ML20245A159
| ML20245A159 | |
| Person / Time | |
|---|---|
| Issue date: | 01/29/1987 |
| From: | Sheron B Office of Nuclear Reactor Regulation |
| To: | Speis T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20237J938 | List: |
| References | |
| FOIA-87-350 NUDOCS 8702180629 | |
| Download: ML20245A159 (200) | |
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MEMURANVUM FOR: Themis P. Speis, Director I Division of Safety Review and Oversight, NRR FROM: Brian Sneron, Deputy Director Division' of Safety Review and Oversight, NRR 1
SilR.lF C I : FORTHCOMING MEtTING WITH INDUSTRY STLEHING COMMITTEE FOR PLANT LIFT LXTENSION On Thursday, February S,1987, a meeting will be held with Tne Industry s
Steering Committee for Plant Life Extension to discuss the status of both the industry and NRC programs in this area. The meeting will be held in Room P-118 fromgp.m. to JR1Id p.m. The agenda is attached. - I
//6 3l50 g .g ( ;j (,j mlw.:. ..aa Brian Sheron, Deputy Director vivision of Safety Review and Oversight Office of Nuclear Reactor Regulation cc: V. dtello H. Denton R. Yoi1mer NKR Division Directors
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E. Beckjord, RES
- G. Arlotto, RES i L. Shao, RES i J. Vora, RES E. Jordan, IE R. Capra, E00 R. Bosnak Wieary J. Jackson N. Anderson PUR J. Scinto, 0GC Receptionist - Phillips Bldg.
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1 AGENDA MEETING WITH INDUSTRY STEERING COMMITTEE FOR PLANT LIFE EXTENSION February 5, 1987 1:00 PM to 3:30 PM j P118 i i
1:00 Introductory Remarks B. Sheron l 1:05 Industry Program -
Industry Steering Committee 2:00 Development of Proposed Policy .
on License Renewal B. Sheron 2:30 NRC Aging Research L. Shao q 3:00 Discussion All l
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U I P E A M M M A V O L E S l t O O C R T U T T E N N E S G S I D O O W S '0 E Y N L C C E E 4 R S U O E E N t I 9 1 D I M _ E l i T - - - - - - - - 8 . ~ \ . F O - N O I S T T C _ E S _ V O A D R C R _ E E F S M _ E G U R R N I S E ?> S N T _ 0 A O A _ 4 E C E R R > C Y G D N T E I I G C N T Y A I A L E P M E L O R L B A A A C C C C E D I T E B N 3 7 T C V A 9 A I R S 1 M S D E I M l E E O A l R S E D I A E G T I D E P R A D Y N 3 R E U S S A 7 O 4 S O 9 1 I C 1 D E l l L R N N C A R P A - A X E Y N E L E Y I T D A 2 1 M T E E 0 I I F 1 3 D L 2 C I T A T O I A W A O T Y T > P D I T N A O E T W T U Y R I T E I T C G N N R C N I E A D I C N S S G E '0 W A S F P N A O O L T F E A N P I 8 9 L P I O L C A T 1 S N C / A C A S D L R - T U C Y P E I I C A , D l i N D M O S t l N I T U E O G L T A E M W T N N E I E G O W E O I N Y O R E L C N R U L T G N P E N U l i A M A T W C T S O O O O L U E A O '0 N N C N P F N E T 7 9 1 D I M E l i T - - - - - - - - . 9 T N E M E C A - L P E - E R S R N O E F E P L X Y C E T Y I N C C O I A E P F T A I R N A C L A O C T E S E I R S W R Y T O E A P N A l C E C E i E D T T Y C A R N F N N 0 E P O O E E 7 E I T M R G D T I N T E R - N L D A C C s U 0 I S A N T A A C 6 A U O R P L N R O M P O E E N C P I E C R N R V C L M E O A A I F N T R O I S I R Y A O T D L R S E E E F N O U T G E E N E K D C L C A I C S A X M U I R N V S. U E E D R O Et E B I K S F T S O T A i R N L S S C A I O I N O E M B F N I T M T K I M S C I G T P O T D E S A l I E A D N F E i T C N T B E I V C E U M I L W D A I F N I O N E O C D I Z R D R C O A I A E T E N D L G A E R T N B E I E E L P S I T O V D R C E O A N X V E N P U D C M O E A L A S I N S G N E N I T G X A E E E I F I I T - - - L - - - - 9 8 _ / N _ O I T A P I C I T _ R - A E P _ M I D T N A D _ A T E S L E R E E D L T S E E E C Y NI S T N M E C Y R Y I T R V O G I S Y R T T F S L T S N S C F E S S I E E C N E N U O U C N D J M O D A N B A R " N O I O P 0 I R L R 4 P P G X G , T N E O E K R E N Y I L R C R E E O T W P P N O T M I I L O U W F T R N I A E A O S A I T R T T C G C P S M E U U E I A F E R I L I Y R S R I E P I L N , S F L M N T D I P E A " T O A I I N O , O W P O D Y Y N Y E E A T C T L L R N , I I O L E Y L L T U B B R I N E D A I D R T O C N N T O R T U P A A A F U S V U O U Y E L S P S B C R L P T A M U D I O E O E N R O E N C U I E T R I N R C O D E N A F N E L U T G U A A G T N P E E I O D N D L R I E R E K V V O V E O E O E E R R C D S - - - - - P P S S 9 O' 1 1 1 e i ? 1 I i - I I Z CC l J l T h e O Cr:: CL. Cd CC Lu > l t I Ln i LLJ J CL D Z O 7 1 l i i 1 l D - 1 c) i e 4 C3 2 M C3 Z < C:C ! W W I a 4 O L.) 1 l l i 9 4 l l l J Codes and Standards Subcommittee 1 Charter e Act as a link between the Steering Committee and various organizations working on codes and standards for life extension I l e Monitor the activities of code and standards organizations that may affect life extension l l l l e Assure that issues developed in industry sponsored studies and methods developments are appropriately considered in amended codes and standards i e Communicate the Steering Committee's recommendations i i 4 Codes and Standards Subcommittee Membershio and Responsibilities i e Subcommittee membership shoulrl be represented by a cross-section of knowledge. These should include metallurgy and materials, mechanical, electricai, civil / structural disciplines. e Voting membership of the subcommittee will be restricted to utility employees. e Consultants may attend on an as-needed basis, either as requested by the Subcommittee or as designated by a utility as their representative. e The Chairman will represent the Steering Committee as a l member of the National Board of Codes and Standar'ds. ) e Individual Subcommittee members will represent the Steering Committee on designated codes and Standards i Organizations, working groups, and task forces. I e The Subcommittee representatives will identify the specific 4 actions before Codes and Standards Committees to the Chairman and propose utility positions regarding these actions for subsequent presentation to the Subcommittee and to the Steering Committee. l e Af ter the Steering Committee has approved a position, the Subcommittee representative will convey these approved l positions to the respective organization for incorporation. Other utilitly representatives on various Codes and Standards organizations will be advised of these positions. e The Subcommittee Chairman assures, via his voting rights on the National Board, that these positions have been adequately implemented. j 1 l \ l Codes and Standards Subcommittee Deliverables i e Progress / Status Reports l e Position Papers; contents include: l - the reason for the need for a Code or Standard revision l - whether the need is primarily to satisfy regulatory i issues, as contrasted with a reliability issue, or whether it addresses both - whether the need is procedura1(1.e, a paper process) or is directly related to material conditions ' - what has been proposed; and by whom j l - the knowledge base from which the methods can be i validated - what sort of evidence will be required to show l conformance - the state of the art for providing the required evidence - how the proposed code or standard is intended to be used by utilities - how it is to be enforced; where and when it will be applicable - assessment with respect to the backfit rule philosophy; if possible, a realistic cost-benefit analysis should be performed - consequences of not developing a proposed code or standard . 1 PILOT TOPICAL VARIANCE STUDY REPORTS TOPICAL REPORTS ( 1r INDUSTRY GENERIC e TOPICAL REPORTS t V V V /\ /\ N ) j './ ARE EXISTING s'NYES NO, IS R&D s\'N CODES & REQUIRED ('N STANDARDS \ SUFFICIENT [ 7 Y N7 , NO NO ACTION REQUIRED [ j YES V V INITIA fE CODE RECOMMEND AND/OR , COMMITTEE INITIATE R&D l EFFORT EFFORT i Figure 1 t i 1 1 ) Z ' L) O of c. CL. CC of O t-- -t D LD LLJ QC l )! l L____________--- 1 THEME: CONTINUATION OF SAFE / RELIABLE PERFORMANCE l 40 YEAR LICENSE TERM DERIVED FROM AUTHORIZATION PERIOD l l RENEWAL NEED NOT BE A WATERSHED EVENT NO DIRECT TIE TO SAFETY OR ENVIRONMENTAL IMPACT 2 FOCUSED REVIEW TO CONFIRM ADEQUACY SCOPE NECESSARILY LIMITED - ENABLES PROPOSED TIMETABLE i ALLOW ECONOMIC DECISION ON LIFE EXTENSION l l t I KEY ELEMENTS OF INDUSTRY POSITION PRICIPLES RENEWAL PROCESS DEALS WITH A KNOWN ENTITY FOCUS ON AGE-RELATED DEGRADATION OF SAFETY-RELATED' EQUIPMENT MAINTENANCE OF THE EXISTING LEVELS OF SAFETY MAINTENANCE OF THE EXISTING LICENSE / DESIGN BASIS FLEXIBILITY NEEDED MANIFESTATION ENVIRONMENTAL ASSESSMENTS ARE ADEQUATE l j PROCESS LOOKS LIKE AN AMENDMENT '1 i I .1 RENEWAL PROCESS WILL DEAL WITH A KNOWN ENTITY PLANT DESIGN + ) 1 OPERATING STAFF + f- > PERFORMANCE CORPORATEMANAGEMENTj PERFORMANCE OVER TIME > OPERATING HISTORY (OPERATING-DATA) OPERATING DATA ENABLES EVALUATION OF AGE-RELATED DEGRADATION OPERATING HISTORY CAN AID JUDGEMENT STAFF CONFIDENCE IN LICENSEE DEGREE OF DOCUMENTATION VARIABILITY IN APPROACH I RENEWAL APPLICATION IS NOT A HYPOTHETICAL PROPOSAL 4 FOCUS ON AGE-RELATED DEGRADATION OF SAFETY-RELATED EQUIPMENT LOGICAL CRITERION FOR PLEX DOES (ITEM) HAVE SIGNIFICANT IMPACT ON OVERALL l PLANT SAFETY l l DOES MECHANISM BECOME OF CONCERN ONLY IN EXTENDED ' OPERATION SHOWING OF ADEQUACY OF EXISTING MONITORING AND MAINTENANCE PROGRAMS USE OF OPERATING DATA l j USE OF PROBABILISTIC TECHNIQUES i I 1 I EXISTING LEVELS OF SAFETY WILL BE MAINTAINED : AND EXISTING LICENSING / DESIGN BASIS WILL BE MAINTAINEQ . (1.E. THE STANDARD FOR JUDGEMENT SHOULD NOT CHANGE) EACH PLANT SATISFIES THE REGULATIONS ; J UNIQUE DESIGN UNIQUE TIMING OF SUBSEQUENT REQUIREMENTS "NEW" SAFETY INFORMATION HAS BEEN INCORPORATED FLEXIBILITY NECESSARY TO ACCOMMODATE DIFFERENCES l BACKFIT RULE IS PART OF THE BODY OF REGULATIONS DOES NOT PREVENT BACKFITS I GUIDES DECISIONS ON APPLICABILITY 1 PERFORMANCE OF MATURE PLANTS HAS NOT BEEN DECREASED WITH AGE l f ENVIRONMENTAL ASSESSMENTS (EA'S) ARE ADEQUATE I RENEWAL APPLICATION WOULD PROMPT AN E.A. STAFF EXPERIENCED IN PREPARATION SAME PROCESS FOR ALL LICENSE AMENDMENTS E.A. COULD DISCLOSE ANY SIGNIFICANT IMPACTS RELATED TO PREVIOUS ENVIRONMENTAL STUDIES ! DETERMINE IF IMPACTS ARE BEYOND MITIGATION EFFECTS LIKELY TO BE SIGNIFICANT ~ TYPICALLY CONSISTANT WITH PROJECTIONS OVERALL PROCESS SIMILAR TO AMENDMENT RENEWAL TREATED UNDER AMENDMENT PROCEDURES (50.90 - 50.92) l -u------ - _ ___a _____ TASKS FOR LICENSING SUB-COMMITTEE IN 1987 i RESPONSE TO COMMENTS BY OTHERS POLICY WHITE PAPER DISTILLATION OF DOCUMENT TO DATE l AVAILABLE FOR USE BY OTHERS l I MONITORING AND SUPPORT OF CP/0L APPLICATIONS LISTING OF POTENTIAL REGULATION CHANGES l FEW IN NUMBER - BASED ON PREMISE OF APPLICABILITY OF AMENDMENT PROCESS DRAFT OF RULEMAKING PETITIONS 10 CFR 51.20(B)(2) l l l I l I I' l ' l m 9 b a:C E , r l D 1 w l l l l 1 I l' i 1 l l l e f . i 1
- 4 l
o NUPLEX PROGRAM IN ORDER TO PLAN FOR FUTURE POWER NEEDS, SOME OWNERS WILL NEED LICENSE RENEWAL IN HAND BY 1995.
