ML20214V025
| ML20214V025 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/03/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-179A, NUDOCS 8706110412 | |
| Download: ML20214V025 (2) | |
Text
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Tech. Spec. 6.9.1.7 VIROINIA ELECTRIC AND Powna COMPANY RIcumown,VINGINIA 20261 W. L. Srawant vaca Passionny NuctaAm Oramartone June 3, 1987 U. S. Nuclear Regulatory Commission Serial No. 87-179A Attn: Document Control Desk E&C/JYR:ssb Washington, D. C.
20555 Docket No. 50-338 License No. NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 RELOAD INFORMATION FOR CYCLE 7 REDESIGNED CORE
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North Anna Unit No. 1 is currently in its Cycle 6/7 refueling outage. We have completed the fuel examination and core redesign program described to you in our letter dated April 13, 1987 (Serial No.87-179). The fuel rod examination J
program has consisted of ultrasonic testing _ and visual inspection via binoculars and high magnification TV.
As a result of these inspections, the 4
Company has developed a revised Cycle 7 reload _ core design.
Two assemblies with known failures were replaced with other assemblies from our spent fuel
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pool.
The Cycle 7 reload core was analyzed in accordance with the methodology j
documented in the approved topical report VEP-FRD-42, Rev. 1-A, " Reload Nuclear Design Methodology," using NRC approved codes as referenced in this topical report.
The results of these analyses indicated that no key analysis parameters would become more limiting during Cycle 7 operations than the values assumed in the currently applicable safety analyses. Further, the analyses demonstrated that the current Technical Specifications, as approved through Operating License Amendment No. 95, are appropriate and require no additional changes.
In our letter dated April 13, 1987, we provided the Cycle 7 Core Surveillance Report as required by North Anna Unit No. 1 Technical Specification 6.9.1.7.
The Cycle 7 Core Surveillance Report values for Fxy and the axial power distribution surveillance limit, Pm remain unchanged by the redesign of the Cycle 7 reload core.
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4 The analyses necessary to support Cycle 7 operation have been performed and reviewed by.our technical staff.
In addition, a review has 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 10CFR50.59 will exist as a result of the Cycle 7 reload Core.
Very truly yours,
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W. L. Stewart
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1 cci U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station l
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