ML18136A377

Responds to Draft NUREG-0630.Application of NUREG-0630 Will Result in Peak Clad Temps in Excess of Criteria Delineated in 10CFR50.46.Affidavit Encl

ML18136A377
Person / Time
Site:	Surry, North Anna
Issue date:	01/11/1980
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
039, 39, NUDOCS 8001150300
Download: ML18136A377 (3)

Text

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I VIRGINIA ELECTRIC A.ND POWER COMPANY RICHMOND, VIRGIN.IA 23261 January 11, 1980 Mr. Darrel G. Eisenhut Serial No.: 039 Acting Director FR/MLB: mvc Division of Operating Reactors 50-339 Docket Nos.: 50-280 Office of Nuclear Reactor Regulation 50-404 50-281 United States Nuclear Regulatory Commission 50-338 50-405 Washington, DC 20555 License Nos.: DPR-32 DPR-37 NPF-4

Dear Mr. Eisenhut:

We have reviewed your letters of November 9, 1979, November 27, 1979, and December 20, 1979, as well as Mr. Vassallo's letter of November 28, 1979 (transmittal of draft NUREG-0630), from the standpoint of determining both the applicability and impact from incorporating draft NUREG-0630. It is our determination that the impact of applying draft NUREG-0630, assuming it is applicable and no other benefits are considered, will result in peak clad tempera-tures in excess of the criteria delineated in 10 CFR 50.46 for North Anna Units 1 and 2 and Surry Units 1 and 2. No analyses have been performed under 10 CFR 50.46 for North Anna 3 and 4. When this ana~ysis is performed, it will be performed in full compliance with Appendix K to 10 CFR 50. As a consequence of our above determination on North Anna 1 and 2 and Surry 1 and 2, we have worked with Westinghouse and appropriate members of the NRC staff to quantify these impacts and to identify available benefits to offset these impacts. The specific impact and benefit data provided to the NRC staff on North Anna and Surry as a result of our joint Vepco/Westinghouse meeting with the NRC staff on December 20, 1979 supports continued operation without the need for changes to the Technical Specifications in order to meet the criteria of 10 CFR 50.46 (reference NRC (A. Schwencer) to Vepco (W. L. Proffitt) letter of December 28, 1979, Docket No. 50-338).

We are continuing our assessment of the applicability of the data and modeling techniques being proposed in draft NUREG-0630. However, our conclusion at this time is that the modeling of fuel rod burst temperature and degree of flow blockage in our currently applicable LOCA-ECCS submittals are correct. We will promptly inform you should our assessment of the impact and applicability of draft NUREG-0630 change significantly. /Jo37

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e e Vrnorn1AELEcTmcANDPowERCoMPANYTo Mr. Darrel G. Eisenhut 2 Should you have questions, please contact our Mr. M. L. Bowling at (804) 771-3183.

Very truly yours,

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C. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors Mr. O. D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management

e COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

Before me, a Notary Public, in and for the City and Common-weal th aforesaid, today personally appeared C. M. Stallings, who being duly sworn, made oath and said (1) that he is Vice President-Power Supply and Production Operations, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements r in the Amendment are true to the best of his knowledge and belief.

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Given under my hand and notarial seal this Jl.!..h. day of

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My Commission ex~ires

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