ML20077K528

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Application for Amends to Licenses NPF-4 & NPF-7,increasing RCS Temp Average to 587.8 F
ML20077K528
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/30/1982
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20077K532 List:
References
726, NUDOCS 8301130098
Download: ML20077K528 (4)


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, December 30, 1982

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A M/ , ifr., Ha rold R'.lDenton, Director Serial No.: 726 g s Officy 6f' Nuclear Raactor Regulation FR/CLD: gmj Attn; -Mrs-Robert A. Clark ~, Chief Docket Nos.: 50-338 Operat' ink Reactors Branch No. 3 50-339 Division of Licensing License Nos.: NPF-4

- U. S.,PNelear Reguldtisry Coraission NPF-7 g' ~

Nashington, D. C. 20533

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W ._ - Gentlenen:  %

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s AMENDMEhhTOOPERATINGLICENSESNPF-4ANDNPF-7

, NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 t

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- ' J^ PROPOSED TECHNICAL SPECIFICATION CHANGE

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- , Pursuant to 10CFR50.90, the Virginia Electric and Power Company requpsts an amendment,'in the form of changes to the Technical 3 Sp c.ifications.7to' Operating License Nos. NPF-4 and NPF-7 for the North i[

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_m . Anna Power Station Unit Non. I and 2.

/ As, discussed with members of the Staff in meetings on August 11, 1981 and .,Ju'ne' 9, 1982, Vepco is engaged in a program to maximize the f

j clectrical output of North Anna Unit Nos. I and 2. Amendment No. 41 to f , Operating License NPF-4 allows operation of North Anna Unit No. I with a Nit-g _ , reactor coolant system (RCS) average temperature (Tavg) of 582.8 F. The

',, proposed changes of this agendment will allow operation of the North Anna s unirs with a Tavg of 587.8 F. The increase in Tavg will further increase jy ,

secondary side steam pressure, resulting in greater plant electrical F - ' N '.autput.

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Enclosures 1 and 2, respectively, provide Safety Evaluations for j ,the NSSS and Balance of Plant (B0P) systems in support of this request.

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; Several Chapter 15 FSAR safety analyses were performed to support plant

, operation with a Tavg of 587.8 F. The appendix to Enclosure 1 documents these analyses with revised FSAR pages for the affected transients. The l_ -f I' - accidents reanalyzed included a large break LOCA performed at the uprated conditions which resulted in an FQ limit of 2.20. Enclosure 4 provides Coru Surveillance Reports associated with this limit for the current s

plant cycles, North Anna 1, Cycle 4 and North Anna 2 Cycle 2. The y , specific Technical Specifications changes required for this change are J ,

y given in Enclosure 3. 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) l'4 / document and the plant procedures upon approval of this request.

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( ,. As noted in Enclosure 2, the BOP review determined no required plant modifications to support operation at the uprated conditions. The

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1 visonwu EI.EctaIC AND POWEB COMPANY TO Mr. Harold R. Denton 2 Unit No. 2 Mono-Ball support modification identified during the 2.5 F Tavg increase review is designed to be acceptable for a Tavg of 587.8 F.

The BOP review did reveal a decrease in feedwater regulating valve operational flexibility at the uprated conditions. A change in valve trim is being investigated to provide improved valve performance.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that this request does not involve any unreviewed safety questions as defined in 10CFR50.59.

We have evaluated this request in accordance with the criteria in 10CFR170.22. Since this request involves a safety issue which the staff should be able to determine does not involve a significant hazards consideration for Unit No. I and a duplicate safety issue for Unit No. 2, a Class III license amendment fee and a Class I license amendment fee is required for Unit No. I and Unit No. 2, respectively. A voucher check in the amount of $4,400.00 is enclosed in payment of the required fee.

We are interested in implementing the 7.5 F increase in Tavg on Unit No. 2 during the Spring 1983 refueling outage, which ends on May 15, 1983. This would provide an opportunity to perform any feedwater regulating valve trim changes which may be desired. Consequently, we wish to discuss this request with appropriate members of the Staff in January 1983. Please contact us if you need additional information to review this submittal.

Very truly yours, l

l, W i W. L. Stewart i

Enclosures (1) NSSS Safety Evaluation for Tavg 587.8 F (2) B0P Safety Evaluation for Tavg of 587.8 F l (3) Proposed Technical Specifications Changes l (4) Core Surveillance Reports for North Anna 1, Cycle 4 and North Anna 2, Cycle 2 (5) Voucher Check for $4,400.00 cc: Mr. James P. O' Reil)v Regional Administrator Region II Atlanta, GA 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 Comonwealth aforesaid, today by W. L. Stewart, 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 3 6 day of be= I- ,19 b .

My Comission expires: 4 .;L 6 , 19 pf ,

Om d . MCA Notary Public (SEAL)

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, vfRGlhtA ELECTRIC AND PowtA COMPANY - - - - -

lcHectvoucwen o ssue sann No 25 carcn wo MUD _ DATE 1P/P7/AP venoon NO IM1

- LINE DATE INVOICE NO/OR DESCRIPTION GROSS AMOUNT DISCOUNT NET AMOUNT l 1 12/21/82 .NA LE2 TECH SPEC CHANGE 4,400.00 0.00 4,400 00 1

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ATTACHED CHECK ISSUED AS PAYMENT OF ITEMS LISTED ABOVE - PLEASE DETACH STUB AND CASH CHECK PROMPTLY.

Vepco VinoiNiA ELECTnlC AND PowEn COMPANY BANK OF VIRGINIA '

VOID IF NOT CA:iH50 IN 90 DAYS >

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PAY FOUR THOUSAND FOUR HUNDRED AND ,00/100 DOLLARS . ,,, , _ , ,

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l. UNITED STATES' NUCLEAR' g. , ,

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