. 1993 ATTENDANCE LIST NRC MEETING WITH WESTINGHOUSE OWNERS GROUP (WOG)
LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM NAME ORGANIZATION Steve Hoffman NRC William Travers NRC Scott Newberry NRC John Giddens Southern Nuclear /WOG Bob Link Wisconsin Electric /WOG Ted Meyer Westinghouse Steve Tritch Westinghouse Tom Murley NRC Frank Akstulewicz NRC Rebecca Nease NRC Dennis Crutchfield NRC Lynn Connor Southern Technical Services Steve Reynolds NRC P.T. Kuo NRC l
Jeff Sharkey NRC Frank Talbot NRC Scott Flanders NRC Debbie Jackson NRC I
l C. Ken McCoy Georgia Power Company /WOG Paul Shemanski NRC Scott Wingate NUS Larry Walsh WOG Chairman David Stellfox McGraw-Hill Sam Lee NRC Ron Parkhill NRC Tom Tai Bechtel Anthony Pfeffer Bechtel Raj Anand NRC Gregory D. Robison Duke Power Co./WOG Doug Walters NUMARC Tom Hiltz NRC i
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UFE CYCLE MANAGEMENT A L%
Ennn i
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UCENSE RENEWAL PROGRAM PRESENTATION TO THE l
NUCLEAR REGULATORY COMMISSION August 18,1993
l AGENDA
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. __. _ WOG-NRC LICENSE RENEWAL MEETING 1
AUGUST 18,1993 l
i INTRODUCTION j
l Participants (NRC/WOG/W) i Utility Perspective on License Renewal j
Overview of Westinghouse Owners Group OVERVIEW OF WOG LIFE CYCLE MANAGEMENT /
LICENSE RENEWAL PROGRAM Program Overview WOG Strategy for License Renewal Program Objectives Management Structure / Charter Program Plan l
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Integrated Plant Assessment (IPA) Process Generic Technical Reports INDUSTRY INTERACTIONS i
Owners Groups 1
NUMARC LRI AHAC i
CE Utilities FUTURE INTERACTIONS WITH NRC l
IPA Process Submittal Screening (ITLR) Submittal Technical Report Format and Content Technical Report Submittal /SER Request NRC PERSPECTIVE ON LICENSE RENEWAL NRC License Renewal Workshop Reaction to WOG LCM /LR Program CLOSING REMARKS NRC WOG
UFE CYCLE MANAGEMENT i
N UCENSE RENEWAL PROGRAM l
UTILITY PERSPECTIVE ON LICENSE RENEWAL:
l o
REGULATORY PROCESS AND REQUIREMENTS NEED TO BE STABILIZED AND WELL-DEFINED COST TO ACHIEVE PLANT-SPECIFIC LICENSE RENEWAL o
l MUST BE AFFORDABLE l
o RENEWED LICENSE SHOULD MAXIMlZE THE USE OF CURRENT LICENSING BASIS AND EXISTING PROGRAMS 1
o COST TO OPERATE DURING THE RENEWAL PERIOD l
SHOULD BE AT OR BELOW THE EXISTING COST OF OPERATION l
1 l
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UFE CYCL.E MANAGEMENT UCENSE RENEWAL PROGRAM OVERVIEW WESTINGHOUSE OWNERS GROUP i
t i
i A voluntary organization comprised of representatives from Westinghouse and each utility that owns a 4
Westinghouse designed nuclear steam supply system 24 United States utilities 8 International utilities j
l Westinghouse The WOG mission is to achieve mutual benefit, both j
l technical and financial through joint licensing and j
nuclear plant operations programs 1
Westinghouse Owners Group Management Structure j
Executive Advisory Committee provides j
guidance on philosophy, direction and budget j
considerations Steering Committee is the governing body
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i that establishes policy, direction and j
expenditure controls l
Subcommittee and working groups address
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current programs, development of proposed programs l
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l UFE CYCLE MANAGEMENT U
UCENSE RENEWAL PROGRAM 1
PROGRAM OVERVIEW LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM o
ENDORSED BY WOG EXECUTIVE ADVISORY COMMITTEE
- JAN 26 l
o PROGRAM AUTHORIZED AT WOG - FEB 11-14 GENERAL l
SESSION l
o
$8.74 MILLION PROGRAM i
o 5 YEAR DURATION o
BASIC OBJECTIVES o
ASSIST PLANTS WITH LIFE CYCLE MANAGEMENT l
o RECOGNIZE AND UTILIZE MAINTENANCE RULE ACTIVITIES WHICH ARE SIMILAR TO LICENSE RENEWAL RULE REQUIREMENTS o
DEVELOP A COST-EFFECTIVE APPROACH TO LICENSE RENEWAL i
l UPE CYCLE MANAGEMENT e
UCENSE MENEWAL PROGRAM
]
WOG STRATEGY FOR LICENSE RENEWAL 1
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DEVELOP A COST EFFECTIVE APPROACH TO LICENSE I
RENEWAL Establish a consistent approach to License l
)
Renewal for WOG plants j
l Work with NUMARC to resolve policy issues j
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Work with industry to develop common 1
methods and integrate activities i
RESOLVE TECHNICAL ISSUES ON A GENERIC BASIS Develop Generic Processes l
Integrated Plant Assessment (IPA) l l
Screening Criteria / Process
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b Develop Bounding Technical Reports i
For all WOG or a group of WOG plants Obtain SERs on these reports
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Reference technical reports in plant specific license renewal applications I
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UFE CYCLE MANAGEMENT w
UCENSE RENEWAL PROGRAM PROGRAM OBJECTIVES Take advantage of previous and ongoing industry work, including NPAR, NUMARC/NUPLEX for application to Life Cycle Management concerns-Maintenance Rule Compliance O&M Cost Reduction j
Plant Economic Viability l
Establish consistent approach to License Renewal for WOG Plants Reduce License Renewal Cost for individual Plants:
Resolve Technical issues on Generic Basis Use EPRl/ DOE funding where possible Work with NUMARC to integrate License Rule / Maintenance Rule and resolve other policy issues Obtain NRd acceptance of Generic Work, i.e.,
Technical Reports Reduces Resource Requirements Resolves W issues on generic basis Establish an Aging Management information System to support WOG Life Cycle Management / License Renewal efforts
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UI L CYCLE MANA(El MI HI WMWWW A tw
- 859 M sr UCf NSE HENt WAL PFtOGHAM MANAGEMENT STRUCTURE WOG LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM i
WOG EXECUllVE ADVISORY COMMITTEE NftC COMMI$SiONE 11S POLICY MANAGEMtNI NUMAflC ISSUES WOG StEEM POL 8CY OGo, EPftl, DOE, C N 48IEE ISSUES UlitillES VENDOHS WOG ECM i LR WORMING GROUP HilC COHE GROUP WOG SUSCOMMITIEES
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- CHAND E PROGHAM 11 CitNGC AL e ANAtySIS
- VICE-CHAIR MANAGEH ISSUES 4
e LICENSING
- AHIG COOR.
- MAIERIALS INPUg
- OTHEM Ulltif y g Priogngu
- OPEHAllONS MEM9ERS COOllDINATOR e SVSIEMS & EOUDPMENI ENGINEEfilNG OTHER WOflMING GHOUP Ullt11Y Mt MHillS 6
- LCMIt H PHOGHAM e Pt ANI GROUPS e IMPLEMENilNG PL ANIS i
1 l
UFE CYCLE MANAGEMENT UCENSE RENEWAL PROGRAM 4
i PROGRAM PLAN WOG LCM /LR Program Plan, Revision 0 completed in July,1993 Program Plan Contents Overview of WOG LCM /LR Program i
Program Description Scope of Work IPA Technical Reports Integration Activities Aging Management Information System Operating Policy and Guidelines Program Management, Control and Communications Living Document
UFE CYCLE h&ANAGEMENT j
j UCENSE RENEWAL PROGRAM i
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l GENERIC TECHNICAL REPORTS i
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Group 1 Start End
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RHR System 7/93 3/94 j
Motor Operated Vr'ves i
Heat Exchangers/ Tanks l
RV Supports /RCS Supports i
Group 2 1/94 9/94 4
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Group 3 7/94 3/95 Group 4 1/95 9/95 l
Group 5 7/95 3/96 i
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l Group 6 1/96 9/96 l
Group 7 7/96 3/97
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Group 8 1/97 9/97 i
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UFE CYC1.2 AGEMENT
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1 INTEGRATED PLANT ASSESSMENT PROCESS 1
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The WOG IPA is intentionally being developed
. to be identical to the IPA Process being establ.ished via NUMARC industry activities i
The balance of the WOG IPA process is being l
developed and is expected to be submitted to the NRC in the Fall of 1993 with the intent of obtaining a Safety Evaluation Report i
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Significant reliance on previously approved Technical Reports l
UFE CrCLE MANAGEWENT uemie awewn enoonAu INDUSTRY INTERACTIONS The WOG LCM /LR Program is represented and participating on the NUMARC License Renewal Implementation AHAC and Executive AHAC i
4 The WOG LCM /LR Working Group is interacting with all organizations that had or do have active License Renewal Programs B&W Owners Group GLRP BWR Owners Group i
Northern States Power /Monticello Yankee-Rowe-CE - NSSS Utilities i
Do not have a generic License Renewal j
l Program Several utilities are not able to benefit I
directly from generic activities
)
WOG/W is inviting CE-NSSS utilities to join the WOG LCM /LR program to provide l
opportunity to benefit from active participation by all nuclear utilities in License Renewal activities
f UFE CYCLE lAANAGEMENT i
UCENSE RENEWAL PROGRAM FUTURE INTERACTIONS WITH THE NRC WOG IPA Process anticipated to be submitted for NRC SER in October,1993 WOG IPA Screening Process anticipated to be submitted for NRC SER in late November,1993 1
l Technical report standard format and content l
anticipated to be defined (consistent with other I
industry participants) by October,1993 l
Initial technical report submittals for SERs anticipated in March,1994 Subsequent technical report submittals through 1997 NRC fee waiver discussion l
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l LIFE CYCLE MANAGEMENT A tk EEEE i
RENX N rr l
LICENSE RENEWAL PROGRAM
'I PROGRAM PLAN Rev.0 i
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July 1993 i
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WESTINGHOUSE OWNERS GROUP LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM EXECURVE
SUMMARY
a in February,1993, the Westinghouse Owners Group (WOG) authorized the Life Cycle Management / License Renewal Program to resolve the following issues and concems:
o Management of Aging o
Establishment of a consistent approach to license renewal l
o Reduction of the cost of license renewal o
integration of similar activities with the Maintenance Rule o
Participation in activities with other industry organizations Program direction is vested in the LCM /LR Working Group, comprised of representatives from all WOG members.
A major effort of the Program is the preparation of Generic Technical Repc ts documenting effective life cycle management techniques for those plant systems and components (treated as commodity groups) considered important to license renewal. These Technical Reports are prepared as non-proprietary WCAPs and submitted to the NRC for review and approval. The Reports guide member utilities in their efforts at managing aging in important plant components, while providing a document to be referenced in their plant-specific license renewal applications. A two-part database effort supports the Technical Report process: First, plant environmental and equipment information from all WOG plants is used to determine plausible aging mechanisms on a bounding basis. Second, a collection of current applicable industry information on aging mechanisms and effective maintenance programs supports the i
life cycle management recommendations.
Significant participation in industry activities related to interpretation and implementation of the license renewal rule (10CFR54) assures that the WOG interests are addressed.
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WESTINGHOUSE OWNERS GROUP l
LIFE CYCLE MANAGEMENT / LICENSE RENEWAL PROGRAM l
PROGRAM PLAN t
Rev.O July 1993 t
7///Y2 APPROVED:
R. A. Newton, Chairrnan, LCM /LR Working Group Date APPROVED:
2 8. b d 74 /t 3 T. A. Meyer, Westing (ouse Prograrn Manager Date i
LCM /LR Rev. 0 1
July 1993
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WOG LCM /LR PROGRAM PLAN s
1 TABLE OF CONTENTS 1.
I NTR O D U CTIO N................................................
4 1.1 PROGRAM 4
i 1.2 ORGANIZATION OF THIS PLAN...............................
4 1.3 OVERVIEW OF THE LCM / LR PROGRAM.......................
5 1.3.1 INDUSTRY ACTIVITIES................................
