ML20006A511

Application for Amends to Licenses NPF-4 & NPF-7 to Support Planned Fuel Design Change from Westinghouse Low Parasitic 17x17 (Lopar) Fuel Assembly to New 17x17 Assembly W/Vantage 5H Fuel Assembly Design Features

ML20006A511
Person / Time
Site:	North Anna
Issue date:	01/15/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20006A512	List: ML20006A511 ML20006A515
References
89-795, NUDOCS 9001290054
Download: ML20006A511 (3)

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z VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 15,1990 United States Nuclear Regulatory Commission Serial No. 89 795 Attention: Document Control Desk NO/DLDM:Jmj 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 NORTH ANNA FUEL ASSEMBLY DESIGN 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 License Nos. NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2,

.respectively. ,

These amendments are submitted to support a planned fuel design change from the Westinghouse Low Parasitic 17x17 (LOPAR) Fuel Assembly to a new 17x17 assembly with Westinghouse VANTAGE SH Fuel Assembly design features.

The new assembly design, designated North Anna Improved Fuel (NAIF), utilizes Zircaloy grids and smaller diameter thimble tubes. As a consequence of smaller diameter thimble tubes, a change to the Technical Specification governing the ,

maximum allowable control rod drop time is being requested. The proposed change to the Technical Specifications are needed to support initial use of the North Anna improved Fuelin North Anna Unit 2 Cycle 8, November 1990 startup. Attachment 1 contains the proposed Technical Specification changes and Attachment 2 provides a safety evaluation of the impact of the fuel assembly design change. I This request has been reviewed by the Station Nuclear Safety and Operating l Committee. It has been determined that this request does not involve any unreviewed  :

safety questions as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for the determination that no significant hazard 1 consideration is involved is presented in Attachment 2, in accordance with 10 CFR  :

50.91(a) and the guidance provided in generic letter 86-03. l Very truly yours, W. L. Stewart I Senior Vice President - Nuclear 90o1290054 900115 PDR P

ADOCK 05000338 PDC L/ (A h 4f i I

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Attachmants

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

2. Safety Evaluation for Implementation of North Anna improved Fuel Product

3. Significant Hazards Evaluation for Implementation of North Anna improved Fuel Product cc: United States Nuclear Regulatory Commission Region il

< 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident inspector North Anna Power Station  :

Commissioner ,

Department of Health Room 400 109 Governor Street Richmond, Virginia 23219 I l-4

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i N COMMONWEALTH OF VIRGINIA )

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COUNTYOFHENRICO )

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 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 /6Eday of bdArnons- , 19 90.

My Commission Expires: ISA>ou n f6 . 19.90_. -

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