ML111230352

Requests Review of Reactor Sys Transient Analysis Code & Issuance of Safety Evaluation.Topical Rept Will Be Provided

ML111230352
Person / Time
Site:	Surry, North Anna
Issue date:	10/23/1979
From:	Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML111230353	List: ML111230352 ML18136A112
References
872, NUDOCS 7910290270
Download: ML111230352 (1)

Text

• 0 VIRGINIA E]LECTRIC AND POWER COMPANY RrcnMoNxz,VIxtorNxA, 23261 October 23, 1979 Mr. Harold R. Denton, Director Serial No. 872 Office. of Nuclear Reactor Regulation FR/MLB: mvc Attn: Mr. Albert Schwencer, Chief Docket No.: 50-280 Operating Reactors Branch No. 1 50-281 Division of Operating Reactors 50-338 U. S. Nuclear Regulatory Commission 50-339 Washington, DC ,20555 S "License

. No.: DPR-32 DPR-37 NPF-4

Dear Mr. Denton:

The Virginia Electric and Power Company (Vepco) is actively developing a reload design and safety analysis capability. -An essential part of this develop ment is the reactor system transient analysis code, RETRAN, which is being developed under the sponsorship of the Electric Power Research Institute. Since the RETRAN computer code can be used for reload safety analysis purposes, Vepco has joined with other utilities in requesting a timely review by the NRC of RETRAN and issuance of a Safety Evaluation Report. This generic review~request of RETRAN was trans mitted to you by letter dated October *22, 1979 from Stanley Ragone, Vepco President, and a copy of this letter is attached. As a member of this group, Vepco is.committed to paying a proportionate share of any NRC review fee.

It is intended by Vepco to use the RETRAN code to obtain better under standing of reactor transients, support operator'training programs, and to perform plant-specifilc analysis to supplement vendor performed generic analysis. Vepco specific plans also call for the use of RETRAN as an integral part of a package of codes to be used for reload licensing analyses after July 1980. A topical report qualifying the use of RETRAN on Vepco nuclear units will be provided for your review in the near future. This report will be similar in terms of scope and detail to the topical reports previously provided to you on the Vepco versions of the PDQ07, FLAME, and COBRA IIIC/NIT models which are also part of our reload package.

We would be pleased to discuss these plans in more detail with you in the interest of expediting .the RETRAN review process.

Very truly yours, W. N. Thomas Vice President Fuel Resources Attachment