5 j
1.3.2 PROJECT AUTHORIZATION............................
6 1.3.3 EP RI P ROPOSAL....................................
6 1.0.4 WORKIN G GROU P...................................
6 2.
PROGRAF A DESCRIPTION........................................
7 j
2.1 COPE OF WORK 8
2.1.1 TASK 1, PROGRAM MANAGEMENT......................
8 2.1.2 TASK 2, EPRI PROPOSAL DEVELOPMENT.................
9 i
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2.1.3 TASK 3, GENERIC TECHNICAL REPORTS.................
9 2.1.4 TASK 4, EPRI PROGRAM EXECUTION.................... 13 i
2.1.5 TASK 5, PLANT GROUPINGS AND TECHNICAL REPORTS....
15 2.1.6 TASK 6, GENERIC LCM /LR IMPLEMENTATION PLAN........
16 l
2.1.7 TASK 7, IMPLEMENTING PLANT IDENTIFICATION........... 17 2.1.8 TASK 8, LIFE CYCLE MANAGEMENT / MAINTENANCE RULE i
INTEGRATION....................................... ' 18 2.1.9 TASK 9, AGING MANAGEMENT INFORMATION SYSTEM.....
19 i
l 22 OPERATING POLICY AND GUIDELINES........................
22 i
l 2.2.1 SYSTEM TECHNICAL REPORT PROCEDURE..............
22 l
2.2.2 COMPONENT TECHNICAL REPORT PROCEDURE..........
22 2.2.3 SYSTEM AND STRUCTURE SCREENING PROCEDURE......
22 i
2.2.4 COMPONENT SCREENING PROCEDURE................
23 2.2.5 INFORMATION MANAGEMENT PROCEDURE...............
23 2.2.6 ACTION ITEMS PROCEDURE..........................
23 2.2.7 TECHNICAL REPORTS WRITERS GUIDES................
23 2.2.8 USE OF REFERENCE PLANT DESCRIPTIONS..............
23 2.3 S C H E D ULE AND COSTS....................................
23 2.3.1 DETAILED TAS K SCHEDULE...........................
24 2.3.2 PF.OGRAM COST ESTIMATES.........................
29 2.3.3 MAJOR MILESTON ES...............................
30 3.
PROGRAM MANAGEMENT....................................... 32 3.1 WOG MANAGEMENT STRUCTURE FOR LCM /LR PROGRAM........
32 3.2 LCM /LR WORKING GROUP.................................
32 3.3 WESTINGHOUSE INTERNAL MANAGEMENT STRUCTURE.........
33 1
LCM /LR Rev. 0 2
July 1993 i
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i 4.
PROGRAM CONTROL'..........................................
34 4.1 CONTROL OF THE PROGRAM PLAN........................
34
.l 4.2 TRACKING OF SCHEDULE, COST, TASK PERCENT COMPLETION...
35-i 4.3 STATUS REPORT DESCRIPTION, FREQUENCY & DISTRIBUTION....
35 t
5.
PROGRAM COMMUNICATIONS...................................
35 5.1 ROSTER OF WORKING GROUP MEMBERS.....................
35 5.2 MEETINGS, FREQUENCY & ATTENDANCE.....................
35 5.3 REPORTING TO STEERING COMMITTEE, SUBCOMMITTEES........ - 36 l
5.4 IN D U STRY h'TER ACTION S.................................
3 6 APPENDIX A.
REFERENCE PLANT DESCRIPTION.....................
37 APPENDIX B.
GLOSSARY........................................
46 APPENDIX C.
LIST OF ACRONYMS.................................
55 i
APPENDIX D.
REVISION RECORD.... -.............................
58 i
APPENDIX E.
B IB LIOG RAP HY.....................................
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LCM /LR Rev. 0 3
July 1993
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1 INTRODUCTION l
1.1 PROGRAM GOALS j
Given the rapidly growing interest in, and need for, Life Cycle Management and License
[
Renewal, this Program has been developed for the WOG to enable it to:
exert a leadership role in the industry in these areas, j
assure that its member utilities' interests are reflected in all industry initiatives, and l
l provide a means to integrate LCM (Life Cycle Management), Maintenance Rule and l
License Renewal requirements to tne technical and economic benefit of WOG members.
i The Program is intended to provide benefits to utilities who currently or expect to pursue license renewal in the future as well as to provide benefits to all plants, including the newer plants, by providing aging management and life cycle benefits.
1.2 ORGdNIZATION OF THIS PLAN This Program Plan is divided into five major sections.
The first section provides an overview of the program up to the time when this program plan was developed.
l The second section provides a detailed description of the program tasks to be performed, describes the policies and procedures under which the tasks will be performed, md presents a detailed schedule completion of major tasks and subtasks.
i The third section describes the management structure for both the WOG and Westinghouse i
and defines the responsibilities and relationships of the different parties.
The fourth section describes the mechanisms for financial, cost, and technical management of the program, including the types of reports to be developed to document progress, their frequency, and their distribution.
The fifth section describes the communications utilized to execute this program, including phone, fax, meetings, status reports to the WOG, and industry interactions.
An appendix provides a description of a composite reference plant which will be used to develop test cases and examples for the methodologies evolved under this program.
LCWLR Rev. 0 4
July 1993
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1.3 OVERVIEW OF THE LCM / LR PROGRAM Starting with its inception, the WOG LCM /LR Program has differed in many respects from I
previous WOG programs. Initially motivated by industry concems for the license renewal process, endorsed by the Executive Advisory Committee, and then approved as a multi-year, multi-million dollar program, the Program included a specific task to clarify both scope and cost. The following overview sections describe the major activities leading up to the development of this Program Plan.
r 1.3.1 INDUSTRY ACTIVITIES By the end of 1992, interest in Life Cycle Management / License Renewal and related activities within the industry had increased significantly as illustrated by the following events:
o The initiation of the B&W Owners Group Program on License Renewal and its active interaction with NRC in developing / resolving policy issues for the industry, o
The active interest in license renewal of individual utilities such as the Calvert Cliffs
- plant, o
Active industry support funded by utilities through EPRI involving LCM /LR program i
development, o
The establishment of a growing NRC staff to address License Renewal, whose costs are likely to be distributed to all utilities, including WOG plants, o
The growing realization that as nuclear plants near mid-life of their current license it is becoming increasingly difficult to justify their economic viability because of the decreasing remejning licensed life, o
The current and growing need for aging management to support economic as well as f
safety concems that might also support future license renewal requirements, o
The need to comply with the Maintenance Rule over the next 3 to 4 years, with this compliance expected to directly support license reriewal requirements, o
The funding of license renewal activities by EPRI in their Request for Proposal RFP 3075-7, o
The potential for other industry financial support for aging management / license renewal activities such as DOE.
o Utility initiatives focused through NUMARC to maintain / improve nuclear plant cost competitiveness and achieve maximum utilization of the facilities useful life.
LCM /LR Rev. 0 5
July 1993
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)j 1.3.2 PROJECT AUTHORIZATION
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The Project Authorization was developed over a relatively short period of time to enable the i
WOG members to participate in the industry activities and obtain the benefits summarized l
above through approval of an overall program. Given the short period available to develop l
this program, future changes were anticipated. In order for the WOG to define and control i
such changes, the development of this Program Plan was included as a specific program task.
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The program objectives of the Project Authorization are as follows:
Take advantage of previous and ongoing industry work on aging management (NPAR) o and the lead plant program (NUMARC/NUPLEX) for application to aging management concems including:
o Maintenance Rule compliance, o
O&M cost reductions, and '
i o
economic viability of nuclear plants including LCM i
o identification / mitigation of operational risks and uncertainties o
Reduce the cost of license renewal for individual utilities by:
I o
Resolving technical issues on a generic basis I
o Using EPRl/ DOE funding wherever possible to minimize program cost
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o Working with NUMARC to integrate License Rule / Maintenan::e Rule and to l
resolve other policy issues.
Establish a consistent approach to license renewal for WOG plants -
I o
Establish an Aging Management Information System to support WOG aging -
o management and license renewal efforts.
Take advantage of the premise that NRC acceptance of generic work is more likely o
since it reduces their resource requirements, resolves Westinghouse issues on a generic basis, and promotes a more stable, predictable licensing environment.
1.3.3 EPRIPROPOSAL On December 11,1992, EPRI issued a Request for Proposal, RFP3075-7
- License Renewal Technical Demonstration Plants - Resolution of Generic PWR License Renewal issues." The stated objective of this program is to
- resolve key license renewal technical issues on a generic basis for Westinghouse, Combustion-Engineering and Babcock & Wilcox units.* Task i
2 in the Project Authr'rization included the effort to respond to the RFP on behalf of the WOG and to obtain EPRI financial support for a portion of the work scope anticipated for this WOG LCM / LR program.
I 1.3.4 WORKING GROUP l
As part of the Program Management organization proposed in the Project Authorization, a Working Group was defined, made up of utility members, which would direct and control all I
work performed in support of the Program. Figure 2-1 illustrates the management structure LCM /LR Rev. 0 6
July 1993
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Figure 2-1 WOG LCM /LR PROGRAM MANAGEMENT STRUCTURE PROPOSED IN THE PROJECT AUTHORIZATION WOG Fraam e Advisory v
N D W ARC Pohev issues WOG Steering Pohev OGs, EPft, DOE, Comdignee issues UIBhos Vendors i
WOG Subcommieses
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o Analyons WOG Mh*
o Uconsang hM
-[mw 3
o Motonels
- 'D D cameus=
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o Operemons e pueny chairmen o Systems & Equipment o LewLA Program Engsnoonng
- Plant Groupe e implerneneng Planes I
o Ad Hoc Techn6eal Groups input proposed in the Project Authorization for the Program, including the initial definition of the Working Group.
2.
PROGRAM DESCRIPTION l
The following sections describe the tasks to be performed in this Program to accomplish the l
program objectives given in Section 1.3.2.
A basic premise of this program is that the work will be performed on a " bounding technical analysis' basis. It is the intent of the following work scope to address, via
- bounding technical analyses," only those issues that are common to all WOG plants or defined categories or groups of WOG plants. The resulting Generic Technical Reports will address LCM, the l
LCM /LR Rev. 0 7
July 1993 1
L maintenance rule, and license renewal, and will be designed to be used to establish a firm technical basis to implement aging management / life cyc!e management programs, and to be referenced by individuel licensees as part of their plant specific License Renewal Applications.
Efforts that are clearly plant specific or apply to a plant specific License Renewal Application are not part of this WOG program.
t 2.1 SCOPE OF WORK The original scope of work presented in the Project Authorization was acknowledged to be limited in detail. This section provides expanded detail for each of the nine tasks to clarity the nature of the work to be performed, deliverables, schedules and costs.
2.1.1 TASK 1, PROGRAM MANAGEMENT The initial program task requires development of a Program Plan which describes how the Program will be managed, controlled and coordinated with NUMARC and other related industry activities. While the initial Program plan, scope and costs were defined in the Project Authorization to facilitate approval and implementation of the Program as soon as possib!e for 1
the benefit of the WOG some of the detailed scope and corresponding costs remained to be clarified.
i The Program Plan documents utility and Westinghouse program management structure, the program control procedures, the WOG utility interfaces and the means by which this program will coordinate its efforts with other industry programs and groups such as the B&W Owner's Group Generic License Renewal Program and NUMARC. The Plan explicitly considers and supports periodic meetings with both NRC and NUMARC.
2.1.1.1 Detailed Scoping / Cost Estimates The Program Plan defines the number of technical reports to be developed, and from this derives a more accurate cost estimate for the entire program. The Plan allows for scope and schedule adjustments to control the cost to the WOG in any particular year.
2.1.1.2 Schedule The Program Plan provides a schedule for initiation and completion of all of the detailed tasks defined as part of this program. The tool used to develop the schedule has sufficient flexibility to permit frequent schedule adjustments and to test different schedular assumptions (e.g., the time required to complete NRC review / approval of a technical report).
2.1.1.3 Process Development The Program Plan includes the development of needed guidelines and tools to facilitate the completion of subsequent LCM. maintenance rule, and LR tasks. These " process aids" will be used subsequently to standardize work efforts performed by different functional groups over an extended period.
l 1
LCM /LR Rev. 0 8
July 1993 1
2.1.1.4 Quality Assurance (QA)
The Program Plan defines the necessary OA procedures to be followed to assure the technical accuracy and consistency of the documents produced by this Program. All work performed in this Program will meet the Westinghouse WCAP-8370 Quality Assurance Requirement.
