ML18149A117
| ML18149A117 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 04/21/1986 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| 86-169, NUDOCS 8604280362 | |
| Download: ML18149A117 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWABT VxcE PRESIDENT Nu CLEAR OPERATIONS April 21, 1986 Mr. Harold R. Denton, Director 1
Office of Nuclear Reactor Regulation Attn:
Mr. Lester S. Rubenstein, Director PWR Project Directorate No. 2 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NO. 1 RELOAD INFORMATION FOR CYCLE 9 Serial No.86-169 E&C/GMS/asp Docket No.
50-280 License No.
DPR-32 Surry Unit No. 1 will complete its eighth cycle of operation on or about May 9, 1986.
The purpose of this letter is to advise you of our plans for the Cycle 9 reload core.
During Cycle 8 operation, Surry Unit 1 experienced levels of primary coolant radioactivity which, although well within the limits of the Technical Specifications, were indicative of fuel element defects in the core.
As a result of the primary coolant activity, Virginia Electric and Power Company will examine the fuel assemblies to identify those assemblies containing fuel defects.
As in previous fuel rod examination programs, this program will consist of ultrasonic inspection, visual inspection via binoculars and high magnification television, and fuel assembly cleaning, if required.
Based upon these fuel inspections, the Virginia Electric and Power Company will develop the Surry 1 Cycle 9 reload core design using irradiated fuel assemblies determined to be acceptable for reuse.
We intend to perform this redesign process in accordance with the provisions of 10 CFR 50.59, thereby minimizing the licensing impact of the inspection program.
- However, in the event that Technical Specifications changes or accident re-analysis requiring prior _NRC review and approval are necessary to support Cycle 9 operation, we will be contacting you to request an expeditious review.
8604280362 860421 PDR ADOCK 05000280 P
We have discussed the upcoming Surry 1 fuel inspection and redesign effort with the NRC Surry Project Manager and will keep him apprised of any significant developments.
Please contact us if you have questions or require additional information at this time.
Very truly yours,
'JL~
W. L. Stewart cc:
Dr. J. Nelson Grace Regional Administrator Region II Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A NRC Senior Resident Inspector Surry Power Station