ML20099E425
| ML20099E425 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/31/1992 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-091, CON-NRC-92-91 VPNPD-92-278, NUDOCS 9208100175 | |
| Download: ML20099E425 (2) | |
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Elecinc POWER COMPANY 2M w uchoanao b 2046 MNome w 5320b2046 M M)2242 2 VPNPD 278
' NRC-9 2- 091 July 31, 1992 Document Control Desk U.
S. NUCLEAR REGULATORY COMMISSION
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Mall Station P1-137 Washington, DC 20555 Gentlemen:
D9CKET 50-266 CYCLE 20 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 1 Point Beach Nuclear Plant, Unit 1, was shut down for refueling at the end of Cycle 19 operation on April 10, 1991.
Cycle 15 burn-up was approximately 10,962 MWD /MTU.
Unit 1 began operation for Cycle 20 on June 5, 1992 following an eight-week refueling and maintenance outage.
Reload-Region 22 for Unit 1 Cycle 20 operation contains 28 Westinghouse 14 x 14 upgraded Optimized Fuel Assemblie.: (OFA).
Upgraded OFAs include removable top nozzles, debris fiTrer bottom nozzles, and extended burnup geometry.
This is the third reload region of upgraded CFA fuel inserted into the Unit 1 core.
The use of upgraded OFA fuel in both Point Beach Nuclear Plant units was
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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 cpproved under License Amoniment No. 120 and implemented for' Cycle 20 are increased allow'c'e core power peaking factors, thimble plug removal, the use of hafnium peripharal 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 20.
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'The mechanical and thermal-hydraulic designs for the Unit 1 Cycle 20. reload core are similar tc those of previously ieviewed 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 License' Amendment Nos.-120 and 123'for Unit 1.
For those
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' 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 raload core meets the current F xP limit of 2.5 and the current FAH-limit q
'g of 1.70.
l 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 OFA cafety reports, and in earlier-reload cycle safety evetuation reports.
The reload-safety' report for Unit 1 Cycle 20 concludes that no unrevicwed-safety questions,.as defined in 10 CFR 50.59, are involved in the operation of Unit 1 during Cycle 20.
This-10 CFR 50.59 ovaluation 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 ist the bSginning of each cycle.
Please contact us if you'have'any questions regard.i..g the Cycle 20 reload design or operation.
r very truly yo rs,
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Bob Link lice Prealdent
' Nuclear Power Copies to NRC-Resident Inspector NRC Regional Administrator, Region III
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