ML18139B399

Forwards VEP-FRD-42, Reload Nuclear Design Methodology.

ML18139B399
Person / Time
Site:	Surry, North Anna
Issue date:	06/12/1981
From:	Thomar W, Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18139B400	List: ML18139B399 ML18139B401
References
350, NUDOCS 8106180186
Download: ML18139B399 (2)

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VIRGINIA ELECTRIC A.ND POWER COMPANY RICHMOND~ VIRGINlA 23261 W. N.THOMAS June 12, 1981 VICE PRESIDENT FUEL RESOURCES Mr. Harold R. Denton, Director Serial No. 350 Office of Nuclear Reactor Regulation FR/TLW: plc Attn: Mr. D. G. Eisenhut, Director Docket Nos. : 50....:230 Division of Licensing 50-281 U.S. Nuclear Regulatory Commission 50-,338 Washington, DC 20555 50-,339 License No.: DPR-,32 DPR-37 NPF-4 NPF-7 Gentlemen:

VEPCO RELOAD NUCLEAR DESIGN METHODOLOGY Enclosed for your review are forty (40) copies of the Vepco Topical Report VEP-FRD-'42, "Vepco Reload Nuclear Design Methodology".

This report is one of a series of topical reports supplying general information pertaining to the nuclear reload licensing and core follow support capabilities which have been developed at Vepco. It describes Vepco's methods for reload core design and reload key parameter generation.

The key parameters serve as input to our safety analysis codes, and to the RETRAN code in particular. The Vepco topical report, which describes the use of RETRAN in safety analysis, has been submitted (VEP-FRD-41, transmitted by letter to you dated April 14, 1981, Serial ijo. 215). As indicated in my letter to you dated October 17, 1980 (Serial No. 856) we may be supporting reload license amendments with the capabilities described in these reports in the fourth quarter of 1981.

The recommendations of the North Anna and Surry Station Nuclear Safety and Operating Committees, and the System Nuclear Safety and Operating Committee have been incorporated into this report. This report has also been reviewed by the Safety Evaluation and Control staff. Further, it has been determined that the methodology and analysis capability described herein do not involve an unreviewed safety question as defined in 10CFR 50.59.

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VIRGINIA ELECTRIC AN; POWER COMPANY TO Mr. Harold R. Denton We are aware that a fee will be required for the topical report review and will transmit the assessed fee upon.completion of the review.

If you have any questions on the material in this topical report, .please contact us.

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W. :N. Thomas cc: 1'1r. Robert*A. Clark, Chief Operating Reactors .Branch ijo.*3 Division of Licensing Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensi_ng