ML20062F999
| ML20062F999 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/15/1990 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-90-118 VPNPD-90-471, NUDOCS 9011280318 | |
| Download: ML20062F999 (2) | |
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Electnc POWER COMPANY 231 W Mchwn Po Box 2046. Mdwodeo WI 53201 M14) 221234f VPNPD-90-471 NRC-90-11g November 15, 1990 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.C.
20555 Gentlement DOCKET 50-301 CYCLE 17 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 2 Point Beach Nuclear Plant, Unit 2, was shut'down for refueling at the end of Cycle 16 operation on October 6, 1990. 1 Cycle 16 burn-up was approximately 10,777 MWD /MTU.
Unit:2 is expected to begin operation for Cycle 17 on November 18, 1990 following a six-week refueling and maintenance outage.
Reload Region 19 for Unit 2 Cycle 17 operation contains 28 l
Westinghouse 14 x 14 upgraded Optimized Fuel Assemblies (OFA).
Upgraded OFAs include removable top nozzles, debris filter bcttom nozzles, and extended burnup geometry.
This will be the second 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 137) for Unit 2.
Additional changes / approved under LicenserAmendment No. 123 and implemented for Cycle 17 are_ increased allowable core power peaking factors, thimble _ plug removal, and the use of hafnium l
peripheral power suppression. assemblies.
License Amendmett No.
126, which approved the removal of the f(AI) function from the overpower delta-T cetpoint calculation, was also considered in the safety evaluations performed for. Cycle 17.
The mechanical and thermal-hydraulic designs for the Unit 2 Cycle 17 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 (Z)xP limit of 2.5 and the g
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e Document Control Desk November 15, 1990 Page 2 current FAH limit of 1.70.
Additionally, the reload core meets the more restrictive administrative limit on Fo(Z)xP of 2.43.
The administrative. limit on F (Z)xP has been tdaporarily g
established because of an error that was discovered in the decay heat model used for the Large Brt.ak LOCA analysis calculation performed by Westinghouse.
This error was previously reported in LER 90-007-00 for Point Beach Nuclear Plant, Units 1 and 2.
Information regarding a revised analysis which supports the temporary administrative limit on F (Z) of 2.43 was provided in a o
letter from C. W. Fay of Wisconsira Electric to R. B.
Samworth of the NRC, dated October 31, 1990.
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.
Not in accordance with past practice, the Westinghoune reload i
safety evaluation for Cycle 17 also relies on the revised Large Break LOCA analysis mentioned above.
The reload safety report for Unit 2 Cycle 17 concludes that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the operation of Unit 2 during cycle 17.
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 beginning of each cycle.
Please contact us if you have any. questions regarding the cycle 17 reload design or operation.
Very truly yours, L
C/
C. W. Fay Vice PMesident Nuclear Power Copies to NRC Resident Inspector NRC Regional Administrator, Region III F
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