ML20148P509
| ML20148P509 | |
| Person / Time | |
|---|---|
| Issue date: | 01/15/1988 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-675A NUDOCS 8801290161 | |
| Download: ML20148P509 (72) | |
Text
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JAN 151983
,3froMt Noh675 MEMORANDUM FOR:
The Record FROM:
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MEETING WITH INTERNATIONAL TECHNOLOGY (IT)
CORPORATION TO DISCUSS THE DOE ADVANCED REACTOR SEVERE ACCIDENT PROGRAM (ARSAP)
INTRODUCTION A meeting of the NRC Research staff and the Standardization and Non-Power Reactor Project Directorate staff with representatives of International Technology Corporation was held at the NRC offices in Bethesda, Maryland, on December 16, 1987. The purpose of the meeting was to provide information on the ARSAP program, its objectives, participants, structure, accomplishments to date and expected FY88 results. Also, IT Corporation expected to obtain NRC feedback on issues. provides a list of those in attendance. provides the viewgraphs which IT used to discuss the ARSAP program.
DISCUSSION The expectations of the discussion are well ider tified in the view graphs.
Also the ARSAP program and objectives are well stated in the view graphs.
The expected turnaround time for review of ARSAP *.opic papers was six months.
EPRI and GE has de probabilityof10~finedanaccidentwhichwouldbenogreaterthana 4
for 25 rems at i mile frem the reactor. The staff l
requested the basis for this criterion.
It was incicated that a paper was under development to support this criterion.
1 Much of the discussion related to the use of the MAAP code and how the staff would deal with this code and with the staff sponsored MELCOR code.
It was clear that the staff needed to address this issue and comitted to respond to the industry. Also, the industry wanted to know how RES and NRR would work together to review the issues.
They wanted to know the process which would l
be implemented to deal with the ARSAP issues.
It was clear that RES would be the prime reviewers; however, it was not clear to the industry how NRR and RES would interact. The staff connitted to respond to these issues.
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l' JAN 151988 Zoltan Rosztoczy discussed the development of the severe accident regulation.
Currently RES has three projects related to this. These include:
1.
Development of a Severe Accident Regulation 2.
Develop a Comission Policy on Standardize Plants 3.
Coordinate major programs.
RES does have a Reg. Guide development program on Severe Accident Statement.
They also are developing a Severe accident policy involving accident prevention and containment performance. Also under consideration is a PRA rule.
It is their intent to have the rules and reg. guides in place by the first of 1990.
RES will have quarterly meetings with industry to envelope the Reg. Guides.
The meetings will be held with NUMARK as information meetings for industry on the most important issues. RES has also considered working with EPRI on the Standardized Plants programs. General requirements will be defined in the rules with the specific details identified in the Reg. Guides.
The staff indicated that the use of the MAAP code and its alternate should be discussed in the Licensing Review Bases.
Guy S. Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects
Enclosures:
As stated DISTRIBUTION:
1 Central File NRC PDR PDSNP Reading LRubenstein GVissing EHylton OGC-White Flint EJordan JParticw NRC Participants ACRS (10)
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NA/pg PDSf9j PDSNM GVikin,g LRubenstein 01/j'y88 01//f/88
O
. i Zoltan Rosztoczy discussed the development of the severe accident regulation.
Currently RES has three projects related to this. These include:
1.
Development of a Severe Accident Regulation 2.
Develop a Commission Policy on Standardize Plants 3.
Coordinate major programs.
RES does have a Reg. Guide development program on Severe Accident Statement.
They also are developing a Severe accident policy involving accident prevention and containment performance. Also under consideration is a PRA rule.
It is their intent to have the rules and reg. guides in place by the first of 1990.
RES will have quarterly meetings with industry to envelope the Reg. Guides.
The meetings will be held with NUMARK as information meetings for industry on the most important issues. RES has also considered working with EPRI on the l
Standardized Plants programs. General requirements will be defined in the
{
rules with the specific details identified in the Reg. Guides.
The staff indicated that the use of the MAAP code and its alternate should be discussed in the Licensing Review Bases.
Guy S. Vissing, Prof ct Manager i
Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects
Enclosures:
As stated 1
l l
=
Attendance List For i
Meetina With DOE /IT Corp.
Concerning Advanced Severe Accident Program (ARSAP)
December 16, 1987 i
Name Organization i
Guy S. Vissing NRR/PDSNP t
R. W. Houston RES Mario Fontane IT Corp.
Tony Buhl IT Corp.
