ML19341B093
| ML19341B093 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/27/1981 |
| From: | Thomas W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 045, 45, NUDOCS 8101300188 | |
| Download: ML19341B093 (1) | |
Text
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VinoixA ELucrHIC AND POWE N COM PANY Ricnwoxn,VauorxzA SUubt hT 2 0 lhhf b v.s.maene,w w p
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January 27, 1981 g
- ium Mr. Harold R. Denton, Director Serial N. *7 5
h Office of Nuclear Reactor Regulation M
g /g Attn:
Mr. Robert A. Clark, Chief FR/WCB: mvc Operating Reacters Branch No. 3 Division of Licensing Docket No.:
50-338 U. S. Nuclear Regulatory Commission Washington, DC 20555 License No.: NPF-4
Dear Mr. Denton:
RELOAD INFORMATION FOR CYCLE 3 NORTH ANNA NUCLEAR POWER STATION UNIT 1 Norch Anna Unit No. 1 completed its second cycle of operation on December 28, 1980 and went into an outage for refueling. The purpose of this letter is to advise you of our plans for the Cycle 3 reload core.
The Cycle 3 reload core was analyzed in accordance with the methodo-logy docu=ented in Westinghouse topical report WCAP-9272 entitled " Westinghouse Reload Safety Evaluation Methodology." The results of this analysis indicated that no key analysis parameters would b'ecome more limiting during Cycle 3 operation than assumed in the currently applicable safety analysis. Therefore, no accident reanalysis was required.
Further, the analysis demonstrated that the current Technical Specifications, as approved through Amendment No. 23, 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, a review has been performed by both the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee.
It has been determined that no unreviewed safety questions as defined in 10 CFR 50.59 will exist as a result of the Cycle 3 reload core.
l Verification of the reload core will be performed through a startup physics testing program.
Unless otherwise indicated, this program will be consistent with documentation provided in our topical report VEP-FRD-36A, "Contral Rod Reactivity Wor *.h Determination by the Rod Swap Technique,"
I transmitted by our letter to you dated January 16, 1981, Serial No. 023.
l This letter is provided for your information.
However, should you l
have questions, please contnet us at your earliest convenience.
Verytrulyyours[,
l
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- Y W. N. Thomt.s Vice President cc:
Mr. James P. O'Reilly, Director Fuel Resources Office of Inspection and Enforcement Region II I
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610 a u %M f
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