ML20217P137
| ML20217P137 | |
| Person / Time | |
|---|---|
| Issue date: | 04/02/1998 |
| From: | Coe D NRC (Affiliation Not Assigned) |
| To: | Borchardt R NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9804090327 | |
| Download: ML20217P137 (26) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
'4 WAsHINeToN, D.C. SOASH001
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April 2,1998 i
MEMORANDUM TO:
R. W. Borchardt, Chief inspection Program Branch Office of Nuclear Reactor Regulation
{
^hrald R. Klingler, Acting Chief THRU; Operating Reactor Program section inspection Program Branch FROM:
Douglas H. Coe Senior Reactor Analyst t
?
SUBJECT:
SUMMARY
OF PRA PRACTICES INFORMATION EXCHANGE MEETING BETWEEN INPO AND NRC STAFF ON MARCH 26,1998 Subject meeting was conducted as an open public meeting in the Atlanta Federal Center, Atlanta, Georgia. Attendance at this meeting is shown on attachment 1.
The meeting was divided into three parts: an NRC-led tiiscussion on our initiatives related to the use of risk analysis tools and information in our inspection activities, an INPO-led discussion on INPO initiatives related to their assessment of licensee uses of PRA, and a~ third part (closed to the public) for an INPO presentation on the proprietary Equipment Performance and Information Exchange (EPIX) database and software. The EPIX program is intended to replace the NPRDS function of industrywde access to nuclear plant equipment failure informaton and to provide the NRC staff with plant-specific reliability data for risk-informed assessments of licensee performance.
The meeting provided a valuable opportunity for the discussion of common issues related to the use of risk information forinspection and assessment programs. Similar future working-level meetings i
could effectively be conducted coincidentally with the periodic senior management meetings between NRC and INPO management.
Mr. Luis Reyes, Region 11 Administrator, opened the meeting with brief introductory remarks and a summarization of recent speeches by Chairman Jackson regarding the Commission's intent to expand the use of PRA-related methods within the agency. The NRC-led discussion (see attachment 2) focused on the objectwos of the inspection program, the implementation of the Senior Reactor Analyst program, and recently updated inspection guidance and inspector training in the use of PRA information.
-[
The INPO-led discussion (see attachment 3) highlighted several interesting points:
INPO is supporting two full time staff persons having technical PRA expertise gained from prior experience and INPO " reverse loan" assignments to licensee PRA group a.
individuals typically perform a 1-day PRA
- pre-visit" prior to regularly scheduled INPO -
3 evaluations. These pre-visits develop information for the use of the INPO evaluation team, regarding the licensee's use of PRA.
EC file CElffEB COPY wh+2p[/7 Q.13 y p /4 -f 9004090327 980402 PDR ORG EPSINPO
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- b. During its evaluations of licensees, INPO assesses the extent to which a licensee utilizes PRA in its actndbes and the rigor of programmatic controls in place if and when PRA is used.
INPO has made a conscious decision not to evaluate technical adequacy of licensee PRA methods, relying instead on the activities of the industry owners groups to develop PRA certification standards. This also means that INPO does not assess the adequacy of PRA used for regulatory purposes (e.g., as part of the basis for a license amendment request).
- d. INPO expects all licensees to use PRA at a minimum in support of 1) training and 2) for equipment outage configuration control. This is due to INPO's belief that licensee performance in these areas has the most direct risk-impact on the plant and therefore should be the most risk-informed.
- e. In 1993, INPO raised a question with licensees as to whether they might consider using PRA methods to evaluate the risk of accident sequence end-states that do not progress all the way to core damage (i.e., "altemate end-states"). Such end-states might include BWR emergency depressurization, and could result in large economic burdens. To date, INPO is not aware of any licensee formally using PRA in this manner, f.
If a licensee requests a PRA assist visit from INPO, it is typically conducted by using personnel currently working in other industry PRA groups.
Please let me kr ow if you have any questions about this meeting.
Attachments: 1. Attendance List
- 2. NRC presentation slides 1
- 3. INPO presentation slides (open meeting portion) l cc: F. Gillespie
' M. Rubin i
P. Baranowsky
. M. Cunningham
-)
M. Cullingford i
G. Pany
- Distribution:
D. Coe, NRR T. Hiltz, NRR A. Ramey-Smith, RES (T-10-E-50)
P. Wilson, NRR (0-10-E-4)
S. Mays, AEOD (T-4-A-9)
R. Bemhard, Region il W. Rogers, Region 11 L. Reyes, Region 11
)
J. Trapp, RI T. Shediosky, RI
'l S. Burgess, Rlil M. Parker, Rlli 1
J. Shackelford, RIV W. Jones, RIV PDR ACRS OGC' D. Matthews, NRR (0-10-H-5) i DOCUMENT NAME: G:\\SECY2\\lNPOSUM.DHC To receivi e copy of this document, indicate in the bor "C" = Cop f without enclosures "E" = Copy with enclosures "N" = No copy OFFICE ~
PIPB DISP _ sJ B l
l l
l NAME DHCoe bW//C -
DATE 04/O 2 498 OFFICIAL RECORD COPY
PRA PRACTICES INFORMATION EXCHANGE MEETING BETWEEN INPO AND NRC STAFF ON MARCH 26,1998 The NRC attendees were as follows:
D. Coe, HQ USNRC T. Hiltz, HQ USNRC A. Ramey-Smith, HQ USNRC P. Wilson, HQ USNRC S. Mays, HQ USNRC R. Bembard, Region 11, USNRC W. Rogers, Region 11, USNRC L. Reyes, Region ll, USNRC (opening remarks) i The INPO attendees were as follows:
Joe Solymossy, INPO Tony Brooks, INPO Bruce Logan, INPO Bruce Keener, INPO Glen Masters, INPO Members of the public present during the open portion of the meeting were as fc!Iows:
i T. Pietrangelo, NEl i
D. Perkey, NUS Information Services 1
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