ML20093D848
| ML20093D848 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/09/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 365, NUDOCS 8407170251 | |
| Download: ML20093D848 (2) | |
Text
. _ _ _ _
.N VIHOINIA ELucTnIc Axn Powna COMPANY nicnwoxn, Vino 1xrA canon W.L.stam ar xd7dE.2"...
July 9, 1964 Mr. Harold R, Denton, Director Serial No. 365 Office of Nuclear Reactor Regulation PSE/NAS:vdu:2001N Attn: Mr. Steven A. Varga, Chief Docket No.:
50-281 Operating Reactors Branch No.1 License No.: DPR-32 Division of Licensing U. S. Nuclear Regulatory Conmission Washington, D. C.
20555 Gentlemen:
RELOAD INFORMATION FOR CYCLE 8 YURRY POWER STATION UNIT N0. 1 Surry Unit No.1 is currently scheduled to complete its sevent'h cycle of operation on or about September 28, 1984. The purpose of this letter is to advise you of our plans for the Cycle 8 reload core.
The Cycle 8 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled " Westinghouse Reload Safety Evaluation Methodology". The results of this analysis indicated that no key analysis parameters will become more limiting during Cycle 8 operation than the values assumed in the currently applicable Safety Analyses.
.The Cycle 8 reanalysis demonstrated that the current Technical Specifications, as approved through Amendment Nos. 95 and 96 for Surry Units 1 and 2, re-spectively, are appropriate and require no additional changes.
The analyses necessary to support Cycle 8 operation have been performed and reviewed by our technical staff, using the Westinghouse methodology and analysis techniques.
In addition, a review has been performed by both the Station Nuclear Safety anc' Operation Committee and the Safety Evaluation and Control. s taff.
It has been determined that no unreviewed safety questions as defined _in 10 CFR 50.59 will exist as a result of the Cycle 8 reload core.
During Cycle 7 operation, Vepco experienced levels of primary coolant radioactivity which, although within the limits of the Technical Specifications, were indicative of fuel element defects in the core. As a result of the primary coolant activity, Vepco is planning a fuel examination program to identify the assemblies containing fuel defects. You will be notified if a redesign of the
-Cycle 8 loading pattern is-required, and we will inform you by approximately November 1,1984 of the results of our evaluation of the alternate loading pattern in accordance with'10 CFR 50.59.
8407170251 840709 PDR ADOCK 05000281 p
P PM I Q
i vIkOINIA Es.zcTate Awo POwzu COMPANY TO Mr. Harold R. Denton, Director In the. event that Technical Specification changes are required to support Cycle 8 operation with a revised core loading pattern, we will be contacting you to request expeditious review of the change request.
This accelerated review would be needed to support our current operating schedule which calls
- for Cycle 8 startup by app *oximately December 14, 1984.
This letter is provided for your information and planning. However, should you have questions, please contact us at your earliest convenience.
Very truly yours,
/
fi{dQr e
W. L. Stewart cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No.1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station L.
..