George David C-E i
4 Mike Green C-E Paul Haas IT Corp.
Dave Leaver IT Corp.
i Jerry N. Wilson NRC/RES Bob Copp EG&G/INEL l
Zoltan R. Rosetoczy NRR/RES L. S. Rubenstein NRC/NRR l
Paul Leech NRR/PDSNP l
Dino Scaletti NRR/PDSNP Tom King RES/DRA/ARGIB William Beckner RES/DRPS/RHFB Charlie Brinkman C-E Bethesda Rick Sumnitt IT Corporation Dan Giessing DOE l
l 4
i d
Encisoure 2 ADVA.NCED REACTOR SEVERE ACCIDENT PROGRAM (ARSAP)
TONY BUHL BOB COPP MARIO FONTANA PAUL HAAS PRESENTED TO THE NUCLEAR REGULATORY COMMISSION DECEMBER 16, 1987
THIS MEETING CONTINUES ARSAP/CE-NRC INTERACTIONS MEETINGS ERIC BECKJORD AND RES STAFF -
JULY 16,1987 TOM MURLEY AND NRR MANAGERS
- AUGUST 3,1987 GUY VISSING AND NRR AND RES STAFF - AUGUST 12, 1987 WAYNE HOUSTON, GUY VISSING MARK CUNNINGHAM, -
OCTOBER 14, 1987 1
THE PURPOSE OF THIS BRIEFING IS TO:
[1?
PROVIDE INFORMATION ON THE ARSAP PROGRAM 9
MISSION / OBJECTIVES S
PARTICIPANTS / INTERFACES S
STRUCTURE S
ACCOMPLISHMENTS TO DATE AND EXPECTED FY88 RESULTS
THE PURPOSE OF THIS BRIEFING IS TO: (2)
(2's REVIEW THE PLANNED CE/ARSAP S/A ISSUE RESOLUTION APPROACH O
PROCESS S
ISSUE TOPIC PAPER S
SCHEDULE S
EXPECTED RESULTS l'3'I IDENTIFY OPPORTUNITIES FOR TECHNICAL INFORMATION EXCHANGE 1
i
EXPECTATIONS FOLLOWING THIS PRESENTATION
[1)
TO IDENTIFY NRC PROGRAMS AND KEY STAFF IN AREAS PERTINENT TO ALWR SEVERE ACCIDENT ASSESSMENT, AND UNDERSTAND NRR - RES ROLES AND RESPONSIBILITIES
-[2)
TO OBTAIN NRC VIEWS ON AND POSSIBLE APPROACHES FOR CONSIDERING SEVERE ACCIDENTS IN LICENSING / CERTIFICATION
~
REVIEWS
'l31 TO OBTAIN CONCURRENCE ON THE CE/ARSAP S/A ISSUE RESOLUTION PROCESS AND SCHEDULE
[4?
TO 03TAIN NRC FEEDBACK ON THE PROPOSED TECHNICAL INFORMATION EXCHANGE l
l I
i l
l THE ARSAP PROGRAM 4
l O
1 i
DOE ARSAP MISSION e
ASSIST IN THE EARLY RESOLUTION OF RISK SIGNIFICANT SEVERE ACCIDENT ISSUES SO THAT THEY WILL NOT BE MAJOR ISSUES FOR EVOLUTIONARY ADVANCED LIGHT WATER REACTORS DURING THE 1990'S i
m..
DOE ARSAP OBJECTIVES e
SUPPORT DOE DESIGN VERIFICATION PROGRAM REACTOR VENDORS' SEVERE ACCIDENT c2 ASSESSMENT, ANALYSES, AND l
ISSUE RESOLUTION O
PROVIDE INPUT TO, REVIEW, AND SUPPORT EPRI REQUIREMENTS DOCUMENT IN SEVERE ACCIDENT AREAS.
e ACHIEVE MORE GENERIC RESOLUTION OF SEVERE ACCIDENT ISSUES -- THAN MAY OCCUR THROUGH SUPPORT OF VENDOR CERTIFICATION OR OF EPRI REQUIREMENTS DOCUMENT
-- SUCH THAT THEY ARE NOT lSSUES FOR ALWR's.
l
ARSAP PARTICIPANTS l
DOE:
SUPPORTING AGENCY EG&G IDAHO:
PROGRAM MANAGER IT CORPORATION:
TECHNICAL DIRECTOR FAl:
SUBTLER CONTRACTOR FOR ANALYSIS METHODS DEVELOPMENT LEAL:
CONSULTANT FOR REGULATORY ISSUES CE:
ALWR DESIGN VERIFICATION CONTRACTOR ITAG:
INDUSTRY TECHNICAL ADVISORY GROUP
1 ARSAP ORGANIZATION DOE j
ALWR DESIGN j
VERIFICATION PROGRAM COMBUSTION ENGINEERING PROGRAM MANAGER EG&G IDAHO TECHNICAL DIRECTOR INDUSTRY TECHNICAL IT CORPORATION ADVISORY GROUP 1
i l
ANALYSIS METHODS REGULATORY ISSUES ISSUE DEVELOPMENT DEVELOPMENT LEAL PRA DEVELOPMENT &
FAUSKE & ASSOCIATES, INC.
(CONSULTANT)
APPLICATION j
(SUBTLER CONTRACTOR)
EPRI SUPPORT j
IT CORPORATION i
ARSAP SUPPORT TO INDUSTRY TO ADDRESS SEVERE ACCIDENT ISSUES WITH NRC ARSAP Topic o issu Papers CE System 80+
M thods certification o PRA Support o Reg. Support hAlA k Al EPRI N
ALWR Requirements l
3 Document p
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Certification i
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APWR I
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Certification I
SEVERE ACCIDENT REQUIREMENTS FOR ALWRs ARE IDENTIFIED IN THE NRC SEVERE ACCIDENT POLICY STATEMENT APPROVED ON AUGUST 3,1985 e
DEMONSTRATE COMPLIANCE WITH PRESENT REGULATIONS S
DEMONSTRATE TECHNICAL RESOLUTION OF ALL UNRESOLVED SAFETY ISSUES AND HIGH
~.
