ML20064A871
| ML20064A871 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/11/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20064A872 | List: |
| References | |
| 90-533, NUDOCS 9010010109 | |
| Download: ML20064A871 (2) | |
Text
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9' VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 11,1990 United Statt s Nuclear Regulatory Commission Serial No.
90 533 Attention: Document Con 9o1 Desk NL&P/JYR:Jmj Washington, D.C. 20555 Docket No.
50 339 License No, NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPAE NORTH ANNA POWER STATION UNIT NO. 2 RELOAD INFORMATION FOR CYCLE 8 North Anna Unit 2 completed its seventh cycle of operation on August 21,1990 and entered into an outage for refueling. The purpose of this letter is to advise you of our plans for the Cycle 8 reload core and to transmit to you the Core Surveillance Report containing specific power distribution limits applicable for Cycle 8 operations.
The Cycle 8 reload core was analyzed in accordance with the methodology 1
documented in the approved topical report VEP-FRD-42, Revision 1-A, " Reload i
Nuclear Design Methodology," using NRC approved codes as referenced in the 1
topical,.The information in the repor1 was developed in accordance with our topical report VEP NE 1 A," Relaxed Power Distribution Control Methodology and Associated FO Surveillance Technical Specifications." These analyses.were pedormed and reviewed by our technical staff. The results of these analyses indicated that no key analysis parameters would become more limiting during Cycle 8 operation than the values assumed in the currently applicable safety analyses. Further, the analyses demonstrated that the current Technical Specifications are appropriate and require no additional changes, A review has been performed by the Station Nuclear Safety and Operating Committee, it has been determined that no unreviewed safety question as defined in 10 CFR 50.59 will exist as a result of the Cycle A reload core. provides the Cote Surveillance Report which consists of the specific Cycle 8 values for N(Z) and the Axial Flux Difference Limits. These limits are based upon the current total peaking factor (Fq) limit et 2.19,
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1 If r. re, design of the Cycl 6 o core is required because of fai!ed fuelin the Cycle 7 core, j
the attached Core Surveillance Report may be revised, in addition, a walver of Technical SpcMication 6.9.1.7, 60 day advance notice requirement would be required.
Should the proposed Technical Specifications in our August 8,1990 submittal, "Techniaal Specification Change Per Requirements of Generic Letter 88-16," be approved prior to the completion of a Cycle 8 redesign, a Core Operating j
Limits Report with wased core surveillance information will be provided in accordance s
with the specifications outlined in our submittal.
l This letter is provided for your information and planning. However, should you have questions, please contact us at your earliest convenience.
Very truly yours, as W. L. Stewart Senior Vice President - Nualear Attachment 1.
Core Surveillance Report iar North Anna 2, Cycle 8 cc:
United States Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station 1
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