IA-86-263, Annotated Notes for Discussion W/K Stadie Re IAEA & Nea & PWG-1 Activities
| ML20212M192 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1986 |
| From: | Heltemes C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Hauber R NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP) |
| Shared Package | |
| ML20212M158 | List:
|
| References | |
| FOIA-86-126, FOIA-86-127, FOIA-86-131, FOIA-86-166, FOIA-86-201, FOIA-86-209, FOIA-86-263, FOIA-86-80, FOIA-86-82 NUDOCS 8608250407 | |
| Download: ML20212M192 (9) | |
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f g,v NOTE T0: Ron Fauber, IP 'O- j f FROM: C. J. Heltemes, Jr., Director ' b Office for Analysis and Evaluation of Operational Data
SUBJECT:
NOTES FOR DISCUSSION WITH K. STADIE
- 1. The PWG-1 activities seem to be in good shape. The technical meetings have focused on generic issues of wide interest. The NEA Incident Reporting System is well supported and.is being used for all countries.
One uncertainty is the new Chairperson, Ms. Dupuis from France. She is new to the PWG.
- 2. I believe .the ed for better communication and cooperation ~ ~ ~
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- a. Both IAEA and NEA are implementing Incident Reporting Systems. The objective should be to drive these two systems together so that in reality there is only one system - common reporting criteria, common format and content of reports, and distribution to all countries.
NEA has not been present in past IAEA weetings on the IAEA-IRS.
There seems to be little or no communication by IAEA/NEA staff to achieve commonality.
A series of meetings are planned by IAEA on how to strenghten the IAEA-IRS. Will NEA work to assure these meetings are productive and useful?
- b. Both IAEA and NEA sponsor techair.al meetings, and there is one joint meeting per year on technical subjects.
NEA schedules technical sessions during PWG-1 discussions rather than during ,ioint meetings.
IAEA schedules technical ineetings that apparently overlap NEA -
meetings.
For example, IAEA is sponsoring a large study of scram frequency, complete with questionnaires. Several IAEA meetings on this subject were held. The IAEA study is due out in the next few months. NEA is sponsoring a large international meeting on scrams in April (Tokyo) and all countries have been requested to fill out a different questionnaire. 8608250407 e60:3'.2 PDR FOIA GAPDE86-80 PDR h,
R. Hauber --
IAEA has scheduled a meeting on valves in Ma.v. This subject has been covered in previous NEA PWG-1 meetings.
- c. There seems to be no overall coordinated plan on defining problems reouiring attention and addressing these problems through well-focused and coordinated meetings. Since neither the U.S. nor other countries can attend all meetings, there is an inefficient and incomplete sharing of information. This would seem to be a subject where INSAG could provide invaluable direction and assistance.
Please let me know if I can provide any additional information or assistance.
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(.J . e eme Jr., Director
(@ ce for Analysis and Evaluation of Operational Data cc: J. Roe
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' s PWG-1 (Human Factors)
- NRC decision to pull out of the human factors work at Halden beginning in 1987 ($700K), if and when it becomes known to Stadie, will cause a strong reaction from him.
- PWG-1 and the Halden Project recently agreed to exchange information on computered control rooms and the man-machine interface.
NRC recently agreed to host a CSNI Specialists Meeting on Training in the Spring of 1987. Co-sponsors: NRC, INPO, ANS/ ENS and CSNI.
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B. Sheron 1/30/86 CSN!-FUTURE DIRECTIONS FOR PWG-2
- WHAT SHOULD BE THE PWG 2 PROGRAM FOR THE NEXT SEVERAL YEARS 7 i
- conglete work on code assessment matrix
- continue thenmal-hydraulic standard problems ,
- continue and complete ex-vessel severe accident T/H behavior standard l problems !
core / concrete reactions
- H2 Production & dispersion
- additional standard problems in severe accident areas
- containment performance containment loads /
WHAT SHOULO 8_E THE RELATION 5HI_P__8ETWEEN PWG 2 AND_THE_OTHER PWGfS There is currently no defired relationship between PWG 2. PWG 4 and PWG 5.
As such. there is an overlap in activities (e.g., both groups are working on scane aspects of core-concrete interactions). Sheron has repeatedly tried to have PWG-2 coordinate its " interactive" activities with the other PWGs but has not succeeded yet.
HOW DOES PWG-2 H_ELP NRC7 code assessment matrix developed by PWG-2 very useful to RES in developing NRC's code assessment matrix international standard problems provide source of unique experimental j data from foreign facilities. In era of declining budgets, this data becomes more valuable to NRC.
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WHAT DOES NRC WANT _FROM mig-27 finish work on code assessment satrix continue international standard prvblem program (thermal-hydraulic only, no fuel problems needed at this time)
NRC is currently developing thermal-hydraulic computer codes uncertainty assessment methods. We very much would like the international cosaunity, through PW6-2 to review and comment on these methods.
- - RES would like European participation ($) in the " thermal / hydraulic technical center of excellencra (INEL)"
. access to severe accident data free foreign facilities.
