ML20069F562

Discusses Cycle 5 Core Reload.Tech Spec Changes Not Required for Operation During Cycle 5,per WCAP-9272. Verification of Reload Core Design Performed Per Std Startup Physics Tests

ML20069F562
Person / Time
Site:	Farley
Issue date:	03/17/1983
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8303230227
Download: ML20069F562 (2)

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Mailing Address Atbama Power Company

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• 600 Nonh 18th Street Post Offica Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.

Ral%;;%7"' AlabamaPbwer the southem elect!c system March 17,1983 Docket No. 50-348 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. A. Varga Joseph M. Earley Nuclear Plant - Unit 1 Cycle-5 Reload Gentlemen:

Farley Unit 1 is currently in its fourth refueling outage with Cycle-5 startup scheduled to commence in late March,1983. This letter is to advise you of Alabama Power Company's review of and plans regarding the Farley Unit 1 Cycle-5 core reload.

The Farley Unit 1 Cycle-5 core reload was designed to perform within the current nominal design parameters, Technical Specifications and related bases, and current setpoints. A total of 60 fresh fuel assemblies were utilized in the design for a Cycle-5 core total of 4 Region 1, 5 Region 3, 16 Region 4, 2 Region 4A, 50 Region 5, 40 Region 6, and 40 Region 7 fuel assemblies arranged in a low neutron leakage loading pattern. The 20 fresh Region 6 fuel assemblies are identical to the Region 6 fuel assemblies previously inserted for Cycle-4. The mechanical , nuclear and thermal-hydraulic design of the Region 7 fuel assemblies is identical to the previous region except for a reduction of rod internal pressure, the use of a reconstitutable bottom nozzle, and a modified corner grid strap design to prevent grid hangup during refueling. These changes are generic in nature to the 17X17 fuel assembly and are not reload deperident. The two Region 4A demonstration assemblies which were described in the July 1978 Westinghouse report " Optimized Fuel Assembly Demonstration Program" (WCAP-9286) princi-pally incorporate reduced fuel rod diameter and the use of Zircaloy 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 during transient conditions analyzed than for the standard fuel assemblies. These demonstration asssemblies were used previously in Cycles 2, 3 and 4. )()C)f 8303230227 830317 PDA ADOCK 05000348 P PDR

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Mr. S. A. Varga March 17,1983 U. S. Nuclear Regulatory Commission Page 2 4

Alabama Power Company has performed a detailed review of the Westinghouse Reload Safety Evalation Report (RSER) for Farley Unit 1 Cycle-5, including all postulated incidents considered in the FSAR and the Westinghouse fuel densification report, WCAP-8219, " Fuel Densification Experimental Results and Model for Reactor Operation." The RLER included a review of the core characteristics to determine those paramete s affecting the postulated accident analyses reported in the Farley analyses. Alabama Power Company concluded that Cycle-5 design parameters are conservative with respect to those assumed in the previous analysis; therefore, no accident was reanalyzed based on Cycle-5 parameters. This verification is consistent 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 reload safety evaluation demonstrated that Technical Specification changes are not required for operation of Farley Unit 1 during Cycle-5.

Alabama Power Company's Plant Operations Review Committee and Nuclear Operations Review Board have concluded that no unreviewed saf ety questions defined by 10CFR50.59 are involved with this reload. Therefore, based on this review, an 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. These tests will include, but not be limited to, measurements of:

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

Results of these tests and a core loading map will be submitted within ninety (90) days after startup of Cycle-5. .

Yours very truly,

. . layton J r.

FLCJr/MDR:mjh-D16 cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford

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