2.1.2 TASK 2, EPRI PROPOSAL DEVELOPMENT 2.1.2.1 issue Proposal This Task includes the effort to respond to the RFP on behalf of the WOG in order to obtain EPRI financial support for a portion of the work scope in the WOG LCM / LR program. This Task has been completed with the submittal of a completed proposal to EPRI on March 12, 1993.
2.1.2.2 Oral Presentation EPRI requested an oral presentation of the proposal to their LCM committee members. This presentation was made as requested on March 30,1993.
2.1.2.3 Contract Negotiation This stage of Task 2 will define the exact scope and terms & conditions of the contract.
2.1.3 TASK 3, GENERIC TECHNICAL REPORTS Three types of generic technican reports are considered: system, commodity, and major component. The process for preparation of the reports is the same and is graphically illustrated in Figure 2-2. There are the following five phases to the preparation of topical reports:
1.
The project startup phase which includes the development of system boundaries, commodity groupings, data surveys, report contents, unique issues and available information. The deliverables are boundary and group definitions and the report table of contents.
2.
The program and aging basis review phase which includes gatnering industry experience, data survey results, function identification, plausible age-related degradation mechanisms (ARDM), performance criteria, and component ARDM matrices. The deliverables are ARDM matrices and adequate program checklists.
3.
The effective program and attemative evaluation phase which includes applicability of programs to specific ARDMs, technical justification and documentation, economic analyses of attematives, and potential modifications and one time actions. The deliverables are effective program reports and altemative analysis.
LCM /LR Rev. 0 9
July 1993 l
1
i l
Figure 2-2 TECHNICAL REPORTS PROCESS 1.0 PROJECT STARTUP 1.1 Project Kickoff 1.2 Define System Boundaries, Commodity Groups 1.3 Report Workshop on Boundaries / Groups, Report Contents, Unique issues and Existing Efforts (Bibliography) 1.4 Data Survey Deliverables:
Boundary / Group Definition, Report T.O.C.
2.0 ADEQUATE PROGRAM AND AGING DASIS REVIEW 2.1 Screen & Index Data per Gurvey results, industry experience 2.2 Review Adequate Programs for Function / Function Degradation, Performance Crrteria 2.3 Aging Analysis of Plausible ARDMs. any unique characteristics 2.4 System / Commodity Report Cross Reference Deliverables:
ARDM Matrix, Adequate Program Checklist 3.0 EFFECTIVE PROGRAMS & ALTERNATIVES EVALUATIONS 3.1 AHTG Meeting (no.1) 3.2 Effective Program Review for Applicability, Requirements, Economics, Technical Justification 3.3 Review of Attematives: Analysis, Modifications, One-Time Actions Deliverables:
Effective Programs Report, Attematives Summary 4.0 VALIDATION AND REVIEW 4.1 Assemble Technical Report Contents 4.2 Technical Group Working Meeting (no. 2) 4.3 Technical Editing 4.4 WOG Review (AHTG, Core Group, Working Group) 4.5 AHTG Meeting to Resolve Comments, Prepare Draft (no. 3)
Deliverable:
Draft WCAP 5.0 ISSUE DRAFT REPORT 5.1 Industry Review 5.2 AHTG Working Meeting to Resolve Comments, Prepare Final Copy (no. 4) 5.3 EPRI information Syctem inputs 5.4 issue WCAP Deliverable:
Final WCAP for NRC Submittal I
i i
)
LCM /LR Rev. 0 10 July 1993 i
]
4.
The validation and review phase which includes assembling the topical report, technical editing, WOG review, comment resolution and draft report production. The deliverable is a draft report.
l 5.
The final report phase includes industry review, comment resolution, final production editing and issuance of the report. The deliverable is a final report.
s 2.1.3.1 System Technical Reports Format and Content The format and content of a system technical report is graphically shown in Figure 2-3 and has the following seven sections:
==
Introduction:==
Provide a brief description of the system to distinguish it from other systems; set the mechanical, electrical, and I&C boundaries to provide the cutoff from one system to another; identify the comprment types to standardize on the level of breakdown of components.
System Function: Develop the system functions using Current Licensing Basis (CLB) information and a function tree format; provide the functions of the system for each FSAR t
accident analysis; identify any functions provided in the Technical Specifications or docketed in correspondence with the NRC for ATWS, Appendix R, Blackout, and PTS.
Component Function: Establish a generic component function matrix for each component type to standardize functions for components from one system to another; identify the components and their functions associated with each system function.
License Renewal Rule / Maintenance Rule Screen: Identify each system functions covered by either the license renewal rule (LR) or maintenance rule (MR); identify the components and their functions associated with 'he LR or MR.
r Component Aoino Evaluations: Provide direction on where the components will be evaluated for ARDMs; assign components as commodities, major components or system unique components; separate topical reports will be prepared for commodities and major components; evaluate ARDM for system unique components in System Topical Reports. For EPRI system topical reports, the reports will also contain aging mechanisms and effective aging management evaluations for the system commodity and major components.
Commodity and Maior Component Data Collection; Prepare surveys to representative Westinghouse plants to obtain environments, materials, and stressors for commodities and major components; compile the replies into databases with ranges for each parameter; use the bounding value (high or low) for the range to evaluate ARDMs; also solicit listings of existing maintenance programs for the system compoPents from representative Westinghouse
{
plants; provide the databases and existing programs for use in writing commodity and major component topical reports.
l System Unioue Component Evaluations: Evaluate system unique components in the System Topica! Report using expert system methodology to facilitate the large number of evaluations; I
compile the environraent, materials and stressors into a database, prepare a LCM /LR Rev. 0 11 July 1993
l i
l Figure 2-3 i
SYSTEM TECHNICAL REPORT PROCESS DIAGRAM i
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System i
Functions CLB j
Component
~ Functions 1P i
LR4AR/IPP Screen
-i Commodity Major -
System Unique 5
Groups Components.
Components i
i-Environment E
Materials Component /
t Stressors ARDM Matrix i'
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Existing Effective I
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LCfNLR Rev. 0 12 July 1993 -
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1
component /ARDM matrix, evaluate the ARDMs against existing maintenance programs, document results and recommend actions if modifications to programs or new programs are required to manage ARDMs.
2.1.3.2 Commodity Group Technical Reports Format and Content The format and content of commodity group technical reports is graphically shown in Figure 2-4 and has the following five sections:
l
==
Introduction:==
Provide a description of the component types included within the commodity group, the generic functions of the component types, and the system-specific component functions.
Proaram Identification: Prepare surveys to representative Westinghouse plants to obtain environments, materials, and stressors for commodity, compile survey results into databases with ranges for each parameter, and collect listings of existing maintenance programs.
Aoino Evaluation: Evaluate commodity components using expert system methodology to facilitate the large number of evaluations; use the bounding value (high or low) values from the databases for evaluation of ARDMs, and prepare a commodity ARDM matrix.
Effective Procram Review: Evaluate the identified ARDMs against exist;ng programs, assure programs have written acceptance criteria and action items if the criteria are not met, and justify and document results.
Attemative Considerations: Provide alternative considerations for effective management of ARDMs by one-time action such as inspection, analytical analysis or potential modifications and redesigns.
2.1.3.3 Major Component Technical Reports Format and Content (Later) 2.1.3.4 Submittals to NF,C All Generic Technical Reports will be developed as non-proprietary WCAPs and submitted for NRC review and approval, either via a Safety Evaluation Report (SER) or equivalent.
2.1.4 TASK 4 EPRI PROGRAM EXECUTION l
The final EPRI program will be a subset of the WOG Program - Task 3, and will consist of the preparation, submittal, and defense of 5 generic technical reports.
In the context of this EPRI RFP, Westinghouse has implemented a teaming arrangement with Gilbert / Commonwealth, Inc. of Reading, Pennsylvania, and Yankee Atomic Electric Company of Bolton, Massachusetts, to jointly work toward the resolution of technicalissues for Westinghouse PWR plants. Gilbert / Commonwealth has previous experience in the overall planning of license renewal strategies, while Yankee Atomic was responsible for the lead plant LCM /LR Rev. 0 13 July 1993 l
t
1 1
1 Figure 2-4 i
COMMODITY TECHNICAL REPORT PROCESS i
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Group / Subgroup Commodity Requirements l
Definition Critical Functions i
l Function / Function Degradation Prograrn Performance Critena identitication l
i Corrective Action i
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Environmental Aging Materials i
Evaluation I
-- Stressors j
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t Effective inspection, Monitoring, Performance Req j
l Acceptance Criteria & Basis j
Program
=
Review Corrective Actions l
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qt One Time Action Attemative Anal sis
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Y Considerations Modification / Redesign i
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I LCM /LR Rev. 0 14 July 1993 l
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activities at the Yankee Rowe plant, and thus bring that expertise to the p.oject. Key technical issues important to license renewal which need to be addressed have been previously identified by several documented studies. These can be grouped into the hardware categories of systems, structures, and components, (SSC) or technical issues. While many of these issues are generic across (effectively) all plants in the domestic nuclear industry, certain ones are specific to the Westinghouse design, but fairly generic across the WOG plants.
Because of the large number of plants included in the WOG, these latter items are considered to be the most amenable to resolution using the support of the EPRI License Renewal Program.
2.1.5 TASK 5, PLANT GROUPINGS AND TECHNICAc REPORTS l
For the WOG LCM /LR generic evaluations a standardized approach to identification of systems, structures, components, and their functions has been developed. After system boundaries and commodity grouping have been agreed upon for each technical report, plant l
groupings and bounding evaluations will be used to perform the evaluations. The groupings l
and bounding analysis will allow the most coverage of plants with each technical report.
l 2.1.5.1 System and Structure identification I
l The generic plant systems and structures will be based on the NPRDS system and structure l
nomenclature and component types. The NPRDS norrenclature and comptinent types is used i
by all WOG plants and will easily allow individual plants to compare their equivkent system or structure to the generic system or structure.
2.1.5.2 Functional Grouping Generic system and structure functions wll be obtained by using a base line FSAR accident analyses (such as for a 2-loop plant) and checking the resulting design basis event functions with other plant types to assure that important generic functions are not missed. In the same manner base line technical specifications, ATWS, Appendix R, LCOs, etc. will be selected and checked to assure that all generic important system and structure functions are identified. A generic function tree approach will be used to develop the functions. This approach is simple to underste7d and can be easily used by individual plants to identify plant-specific functions.
2.1.5.3 Common Groupings The evaluations of systems, structures and components will be made by grouping plants with common structures, systems, functions and components. An example of a structural groupings would be dry versus wet containments. An example of a system groupings would be high head safety injection systems versus low head safety injection systems. An example of a component groupings would be B31.1 piping versus Section ill piping.
l 2.1.5.4 Bounding Analysis The technical evaluation of the applicable aging mechanisms for components would usa a bounding approach. The stressors, environments, and materials of fabrication for the components will be surveyed and the bounding (either high or low) values for parameters LCM /LR Rev. 0 15 July 1993 l
effecting the mechanism will be used to determine if the mechanism exists. Plant-specific application would then be made by assuring its parameter valuE S were within the bounds of the generic analysis.
2.1.6 TASK 6, GENERIC LCM /LR IMPLEMENTATION PLAN This task will develop a life cycle / license renewal plan intended for use by all participating WOG plants, that will provide the most cost effective life cycle process, including guidance in the preparation of a license renewal application.
The plan is intended to:
o Provid guidance and implementation methods relative to the process for the preparation and submittal of a license renewal application to the NRC o
Discuss the level of corporate commdment required for a life cycle process in terms of overall objectives and resource requirements o
identify and discuss strategies to resolve applicable technical issues and integrate otner industry efforts such as maintenance rule compliance when applicable.
The goal of the WOG life cycle / license renewal plan is to provide the option for early license renewal and provide economic flexibility for long range strategic planning. The plan will emphasize tasks that preserve the license renewal option and enhance the ability to cost effectively operate the plant during its existing license period.
An initial plan will be developed early in the WOG LCM /LR Program based on a composite of industry experience and WOG initiatives. Later in the program, this Life Cycle / License Renewal Plan will be updated and revised consistent with the technical and policy actions that occur during the implementation of the overall LCM /LR Program. This will enable an initial document to be developed and used to provide guidance during the implementation of the overall Program for the plant group documents and for any individual implementing plants.
