ML20116N820

Application for Amends to Licenses NPF-4 & NPF-7,revising Tech Specs Re pressure-temp Limit Curves to Be Applied During Heatup & Cooldown.Fee Paid

ML20116N820
Person / Time
Site:	North Anna
Issue date:	04/30/1985
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20116N821	List: ML20116N820 ML20116N833 ML20116N836
References
85-290, NUDOCS 8505070364
Download: ML20116N820 (4)

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April 30, 1985 WRGINIA POWER Mr. Harold R. Denton, Director Serial No.85-290 Office of Nuclear Reactor Regulation E&C/NAS:ses:2013N Attn: Mr. James R. Miller, 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, DC 20555 Gentlemen:

VIRGINIA POWER NORTH ANNA POWER STATION UNITS N0. 1 AND 2 REACTOR VESSEL MATERIALS SURVEILLANCE REPORTS AND PROPOSED TECHNICAL SPECIFICATIONS CHANGES Pursuant to 10 CFR 50.90, Virginia Power requests amendments, in the form of changes to the Technical Specifications, to Operating Licenses NPF-4 and NPF-7 for North Anna Units No.1 and ?, renectively.

In accordance with the cun at Technical Specifications and with 10 CFR 50 Appendices G and H, Virginia Power has updated the pressure-temperature limit curves to be applied during heatup and cooldown. The updated curves, which are valid through 10 Effective Full Power Years (EFPY) for each unit, are based on conservative extrapolated vessel irradiation levels which reflect the results of evaluations of the first surveillance capsules removed from the two units. The removal and evaluation of these capsules constitutes part of the Reactor Vessel Materials Surveillance Program established by Virginia Power in accordance with the latest version of 10 CFR 50 Appendix H.

Attachments 1 and 2 provide the proposed Technical Specifications changes for Units 1 and 2. In addition .to the revised pressure-temperature limit curves, accompanying changes to the reactor heatup rate limits and the low temperature overpressure protection (Power Operated Relief Valve) setpoints are also provided. Attachment 3 is a Safety Evaluation of the proposed changes.

The surveillance capsule evaluations, wnich were performed by. Babcock and Wilcox, are provided as Attachments 4 and 5 for Units-1 and 2, respectively.

-Attachment 6 provides a_ description of the neutron fluence calculations and development of the revised Appendix G pressure-temperature limits which form the basis of the proposed changes. Please note that for North Anna Unit 2, the Attachment 6 pressure-temperature limits supersede those included in

' Attachment 5.

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Mr. Harold R, Denton Page 2 e

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The proposed changes and supporting documentation have been reviewed and approved by the Station Nuclear Safety and Operating Committee and by the Safety Evaluation and Control Staff. It has been determined that this request does not pose any unreviewed safety question 'as defined in 10 CFR 50.59 nor does it pose a significant hazards consideration as defined in 10 CFR 50.92.

The current limits on Unit 1 are valid to at least 5 EFPY. In the event-the 5 EFPY of energy generation is achieved on Unit 1 prior to receipt of your approval of the. proposed changes, our intent is to administratively implement the 10-year reduced limits at that time. Based on our current operating and refueling schedules, we anticipate reaching 5 EFPY on Unit 1 by the Spring of 1986.- The current Unit 2 limits are based on 8 EFPY of energy generation.

Based on current schedules, 8 EFPY of energy generation will not be reached before 1990.

We have evaluated this request in accordance with the criteria in 10 CFR 170.12. A check in the amount of $150 is enclosed as an application fee.

Very truly yours, I I W. L. Stewart Attachments:

1. Proposed Technical Specifications Change - Unit 1

2. Proposed Technical Specifications Change - Unit 2

3. Safety Evaluation

4. BAW-1638'- Unit 1 Surveillance. Capsule Evaluation Report

5. BAW-1794 -' Unit 2 Surveillance Capsule Evaluation Report

6. BAW-1872 - Development of Updated Pressure-Temperature Limit Curves - 1 Units 1 and 2 l cc: Dr. J. Nelson Grace l Regional Administrator Region II Mr. M. W. Branch NRC Resident Inspector North Anna Power Station j u

Mr. Charles .. Price .

l Department.of Health  !

! 109 Governor Street ll Richmond,_Virginiu 23219 i

b COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth afc. resaid , - today by R. J. Hardwick, Jr. who is Manager -

. Nuclear Programs and Licensing, of-Virginia Power. 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 DO day of AP. .\ , 19 M .

My Commission expires: kb.nen , 10 ,19 SS .

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE UNIT 1 C

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