PRIORITY GENERIC SAFETY ISSUES S
COMPLETE A PROBABILISTIC SAFETY ASSESSMENT e
COMPLETE STAFF REVIEW OF DESIGN... DETERMININSTIC ENGINEERING AND ANALYSIS AND JUDGEMENT COMPLEMENTED BY PRA 1
ARSAP PROGRAM STRUCTURE THE ARSAP PROGRAM IS STRUCTURED TO SUPPORT RESOLUTION OF SEVERE ACCIDENT ISSUES CONSISTENT WITH THE NRC SEVERE ACCIDENT POLICY STATEMENT e
WBS 1.
MANAGEMENT AND PLANNING e
WBS 2.
SEVERE ACCIDENT ISSUES RESOLUTION e
WBS 3.
SEVERE ACCIDENT ANALYSIS METHODOLOGY e
WBS 4.
PRA METHODOLOGY AND APPLICATION CRITERIA e
WBS 5.
REGULATORY COMPLIANCE ALTERNATIVES S
WBS 6.
CERTIFICATION PROCESS DEVELOPMENT AND SUPPORT
ARSAP PROGRAM STRUCTURE (2) e WBS 7.
LESSONS LEARNED NOTEBOOK O
WBS 8.
EPRI P.EQUIREMENTS DOCUMENT e
WBS 9.
EPRl/ VENDOR 600 MWe PLANT DESIGN AND CERTIFICATION e
WBS 10. CE SYSTEM 80 PLANT DESIGN AND CERTIFICATION e
WBS 11. GE ABWR PLAN SUPPORT e
WBS 12. WESTINGHOUSE APWR PLANT SUPPORT e
WBS 13. CHERNOBYL RELATED ISSUES
WBS 10 ENCOMPASSES l
SUPPORT FOR CE SYSTEM 80--
PLANT DESIGN AND l
CERTIFICATION S
REVIEW OF SEVERE ACCIDENT ISSUES RELEVANT TO CE DESIGN e
DEFINITION OF SEVERE ACCIDENT SEQUENCES FOR ANALYSIS e
PERFORMANCE OF SEVERE ACCIDENT ANALYSIS 9
SUPPORT FOR SYSTEM 80+ PRA e
ASSESSMENT OF SEVERE ACCIDENT MITIGATION FEATURES S
SUPPORT OF FINAL DESIGN APPROVAL AND NRC REVIEW PROCESS l
y-.--., --
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ymy
e ARSAP MAJOR ACCOMPLISHMENTS TO DATE
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PROGRAM MANAGEMENT AND PLANNING S
PROGRAM PLAN AND INPLEMENTATION PLAN COMPLETED l' ANNUAL UPDATES'l 9
INTERFACES WITH EPRI AND VENDORS ESTABLISHED 9
INDUSTRY TECHNICAL ADVISORY GROUP [lTAG) OPERATING
l ARSAP MAJOR ACCOMPLISHMENTS TO DATE (2) l l
SEVERE ACCIDENT ANALYSIS METHODOLOGY S
MAAP AND MELCOR CHOSEN AS PRIMARY ANALYTICAL INTEGRATED CODES S
MAAP MODELING IMPROVEMENTS AND BENCHMARKING PLANNED AND UNDERWAY 1
9 MAAP CODE CONFIGURATION QUALITY CONTROL [CCQC'J PROCEDURE ESTABLISHED
ARSAP MAJOR ACCOMPLISHMENTS TO DATE (3)
PRA METHODOLOGY AND APPLICATIONS S
GUIDANCE FOR USE OF PRA IN DESIGN BEING DEVELOPED S
PRA GROUNDRULES AND ASSUMPTIONS DEVELOPED FOR EPRI S
HIGH LEVEL FUNCTIONAL PRA MODELS DEVELOPED FOR EPRI
l ARSAP MAJOR ACCOMPLISHMENTS TO DATE (4) 1 REGULATORY ALTERNATIVES AND CERTIFICATION PROCESS S
WHITE PAPERS WRITTEN ON POTENTIAL ACTIVITIES AND RESULTS S
ON HOLD DUE TO FUNDING LIMITATIONS
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ARSAP MAJOR ACCOMPLISHMENTS TO DATE (5)
SUPPORT TO VENDORS S
CE SUPPORT IN PROGRESS S
GE SUPPORT IN PROGRESS 9
MONITORING WESTINGHOUSE PROGRAM an.--~
ARSAP MAJOR ACCOMPLISHMENTS TO DATE (6)
SUPPORT TO EPRI S
SIGNIFICANT INPUT TO EPRI ALWR REQUIREMENTS DOCUMENT CHAPTERS 1 AND 5 9
DETAILED REVIEW OF CHAPTERS 1,2,3,4,5 9
INPUT ON CHAPTER 6 IN PROGRESS S
TECHNICAL SUPPORT FOR S/A -
RELEVANT REQUIREMENTS, e.g., H 2 CONTROL
ARSAP MAJOR ACCOMPLISHMENTS TO DATE l
(7) l RESOLUTION OF S/A ISSUES S
IDCOR/NRC RESOLUTION EXPERIENCE AND RELEVANCE TO ALWRs SUMMARIZED AND LESSONS LEARNED EXTRACTED S
RESOLUTION PROCESS ESTABLISHED AND IMPLEMENTATION STARTED S
PARTICIPATED IN U.S.