6 I
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.6 PRIMARY OBJECTIVES OF THE NRC THROUGH PWG-3
- 1. CONTAlteENT ESTABLISH INTERNATIONAL COOPERATION ON AND FORUM FOR ANALYTICAL PREDICTION AND ANALYSIS OF RES'S CONTAINMENT EXPERIMENTS.
- 2. AGING DEVELOP PWG-3 COOPERATION AND PROGRAM IN AGING AND LIFE EXTENS '
MA y S AND COMPONENTS OF PRIMARY SYS b .
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DRIVE OECD-NEA TO FORM A SENIOR GROUP TO COORDINATE AND POSSIBLY DIRECT AGING AND LIFE EXTENSION EFFORTS IN EMBER COUNTRIES:
O FORMULATE QUESTIONS 0 DEVELOP RESEARCH PROGRAMS 0 ESTABLISH LFE EXTENSION CRITERIA
- 3. EPFM CONTINUE TO GET INTERNATIONAL INPUT TO AND CRITIQUE OF OUR EPFM TEST AND CRITIQUE OF OUR EPFM TEST AND ANALYSIS METHODS.
14 . 10E CONTINUE PISC-III EFFORTS TO DEMONSTRATE IMPROVED ISI CAPABILITIES ,
AND ACCEPTABLE UT METHODS FOR INSPECTION OF CAST AND WROUGHT STAINLESS STEEL.
PWG-3 Future Program as proposed by Consultant"s Meeting 25 November 1985, OECD, Paris Non-Destructive Examination o PISC-III International Recommendation for Improved NDE '
o Continuous Monitoring for Defects and Plant Service Life o Eddy Current NDE Fracture and Related Subjects o Elastic-Plastic Fracture Mechanics Reform EPFM Sub Group o Residual Stress I.S.P.
o Stress Analysis I.S.P.
o Steam Generator Tube Plugging Criteria Analysis o Crack Arrest
,, o Safety Assessment of Cracks o Vessel Failure Mode and Probability o Environmentally Assisted Cracking o Welding Containment o Program to be developed Aging, Degradation and Life Extension o Program to be develo' ped o Specialists Meeting, Stockholm, 1987 h
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T. P. Spels 1/30/86 CSNI-FUTURE DIRECTIONS FOR PWG-S
- 1. WHAT S MULD BE THE PWG S PROGRAM FOR THE NEXT SEVERAL YEAR $f complete work on survey of PRA methods, based upon selected plant-specific PRA examples.
complete the survey of applications of PRA to reactor regulation, design, or operation in CSNI member countries.
Reliability Assurance / Reliability Engineering status: startina A workshop will be held in May '86 with invited speakers
- (primerfly from utilities) to describe their success (or failure)
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in using PRA and/or reliability engineering in operations, safety management, and in dealing with regulations. The subsequent direction of this effort will be decided following this meeting.
Review of Safety Goal Activities
_S_tatus : Continuing activity involving exchange of informatien on safety goals and implementation related issues.
Human Intervention in Severe Accidents; interaction with PWG No. 1 effort just starting.
- 2. WHAT SHOULD BE THE RELATIONSHIP BETWEEN PWG 5 AND THE OTHER PWG's?
This group by its very nature (RISK ASSESSMENT) depends to varying degrees on the other PWGs for input into its activities; e.g., it
! depends on: PWG #1 for reliability data of components, systems, etc.,
as well as human factor related info; PWG #2 for thenmal-hydraulic analysis, especially frun severe accidents which are being dealt by the PWG #2's task force on ex-vessel thermal hydraulics, and on PWG #4 for source term and environmental consequences.
But overall this dependence is a voluntary one and no PWG (including this one) has the means (e.g., via its charter) to get input from: the .
other groups. In general there is some overlap between the groups especially in "multidisciplinary" issues; e.g., both PWGs 2, 4 and S
- * ' "91/:M545 14 5B FO.C12 EN!r5 are involved in severe accident related efforts and all of them have j proposed programs that will further increase their involvement and also lead to more overlap. I reconsend that this area should be included in the agenda of the next CSNI meeting for resolution.
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- 3. HOW DOES PWG-5 HELP _NR_C?
availability of data, not noms 11y available in one's own country.
automatic peer review of data, its usefulness, specific applicabilities and limitations.
- inmediate availability of all relevant information in an evolving technology idevelopment and use of_ PRA in regulatory decision seking).
- development of consensus, i
- 4. WHAT DOES NRC WANT FROM PW6-5?
Even though NRC has been the leader ir the development and use of PRA techniques starting with WASH-1400, most countries with advanced nuclear programs have in recent years began to develop and use PRA in 4
their prograss; this us'e has lead to the. development of improved l methods, increases in the data base, and is also exploring more sophisticated uses and applications ranging from decisions involving normal plant operations to the management of severe accidents.
l Therefore it benefits NRC to have access not only to the additional l data that is being developed, but to the methods, the logic of their use and limitations, etc. this is most true for the next few years l
when NRC will be implementing the Commission's severe accident policy and safety goals; in addition, the concensus that is derived with the other CSNI countries is these areas help us with our Cossaission, the ACR$ and the public in general.
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