ML18142A149

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Advises of Plans Re Cycle 8 Reload Core.Results of Analysis Per WCAP-9172 Indicate No Key Parameters Will Become More Limiting During Cycle 8 than Values Assumed in Applicable Safety Analyses
ML18142A149
Person / Time
Site: Surry Dominion icon.png
Issue date: 12/21/1984
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
741, NUDOCS 8412280037
Download: ML18142A149 (2)


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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VJ.CE PRESIDENT NUCLEAR OPERATIONS December 21, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Gentlemen:

Serial No.:

741 E&C:GMS:vdu:2001N Docket No.:

50-281 License No.:

DPR-37

  • VIRGINIA ELECTRIC :AND POWER COMPANY RELOAD INFORMATION *FoR*cYClE 8 SURRY *pQWER*STATION UNIT NO. 2 Surry Unit No. 2 is currently scheduled to complete its seventh cycle of operation on or about March 22, 1985.

The purpose of this letter is to advise you of our plans for the Cycle 8 reload core.

The Cycle 8 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 "Westinghouse Reload Safety Evaluation Methodology".

The results of this analysis indicated that no key analysis parameters will become more limiting during Cycle 8 operation than the values assumed in the currently applicable Safety Analyses.

The Cycle 8 reanalysis demonstrated that the current Technical Specifications are appropriate and require no additional changes.

Cycle 8 is currently scheduled to begin operation on May 21, 1985.

The analyses necessary to support Cycle 8 operation have been performed and reviewed by our technical staff using the Westinghouse methodology and analysis techniques.

In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that no unreviewed safety questions as defined in 10 CFR 50.59 will exist as a result of the Cycle 8 reload core.

37 841221 94122B000CK 05000281 pDR AD pDR p

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e VIRGINIA. ELECTRIC.AND POWER COMPANY TO Mr. Harold R. Denton, Director This letter is provided for your information and planning.

However, should you have any questions, please contact us at your earliest convenience.

cc:

Mr. James P. O'Reilly Regional Administrator Region II Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station Very truly yours, fl!lt::i;t W. L. Stewart r