ML18153C845

Application for Amends to Licenses DPR-32 & DPR-37,changing Tech Specs to Remove Plant Records Vault Fire Suppression Sys Operability Requirements & Include Operability Requirements for Emergency Switchgear Room

ML18153C845
Person / Time
Site:	Surry
Issue date:	12/19/1991
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C846	List: ML18153C845 ML18153C847
References
91-747, NUDOCS 9112270030
Download: ML18153C845 (3)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 19, 1991 United States Nuclear Regulatory Commission Serial No.91-747 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 RECORDS VAULT FIRE SUPPRESSION SYSTEM TECHNICAL SPECIFICATION CHANGE 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 Licenses No. DPR-32 and DPR-37 for the Surry Power Station Units 1 and 2 respectively. The proposed Technical Specification change will remove the the plant records vault fire suppression system operability requirements and include operability requirements for the Emergency Switchgear Room fire suppression system.

Attachment 1 provides the proposed Technical Specification change.

Surry Power Station is building a new administration building outside the protected area which will have a records vault. The new records vault will have a water/sprinkler fire suppression system. The existing records vault has a Halon fire suppression system. Since the records vault fire suppression system does not protect safety-related equipment, the operability requirements are being eliminated from Technical Specifications.

This request has 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 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 no significant hazards consideration determination is included i_n Attachment 2.

Very truly yours,

,. ,., n tJL)0for W. L. Stewart Senior Vice President - Nuclear

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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

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 - 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 th is ,/9 *ZJIday of ./Vt~ dJ7 !u/lJ, 19 q J.

My Commission Expires: {'-".d1,-'--++,'t1'c,4-,'J~*--=-;S~/~-' 1gqtJ.

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Notary Public (SEAL)