ML20134P907
| ML20134P907 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/03/1985 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Butcher E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-85-95 VPNPD-85-284, NUDOCS 8509090093 | |
| Download: ML20134P907 (2) | |
Text
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l Wisconsin Electnc roara couessv 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE. WI 53201 September 3, 1985 VPNPD-85-284 NRC-85-95 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. E. J. Butcher, Acting Chief Operating Reactors, Branch 3
[
Gentlemen:
1 DOCKET NO. 50-301 CYCLE 12 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 2 A refueling shutdown for the Point Beach Nuclear Plant Unit 2 is presently planned to begin in early October 1985.
This shutdown will be at the end of Unit 2 Cycle 11 operation..
Cycle 11 burnup will be approximately 9,900 mwd /T.
Point Beach Unit 2 startup for Cycle 12 is expected to occur in November 1985 following a seven-week refueling and maintenance outage.
The reload region for Unit 2 Cycle 12 operation will 4
l contain 28 Westinghouse 14x14 Optimized Fuel Assemblics (OFA).
This will be the second reload region of OFA fuel' inserted into the Unit 2 core.
The use of OFA fuel in both Point Beach Nuclear Plant units was reviewed and approved as reported in the NRC l
Safety Evaluation Report issued on October 5, 1984 in support of License Amendments 86 and 90 for Units.1 and 2, respectively.
) i The mechanical and thermal-hydraulic design for the Unit 2 Cycle 12 reload core is similar to'that of previously re-viewed 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 90 for Unit 2, so that the core charac-3; teristics will be less limiting than previously reviewed and accepted.
For those postulated accidents presented in the FSAR l
which could be affected by the reload core,/ reevaluation has
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demonstrated that the results of the postulatgd events are with-3 3 in allowable limits.
The regoad core meets F xP limit of less than 2.21 and the current FA limits-of less khan 1.58.
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8509090093 850903 DR ADOCK 05000301
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o Mr. H. R. Denton September 3, 1985 In accordance with past practice, the Westinghouse reload safety evaluation report relies on previously reviewed and accepted analyses as reported in the FSAR, the OFA transi-tion safety reports, and in earlier reload cycle safety eval-4 uation reports.
The reload safety evaluation report demon-strates that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in operation of the fuel during Cycle 12 and, therefore, no application for license amend-ments, beyond those already approved by the NRC in License Amendment No. 90, are required for Cycle 12 operation.
This 10 CFR 50.59 evaluation will be confirmed by the Manager's sSupervisory Staff prior to startup of Cycle 12.
Verifica-
' tion of the core design will be performed by means of the standard startup physics tests normally performed at the beginning of each cycle.
Please note that on April 10, 1985 Wisconsin Elec-tric applied for a license amendment for Point Beach Nuclear Plant, Units 1 and 2, to incorporate additional requirements for reactor coolant pump operation.
We anticipate implementing these proposed Technical specifications'on or before the start-up of Unit 2 Cycle 12.
Very truly yours, f'
(/b Vice President-uclear Power C. W. Fay LNW/smw
! Copy to NRC Resident Inspector I
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