ML20028G489

Discusses Cycle 10 Reload.Refueling Shutdown for End of Cycle 9 Planned to Begin Late Mar 1983 at Burnup of Approx 9,150 Mwd/T Plus/Minus 500 Mwd/T.Core Will Consist of Westinghouse 14x14 Optimized Design & 14x14 Std Design Fuel

ML20028G489
Person / Time
Site:	Point Beach
Issue date:	02/03/1983
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8302090408
Download: ML20028G489 (2)

Text

fl POWER COMPANY 231 W. MICHIGAN, P.O. BOX 2046, MILWAUMEE, WI 53201 February 3, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION.

Washington, D. C. 20355 Attention: Mr. R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen:

I DOCKET NO. 50-301 CYCLE 10 RELOAD POINT EEACHiNUCLEAR PLANT, UNIT 2 As you are aware, Point Beach Unit 2 is currently in its ninth cycle of operation 4 The refueling shutdown at the end of Cycle 9 is planned to begin in late March 1983 at a barnup of approximately 9150 MWD /T within a range of +500 MWD /T. During the refueling, the four demonstration assemblies of Westinghouse 14x14 optimized design will be loaded into the core for their third cycle of irradiation along with 48 fresh standard design 14x14 reload assemblies. The remainder of the core will be of standard 14x14 design Westinghouse fuel. Our letter of July 1, 1980 advised you of our plans in respect to the demonstration program and utilization of the four 14x14 Optimized Fuel Assemblies (OFA's).

The performance of Westinghouse OFA fuel, as demonstrated by recent experience at Point Beach Unit 2, Farley Unit 1, and Salem Unit 1, has been favorable and no indication of behavior different from that anticipated has been observed. During the next Unit 2 refueling, the-demonstration assemblies will be visually examined to verify that their condition is as expected. This letter is to advise you of our plans for the further utilization of the four demonstration assemblies in Unit 2 Cycle 10.

For thei Cycle 10 irradiation, the demonstration assemblies wi' _a be placed in core locations that prevent them from becomit.g '.aad assemblies during normal operation or from leading to r. ore limiting conditions during transient conditions

-than analyzed for the standard design fuel assemblies.

8302090408 820203 E PDR ADOCK 05000301 L P PDR

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i Mr. H. R. Denton February 3, 1983 The Unit 2 Cycle 10 core design was completed as for previous cycles except that the criteria mentioned above governed as to location of the demonstration assemblies in the Cycle 10 reload core. As with previous cycle denigns, core characteristics were found to be less limiting than previously reviewed and accepted or, for those postulated accidents presented in the Final Safety Analysis Report (FSAR) which could be adversely affected by the reload core, re-evaluation has demonstrated that the results of postulated events are within allowable limits.

The Reload Safety Evaluation was performed in accordance with WCAP-9272, " Westinghouse Reload Safety Evaluation Methodology".

A technical review of the Westinghouse Keload Safety Evaluation for Point Beach Unit 2 Cycle 10 was performed by cur Nuclear Engineering Section and Point Beach Nuclear Plant staffs and included an assessment of the impact of the demonstratica aasemblies on the Cycle 10 core design and safety analyses.

There were no unreviewed safety questions as defined by 10 CFR 50.59; therefore, applications for amendment to the Unit 2 Operating License or for a Technical Specification changs are not necessary.

Verification of the core design will, of course, be performed by means of the standard start-up physics tests normally performed at the start of each cycle. The rod exchange method of performing worth measurements, which has been employed in previous cycles, will be employed in the Unit 2 Cycle 10 start-up physics test program.

Very truly yours, e

6v Vice Presi ent - Nuclea*. Power C. W. Fay Copy to NRC Resident Inspector t

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