ML20128H897
| ML20128H897 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/10/1993 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-93-017, CON-NRC-93-17 VPNPD-93-033, VPNPD-93-33, NUDOCS 9302170217 | |
| Download: ML20128H897 (2) | |
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Qlj% 1 Becinc POWER COMPAM 2M w vomm to n 2No vram w mm Wamt2M5 VPNPD 033 NRC 017 February 10, 1993 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
DOCKET 50-301 CYCLE 19 B LQhQ POINT BEACH NUCLEAR PLANT. UNIT 2 Point Beach Nuclear Plant, Unit 2, was shut down for refueling at the end of Cycle 18 operation on September 26, 1992.
Cycle 18 burn-up was approximately 10,772 MWD /MTU.
Unit 2 began operation for Cycle 19 on November 18, 1991, following a 7-week refueling and maintenance outage.
Reload Region 21 for Unit 2 Cycle 19 operation contains 28 Westinghouse 14 x 14 upgraded Optimized Fuel Assemblies (OFA).
Upgraded OFAs include removable top nozzles, debris filter bottom nozzles, and extended burn-up geometry.
This is the fourth 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 8, 1989, in support of License Amendment No. 123 (Technical Change Request 127) for Unit 2.
Additional changes approved under License Amendment No. 123 and implemented for Cycle 19 are increased allowable core pewer peaking factors, thimble plug removal, the use of hafnium peripheral power suppression assemblies, integral fuel burnable absorber assemblies, and axial blankets.
License Amendment No. 326, 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 2 Cycle 19 reload core are similar to those of previously reviewed and accepted reload designs containing OFA fuel.
Two minor' mechanical changes to the new fuel are:
(1) top and bottom anti --
snag grids, and (2) a longer two-piece bottom grid insert.
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February 10,-1993 Page 2
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. changes have been evaluated by Westinghouse, and it-has been determined that these changes do not affect the previous wachanical and thermal-hydraulic. designs.
This core is designed to operate under nominal design parameters-and the approved Technical Specifications, including those provided-with License Amendment Nos. 123 and 126 for Unit 2.
For those postulated accidents presented in the FSAR which_could be affected by-the reload core, re-evaluationLhas demonstrated =that the results 1
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 q
of 1.70.
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 safety-reports, and in earlier reload cycle safety _ evaluation reports.
The reload safety report for Unit 2 Cycle 19 concludes that no-unreviewed safety questions, as defined in_10 CFR 50.59, are involved in the operation of Unit 2 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 conducted at the beginning of this. cycle.
Please contact us, if you have any questions regarding the Cycle 19 reload design or operation.
Sincer
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< &ely,J Bob Link Vice President Nuclear Power CAC/skf cc:
NRC Resident Inspector NRC Regional Administrator, Region III Subscribed and sworn to before me this_
104 day of G bm e,,
, 1993.
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.uu K6ta'ry fublic, State of Wisconsin
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