ML20058C161
| ML20058C161 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/25/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20058C164 | List: |
| References | |
| 90-533B, NUDOCS 9011010015 | |
| Download: ML20058C161 (2) | |
Text
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s-e VIHOINIA I$1.ECTHIC AND POWER COMPANY i
RICIIMOND,VIHotNIA 20201
[
October 25,1990 i
United States Nuclear Regulatory Commission Serial No.
90-533B Attention: Document Control Desk NL&P/JYR:Jmj l
Washington, D.C, 20555 Docket No.
50-339 License No.
N PF !
Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 REVISED RELOAD INFORMATION FOR CYCLE 8 i
North Anna Unit No. 2 completed its seventh cycle of operation on August 21,1990 and entered into an outage for refueling. A redesign of the Cycle 8 core necessitates a revision to the Core Surveillance Report previously transmitted to you (" Reload Information for Cycle 8," Serial No. 90 533, dated September 11, 1990).
We requested a waiver of the 60 day advance submittal requirement of Technical Specification 6.9.1.7 (" Technical Specification Reporting Requirements for the Core Surveillance Report," Serial No. 90 533A, dated October 4,1990) and proposed a revised submittal date for the Core Surveillance Report. This letter transmits to you the revised Core Surveillance Report for the redesigned Cycle 8 core.
The Cycle 8 reload core was. analyzed in accordance with the methodology-documented in the approved topical report VEP FRD 42, Revision 1-A, " Reload Nuclear Design Methodology," using NRC approved code: as referenced in the topical. The information in the report 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 performed and reviewed by our technical staff. The resultr of these analyses indicated that no key analysis parameters would become more i.miting 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 8 reload core.
, proviaes the Core 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 of 2.19.
9011010015 9o102'i PDR ADOCK 0500o339 dog l
F PDF 9i s
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'This letter is provided for you: Information end planning. However, should you have questions, please contact us at your earliest conven!ance.
Very truly yours,
'/ (R4
'O t'f W. L. Stewart Senior Vice President Nuclear Attachment
- 1. Core Surveillance Report for North Anna 2, Cycle 8 x:
United States Nuclear Regulatory Comm!ssion Region ll 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S, Lesser NRC Senior Resident inspector i
North Anna Power Station i
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