ML18153D087

Application for Amends to Licenses DPR-32 & DPR-37, Establishing Operating Requirements for Recirculation Mode Transfer (Rmt) Function,Including LCO Action Statement & SR for Rmt & Deleting RWST Max Vol Requirements

ML18153D087
Person / Time
Site:	Surry
Issue date:	08/07/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A715	List: ML18151A714 ML18153D087
References
92-481, NUDOCS 9208120256
Download: ML18153D087 (3)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 7, 1992 United States Nuclear Regulatory Commission Serial No.92-481 Attention: Document Control Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION FOR THE RECIRCULATION MODE TRANSFER FUNCTION Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes establish operating requirements for the recirculation mode transfer function (RMT) and include the following:

1) Limiting Conditions for Operation, Action Statements, and Surveillance Requirements for the RMT function, 2) deletion of refueling water storage tank maximum volume requirements and clarification of refueling water storage tank water temperature requirements, and 3) administrative changes to provide consistency throughout.

The proposed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that the proposed changes involve an unreviewed safety question as defined in 10 CFR 50.59, but do not involve a significant hazards consideration as defined in 10 CFR 50.92. Specifically, the change in actuation logic for RMT from two-out-of-four to two-out-of-three would insignificantly increase the probability of a malfunction of safety-related equipment. A discussion of the changes and the basis for our no significant hazards consideration determination are included in Attachment 2.

• Very truly yours, JL~

W. L. Stewart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification

2. Discussion and Significant Hazards Consideration

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cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

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COMMONWEALTH OF VIRGINIA )

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COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President -

Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and beli. f.

Acknowledged before me this ?Z! day o, , 199.z_.

My Commission Expires: lffiJ 3/

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Notary ublic .

(SEAL)