ML20235P279

Forwards Rept on Pilgrim Station Safety Enhancements, Per NRC .Rept Provided Detailed Description of Safety Enhancement Program Hardware Changes That Util Voluntarily Elected to Implement

ML20235P279
Person / Time
Site:	Pilgrim
Issue date:	07/08/1987
From:	Bird R BOSTON EDISON CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20235P281	List: ML20235P279 ML20235P283
References
87-111, NUDOCS 8707200428
Download: ML20235P279 (2)

Text

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BOSTON EDISON Executive offices 800 Boylston Street Boston, Massachusetts 02199 Ralph G. Bird July 8, 1987 Senior Vice President - Nuclear BECo Ltr.87-111 Mr. Steven A. Varga, Director Division of Reactor Projects, I/II 2 United States Nuclear Regulatory Commission ]

Hashington, D. C. 20555 l License DPR-35 Docket 50-293 INFORMATION REGARDING PIIGRIM STATION SAFETY ENHANCEMENT PROGRAM

Reference:

NRC Letter, Proposed Enhancement to the Mark I Containment -

Pilgrim Station, dated April 30, 1987

Dear Mr. Varga:

As agreed during July 1, 1987 discussions between Frank Miraglia, USNRC, and John Fulton, Boston Edison Company (BECo), we are submitting this response to your letter to BECo dated April 30, 1987. Enclosed for your information is a detailed description of the Safety Enhancement Program (SEP) hardware changes that BECo has voluntarily elected to implement for Pilgrim Nuclear Power Station (PNPS). The description of procedural changes and personnel  !

l training will be furnished under separate cover. A current implementation l schedule for the SEP modifications will also be furnished separately. A )

condition is that the modifications scheduled during the current outage do not l require prior governmental approval. Should this condition not be met for any of these voluntary modifications, with the result that the current implementation schedule must be extended, then BECo will be unable to implement the affected modifications during the current outage.

Additional documentation will be available for review by the NRC Staff at BECo's Braintree offices or the PNPS site. Cognizant BECo personnel will be available at those locations for discussion with the Staff.

Current evaluations of the benefit from the SEP modifications are based primarily upon extensive, although still preliminary, analyses and qualitative engineering judgments. Final quantitative analysis must, in accordance with the stated long term gcal of the SEP, await final identification of modifications and completion of the Individual Plant Evaluation (IPE).

BECo understands that the NRC intends to issue later this year a generic letter requiring all plants to perform an IPE as part of the 8707000400 07o7o3 PDR ADOCK ObOOO;M3 P pm Dk u

i Mr. Steven Varga July 8, 1987 closure of the Commission's Severe Accident Policy Statement. When that requirement is issued, BECo expects to complete the IPE and promptly make the results available in accordance with the review process prescribed by the generic letter.

1 Please feel free to contact me or Edward Howard, of my staff at (617) '

849-8900 if you have any questions concerning the matter addressed in this response.

R. G. ird l

Enclosures 1

I, cc: Nuclear Regulatory Commission j Document Control Desk l Washington, D. C. 20555 Nuclear Regulatory Commission Region I i l 631 Park Avenue 1 l

King of Prussia, PA 19406 l Senior NRC Resident Inspector Pilgrim Nuclear Power Station Mr. R. H. Wessman, Project Manager Division of Reactor Projects, 1/I1 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 1

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