ML20043D651

Discusses Cycle 18 Reload on 900519,following 7-wk Refueling & Maint Outage.Reload SER for Cycle 18 Demonstrates That No Unreviewed Safety Questions,As Defined in 10CFR50.59, Involved in Operation of Unit During Cycle

ML20043D651
Person / Time
Site:	Point Beach
Issue date:	05/25/1990
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-90-052, CON-NRC-90-52 VPNPD-90-258, NUDOCS 9006110029
Download: ML20043D651 (2)

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o Wisconsin 1 Electnc PONER COMPAM m w tuyn o n to 2on w.aae+ # L3m M 72W5 VPNPD-90-258 NRC-90-052 i

May 25, 14i0 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.C. 20555 Gentlemen:

DOCKET 50-266 CYCLE 18 ItELOAD POINT BEACH NUCLEAR PLANT, UNIT 1 Point Beach Nuclar Plant Unit I was shut down for refueling at'the end of Cycle 17 operation on March 31, 1990. Cycle 17 burn-up was 10,514 MWD /MTU. Unit 1 began power operation for Cycle.18 on May 19, 1990, following a seven-week refueling and snaintenance outage.

Reload Region 20 for Unit 1 Cycle 18 operation contains 29-Westinghouse 14 x 14 upgraded Optimized Fuel Assemblics (OFA). 1 Upgraded OPAs include removable top nozzles, debris filter bottom I nozzles, and extended burnup geometry. This is the.second reload j region of upgraded OPA fuel inserted into the'. Unit 1 core. The use of upgraded OPA fuel:in both Point Beach Nuclear Plant units was reviewed and approved, as reported in the NRC Safety Evalu-ation issued on May 8, 1989, in support of License Amendment No. 120 (Technical Specification Change Request 127) for Unit 1.

Additional changes approved under License Amendment No. 120 and implemented for Cycle 18 are increased allowable core power peaking f actors, thimble plug removal, and the use of flafnium peripheral power suppression assemblies.

The 29 new fuel assemblies include 16' assemblies with 4.0 w/o U-235, 12 assemblies with 4.2 w/o U-235, and I assembly with 2.6 w/o U-235. The 2.6 w/o assembly was manufactured during the 1 refueling outage to replace a once-burned fuel assembly that was -

damaged during fuel motion. This change in the loading pattern was included in-the Cycle 18 reload safety evaluations, j The mechanical and thermal-hydraulic designs for the Unit-1 i Cycle 18 reload core are similar to those of previously reviewed j

-and accepted reload designs containing 0FA fuel. This core is '

designed to. operate under nominal design parameters and the pm n=Cx e g 9006110029900m.ge m,-,,,,,,,, c ,'

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Document Control Desk i May 25, 1990 Page 2-f approved Technical Specifications, including those provided with  :

License Amendment No. 120 for Unit 1. For those postulated acci- '

dents presented in the FSAR which could be affected by the reload >

core, re-evaluation has demonstrated that the.results of the pos-tulated events are within allowable limits. The reload core meets the current FO xP limit of 2.5 and the current F-delta-H limit of 1.70. r In accordance with past practices, the Westinghouse reload safety evaluation report relies on previously reviewed and accepted. s analyses as reported in the PSAR, in the upgraded 0FA safety reports, and in earlier reload cycle safety evaluation reports, t The reload safety evaluation report for Unit 1 Cycle 18  ;

demonstrates that no unreviewed safety questions, as defined i

-in 10 CPR 50.59, are involved in the operation of Unit 1 during Cycle 18. No application for Ideense amendments are required for Cycle 18 operation. This 10 CFR 50.59 ovaluation was confirmed by '

the Manager's Supervisory Staff prior to. start-up of Cycle 18.  ;

Verification of the core design was performed by means of the standard start-up physics-tests normally conducted at the beginning of each cycle, f, Please contact us if you have any questions regarding-the Cycle 18 reload design or operation.

Very truly yours, i

? h';

((Oli C. W. Fay -

Vice PYesident Nuclear Power t Copies to NRC Resident Inspector NRC Region III Administrator 4

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