ML19340C291

Advises That Application to Amend OL Is Not Required for Operation During Cycle 3 Since No Unreviewed Safety Questions Are Involved W/Reload.Results of Std Tests & Core Loading Map Will Be Submitted within 90 Days of Startup

ML19340C291
Person / Time
Site:	Farley
Issue date:	10/31/1980
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8011140448
Download: ML19340C291 (2)

Text

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- Alabtma Power Comptny

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• 600 North 18th street Post Ctfics Box 2641 eermmgnam. Alabama 35291

. Telephone 205 250-1000 ,,,

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! F. L. CLAYTON, JR.

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i senior vice President . Alabama Power

' tb scomern electic sistem -

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I October 31, 1980

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! Docket No. 50-348 '

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i Director of Nuclear Reactor Regulation i

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U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. Varga L

J. M. FARLEY UNIT 1 CYCLE 3 RELOAD J

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Dear Mr. Varga:

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! Farley Unit 1 is currently in its second cycle of operation with a

! refueling outage scheduled to. commence early November 1980. Cycle 2 operation will be terminated within a cycle burnup range of 9,000 to 10,500 MWD /MTV. This letter is to advise you of Alabama Power Company's

! review of and plans regarding the Farley Unit 1, Cycle 3 reload core.

l The Farley Unit 1, Cycle 3 reload core was designed to perform under

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current nominal design parameters, Technical Specifications and related

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bases, and current setpoints. A total of 1 Region 1, 52 Region 3, i 50 Region 4, 2 demonstration assemblies designated as 4A, and 52 Region 5 assemblies will be inserted at the refueling outage. The mechanical, nuclear and thermal hydraulic design of the Region 5 fuel assemblies is identical except for enrichment to the standard 17x17 fuel assemblies currently operating in Cycle 2. The Region 4A assemblies are special test assemblies of a new Westinghouse design as described in the Westinghouse report entitled, "Octimized Fuel Assembly Demonstration Program," (WCAP-9286) July 1978. This new design involves several minor design changes, principally the reduction in fuel rod diameter and the incorporation of Zircalloy spacer grids for all but top and bottom grid lo.:ations. These assemblies currently perform as part of Cycle 2 ~

l core. The reload core design places these test assemblies into core locations that prevent them from becoming lead assemblies during normal operation or leading to more limiting conditions during transient conditions

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than analyzed for the standard design fuel assemblies.

Alabama Power Company performed a detailed review of the Westinghouse Reload Safety Evaluation Report (RSER' for Farley Unit 1, Cycle 3, including

' all postulated incidents considered in the FSAR and the fuel densification j i report. The RSER included a review of the core characteristics to determine j l [OCd

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Mr. S. Varga October 31, 1980 those parameters affecting the postulated accident analyses reported in the Farley FSAR. Alabama Power Company concluded that Cycle 2 design parameters are conservative with respect to those assumed in the FSAR; therefore, no accident was rea,alyzed based on Cycle 3 parameters. This is consistent with the Westinghouse reload safety evaluation methodology as outlined in the March 1978 Vestinghouse topical report entitled,

" Westinghouse Reload Safety Evaluation Methodology," (WCAP-9272).

3.dditionally, Alabama Power Company has verified that the Cycle 3 design precluded the two special test assemblies from becoming more limiting than the standard design assemblies during both normal operation and transient conditions.

The reload safety evaluation demonstrated that Technical Specification changes are not required for operation of Farley Unit I during Cycle 3.

Alabama Power Company's Plant Operations Review Committee and Nuclear Operations Review Board have concluded that no unreviewed safety questions defined by 10 CFR 50.59 are involved with this reload. Therefore, based on this review, application for amendment to the Farley Unit 1 operating license is not required.

Verification of the reload core design will be perfomed per the standard startup physics tests normally performed for Westinghouse PWR reload cycles. These tests will included, but not be limited to:

(1) Control rod drive tests and drop time; (2) Critical boron concentration measurements; (3) Control rod bank worth measurements; (4) Moderator temperature coefficient measurement; (5) Startuo power distribution measurements using the incore flux mapping system.

Results of these tests and a core loading map will be submitted within ninety (90) days of startup of Cycle 3.

Yours very truly,

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F. L. Clayton, J r. -

4 MDR:rt cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. E. A. Reeves Mr. W. H. Bradiord