INVOLVEMENT IN lAEA CHERNOBYL ACTIVITES
ARSAP PLANNED FY88 MAJOR RESULTS S
SIX SETS OF S/A ISSUE TOPIC PAPERS TO NRC, INTERIM GUIDANCE ON MAJORITY OF ISSUES S
MODIFICATidNS AND BENCHMARKING OF MAAP COMPLETED e
UPGRADED FUNCTIONAL PRA MODELS COMPLETED AND 1
DEMONSTRATED FOR EPRI S
FIRST EDITION OF LESSONS LEARNED NOTEBOOK PUBLISHED; ANNUAL UPDATES DRAFTED
ARSAP PLANNED FY88 MAJOR RESULTS (2) 9 TECHNICAL REPORTS IN SUPPORT OF EPRI REQUIREMENTS DOCUMENT AND CE/ARSAP ISSUE RESOLUTION, e.g., HYDROGEN CONTROL,RCS DEPRESSURIZATION e
TECHNICAL REPORTS IN SUPPORT OF CE SYSTEM 80+
SEVERE ACCIDENT ANALYSIS e
TECHNICAL REPORTS ON PRA EXTERNAL EVENTS ANALYSIS AND SUPPORT SYSTEM SENSITIVITY S
TECHNICAL REPORTS IN SUPPORT OF GE ABWR S/A ANALYSIS, e.g., SEISMIC FRAGILITY DATA, ATWS ANALYSIS
8 e
4 l
l f
SEVERE ACCIDENT ISSUE RESOLUTION O
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l DOE /ARSAP/CE ARE WORKING l
WITH THE NRC TO RESOLVE l
SEVERE ACCIDENT ISSUES 9
RESOLUTION PROCESS WAS PRESENTED IN BRIEFINGS TO BECKJORD, MURLEY AND MANAGERS ll7/16/87), I;8/3/87)
S PROCESS AND SCHEDULE DETAILED WITH NRC NRR STAFF ll8/12/87)
S FIRST SET OF ISSUE PAPERS
~
SUBMITTED TO NRC 1: 11/24/87) e SECOND SET OF ISSUE PAPERS DRAFTED S
TECHNICAL EXCHANGE ON MAAP AND MELCOR PLANNED ll1/5-7/88)
DOE /ARSAP/CE ARE INTRODUCING SEVERE ACCIDENT ISSUES TO NRC FOR RESOLUTION THROUGH THE CE SYSTEM 80-- CERTIFICATION PROCESS e
ISSUE TOPIC PAPERS WILL PRECEDE THE CE SYSTEM 80+
CERTIFICATION SUBMITTAL, BUT WILL BE PART OF THE CERTIFICATION PROCESS
A PROCESS FOR RESOLUTION OF SEVERE ACCIDENT ISSUES WAS PRESENTED TO BECKJORD, MURLEY, AND NRR AND RES STAFF (a)
A SCHEDULE FOR SUBMITTAL AND REVIEW OF THE TOPIC PAPERS (b)
A REQUEST FOR NRC TO PROVIDE INTERIM GUIDANCE SO THAT SUBSEQUENCT WORK WILL BE ON TRACK (c)
A DOCUMENTED FINAL RESOLUTION w--
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_._____. __ _ _.,,,__,_ ~.,,,_____,__,, _ _
l THE SEVERE ACCIDENT RESOLUTION PROCESS CONSENSUS ON DEFINITION OF ISSUE RESOLUTION v
PRODUCE ARSAP 4
TOPIC PAPER v
REVIEW WITH CE & ITAG
~
AND MODIFY TOPIC PAPER v
CONDUCT NRC REVIEW AND INTERIM ANALYSIS / DESIGN GUIDANCE MODS.
