ML20091N098
| ML20091N098 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/20/1992 |
| From: | Zach J WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-006, CON-NRC-92-6 VPNPD-92-037, VPNPD-92-37, NUDOCS 9201300052 | |
| Download: ML20091N098 (2) | |
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.x a,y Wisconsin Electnc POWER COMPANY 231 w Meen, no iku 204s weam wi 53201 14sa) 22o234s VPNPD 0 37 NRC-92 006 January 20, 1992 Document-Control Desk U.
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NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
DOCKET 50-331 CYCLE 18 RELOAD POINT BEACH NUCI EAR PLANT. UNIT 2
' Point Beach Nuclear Plant, Unit 2, was shut down for refueliny at i
the end of Cycle 17 operation on September 27, 1991.
Cy_cle 17
' burn-up was approximately 10,778 MWD /MTU.
Unit 2 began operation for Cycle ~18 on November 14, 1991 fo? lowing a seven-week refueling and maintenance outage.
-Reload Region 20 for Unit 2. Cycle 18 operation contains 28 Westinghouse 14.x 14' upgraded Optimized Fuel-Assemblies (OFA).
i
- Upgraded OFAs include removable top nozzles, debris filter bottom
-nozzles, and extended burnup geometry.
This is the third reload region of upgraded OFA. fuel inserted into-the Unit 2 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 S, 1989, in cupport of Licence Amendment No. 123 (Technical Specification Change Request 127)-for-Unit 2.-
. Additional changes approved under License' Amendment No. 123 and l.
- -implemented-for Cycle 18 are increased allowable core power peaking.
L factors,. thimble plug removal, the'use of' hafnium peripheral power suppression assemblies, integral fuel burnable absorber assemblies, and--axial blankets.
License Amendment No. 126, which approved the removal ~ of; the f( AI)- function from the overpower delta-T setpoint<
L
. calculation, was also considered in the safety evaluations performed for-. cycle 18.
The mechanical-and-thermal-hydraulic designs-for the Unit 2 Cycle
'18 reload core arc similar to those of previously reviewed and l
accepted-reload designs ~containing OFA fuel.
This core is designed
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January 20, 1992 Page 2 to operate under nominal design parameters and the approved Technical Apecifications, including these provided with License Amendment Nos. 123 and 126 for Unit 2.
For those accident sequences presented in the PSAR 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 current FAH limit of q
1.70.
In accordance with par
- practice, the Westinghouse reload safety evaluation report relles on previously reviewed and accepted analyses as reported in the FSAR, in the upgraded OFA safety reports, and in earlier reload cycle safety evaluation reports.
The reload safety report for Unit : Cycle 18 concludes that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the operation of Unit 2 during Cycle 18.
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 conducted at the beginning of this cycle.
Please contact us if you-have ani questions regarding the Cycle 18 reload design or operation.
Sincerely, wu James J.
Zac:
Vice President Nuclear Power Copy to:
NRC Resident Inspector NRC Regional Administrator, Region III Subscribed and swo{n to before me this.2! ? day of 1992.
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Notary Public, State of Wisconsin My Commission expires E 2 ? ' 'H/.
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