ML20052A904

Advises of Plans for Cycle 4 Reload Core Analysis Per Methodology Documented in WCAP-9272, Westinghouse Reload Safety Evaluation Methodology. Core Surveillance Rept Containing Specific Power Distribution Limits Encl

ML20052A904
Person / Time
Site:	North Anna
Issue date:	04/23/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Denton J Office of Nuclear Reactor Regulation
References
254, NUDOCS 8204290365
Download: ML20052A904 (5)

Text

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e VIROINIA ELECTRIC AND POWER COMmNY HICIIM OND, VIHOINIA 2 0 2 61

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April 23, 1982

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Mr. Harold R. Denton, Director Serial No-254 Of fice of Nuclear Reactor Regulation FR/GLD: sbw Attn:

Mr. Robert A. Clark, Chief D cket No: 50-338 Operating Reactors Branch No. 3 Division of Licensing License No: NPF-4 U. S. Nuclear Regulatory Commission Washington, D.

C.

20555 Centlemen:

RELOAD INFORMATION FOR CYCLE 4 NORTH ANNA NUCLEAR POWER STATION UNIT NO.1 North Anna Unit No. 1 is scheduled to complete its third cycle of operation on May 21, 1982 and will go into an outage for refueling. The purpose of this letter is to advise you of our plans for the Cycle 4 reload core and to transmit to you the Core Surveillance Report containing specific power distribution limits applicable for Cycle 4 operation.

The Cycle 4 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled

" Westinghouse Reload Safety Evaluation Methodology." The results of this analysis indicated that no key analysis parameters would become more limiting during Cycle 4 operations than the values assumed in the currently applicable safety analysis.

Further, the analysis demonstrated that the current Technical Specifications, as approved through Operating License Amendment No.

38, are appropriate and require no additional changes.

A detailed review of the Westinghouse methodology, analysis tech-niques 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 Safety Evaluation and Control staff.

It has been determined that no unreviewed safety questions as defined in 10 CFR 50.59 will exist as a result of the Cycle 4 reload core.

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i visoix 4 Es.mcTaic axo Powra coxe4xy to Mr. Harold R. Denton provides the Core Surveillance Report containing the specific Cycle 4 values for Fxy and the axial power distribution surveillance limit, Pm.

This report is being provided as required by North Anna Unit No.

1 Technical Specification 6.9.1.10 and is based on the recently approved total peaking factor (Eq) limit of 2.14.

Verification of the reload core will be performed through a startup physics testing program.

Unless otherwise indicated, this program will be consistent with the program proposed for North Anna Unit No. 2 in my letter to you dated April 8,1982, Serial No. 204.

This letter is provided for your information. However, should you have questions, please contact us at your earliest convenience.

Very truly yours,

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R. H. Leasburg Attachment (1) Core Surveillance Report for North Anna 1, Cycle 4 cc:

Mr. James P. O'Reilly, Regional Administrator Office of Inspection and Enforcement Region II i

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4 ATTACHMENT 1 Core Surveillance Report North Anna 1, Cycle 4 L

1 of 2 TABLE 1 NORTH ANNA UNIT 1, CYCLE 4 CORE SURVEILLANCE LIMITS, F2 = 2.14 core planes I.

The F-XY limits for RATED THERMAL POWER within specific shall bei 1.

Txy-RTP

$ 1.71 for all core planes containing bank "D"

control rods, and 2.

Fxy-RTP f 1.60 for all unrodded core planes.

II.

The axial power distribution surveillance threshold power level shall bei 100% of RATED THERMAL POWER.

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