FIRM NRC POLICY AND PROCESS FOR LICENSE RENEWAL ARE NEEDED IN 1991 TO SUPPORT PREPARATION, REVIEW, AND APPROVAL OF THE ;
FIRST APPLICATIONS. {
NRC'S RECENT EFFORTS TO ACCELERATE DEVELOPMENT OF LICENSE RENEWAL POLICY ARE APPRECIATED BY THE INDUSTRY.
l NUPLEX STEERING COMMITTEE EFFORTS FOCUS ON GENERIC '
ACTIVITIES SO OWNERS CAN USE COMMON TECHNIQUES FOR LIFE l
EXTENSION EVALUATIONS.
A GENERIC APPROACH IS ALSO DESIREABLE FOR REGULATORY REVIEW BY NRC.
4 THE DEVELOPMENT OF AN EFFICIENT AND STABLE LICENSE RENEWAL PROCESS WILL BE OF BENEFIT TO BOTH THE INDUSTRY AND THE NRC THEREFORE, WE BELIEVE THAT CLOSE INTERACTION BETWEEN NUPLEX AND NRC iS ESSENTIAL.
THE NUPLEX APPROACH DRAWS HEAVILY ON THE RECOMMENDATIONS OF THE AIF/NESP STUDY ON THE REGULATORY ASPECTS OF LIFE EXTENSION.
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OVERVIEW OF PLANNED STEERING CCMMITTEE ACTIVITIES
- 1. TECHNICAL SUBCOMMITTEE ACTIVITIES
. EXISTING PILOT STUDIES
. VARIANCE STUDIES
. INDUSTRY TOPICAL REPORTS AND NRC ITERATION
. IDENTIFY AND MONITOR RESOLUTION OF TECHNOLOGY ISSUES PLANNING AND INFORMATION SYSTEMS DECISIONMAKING TOOLS GENERIC METHODOLOGIES l 2. CODES AND STANDARDS SUBCOMMITTEE ACTIVITIES
. LIAISON WITH CODES AND STANDARDS COMMITTEES LIAISON WITH STEERING COMMITTEE SUBCOMMITTEES
- 3. LICENSING SUBCOMMITTEE ACTIVITIES TIMING ISSUES AND SCHED'ULES
. GUIDANCE DOCUMENTS REGULATORY POLICY POSITIONS SLIDE 4
2 :
EXAMPLE #1 OF INTERACTIVE TASKS DEVELOP INDUSTRY TOPICAL REPORTS I
PURPOSES: )
I PROVIDE LIFE ASSESSMENT METHODOLOGY AND DATA TO ALL
- UTILITIES INTERESTED IN PLANT LIFE EXTENSION-PROVIDE LIFE ASSESSMENT METHODOLOGY FOR SAFETY RELATED -
ITEMS WHICH, AFTER ITERATION WITH NRC, WILL PROVIDE FOR I GENERIC TREATMENT OF SUCH ITEMS '
I 1
TASK WORK ELEMENTS / MILESTONES:
A. PROTOTYPE ITRs WHICH WILL HELP IN DEFINING THE DEVELOPMENT -
AND REVIEW PROCESS FOR ASSESSING SPECIFIC TECHNICAL ISSUES.
INITIAL ITRs WILL ADDRESS:
~
LARGE DRY CONTAINMENT
. PWR P.EACTOR VESSEL BWR REACTOR VESSEL B. INTERACTION WITH NRC ON REVIEW OF ITRs C. DEVELOPMENTOF REMAINING ITRs SLIDE 5-l
- i. .:
o EXAMPLE #2 OF INTERACTIVE TASKS GENERIC GUIDES FOR LIFE EXTENSION TO EVALUATE SAFETY AND ENVIRONMENTAL IMPACT PURPOSE i
PROVIDE GUIDES / METHODOLOGY FOR UTILITIES TO USE FOR THElR OWN EVALUATIONS AND TO PRESENT THEIR JUSTIFICATION FOR PLANT LIFE EXTENSION TO NRC.
TASK WORK ELEMENTS / MILESTONES A. DEVELOP A PROTOTYPE GENERIC GUIDE TO TEST THE PROCESS l
SCREENING CRITERIA (1987 ACTIVITY)
B. INTERACTION WITH NRC ON REVIEW OF GENERIC GUIDE C. DEVELOP OTHER GENERIC GUIDES WHICH MAY INCLUDE.3UCH ISSUES AS: )
CONTENT OF A" LICENSE RENEWAL APPLICATION" OPERATIONAL PERFORMANCE REPORT ,
ENVIRONMENTAL REPORT l AS APPROPRIATE i
SLIDE 6
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l COMPONENTS WHICH ARE THE l
- SUBJECT OF LIC3NSE RENEWAL i l
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'N ggx l ALL PLANT /
'MO \
r\ LESS COMPONENTS m
i COMPONENTS ROUTINELY !
l CONTROLLED SAFETY SIGNIFICANT COMPONENTS SUBJECT SAFETY SIGNIFICANT TO AGE-RELATED COMPONENTS DEGRADATION ,
t i
THE SUBJECT OF LICENSE RENEWAL SLIDE 7
~I, I
1 MEETING WITH INDUSTRY STEERING COMMITTEE FDP PLANT LIFE EXTENSION AGING - LIFE EXTENSION RESEARCH MATERIALS, ENGINEERING BRANCHES l
DFS/RES FEBRUARY 5, 1987 I
NRC HEADQUARTERS, BETHESDA, MD l C. Z. SERPAN, JR.
l l
l l
REACTOR VESSELS AGING l 0 MAJOR ELEMENTS UNDEP STUDY 0 MANY BASES ALREADY GOOD FOR 40 YEARS 0 TECHNICAL AREAS .
l l
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PRESSURIZED THERMAL SHOCK i .
l l -
FRACTURE TOUGHNESS AND EMBRITTLEMENT -
FRACTURE MECHANICS PREDICTION AND EVALUATION METHODS l
SURVEILLANCE DOSIMETRY CRACK GROWTH LIFE EXTENSION O NEED TO DEFINE CRITICAL ISSUES 0 EMBRITTLEMENT AND DOSIMETRY > 40 YEARS o VESSEL ANNEALING 0 VESSEL REPLACEMENT 0 CORE INTERNALS EMBRlYTLEMENT 0 CRD N0ZZLE CRACKING
1 l
l PTPING l
AGING 0 MAJOR ELEMENTS UNDER STUDY l 0 MANY BASES ALREADY GOOD FOR 40 YEARS i
0 TECHNICAL AREAS PIPE FRACTURE ANALYSIS AND TEST CRACKING OF BWR STAINLESS t
STEEL PIPES .
I WATEP CHEMISTRY ,
PIPE WALL THINNING l l
I LIFE FXTENSION l
l 0 NEED TO DEFINE CRITICAL ISSUES 0 AGING OF CAST STAINLESS STEEL 0 FATIGUE DESIGN LIFE REMAINING 4
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i STEAM GENERATORS l
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4, STEA GENERATORS
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The NSP Monticello Pilot Plant Study
- 1983-84 NSP Management Determines that Life Extension Feasibility Study Should be Made for Nuclear Generating ;
Plants
- 1984 NSF Requests Proposals from Engineering Consultants to Manage Nuclear Plant Life Extension Study ,
i
- Fall 1984 Multiple Dynamics in Conjunction with General Electric Company Selected for Life Extension Study' l l
- Spring 1985 EPRI Co-Funding
- Spring 1985 DOE /Sandia Co-Funding ,
l
- Summer 1985 First EPRI/ DOE /NSP/ Virginia Power Workshop ;
in Detroit ,
1
- ASME Section XI Life Extension Working Group Activities
- IEEE Life Extension Working Group Activities ;
i
- Boiling Water Reactor Owners Group Life Extension Committe Activities
- BWROG, Sandia/ DOE, EPRI, NSP PLEX Project Review Committee Activites
- February 1986 NSP Submits Applications for "40-Year" Operating Licenses for Monticello-and Prairie Island Nuclear Generating Plants i
- Susser 1986 PLEX Management Plan Development for Follow-on Work Following Pilot Study
- Spring 1987 Anticipate Completion of Phase I of Monticello Pilot Life Extension Study. Issue of' EPRI/ DOE Project Report
- Early 1987 ,
NSP to Initiate Phase I Life Extension '
Study for Prairie Island Nuclear Generating Plant l
l
_g_
~
'. MULTIPLE DYNAMICS CORPORATION PROJECT INSTRUCTION D ATE ISSUED DOC. NO.
SUBJECT:
MONTICELLO PLANT LIFE June 1986 NSPE-11-2868
! EXTENSION PROGRAM 2 PAGE 3 REVISION:
- 2. OBJECTIVES The Life Extension Program consists of two sets of objectives. The first set constitutes the overall generic utility objectives and the second set defines the l plant specific objectives.
l
( a) Generic Utility Objectives
. Extend plant life a fixed number of years
. Life extension must be based on cost / benefit Assure that current licensed plant life objectives are met
. Improve overall plant availability
. Enhance and improve the cost-effectiveness of current preventive maintenance and inspection programs
. Develop the data base for licensing justification to amend the plant license Identification of early corrective actions
. Maximize generic program application
. Coordination of BWR/PWR and other life extension l
activities
. Prepare and issue a comprehensive BWR Life Extension Program work book
. Prepare and conduct a plant life extension workshop to transfer technology to industry, EPRI, DOE and other interested parties ,
. Determine components , parameters, technolog ies and strateg ies that require further and future research, development and investigation' l
l
MULTIPLE DYNAMICS CORPORATION PROJECT INSTRUCTION D ATE ISSUED DOC. NO. l
SUBJECT:
l MONTICELLO PLANT LIFE June 1986 NSPE-11-2868 l EXTENSION PROGRAM ]
2 PAGE 4 I REVISION:
I l
(
( b) Plant Specific Objectives .
