ML18139B615

Provides Info Re Util Plans for Cycle 6 Core Reloads.No Unreviewed Safety Questions as Defined in 10CFR50.59 Will Exist as Result of Subj Reload.Verification of Reload Core Will Be Performed Through Startup Physics Testing Program

ML18139B615
Person / Time
Site:	Surry
Issue date:	11/16/1981
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
638, NUDOCS 8111190322
Download: ML18139B615 (2)

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VIRGIN1A ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 November 16, 1981 R.H.LEASBUBO VxcE PRESn>ENT NUCLEAR 0PERATXONS Mr. Harold R. Denton, Director Serial No.: 638 Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief. FR/NAS:gmj Operating Reactors*Branch.No. *1 Division.of.Licensing Docket No.: 50-281 U.S. Nuclear Regulatory Commis-sion.

Washington, D.C. 20555 License No.: DPR-37

Dear Mr. Denton:

RELOAD INFORMATION FOR CYCLE 6 SURRY NUCLEAR POWER STATION UNIT NO. 2 Surry Unit No. 2 completed its fifth cycle of operation on November 6, 1981. The purpose of this letter is to advise you of our plans for the Cycle 6 reload core.

The Cycle 6 reload'core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled "Westinghouse Reload Safety Evaluation Methodology." The results of this analysis indicted that no key analysis parameters would become more limiting during Cycle 6 operations than the values assumed in the currently applicable safety analysis. Further, the analysis demonstrated that the current Technical Specifications, as approved* through Amendment No. 73, are appropriate and require no additional changes.

A detailed review of the Westinghouse methodology, analysis techniques and results has been conducted by our technical staff. In addition, a review has been performed by both the Station Nuclear Safety and Operating Conunittee 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 6 reload core.

Verification of the reload core will be performed through a startup physics testing program. Unless otherwise indicated, this program will be consistent with documentation provided in our topical report VEP-FRD-36A, "Control Rod Reactivity Worth Determination by the Rod Swap Technique," transmitted by our letter to you dated January 16, 1981 (Serial No. 023). This report is a revision of VEP-FRD-36, an fJ 00 J s

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e e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 2 earlier topical report of the same title.

This letter is provided for your infonnation. However, should you have questions, please contact us at your earliest convenience.

Veryt,x 11:.aSburg cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II L