ML18153B586
| ML18153B586 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/25/1989 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18153B587 | List: |
| References | |
| 88-476A, NUDOCS 8901270322 | |
| Download: ML18153B586 (2) | |
Text
10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W.*.R. CARTWRIGHT VICE PRESIDENT NUCLEAR January 25, 1989 United States Nuclear Regulatory Commission Attention:
Document Control Desk Washingtori, D. C.
20555 Gentlemen:
. VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 INDIVIDUAL ROD POSITION INDICATION SYSTEM SUPPLEMENTAL CHANGES TO PROPOSED TECHNICAL SPECIFICATION Serial No.
NO/ETS:vlh Docket Nos.
License Nos.
88-476A 50-280 50-281 DPR-32 DPR-37 Pursuant to 10 CFR 50.90, on August 5, 1988 Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Unit Nos. 1 and 2, respectively.
The proposed Technical Specifications change, as supplemented, clarifies the operability requirements of the Individual Rod Position Indicating (IRPI)
System during a reactor startup (rod motion to achieve criticality) and power operations.
Pages changed due to this supplement to the August 5th submittal are included in Attachment 1.
The original changes and the supplemental changes to Technical Specification pages 3.12.-10 and 3.12-11 are identified with bars and double bars in the right margin respectfully.
The previously submitted safety evaluation and significant hazards considerations review for the proposed changes remain unchanged and are not resubmitted in this cor-respondence.
This supplemental change has 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 alter the original safety analysis and therefore, does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92.
C, Pursuant to 10 CFR 170 an application fee was submitted on August 5, 1988, and therefore, no fee is included with these supplemental changes.
Should you have any questions, please contact us.
Attachment Proposed Technical Specification cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. William E. Holland NRC Senior Resident Inspector Surry Power Station Mr. B. C. Buckley NRC Surry Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219