This approach also assures that the final Life Cycle / License Renewal Plan will take advantage of the Program results and any interim industry actions that may impact the plan.
2.1.6.1 Program Justification and Feasibility Program goals are provided in terms of economic and technical feasibility. Other considerations typically required for the decision to proceed with a program are identified.
Generic economic considercions will be identified and in " de license renewal costs and costs of replacement power. After incorporation of utility specifics, these considerations can i
be used as one of the inputs to assess the viability of pursuing a life cycle program.
2.1.6.2 Implementation Logic / Methods Process logic for tasks associated with the Integrated Plant Assessment will be defined using structured process analysis techniques. Process logic will identity technical / functional requirements, information management considerations, and integration of other applicable LCM /LR Rev. 0 16 July 1993
near term requirements such as the Maintenance Rule. Administrative and technical procedure considerations are defined.
2.1.6.3 Project Management Details Major tasks required to submit, review, and approve a license renewal application will be defined using a detailed work breakdown structure (WBS). Generic schedule and resource (manpower) for each major task will be identified. A cost range process will be identified for evaluating uncertainty factors that can impact the base resource estimate. Major tasks to be addressed include:
o Integrated Plant Assessment o
- FSAR Supplement
- EnvironmentalImpact
- Revised Technical Specifications o
information Management o
implementatbn Planning o
Major Component & Issues Engineering 2.1.6.4 Life Cycle Strategies Strategies to combine WOG Program deliverables and EPRI License Renewal initiatives into a total life cycle program will be identified. This section will also identify integration of applicable industry issues. Integration strategies for WOG deliverables and industry issues will identify technical and financial impacts where appropriate.
2.1.6.5 Program Plan Revision The life cycle program plan will be developed early in the WOG LCM /LR Program based on information currently available for the technical and policy areas identified above. Later in the program, the ' ife Cycle Plan will be updated and revised consistent with the technical and policy actions that occurred during the implementation of this program. Incorporation of one revision cycle will assure that the program incorporates WOG lessons learr..:~' and takes advantage of appropriate industry initiatives such as the EPRI demonstration program.
2.1.7 TASK 7, IMPLEMENTING PLANT IDENTIFICATION One or more implementing plants will be identified within each of the groupings resulting from Task 5. These plants will be identified on the basis of their own interest and ability to pursue license renewal and could be identified on the basis of an " unnamed" reference plant or a named reference plant.
Each of these plants will proceed to resolve plant-unique issues in their plant-specific License Renewal Applications. The costs associated with the plant-unique issues and any contribution l
to the plant-specific License Renewal Application (other than referenceable generic technical reports) are not included in this WOG Program but would be the responsibility of the individual plants. The WOG LCM /LR Program will support these implementing plants technically as well i
I I
LCM /LR Rev. 0 17 July 1993 i
as relative to regulatory policy decisions.
2.1.7.1 Develop implementation Schedule This task will also develop a schedule for all WOG plants showing the recommended starting times and potential schedule of activities required for preparing a License Renewal Application, based on the required effort and duration expected as a result of previous Program efforts, and the initial license date of each plant.
2.1.8 TASK 8, LIFE CYCLE MANAGEMENT / MAINTENANCE RULE INTEGRATION This task will take advantage of industry initiatives in this area and provide recommendations for implementation aimed at integrating the Maintenance Rule (10CFR50.65) and the License Renewal Rule (10CFR54). Life Cycle perspectives will be used to produce cost effective means to implement both rules and also derive O&M cost reductions and improved plant availability for WOG plants.
The equipment scope of both rules is basically similar with many components identified as "important" during the screening process for each rule. Plant O&M practices are the basis for implementing each rule. The license renewal rule requires identification of programs that will be " effective"in managing the effects of age related degradation. The maintenance rule is based on preventative maintenance activities and performance and condition monitoring activities. Note that pedormance monitoring and goal setting for maintenance rule implementation is performed at the system level and not at the individual component level.
Integration of maintanance rule considerations in the WOG program will be based on the following common activities:
2.1.8.1 Screening Because of the similarity in the " Scope" statements in the two rules, a single screening process will be developed to encompass both rules. This single process will allow individual utilities to screen separately for both rules, if desired.
2.1.8.2 Program Reviews Review and evaluation of plant O&M practices relevant to both rules will be coordinated.
WOG technical reports will be based on two levels of program reviews. Initial program reviews will be based on life cycle perspectives and identify maintenance activities that provide a high degree of confidence that equipment degradation is identified and corrected.
The second level of program reviews will identify those attributes required to satisfy the l
definition of an
- effective program for license renewal:
I Identifying and describing any effects of ARDUTLR Describing conditions or parameters used to establish acceptance criteria Proposing corrective actions if acceptance criteria are not met Identifying administrative controls for implementation LCM /LR Rev. 0 18 July 1993 i
~
2.1.8.3 industry interactions The WOG approach to maintenance rule integration will be performed in concert with NUMARC and through coordination with other industry groups. Life cycle perspectives are intended to provide a balance of corrective and preventative maintenance activities that can be employed to provide a high degree of confidence that equipment degradation is identified and corrected, that equipment life is optimized, and that the maintenance program is cost effective. Surveillance, inspection and testing activities assure that the equipment needed for safe and reliable operation will perform within required limits. Predictive maintenance monitoring and diagnostic techniques are used to plan maintenance prior to equipment failure.
Consideration is als6 given to attematives to unaintenanca cuch as eno time ana!ysis or modifications.
2.1.9 TASK 9, AGING MANAGEMENT INFORMATION SYSTEM A computerized Aging Management Information System (AMIS) will be developed to facilitate the collection, storage and manipulation of component, component characteristics and aging management information which will be generated as the WOG LCM /LR Program. AMIS will consist of two basic parts: active databases containing information from WOG plants plus other data necessary for aging degradation evaluations, and a passive, read-only library containing published industry information on aging management. To the extent possible, expert systems or other types of software will be used to screen, evaluate and document aging management results. All information accumulated during this task will be available for use by WOG members.
The initial phase of the database part of AMIS will deOlop the databases for component types and characteristics needed for aging management. Thew databases will be populated by replies to questionnaires from representative WOG plants. Tra cecond phase will develop tha expert systems needed to screen, evaluate and document the aging management results.
Figure 2-5 illustrates the expected relationship between the databases and an expert system.
]
Two types of databases are needed to determine applicable age related degradation mechanisms (ARDMs). Component type databases comain information specific to individual components and the component environmental databases are applicable to the broader areas of system chemistries, building locations, piping classifications and metal types.
2.1.9.1 Component Type Databases These databases store component-specific data:
Pipino Database This database contains information on specific piping and includes data on plant identification, l
number of RCS loops, applicable system, piping c!assification, building location, type of fluid, size, wa!! thickness, flow rate, pressure, temperature, insulation, and connection types.
I LCM /LR Rev. 0 19 July 1993
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Figure 2-5 EXPERT SYSTEM LINKS TO DATABASES m
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Valve Database I
This database contains information on specific valves and includes data on plant identification,-
number of RCS loops, valve unique number, valve type, applicable system, piping location, l
insulation, and connection types.
i Heat Exchancer Database l
This database contains information on specific heat exchangers and includes data on plant identification, number of RCS loops, heat exchanger unique number, applicable system, flow l
rates, pressure, temperature, insulation, and connection types.
Tank Database i
This database contains information on specific tanks and includes data on plant identification,-
(
number of RCS loops, tank unique number, applicable system, insulation, materials of i
construction and weld types.
l Pumo Database I
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l l
This database contains information on specific pumps and includes data on plant identification, number of RCS loops, pump unique number, applicable system, pump type, insulation, and connection types.
Miscellaneous Database 2
This database contains information on components which do not fit into the other component l
type databases and include plant identification, number of RCS loops, unique component number, component type, applicable system, insulation, and weld connections.
(
2.1.9.2 Component Environmental Databases I
These databases contain information on system chemistry, metal type, building location and pipe classification.
l System Chemistry Database l
This database contains the fluid type, we.er or steam, and the chemistry for each system or l
subsystem. The types of chemistry stored are chlorine, fluorine, ph, conductivity, etc.
I Metal Type Database This database contains the material constituents of the fabrication of the component and includes caton, chromium, iron, etc. (ASTM categories)
Buildino Database j
i i
This database stores the temperature and neutron exposure for locations within plant i
LCM /LR Rev. 0 21 July 1993
3
}
buildings.
l Pipe Classification Database This database stores the materials and pressure and temperature ratings for standard system valves, fittings and piping.
2.1.9.3 Aging Management Library
)
1 l
This part of AMIS is a read-only collection of significant published industry information relating to life-cycle and aging management. Documents are collected and scanned to obtain electronic images of the text and figures, and retrieval is facilitated by an extensive key-word capability.
J 2.2 OPERATING POLCf AND GUIDELINES This section contains the policies under which the program tasks will be executed, and also the guidelines to be used in executing those policies.
Policies and cjuidelines will be established in written procedures to standardize the generic I
l methodology for performance of WOG LCM /LR activities. The procedures will be of sufficient
[
detail to allow an experienced nuclear industry engineer to reproduce the results and to allow a plant-specific application of the methodology by either reference or reference with some modification to the generic topical reports. The following procedures will be developed as a
{
minimum:
2.2.1 SYSTEM TECHNICAL REPORT PROCEDURE This procedure provides guidance for a standardized format and content of system topical reports. It includes guidance on system functions, references, evaluation bases, degradation mechanisms, life cycle management, reviews, approvals, issuance and distribution, l
)
2.2.2 COMPONENT TECHNICAL REPORT PROCEDURE j
This procedure provides guidance for a standardized format and content of component topical reports. It includes the component types and functions, references, evaluation bases, degradation mechanisms, life cycle management, reviews, approvals, issuance and distribution.
22.3 SYSTEM AND STRUCTURE SCREENING PROCEDURE This procedure provides screening guidance to determine important to License Renewal Rule (ITLR), important to Maintenance Rule (ITMR) and important to power production (ITPP) plant systems and structures it includes boundary definitions, a reference plant list of systems and structures, function identification, component types, selection criteria, documentation, reviews, approvals, issuance and distribution.
LCM /LR Rev. 0 22 July 1993
I' I
2.2.4 COMPONENT SCREENING PROCEDURE This procedure provides screening guidance for components in ITLR, ITMR and/or ITPP systems or structures to determine which components are necessary for the system or I
structure to function, which components are subject to age-related degradation and which components have effective aging management programs, it includes component type generic functions, references, selection criteria, documentation, reviews, approvals, issuance and distribution.
2.2.5 INFORMATION MANAGEMENT PROCEDURE This procedure provides guidance for database development to ensure that information is accurately entered, stored, processed, maintained and reported. It includes the structure and i
format of each database, data standardization, database control and security, report generation, reviews, approvals, issuance and distribution.
I 2.2.6 ACTION ITEMS PROCEDURE This procedure provides guidance to ensure action items arising from WOG LCM /LR activities are identified, appropriately addressed and their status tracked. It includes a description of the action item, responsible person for generation and closecut, initiating document, l
scheduled closecut date, actual closecut date and documentation of closecut.
2.2.7 TECHNICAL REPORTS WRITERS GUIDES Separate Writers Guides will be developed to facilitate the consistent and thorough preparation of the Technical Reports as non-proprietary WCAPs. These Writers Guides will be integrated with the appropriate procedures described above.
i 2.2.8 USE OF REFERENCE PLANT DESCRIPTIONS An initial composite reference plant description h provided in Appendix A to facilitate demonstration and testing of procedures developed under this program. The lists of l
equipment, systems, and source documents can also be used as examples to illustrate l
technical reports and presentations. This reference plant description will be further modified as required to benefit WOG member utilities' use of the resulting program documents.
2.3 SCHEDULE AND COSTS This Program was approved by a majority vote at the February,1993 WOG General Session.
The duration of the Program wac described in the Project Authorization as 5 years.
Therefore, the Program as currently configured will be completed in February 1998.
An initial estimate of relative task durations was provided in the Project Authorization. This estimate is revised as part of this Program Plan to better define Task and sub-Task i
schedules, and to better determine the Program cost in individual years.
