ML20042D748

Application for Amends to Licenses NPF-4 & NPF-7, Incorporating Changes Into Design Features Section of Tech Specs Re Use of Solid Stainless Steel or Solid Zircaloy-4 Filler Rods in Place of Fuel Rods

ML20042D748
Person / Time
Site:	North Anna
Issue date:	03/29/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20042D749	List: ML20042D748 ML20042D750
References
89-773A, NUDOCS 9004050309
Download: ML20042D748 (3)

Text

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VrHOINIA El.EC'THIC AMD POWEH COMI%NY Hwuxoxo, Vino:wsA ununi March 29,1990 United States Nuclear Regulatory Commission Serial No. 89 773A Attention: Document Control Desk NL&P/JYR Washington, D.C. 20555 Docket Nos. 50 338 50 339 License Nos. NPF-4 NPF 7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE - SUPPLEMENT Pursuant to 10CFR50.90, the Virginia Electric and Power Company requested amendments, in the form of changes to the Technical Specifications, to Operating License Nos. NPF 4 and 7 for North Anna Power Station Units 1 and 2, respectively by letter dated 1/16/90. The purpose of the amendments was to incorporate changes into the Design Features Section of each Unit's Technical Specifications. The changes allowed the use of solid stainless steel or solid Zircaloy 4 filler rods in place of fuel rods that are known to be failed and removed the rod uranium weight limit of 1780 grams.

Subsequent to the aforementioned amendments, we received NRC Generic Letter 90-02, " Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications," dated 2/1/90. As a result, we are requesting changes to the previously submitted amendments, to be consistent with the guidance in Generic  ;

Letter 90 02.

This request has been reviewed by the Station Nuclear Safety and Operating .

Committee. It has been determined that this request does not involve any unreviewed l safety questbns as defined in 10CFR50.59 or a significant hazards consideration as  !

defined in 10CFR50.92. The basis for the determination that no significant hazard i consideration is involved is presented in Attachment 3, in accordance with 10CFR50.91(a) and the guidance provided in Generic Letter 86-03.

Very truly yours, k W. L. Stewart Senior Vice President - Nuclear 1

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0t 0 9004050309 900329 3 DR ADOCK0" cog:8 <(i l

4, Attachments:

1. Proposed Technical Specification Changes for North Anna Units 1 & 2

2. Markup of the North Anna MER!TS Technical Specifications 3.10 CFR 50.92 Significant Hazards Determination ec: United States Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior flesident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219  !

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1 COMMCt!i.', EALTH OF VIRGINIA ) l

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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 4

i 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 29 day of A-L ,19fA.  :

My Commission Expires: t #s J/ , 19 8 a r; -

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