ML19341C462
| ML19341C462 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/06/1981 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19341C463 | List: |
| References | |
| NUDOCS 8103030550 | |
| Download: ML19341C462 (7) | |
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e UNITED STATES 0,,
NUCLEAR REGULATORY COMMISSION p'
n w AsHINGTON, D. C. 20958
.o February 6,1981 Docket No. 50-165 LICENSEE:
Consumers Power Company FACILITY:
Big Rock Point Plant
SUBJECT:
SUMMARY
OF MEETING HELD ON JANUARY 19, 1981 TO DISCUSS THE PROBABILISTIC RISK ASSESSMENT PROGRAM BEING CONDUCTED BY CONSUMERS POWER COMPANY FOR THE BIG ROCK POINT PLANT On January 19, 1981, a meeting was held in Bethesda, Maryland with representatives of Consumers Power Company and their consultants.
A list of attendees is enclosed (Enclosure 1). The purpose of the meeting was to provide the NRC staff with an overview of the Probabilistic Risk Assessment (PRA) Program being conducted by Cc,nsumers Power Company for the Big Rock Point Plant.
As stated during the meeting, the purpose of the PRA is to " employ the techniques of probabilistic risk assessment to support the continued safe operation of the Big Rock Point Nuclear Plant." The scope, approach, methodology, and data sources used in the PRA were summarized.
Copies of the viewgraphs used in the presentation are shown in Enclosure 2.
The results of the PRA were just recently submitted to the licensee by the contractor (SAI); accordingly, the licensee had not reviewed the report and the results should be considered preliminary.
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Sabotage and detailed quantification of the probability of failure to scram were excluded from the scope of the PRA. Values for the probability of failure to scram were taken from NUREG-0460. The NRC staff stated that the licensee should provide a basis as to why the methods used in NUREG-0460 are applicable to the Big Rock Point Pl ant.
The PRA includes the effect of potential modifications on reducing the total core damage frequency. A preliminary qualitative comparison was made of Big Rock Point risk with the decision rules proposed in NUREG-0739, "Ar, Approach to Quantitative Safety Goals for Nuclear Power Plants." The preliminary results show that for the potential post-modification status, most of the hazards states fall below the NUREG-0739 goal level.
For the case of large scale uncontrolled release from the containment (given a large scale fuel melt), these preliminary results fall between the goal and limit fur most sequences.
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l The total core damage frequency for ATWS for various modifications was also discussed. The approach that the licensee intends to use for evaluating the utility of a containment shield wall was also summarized as shown in Enclosure 2.
The licensee intends to review the PRA report prepared by SAI and to discuss the results at another meeting sometime in March.
0)a% A. fsahr-Walter A. Paulson. Project Manager Operating Reactors Branch #5 Division of Licensing Enclosures :
As stated cc w/ enclosures:
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Mr. David P. Hof fman February 6,1981 cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Conparty Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Conparty Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal Esq., Chairman U. S. Nuclear Regulatory Comission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Charlevoix Public Library
'ioute 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 4B103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Off, ice of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Director, Criteria and Standards Mr. Jim E. Mills Division Route 2, Box 108C Office of Radiation Programs Charlevoix, Michigan 43720 (ANR-460)
U. S. Environmental Protection Thomas S. Moore Agency Atomic Safety & Licensing Appeal Board Washington, D. C.
20460 U. S. Nuclear Regulatory Comission Washington, D. C.
20555
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Mr. David P. Hoffman February 6,1981 CC r.
Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Ms. JoAnn Bier 20.4 Clinton Street
' Charlevoix, Michigan 49720 e
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LIST OF ATTENDEES i
W. Paulson NRC D. Leaver Sci. Appl., Inc.
A, Larner NRC D.-Blanchard CPCo P, Wood SAI C. Graves NRR i
W. Hodges.
NRR F. Eltawila NRR D. Hoffman CPCo D.'.VandeWall e CPCo K. Brienzo CPCo G. Withrow CPCo F. Skopec NRR D. Collins NRR H. Ornstein NRC D. Crutchfield NRC W. Vesely NRC A. Thadani NRC a
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