A S
MY YES v
FINAL RESOLUTION DOCUMENTED BY NRC
0 TOPIC PAPER SETS -
SCHEDULE FOR SUBMITTAL TO CE SET 1. RESOLVED IDCOR/NRC ISSUES -
APPLICABILITY TO ALWRS (10/87)
SET 2. PLANT RESPONSE UNDER SEVERE ACCIDENT CONDITIONS (12/87)
SET 3. PROBABILISTIC METHODS (2/88)
SET 4. RISK REDUCTION METHODS (4/88)
SET 5. RISK RESULTS (6/88)
SET 6. APPLICATIONS OF SEVERE ACCIDENT ANALYSIS (9/88)
RESULTS EXPECTED FROM THE ARSAP/CE NRC SEVERE ACCIDENT ISSUE RESOLUTION PROCESS INCLUDE:
S CONCURRENCE ON IDENTIFICATION OF ISSUES S
CONCURRENCE ON TECHNICAL APPROACH AND CRITERIA FOR RESOLUTION S
INTERIM NRC GUIDANCE SO DESIGN CERTIFICATION CAN PROCEED S
RESOLUTION DOCUMENTATION S
TIMELY AND STABLE AND REGULATORY INTERPRETATION FOR CERTIFICATION
l e
ARSAP/CE NRC TECHNICAL INFORMATIVE EXCHANGE O
TECHNICAL INFORMATION EXCHANGE WITH NRC IS PROPOSED FOR:
9 SEVERE ACCIDENT ANALYSIS METHODOLOGY S
REVIEW AND INTERPRETATION OF EXPERIMENTS
- - - - -. - - -. - -.,,... -. - ~ - - -.
. - - -.,..,..,. -..,, - ~
BOTH NRC AND DOE /ARSAP WILL BENEFIT FROM TECHNICAL INFORMATION EXCHANGE TECHNICAL ISSUES S
THE MAAP AND MELCOR CODES ARE A FORMALIZED STRUCTURE FOR COMMUNICATING KNOWLEDGE, ASSUMPTIONS AND TECHNICAL DATA ABOUT SEVERE ACCIDENT PHENOMENOLOGY
- - - - ~.
BOTH NRC AND DOE /ARSAP WILL BENEFIT FROM TECHNICAL INFORMATION EXCHANGE (2)
MODELING S
CLEARER UNDERSTANDING OF EACH OTHERS' CODES AS THEY EXIST WILL BE OBTAINED G
PLANNED APPROACHES FOR FUTURE DEVELOPMENTS WILL BE CONFIRMED OR POSSIBLY ALTERNATIVE APPROACHES IDENTIFIED 9
INSIGHTS ON SELECTION OF EXPERIMENTS AND ANALYSIS OF RESULTS FOR BENCHMARKING THE CODES WILL BE DEVELOPED
BOTH NRC AND DOE /ARSAP WILL BENEFIT FROM TECHNICAL INFORMATION EXCHANGE (3)
INTEGRAL CODE COMPARSIONS S
NRC WILL HAVE A STANDARD PROBLEM COMPARSION OF MAAP PRIOR TO CE SUBMITTAL OF MAAP RESULTS IN THE SYSTEM 80+ CERTIFICATION 9
DOE /CE/ARSAP WILL GAIN INSIGHTS ABOUT PLANNED OR POTENTIAL MAAP MODIFICATIONS AND BENCHMARKING S
SOME DEGREE OF MUTUAL CONFIRMATION OF CURRENT MODELS AND RECENT MODIFICATIONS WILL BE OBTAINED
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OPPORTUNITITES FOR NRC FAMILIARIZATION WITH MAAP ARE INHERENT IN THE 1
CE/ARSAP NRC. INTERACTION PROCESS e
DURING THE INTERACTIONS ON S/A TOPIC SET 1 NRC QUESTIONS PERTINENT TO MAAP AND THE PROPOSED ISSUE RESOLUTIONS WILL BE ADDRESSED
- ARSAP PLANS FOR MAAP MODELING IMPROVEMENTS AND
~
BENCHMARKING WILL BE REVIEWED
- THE CODE CONFIGURATION QUALITY CONTROL PROCEDURE BEING FOLLOWED BY ARSAP IN DEVELOPING MAAP MODELS WILL BE PRESENTED
OPPORTUNITIES FOR NRC FAMILIARIZATION WITH MAAP ARE INHERENT IN THE ARSAP/CE NRC INTERACTION PROCESS (2?
S DURING THE INTERACTIONS ON S/A TOPIC SET 2 UNRESOLVED NRC QUESTIONS PERTINENT TO MAAP AND THE PROPOSED ISSUE RESOLUTIONS WILL BE ADDRESS S
NRC STAFF WILL BE PROVIDED WITH COPIES OF ALL TECHNICAL REPORTS ON ARSAP MODELING AND BENCHMARKING ACTIVITIES AS THEY ARE COMPLETED ALONG WITH PERIODIC BRIEFINGS IF DESIRED
.i 1
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OPPORTUNITIES FOR NRC FAMILIARIZATION WITH MAAP ARE INHERENT IN THE ARSAP/CE NRC INTERACTION PROCESS (3)
S PROPOSED TECHNICAL EXCHANGES ON MAAP AND MELCOR WILL ADDRESS SPECIFIC QUESTIONS ON THE TWO INTEGRATED ACCIDENT ANALYSIS CODES
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S A
SUMMARY
PAPER ON SEVERE i
ACCIDENT CODE CAPABILITY WILL BE ONE OF THE S/A TOPIC PAPERS S
INTERACTIONS WITH NRC STAFF IN SUPPORT OF CE WILL BE CONTINUED WHEN MAAP RESULTS ARE SUBMITTED FOR SYSTEM 80+
9 ARSAP ACTIVITES WILL BE COORDINATED WITH EPRI USERS' GROUP
POTENTIAL ARSAP TECHNICAL EXCHANGE WITH NRC EXPERIMENTS PROGRAMS INCLUDES e
PROVIDING NRC WITH REVIEW OF RESULTS, INTERPRETATIONS, ETC.
