ML18153D117

Suppl to 911230 Amend Applications 165 & 164 to Licenses DPR-32 & DPR-37,respectively,reinstating Allowed Outage Time for Surveillance Testing of Nonessential Svc Water Isolation Actuation Logic & Reformatting Logic

ML18153D117
Person / Time
Site:	Surry
Issue date:	09/04/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153D118	List: ML18153D117 ML18153D119
References
92-579, NUDOCS 9209150021
Download: ML18153D117 (3)

Text

• VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 4, 1992 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No. NO/ETS Docket Nos. License Nos. PROPOSED TECHNICAL SPECIFICATION CHANGES NON-ESSENTIAL SERVICE WATER ISOLATION ACTUATION LOGIC 92-579 50-280 50-281 DPR-32 DPR-37 Pursuant to 1 O 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.

In a previous Technical Specification Amendment (Nos. 165/164), dated December 30, 1991 , the permissible bypass condition for performing surveillance of the non-essential service water isolation actuation logic was inadvertently eliminated.

Therefore, the proposed changes will reinstate the allowed outage time for surveillance testing of the non-essential service water isolation actuation logic and include operability requirements and an action statement for the actuation logic. In addition, the surveillance requirements for the actuation logic are being reformatted to parallel the operability requirements.

The requested Technical Specification changes are provided in Attachment

1. 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 involve an unreviewed safety question as defined in 1 O CFR 50.59, but do not create a significant hazards consideration as defined in 1 O CFR 50.92. Specifically, the increase in allowed outage time for maintenance and testing of the actuation logic 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. -9209 f 500i1--9209c54

---PDR ADOCK 05000280 p PDR

• In order to allow orderly implementation of the amendments, we request that the ~mendments be issued with an effective date of up to 30 days after the date of issuance.

Very truly yours, fr W. L. Stewart Senior Vice President

-Nuclear Attachments

1. Proposed 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. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

• COMMONWEAL TH OF VIRGINIA ) ) COUNTY OF HENRICO )

• The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, 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 /'(I day of,~. 19~. My Commission Expires: ( ~c 3/ , 19Ei; /Q-'iJ!wL Notary Public , (SEAL) --.. '