ML20079G971

Application for Amends to Licenses NPF-4 & NPF-7,revising Spec 4.4.5.4.a.9 to Provide Preservice Insp (Baseline Eddy Current Exam) Requirements for Steam Generator Tubing

ML20079G971
Person / Time
Site:	North Anna
Issue date:	10/03/1991
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20079G976	List: ML20079G971 ML20079G978
References
91-459, NUDOCS 9110100044
Download: ML20079G971 (3)

Text

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. , VilMUNI A IU.HCTHIC AN D MOWEH CObllMY lh r n oiou n, Vnunn:A caum October 3, 1991 U.S. Nuclear Regulatory Commission Serial No.91-459 Attention: Document Control Desk NL&P/JBL: R0 Washington, D.C. 20555 Occket Nos. 50 338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND DOWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 ERQEQSED TECHNICAL _ SPECIFIC ATION CH ANGf;

- AUGMENTED STEAM GENERATOR INSPECTION PROGR AM EBESERVICE EX AMIN ATION REQUIREMENTS Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of a change to the Technical Specifications, to Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively. The proposed Technical Specifications change will revise Specification 4.4.5.4.a.9 which provides preservice inspection (baseline eddy current examination) requirements for steam generator tubing. ,

The proposed Technical Specifications change is presented in Attachments 1 and 2 tor Units 1_ and 2, respectively. The proposed changes create a Specification identical to Suiveillance Requirement 4.19.E.a.9 for Surry Power Station Units 1 and 2. In addition, the proposed changes are -substantially -the same- as Surveillance Requiroment 4.0.6.4.a.9 of the recently apprcmd Technical Specifications for Comanene. Peak Unit 1. A discussion of the proposed changes and a safety evaluation is provided in Attachment 3.

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 this request does 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 that this change does not involve a significant hazards consideration is provided in Attachment 4.

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'Should you have any questions or require additionalinformation, please contact us at your earliest convenience.

Very truly yours, W. L. Stewa'rt sx Senior Vice President - Nuclear Attachments 1 Proposed Technical Specifications Change for North Anna Unit 1

2. Proposed Technical Specifications Change for North Anna Unit 2

3. Discussion of Changes and Safety Evaluation 4.10 CFR 50.92 No Significant Hazards Consideration Evaluation ec: U.S. Nuclear Regulatory Commission Region 11-101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street' Richmond, Virginia 23219 l

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i COMMONWEALTH OF VIRGINIA )

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COUNTYOF 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 Preside'nt - Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoin0 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 Y day of d2ded , 199L.

My Commission Expires: ( Me AL_ , 19 9 I.

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- kbLdh-Notary '3ublic 1

(SEAL)

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