ML18153C434

Application for Amends to Licenses DPR-32 & DPR-37,revising Tech Specs Re Pressure at Which Leak Rate Testing Performed & Definition of Test Pressure for Emergency Escape Airlock

ML18153C434
Person / Time
Site:	Surry
Issue date:	11/14/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C435	List: ML18153C434 ML18153C436
References
90-245, NUDOCS 9011200183
Download: ML18153C434 (3)

Text

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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 14, 1990 United States Nuclear Regulatory Commission Serial No.90-245 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 TYPE A TESTING AT CONTAINMENT DESIGN PRESSURE Pursuant to 1O CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station Units 1 and 2 respectively. This proposed change will revise the pressure at which Leak Rate Testing is performed and define the test pressure for the emergency escape airlock.

A reanalysis of the containment and safety system performance was completed to resolve a canal inventory (ultimate heat sink) concern. Assuming the worst case conditions for containment pressure transient, the peak accident pressure is predicted to rise to 44.98 psig. Therefore, the Technical Specification is being changed to require that leak rate testing be performed at a pressure equal to or greater than 45 psig.

It is impractical to perform leak rate testing of the emergency escape airlock seal in the same direction as accident pressure. The airlock is tested at a reduced pressure in the opposite direction of accident pressure in accordance with the manufacturer's guidance. Therefore, in accordance with 1O CFR 50 Appendix J requirements, we are including the reduced test pressure in our Technical Specifications. Another change being proposed is to correct a typographical error for maximum service water temperature. The proposed changes are included in Attachment 1.

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e This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed change does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 1O CFR 50.92. A discussion of the change and the basis for our no significant hazards consideration determination is included in Attachment 2.

Very truly yours, i~L~

W. L. Stewart Senior Vice President - Nuclear Attachment

1. Proposed Supplemental Technical Specification Change

2. Discussion and Significant Hazards Consideration Determination.

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

e COMMONWEALTH OF VIRGINIA )

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COUN1Y 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 belief.

Acknowledged before me this /i/?llday of ~&d, 1910.

My Commission Expires: ~ 3/ , 19_qi

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Notary Vu1'1ic

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