ML20053E617

Application for Amend to Licenses NPF-4 & NPF-7.Changes Allow Operation W/Rcs Average Temp of 582.8 F as Opposed to Current Temp of 580.3 F & Will Increase Secondary Side Steam Pressure,Resulting in Greater Plant Electrical Output

ML20053E617
Person / Time
Site:	North Anna
Issue date:	06/08/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20053E618	List: ML20053E617 ML20053E626 ML20053E631 ML20053E635
References
327, NUDOCS 8206090077
Download: ML20053E617 (3)

Text

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VINUINIA ELucrutc ann Powen COMPANY HICH MOND, Y1HORNIA 20 261 H.H.LnANSU50 vaca Pummonens Noctuam UramAssums June 8, 1982 Mr. Harold R. Denton, Director Serial No.: 327 Office of Nuclear Reactor Regulation FR/CLD: plc Attn: Mr. Robert A. Clark, Chief Docket Nos.: 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos.: NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D.C. 20555 Centlemen:

AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PRnPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station Unit Nos. 1 and 2.

As discussed with members of the Staff in a meeting on August 11, 1981, Vepco is engaged in a program to maximize the electrical output of North Anna Unit Nos. 1 and 2. The proposed changes of this amendment vill allow operation of the North Anna units with a reactor coolant system (RCS) average temperature of 582.80F as opposed to the current RCS average temperature of 580.30F. The increase in Tavg will increase secondary side steam pressure, resulting in greater plant electrical output.

Enclosures 1 and 2, respectively, provide Safety Evaluations for the NSSS and Balance of Plant (BOP) systems in support of this request. The specific Technical Specifications changes required are given in Enclosure 3.

Since the 2.50F increase in RCS average temperature was incorporated in the original Chapter 15 safety analyses, no new analyses are required for this amendment and only three changes are required to the Technical Specifications.

Several associated setpoint changes are required for operation at the increased RCS average temperature, and these will be incorporated into the Precautions, Limitations and Setpoints (PLS) document and the plant procedures upon approval of this request.

As noted in Enclosure 2, the BOP review determined that three North Anna Unit No. 2 bbin Steam Line Mono-Ball supports located on a non-safety related portion of the piping will require modifications. The engineering associated with this change is underway, and we will complete the modifications prior to impicmenting the proposed RCS average temperature increase on Unit No. 2.

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2 Vauoix4 Etzera:C Am Powra COMPANY 70 Mr. Harold R. Denton 1

This request has been reviewed and approved by the Station a Nuclear Safety and Operating Committee and the Safety Evaluation and 1

Control staff. It has been determined that this request does not involve j any unreviewed safety questions as defined in 10CFR50.59.

} We have evaluated this request in accordance with the criteria i in 10CFR170.22. It has been determined that this request requires a Class III amendment fee. Accordingly, a voucher check in the amount of l $4,400.00 is enclosed in payment of the required fee.

Since the magnitude of the impact of the 2.50F increase in avert.ge temperature is minor and consistent with our discussions with i the Staff on August 11, 1981, we would like to implement the changes for i North Anna Unit No. I during the current Cycle 3-4 refueling outage.

Consequently, we wish to discuss this request with appropriate members of the Staff in early June. Please contact us if you need additional information to review this submittal.

I Very t yy yDurs, i

R. . Leasburg

! Enclosures I

(1) NSSS Safety Evaluation for Tavg of 582.80F i (2) BOP Safe'y Evaluation for Tavg of 582.8 F (3) Proposed Technical Specifications Changes 4 (4) Voucher Check for $4,400.00 I cc: Mr. James P. O'Reilly

Regional Administrator i Region II Atlanta, CA 30303 I

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COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R. H. Leasburg, who is Vice President-Nuclear Operations, of the 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.

Acknowledged before me this <f T day of h_ , 19 /2..

f My Commission expires: M5 , 19 #6 .

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