MADE BY ARSAP IN THE COURSE OF BENCHMARKING AND ISSUE RESOLUTION S
PROVIDING INPUT ON CURRENTLY PLANNED EXPERIMENTS WHICH COULD HELP PROVIDE CONFlRMATORY INFORMATION FOR ADVANCED LWRs WHILE NOT DETRACTING FROM GOALS FOR CURRENT LWRs e
PROVIDING INPUT ON POTENTIAL l
FUTURE EXPERIMENTS I
1 l
e i
SUMMARY
i
SUMMARY
DOE /CE/ARSAP IS PROVIDING ITS RESOURCES AND EXTENSIVE EXPERIENCE IN PRACTICAL ASSESSMENT OF SEVERE ACCIDENT ISSUES TO WORK WITH THE NRC TO RESOLVE ALWR SEVERE ACCIDENT ISSUES THIS WILL BE ACCOMPLISHED BY:
S CE/ARSAP ISSUE RESOLUTION PROCESS IN THE SYSTEM 80+
CERTIFICTION EFFORT S
SUPPORT OF THE EPRl/NRC INTERACTIONS ON THE ALWR REQUIREMENETS DOCUMENT S
TECHNICAL INFORMATION EXCHANGE ON METHODOLOGY AND EXPERIMENTS 4
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- -. -, - ~
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REMAINING AGENDA l'1'l TO IDENTIFY NRC PROGRAMS AND KEY STAFF IN AREAS PERTINENT OT ALWR SEVERE ACCIDENT ASSESSMENT, AND UNDERSTAND NRR -
RES INTERACTIONS l
l'2'I TO OBTAIN NRC VIEWS ON AND POSSIBLE APPROACHES FOR CONSIDERING SEVERE ACCIDENTS IN LICENSING / CERTIFICATION
~
REVIEWS I'3'i TO OBTAIN CONCURRENCE ON THE CE/ARSAP S/A ISSUE RESOLUTION PROCESS AND SCHEDULE
'i4'l TO OBTAIN NRC FEEDBACK ON THE PROPOSED TECHNICAL l
INFORMATION EXCHANGE
4 APPENDIX ARSAP PROGRAM STRUCTURE DETAILED S/A ISSUE RESOLUTION PROCESS AND INTERFACE WITH TOPIC PAPER SETS i
ARSAP WBS TASK INTERFACES Wils-2 WIIS-3 SEVEltE SEVEllE ACCIDEN T WBS-Il ACCIDiifJ1 ISSUE
- +-
IDE TJ11I IC A IlofJ ArJALYSIS EPill
& IIESOLUllON METilODOLOGY REQUIREMEN T S DOCUMErJT u
WilS-4 r
Pila MElllODOLOGY epi COOMW ACllVITIES Wits-S llEGUI AI OltY WBS-10
-> CE SYST EM BO -i CO MI'LI ATJ CE SUPPOllT i
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DEVELOPMENT OESIGrJS SUPPORT g
AND SUPPORT L___________________1____________________J g
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ARSAP PROGRAM STRUCTURE THE ARSAP PROGRAM IS STRUCTURED TO SUPPORT RESOLUTION OF SEVERE ACCIDENT ISSUES, CONSISTENT WITH THE NRC SEVERE ACCIDENT POLICY STATEMENT WBS 1.
MANAGEMENT AND PLANNING
- POLICY DEVELOPMENT
- PROGRAM MANAGMENT
~
- ORGANIZATION INTERFACES WBS 2.
SEVERE ACCIDENT ISSUE RESOLUTION 3
- ISSUE IDENTIFICATION
- TOPIC PAPER DEVELOPMENT
- ISSUE RESOLUTION AND DOCUMENTATION
ARSAP PROGRAM STRUCTURE (2)
WBS 3.
SEVERE ACCIDENT ANALYSIS METHODOLOGY
- SELECTION AND DEVELOPMENT OF ANALYSIS TOOLS REVIEW OF EXPERIMENTAL DATA AND RECOMMENDATIONS BENCHMARKING AND VALIDATION AND VERIFICATION WBS 4.
PRA METHODOLOGY AND APPLICATION CRITERIA
- GUIDANCE FOR USE OF PRA IN DESIGN
- GUIDANCE FOR REGULATORY APPLICATIONS OF PRA DEVELOPMENT OF EPRI FUNCTIONAL PRA'S DEVELOPMENT OF EPRI PRA GROUND RULES AND ASSUMPTIONS l
ARSAP PROGRAM STRUCTURE (3)
WBS 5.
REGULATORY COMPLIANCE ALTERNATIVES
- SUPPORT OF RISK BASED ASSESSMENTS OF INEFFECTIVE REQUIREMENTS PROPOSAL OF ALTERNATIVES
- SUPPORT OF VENDOR /EPRI EFFORTS WITH NRC WBS 6.
