ML18153C024

Application for Amends to Licenses DPR-32 & DPR-37.Amends Restore Allowed Leakage Spec for Recirculation Spray Sys, Inadvertently Deleted W/Table 4.5-1 by Tech Spec Amends 128 & 128.Allowed Total Safety Leakage Will Be Retained

ML18153C024
Person / Time
Site:	Surry
Issue date:	12/22/1989
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C025	List: ML18153C024 ML18153C027
References
89-800, NUDOCS 9001020281
Download: ML18153C024 (3)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 22, 1989 United States Nuclear Regulatory Commission Serial No.89-800 Attention: Document Control Desk NO/JZL:

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 ALLOWED LEAKAGE FOR THE RECIRCULATION SPRAY AND SAFETY INJECTION SYSTEMS Pursuant to 10 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 change restores the allowed total leakage specification for the recirculation spray system that was inadvertently deleted with Table 4.5-1 by Technical Specification Amendment Nos. 128 and 128. Table 4.11-1, which provides the assumed component specific leakage and the resulting allowed total system leakage for the safety injection system, is being deleted. The allowed total safety injection system leakage will, however, be retained. Requirements are also being added to periodically verify that total system leakages are within the allowed limits.

Th\s request has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our determination of no significant hazard is included in Attachment 2.

W. L *Stewart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification Change

2. Significant Hazards Consideration Determination

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e 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

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. R. Cartwright, who is Vice President - Nuclear Operations, for 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 Z2 day of .Jli.evmlu.,v , 19~.

My Commission Expires: ~ e5 , 19R.

____/f'~~_l//dL_ __

Notary Public (SEAL)