ML19095A278

Response to Letter of 1/25/1978 Concerning Design of Reactor Vessel Support System, Advising, Interim Progress Including Task Group of Utilities with Westinghouse Plant Has Been Formed

ML19095A278
Person / Time
Site:	Surry
Issue date:	03/07/1978
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Case E, Stello V Office of Nuclear Reactor Regulation
References
Serial No. 067 /012578
Download: ML19095A278 (1)

Text

e VIRGINIA ELECTRIC ij[~RMM W?(t'.1)17 fi1'"1H~U 17 ru rijuuLErr A.Nlli!hRo~n':$LR_v~1J)~~~~f.U u 10lifi)lm1J

~u.JJfj RICHMOND,VI:ROU-,IA 23261 March 7, 1978' s,  ::'iJfJ(>*c .; '

. . -~ -..

~

• . ): 'V ; * ... ~ - : - ' - : ~ - - *

• ""7-**.;.-:. *:** i 1 .~ *--,'",..-J Mr. Edson G. Case, Acting Director Sen.al No. 067 /012578 --,...,=,~

Office of Nuclear Reactor Regulation PO&M/DLB:dgt U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 Attention: Victor Stello, Jr. Director License Nos. DPR-32 Division of Operating Reactors DPR-37

Dear Mr. Case:

This is in response to your letter of January 25, 1978*, concerning the design of the reactor vessel support system for Surry Power Station Unit Nos.

1 and 2. Your letter requested a response within 30 days indicating our in-tent to proceed with an evaluation of the overall asymmetric loss of coolan.t accident loads as described in your letter and attachments. You also request-ed that within 90 days we submit our detailed schedule for providing the re-quired evaluation.

This letter is to notify you that a task group of utilities with West-inghouse plants has been formed, of which Virginia Electric and Power Com-pany is a participant, to examine the complexity of primary system main cool-ant piping system breaks as outlined in your January 25, 1978 letter and to identify similarities between Westinghouse plants for the purpose of deter-mining a consistent evaluation of this issue. The task group has met with Westinghouse and with the NRC during the past several months for the purpose of developi..~g a program that is acceptable to both parties. Preliminary

-wo.r:k is proceeding -,which will allow the task group to outline a realistic program within the 90 days you requested.

The exact content of this program is not known at this time, but its purpose will be to re-assure the original plant design and assure the safety of the plant should a pipe break occur at specified locations in the reactor coolant system. The particular resolution of this issue will vary from plant to plant, but as a minimum it will include an analytical evaluation that assesses the safety of the plant. If needed, this evaluation may be supple-mented by a plant modification, probability analysis or augmented inservice inspection.

Very truly yours,

//,; /~)? ' ,,Jj~l.'i;;;£.-<,.~*,:::,._,.-

'-.v

.-7 ~r"'.

'.,. ~ . ~

J C. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. James P. O'Reilly 7:::,1("t-r--...

-*-*.J..::.(_,)010