. Implementation of a workable life extension program Identify life threatening components and parameters
. Develop methods and procedures for life-long program updating and maintenance Provide recommendations and procedures for enhanced monitoring, surveillance, inspection and sampling / testing as required and appropriate
. Identify potential improvements for life enhancement through operational changes, modifications
. Develop a comprehensive life extension strategy l through application of the Plant Cycle Management Chart
. Provide adequate plant personnel training in administration of the program i
Conduct a cost / benefit analysis for plant unique i application at Monticello The end result of the Plant Life Extension Program for Monticello will demonstrate a feasible, cost-effective method for extending the useful life of the plant and ;
provide an adequate long-term data base to support regulatory relicensing or license modification. ,
l 9
MULTIPLE DYNAMICS CORPORATION .
PROJECT INSTRUCTION D ATE ISSUED DOC. NO.
SUBJECT:
MONTICELLO PLANT LIFE June 1986 NSPE-11-2868 -
EXTENSION PROGRAM REVISION: 2 PAGE 5 l l
l
(D. Musolf). The project directors are Mr. L. Nolan for NSP and Mr. F. Gregor for MDC. The project team is supported by individuals and organizations as shown on Fig ure 1.
I MDC is under contract to NSP and will be responsible for conducting the work scope as defined in Section 4, l including technical direction, review and approval of the GE work scope activities which are Monticello plant specific. NSP will maintain commercial and Quality Assurance responsibilities for the GE contract. i Mr. D. Musolf (NSP) will maintain communications with EPRI, Sandia (DOE), the BWR Owners Group, and the PWR l Lif e Extension Program (VEPCO) . Mr. Musolf will also coordinate purchase orders and contracts with NSP, monitor the NSP budget, and maintain NSP administrative functions.
Mr. F. Gregor vill direct MDC, GE and any other special consultant project activities including project planning, coordir ,*. ion of technical g uidance , review and approval .
Mr. Gregor will also assist Mr. Musolf as required in maintaining communications and technical interchange with EPRI, Sandia (DOE), the BWROG, and with the PWR program.
l J
1
[-
- MULTIPLE DYNAMICS CORPORATION j
PROJECT INSTRUCTION D ATE lSSUED DOC. NO.
SUBJECT:
! MONTICELLO PLANT LITE June 1986 NSPE-11-2868 -
' l EXTENSION PROGRAM 2
REVISION: PAGE 6 l
l Mr. L. Nolan will coordinate, where necessary, NSP project activities including tecnnical direction, review, approval, and assistance with plant records, surveil-lance, maintenance and testing activities as required by l the program.
i Mr. D. Lehnert will coordinate, review and approve the MDC project team activities including technical direction. 1 To facilitate ready plant access for document / records r etriev al , inspections and walkdowns as necessary, MDC will maintain a liaison office at the Monticello site.
Mr. L. Nolan (NSP) will coordinate the MDC liaison activities.
Project Administration, including cost and schedule control, progress reporting and quality assurance will f be maintained by MDC through Mr. M. Anton.
General Electric (GE) will contribute as a special consultant for the specific work scope described in Reference (13).
A contingency has been established for the use of other special consultants where certain expertise is d.esired or necessary based on recommendations from MDC and approval by NSP. Such services may include metallurgical investig ations, special testing and analytical assistance.
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8 MONTICELLO PLANT LIFE EXTENSION PROGRAM OVERVIEW
s e
PROGRAM PLAN OBJECTIVES o DETERnlNE POTENTIAL EXTENSION YEARS l
l i o INVESTIGATE TECHNICAL ISSUES /0BSTACLES
- o ASSESS COST-BENEFITS 1
o ASSURE CURRENT LIFE G0AL IS MET l
l o IDENTIFY PREVENTIVE ACTIONS, FUTURE WORK o ESTABLISH BASIS FOR LICENSE AMENDMENT
.. 1 PROGRAM STEPS o MAJOR C0hPONEhT INVENTORY (120) o CRITICAL COMP 0 net 1T SELECTION, P.AtiKING o CRITICAL COMPONENT ASSESSMENTS (27) l o CATEGORIZE RENAINING COMPONEhTS !
i
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o EVALUATE ANOTHER 26 COMPO!1EliTS l
o C0tiCUCT FIRST-CUT EC0t!OMIC ANALYSIS ,
l I
o ISSUE REPORTS J
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a: / 1 CC 50c SCO 7Co &r W j Average Score Figure 1: Scoring Sensitivity Chart Top 24 Components I
1 EVALUATION RESULTS COMPONENT RANKING RANK C0hP0 MENT 1 VESSEL PRESSURE BOUNDARY 2 REACTOR PEDESTAL 3 DRYWELL FOUNDATICN 4 BIOLOGICAL ShlELD 5 REACTOR BUILDING BASEMAT 6 FUEL POOL SLABS AhD WALLS l
l 7 SACRIFICIAL SHIELD WALL 8 DRYWELL METAL SHELL ,
i 9 SUPPRESSION CHAMBER INCLUDING SUPPORTS 10 RP'l SUPPORT 11 REACTOR BUILDING FLOOP SLABS AND WALLS 12 CCNTROL ROOM 13 CRD HOUSlHGS EXTERNAL 14 CRD HOUSINGS INTERHAL 15 TURElHE PEDESTAL 16 SHROUD !
17 CORE SUPPORT PLATE 18 CORE TOP AND BOTT0h GRID 19 VEkT LlHES INCLUDING BELLOWS j 20 VENT HEADERS AND DOWNC0r.ERS 21 E"ERGENCY DIESEL GENERATORS 22 REACTOR RECIRCULATION LINES 23 JET PUMPS 24 N0ZZLE SAFE ENDS
i l i
j CRITICAL COMPONENT TOPICAL REPORTS (1) REACTOR VESSEL PRESSURE BOUNDARY, INCLUDING HEAD, FLANGE, l
SKIRT, AND STUB TUBES
)
(2) C0tJCRETE STRUCTURES, REACTOR PEDESTAL, DRYWELL FOUNDATION, BIOLOGICAL SHIELD, FUEL POOL SLABS AND WALLS, REACTOR BUILDING BASEMAT, SACRIFICIAL SHIELD WALL, REACTOR BUILblNG )
FLOOR SLABS AND WALLS, AND THE TURBINE PEDESTAL I (3) DRYWELL METAL SHELL .
(11) SUPPRESSION CHAP.BER, SUPPORTS, VENT LINES AND BELLOWS, VENT HEADERS AND DOWNCOMERS (5) REACTOR VESSEL SUPPORT (E) CONTROL ROOM l
(7) CRD HOUSINGS AND GulbE TUBES j (8) SHROUD, SHROUD LEDGE, CORE SUPPORT PLATE, CORE TOP GUIDE, ANI.
JET PUKPS ;
(9) EMERGENCY DIESEL GENERATORS (IC) PEACTOR RECIRCULATION LINES, PUMP AhD VALVE BODIES :
(11) N0Z2LE SAFE ENDS, THERMAL SLEEVES (12) ECCS, MAIN STEAM AND FEEDWATER PIPING INSIDE PRIMARY CONTAINMENT 4
._- _ __------.________-_-D
[.
)
(
CRITICAL ELEMENT ASSESSMENT l
l i
l o GRIGINAL DESIGN BASIS, CRITERIA, CODES, EQ o IDENTIFY, ASSESS ALL FEASIBLE DEGRADATION PARArETERS j o EVALUATE OPERATING RECORDS, HISTORY l
151,f1AINTENANCE l PAST REPAIRS, REPLACEMENTS, IMPROVEMENTS o ASSESS RELEVANT TEST DATA o REVIEW DATA BASES, NPRDS, C0f.FASS, CPEC-2 I l
o IN-SITU INSPECTIONS, LIMITED TESTING, SAMPLlhG l
o DETERMlNE RATE OF DEGRADATION, LIFE USAGE o LIFE TRENDING AND PROJECTION TO REACH LIMITS o IDENTIFY LIFE LIMITING DEGRADATION PARANETER(S) o IDENTIFY /RECOV. MEND ACTIONS PREVENTIVE MEASURES TESTING, fiONITORING, INSPECTION DIAGNOSTICS PECORDS, DATA NEEDS ,
l R&D o INITI AL LIFE CYCLE AND PLEX ACTIVITY COSTS o REPORTS REVIEW BY NSP, EPRI, SANDIA, BWR-0G ;
l
.. l l
PROGRAM RESULTS l
MAJOR CONCLUSIONS l
i o RPV lilTERNALS, STUB TUBES IS A MAJOR RISK l
l o CONTROL ROOM CAPACITY, TECHNICAL OBSOLESCENCE l
o CONTAINMENT PRESERVATION, CORROSION l
o CONCRETE PRESERVAT10ll, MAINTENANCE o HYDR 0 TESTING ABOVE 212'F o STEAM tlNE EROSION o THERt.AL SLEEVE / SAFE LND REPLACEMENTS o RECIRC PIPING LONG TERM PERFORMANCE UNCERTAIN o Et;ERGEhCY AC/DC CAPACITY LIMITATIONS i
~l I
.. l i
TABLE 1 l CRITICAL COMPCNENT LIFE ESTIMATES COMPCNENT DEGRADATION ESTIKATE:
5"B CC MPCN ENT P A RAMETE R LIFE (YES> ]
Reacter Vessel Beltline Embrittlement >90 Support Knuckle Thermal Fatigue 70 He&d Bolting Cyclic Fatigue 65 Refuel Bellows Skirt Fatigue 60 CRD Stub Tube Weld IGSCC <40 CRD Housing Fatigue >200 Tube-Stub tube weld IGSCC 40-60 RPV Internals ICSCC/IASCC <70 Jet Pump Components ICSCC/ Vibration <40 PPV Support Skirt Fatigue >100 Skirt Cylinder Corrosion >150 1
RCPS Piping Fatigue >70 i C:rrosion/Eresien '> S O I l
Contairren: (Terus) C0rrosion >70 Be11cws FatigJe 95 Vent System Fatigue 95 Drywell Shell Corrosion >150 I Fatigue 200 i i
Recir:. Sys. Piping ICSCC >25 (316 NG)
Pump / Valve Castings 475 *C Embrittlement (25 Control Center Capacity / Space 25-40 Diesel venerator Engine Wear >100 Generator Winding s Wear / Fatigue <30 Concrete Structures vibration, Fatigue >70 Shielding Radiation <65 l
l t
t PILOT STUDY - LESSONS LEARNED o CRITICAL COMPONENT REVIEW COMPLETE 70-YEAR LIFE TECHNICALLY ACHIEVABLE SOf1E ITEMS ARE NOT MAKING YEAR 40 t
KEY PREVENTIVE ACTIONS NEEDED S00N IN-PLANT TEST RESULTS l
RECORDS MANAGEMENT IS MAJOR PROBLEM NO " BIG" SURPRISES o PLEX COST BENEFITS ARE 4: 1 TO 8:1 o SIGNIFICANT GENEdlC WORK REMAINS o IUPROVED 0&M,1S1, DI AGNOSTICS ARE IMPORT ANT 4
i
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2 d
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0 l L
0 150 - ]
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M 1996 2006 2013 223 2006 l
' DATE (TIARS)
I I
r 1
i e
l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ . _ _ . . . _____ _ _ _ a
MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
I
- l
SUBJECT:
REACTOR PRESSURE VESSEL KEY PARAMETERS k O FATIGUE CUE TO THERMAL CYCLING l
O BELTLINE EMBRITTLEMENT C CRD PENETRATION IGSCC LIMITING SUBCOMPONENTS EST. LIFE (YRS) l l
O SUPPORT SKIRT KNUCKLE 70 0 BOLTING 65 O REFUELING BELLOWS SKIRT 60 0 CRD STUB TUBES ?
