ML18152A793

Advises of Plans for Cycle 10 Core Reload.Cycle Will Mark First Use of Facility Improved Fuel Product.Cycle 10 Core Reload Analyzed Per Methodology Documented in Util Topical Rept VEP-FRD-42,Rev 1-A, Reload Nuclear Design....

ML18152A793
Person / Time
Site:	Surry
Issue date:	03/22/1988
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-117, NUDOCS 8803310148
Download: ML18152A793 (2)

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• e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE Pl<ESIDENT March 22, 1988 NUCLEAR 0PE:RATIONS U. S. Nuclear Regulatory Commission Serial No.88-117 Attn: Document Control Desk E&C/RCA/cdk Washington, D.C. 20555 Docket No. 50-280 License No. DPR-32 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 RELOAD INFORMATION FOR CYCLE 10 Surry Unit No. 1 is scheduled to complete its 9th cycle of operation on April 2, 1988. The purpose of this letter is to advise you of our plans for the Cycle 10 core reload. This cycle will mark the first use of the Surry Improved Fuel product, approved by your staff in their letter of January 6, 1988.

The Cycle 10 core reload was analyzed in accordance with the methodology documented in Virginia Electric and Power Company Topical Report VEP-FRD-42, Rev. 1-A, "Reload Nuclear Design Methodology, 11 using NRC approved codes as referenced in the topical. These analyses were performed and reviewed by our technical staff. The results of these analyses indicated that no key analysis parameters would become more limiting during Cycle 10 operations than the values assumed in the currently applicable Safety Analyses. 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 10 reload core. In addition, no Technical Specifications changes are required as a result of Cycle 10 operation with this core loading pattern.

During Cycle 9 operation, Surry Unit 1 has experienced levels of primary coolant radioactivity which, although well within the limits of the Technical Specifications, were indicative of one or two fuel element defects in the core. As a result of the primary coolant activity, Virginia Electric and Power Company will examine the fuel assemblies to identify those assemblies containing fuel defects. This program will consist of ultrasonic and visual inspec-tions.

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Based upon these fuel inspections, the Virginia Electric and Power Company will, if necessary, redesign the Surry 1 Cycle 10 reload core using irradiated fuel assemblies determined to be acceptable for reuse. We intend to perform any redesign process in accordance with the provisions of 10 CFR 50.59, thereby minimizing the licensing impact of the inspection program. However, in the event that Technical Specifications changes or accident re-analysis requiring prior NRC review and approval are necessary to support Cycle 10 operation, we will be contacting you to request an expeditious review.

This letter has been provided for your information. Should you have any questions, please contact us at your earliest convenience.

Very truly yours, cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-I/II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219