ML20077F240

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Application for Amend to Licenses NPF-4 & NPF-7,changing Tech Specs by Reducing Length of Time for Core Surveillance Rept Submittal from 60 Days to 30 Days Prior to Initial Criticality
ML20077F240
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/26/1983
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20077F243 List:
References
416, NUDOCS 8308010304
Download: ML20077F240 (4)


Text

. .

VIRGINIA ELucTulc AND Powna COMPANY Ricitxoxn,VIHOINIA 20061 IcN.'.".'", July 26, 1983 Necream OP.BATION.

Mr. Harold R. Denton, Director Serial No. 416 Office of Nuclear Reactor Regulation N0/ CTS:hca 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 Comission NPF-7 Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.99, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating Licenses NPF-4 and NPF-7 for the North Anna Power Station, Unit Nos. I and 2.

The proposed changes are enclosed.

Presently, the Core Surveillance Report, which describes F limits and the surveillance power level for each reload cycle, must be suNiitted to the Nuclear Regulatory Comission Statf 60 days prior to initial criticality for each cycle. This proposed change would reduce the length of time, prior to 4

crfticality, for report submittal, from 60 days to 30 days. This reduction in submittal time will allow more flexibility in scheduling core design tasks and refueling outage planning. This change is administrative in nature and will not affect the validity of information and conclusions in the Core Surveillance Report, nor will it affect the need for frequent axial power distribution surveislance. The proposed Technical Specification change is provided in Attachment 1. A discussion of the proposed Technical Specifications is provided in Attachment 2.

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 pose an unreviewed safety question as defined in 10 CFR 50.59 or a-significant hazards consideration-as defined in 10 CFR 50.92.

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8308010304 830726 PDR ADOCK 05000338 P PDR ,

. e vmoim tucram no rom comn w Harold R. Denton We have reviewed this request in accordance with the criteria in 10 CFR 170.22.

Since this request involves a safety issue which the Staff should be able to determine does not involve a significant hazards consideration for Unit 1 and a duplicate safety issue for Unit 2, a Class III license amendment fee and a Class I license amendment fee are required for Unit 1 and Unit 2, respectively.

A check in the amount of $4,400 is enclosed in payment of the required fees.

Very truly yours, c' .n l . h W. L. Stewart Attachments:

1. Proposed Technical Specification Change for Core Surveillance Report.
2. Discussion of Proposed Technical Specification Change.
3. Voucher Cneck for $4,400.

cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. M. B. Shymlock NRC Resident Inspector North Anna Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 i

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L COMMONWEALTH OF VIRGINIA )

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CITY OF RICHM0?D )

The foregoing document was acknowledged before me, in and for the City and Commonwealth 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 M day of d ,1923 .

  1. l My Cc mission expires:  ? 24 , 19 V .

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