ML18143B687
| ML18143B687 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/28/1985 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18143B688 | List: |
| References | |
| 85-240, TAC-60056, TAC-60057, NUDOCS 8510310353 | |
| Download: ML18143B687 (3) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDEN":I" NuCLEAR OPERATIONS October 28, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.' S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE REVISE MAXIMUM K-EFFECTIVE AT REFUELING cm,,DITIONS Serial No.
E&C/GMS:acm Docket Nos.
License Nos.85-240 50-280 50-281 DPR-32 DPR-37 Pursuant to 10CFR50.90, Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos.
1 and 2.
VEPCO is requesting an increase in the maximum K-effective allowable during refueling conditions from the current value of 0.90 to 0.95 for Surry Units 1 and 2.
VEPCO has found the current Technical Specification limit on K-effective at refueling restrictive from a core reload design standpoint because of increasingly reactive core designs.
The current limit of 0.90 has resulted in increased burnable poison requirements which pose a penalty in the area of effective fuel utilization.
This proposed change in K-effective will provide greater flexibility during the reload core design process while maintaining the required safety margin.
The 0.95 limit on K-effective is consistent with the limit specified in the Westinghouse Standard Technical Specifications. provides the proposed change to Sections 3.8.A and 3.10.A of the Surry Technical Specifications. provides a Safety Evaluation of the changes.
This *request has been reviewed 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 an unreview.~d safety question as defined in 10CFR50.59 nor does it pose a significant hazards consideration.as defined in 10CFR50.92.
We have evaluated this request in accordance with the criteria in 10CFR170.12.
An application fee in the amount of $150 is warranted. With
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VIRGINIA ELECTRIC t::ND Pow:im COMPANY TO Mr. Harold R. Denton reference to your letter dated August 16, 1985, we wish to apply Check No.
48858 dated October 9, 1984 to this application fee.
We request your approval of the Technical Specification changes by January 15, 1986 in order to ensu~e that the revised Technical Specifications are in place in time for use with the Surry 1 Cycle 9 reload design analysis.
Very truly yours,
~l~
W. L. Stewart Attachments
- 1.
Proposed Technical Specification Change
- 2.
Safety Evaluation cc:
Dr. J. Nelson Grace Regional Administrator Region II Mr. Terence L. Chan NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219
e COMMONWEALTH OF VIRGINIA)
)
CITY OF RICHMOND
)
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 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 'a,~
day of My Commission expires:
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