RECOMMENDED ACTIVITIES (f.tAJOR)
O REFINE FATIGUE MARGIN & IMPROVE CYCLE COUNTING l l
O BELTLINE VOLUMETRIC EXAMINATION R+D C INSPECT CRD PENETRATIONS o R+D HYDROTESTING ABOVE 212 F 0 LONG-TERM RTNDT SPE"IMEN PROGRAM i
i
. l I
i MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
l
SUBJECT:
CONTROL R00 ORIVES/ HOUSINGS 1
KEY PARAMETERS o IGSCC o FATIGUE O WEAR I
LIMITING SUBCOMPONENTS EST, LIFE (YRS)
O TUBE-STUB TUBE WELD O CRD HOUSING (FATIGUE) 276 O
O RECOMMENDED ACTIVITIES (MAJOR) i O iupLEMENT HWC O CRD HOUSING INSPECTIONS (12 PER S YEARS)
I O DEVELOP CRD HOUSING REPAIR PROGRAM O DEVELOP CRD STUB TUBE INSPECTION METHODS i
l 1
l i.
1
, i j
1 l
i I
j Updated Probability of l Crack initiation in the CRD Housing i 4.
as.. vt TH cut vano mnem.,$,,,
so.. l l I
! l
, as..
\ R i
b y so.. 1 10=-
WifH HYDROCf 4 WAftR CHINI$fRV !
- -- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l e
10 20 30 40 50 60 70 Yeors of Operation l 1
l l
Updated Probability of C.RD Housing Failure so i... 1 l'
te.a WITW 110RMAL
,3,,
WA?tt Chim!$'R7
/
b 10<'
& e.-
l vf7H uvonor.tw I
WAf!R CHIM11?RY to 20 30 40 50 60 70 Yeors of Operation
MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
SUBJECT:
REACTOR VESSEL INTERNALS KEY PARAMETERS I
O VIBRATION, FATIGUE ,
l
! o EROSION i
j LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O SHROUD SUPPORT CYLINDER O BOTTOM BEAM (TOP GUIDE) o BEAM-PLATE WELDS (CORE PLATE)
O RISER ELBOW WELD (JET PUMPS)
RECOMP.>dNDED ACTIVITIES (MAJOR)
O HWC IMPLEMENTATION O 5-10 YEAR VT INSPECTIONS o DEVELOP UNDERWATER UT ROBOTS O STUDY, DEVELOP REPAIR TECHNIQUES
f l
l l
l 1 l I l- I I
l i
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i l
SUMMARY
OF RPV INTER!!ALS I
I '
l i
' LIFE PREDICTION ASSESSMENT l
l 60 Year Probability Prediction j Crack Initiation ( ) Repair /keplacemect (1)
Component and Most Limiting Location V/O HCV Vith FVC8 V/O NVC Vith KVC' Core Shroud l
Shroud to Core Support Cylinder 64.2 26.0 22.1 5.5 Attachment Top Guide Instrument Slet on Bottom Beacs 39.6 25.1 23.0 12.3 l
i Core Plate i Beam to Piste Velds 37.4 13.3 13.2 3.5 .
1 Jet Pumps Riser Elbow to Thermal Sleeve Veld and Riser Support Braces 38.8 21.3 18.1 8.0
- Assumes NVC implementation in plant year 15 l 4
1 i
f I
i
4 1
l l
i j
4 1
1 1
1 1
PREDICTED MONTICELLO SHROUD LIFE PREDICTED MONTICELLO CORE PLATE Life !
WO57 UWmNO LOCA9CN bOS" .AftM LCCASON l Ita 100 , j l
,ss - .s:
l ,
! l 80 - 83 - 4 1
- 70 - 70- ,
i i
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30 30 .
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23- 20 l .
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1 l
e 2: 4: i: e :: 4: e vms er ess e.sv.:, vms e, ,s. : e.g.ces 1
1 PREDICTED MONTICELLO TOP GUIDE LIFE JET PUMP RISER SUBASSEMBLY g
0N hsCST Litsff us3 LOC.T104 a-
- i j n- 3, i l e- - 1 EU .
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l l
1 MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
SUBJECT:
REACTOR PRESSURE VESSEL SUPPORT KEY PARAMETERS O FATIGUE INDUCED DURING STARTUP/ SHUTDOWN O GENERAL CORROSION O
LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O SKIRT EXTENSION (FATIGUE) 118 O SKIRT CYLINDER (CORROSION) 150 0
0 RECOMMENDED ACTIVITIES (MAJOR)
O REANALYSIS OF SKIRT TO INTERACTIVELY MODEL W/ PEDESTAL O VISUAL INSPECTION OF SUPPORT INTERIOR 1
o I i
l l
l 1
1 1
l l
l l
MONTICELLO PLANT LIFE EXTENSION PROGRAM !
TOPICAL REPORT
SUMMARY
t 1
SUBJECT:
REACTOR PRESSURE VESSEL SAFE ENDS KEY PARAMETERS O IGSCC O FATIGUE DUE TO THERMAL CYCLING O MECHANICAL WEAR / BYPASS LEAKAGE LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O STAINLESS STEEL SAFE ENDS (IGSCC) <40 0 CARBON STEEL SAFE ENDS (FATIGUE) 60-70 1
O I
O RECOMMENDED ACTIVITIES (MAJOR)
O INCREASE INSPECTION FREQUENCY O INSPECT FEEDWATER SPARGER/ THERMAL SLEEVE FIT C R+D IMPROVED WATER CHEMISTRY (COST / BENEFIT) ,
)
O CYCLE (TEMPERATURE) MONITORING l
i t
l
. j
.. j 1
MONTICELLO PLANT LIFE EXTENSION PROGRAM j TOPICAL REPORT
SUMMARY
I S'UBJECT: REACTOR COOLANT PRESSURE BOUNDARY PlPING KEY PARAMETERS O FATIGUE j O CORROSION / EROSION ,
O DYNAMIC EFFECTS LIMITING SUBCOMPONENTS EST. LIFE (YRS) ;
i O RHR PIPING (FATIGUE) 47 l O MS PIPING (FATIGUE) 70
! l O TW PIPING (FATIGUE) 70 0 PIPING (CORROSION) 81 RECOMMENDED ACTIVITIES (MAJOR)
O FRACTURE TOUGHNESS TESTING O VIBRATION MONITORING o TRANSIENT MONITORING O STEAM LINE EROSION MEASUREMENT l
I L.
1 i
i l
l l
MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
SUBJECT:
ORYWELL METAL SHELL ,
I KEY PARAMETERS ]
O EXTERIOR SHELL CORROSION O LOCALIZED CORROSION (EMBEDDED REGION & SAND POCKET .
REGION) I O SHELL FATIGUE l LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O GENERAL SHELL (CORROSION) 160 l O SHELL FATIGUE 200 l
O LOCALIZED CORROSION UNKNOWN (PART OF 1 FOLLOW-ON l ACTIvITI S}
O l
RECOMMENDED ACTIVITIES (MAJOR) e 2LL THICKNESS MONITORING PROGRAM O EXAMINATION OF EMBEDDED SHELL REGION O BELLOWS EXAMINATION & TATIGUE EVALUATION l O DOCUMENT MINIMUM SHELL THICKNESS VALUES
MONTICELLO PLANT LIFE EXTENSION PROGRAM TOPICAL REPORT
SUMMARY
SUBJECT:
SUPPRESSION CHAMBER AND VENT SYSTEM KEY PARAMETERS O GENERAL ATMOSPHERIC CORROSION O THERMAL EXPANSION INDUCED TATIGUE DURING STARTUP/
SHUTDOWN O FATIGUE AT VENT HEADER /DOWNCOMER INTERSECTION LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O VENT LINES /VENTHEADER (CORROSION) 76 o VENT LINE BELLOWS (TATIGUE) 95
! O VENT HEADER /DOWNCOMER INTERSECTION 95 O
RECOMMENDED ACTIVITIES (M AJOR)
O THICKNESS MEASUREMENT OF VENT LINE AND VENT HEADER o VISUAL INSPECTION OF VENT LINE BELLOWS O DEVELOPMENT OF INSPECTION PROGRAMS VENT LINE AND PENT HEADER INTERIORS AND EXTERIOR O EXPANSION OF INSPECTION PROGRAMS FOR SUPPRESSION CHAMBER INTERIOR AND EXTERIOR 1
l 1
.- b i
l 1
i MONTICELLO PLANT LIFE EXTENSION PROGRAM l l
TOPICAL REPORT
SUMMARY
I J
SUBJECT:
REACTOR RECIRCULATION LINES KEY PARAMETERS O 475 C THERMAL EMBRITTLEMENT EFFECTS o STRESS CORROSION CRACKING EFFECTS O FATIGUE j I '
LIMITING SUBCOMPONENTS EST. LIFE (YRS) i O RECIRC. PUMP CASINGS 20 0 RECIRC. VALVE BODIES 20 0 RECIRC. SYS. PIPING >25 )
l O RHR RETURN S.S. PIPING >25 l
1 RECOMMENDED ACTIVITIES (MAJOR) l O ENHANCED NDE OF CAST / WROUGHT WELD INTERTACES l (DEVELOPMENT AND PERFORMANCE)
O DEVELOPMENT OF LONG-TERM WELD CVERLAY METHOD i
O LONG-TERM HYDROGEN WATER CHEMISTRY AND IHSI EFFECTS O PERFORMANCE OF ENHANCED UT AT END OF OPERATING LICENSE I
l l ,
l l
l l
i MONTICELLO PLANT LIFE EXTENSION PROGRAM i
TOPICAL REPORT
SUMMARY
i
SUBJECT:
PLANT CONTROL CENTER j i
KEY PARAMETERS O PHYSICAL SPACE IN E>.ISTING STRUCTURES O COMPONENT HARDWARE SPARE CnPACITY O GROWTH RATE OP 1E AND BOP SYSTEMS ,
LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O 1E SPACE-CONTROL ROOM AREAS (20-40 YRS)
O PENETRATIONS, CABLE TRAYS IN CONTROL CENTER l
O POTENTIAL "GRANDPATHERING" ISSUES j
O STRUCTURAL LOADS IN CERTAIN PLOORS AND WALLS i
i
- RECOMMENDED ACTIVITIES (MAJOR) )
l O INVENTORIES OF SPARE CAPACITY AND PHYSICAL SPACE O COMPREHENSIVE STRUCTURAL REANALYSES O BETTEP CONFIGURATION CONTROL SYSTEM ,
O TECHNOLOGY UPGRADES TO OVERCOME LIMITATIONS O RESOLVE "GRANDPATHERING" ISSUES i 0 CONTROL OF SPACE UTILIZATION l
l l
l l
l 1
. 1 3 T )
x.
