ML20039C254

Submits Updated Status of Cycle 4 Reload,Documenting That Application for OL Amend Is Not Required.Reload Safety Evaluation Demonstrated That No Tech Spec Changes Are Needed for Operation During Cycle 4.Design to Be Verified

ML20039C254
Person / Time
Site:	Farley
Issue date:	12/18/1981
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8112290130
Download: ML20039C254 (2)

Text

M2iling Addrsts Alabama Power Company 600 North 18th Street Post Office Box 2641 Bermmg5am. Alabams 35291 7

Telephone 205 783-6081 F. L Clayton, Jr.

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Docket No. 50-348 RECUED E

DEC 2 81981" ;

Director of Nuclear Reactor Regulation M n.

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U. S. Nuclear Regulatory Comission Washington, D. C.

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Attention: Mr. S. A. Varga JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 1 CYCLE 4 RELOAD

Dear Mr. Varga:

Joseph M. Farley Nuclear Plant Unit 1 is currently undergoing a refueling outage coincident with turbine generator repair with criticality for Cycle 4 scheduled for March, 1982. The Cycle 4 core was designed to perform under current design parameters, Technical Specifications and related bases, and current setpoints.

Cycle 4 is composed of a total of 32 Region 6, 52 Region 5, 50 Region 4, 2 Region 4A, 20 Region 3, and 1 J

Region 1 fuel assemblies. The newly inserted Region 6 fuel assemblies' mechanical, nuclear and thermal hydraulic designs are identical to the standard assemblies currently used. The demonstration assemblies which were described in WCAP-9286, July, 1978 pricipally incorporate reduced fuel rod diameter and the use of Zircalloy spacer grids for all but the top and bottom grid locations. 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 l

during transient conditions analyzed than for the standard fuel assemblies.

These demonstration assemblies were used previously in Cycles 2 and 3.

Alabama Power Company performed a detailed review of the Westinghouse Reload Safety Evaluation Report (RSER) for Farley Unit 1, Cycle 4, including all postulated incidents considered in the FSAR and the fuel densification report, WCAP-8291-A, March, 1975. The RSER included a review of the core characteristics to determine those parameters affecting the postulated accident analyses reported in the Farley FSAR. The incidents whose consequences could potentially be affected by the reload core characteristics were reanalyzed. Alabama Power Company verified that the reanalyses were performed in accordance with the Westinghouse reload safety evaluation methodology as outlined in the March,1978 Westinghouse topical report entitled,

" Westinghouse Reload Safety Evaluation Methodology," (WCAP-9272). The results of these reanalyses were verified to be within previously reviewed OOl and accepted limits. Additionally, Alabama Power Company has verified that y

the Cycle 4 design precludes the two special test assemblies from becoming more limiting than the standard design assemblies during both normal 7g operation and transient conditions.

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6 Director of Nuclear Reactor Regulation December 18, 1981 U.S. Nuclear Regulatory Commission Page 2 The reload safety evaluation demonstrated that Technical Specification changes are not required for operation of Farley Unit 1 during Cycle 4.

Alabama Power Company's Plant Operations Review Committee and Nuclear Operations Review Board have concluded that no unreviewed safety questions as 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 performed per the standard startup physics tests normally performed for Westinghouse PWR reload cycles.

Sincerely yours, Y h clc' F. L. b ayton,fr; d FLCJr/MDR:jc-cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford