ML18153D379

Application for Amends to Licenses DPR-32 & DPR-37,updating Augmented Insp Program for Sensitized Stainless Steel to Incorporate Newer Code Requirements While Maintaining Increased Insp Philosophy of ASLB

ML18153D379
Person / Time
Site:	Surry
Issue date:	07/02/1993
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153D380	List: ML18153D379 ML18153D381
References
93-401, NUDOCS 9307150030
Download: ML18153D379 (3)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

\

July 2, 1993 United States Nuclear Regulatory Commission Serial No.93-401 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 CHANGES AUGMENTED INSPECTION PROGRAM SENSITIZED STAINLESS STEEL Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes will update the augmented inspection program for sensitized stainless steel to incorporate the newer Code requirements, while maintaining the increased inspection philosophy of the Atomic Safety and Licensing Board. The proposed changes will result in reduced radiation exposure each refueling outage while maintaining a commensurate level of nuclear safety. The proposed changes are included as Attachment 1.

The proposed changes have 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 1o CFR 50.59, or create a significant hazards consideration as defined in 1o CFR 50.92. A discussion of the changes and the basis for our no significant hazards consideration determination are included in Attachment 2.

Very truly yours,

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• W. L. Stewart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification

. 2. Discussion and Significant Ha~ards Consideration 1 ~008:1

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

Suite2900 *

. Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Pow~r Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

e e 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. 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. * *

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Acknowledged before me this _Z}!__day of , 19gf.

• My Commission Expires: LliZrur : ;

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Notary Public (SEAL) .