MONTICELLO PLANT LIFE EXTENSION PROGRAM J
.]
TOPICAL REPORT
SUMMARY
j
SUBJECT:
EMERGENCY OlESEL GENERATORS l
KEY PARAMETERS l
1 O MAINTENANCE j l
o TESTING FREQUENCY '
a O ENGINE MUST HAVE CONSTANT OIL CIRCULATION AND PRE-HEATING IN STANDBY MODE 4 LIMITING SUBCOMPONENTS EST. L!FE (YRS) 1 I
4 I g, O GENERATOR WINDINOS (WEAR) 20 k l
O CENERATOR (OBSOLESCENCE) 60
,.l O ENGINE (WEAR) '100 ,'
I !
O l
l RECOMMENDED ACTIVITIES (MAJOR) j i
O STOCK SPARE GENERATOR i O TEST PROGRAM REVIEW O MAINTENANCE INTERNAL REVIEW i
o CENERATOR WINDING INSPECTIONS l
i l
l L _ _ _ _ . _ _ _ _ .
t.
l l~
1 l ,
{ MONTICELLO PLAT 4T LIFE EXTENSION PROGRAM J
TOPICAL REPORT
SUMMARY
SUBJECT:
CRITICAL CO*'F.TE STRUCTURES KEY PARAMETERS O EMbEDMENT/REBAR CORROSION O GENERIC DURABILITY (STRENGTH, SHRINKAGE, CRACKS, FATIGUE)
O VIBRATION, CHEMICAL SPILLS 1
LIMITING SUBCOMPONENTS EST. LIFE (YRS)
O BIOLOGICAL SHIELD (RADIATION) 65 i
O REACTOR BLDG. BASEMAT 65 O MO SET FLOOR SLAB (FATIGUE) 65 O TURBINE PEDESTAL (VIBRATION) 65 RECOMMENDED ACTIVITIES (MAJOR)
O DEVELOPMENT OF MORE ACCURATE METHODS OF PREDICTING SERVICE LIFE O COMPILATION OF TESTING DOCUMENTATION AND SAMPLES DEVELOPMENT OF REPAIR PROCEDURES FOR CONCRETE /REBAR O DEVELOPMENT OF ACCEPTANCE CRITERI A FOR CRACKS, POPOUTS, SPALLS, ETC.
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MEETING WITH INDllSTRY STEERING COMMITTEF FOP PLANT LIFE EXTENSION AGING - LIFE EXTENSION RESEARCH MATERIALS, ENGINEERING BRANCHES DFS/RES FEBRUARY 5, 1987 l
l NRC HEADQUARTERS, BETHESDA, MD I l
I C. Z. SERPAN, JR, l
C-3a
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1 1
1 l
l REACT 0P VESSELS l i
l b i AGING l l
i 0 MAJOR ELEMENTS UNDEP STUDY 0 MANY BASES ALREADY GOOD FOR 40 YEARS 0 TECHFICAL AREAS 1
PRESSURIZED THERMAL SHOCK l FRACTURE TOUGHNESS AND EMBRITTLEMENT j l
FRACTURE MFCHANICS PREDICTION AND EVALUATION METHODS SURVEILLANCE DOSIMETRY CRACK GROWTH LIFE EXTENSION O NEED TO DEFINE CRITICAL ISSUES O EMBRITTLEMENT AND DOSIMETRY > 40 YEARS 0 VESSEL ANNEAllNG 0 VESSEL REPLACEMENT 0 CORE INTERNALS EMBRITTLEMENT 0 CRD N0ZZLE CRACKING
s ,.
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l PIPING AGING o MAJOR ELEMENTS UNDER STUDY 0 MANY BASES ALREADY GOOD FOR LIO YEARS o TECHNICAL AREAS PIPE FRACTURE ANALYSIS AND TEST CRACKING OF BWR STAINLESS STEEL PIPES WATEP CHEMISTRY PIPE WALL THINNING LIFE FYTENS10N o NEED TO DEFINE CRITICAL ISSUES 0 AGING OF CAST STAINLESS STEEL o FATIGUE DESIGN LIFE FEMAINING
1 l
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SlEAM GENERATOPS AGING
! O SURRY PROGPAM ONLY PAPTIAL ANSWEP O LOW PROBABILITY OF ALL GENEPATORS REACHING 40 YEARS O FATER CHEMISTRY CONTROL 0 TECHNICAL AREAS l
l l
INTEGRITY OF DEGRADED TUBES NDE ECT RELIABILITY IN-SERVICE INSPFCTION PLAN LIFE EXTENSION O NEED TO DEFINE CRITICAL APFAS O WATER CHEMISTRY 0 IMPROVED NDE RELIABILITY l
3 1
i i
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e S
EPFSTRUCTIVE EXAMINATIN' AGING ,
O MAJOR ELEMENTS UNDEP STLIDY 0 IMPROVEMFHTS IN DETECTION AND SIZlNG RELIABILITY IN UT AND A/E FOR 40 YEAR LIFE O UT OF OVERLAYS O TECHNIC /.L AREAS ACCURATE DETECTION AND SIZING OF FLAWS IN:
- CARBON STEEL VESSELS, N0ZZLES AND PIPIPG WROUGHT AND CAST STAINLESS STEEL COMPONENTS j BIMETALLIC JOINTS LIFE EXTENSION l
I O NEED TO DEFINE CRITICAL AREAS-0 NDE METHOD FOP MATERIAL PROPERTIES O UT OF STAINLESS STEEL P1PE AND COMPONENTS AND N0ZZLES o UT OF STAINLESS CLADDING 4
. s l
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l CONCRETF STRUCTURES 1
l AGING l
0 INTRODUCTORY PROGRAM FORMULATED l
l 0 PEWORK AND INSPECTION REQUIRFMEFTS l
FOR AGED CONCRETE STRUCTURES ;
O TECHNICAL AREAS REBAR RElFFORCEMENT CORROSION CHEMICAL REACTIONS WITHIN CONCPETE MICR0 CRACK!NG DUE TO THERMAL AND CYCLIC LOADING l 1
PADIATION FFFECTS ON CONCRETE DEGRADATION DEGRADATION OF STRUCTURAL STIFFFFSS )1 EFFECTS OF MAINTENANCE ON THE ABOVE I
LIFE EXTENSION ,
l 0 NEED TO DEFINE CRITICAL ISSUFS O DEGREE OF STRENGTH DEGRADATION BFYOND 40 YEARS i 0 SHIFT OF SEISMIC RESPONSE FREQUENCY 0 CONTAINMENT RFTENTION CAPABILITIES l
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0 DECREASE IN STRUCTURAL MARGINS l 0 MAINTENANCE AND RFPAIR REQUIREMENTS i
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j Codes and Standards Subcommittee Charter e Act as a link between the Steering Committee and various organizations working on codes and standards for life extension e Monitor the activities of code and standards organizations that may af fect life extension e Assure that issues developed in industry sponsored studies and methods developments are appropriately considered in amended codes and standards I e Communicate the Steering Committee's recommendations l
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Codes and f,tandards Subcommittee Mernbershio and Responsibilities e Subcommittee membership should be represented by a cross-section of knowledge. These should include metallurgy and materials, mechanical, electrical, civil / structural disciplines.
e Voting membership of the subcommittee will be restricted to utility employees.
e Consultants may attend on an as-needed basis, either as requested by the Subcommittee or as designated by a utility as their representative.
i e The Chairman will represent the Steering Committee as a member of the National Board of Codes and Standards.
i e Individual Subcommittee members will represent the Steering Committee on designated codes and Standards Organizations, working groups, and task forces.
e The Subcommittee representatives will identify the specific -
actions before Codes and Standards Committees to the Chairman and propose utility positions regarding these actions for subsequent presentation to the Subcommittee and to the Steering Committee.
e Af ter the Steering Committee has approved a position, the Subcommittee representative will convey these approved positions to the respective organization for incorporation.
Other utilitly representatives on various Codes and Standards organizations will be advised of these positions.
e The Subcommittee Chairman assures, via his voting rights on the National Board, that these positions have been adequately implemented.
j Codes and Standards Subcommittee Deliverables e Progress / Status Reports e Position Papers; contents include:
- the reason f or the need for a Code or Standard revision
- whether the need is primarily to satisfy regulatory i lesues, as contrasted with a reliability issue, or whether it addresses both
- whether the need is procedural (1.e, a paper process) or is -
directly related to material conditions
- what has been proposed; and by whom
- the knowledge base from which the methods can be validated l
- what sort of evidence will be required to show conformance
- the state of the art for providing the required evidence
- how the proposed code or standard is intended to be used j by utilities I
- how it is to be enforced; where and when it will be j applicable 1
- assessment with respect to the backfit rule philosophy; if possible, a realistic cost-benefit analysis should be performed
- conse%vences of not developing a proposed code or standard
PILOT TOPICAL VARIANCE STUDY REPORTS TOPICAL REPORTS j l l INDUSTRY GENERIC TOPICAL REPORTS 1r 1
^r IP f l
/
ARE EXISTING YES NO R&D 1 CODES & l REQUIRED STANDARDS SUFFICIENT
[ 7 7 1r NO ACTION No REQUIRED YES i
1f II INITIATE CODE RECOMMEND AND/OR COMMITTEE INITI ATE R&D EFFORT EFFORT Figure I
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'O THEME: CONTINUATION OF SAFE / RELIABLE PERFORMANCE
- (10 YEAR LICENSE TERM DERIVED FROM AUTHORIZATION PERIOD
- RENEWAL NEED NOT BE A WATERSHED EVENT NO DIRECT TIE TO SAFETY OR ENVIRONMENTAL IMPACT
. FOCUSED REVIEW TO CONFIRM ADEQUACY
- SCOPE NECESSARILY LIMITED - ENABLES PROPOSED TIMETABLE ALLOW ECONOMIC DECISION ON LIFE EXTENSION 1
l 4
i 1
KEY ELEMENTS OF INDUSTRY POSITION i
PRICIPLES RENEWAL PROCESS DEALS WITH A KNOWN ENTITY FOCUS ON AGE-RELATED DEGRADATION OF SAFETY-RELATED Ecu PMENT MAINTENANCE OF THE EXISTING LEVELS OF SAFETY MAINTENANCE OF THE EXISTING LICENSE / DESIGN BASl$
FLEXIBILITY NEEDED MAN 1FESTATION i
ENY!RONNENTAL ASSESSMENTS ARE ADEQUATE .
