ML18153B945

Application for Amends to Licenses DPR-32 & DPR-37,changing Tech Specs to Relax Lift Setpoint Tolerances in Order to Provide Greater Operational Flexibility in Meeting Periodic Test Requirements Established by Safety Analysis

ML18153B945
Person / Time
Site:	Surry
Issue date:	10/18/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153B946	List: ML18153B945 ML18153B947
References
89-453, NUDOCS 8910300075
Download: ML18153B945 (3)

Text

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.' e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 18, 1989 United States Nuclear Regulatory Commission Serial No.89-453 Attention: Document Control Desk NO/ETS:vlh 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 CHANGE PRESSURIZER SAFETY VALVE LIFT SETPOINT TOLERANCE INCREASE Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for Surry Units No. 1 and 2, respectively.

The current Technical Specifications requirements for pressurizer safety valve lift setpoint tolerances are unnecessarily restrictive. Therefore, relaxation of the lift setpoint tolerances is proposed in order to provide greater operational flexibility in meeting periodic test requirements established by safety analysis.

Attachment 1 provides the proposed Technical Specifications changes for Units 1 and

2. Attachment 2 is a safety evaluation of the proposed changes. These changes and the supporting documentation have been approved by the Station Nuclear Safety and Operating Committee and by the Safety Evaluation and Control Staff. It has been determined that this request does not pose any unreviewed safety question as defined in 10 CFR 50.59 nor does it pose a significant hazards consideration as defined in 1o CFR 50.92. The basis for the determination that no significant hazards consideration is involved is presented in Attachment 3 in accordance with 10 CFR 50.91 (a).

Very truly yours, llL<;~~-

w. L. Stewart Senior Vice President - Power Attachments

1. Proposed Technical Specification Change

2. Safety Evaluation

3. 10 CFR 50.92 Evaluation Aoot

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

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland 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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COUNlY 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 - Power, 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 belief.

Acknowledged before me this /$ day of (/J~ , 198!l._.

My Commission Expires: * ~ ZS: 19~.

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Notary Public (SEAL)