ML20151G895
| ML20151G895 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/11/1988 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-88-036, CON-NRC-88-36 VPNPD-88-202, NUDOCS 8804200176 | |
| Download: ML20151G895 (2) | |
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e WISCONSIN Electnc eona corepasr 231 W. MICHIG AN, P.O. BOX 2046. MILWAUKEE, W153201 (414)277 2345 VPNPD-88-202 NRC-88-036 April 11, 1988 U.
S.
NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.
C.
20555 Gentlemen:
DOCKET 50-266 CYCLE 16 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 1 A refueling outage for the Point Beach Nuclear Plant Unit 1 began on April 8, 1988.
This shutdown was at the end of Unit 1 Cycle 15 operation.
Cycle 15 burn-up was approximately 10,400 Megawatt-Days / Metric Tons Uranium (MWD /T).
Point Beach Unit 1 start-up for Cycle 16 is expected to occur in May 1988 following a six-week refueling and maintenance outage.
Reload Region 18 for Unit 1 Cycle 16 operation will contain 28 Westinghouse 14 x 14 Optimized Fuel Assemblies (OFA).
This will be the fourth reload region of OFA fuel inserted into the Unit 1 core.
The use of OFA fuel in both Point Beach Nuclear Plant units was reviewed and approved, as reported in the NRC Nuclear Safety Evaluation Report issued on October 5, 1984, in support of License Amendnent 86 for Unit 1.
The Cycle 16 core wil] contain eight 8-rodlet "water displacer" assemblies.
The "water displacer" rod assemblies are essentially the same as the burnable absorber rod assemblies (BPRAs), which contain borosilicate glass as a burnable absorber, except that the "water displacer" rods contain no absorber and are pressurized with helium.
Engineering review of the "water displacer" design has verified that, even if leakage occurs, no design or safety concerns are posed.
The mechanical and thermal-hydraulic design for the Unit 1 Cycle 16 reload core is similar to that of previously reviewed and ac-cepted reicad designs containing OFA fuel.
This core is designed to operate under nominal design parameters and within the approved Point Pseach Technical Specifications, including those provided 7h with License Amendment 86 for Unit 1, so that the core character-istics will be less limiting than those previously reviewed and 1 0 0804200176 800411 PDR ADOCK 05000266 a
p PDR
URC Document Control Desk April 11, 1988 P a ?'.
2 accepted. 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 postulateg events are within allowable limits.
TheregoadcoremeetstheFxPlimit of less g
than 2.21xK(z) and the F limit of less than 1.58.
3g 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 OFA transition safety reports, and in earlier reload cycle safety evaluation reports.
The reload safety evaluation report for Unit 1 Cycle 16 demon-strates that no unreviewed safety questions, as defined in 10 CFR 50.59, are involved in the operation of Unit 1 during Cycle 16.
No license amendments beyond those already approved by the NRC are required for Cycle 16 operation.
A 10 CFR 50.59 safety evaluation will be confirmed by the Point Beach Manager's Supervisory Staff prior to start-up of Cycle 16.
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 16 reload design or operation.
Ve:y truly yours, b
Uffif C. W.
Fay (
Vice President l
Nuclear Power Copies to NRC Resident Inspector NRC Regional Administrator-Region III