ML20125C645

Notifies of 791025 Meeting W/Utils to Discuss Probabilities Assessment of Station Blackout at Facilities & to Establish Recommended Approach for Applicability to All Affected Plants

ML20125C645
Person / Time
Site:	Crystal River, Cook, Zion  File:ZionSolutions icon.png
Issue date:	10/23/1979
From:	Gamill W, Gammill W Office of Nuclear Reactor Regulation
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR NUDOCS 8001110079
Download: ML20125C645 (3)

Text

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t'.EMORAND'JM FOR: Darrell G. Eisenhut, Acting Director k. Yf' Division of Operating Reactors M>

" ROM: William P. Ganmill, Acting Assister.: Director fc-  !

Operatirig Reactor Projects i Division of Operating Reactors l

SUBJECT:

FORTHCOMING MEETING WITH I'4DI ANA AND MICHIG'N ELECTRIC CO. , COMM0'r.4EALTH EDISON CO. , AND FLORIDA P0.4ER CORP.

ON STATION BLACVDUT FOR D. C. COOK UNIT fio. 2, ZION STATION UNIT NOS.1 AND 2, AND CRYSTAL RIVER UNIT NO 2 Date and Time: Thursday, October 25, 1979 9:00 am Locaticn: Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Building i Bethesda, Maryland Room P-500

Purpose:

To discuss the basis, results, and implications of a probabilistic assessment of station blackout (loss of '

offsite power, failure of diesel generator and AC l

dependency for auxiliary feedwater systems) for the '

Cook 2, Zion 1 & 2, and Crystal River 3 facilities and establish a recommended approach for applicability to all affected plants.

Participants:

NRC EPRI A. Schwencer P. Baranosky E. Zabrosky, et al .

R. Reid F. Rowsome i D. Wigginton M. Aya ck AIF-Daner's Group I E. Reeves e J. Ward, et al.

M. Fairtile (S. D.Hanau' Ros V' r P. Matthews G. Lainas I M'.E C W. Russell E. Jordan R. Jurgensen, et al. i 1

l CEC FPC F.~ Pet ;. l e s , e t al . E. Si p:o , et al

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Willian P. Ga-ill , Actin; Msistant l Director 9 ps sti : r-"r  ;

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$W DRAFT AGENDA: NRC/INDUS RY MEETING ON STATION BLAC.. JUT October 25, 1979 9:00 a.m.

Attendees: NRC: Probabilistic Analysis Staff, Office cf Nuclear Regulatory Research Office of Nuclear Reactor Regulttion Industry: Commonwealth Edison (Zion)

Florida Power Corp. (Crystal River) l Indiana Michigan Electric Co. (DC Cook)

NSAC/EPRI AIF ,

Background .

The Probabilistic Analysis Staff has developed a rough estimate of the expected frequency of core damage via loss of offsite power, failure of all emergency diesel generators, and failure of the auxiliary feedwater systems in PWR's, with mostly plant specific failure rate data. The results suggest that there is a wide variation in risk from plant to plant and that the WASH-1400 reference PWR plant is among the lowest risk plants. The failure rate data used is subject to verification and may not fully reflec t present plant conditions .

The meeting is called to alert the industry to the problem and to communicate our needs for additional data with which to verify the calculation, assess the urgency l of the problem for those plants with the highest estimated frequecy, and to discuss I means of improvement.

Agenda 9:00 - 9:05 NRR Introduction - A. Schwencer 9:05 - 9:35 Pat Baranowski (PAS /RES) - Description of the Analysis 9:50 - 10:20 Frank Rowsome (PAS /RES) - Risk implications of the results, data requirements to refine the estimate and assess urgency, and avenues for quick fixes.

10:20 - 10:30 Break 10:30 - 11:30 Joint RES/NRR/ Industry discussion of the above three plants as typical examples of this potential problem.

11:30 - 12:00 Joint RES/NRR/NSAC/AIF discussion of the generic issue.

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