LCM /LR Rev. 0 23 July 1993
4 2.3.1 DETAILED TASK SCHEDULE A list of program milestones was provided in the initial Project Authorization, based on initial l
estimates of task duration and reflecting attempts to level costs. The first of these milestones, l
l submittal of the EPRI proposal, was completed on schedule. The second milestone, *lnitiate
[
l work on EPRI program," did not begin as scheduled because of delays on the part of EPRI in 1
issuing a contract.
t I
i Starting and completion dates for each of the major Program tasks following development of the Program Plan are shown in the following table. Tasks 3 and 5 involve the preparation of l
Technical Reports and submittal of those reports for NRC review and approval. These tasks involve significant uncertainty in the completion dates, and it is possible that some will occur l
later than the end of this Program, February 15,1998.
l SCHEDULE FOR MAJOR PROGRAM TASKS Task No.
Task Description Start Date End Date 1
Program Plan March 15,1993 June 1,1993 l
2.
EPRI Proposal February 15,1993 March 12,1993 3.
(21) Generic Technical Reports July 1,1993 July,1996 j
4.
EPRI Technical Reports July 1,1993 August,1994 5.
(13) Plant Groupings / Reports January 1.1996 February 15,1998 i
6.
Generic implementation Plan January 3,1994 December 30,1994 Update Generic Plan June 2,1997 December 31,1997 i
7.
Implementing Plants / Schedule January 1,1996 May 1,1996 8.
Integration June 1,1993 July 31,1995 9.
Aging Mgmt Information System June 1,1993 February 15,1998 The overall Program schedule is provided as Figure 2-6. To facilitate cost leveling, some of the major tasks have been divided into subtasks, and are identified as such on the schedule.
l Starting dates for the development of Generic Technical Reports are as follows. It is recognized that certain reports might be done with separate sections to reflect natural plant groupings (or as separate reports for the different groupings). Group 1 reports are expected i
to be partially funded by EPRI.
STARTING DATES FOR GENERIC TECHNICAL REPORTS Task Number & Topic Stad Date Group 1 July 1,1993 6110.05 RHR System 6110.06 Check Valves 6110.07 Motor Operated Valves 6110.08 Heat Exchangers/ Tanks 6110.09 RV Supports /RCS Supports LCM /LR Rev. 0 24 July 1993
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Figure 2-6 LCM /LR PROGRAM SCHEDULE i
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4 STARTING DATES FOR GENERIC TECHNICAL REPORTS (CONT)
Task Number & Topic Start Date
~
Group 2 January. 3,1994 ~
f 6110.10 Rx Pressure Vessel l
6110.11 Pumps 6110.12 Safety Valves 6110.13 AFW System Group 3 July 1,1994 6110.14 RV Intemals 6110.15 Pressurizer 6110.16 Motors
'l 6110.17 Cables
-i Group 4 January 2,1995 l
6110.18 EDG 6110.19 Class 1 Structures 6110.20 Batteries l
6110.21 CCW System r
Group 5 July 3,1995 l
6110.22 RCS Piping 6110.23 Nuclear instrumentation
]
6110.24 Non-Nuclear instrumentation 6110.25 CVCS i
6105.01 4 Reports performed January 1,1996 l
as " groupings" 6105.02 5 Reports performed July 1,1996 l
l as " groupings 6105.03 5 Reports performed January 1,1997 i
as " groupings t
To support the more detailed scheduling required as par 1 of this plan to achieve cost leveling over the Program years, and to consider the contracted needs and schedule of the EPRI program, the completion dates on several of the later milestones have been modified and l
intermediate milestones added. The following assumptions are made concerning preparation of Generic Technical Reports (Figure 2-7):
LCM /LR Rev. 0 27
' July 1993 l'
i Figure 2-7 TYPICAL SCHEDULE FOR GENERIC TECHNICAL REPORT l
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l TYPICAL SCHEDULE FOR GENERIC TECHNICAL REPORT Task Cum. Time to Completion as Draft WCAP 1.
Identify Personnel & Schedule
.5 month i
2.
Review industry Experience 1 month M.
Meet with NRC, begin report dev.
3.
Contplete characterization 3 months t
4.
Complete aging evaluation 5 months i
5.
Complete aging management 7 months
[
6.
Complete report dratt 8 months M.
Draft Report Complete 4.
Review, comment 8.5 months M.
Final Report Complete, to NRC 5.
NRC Review 12 months M.
SER issued 6.
Final Report w/SER issued 12.5 months Using these assumptions, tentative completion dates for the initial Technical Reports can be i
derived as follows:
PROJECTED COMPLETION DATES (DRAFT WCAP) FOR TECHNICAL REPORTS I
Group Completion Date - Draft WCAP Group 1 March 16,1994 Group 2 September 16,1994 Group 3 March 16,1995 Group 4 September 15,1995 Group 5 March 15,1996 4 Reports performed 1
as " groupings" September 13,1996 5 Reports performed as " groupings March 14,1997 4 Reports performed as " groupings September 16,1997 2.3.2 PROGRAM COST ESTIMATES Cost estimates have been derived from the assumptions included in the original Project Authorization for each major task and for individual reports. Certain tasks were divided into smaller subtasks to facilitate cost leveling.
l LCM /LR Rev. 0 29 July 1993 l
I l
i Figure 2-8 shows the estimated expenditures by year. Figure 2-9 provides a cost estimate by quarter for the entire Program duration.
Figure 2-8 I
PROGRAM COST BY CALENDAR YEAR (values shown have units of $1000) i l
RESOURCE 1993 1994 1995 1996 1997 1998 TOTAL ENGINEER 743 1242 1298 1274 646 25 5428 i
TECHNICIAN 97 150 146 141 96 7
637 MATERIAL & SERVICES 267 563 500 479 396 12 2217 TRAVEL & LMNG 104 96 101 92 62 3
458 PROGRAM TOTAL 1211 2051 2045 1986 1400 47 8740 EPRI FUNDING 300 300 600 NET WOG COST 911 1751 2045 1986 1400 47 8140 2.3.3 MAJOR MILESTONES The major uncertainty in completing Program tasks lies in the time required to complete and i
obtain acceptance from the NRC on the Technical Reports. While an average time to complete can be proposed, a large number of variables still affect the actual time. For this reason, separate assumptions were made regarding scheduling to evaluate limiting case conditions.
REMAINING MAJOR MILESTONES DUE DATE 3.
Complete initial Program Plan June,1993 4.
Complete initial Generic LCfNLR Implementation Plan December,1994 5.
Issue recommendations / procedure for i
integration of LR/MR/ LCM December,1993 (part 1)
July 1995 (part 2) 6.
Complete plant groupings matrix January,1996 7.
Complete WOG-Generic technical reports March,1996 (WCAPs)
LCM /LR Rev. 0 30 July 1993 i
i l
l Figure 2 9 PROGRAM COST ESTIMATE BY CALENDAR OUARTER l
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LCM'LR Rev. 0 31 July 1993
9.
Update Generic LCWLR implementation Plan December,1997 10.
Comp!ete identification of implementing plants and schedule plan May,1996 11.
Complete plant-group issues reports January,1998 12.
Complete aging management info system February,1998 3.
PROGRAM MANAGEMENT This section describes the management structures which exist or have been created to support the execution of the Program.
3.1 WOG MANAGEMENT STRUCTURE FOR LCM /LR PROGRAM The normal WOG procedure for assigning technical issues to one of the technical subcommittees was subverted for this Program because of its size and expected duration.
Norma!!y, to effectively deal with specific technical issues, WOG subcommittees routinely establish dedicated working groups; these working groups are dissolved when the initiating technical issue is resolved.
32 LCM /LR WORKING GROUP For the LCM /LR Program, a Working Group was established which reports directly to the WOG Steering Committee. This arrangement facilitates direct reporting of status, and permits frequent policy direction. Figure 3-1 illustrates the current working group structure.
32.1 CHAIR, VICE-CHAIR, AD HOC TECHNICAL GROUP COORDINATOR The Working Group chairman is appointed by the Steering Committee. Utility personnel are proposed for the positions of vice-chair and Ad Hoc Technical Group (AHTG) coordinator with concurrence by the Working Group members.
3.2.2 CORE GROUP A core group consisting of 6-8 utility members is derived by consensus from the larger Working Group membership. The core group will provide technical direction and monitor the program on a day-to-day basis.
32.3 AD HOC TECHNICAL GROUPS Ad hoc technical groups are formed from the Working Group membership to support the development of identified technical reports. Each AHTG will be chaired by a member of the Core Group, and wi!! include a technical lead from Westinghouse. Membership on each AHTG wi!! be based on the issue being addressed, and will come from WOG utility members, Westinghouse, and/or subcontractors, as needed.
LCM /LR Rev. 0 32 July 1993
1 Figure 3-1 LCtNLR MANAGEMENT STRUCTURE
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3.2.4 CHARTER The organization of the Working Group, its officers, functions, and duties, are provided in a dedicated Charter.
1 l
I 3.3 WESTINGHOUSE INTERNAL MANAGEMENT STRUCTURE 1
I 3.3.1 PROGRAM MANAGER 1
The Westinghouse Program Manager will have overall responsibility for the timely and accurate execution of all program tasks. He will also be cognizant of all subcontractor arrangements.
LCtNLR Rev. 0 33 July 1993 i
i
F I-l 3.3.2 PROGRAM COORDINATOR l
The Westinghouse Program Coordinator will be responsible for day-to-day functioning of the l
Program. Along with the Program Manager, the Program Coordinator will facilitate tracking of task completions, addressing schedular impacts, supporting all meetings and presentations, providing the periodic reports to the Working Group chairman, and completion of all paperwork associated with subcontractor relations.
3.3.3 MANAGEMENT ADVISORY GROUP This group of upper Westinghouse management is kept aware of Program progress, and facilitates the performance of tasks by Westinghouse personnel.
3.3.4 TECHNICAL ADVISORY GROUP l
This group consists of Westinghouse functional managers and lead technical personnel and provides technical dirsction to the different tasks being performed in-house.
3.3.5 WOG. PROJECT OFFICE The WOG Project Office supports the LCM /LR Working Group via a project engineer and management attention, as required. This office provides the WOG financial tracking information and supports meeting scheduling / arrangements and communications as necessary.
4.
PROGRAM CONTROL This section contains descriptions of the mechanisms which will be used to control (through regular monitoring) Program expenditures, task completion, and adherence to schedule.
l 4.1 CONTROL OF THE PROGRAM PLAN l
l This Program Man contains information essential to the successful execution of the WOG l
LCM /LR Program. As such, it is a controlled document and subject to a signoff procedure when revised.
l l
Each approved version of the Program Plan will bear the signatures of the WOG LCM /LR Working Group Chairman and the Westinghouse Program Manager. The signatures attest that the information in that version is accurate, has been reviewed by Core Group members, and current at the time of signing. The revision date will correspond to the signature date.
The revision number will increase by one for each signed revision; the initial version will be i
Rev. 0.
l' l
Revisions to the Program Plan can be made as often as necessary to reflect the changes that are certain to occur during the life of the Program. A record of the changes will be maintained as part of the Program Plan (Appendix D).
LCM /LR Rev. 0 34 July 1993 1
l J
42 TRACKING OF SCHEDULE, COST, TASK PERCENT COMPLETION The tasks included in the schedule presented in Section 2 will be reviewed on a regular basis to determine extent of completion. Each major task will be divided into subtasks to reflect individual work items. Completion percentages will be provided by individual technical 13rd engineers. From these, a composite completion percentage will be calculated for each najor task. This will allow the validity of schedule completion dates to be assessed.
Similarly, the WOG cost accounting system will be used to compile a percent expenditure for each major item on the task schedule. From this information, a comparison can be derived of the expenditures relative to task completion.
4.3 ST FUS REPORT DESCRIPTION, FREQUENCY & DISTRIBUTION Several types of reports will be developed on a monthly basis to document program progress to date:
Summary of expenditures, by task Summary of percentage completion, by task Summary of milestones comp!eted Any impacts on the original schedule, and resulting adjustments l
Personnel active in the program i
5.
PROGRAM COMMUNICATIONS This section describes the means, frequency and intent of communications within the WOG, between WOG and Westinghouse, within Westinghouse (and its subcontractors), and between l
Program parties and other industry parties.
5.1 ROSTER OF WORKING GROUP MEMBERS This list is maintained by the WOG Project Office and includes names, mailing addresses, and phone and fax numbers.
5.2 MEETINGS, FREQUENCY & ATTENDANCE The WOG LCfNLR Working Group will meet approximately four times per year. These meetings will be held at locations convenient to member utilities. Representatives of all WOG member utilities and cognizant Westinghouse personnel are invited to these meetings.
