ML20080F788
| ML20080F788 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/18/1995 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-95-006, CON-NRC-95-6 VPNPD-95-011, VPNPD-95-11, NUDOCS 9501310105 | |
| Download: ML20080F788 (2) | |
Text
V.,
Wisconsin Electnc POWER COMPANY 231 W McNgan, Po Bon 2046. Mawoukee. WI 53201 2046 (414)221 2345 VPNPD-95-011 NRC-95-006 January 18, 1995 Document Control Desk U.S.
NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
DOCKET 50-301 CYCLE 21 RELOAD POINT BEACH NUCLEAR PLANT UNIT 2 Point Beach Nuclear Plant Unit 2 was shut down for refueling at the end of Cycle 20 operation on September 24, 1994.
Cycle 20 burn-up was approximately 11,307 MWD /MTU.
Unit 2 began operation for Cycle 21 on November 1, 1994, following a 38-day refueling and maintenance outage.
Reload Region 23 for Unit 2, Cycle 21 operation contains 29 Westinghouse 14 x 14 upgraded Optimized Fuel Assemblies (OFA).
Four water displacer assemblies, nine assemblies with Integral Fuel Burnable Absorber and twelve Peripheral Power Suppression Assemblies, are also included in the core.
The mechanical and thermal-hydraulic designs for the reload core are similar to those of previously reviewed and accepted reloac designs containing OFA fuel.
Changes include a reduction in the Minimum Measured Flow Rate, new core thermal limits and a change to the OPAT setpoint function.
The changes are the subject of Technical Specifications Change Request 177.
Safety analyses show that all safety criteria are met and the conclusions presented in the Final Safety Analysis Report remain valid.
The reload safety evaluation report concludes that no unreviewed safety qu(1tions, as defined in 10 CFR 50.59, are involved in the operation of Unit 2 during Cycle 21.
The 10 CFR 50.59 evaluation i
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.
The return to full power was limited by hot channel
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U.S. Nuclear Regulatory Commission Janudry 18, 1995 Page 2 factors and an unexpected quadrant tilt in the core.
Admini-strative limits were maintained to ensure no hot channel factors were exceeded.and the unit achieved full power on December 1, 1994.
Please contact us if you have any questions regarding the Cycle 21
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reload design or operation.
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Sincerely, i
I Bob Link Vice President Nuclear Power RJK/jg cc:
NRC Resident Inspector NRC Regional Administrator, Region III l
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