ML18153B606
| ML18153B606 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/06/1989 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 88-117A, NUDOCS 8902130288 | |
| Download: ML18153B606 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. R. CARTWRIGHT Vl.CE PR.ESID.ENT NUCLEAR February 6, 1989 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 RELOAD INFORMATION FOR CYCLE 10 Serial No.
88-ll?A NO/
Docket No.
50-280 License No.
DPR-32 Surry Unit No.
1 started its 10th cycle of operation on July 14, 1988.
Shortly after startup, the primary coolant activity registered a step increase, indicative of fuel failure.
When Unit No. 1 shut down on September 14, 1988 to address other concerns, we also inspected the core for the failed fuel.
The failed assembly was identified and replaced with another assembly of similar reactivity characteristics. The integrity of the assemblies to be reused in the Cycle 10 redesigned core was certified by the inspection program.
The redesigned Cycle 10 core reload was analyzed in accordance with the methodology documented in Virginia Electric and Power Company Topical Report VEP-FRD-42, Rev. 1-A, 11Reload Nuclear Design Methodology, 11 using NRG-approved codes as referenced in the topical. These analyses were performed and reviewed by our technical staff.
The key safety analysis parameters were compared to the limit values defined by the currently applicable Safety Analyses.
The results of this evaluation demonstrated that the existing Safety Analyses remain bounding and no new Safety Analysis is required.
In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that no unreviewed safety questions as defined in 10 CFR 50.59 will exist as a result of operation with the Cycle 10 reload core.
In addition, no Technical Specifications changes are required as a result of Cycle 10 operation with this core loading pattern.
This letter has been provided for your information.
Should you have any questions, please contact us at your earliest convenience.
Very truly yours, cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. B. C. Buckley NRC Surry Project Manager Project Directorate II-2 Division of Reactor Projects - I/II