ML18149A216

Advises of Plans for Cycle 9 Core Reload.Reload Analyzed Per Methodology in Rev 1 to VEP-FRD-42, Reload Nuclear Design Methodology & Consistent W/Documentation in WCAP-9272, Westinghouse Reload Safety Evaluation....

ML18149A216
Person / Time
Site:	Surry
Issue date:	07/10/1986
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Rubenstein L Office of Nuclear Reactor Regulation
References
86-169A, NUDOCS 8607170380
Download: ML18149A216 (2)

Text

• " ... e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS July 10, 1986 Mr. Harold R. Denton, Director Serial No. 86-169A Office of Nuclear Reactor Regulation E&C/GMS/acm Attn: Mr. Lester S. Rubenstein, Director Docket Nos. 50-280 PWR Project Directorate No. 2 License Nos. DPR~32 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NO. 1 RELOAD INFORMATION FOR CYCLE 9 Surry Unit No. 1 completed its eighth cycle of operation May 10, 1986.

The purpose of this letter is to advise you of our plans for the Cycle 9 core reload.

As discm;sed in our previous letter on this subject (Serial No.86-169, dated April 21, 1986), Virginia Electric and Power Company conducted fuel rod examinations of fuel assemblies irradiated during Surry Unit 1, Cycle

8. This program has included ultrasonic examination, visual inspection, and fuel assembly cleaning (debris removal). Based on the results of these inspections, we have developed the Cycle 9 core reload design. The fuel integrity of the irradiated fuel assemblies to be reused in the Cycle 9 redesigned core has been confirmed by the inspection program.

The Cycle 9 core reload was analyzed in accordance with the methodology documented in Virginia Electric and Power 9ompany Topical Report VEP-FRD-42, Rev. 1, "Reload Nuclear Design Methodology", using NRC approved codes as referenced in the topical. This methodology is consistent with that documented in Westinghouse Topical Report WCAP-9272, entitled "Westinghouse Reload Safety Evaluation Methodology." 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 9 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 9 redesigned reload core. In addition, no Technical

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e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr, Harold R. Denton Specifications changes are required as a result of Cycle 9 operation with the redesigned core loading pattern.

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

Very truly yours, W. L. Stewart cc: Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A NRC Senior Resident Inspector Surry Power Station Mr. A. F. Gibson, Acting Director Division of Reactor Projects