The WOG LCfNLR Core Group will meet approximately once per month, or as deemed necessary by the Working Group Chairman or the Core Group. These meetings will generally be scheduled in Pittsburgh to ha'fe improved access to Westinghouse personnel involved in l
l the program. Because these are working, technical meetings, representatives of other l
Owners Groups and NUMARC will routinely be invited, along with all of the Core Group utility l
and Westinghouse members.
1 l
LCtNLR Rev. 0 35 July 1993 i
The Ad Hoc Technical Groups will meet on an as-needed basis to support development of the Generic Technical Reports. The Technical Reports Process in Figure 2-2 identifies four specific meetings of the AHTG for a particular report, but also includes a " kickoff" and a
" workshop.* lt is expected that the AHTGs responsible for the first Technical Reports will probably meet six or seven times over the 8 months allocated for report production. Later AHTGs might not need to meet as often due to process refinements.
Additional meetings with other Owners Groups, NUMARC and the NRC are expected to occur on a regular basis as the Program is developed and matures. Attendance at these meetings will generally be limited to the Core Group Chairman, Vice-Chairman, and AHTG coordinator, and the Westinghouse lead personnel.
5.3 REPORTING TO STEERING COMMITTEE, SUBCOMMITTEES LCM /LR Program Status will be provided at every meeting of the WOG Steering Committee and at every Ocncral Session. Regular updates will be provided to WOG subcommittees as requested for information purposes.
5.4 INDUSTRY INTERACTIONS It is expected that NUMARC will provide the forum and organizational structure for the WOG Program to interact with other related industry programs, and in presenting a united industry voice to promote resolution of license renewal rule issues.
i h
LCM /LR Rev. 0 36 July 1993
=
1 APPENDIX A.
REFERENCE PLANT DESCRIPTION 1
NPRDS (INPO) SYSTEM DEFINITIONS EXPANDED BY SYSTEM DESCRIPTIONS FROM WOG TRAP PROGRAM f
i This system listing is derived from a similar listing used in the WOG Trip Reduction and i
Assessment Program (TRAP), which, in tum was derived from the Nuclear Plant Reliability Data System (NPRDS) designations and definitions. It locates equipment within particular systems to permit accurate groupings and system assessments. The TRAP list was expanded based on comparisons with system and building listings for a representative l
composite of WOG plants. These added systems / buildings are highlighted by having their text in upper case letters.
NOTE: This description will continue to be developed as the program matures.
SYS SYSTEM NAME DESCRIPTION AAD Control Room A/C Equipment for heating, cooling,
{
filtering control room air, provision l
for isolation /recire mode AAE Aux. Building Ventilation Equipment for heating, cooling, I
filtering auxiliary building atmosphere.
Supplemented by individual room coolers i
for safeguards pumps and equipment.
Ducting, fans, f11ters, dampers to
{
exhaust contaminated air to primary vent stack AAF Elec. Equip. Ventilation Fans, louvers, ductwork to assure coolir,g of electrical equipment, process
[
and protection gear AAG Screen House Ventilation Fans, louvers and ductwork to either i
bring in outside air or recirculate air to maintain building temperature AAH Turbine Bldg. Vent. Syst.
Fans, dampers, fire dampers, ductwork to maintain building temperature AAI ADMIN BUILDING VENTIIATION AIR CONDITIONING, HEATING, FANS, DUCTWORK, LOUVERS, TO MAINTAIN BUILDING TEMPERATUR" ABD Fire Protection System Fire detection and suppression equipment, firewater pumps, spray nozzles, piping, also halon & CO2 l
subsystems j
ACB TELEPHONE, P.A. SYSTEM PIANT PAGING SYSTEM, WIRELESS TELEPHONE COMMUNICATIONS SYSTEMS, ELECTRONICS, l
POWER SUPPLIES i
I LCM /LR Rev. 0 37 July 1993 l
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ACC Emergency Communication Battery powered phone system for l
1 amargency use, wireless (walkie-talkie) i handsets s
1 I
j CBH Reactor Coolant System Reactor Coolant System, all loops, with
{
pressuriser, PORVs and SVs, pressuriser i
l relief tank, heaters and spray, level l
3 and pressure instrumentation (also used S
for protection) and controls, Reactor.
}
Coolant Pumps include motors and any protection circuitry between the main i
j breaker and the pump, seal leakoff paths, and steam generators.
Includes i
4 RCS flow, temperature, wide range pressure and temperature indications used for protection and control of related systems.
l
+
l CFF Accum Tanks Accumulator tanks, piping, and i
supporting pressurization systems.. Also j
level and pressure instrumentatien 1
EAC offsite Power System All outgoing power. lines beyond the main unit transformer and beyond the unit aux j
(startup) transformer (which brings 1
power back into the plant). Main j
switchyard and high voltage transmission 4
lines (typically > 100Kv, up to 345KV f
j and 500KV)
I i
l EBF Plant AC Power Systems All non-safety' plant power from 25KV down to 120V. Unit Aux Transformer /
Start-up transformer and their j
respective protective circuitry, service Power MCCs,. transformers, cables, j
breakers, busses, relays i
EBK Instrument AC Power Sys.
120VAC Instrument AC Power (Class lE)
I inverters and other regulated power
- i supplies feeding instrument AC, distribution busses i
l' ECC DC Power System and Cont.
All DC systems including batteries and cha.rgers, typically 120 and 250VDC,-used-i j
as " control power" for broe. ors
{
i
' l EDC Elect. Syst. (Protection)
" Safeguards" Class 1E power other than j
3 the 120VAC. Instrument AC.
Diesel driven i
j generators, their respective output l
buses,'all power feeding safeguards 3
buses i
EEB Diesel Generator System Emergency Diesels, support systems not listed separately, generators, exciter i
and voltage regulator circuitry i
I EEC DIESEL STARTING AIR AIR TANKS, COMPRESSORS & MOTORS, i
FILTERS, VALVES & OPERATORS, CIRCUITRY
]
TO CONTROL OPERATION t
i LCM /LR Rev. 0 38
. July 1993 i
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l EEF DIESEL COOLING WATER JACKET WATER HEAT EECHANGER, PUMP &
MOTOR, HEATER, SURGE TANK, VALVES &
OPERATORS, CIRCUITRY TO OPERATE, l
PROTECTION CIRCUITS
{
l EEG DIESEL FUEL OIL DAY TANK, FILTERS, PUMPS & MOTORS,
[
j VALVES & OPERATORS, CIRCUITS FOR i
PROTECTION AND OPERATION EER DIESEL LUBE OIL LUBE OIL COOLER, HEATER, PUMPS & MOTORS, VALVES & OPERATORS, CIRCUITRY FOR OPERATION AND PROTECTION EFA Lighting Systa= (Emergency) Plant lighting supplied by emergency l
power, battery back-up local lighting j
l EFB PLANT LIGHTING NORMAL PLANT LIGHTING SUPPLIED BY
~
SERVICE POWER l
1 EGB CATHODIC PROTECTION EGC FREEZE PROTECTICN l
EGH GROUNDING FCD Spent Fuel Pit Cooling Heat exchangers, pumps and motors, valves and operators, piping, filters, domineralizers, to cool and clean spent e
' fuel pool water i
FCE Refueling Water System Includes RWST and piping up to the suction valves of pumps taking suction on the RWST.
I i
FDF Fuel Handling & Storage Spent fuel pool with storage racks, bridge crane, new fuel storage, overhead i
crane FDG Refueling Equipment Fuel transfer tube and cart, air motor, i
l winch & cables, refueling machine in containment, separate fuel insert
(
handling tools HAB Turbine Gen. & Controls Main Generator and exciter circuitry.
Iso-phase conductors and ducts to the l
main unit output transformer (typically i
l 22k to 345KV) Main transformer.
l I
Generator and exciter breakers and i
protection circuitry i
HAC MAIN TURBINE MAIN TURBINE SHAFT, BLADES, SHROUDS, i
i CASING, TURNING GEAR, STOP AND CONTROL VALVES, COOLING SPRAY EAD MAIN TURBINE LUBE OIL RESERVOIR, PUMPS & MOTORS, ACCUMULATORS, CONTROL VALVES, PIPING, COOLER-t
~!
HAF GENERATOR SEAL OIL RESERVOIR, FILTERS, PUMPS,. PIPING, HAG GENERATOR H2 & CO2 STORAGE TANKS, PIPING, MANIFOLDS, VALVES, PRESSURE REGULATORS l
t LCM /LR Rev. 0 39 July 1993 -
l I
i i
I
l l
HAR STATOR WATER COOLING RESERVOIR, COOLER, PUMPS & MOTORS, VALVES & OPERATORD, PIPING EAI EH CONTROL AND FLUID SYSTEM ELECTRO HYDRAULIC CONTROL SYSTEM, i
l INCLUDES FLUID RESERVOIR, PUMPS, RELIEF AND DRAIN LINES, COOLER UNITS, SERVO VALVES, OPERATORS OF MAIN TURBINE STOP AND CONTROL VALVES, AND INTERCEPT VALVES.
ELECTRONICS WHICH GENERATES CONTROL SIGNALS FOR SERVO VALVES, INSTRUMENTS WHICH PROVIDE SIGNALS I
i (SPEED, LOAD) ARE PART OF OTHER SYSTEMS.
OPERATOR INTERFACE FOR DCMAND SIGNALS ARE INCLUDED HERE HBC Steam System Main Steam System, all piping from SGs to the EP turbine stop valves, main steamline isolation and bypass valves and their operators, steamline safety valves and PORV (atmospheric relief),
steamlines up to the stop valves for turbine-driven main feed pump and aux feed pump EBG Main Steam Systems & Cont.
Steam crossover piping between the HP turbines and Moisture separator Reheaters, and piping back to the LP turbines, intercept valves, MSRs, and MSR steam control system and drains.
EEK EXTRACTION STEAM SYSTIM PIPING, NON-RETURN VALVES, TRAPS, BETWEEN TURBINE CASING AND FIRST ISOLATION VALVE HCB Main Condenser Syst & Cont Main Condenser Air Removal System, all mechanical vacuum pumps or eductors, j
piping, pressure sensors i
EDA Turbine Gland Sealing Turbine Gland Sealing Steam, exhausters, gland steam condenser, pressure control instruments and valves HEC Turbine Bypass Systems Steam Dump System valves and operators, control system circuitry providing signals to valves (instruments are in other systems) i i
HFD Circulating Water System Circulating Water System, pumps and motors (usually located in pumphouse/screenhouse) piping to main condenser water boxes, isolation valves and operators, discharge piping from main condenser to beat sink HHC Aux. Feedwater System Auxiliary Feedwater System, pumps with drivers (both motor and turbine) piping from suction source to main feedwater piping connection, isolation valves, operators and controllers. Does not include start logic for pumps LCM /LR Rev. 0 40 July 1993 i
l i
=
EHE condensate (Inci Cond.)
Main Condenser and Condensate System, pumps (including booster pumps) with their motors and suction / discharge valves, damineralizers, heater drain
]
tanks and pumps, condensing sido of all i
LP feedwater heaters, level controls, i
extends from the main condenser to the l
main feed pump suction valve j
KEF Main Feedwater System Main Feedwater Systam, main food pumps and drivers with supporting systems (lube, EHC, valve operators, speed control circuits and protection), main and bypass feedwater flow control valves with their operators and control circuitry. Tube side of HP feedwater heaters, piping fram suction of main pumps to steam generator shell /
feedring. Steam Generator level control circuitry centrols both pumps and valves EHG CONDENSATE STORAGE &
CONDENSATE STORAGE TANK, TRANSFER PUMPS f
TRANSFER AND MOTORS, VALVES AND OPERATORS, CONTROL CIRCUITRY HIA S/G Blowdown Processing IAD Nuclear Protection Instr.
Nuclear Instrumentat!'n Systam, Source /
Intermediate / and Pwser Range channels, each with detectors, power supplies, fuses, cabinets. Interface to protection logic (systam IBG) is a bistable signal. Permissives P-6, P-8, P-9, P-10 generated by IAD IBG Reactor Protection System All elaments in the signal path from sensors through signal processing circuits, relay or bistable circuits and output controller circuits which are part of the reactor protection function.
i Output from IBG is a signal to open the reactor trip breakers. Both process (Foxboro, 7I00, 7300) and logic (relay and SSPS) equipment l
IBK Engineered Safeguards Sys Engineered Safeguards Systam,
{
instruments and associated process and logic which initiates safeguards actions (containment isolation, stormline and feedlino isolation, safety injection).