PROCESS LOOKS LIKE AN AMENDMENT 1
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RENEWAL PROCESS WILL DEAL WITH A KNOWN ENTITY
- PLANT DESIGN
+
OPERATING STAFF
> PERFORMANCE l i
+ ;
CORPORATEMANAGEMENTj J i I
PERFORMANCE OVER TIME > OPERATINGHISTORY (OPERATING DATA)
OPERATING DATA ENABLES EVALUATION OF AGE-RELATED DEGRADATION OPERATING HISTORY CAN AfD JUDGEMENT STAFF CONFIDENCE IN LICENSEE DEGREE OF DOCUMENTATION VARIABILITY IN APPROACH I
RENEWAL APPLICATION IS NOT A HYP0THETICAL PROPOSAL l
i 1
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FOCUS ON AGE-RELATED DEGRADATION OF SAFETY-RELATED E0VIPMENT
= LOGICAL CRITERION FOR PLEX DOES (ITEM) HAVE SIGNIFICANT IMPACT ON OVERALL PLANT SAFETY DOES MECHANISH BECOME OF CONCERN ONLY IN EXTENDED OPERATION
= SHOWING OF ADEQUACY OF EXISTING MONITORING AND MAINTENANCE PROGRANS
= USE OF OPERATING DATA
= USE OF PROBABILISTIC TECHNIQUES j
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4 EXISTING LEVELS OF SAFETY WILL BE MAINTAINED AND EXISTING LICENSING / DESIGN BASIS WILL BE MAINTAINED (I.E. THE STANDARD FOR JUDGEMENT SHOULD NOT CHANGE)
\
- EACH PLANT SATISFIES THE REGULATIONS j UNIQUE DESIGN f i
UN10VE TIMING OF SUBSEQUENT REQUIREMENTS l "NEW" SAFETY INFORMATION HAS BEEN INCORPORATED 1
FLEXIBILITY NECESSARY TO ACCOMMODATE DIFFERENCES i
BACKFIT RULE IS PART OF THE BODY OF REGULATIONS DOES NOT PREVENT BACKFITS
/
GUIDES DECISIONS ON APPLICABILITY PERFORMANCE OF MATURE PLANTS HAS NOT BEEN DECREASED WITH AGE
l l
ENVIRONMENTAL ASSESSMENTS (EA'S) ARE ADEQUATE
= RENEWAL APPLICATION WOULD PROMPT AN E.A.
I STAFF EXPERIENCED IN PREPARATION SAME PROCESS FOR ALL LICENSE AMENDMENTS-l
- E.A. COULD DISCLOSE ANY SIGNIFICANT IMPACTS l
RELATED TO PREVIOUS ENVIRONMENTAL STUDIES DETERMINE IF IMPACTS ARE BEYOND MITIGATION EFFECTS LIKELY TO BE SIGNIFICANT TYPICALLY CONSISTANT WITH PROJECTIONS OVERALL PROCESS SIMILAR TO AMENDMENT RENEWAL TREATED UNDER AMENDMENT-PROCEDURES (50.90 - 50.92)
___._-..-_-______.___u_
s l TASKS FOR LICENSING SUB-COMMITTEE IN 1987 '.
I
- . RESPONSE TO COMMENTS BY OTHERS 1
- POLICY W'HITE PAPER
.l DISTILLATION OF DOCUMENT TO DATE q i
AVAILABLE FOR USE BY OTHERS t
- MONITORING AND SUPPORT OF CP/0L APPLICATIONS
- LISTING OF POTENTIAL REGULATION CHANGES FEW IN NUMBER - BASED ON PREMISE OF APPLICABILITY
! 0F AMENDMENT PROCESS DRAFT OF RULEMAKING PETITIONS 10 CFR 51.20(B)(2) l c
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A PRESENTATION ON THE REGULATORY ASPECTS OF LICENSE RENEWAL l
April 22,1987 i
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l-i SLIDE # 1 ~
TOPICS -
PURPOSE OF MEETING BACKGROUND OF NESP STUDY CONCLUSIONS RE: FRAMEWORK OBSERVATIONS l THEMES RE: APPROACH i
I TECHNICAL ASPECTS OF LICENSE RENEWAL r PROCEDURAL ASPECTS OF LICENSE RENEWAL i
QUESTIONS & ANSWERS l
O e 9 9 e l
I CURRENT STATUS OF INDUSTRY EFFORTS ON LIFE EXTENSION FUTURE INFORMATION EXCHANGE MEETINGS
1
. s
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. SLIDE #2 I
l PURPOSE OF MEETING
. TO PRESENT KEY CONCLUSIONS OF THE RECENT NESP STUDY,
" REGULATORY CONSIDERATIONS FOR EXTENDING THE LIFE OF NUCLEAR POWER PLANTS" (AIF/NESP - 040, December 1986)
- NESP REPORT IS AN INITIAL EXAMINATION OF KEY ISSUES
- THE CONCLUSIONS AND ANALYSES IN NESP-040 SHOULD BE VIEWED AS A USEFUL STARTING POINT FOR THE DEVELOPMENT AND COMMUNICATION OF 1 i ISSUES AND KNOWLEDGE CONCERNING LIFE l EXTENSION AND LICENSE RENEWAL.
TO EXPLAIN THE RATIONALE BEHIND THESE CONCLUSIONS TO PROVIDE NRC'S CONTRACTOR (MITRE) AN OPPORTUNITY TO ASK l
QUESTIONS OF THE SPONSORS AND AUTHORS OF NESP-040 AS A ,
i PRELUDE TO MITRE'S FORTHCOMING RESEARCH EFFORTS TO EXPLORE LICENSE RENEWAL POLICY OPTIONS FOR THE NRC e
silde # 3 ATOMIC INDUSTRIAL FORUM /
NATIONAL ENVIRONMENTAL STUDIES PROJECT STUDY SCOPE & OBJECTIVES
. Identify issues to be Addressed by Utilities and by NRC in Establishing Federal Policy for License Renewal
- Evaluate issues and Recommend Specific Policy Alternatives
. Identify Timing issues Associated with License Renawal
- Assess Utility and NRC Actions to Arrive at License l Renewal Policy, and Provide a Roadmap for Taking Such Actions W
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sIlde # 4 AIF/ NESP SCOTT LEIPER - PROJECT MANAGER MELINDA RENNER - MANAGER, SPECIAL PROJECTS AIF/ NESP TASK FORCE CHAIRMAN - DENNIS COX SOUTHERN CALIFORNIA EDISON MEMBERSHIP ,
l 13 UTILITY SPECIALISTS 1 A E REPRESENTATIVE 1 CONSULTANT REPRESENTATIVE 4 NSSS VENDOR REPRESENTATIVES
i 4
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slide # 5 l
CONTRACTOR GROVE ENGINEERING INC. ,
FRIED, FRANK, HARRIS, SHRIVER AND )
JACOBSON l TECHNICAL RESEARCH R. WALKER /C. NEGIN/ l
) H. FEINROTH )
LEGAL RESEARCH M. ROWDEN/J. KRAEMER i l
PROJECT ADVISORY GROUP:
J. M. HENDRIE (CONSULTANT- FORMER NRC CHAIRMAN)
C. LARSON (NSP - VICE PRESIDENT)
J. T. RHODES (VIRGINIA POWER - VICE PRESIDENT)
M. SHAW (CONSULTANT)
W. R. STRATTON (STRATTON & ASSOC.- FORMER ACRS MEMBER)
(
--_ i
b slide # 6 MILESTONES
{
OCTOBER 1985 STUDY INITIATED
-FEBRUARY 1986 KEYISSUESIDENTIFIED AND PRESENTED TO AIF NESP TASK FORCE APRIL 1986 DRAFT REPORT REVIEWED WITH PROJECT ADVISORY GROUP JUNE 1986 DRAFT REPORT REVIEWED WITH AIF NESP TASK FORCE FOR COMMENT JULY 1986 AIF TASK FORCE COMPLETE REVIEW AND COMMENT ON REPORT AUGUST 1956 GROVE ENGINEERING REVISE AND SUBMIT FINAL REPORT OCTOBER 1986 NESP TECHNICAL ADVISORY GROUP. APPROVAL DECEMBER 1986 FINAL REPORT PUBLISHED
b ,
SLIDE # 7 CONCLUSION RE: PROCESS FOR POLICY DEVELOPMENT (CHAPTER 2- APPROACH AND SCHEDULE)
FRAMEWORK OBSERVATIONS AD HOC APPROACH VERSUS FORMAL POLICY MECHANISM RECOMMENDED THREE TIER APPROACH-WHATITIS AND RATIONALE TIERS 1 AND 2 - POLICY STATEMENT AND CHANGES TO
' REGULATIONS l
l l TIER 3-IMPLEMENTING PROCEDURES AND GUIDES 1
SLIDE f 8 First Tier:
Establish Policy
. principles and objectlies e scope and standards for license renewal e review time
- application timing
. Identify regulations to be changed
. pubile comment V
Second Tier:
Modify Regulations e modify timely renewal period 10CFR50.51, need for a plant specific EIS?
e use of amendment versus relicensing j
- Other modifications identified by the Commission e public comment V
t l
Third Tier: ,
Provide Guldance To Licensees i (examples only) I e contents of a submittal ;
- aatety review methode
. evaluations of degradation based on operating records 'j
- evaluations of degradation based on examinations
- Inspection & test in lieu of records l
- evidence of non-degradation for verlous materials i
Three Tiered Approach To Estabilshing -
A License Renewal Process 1
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SLIDE # 10 L THEMES RE: APPROACH (CHAPTER S - SECTIONS 5.2 TO 5.9)
THEME 1 - THE CONTINUITY THEME
' EXTENDING PLANT LIFE BEYOND 40 YEARS IS A REAFFIRMATION OF THE .
ONGOING AND CONTINUOUS PROCESS OF HARDWARE RENEWAL THAT IS AN INTEGRAL PART OF EVERY NUCLEAR POWER PLALPS OPERATING PROGRAM. .
THE PRACTICE OF FOCUSING ON dPECIFIC DEGRADATION MECHANISMS AND ESTABLISHING CRITERIA TO ASSURE CONTINUED SAFETY OF THE PUBLIC IS THUS ALREADY AN ESTABLISHED POLICY AT THE NRC. LICENSE RENEWAL CAN BE VIEWED AS A CONTINUATION OF THIS POLICY, AND AN OPPORTUNITY TO OVERSEE ITS OVERALL APPLICATION TO BE SURE NOTHING HAS BEEN MISSED."
J11EME.2 THE EXTANT LICENSING BASIS CONCLUSION
" BASED ON THE OVERALL SAFETY RECORD OF NUCLEAR POWER PLANTS DURING THEIR INITIAL TERMS, IT DOES NOT SEEM APPROPRIATE FOR NRC TO INCLUDE NEW CRITERIA IN THE SAFETY EVALUATION OF INDIVIDUAL COMPONENTS OR STRUCTURES FOR UCENSE RENEWAL ITIS RECOMMENDED ,
THAT THE OVERALL COMMISSION POLICY BE ESTABLISHED ON THIS PREMISE.*
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I SLIDE # 11 I
THEME RE: APPROACH -The Continulty Theme
- OWNERS ALREADY PERIODICALLY EVALUATE MATERIAL l CONDITIONS
- AND OWNERS UPGRADE AND MAINTAIN HARDWARE BASED ON THESE PERIODIC EVALUATIONS
- NRC OVERSEES THE OWNER PROGRAMS TO MAINTAIN THE MATERIAL CONDITION OF THE PLANT j
- THE PE*tlODIC OWNER EVALUATION PROGRAMS ALSO PROJECT FUTURE PERFORMANCE
- LIFE EXTENSION EVALUATIONS MERELY LENGTHEN THE PROJECTION TIME FRAME i
- LICENSE RENEWAL EVALUATIONS LOOK AT THE SAFETY RELATED ASPECTS OF SUCH OWNER EVALUATIONS l
9
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- IN
SUMMARY
, THE " CONTINUITY" THEME SAYS THAT AN EVALUATION FOR LICENSE RENEWAL IS REALLY AN EXPANSION OF i WHAT THE LICENSEE ALREADY DOES PERIODICALLY. 1
.]
