ML20155C744
| ML20155C744 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/30/1988 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-88-090, CON-NRC-88-90 VPNPD-88-489, NUDOCS 8810100207 | |
| Download: ML20155C744 (2) | |
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WISCONSIN Electnc we coune 231 W MJCHIGAN P O BOX 2046, MILWAUKEE.WI53201 (414)277-2345 VPNPD 489 NRC-88-090 September 30, 1988 U.S.
NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Station Pl-137 Washington, D.C.
20555 Gentlemen DOCKET 50-301 CYCLE 15 HELOAD POINT BEACll NUCLEAR PLANT, UNIT 2 A refueling shutdown is scheduled for the Point Beach Nuclear Plant, Unit 2, at the end of Unit 2 Cycle 14 operation on October 7, 1988.
Cycle 14 burnup will be approximately 10,900 MWD /MTU.
Point Beach Unit 2 startup for Cycle 15 is expected to occur in November 1987 following a six-week refueling and maintenance outage.
Reload Region 17 for Unit 2 Cycle 15 operation will contain 28 Westinghouse 14 x 14 Optimized Fuel Assemblics (OFA).
This will be the fifth reload region of OFA fuel inserted into the Unit 2 core.
The use of OFA fuel at Point Beach Nuclear Plant was reviewed and approved, as reported in the NRC Nuclear Safety Evaluation Report issued on October 5, 1984, in support of License Amendment 90 (Technical Specificatjo" Change Request 87) for Unit 2.
The mechanical and thermal-hydraulic designs for the Unit 2 Cycle 15 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 90 for Unit 2, so that the core characteristics will be less limiting than those previously reviewed and accepted.
For those postulated accidents presented in the PSAR 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 P xP limit of 2.21 and the current F-delta-H limit g
of 1.58, b
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Document Control Desk September 30, 1988 Page 2 In accordance with past practice, the Westinghouse reload safety evaluation report relics on previously reviewed and accepted analyses as reported in the FSAR, in the OPA transition safety reports, and in earlier reload cycle safety evaluation reports.
The reload safety evaluation report fo-Unit 2 Cycle 15 demonstrates that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the operation of Unit 2 during Cycle 15.
No application for license amendments beyond those already approved by the NRC in License Amendment 90 are, therefore, required for Cycle 15 operation.
A 10 CFR 50.59 safety evaluation will be confirmed by the Manager's Supervisory Staff prior to startup of Cycle 15.
Verification of the core design will be performed by means of the standard startup physics tests normally conducted at the beginning of each cycle.
Please contact us if you have any questions regarding the Cycle 15 reload design or operation.
Very tru.1
- yours, 5'
- f y _-
C.
W.
Fay Vice President Nuclear Power Copy to NRC Regional Administrator-Region III Resident Inspector t
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