ML20058N582

Application for Amends to Licenses NPF-4 & NPF-7,changing Tech Spec Per Requirements of Generic Ltr 88-16

ML20058N582
Person / Time
Site:	North Anna
Issue date:	08/08/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058N585	List: ML20058N582 ML20058N590
References
90-030A, 90-30A, GL-88-16, NUDOCS 9008140211
Download: ML20058N582 (2)

Text

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VinotwrA ELacTwie Axn Powan Comi Aky HICitMOND,VINGINIA 200 61 August 8,1990 U.S. Nuclear. Regulatory Commission Serial No.: 90 030A Attention: Document Control Desk NL&P Washington, D.C. 20555 Docket Nos.: 50-338 50 339 -

License Nos.: NPF-4  !

N PF 4 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY '

NORTH ANNA POWER STATION UNITS 1 AND 2

TECHNICAL- SPECIFICATION CHANGE - PER

l. REQUIREMENTS OF GENERIC LETTER 88-16 l s

On March 29,1990, Virginia Electric and Power Company requested amendments, in

. the form of changes to the Technical Specifications, to Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively. These l ,

requested amendments reflected the guidance provided in Generic Letter 8816; The requested change removed the cycle dependent variables from- the Technical 3 Specifications by referencing a unit and cycle specific Core Operating Limits Report  :

.(COLR)_ which will document the specific parameter limits resulting from Virginia Electric and Power Company calculations.

A discussion between Virginia Electric and Power Company and the NRC regarding this Technical Specification change request was conducted by teleconference on i

June 7,' 1990. During this discussion, Virginia Electric and Power Company agreed to revise their March 29,1990 submittal by referencing the : analytical-methodologies in '

section 6'of the Technical Specifications instead of identifying these references in the COLR.'The revision to the March _-submittal is administrative _ in nature since it only

! < involves location changes-for required information, and identification of additional

? references of analytical methods that may be used to determine the core operating L

limits. These methods have been previously reviewed and approved by the NRC.

L This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed changes do 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. These changes do not impact the results of our original safety analysis and the significant hazards consideration )

determination.

Please replace the appropriate pages in the March 29,1990 submittal with the '

, attached Technical Specification pages in Attachment 1 (6-17 & 6-17a Unit 1 and 6-17

& 17a Unit 2) and the COLR in Attachment 2 (page 5 of 11 Unit 1 and page 5 of 12 Unit 2).

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. A review of the applicable North' Ann'a' MERITS Technical Specification sections has been made, and no change to the MERITS version is needed. j

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Lif you. have~ any' questions or- require additional information, please contact us '

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. Immediately. -

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Very[truly s . i

, - W. L. St art .;

Senior Vice President -. Nuclear ' q Attachments: . .

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1. Proposed Technical Specifications Changes for North Anna Units 1-& 2 ,

2. Proposed Change for North Anna Units 1 & 2 Core Operating Limits Reports cc: U.S. Nuclear. Regulatory Commission

~ Region il 101 Marietta Street,.N.W. .

t Suite 2900l Atlanta, Georgia 30323 -

Mr. M. S. Lesser.

NRC Senior Resident inspector l North Anna Power Station Commissioner Department.of Health ,

Room 400 109 Governor Street Richmond, Virginia 23219 4

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