ML18150A104
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| ML18150A104 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/26/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18150A105 | List: |
| References | |
| 87-188, NUDOCS 8706010272 | |
| Download: ML18150A104 (2) | |
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|---|---|
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Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e iO CFR 50.90 W. L. STEWART May 26, 1987 VICE PRESIDENT NUCLEAR OPERATIONS U. S. Nuclear Regulatory Commission Seri a1 No.87-188 Attn: Document Control Desk E&C/NPW/gmj 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 SURRY IMPROVED FUEL ASSEMBLY Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively.
These amendments are submitted to support a planned fuel design change from the Westinghouse Low Parasitic 15x15 (LOPAR) Fuel Assembly to the 15xl5 Surry Improved Fuel Assembly (modified Westinghouse 15x15 Optimized Fuel Assembly).
The new assembly design utilizes Zircaloy grids and smaller diameter thimble tubes. As a consequence of smaller diameter thimble tubes, a change to the Technical Specification governing the maximum allowable control rod drop time is being requested. In addition, a change is being requested to the design DNBR limit to accommodate the use of the WRB-1 DNB correlation with the new fuel assembly. The proposed changes to the Technical Specifications are provided in Attachment 1 and are needed to support initial use of the Surry Improved Fuel in Surry Unit 1 Cycle 10. Attachment 2 provides a safety evaluation and significant hazards determination of the fuel assembly design change.
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 questions as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92.
e We have evaluated this request in accordance with the criteria in 10 CFR 170.12. A voucher check in the amount of $150.00 is enclosed as an application fee.
Very truly yours,
~L~
W. L. Stewart Attachments
- 1. Proposed Technical Specification Changes
- 2. Safety Evaluation for Fuel Assembly Design Change
- 3. Application Fee cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A Mr. William E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219
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