ML20081H855
| ML20081H855 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/13/1991 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-58 VPNPD-91-188, NUDOCS 9106200077 | |
| Download: ML20081H855 (2) | |
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Wisconsin Electnc POWER COMPANY m w Menom no WN$ swme w wa wm a a.o VPNPD-91-188 NRC-91-58 June 13, 1991 U.S.
NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station P1-137 Washington, D.C.
20555 Gentlemen:
QQCEET 50-266 CYCLE 19 RELOAD POINT BEACH NUCLEAR _ PLANT. UNIT 1 Point Beach Nuclear Plant, Unit 1, was shut down for refueling at the end of Cycle 18 operation on April 6,
1991.
Cycle 18 burn-up was approximately 10,750 MWD /MTU.
Unit 1 began operation for Cycle 19 on May 17, 1991, following a six week refueling and maintenance outage.
Reload Region 21 for Unit 1, Cycle 19, operation contains 28 Westinghouse 14 x 14 upgraded Optimized Fuel Assemblies (OFA).
Upgraded OFAs include rcmovable top nozzles, debris filter bottom nozzles, and extended burn-up geometry.
This is the third reload region of upgraded OFA fuel inserted into the Unit 1 core.
The use of upgraded OFA fuel in both Point Beach Nuclear Plant units was reviewed and approved, as reported in the NRC Nuclear Safety Evaluation Report issued on May 8, 1989, in support of License Amendment No. 120 for Unit 1 (Technical Specification Change Request 127).
Additional changes approved under License Amendment No. 120 and implemented for Cycle 19 are increased allowable core power peaking factors, thimble plug removal, the use of hafnium peripheral power suppression assemblies, integral fuel burnable absorber assemblies, and axial blankets.
License Amendment No. 123, which approved the removal of the f(AI) function from the overpower delta-T setpoint calculation, was also considered in the safety evaluations performed for Cycle 19.
The mechanical and thermal-hydraulic designs for the Unit 1, Cycle 19, reload core are similar to those of previously reviewed and accepted reload designs containing OFA fuel.
This core is designed to operate under nominal design parameters and the approved Technical Specifications, including those provided with sde c &&
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Document Control Desk l
June 13, 1991 Page 2 License Amendment Nos. 120 and 123 for Unit 1.
For those postulated accidents presented in the FSAR which could be affected by the reload core, re-evaluation has demonstrated that the results of the postulated events are within allowable limits.
The reload core meets the current F xP limit of 2.5 and the o
current FAH limit of 1,70.
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In accordance with past practice, the Westinghouse reload safety evaluation report relies on previously reviewed and accepted analyses as reported in the FSAR, in the upgraded 0FA safety reports, and in earlier reload cycle safety evaluation reports.
The reload safety report for Unit 1, Cycle 19, concludes that no l
unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the operation of Unit i during cycle 19.
This 10 CFR 50.59 evaluation has been reviewed and approved by the Manager's Supervisory Staff.
Verification of the core design has been performed by means of the standard start-up physics tests normally conducted at the beginning of each cycle.
Please contact us if you have any questions regarding the Cycle 19 reload design or operation.
Very truly yours, c
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Fay V%ce-President Nuclear Power l
Copies to NRC Resident Inspector NRC Regional Administrator, Region III l
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