CERTIFICATION PROCESS DEVELOPMENT AND SUPPORT REGULATORY ASSISTANCE TO VENDOR CERTIFICATION EFFORTS WBS 7.
LESSONS LEARNED NOTEBOOK ANNUAL UPDATES l
\\
l l
l
ARSAP PROGRAM STRUCTURE (4).
WBS 8.
EPRI REQUIREMENTS DOCUMENT j
REVIEW, COMMENT, AND INPUT TO EPRI REQUIREMENTS DOCUMENT IN SEVERE ACCIDENT AREAS WBS 9.
EPRl/ VENDOR 600 MWe PLANT DESIGN AND 1
CERTIFICATION l
GE DESIGN (SBWR) REVIEW
- WESTINGHOUSE DESIGN (SPWR)
REVIEW
ARSAP PROGRAM STRUCTURE (5)
WBS 10. CE SYSTEM 80 PLANT DESIGN AND CERTIFICATION REVIEW OF SEVERE ACCIDENT ISSUES RELEVANT TO CE DESIGN j
DEFINITION OF SEVERE ACCIDENT SEQUENCES FOR ANALYSIS PERFORMANCE OF SEVERE ACCIDENT ANALYSIS
- SUPPORT TO SYSTEM 80 PRA
- ASSESSMENT OF SEVERE ACCIDENT MITIGATION FEATURES
- SUPPORT OF FINAL DESIGN APPROVAL AND NRC REVIEW PROCESS
ARSAP PROGRAM STRUCTURE (6)
- MAAP USER SUPPORT
- ASSISTANCE IN DEVELOPMENT AND APPLICATIONS OF MAAP MODEL ANALYSIS OF FISSION PRODUCT PARTICLE SIZE -- EFFECT ON SUPPRESSION POOL DF
- SUPPORT FOR PRA SEISMIC ANALYSIS
- SUPPORT FOR ABWR ATWS ANALYSIS i
i
\\NBS 12. WESTINGHOUSE APWR PLANT SUPPORT MONITORING OF ACTIVITES WBS 13. CHERNOBYL
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TOPIC PAPER SET 1:
RESOLVED IDCOR/NRC ISSUES APPLICABILITY TO ALWRS (SINGLE PAPER)
S REACTOR COOLANT SYSTEM NATURAL CIRCULATION I'lDCOR ISSUE 2)
S IN-VESSEL STEAM EXPLOSIONS AND ALPHA MODE FAILURE lllDCOR ISSUE 7)
S EX-VESSEL HEAT TRANSFER MODELS FROM MOLTEN CORE TO CONCRETE 1lDCOR ISSUE 10)
S FISSION PRODUCT RELEASE PRIOR TO VESSEL FAILURE llDCOR ISSUE 1)
S RELEASE MODEL FOR CONTROL ROD MATERIALS I:lDCOR ISSUE 3) i e
FISSION PRODUCT AND AEROSOL DEPOSITION IN RCS AND CONTAINMENT lIDCOR ISSUES 4 AND 12) 1
~
1 TOPIC PAPER SET 1:
UNRESOLVED IDCOR/NRC i
ISSUES APPLICABILITY TO ALWRS l 2)
S EX-VESSEL FISSION PRODUCT RELEASE IDURING CORE -
CONCRET8 INTERACTIONS'l l'lD CO R ISSUE 9)
S REVAPORIZATION OF FISSION PRODUCTS IlDCOR 11) e SECONDARY CONTAINMENT PERFORMANCE I,lDCOR ISSUE 16) 9 MODELING OF EMERGENCY RESPONSE I,lDCOR ISSUE 14)
- l
TOPIC PAPER SET 2:
PLANT RESPONSE UNDER SEVERE i
ACCIDENT CONDITIONS l
9 IN-VESSEL HYDROGEN GENERATION i!DCOR ISSUE 5) l S
CORE MELT PROGRESSION AND VESSEL FAILURE lllDCOR ISSUE 6) 9 DIRECT CONTAINMENT HEATING BY EJECTED CORE MATERIALS IlDCOR ISSUE 8)
S CONTAINMENT PERFORMANCE lllDCOR ISSUE 15) e HYDROGEN IGNITION AND BURNING (IDCOR ISSUE 17)
S DEBRIS COOLABILITY l'IDCOR ISSUE 10)
I I
I
TOPlc PAPER SET 3:
PROBABILISTIC METHODS e
EXTERNAL EVENTS 9
HUMAN FACTORS -- REQUIRED OPERATOR ACTIONS
)
e HUMAN FACTORS --
UNEXPECTED OPERATOR ACTIONS WITH POTENTIAL ADVERSE EFFECT e
HUMAN FACTORS --
QUANTIFICATION OF HUMAN
)
ERROR PROBABILITIES
~
e SUCCESS CRITERIA e
COMMON CAUSE FAILURES S
IDENTIFICATION OF DOMINANT SEQUENCES 1
i I
l TOPIC PAPER SET 4:
RISK REDUCTION MEASURES i
e ESSENTIAL EQUIPMENT PERFORMANCE [lDCOR ISSUE 18')
S SEVERE ACCIDENT MANAGEMENT PLANT EQUIPMENT /INFORMATION SYSTEM CAPABILITY S
