ML20066F951
| ML20066F951 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/18/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20066F953 | List: |
| References | |
| 91-015, 91-15, NUDOCS 9101240288 | |
| Download: ML20066F951 (2) | |
Text
__-
Vina:NIA Ei.ucrule wo Powr;u COMMY Incmtoxo,Vinoam conos January 18,1991 United States Nuclear Regulatory Commission Serial No.. 015--
Attention: Document Control Desk NL&P/JYR:Jmj Wachington, D.C. 20555 Docket No.
50 538 License No.
NFF 4 Gentlemen:
VIRGINIA ELECTRIC-AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 TECHNICAL SPECIFICATION RERORTING REQUIREMENTS FOR THE CORE SURVEILLANCE REPORT FOR CYCLE 9 North Anna Unit 1 has completed its eight.h cycle of operation on~ January 12,1991 and has entered into an outage for refueling. The purpose of this letter is to advio you-of our plans for the Cycle 9 reload core and to tiansmit to you the Core Sv'veillance -
Report containing specific power distribution limits applicable for Cycle 9 operation.
Technical Specification-6.9.1.7 requires-that the Core Surveillance Report be submitted to the NRC sixty days prior to this inforn ation-becoming. effective (Cycle 9 is currently scheduled for criticality on March 12, 1991.) However, the Technical-Specification provides for an alternate submittal date with NRC written approval.
Therefore, in.accordance with_ this Technical Spealfication provision,3we request the sixty day advance submittal requirement of Tec'inical Specification 6.9.1.7 be waived.
by the NRC.
The Cycle' 9 reload core was: analyzed in accordance with -the methodology documented in the approved topical report VEP FRD 42, Revision 1 A, " Reload i
Nuclear Design Methodology," using NRC approved codes as 1eferenced in the topical. The information in the report was developea.in scordance with our topical report VEP-NE 1-A," Relaxed Power Distribution Control Methodology and Associated-FQ Surveillance Technical Specification.".These analyses were performed and reviewed by our technical staff. The results of these analyses indicated that the currently applicable safety analyses remain bounding for Cycle 9 operation. Further, the e.nalyses demonstrated that the current Technical Specificailons are appropriate-and require no additional changes.
A :...'aw has been performed by the Station Nuclear Safety and Operating Committee.
It has been determined that no unrevi6wed safety question as defined in 10 CFR 50.59 will exist as a result of the Cycle 9 reload core.
l l
9101240288 910118
{DR ADOCK0500g8 y/
q
l
. provides the Core Surveillance Report which consists of the specific Cycle 9 values for N(Z) and Axial Flux Difference Limits. These lirnits are based upon the current total peaking factor (Fq) limit of 2.19.
This letter is provided for your information and planning. However, should you have questions, please contact us at your earDes, convenience.
Very truly yours,
$ h3 W. L. Stewart Senior Vice President - Nuclear Attachment
- 1. Core Surveillance Report for North Anna 1, Cycle 9 cc:
United States Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station i
o 1