ML20099D399
| ML20099D399 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/25/1985 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8503110582 | |
| Download: ML20099D399 (2) | |
Text
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9 MSC00 Sin Electnc em cwnw 231 W. MICHIGAN, P.O. B0X 2046. MILWAUKEE, WI 53201 February 25, 1985 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. J.
R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NO. 50-266 CYCLE 13 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 1 A refueling shutdown for the Point Beach Nuclear Plant Unit 1 is presently being planned to commence in early April 1985.
This shutdown will be at the end of Unit 1 Cycle 12 operation.
Cycle burnup will be approximately 11,000 mwd /T.
Point Beach Unit 1 startup for Cycle 13 is expected to occur in early June 1985 following this eight-week refueling and maintenance outage.
The reload core for Unit 1 Cycle 13 operation will contain 28 Westinghouse 14x14 Optimized Fuel Assemblies (OFA).
The use of OFA fuel in both Point Beach Nuclear Plant units was reviewed and approved as reported in the NRC Safety Evaluation Report issued on October 5, 1984 in support of License Amendments 86 and 90 for Units 1 and 2, respectively.
The mechanical and thermal-hydraulic design for this Unit 1 Cycle 13 reload core is similar to that 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 86 for Unit 1, so that the core characteristics will be less limiting than previously reviewed and accepted.
For those postulated accidents presented in the FSAR which could be affected by the reload core, reevaluation has demonstrated that the results of the postulat d events are within allowable limits.
The reload core meets F xP limit of lessthan2.21andthecurrentFAylimitsoflessthan1.58.
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, 9 Mr. H.
R. Denton February 25, 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 transition safety reports, and in earlier reload cycle safety evaluation reports.
The reload safety evaluation report demonstrates that no unreviewed safety questions, as defined in 10 CFR 50.'59, are involved in operation of the fuel during Cycle 13 and, therefore, no application for license amendments, beyond those already approved by the NRC'in License Amendment No. 86, are required for Cycle 13 operation.
This 10 CFR -50.59 evaluation will be confirmed by the Manager's Supervisory Staff prior to startup of Cycle 13.
Verification 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 November 9, 1984 Wisconsin Electric applied for a license amendment for Point Beach Nuclear Plant, Units 1 and 2, to incorporate additions to the overtemperature AT and overpower AT equations in Specifications 15.2.3.1.B(4) and (5),
respectively.
This application was modified by letter dated November 13, 1984.
These changes were approved for Unit 2 on November 16, 1984.
Approval of these changes for Unit 1 operation will be necessary prior to startup of Cycle 13.
Very truly yours,
&y[
Vice Presid nt-Nuclear Power C. W. Fay Copy to NRC Resident Inspector 4
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