THE METHOD USED TO CONDUCT THE PERIODIC EVALUATIONS, AND -
THE SPECIFIC ONE FOR LICENSE RENEWAL, CAN TAKE MANY )
l DIFFERENT FORMS. I IF NEW dVALUATION METHODS, CODES AND STANDARDS, AND REGULATORY APPROACHES ARE REQUIRED FOR AGING,THEY ARE i NEEDED DURING THE INITIAL TERM AND NOT JUST FOR LICENSE l RENEWAL. THEY SHOULD NOT BE TIED TO LICENSE RENEWAL l
THEREFORE, LICENSE RENEWAL ITSELF iS NOT A WATERSHED" l EVENT FROM AN ENGINEERING POINT OF VIEW. THE 'AEGULATORY PROCESS SELECTED FOR LICENSE RENEWAL SHOULD BE
' ESTABLISHED ACCORDINGLY.
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i SLIDE # 13 1 ALTERNATIVE CONSIDERED THE NESP STUDY CONCLUDED THAT SUBJECTING THE ENTIRE PLANT TO A THOROUGH AND COMPREHENSIVE SAFETY EVALUATION, EITHER i DETERMINISTIC OR PROBABLISTIC, OR SOME COMBINATION, WAS NOT RECOMMENDED FOR SEVERAL REASONS:
i
+ OPERATING EXPERIENCE AND DATA ON THE CONTINUING MATERIAL l CONDITION OF THE PLANT / AE A MORE RELIABLE INDICATION OF SAFETY THAN ANALYSES OF HYPOTHETICAL EVENTS. l
. SUCH AN APPROACH IS INCONSISTENT WITH THE REGULATORY POSITION WHICH SAYS THE PLANT IS SAFE ON THE 40TH YEAR OF OPERATION.
ANY CONCERNS ABOUT THE OVERALL SAFETY OF THE PLANT AFTER YEAR 40, WOULD ALSO BE RELEVANT TO EVALUATING THE PLANT DURING ITS INITIAL TERM. THE OWNERS' AND REGULATORS' ACTIONS TO ASSURE SAFETY DURING THE INITIAL TERM, MUST, BY DEFlNITION, BE SUFFICIENT TO ASSURE SAFETY DUR!NG THE EXTENDED TERM.
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SLIDE # 14 l:
THEMES RE: APPROACH -The Licensina Basis
. RATIONALE SIMILAR TO CONTINUITY RATIONALE
. IF PUBLIC SAFETY IS PROTECTED AT YEAR 40 .ALSO PROTECTED AT YEAR 41 ,
. IF NEW INFORMATION DEVELOPS AFTER INITIAL LICENSING, NRC APPLIES ON CASE BASIS...DOESNT WAIT FOR RENEWAL
)
- TMI ACTION PLANITEMS PRESSURIZED THERMAL SHOCK i
. CONSISTENT WITH CURRENT PRACTICE TO APPLY HIGHER l STANDARDS TO NEWER PLANTS,WHILE ALLOWING OLDER l l PLANTS TO CONTINUE OPERATING UNDER PRIOR STANDARDS - l I
- CURRENT NEW SOURCE PERFORMANCE STANDARDS FOR FOSSIL PLANTS
- NAVAL PLANTS SAFETY IS COMBINATION OF OPERATING SKILL AND MATERIAL CONDITION OF PLANT. OLDER PLANTS HAVE LONG TERM DEMONSTRATION OF SAFETY VIA OPERATING RECORD l
i
i SLIDE # 15 TECHNICAL ASPECTS OF LICENSE RENEWAL-
- PRESUMPTION-CONTINUITYTHEMEIS ACCEPTED
- SCREENING PROCESS
+ For Owner: system-by-syste:n review for age-related degradatbn a For NRC: that subset of owner evaluation which affects safety
- For Both; identify subsubset which involves routine inspection, maintenance, replacement. Assure program remains effective.
- Remaining components / systems need to have special evaluations
- COMPONENT EVALUATION PROCESS Key is to evaluate and project performance of remaining components against approved design criteria. Use operat;onal and inspection data, and analytical tools.
l
- Use generic methods where possible . . . Industry Topical Reports
- Codes and standards amended as appropriate 1
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- THE BACKFIT RULE I
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. If,in projecting the future performance of a key component, NRC chooses to use new technical criteria, Backfit Rule should apply.
- PLANT UPGRADES AND MODIRCATIONS
- OPERATING EXPERIENCE a Main rationale for selecting review process and criteria. . .
- Therefore, should consider in renewal review.
- The most relevant information which supports engineering determination on material condition of plant.
Maintenance and inspection results and data - system by system.
Operational performance of entire systems as evidence of continued satisfactory operation, i
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SLIDE # 17 )
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- ENVIRONMENTAL REPORT
- Evaluate any changes in site factors . cooling water, etc.,
which could Affect safe plant performance.
- Evaluate efforts to minimize worker exposure and projected future exposure.
- Basis for N' 1 environmental assessment.
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,' SLIDE # 18 l
PROCEDURAL ASPECTS OF LICENSE RENEWAL l
- NEPA CONSIDERATIONS
. PElS
-TIMELY RENEWAL DOCTRINE i
- HEARINGS 1'
. NATURE
. TIMING ,
- EFFECTIVE DATE OF RENEWED LICENSE
. TACK-ON
. SUPERSESSION l
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INDUSTRY LIFE EXTENSION ORGANIZATIONS
-. NUMARC - EXECUTIVE OVERSIGHT
. NUPLEX STEERING COMMITTEE OVERALL INDUSTRY COORDINATION AND INTERFACE WITH NRC
- TECHNICAL SUBCOMMITTEE
- LICENSINr. SUBCOMMITTEE
- CODES AND STANDARDS SUBCOMMITTEE
. OWNERS GROUPS (B&W, BWR, CE, W)
. EPRI l
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SLIDE # 22
( NUPLEX OBJECTIVES
. COORDINATE INDUSTRY, DOE, EPRI PROGRAM EFFCRTS
. DEVELOP GENERIC UTILITY ASSISTANCE
. SEEK REGULATORY POLICY, FRAMEWORK, PROCESS
- CLEAR, PREDICTABLE, WORKABLE
- IN PLACE ON TIME TO MEET INDUSTRY NEED
- REASONABLE APPLICATION PROCESS TIME
- COMPATIBLE WITH UTILITY PLANNING CYCLE LEAD TIME l.
f
. PROVIDE A FOCUS FOR RAPIDLY GROWING INDUSTRY INTEREST AND ;
I PARTICIPATION l
. OPTIMlZES RESOURCE REQUIREMENTS FOR BOTH INDUSTRY AND NRC I
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SLIDE # 23 NUPLEX PROGRAM
. IN ORDER TO PLAN FOR FUTURE POWER NEEDS, SOME OWNERS WILL NEED LICENSE RENEWAL IN HAND BY 1995.
I FIRM NRC POLICY AND PROCESS FOR LICENSE RENEWAL ARE NEEDED IN 1991 TO SUPPORT PREPARATION, REVIEW, AND APPROVAL OF THE FIRST APPLICATIONS.
NRC'S RECENT EFFORTS TO ACCELERATE DEVELOPMENT OF LICENSE j
. RENEWAL POLICY ARE APPRECIATED BY THE INDUSTRY.
?
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- NUPLEX STEERING COMMITTEE EFFORTS FOCUS ON GENERIC
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- A GENERIC APPROACH IS ALSO DESIREABLE FOR REGULATORY REV;EW ;.
i BY NRC.
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- THE DEVELOPMENT OF AN EFFICIENT AND STABLE LICENSE RENEWAL PROCESS WILL BE OF BENEFIT TO BOTH THE INDUSTRY AND THE NRC THEREFORE, WE BELIEVE THAT CLOSE INTERACTION BETWEEN NUPLEX ,
AND NRC IS ESSENTIAL 1 l
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- THE NUPLEX APPROACH DRAWS HEAVILY ON THE RECOMMENDATIONS OF THE AIF/NESP STUDY ON THE REGULATORY ASPECTS OF LIFE <
EXTENSION, I l
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SLIDE f 25 OVERVIEW OF PLANNED STEERING COMMITTEE ACTIVITIES
- 1. TECHNICAL SUBCOMMITTEE ACTIVITIES EXISTING PILOT STUDIES
+ VARIANCE STUDIES l INDUSTRY TOPICAL REPORTS AND NRC ITERATION IDENTIFY AND MONITOR RESOLUTION OF TECHNOLOGY ISSUES
- PLANNING AND INFORMATION SYSTEMS DECISIONMAKING TOOLS GENERIC METHODOLOGIES
- 2. CODES AND STANDARDS SUBCOMMITTEE ACTIVITIES
- LIAISON WITH CODES AND STANDARDS COMMITTEES LIAISON WITH STEERING COMMITTEL SUBCOMMITTEES
- 3. LICENSING SUBCOMMITTEE ACTIVITIES
- TIMING ISSUES AND SCHEDULES GUIDANCE DOCUMENTS i
- REGULATORY POLICY POSITIONS
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0l A PRESENTATION ON THE REGULATORY ASPECTS OF LICENSE RENEWAL I
To: Nuclear Regulatory Commission By: NUPLEX Steering Committee _
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Slide 1 AGENDA OPENING REMARKS; INTRODUCTION G. NEILS PURPOSE OF MEETING /
BACKGROUND OF NESP STUDY D EDWARDS FRAMEWORK OBSERVATIONS M. ROWDEN SUBSTANTIVE ELEMENTS OF LICENSE RENEWAL H. FEINROTH PROCEDURAL ASPECTS OF i LICENSE RENEWAL J. KRAEMER l l
TIMING D. HOSTETLER l
INDUSTRY PERSPECTIVE G. NE!LS DISCUSSION I
~)
I Slide 2 PURPOSE OF MEETING
. TO PRESENT KEY CONCLUSIONS OF THE RECENT NESP STUDY,
" REGULATORY CONSIDERATIONS FOR EXTENDING THE LIFE OF NUCLEAR POWER PLANTS" (AIF/NESP 040, December 1986)
. - NESP REPORT IS AN INITIAL EXAMINATION OF KEY ISSUES
- THE CONCLUSIONS AND ANALYSES IN NESP-040 SHOULD BE VIEWED AS A USEFUL STARTING POINT FOR THE DEVELOPMENT AND COMMUNICATION OF ISSUES AND KNOWLEDGE CONCERNING LIFE EXTENSION AND LICENSE RENEWAL.
. TO EXPLAIN THE RATIONALE BEHIND THESE CONCLUSIONS .