SEVERE ACCIDENT MANAGEMENT CONDITIONS FOR SAFE STABLE STATES 1
l 9
MITIGATION FEATURES i
i
TOPIC PAPER SET 5: RISK RESULTS e
CONSENSUS ON INTEGRATED SEVERE ACCIDENT ANALYSIS CODE CAPABILITY, VALIDATION AND APPLICATION e
USE OF TMI-2 EXAMINATION 4
RESULTS ON CODE VALIDATION e
SAFETY GOAL IMPLEMENTATION INTERPRETATION OF GOALS AND USAGE OF PRA RESULTS IN COMPARSION WITH GOALS, INCLUDING INTERPRETATION OF UNCERTAINTIES e
UNCERTAINTIES IN PLANT RISK -
EFFECTS OF SYSTEM ANALYSIS UNCERTAINTIES
I l
TOPIC PAPER SET 5:
RISK l
RESULTS J21 I
e UNCERTAINTIES IN PLANT RISK -
EFFECTS OF UNCERTAINTIES IN SEVERE ACCIDENT ANALYSIS (PHENOMENOLOGY, PLANT DAMAGE STATES, METHODOLOGY)
S UNCERTAINTIES IN PLANT RISK -
- TREATMENT OF PROPAGATION OF UNCERTAINTIES 9
UNCERTAINTIES IN PLANT RISK -
- COMPLETENESS OF CHOICE OF SEQUENCES AND CUTOFF PROBABILITIES
TOPIC PAPER SET 6:
APPLICATIONS OF METHODS e
EFFECT OF SEVERE ACCIDENT ISSUES ON REGULATIONS --
PROBABILISTIC DESIGN BASES S
EFFECT OF SEVERE ACCIDENT ISSUES ON REGULATIONS ASSESSMENT OF REGULATORY COMPLIANCE ALTERNATIVES S
EFFECT OF SEVERE ACCIDENT ISSUES ON REGULATIONS --
EFFECTIVENESS OF TECHNICAL SPECIFICATIONS P
l
e-+-sme s.
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+
a Aw
= = ~~
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- -===---'-
THE DIRECT CONTAINMENT HEATING TOPIC PAPER IS AN EXAMPLE OF ISSUE TREATMENT ISSUE DESCRIPTION AND IMPORTANCE DEFINITION CORE DEBRIS DISPERSED IN CONTAINMENT AT VESSEL FAILURE IMPORTANCE CONTAINMENT COULD Fall IMMEDIATELY AFTER VESSEL FAILURE AND COULD OCCUR LARGE SOURCE TERM 1
i e
._-----.----,-r-
,----m-w,
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THE DIRECT CONTAINMENT HEATING TOPIC PAPER IS AND EXAMPLE OF ISSUE TREATMENT [2)
ISSUE STATUS AND TECHNICAL BASIS IDCOR ACTIONS REVIEWED EXISTING CAVITY CONFIGURATIONS AND ESTIMATED THE EFFECT ON DEBRIS DISPERSAL.
DEVELOPED SCREENING CRITERIA.
PERFORMED EXPERIMENTS.
i NRC ACTIONS PERFORMED EXPERIMENTS AND ANALYSES OF DEBRIS DISPERSAL AND DIRECT HEATING.
QUESTIONS EFFECT OF REALISTIC GEOMETRIES ON ENTRAINED DEBRIS.
~
THE DIRECT CONTAINMENT i
HEATING TOPIC PAPER IS AN EXAMPLE OF ISSUE TREATMENT [3)
ISSUE STATUS AND TECHNICAL BA. SIS
[2)
NRC POSITION DEMONSTRATE THAT EACH CAVITY IS ACCURATELY REPRESENTED BY MILLSTONE AND AMOUNT OF DISPERSED DEBRIS TO CONTAINMENT VOLUME IS INSIGNIFICANT.
RECENT RESULT EFFECT OF DISPERSED DEBRIS ON FISSION PRODUCT RELEASE MAY BE POTENTIALLY SIGNIFICANT (NUREG 1150 SUBISSUE).
~
...a THE DIRECT CONTAINMENT HEATING TOPIC PAPER IS AN EXAMPLE OF ISSUE TREATMENT (4'y TECHNICAL APPROACH TO RESOLUTION RESOLUTION DESIGN CRITERIA REQUIRES DESIGN LIKE MILLSTONE.
PROVIDE GEOMETRIC DESIGN CRITERIA FOR CAVITY.
DEVELOP MODEL FOR FISSION PRODUCT RELEASE.
TAKE ADVANTAGE OF RCS DEPRESSURIZATION SYSTEM.
RELATED WORK RECOMMEND TEST OF DEBRIS DISPERSAL FROM MILLSTONE CAVITY TO RESOLVE ISSUE.
PERFORM STUDIES OF THE EFFECT OF DEPRESSURIZATION ON CONDITION AT VESSEL FAILURE.