This equipment is located along with IBG (Reactor Protection) gear, master and slave relays are unique IBL POST ACCIDENT MONITORING IBM SEISMIC INSTRUMENTS l
IBP EETEOROLOGICAL INSTRUMENTS IBR PLANT COMPUTER i
LCM /LR Rev. 0 41 July 1993
IBI PI. ANT SECURITY SYSTEMS IEG Process Protection Instr.
IEH Control Boards and Panels IFI Reactor Control System 1
MAD Waste Process Syst - Liquid MAE Equipment Drain System MBC Waste Processing Syst - Gas MCC Radiation Monitoring Sys MDA WASTE PROCESSING - SOLID PAA SERVICE CAS (N2 & CO2)
PAD Instrument and Serv. Air PBC Sampling System PCG Chemical & Volume Control Chemical and Volume Control System, letdown piping and heat exchangers, orifices, pressure control valve, domineralizers, volume control tank, chemical addition system: hydrogen /
waste gas connections with pressure controls, boric acid tanks and pumps, domineralized water makeup, makeup control system, RCP seal injection flow, charging (both centrifugal and positive displacement pumps), isolation valves on letdown, charging, altern ato charging, alternate pressurizer spray lines and alternate letdown line.
Safety grade charging pumps provide flow to the Boron Injection System.
Safety function includes suction valves and recire (mini-flow) lines.
PCH Boron Recycle System Boron Recycle System, holdup tanks, recycle evaporators, domineralizers, storage tanks PCI Boron Thermal Regen.
Boron Thermal Regeneration System, piping, valves to direct and control flow, chiller unit, domineralizers PEB Auxiliary Steam System RAD In-Core Equip (Mech only)
RBD Rod Cluster Control RBK Control Rod Drive System Rod Control System, motor / generator sets, power cabinets, logic cabinets, power cables to CRDM coils, main and bypass trip breakers.
i LCM /LR Rev. 0 42 July 1993 i
l i
RCD Reactor Core SAC Reactor Bldg Penetration SAF Hot Penetration Cooling SBD Containment Ventilation SBE Containment Heat Removal SBF Ice Condenser Jystem SBG Containment Fan Cooling i
SCE Containment Spray System SCF Annulus Ventilation Syst t
SCG Containment Air Return l
SCI Cmench Spray System SCJ Containment Recire. Spray SDB Containment Isolation Sus SED Combustible Gas Control SPH Safety Injection System SI system, two trains, with pumps, piping, suction and discharge valves, flow and temperature instrumentation SFK HE Safety Injection and UHI Boron Injection System, including BIT, i
supporting piping and heat tracing, isolation valves.
(Charging pumps remain part of CVCS)
SFL Low Pressure Safety RER System, two trains, includit.g both Injection normal cooling mode and injection modo piping. Includes suction valves and j
discharge valves (with motor operators),
1 pumps, heat exchangers, cross-connect piping and valves, flow and temperature instrumentation SRB Penetration Room Vent.
SYY NSSS (General & Refuel)
MAD Nuclear Service Water Service Water / Essential Service Water, pumps (usually located in the pumphouse
/ screenhouse), piping to heat exchangers, return piping WBD Component Cooling Water Component Cooling Water System, pumps with motors, surge tank, heat exchangers, control valves and operators WCC Makeup Water System WDD PIANT HEATING SYSTEM LCtNLR Rev. 0 43 July 1993
WOB Chilled Water System WHI POTABLE WATER SYSTEM WLL SANITARY DISPOSAL SYSTEM WYY BOP (General)
WYZ Plant (General)
XAA CONTAINMENT BUILDING PRIMARY SYSTEM COMPONENTS, STEAM GENERATORS, BIOLOGICAL SHIELD, SECONDARY SHIELD WALL, POLAR CRANE, REFUELING TROLLY / MAST, INCORE MOVEABLE DETECTORS, SPRAY RING MANIFOLDS, RECIRCULATION SUMPS, PENETRATIONS FOR ELECTRICAL / FLUIDS IBB AUXILIARY BUILDING MAJOR AUXILIARY EQUIPMENT: RMR, SI, CHARGING PUMPS, EACH IN SEPARATE ROOMS WITH INDIVIDUAL ROOM COOLERS, CCW PUMPS AND HEAT EXCHANGER, AUX FEED PUMPS, CVCS DEMINERALIZERS/ FILTERS, SAMPLING SYSTEM, HOT LABS, RAD PROTECTION, CONTAINMENT ACCESS, LOCKERS, DECONTAMINATION, MAIN CONTROL ROOM, PROCESS AND PROTECTION CABINETS, BATTERIES AND INVERTERS ICC SERVICE / ADMIN BUILDING GENERAL SERVICES: MACHINE SHOPS, LOCKER l
ROOMS, OFFICES FOR PLANT STAFF IDD TURBINE BUILDING MAIN TURBINE, GENERATOR, EXCITER, MAIN CONDENSER, CONDENSATE AND MAIN FEEDWATER l
PUMPS, FEEDWATER HEATERS, MAIN FEED REG VALVES (BY EXTENSION, FEED AND STEAMLINE ISOLATION VALVES, STEAMLINE PORVS AND SAFETY VALVES), FEEDLINES AND STEAMLINES, KAIN CONDENSER, MSRs, STEAM DUMP SYSTEM, PRIMARY WATER DEMINERALIZERS, AUX BOILER / CONDENSER, MAIN UNIT TRANSFORMER, UNIT AUX /STARTUP TRANSFORMERS, SITE WATER TREATMENT IEE FUEL BUILDING NEW FUEL STORAGE, SPENT FUEL POOL WITH l
RACKS, TROLLY WITH CRANE, OVERREAD CRANE, FUEL POOL COOLING / CLEANUP SYSTEM, FUEL TRANSFER EQUIPMENT, l
IFF DIESEL BUILDING SEPARATE ROOMS FOR EMERGENCY DIESEL l
GENERATORS, EACH WITH ITS OWN STARTING AIR, LUBE, FUEL, COOLING SUPPORT j
SYSTEMS, LOCAL GENERATOR OUTPUT CONTROLS IGG RADWASTE BUILDING COLLECTION POINT FOR ALL RADIOACTIVE WASTE GENERATED ON SITE, TANKS FOR GAS HOLDUP, LIQUID STORAGE, WASTE EVAPORATOR AND DEMINERALIZERS, SOLID WASTE STORAGE, COMPACTING & DRUMMING IHH PUNP/ SCREEN HOUSE CIRCULATING, SERVICE WATER, FIRE WATER PUMPS, TRAVELING SCREENS AND SCREEN WASH LCM /LR Rev. 0 44 July 1993 l
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III SECURITY BUILDING SITE ENTRY ACCESS POINT, CONTROL POINT FOR PERIMETER MONITORING, PERSON!TEL SECURITY RECORDS, EEIT RAD MONITORING l
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APPENDIX B.
GLOSSARY The following terms and definitions are taken primarily from EPRI brochure BR-101747,
" COMMON AGING TERMINOLOGY" A Glossary Useful for Understanding and Managing the Aging of Nuclear Power Plant Systems, Structures, and Components, copyright 1993.
Those terms and definitions preceded by an asterisk are taken from 10 CFR Part 54-l Requirements for Renewal of Operating Licenses for Nuclear Power Plants.
accelerated aging artificial aging in which the simulation of natural aging approximates, in a short time, the aging effects of longer-term service conditions acceptance criterion specified limit of a functional or condition indicator used to assess the ability of an SSC to perform its design function age (noun) time from fabrication of an SSC to a stated time i
age conditioning
^ simulation of natural aging effects in an SSC by the application of any combination of artificial and natural aging age-related degtadation synonym for aging degradation
- a change in a SSC's performance or physical or chemical properties resulting in whole or part from one or more aging i
mechanisms (i.e. changes in dimension, ductility, fatigue resistance, fracture toughness, mechanical strength, polymerization, viscosity, dielectric strength) (10 CFR 54.3)
- age-related degradation unique to license renewal degradation (1) that occurs during the term of the current operating license but whose effects are different in character or magnitude after the term of the current operating license (the l
period of extended operation); or (2) whose effects were not explicitly identified and evaluated by the licensee for the period of extended operation and the ovaluation found acceptable by the l
NRC; or (3) that occurs only during the period of extended operation (10 CFR 54.3) aging (noun) general process in which characteristics of an SSC gradually change with time or use aging assessment evaluation of appropriate information for determining the effects of aging on the current and future ability of SSCs to function within acceptance criteria l
LCM /LR Rev. 0 46 July 1993 1
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j aging degradation aging effects that could impair the ability of an SSC to function within acceptance criteria i
aging effects net changes in characteristics of an SSC that occur with time or j
use and are due to aging mechanisms j
aging management engineering, operations, and maintenance actions to control t
within acceptable limits aging degradation and wearout of SSCs.
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aging mechanism specific process that gradually changes characteristics of an SSC i
with time or use j
- physical or chemical processes that result in degradation (i.e.
t
[
fatigue, erosion, corrosion, erosion / corrosion, wear, thermal -
j embrittlement, radiation embrittlement, microbiologically induced
[
effects, creep, shrinkage) (10 CFR 54.3)-
i artificial aging simulation of natural aging effects on SSCs by the application of stressors representing plant pre-service and service conditions, j
but perhaps different in intensity, duration, and manner of application l
}
breakdown synonym for complete failure characteristic property or attribute of an SSC (such as shape; dimension; weight; condition indicator; functional indicator; performance; or mechanical, chemical, or electrical property)
'l 1
combined effects net changes in characteristics of an SSC produced by two or j
more stressors common cause failure two or more failures due to a single cause i
common mode failure two or more failures in the same manner or mode due to a single cause complete failure tadure in which there is a complete loss of function i
condition surrounding physical state or influence that can affect an SSC; also, the state or level of characteristics of an SSC that can affect its ability to perform a design function condition indicator characteristic that can be observed, measured, or trended to -
l infer or directly indicate the current and future ability of an SSC l
to function within acceptance criteria condition monitoring observation, measurement, or trending of condition or functional indicators with respect to some independent parameter (usually -
i time or cycles) to indicate the current and future ability _ of an.
