ML20235H480
| ML20235H480 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/21/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CON-NRC-87-96 VPNPD-87-397, NUDOCS 8710010067 | |
| Download: ML20235H480 (2) | |
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WISCONSIN Electnc eom coww 1
231 W. MICHIG AN. P.O. BOX 2046, MILWAUKEE, Wl 53201
'(414)277 2345
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VPNPD 397 NRC-87 ;
1 September 21,.-1987 1
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NUCLEAR REGULATORY COMMISSION Document Control Desk l
Washington, D.C.
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J Gentls 'en:
3 DOCKET 50-301 CYCLE 14 RELOAD POINT BEACH NUCLEAR PLANT, UNIT 2 l
A refueling shutdown.is scheduled at Point Beach Nuclear Plant,:
d Unit 2.
on Oct,ber 2, 1987.
This shutdown is at the end of Unit.
j 2,
Cycle 13 operation.
Cycle 13 burn-up will be approximately 10,000 MWD /MTU.
Point Beach Unit 2 start-up for Cycle 14 is-expected to occur.in November 1987 following a six-week refueling and maintenance' outage.
t Reload Region 16 for Unit 2,. Cycle 141 operation will~contain'32 Westinghouse 14 x 14 Optimized Fuel Assemblies (OFA).
This will be the fourth reload region of OFA fuel inserted'into the. Unit 2-l core.
The use of OFA fuel in both/ Point Beach Nuclear' Plant l
units was reviewed and approved,.'as reported in theNRC Nuclear j
Safety Evaluation. Report issued on October: 5, 1984,.in-support of License Amendment 90 (Technical Specification' Change Request i
- 87) for Unit'2.
The Cycle 14 core will also contain fourL4-rodlet'" water I
l displacer"' assemblies.
The " water displacer" assemblies are Li essentially the same as'the burnable: poison assembly.(BPA) l_
tubes, which~contain borosilicate glass as a burnable absorber,-
i except that the " water dispiacer" tubes contain no. absorber'and are pressurized with helium.. Engineering review of.the " water displacer" design has verified.that, even if leakage' occurs,'no
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design.or. safety concerns are posed.
The-mechanical and therma 2-hydraulic' designs'for?the Unit 2 j
Cycle:14 reload core are similar to'those.of previously reviewed j
and accepted. reload designs;containing OFA fuel.
This., core is' l
designed to. operate under nominal design parameters'and the.
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approved. Technical Specifications,: including those ' provided with
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NRC Document Control Desk j
September 21, 1987 Page.2 License Amendment 90 for Unit 2, so that the core i
characteristics will be less limiting than'those previously I
reviewed and accepted.
For those postulated accidents. presented-in the PSAR which could be affected by the reload core, l
re-evaluation has demonstrated that the results of the postul-'
. ated events are within allowable limits.- The reload core design I
meets the fugl power Fg(z) limit of 2.21xK(z) and the current
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full power F limit of less than 1.58.
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In accordance with past practice, the Westinghouse reload cafety j
evaluation report relies on previously reviewed and accepted i
analyses as reported in'the PSAR, in the 0FA reload transition j
safety report, and in ear'.ier reload cycle safety evaluation j
reports.
The reload safety evaluation report for Unit 2 Cycle l
14 demonstrates that no unreviewed safety questions, as~ defined in 10 CFR 50.59, are involved in the operation of Unit 2 during Cycle 14.
No application for license amendments beyond those
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already approved by the NRC in License Amendment 90 are, l
therefore, required for Cycle 14 operation.
A 10 CFR 50.59 l
l evaluation will be confirmed by the Manager's Supervisory Staff prior to start-up of Cycle 14.
Verification of the core design l
will be performed by means of the standard start-up physics l
tests normally conducted at the beginning of each cycle.
Please contact us if you have any questions regarding che Cycle 14 reload design or operation.
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Very truly yours, J
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W.
a Vice President Nuclear Power Copy to NRC Resident Inspector NRC Regional Administrator - Region 111
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