ML18141A256

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Forwards Revised Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code, Per
ML18141A256
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 12/01/1983
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Eisenhut D, Thomas C
Office of Nuclear Reactor Regulation
Shared Package
ML18141A257 List:
References
510, NUDOCS 8312060317
Download: ML18141A256 (1)


Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR 0PERATXONS December 1, 1983 Mr. Darrell G. Eisenhut, Director Division of Licensing Attn:

lft..r. Cecil O. Thomas, Chief Standardization & Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Corrmission Washington, D.C.

20555 Gentlemen:

Serial No.

510 PSE/KLB:plc Docket Nos.:

50-280 50-281 50-338 50-339 License Nos.: DPR-32 DPR-37 NPF-4 NPF-7 VEPCO REACI'OR (X)RE THERMAL-HYDRAULIC ANALYSIS In response to the August 26, 1983, letter from Mr. Cecil o. Thomas accepting the Vepco topical report VEP-FRD-33 for reference in licensing actions By Vepco, we have issued revised versions of this report which include the NRC evaluation letter. Forty (40) copies of the revised version of the report are enclosed for your use.

If you have any guest.ions, please contact us.

cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. M. B. Shymlock NRC Resident Inspector North Anna Power Station Y.ir. D. J. Burke NRC Resident Inspector SUIIY Power Station W. L. Stewart