)
. TO PROVIDE AN OPPORTUNITY TO ASK QUESTIONS OF THE SPONSORS AND AUTHORS OF NESP-040 AS A PRELUDE TO NRC'S EFFORTS TO EXPLORE LICENSE RENEWAL POLICY OPTIONS q
'. TO PROVIDE AN OVERVIEW OF THE INDUSTRY'S EFFORTS TO PURSUE LIFE EXTENSION / LICENSE RENEWAL
.I
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' ATOMIC INDUSTRIAL FORUM /
NATIONAL ENVIRONMENTAL STUDIES PROJECT I l STUDY SCOPE & OBJECTIVES q f i I
. Identify issues to be Addressed by Utilities and by the NRC in Establishing Federal Policy for License Renewal ;
l a
! + Evaluate issues and Recommend Specific Policy Alternatives
- Identify Timing issues Associated with License Renewal l
i
. Assess Utility and NRC Actions to Arrive at Ucense Renewal Policy, and Provide a Roadmap for Taking Such Actions
]
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Slide 4 PROJECT ORGANIZATION l ATOMIC INDUSTRIAL FORUM National Environmental Studies Project -
l
............................,.............)
Life 13 Utility Reps Extens. ion . oOE I Task Force EPRI 4 NSSS Reps r , 1 Grove Engineering / ADVISORY Fried, Frank, Harris, GROUP Shriver, and Jacobson J. RHODES ,
J. HENDRIE i C.LARSON M. SHAW I W.STRATTON l
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4 Slide 5 POLICY DEVELOPMENT.
FRAMEWORK OBSERVATIONS AD HOC APPROACH VERSUS FORMAL POLICY MECHANISM 1
l RECOMMENDED THREE TIER APPROACH-WHAT ITIS AND '
RATIONALE TIERS 1 AND 2 - POLICY STATEMENT AND CHANGES TO REGULATIONS TIER 3-IMPLEMENTING PROCEDURES AND GUIDES j
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SLIDE #6
. First Tier:
Establish Policy I
f - e principles and oojectives <
r e scope and standards for Econse renewal- ,
e review time l l
e application timing
. Identify regulations to be. changed
- public comment l
II Second Tier:
Modify Flegulations e modify timely renewal period ,
a 10CFR50.St, need for a plant spec!fic EIS?
]
. use of amendment versus rolleensing .
e other modifications identif!ed by the Commission {
- public comment )
II Third Tier: 4 Provide Guidance To Licensees (examples only)
+ contents of a submittal
- safety review methods e evaluations of degradation based on operating records
- e evaluations of degradation based on examinations
. Inspection & test in llou of records l
. evidence of non-degradation for various materials )
i a
l Three Tiered Approach To Establishing ;
A License Flenewal Process i i
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PROJECT CONSIDERATIONS
. TWO CRITICAL ASPECTS OF LICENSE RENEWAL REVIEW
- What is the Scope
- What are Criteria for Judging Acceptability t
. NESP STUDY INPUTS INCLUDED
- Recent Utility Experience with CP-OL
- Other Regulatory Reg lmes (UK, Fossil)
- NRC Practice with Test Reactors
- Language of Legislative History
. MAJOR INPUT-FROM NESP SPONSORS "What do the licensees need to do to assure themselves of the safety and regulatory practicability of extended life?"
. TWO BASIC THEMES EMERGED
. REFINED VIA INTERACTION WITH SPONSORS, ADVISORY GROUP, NESP TAG i
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SUBSTANTIVE ELEMENTS OF LICENSE l RENEWAL d
., 3
,i THEME 1 - CONTINUITY .j
" EXTENDING PLANT LIFE BEYOND 40 YEARS IS A REAFFIRMATION OF THE i
, ONGOING AND CONTINUOUS PROCESS OFNARDWARE RENEWAL THAT .
}
IS AN INTEGRAL PART OF EVERY NUCLEAR POWER PLANT'S OPERATING ]
PROGRAM. . . THE PRACTICE OF FOCUSING ON SPECIFIC DEGRA DATION : i MECNAN/SMS AND ESTABLISHING CRITERIA TO ASSURE CONTINUED
'l SAFETY OF THE PUBLIC IS THUS ALREADY AN ESTABLISHED POLICY AT THE NRC. LICENSE RENEWAL CAN BE VIEWED AS A CONTINUATION OF THIS
. POLICY, AND AN OPPORTUNITY TO OVERSEE ITS OVERALL APPLICATION TO
' BE SURE NOTHING HAS BEEN MISSED."
l THEME 2 - EXTANT LICENSING B ASIS ,
l
" BASED ON THE OVERALL SAFETY RECORD OF NUCLEAR POWER PLANTS l DURING THEIR INITIAL TERMS,IT DOES NOT SEEM APPROPRIATE FOR NRC TO INCLUDE NEW CRITERIA IN THE SAFETY EVALUATION OF INDIVIDUAL COMPONENTS OR STRUCTURES FOR LICENSE RENEWAL. IT IS RECOMMENDED 1 HAT THE OVERALL COMMISSION POUCY BE ESTABUSHED ON THIS PREMISE."
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Slide 9 The Continuity Theme
- OWNERS ALREADY REGULARLY EVALUATE THE MATERIAL CONDITION OF THEIR PLANTS
- AND OWNERS UPGRADei AND MAINTAIN HARDWARE BASED ON THESE REGULAR EVALUATIONS
- NRC OVERSEE $ THE OWNERS' ACTIVITIES TO MAINTAIN THE MATERIAL CONDITION OF THE PLANT 4-
- blE OWNER EVALUATION PROCESS ALSO PROJECTS FUTURE PERFORMANCE
- LIFE EXTENSION EVALUATIONS MERELY LENGTHEN THE PROJECTION TIME FRAME
- LICENSE RENEWAL EVALUATIONS LOOK AT THE SAFETY RELATED ASPECTS OF SUCH OWNER EVALUATIONS
_ _ _ _ _ . _ . . _ _ . _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ Im_
, Slide 10
- IN
SUMMARY
, THE " CONTINUITY" THEME SAYS THAT AN EVALUATION FOR LICENSE RENEWALIS REA'.LY AN EXPANSION OF WHATTHE LICENSEE ALREADY DOES. ,,
THE METHOD USED TC, CONDUCT THESE EVALUATIONS, AND THE SPECIFIC ONE FOR LICENSE RENEWAL, CAN TAKE MANY DIFFERENT FORMS.
IF NEW EVALUATION METHODS, CODES AND STANDARDS, AND REGULATORY APPHOACHES ARE REOUIRED FOR AGING,THEY ARE NEEDED DURING THE INITIAL TERM AND NOT JUST FOR LICENSE RENEWAL THEY SHOULD NOT BE TIED TO LICENSE RENEWAL THEREFORE, L.lCENSE RENEWAL ITSELF IS NOT A " WATERSHED" EVENT FROM AN ENGINEERING POINT OF VIEW. THE REGULATORY ;
PROCESS SELECTED FOR LICENSE RENEWAL SHOULD BE 1 ESTABLISHED ACCORDINGLY.
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1 Slide 11
.}
l The Extant Licensina Basis Theme 1
THE LICENSING CRITERIA (BASES) USED TO JUDGE SAFETY DURING AN EXTENDED TERM SHOULD BE THE SAME AS THOSE EVOLVED DURING THE INITIAL TERM AND " EXTANT" AT THE TIME OF LICENSE RENEWAL APPLICATION. 1
{
. IF PUBLIC SAFETY IS PROTECTED AT YEAR 40 .ALSO PROTECTED I AT YEAR 41
- IF NEW lNFORMATION DEVELOPS AFTER INITIAL LICENSING, NRC APPLIES ON A CASE-BY-CASE BASIS. DOESNT WAIT FOR RENEWAL
- TMI ACTION PLAN ITEMS
- PRESSURIZED THERMAL SHOCK
. SAFETY IS COMBINATION OF OPERATING KNOWLEDGE AND MATERIAL CONDITION OF PLANT. OLDER PLANTS HAVE LONG TERM DEMONSTRATION OF SAFETY VIA OPERATING RECORD I
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Slide 12 TECHNICAL ASPECTS OF LICENSE RENEWAL
+ SCREENING PROCESS
. COMPONENT EVALUATION PROCESS
+ THE BACKFIT RULE
- PLANT UPGRADES AND MODIFICATION
. OPERATIONS EXPERIENCE
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Slide 13 PROCEDURAL ASPECTS OF LICENSE RENEWAL q l
r 1
. NEPA CONSIDERATIONS l
. TIMELY RENEWAL DOCTRINE I
J
. HEARINGS
- Nature
- Timing
. EFFECTIVE DATE OF RENEWED LICENSE
- Tack-on
- Supersession
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SLIDE #16 Nuclear Generating Capacity l
110 -
100 -
/
00 -
80 -
70 -
U.S. Nuclear Caacfs go _ ,
(Ggswatts) ,
E L ense [
[
40 -
- *"' ,' Nhac y 30 -
l s
to -
to -
-. A i 1970 1980 1990 2000 goto gogo y ,, ,,,,
Year Currentiv - Nuclear power represents:
- 16% of U.S. electricity supplied
- >40 % for 6 states
- >25% for 13 other states ,
l SUDE 17 i
i IMPACT OF NUCLEAR PLANT RETIREMENTS ON VIRGINIA POWER GENERATING CAPACITY
- l l 10 - j
> l
~
Suny 19012) 8.
Suny 2 9013)
Total .
Generating North Anna t pois)
Capacity 6 - Nonh Anna 2 9020)
(GW) 4-2 O
I i I I l1 I i i ll l 1 l l1 1 I i l 1, 2005 2010 2015 2020 Year
- assumes all fossil plants continue in operation indefinitely 4
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e Slide 18 INDUSTRY'S PERSPECTIVE-WHAT'S CHANGED 1940s to 1970s 1970s to 1980s Predictable LOAD GROWTH Erratic CAPACITY 8 to 10 Years DOUBLING TIME Unpredictable {
i 12% to 15 % RESERVE MARGIN > 40 % I l
i 6 to 8 Years PLANNING CYCLE 12-1_4 Years )
]
Incremental REPLACEMENT Aging Units Not Size Increase RATIONALE Being Replaced l (economy of size) (no incentive)
-l
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> 20 YEARS OLD 80 % i
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. Slide 20 NUPLEX OBJECTIVES
- COORDINATE INDUSTRY, DOE, EPRI PROGRAM j
, EFFORTS 1 l
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- DEVELOP GENERIC UTILITY ASSISTANCE
- SEEK REGULATORY POLICY, FRAMEWORK, PROCESS !
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- Clear, Predictable, Workable
- In Place On Time To Meet Industry Needs Compatible with Utility Planning Cycle Lead Time
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PROVIDE A FOCUS FOR RAPIDLY GROWING !NDUSTRY INTEREST AND PARTICIPATION 1
OPTIMlZE RESOURCE REQUIREMENTS FOR BOTH NRC l AND INDUSTRY
Slide 21 NUPLEX PROGRAM -
+ in order to plan for future power needs, some owners will need license renewal in hand by 1995.
+ Firm NRC policy and process for. license renewal are needed in 1991 to support preparation, review, and approval of the first applications.
+ NRC's recent efforts to accelerate development of license renewal policy are appreciated by the industry.
NUPLEX steering committee efforts focus on generic activities so owners can use common techniques for life extension evaluations.
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A generic approach is also desireable for regulatory review by i NRC.
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. The development of an efficient and stable license renewal i
process will be of benefit to both the industry and the NRC.
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. Therefore, we believe that close interaction between NUPLEX and NRC is essential.
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