ML18139C122
| ML18139C122 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/09/1982 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 621, NUDOCS 8211160388 | |
| Download: ML18139C122 (2) | |
Text
Vepco VIRGINIA ELECTRIC AND POWER COMPANY, RICHMOND, VIRGINIA 23261 November 9, 1982 Mr. Harold R. Denton, Director Offfce of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D,C.
20555 Gentlemen:
Serial No. 621 FR/NAS:bjc Docket No.:
50-280 License No.: DPR-32 RELOAD INFORMATION FOR CYCLE 7 SURRY NUCLEAR POWER STATION UNIT N0.1 Surry Unit 1 is scheduled to complete its sixth cycle of operation in February of 1983.
The purpose of this letter is to advise you of our plans for the Cycle 7 reload core.
The Cycle 7 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled "Westinghouse Reload Safety Evaluation Methodology."
The results indicated that no key analysis parameters would become more limiting during Cycle 7 operations than the values assumed in the currently applicable safety analysis.
Further, the analysis demonstrated that the current Technical Specifications, as approved through Amendment No. 80, are appropriate and require no additional changes.
A detailed review of the Westinghouse methodology, analysis techniques and results has been conducted by our technical staff.
In addition, review µas 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 10CFR 50.59 will exist as a result of the Cycle 7 reload core.
Verification of the reload core design will be performed through a startup physics testing program.
Unless otherwise indicated, this program will be consistent with documentation provided in our topical
!Jool report VEP-FRD-36A, "Control Rod Reactivity Worth Determination by the Rod Swap Technique," transmitted by our letter to you dated January 16, 1981 (Serial No. 023).
This report is a revision of VEP-FRD-36, an earlier topical report of the same title.
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Mr. Harold R. Denton 2
This letter is provided for your information.
However, should you have questions, please contact us at your earliest convenience.
Very truly yours, OL~
W. L. Stewart Vice President Nuclear Operaions cc:
Mr. James P. O'Reilly, Regional Administrator Region II