ML19332C633
| ML19332C633 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/17/1989 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-89-144 VPNPD-89-605, NUDOCS 8911280367 | |
| Download: ML19332C633 (2) | |
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Wisconsin 1 Eihnctnc POWER COMPANY 231 W Michon Po Box 2046. MAMee. Wi 53201 (414)22i 2345 VPNPD-89-605 NRC-89-144-November 17, 1989.
U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station Pl-137 Washington, D.C.
20555 Gentlemen:
DOCKET 50-301 CYCLE 16 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 2 Point Beach Nuclear Plant, Unit 2, was shut down for refueling at the end of Cycle 15 operation on September 23, 1989.
Cycle 15 burn-up was 10,204 MWD /MTU.
Unit 2 will begin operation for Cycle 16 on about November 24, 1989 following a nine-week refueling and maintenance outage..
' Reload Region 18 for Unit 2 Cycle 16 operation contains 28 Westinghouse 14 x 14 upgraded Optimized Fuel Assemblics (OFA).
Upgraded OFAs include removable top nozzles, debris filter bottom nozzles, and extended burnup geometry.
This will be the first reload region of upgraded OFA fuel incerted into the Unit 2 core.
The use of a
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 Specification Change Request 127) for Unit 2.
Additional changes approved under License' Amendment No. 123 and implemented for Cycle 16-are increased allowable core power peaking factors,_ thimble plug removal, and the use of hafnium peripheral power suppression assemblies.
License Amendment No. 126, 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 16.
The mechanical and thermal-hydraulic designs for the Unit 2 Cycle 16 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 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-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 0
and the current F-delta-H limit of 1.70.
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7 USNRC Document Control Desk November 17, 1989-g Page 2 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 safety reports, and:in-i
. earlier reload cycle safety evaluation reports.. The reload safety evaluation report for. Unit 2-Cycle 16 demonstrates that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the J
operation'of. Unit.2 during Cycle 16.
This 10 CFR 50.59 evaluation has been reviewed and approved by the Manager's Supervisory Staff.
Verification of the core design will be performed by means of.the.
standard' start-up physics' tests normally conducted at the begi'nning of each cycle.
Please contact us if you have any questions regarding the Cycle-16 reload design or operation.
Very truly.yours,
[d {
C. ; W Fay Vice-President-Nuclear-Power Copies =to_NRC-Resident Inspector NRC Regional Administrator,' Region III k
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