I LCM /LR Rev. 0 47 July 1993
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SSC to function within acceptance criteria condition trending synonym for condition monitoring conective maintenance actions that restore, by repair, overhaul, or replacement, the capability of a failed SSC to function within acceptance criteria
- current licensing basis (CLB) set of NRC requirements applicable to a specific plant and a licensee's written commitments for ensuring compliance with and operation within applicable NRC requirements and the plant-l specific design basis (including all modifications and additions to
- F such commitments over the life of the license) that are docketed l
and in effect (10 CFR 54.3)
I degradation immediate or gradual deterioration of ularacteristics of an SSC that could impair its ability to function within acceptance criteria degraded condition marginally acceptable condition of an unfalled SSC that could lead to a decision to perform planned maintenance degraded failure failure in which a functional indicator does not meet an l
acceptance criterion, but design function is not completely lost t
l design basis event any of the events specified in the station's safety analysis that i
are used to establish acceptable performance for safety-related functions of SSCs; events include anticipated transients, design basis accidents, extemal events, and natural phenomena design basis event conditions service conditions produced by design basis events design basis event stressor stressor that stems from design basis events and can produce immediate or aging degradation beyond that produced by normal stressors design conditions specified service conditions used to establish the specifications of an SSC (generally includes margin of conservatism beyond expected service conditions) design life period during which an SSC is expected to function within acceptance criteria design service conditions synonym for design conditions deterioration synonym for degradation LCM /LR Rev. 0 48 July 1993
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diagnosis examination and evaluation of data to determine either the condition of an SSC or the causes of the condition i
diagnostic evaluation synonym:
- diagnosis i
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- effective program (EP) documented program to mange age-related degradation unique l
to license renewal that ensures that an SSC important to license renewal will continue to perform its required function or will not prevent the performance of a required function during the period of extended operation (10 CFR 54.3) l environmental conditions ambient physical states surrounding an SSC l
error-induced aging i
degracation aging degradation produced by error-induced conditions l
error-induced conditions adverse pre-service or service conditions of produced by design, fabrication, installation, testing, operation, or maintenance errors 1
error-induced stressor stressor that sterim.5m error-induced conditions and can produce immediate or agu,g degradation beyond those produced by normal stressors failure inability or interruption of ability of an SSC to function within acceptance criteria failure analysis systematic process of determining and documenting the mode, mechanism, causes, and root cause of failure of an SSC failure cause circumstances during design, manufacture, test, or use that have I
led to failure failure evaluation synonym for failure analysis failure mechanism physical process that results in failure failure mode the manner or state in which an SSC fails failure modes and effects analysis systematic process for determining and documenting potential failure modes and their effects on SSCs failure trending recording, analyzing, and extrapolating inservice failures of an SSC with respect to some independent parameter (usually time or cyclec)
LCfNLR Rev. 0 49 July 1993
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functional conditions influences on an SSC resulting from the performance of design functions (operation of a system or component and loading of a structure) functional indicator condition indicator that is a direct indication of the current ability of an SSC to function within acceptance criteria inservice inspection methods and actions for assuring the structural and pressure-retaining integrity of safety-related nuclear power plant components in accordance with the rules of ASME Code,Section XI inservice life synonym for service life (especially in discussions involving
)
ASME Code,Section XI) i 1
inservice test a test to determine the operational readiness of a component or
]
system [ASME Code.Section XI) t inspection synonym for surveillance i
installed life period from installation to retirement of an SSC
- integrated plant assessment (IPA) licensee assessment that demonstrates that a nuclear power
)
plant facility's SSCs important to license renewal will be i
managed to ensure that the facility's licensing basis will be j
maintained during the renewal period (10 CFR 54.3) l life period from fabrication to retirement of an SSC l
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j life assessment synonym for aging assessment life cycle management synonym for life management l
life management integration of aging management and economic planning to: (1) optimize the operation, maintenance, and service life of SSCs; (2) maintain an acceptable level of performance and safety; and (3) maximize return on investment over the service life of the plant lifetime synonym for life maintenance aggregate of direct and supporting actions that detect, preclude, or mitigate degradation of a functioning SSC, or restore to an acceptable level the design functions of a failed SSC--
malfunction synonym for failure 1
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mean time between arithmetic average of operating times between failure failures of an item [lEEE Std 100]
I natural aging aging of an SSC that occurs under pre-service and service conditions, including error-induced conditions normal aging natural aging from error-free pre-service or service conditions normal aging degradation aging degradation produced by normal conditions normal conditions operating conditions of a properly designed, fabricated, installed, operated, and maintained SSC, excluding design basis event conditions normal operating synonym for normal conditions conditions normal stressor stressor that stems from normal operating conditions and can produce aging mechanisms and effects in an SSC
- nuclear power plant nuclear power facility or a type described in 10 CFR 50.21 or i
50.22 (10 CFR 54.3) operating conditions service conditions, including normal and error-induced conditions, prior to the start of a design basis accident or earthquake operating service conditions synonym for operating conditions operational conditions synonym for functional conditions overhaul (noun) extensive repair, refurbishment, or both performance indicator synonym for functional indicator periodic maintenance form of preventive maintenance consisting of servicing, inspection, parts replacement, surveillance, or testing at predetermined intervals of calendar time, operating time, or number of cycles planned maintenance form of preventive maintenance consistir.g of refurbishment or replacement that is scheduled and performed prior to failure of an SSC post-maintenance testing testing after maintenance to verify that maintenance was performed correctly and that the SSC can function within acceptance criteria LCPNLR Rev. 0 51 July 1993 -
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preconditioning synonym for age conditioning i
predictive maintenance form of preventive maintenance performed continuously or at intervals govemed by observed condition to monitor, diagnose, or trend an SSC's functional or conditional indicators; results indicate current or future functional ability or the nature and schedule for planned maintenance premature aging aging effects of an SSC that occur earlier than expected because of errors or pre-service and service conditions not considered explicitly in design pre-service conditions actual physical states or influences on an SSC g
/ to initial operation (e.g., fabrication, storage, transportation, installation, j
and pre-operational testing) l l
preventive maintenance actions that detect, preclude, or mitigate degradation of a functional SSC to sustain or extend its useful life by controlling degradation and failures to an acceptable level; there are three types of preventive maintenance: periodic, predictive, and
- planned l
qualified lifn period for which an SSC has been demonstrated, through testing, analysis, or experience, to be capable of functioning within acceptance criteria during specified operating conditions while retaining the ability to perform its safety functions in a design basis accident or earthquake random failure any failure whose cause or mechanism, or both, make its time of occurrence unpredictable (IEEE Std 100]
reconditioning synonym for overhaul refurbishment planned actions to improve the condition of an unfailed SSC remaining design life period from a stated time to planned retiremen' cf an SSC remaining life actual period from a stated time to retirement of an SSC remaining service life synonym for remaining life remaining usefullife synonym for remaining life 1
- renewal term period of time that is the sum of the additional amount of time j
beyond the expiration of the operating license that is requested in the renewal application plus the remaining number of years on the operating license currently in effect (10 CFR 54.3)
LCfNLR Rev. 0 52 July 1993
4 repair actions to retum a failed SSC to an acceptable condition replacement removal of an undegraded, degraded, or failed SSC or a part i
thereof and installation of another in its place that can function within the original acceptance criteria residual life synonym for remaining life retirement final withdrawal from service of an SSC i
rework correction of inadequately performed fabrication, installation, or maintenance root cause fundamental reason (s) for an observed condition of an SSC that if corrected prevents recurrence of the condition root cause analysis synonym for fai!ure analysis service conditions actual physical states or influences during the service life of an SSC, including operating conditions (normal and error-induced),
design basis event conditions, and post design basis event conditions service life actual period from initial operation to retirement of an SSC i
servicing routine actions (including cleaning, adjustment, calibrations, and replacement of consumables) that sustain or extend the useful life of an SSC t
simultaneous effects combined effects from stressors acting simultaneously l
stress synonym for stressor stressor agent or stimulus that stems from pre-service and service conditions and can produce immediate or aging degradation of an SSC l
survei!!ance observation or measurement of condition or functionalindicators j
to verify that an SSC currently can function within acceptance criteria surveil!ance ryserements test, calibration, or inspection to assure that the necessary l
quality of systems and components is maintained, that facility operation will be within the safety limits, and that the limiting conditions of operation will be met [10 CFR 50.36]
LCM /LR Rev. 0 53 July 1993
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- surveillance testing synonym for surveillance, survei!!ance requirements, and testing l
synergistic effects portion of changes in characteristics of an SSC produced solely by the interaction of stressors acting simultaneously, as distinguished from changes produced by superposition from each stressor acting independently
- systems, structures, and components (SSCs) important to license renewal (1) safety-related SSCs, which are those relied upon to remain functional during and following design basis events to ensure: (i) the integrity of the reactor coolant pressure boundary; (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposure comparable to the 10 CFR part 100 guidelines (2) all non-safety-related SSCs whose failure could directly prevent satisfactory accomplishment of any of the required functions identified above (3) all SSCs relied on in safety analyses or plant evaluations to demonstrate compliance with the Commission's regulations for fire protection, environmental qualification, pressurized thermal shock, anticipated transients without scram, and station blackout (4) All SSCs subject to operability requirements contained in the facility technical specification limiting conditions for operation (10 CFR 54.3) testing observation or measurement of condition indicators under controlled conditions to an SSC currently conforms to acceptance criteria l
time in service time from initial operation of an SSC to a stated time useful life synonym for service life wearout failure produced by an aging mechanism LCWLR Rev. 0 54 July 1993
i l
}
APPENDIX C.
LIST OF ACRONYMS j
ACRS Advisory Committee on Reactor Safeguards l
AEA Atomic Energy Act of 1954 AHTG ad hoc technical group f
AMIS aging management information system i
ANPR Advanced Notice of Proposed Rulemaking ANS American Nuclear Society APA Administrative Procedure Act APPA American Public Power Association i
ARDM age-related degradation mechanism l
ARDUTLR age-related degradation unique to license renewal f
ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers l
ASTM American Society for Testing and Materials
(
ATWS anticipated transient without scram l
B&WOG Babcock and Wilcox Owners Group BWR boiling water reactor CFR Code of Federal Regulations CLB current licensing basis DOE U. S. Department of Energy
)
i EA environmental assessment
]
EDG emergency diesel generator EEP established effective program EP effective program (10CFR54) i LCM /LR Rev. 0 55 July 1993
1 EPRI Electric Power Research institute EQ equipment qualification l
FSAR final safety analysis report GEIS generic environmental impact statement GSI generic safety issue I&C instrumentation and control IEEE Institute of Electdcal and Electronic Engineers INPO Institute of Nuclear Power Operations IPA integrated plant assessment i
IPE individual plant examination i'
IPEEE individual plant examination for external events ISTM inspection, surveillance, testing, and monitoring ITLR important to license renewal ITMR important to maintenance rule ITPP important to power production LCM life cycle management LCO limiting condition for operation LR license renewal l
NEPA National Environmental Policy Act NPAR Nuclear Plant Aging Research NPRDS Nuclear Plant Reliability Data System NRC Nuclear Regulatory Commission NRR Nuclear Reactor Regulation (branch of NRC)
NUBARG Nuclear Utility Backfitting and Reform Group LCM /LR Rev. 0 56 July 1993 i
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i NUMARC Nuclear Management and Resources Council NUPLEX Nuclear Plant Life Extension O&M operations and maintenance j
OGC Office of the General Counsel (NRC)
OMB Office of Management and Budget l
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OPP Office of Policy Planning (NRC)
{
PRA probabilistic risk assessment PTS pressurized thermal shock j
i PWR pressurized water reactor l
l RCS reactor coolant system j
RER Regulatory Effectiveness Review l
)
SCs structures and components i
SEP Systematic Evaluation Program
[
SRP-LR standard review plan for license renewal I
SSCs systems, structures and components l
TBD to be determined l
TIRGALEX Technical integration Review Group for the Aging and Life Extension i
TRAP Trip Reduction and Assessment Program (WOG) l i
i USl unresolved safety issue j
WCAP Westinghouse Commercial Atomic Power (Report prefix)
{
i WOG Westinghouse Owners Group l
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- APPENDIX D.
REVISION RECORD i
Date Description July 1,1993 Rev. O, initial Issue of the Program Plan i
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APPENDIX E.
BIBLIOGRAPHY The following list of documents related to the general area of LCM /LR is provided as guidance for persons new to the subjects or desiring the source documents referred to elsewhere in this Plan.
l l
1.
10CFR54, *REQUIREfCJTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PL,.oTS," Federal Register / Vol 56, No. 240 / Friday, December l
13,1991 (including Statement of Considerations) l 2.
- REQUIREMENTS FOR MONITORING THE EFFECTIVENESS OF MA!NTENANCE AT NUCLEAR POWER PLANTS," Federal Register / Vol 56, No.
132 / Wednesday, July 10,1991
)
3.
SECY 93-049, IMPLEMENTATION OF 10 CFR PART 54,
- REQUIREMENTS FOR j
RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLANTS," March 1, 1993 4.
Memorandum for the Commissioners from NRC General Counsel, License Renewal l
and SECY 93-049. March 9,1993 i
i 5.
SECY 93-113, ADDITIONAL IMPLEMENTATION INFORMATION FOR 10 CFR PART 54,
- REQUIREMENTS FOR RENEWAL OF OPERATING LICENSES FOR NUCLEAR POWER PLANTS," April 30,1993 l
l 6.
COMSECY 93-029, " Draft Rulemaking on License Renewal (OGC Memorandum of
)
5/14/93)," J. R. Curtis, May 28,1993 I
l 7.
Commission Staff Requirements Memorandum, December 21,1992, Endorsing the j
i Staff Senior Mangement Review Team and Providing 6 License Renewal Rule issues i
to Focus on.
8.
WOG Project Authorization, Life Cycle Management / License Renewal, February, l
1993 9.
WOG/ Westinghouse Pmposal responding to EPRI RFP3075-7,
- License Renewal Technical Demonstration Plants - Resolution of Generic PWR License Renewal Issues," March 12,1993 10.
OPP-92-02, CURRENT LICENSING BASIS FOR OPERATING PLANTS, November 30,1992 j
l 11.
- Foundation for the Adequacy of the Licensing Basis,"(A Supplement to.
the Statement of Considerations for the Rule on Nuclear Power Plant License Renewal
- 10CFR Part 54), December,1991 I
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