ML20206A441
| ML20206A441 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/01/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20206A446 | List: |
| References | |
| 86-699, NUDOCS 8704080033 | |
| Download: ML20206A441 (3) | |
Text
,o VINGINIA ELEC'THIC AND PownN CoxiwNY Hicitwoxn,VIHOINIA 20261 W.L.STEWANT vice v==.mawr April 1, 1987 NecLaam ormEATIONB U. S. Nuclear Regulatory Commission Serial No.86-699 Attn: Document Control Desk E&C/NPW/pml:vlh Washington, D. C.
20555 Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE FULLY WITHDRAWN CONTROL ROD POSITION Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operat-ing License Nos. DPR-32 and 37 for Surry Power Station Units 1 and 2, respec-tively. The purpose of the amendments is to incorporate changes into the Surry Technical Specifications which govern the control rod insertion limits.
The changes will allow greater operational flexibility with respect to control rod bank positioning as a means of minimizing localized rod cluster control assembly (RCCA) wear.
Based on recent control rod examinations, Westinghouse has determined that the RCCA fretting wear may reach the Westinghouse recommended maximum as early as 74,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of critical operation time.
Repositioning the RCCA banks is estimated to result in a gain of 37,000 additional hours of critical operation time. Since both Surry Units 1 and 2 are at the recommended criteria, a Technical Specification change is being requested to change the fully withdrawn position from 228 steps to 225 steps.
I Figures 3.12-1A and 3.12-1B of the Technical Specifications have been modified to reflect the change in the fully withdrawn position. The bank overlap and the actual insertion positions as a function of power have not changed.
For ease of interpretation and consistency with Westinghouse Standard Technical l
Specifications the insertion limit curves have been changed from fraction inserted to rod group step position.
Fully withdrawn is indicated on this figure as 225 steps. The proposed changes to the Technical Specifications are provided in Attachment 1.
Our safety evaluation supporting the proposed changes is provided in Attachment 2.
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 any unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR i
50.92.
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We have evaluated this request in accordance with the criteria in 10 CFR 170.
A voucher check in the amount of $150.00 is enclosed as an application fee.
Very truly yours, y
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W. L. Stewart Attachments 1.
Proposed Technical Specification Changes 2.
Safety Evaluation for Change to RCCA Fully Withdrawn Position 3.
Voucher Check cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. William Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate #2 Division of PWR Licensing-A
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
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