ML19242D206

Discusses Procedures & Plans Re Cycle 8 Startup Expected to Commence 791102.Results of Startup Physics Rod Worth Measurements Will Be Submitted within 45 Days Following Verification of Shutdown Margin

ML19242D206
Person / Time
Site:	Point Beach
Issue date:	08/03/1979
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 7908140687
Download: ML19242D206 (2)

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O wisconsin Elecinc powca couesur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUFEE WI 53201 August 3, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. Albert Schwencer, Chief Operating Reactors Branch #1 Gentlemen:

DOCKET 50-266 POINT BEACH NUCLEAR PLANT UNIT 1 CYCLE 8 RELOAD The refueling shutdown at the end of Unit 1, Cycle 7 is planced to commence on September 28, 1979, at a cycle burnup of about 10,000 MWD /T; within a range of -750 MWD /T to +250 MWD /T. Startup of Cycle 8 is expected to occur on November 2, 1979. This letter is to advise you of our plans regardi,19 the Unit 1, Cycle 8 reload core.

The Unit 1, Cycle 8 reload core is designed to operate under current nominal design parameters, Technical Specifications and related bascs, and current setpoints such that:

1. Core characteristics will be less limiting than previously reviewed and accepted; or

2. For those postulated accidents presented in the Final Facility Description and Safety Analysis Report (FFDSAR) which could be affected by the reload core, re-evaluation has demonstrated that the results of the postulated events are within allowable limits. Based on the Westinghouse Reload Safety Evaluation Report (RSER) for Unit 1, Cycle 8 and discussions with Westinghouse, safety evaluations were performed by our Nuclear Projects Office and our Point Beach Plant Supervisory Staff pursuant to the requirements of 10 CFR 50.59(a) and 10 CFR 50.59(b).

The reload fuel mechanical and thermal-hydraulic design for the Cycle 3 reloadcoreisunchangedfromthatofpreviouslyreviewedandacceptedreload designs. The reload core meets the Fg xP limit of less than 2.q2 which is consistent with previous reload nuclear designs. The current Fh limit of less than 1.58, and penalties for rod bow, insure that the DNB ratio .Hwill not be less than 1.30.

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Mr. Harold R. Denton - Page Two August 3, 1979 In accordance with past practice, the reload safety evaluation relied on previously reviewed and accepted analyses reported in the FFDSAR and in earlier reload cycle RSER's. A review was made of the core charac-teristics to detemine those parameters affecting the postulated accident analyses reported in the FFDSAR. In all cases it was found that the effects can be accommodated within the conservatism of the initial assumptions used in the previous applicable safety analyses and thus the conclusions presented in,the FFDSAR remain valid.

The reload safety evaluation demonstrated that Technical Specification changes are not required for operation of Unit 1 at full rated power during Cycle 8 It was also demonstrated that unreviewed safety questions as defined by 10 CFR 50.59 are not involved and therefore application for an amendment to the Unit 1 operating license is not required.

Verification of the core design will of course ce perfomed by means of the standard startup physics tests normally perfomed at the start of each cycle. The rod bank exchange method of perform.'ng rod worth measurements will be used for the Unit 1 Cycle 8 startup physics tests. In accordance with Item 5 of Mr. A. Schwencer's letter of April 10, 1979, the results of the startup physics rod worth measurements will be fomally submitted to the NRC within 45 days following verification of shutdown margin.

Very truly yours, y/

,is 7-C. W. Fay, Director Nuclear Power Department l . l

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