ML20066K127

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Discusses Review of Draft Pra.Review Revealed Two Significant Areas in Assessment Which Were Not Treated Appropriately
ML20066K127
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/24/1982
From: Boyer V
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NUDOCS 8211290411
Download: ML20066K127 (4)


Text

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,n PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O'. BOX 8699 PHILADELPHIA. PA.19101 (215)841-4500 V. S. DO Y ER SR. V8C E PRESIDE NT November 24, 1982 nucoEaR eowE R Mr. Darrell G. Eisenhut Division of Licensing Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Washington, DC 20555 Ref:

1)

Board Notification No.82-108, Memo for the Atomic Safety and Licensing Board for Limerick Generating Station, Units 1 and 2 From:

Thomas M. Novak, Asst. Director for Licensing, Division of Licensing -

Dated:

October 27, 1982 2)

Limerick Generating Station, Probabilistic Risk Assessment, throuah Revision 5, September 1982

Dear Mr. Eisenhut:

l We have undertaken a review of the draft, "A Review of the Limerick Generating Station Probabilistic Risk Assessment," by Brookhaven National Laboratory which we received by reference 1.

Our review has disclosed a number of areas in the assessment which we do not believe were treated appropriately.

Two issues which appear to be of significance to the overall evaluation are:

1) the initiating frequency for the Loss of Off-site Power (LOOP) and 2) the evacuation modcl used in the analysis.

For Loss of Off-site Power considerations, the Limerick PRA (reference 2) used data baF3d on actual experience of the local electrical power systems round the Limerick site.

The Brookhaven analysis, on the other hand, used a national data base to derive its estimate for the initiating frequency.

Philadelphia Electric recog-nized the importance of a reliable off-site electrical system at the time of the siting and early design stages of Limerick, and we firmly j

believe that the present design provides the highest order of reli-ability.

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E November 24, 1982 2

Mr. Darrell G. Eisenhut For the evacuation model, the Limerick PRA utilized the same methods as used in NASH-1400 in accordance with instructions from the NRC.

Brookhaven, on the other hand, used a significantly different model.

Detailed comments are presently being developed relating to the above and other areas of the Brookhaven analysis.

We suggest a meeting in early December to discuss with you and BNL the results of our review.

Sincerely, cc:

(see attached service list) 4 1

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cc: Judge Lawrence Brenner Judge Richard F. Cole Judge Peter A. Morris Troy B. Conner, Jr., Esq.

Ann P. Ilodgdon Mr. Frank R. Romano Mr. Robert L. Ar.thony Mr. Marvin I. Lewis Judith A. Dorsey, Esq.

Charles W. Elliott, Esq.

Mr. Alan J. Nogee Robert W. Adler, Esq.

Mr. Thomas Gerusky Director, Pennsylvania Emergency Management Agency Mr. Steven P. liershey James M. Neill, Esq.

Donald S. Bronstein, Esq.

Mr. Joseph 11. White, III Dr. Judith 11. Johnsrud Walter W. Cohen, Esq.

Robert J. Sugarman, Esq.

Mr. W. Wilson Goode Atomic Safety and Licensing Appeal Board Atomic Safety and Licensing Board Panel Docket and Service Section l

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