NPL-97-0025, Submits Supplemental Info Re TS Change Request 194 Re Low Temp Overpressure Protection Sys.Calculation,Encl

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Submits Supplemental Info Re TS Change Request 194 Re Low Temp Overpressure Protection Sys.Calculation,Encl
ML20134C242
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/27/1997
From: Dante Johnson
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134C245 List:
References
NPL-97-0025, NPL-97-25, NUDOCS 9701310298
Download: ML20134C242 (2)


Text

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Wisconsin l Electnc  :

POWER COMPANY 231 W Michigan, PO Box 2046. Mdwoukee. W153201-2046 (414)221 2345 NPL 97-0025 January 27,1997 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

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Dear Sir / Madame:

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DOCKETS 50-266 AND 50-301 SUPPLEMENT TO TECHNICAL SPECIFICATION CIIANGE REOUEST 194 j LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM l POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 In a letter dated September 19,1996 and supplemented in a January 13,1997 letter, Wisconsin Electric submitted Technical Specifications Change Request (TSCR) 194, which proposed changes to the Point Beach Nuclear Plant Units 1 and 2 Technical Specifications Section 15.3.15,

" Overpressure Mitigating System" and Section 15.3.1, " Reactor Coolant System.

During NRC staff review of our Calculation No. 96-0273, which was included in the January 13 submittal, it was determined that a plant specific neutron fluence attenuation evaluation was used in lieu of the generic guidance for fluence attenuation contained in Regulatory Guide 1.99, Revision 2 (RG 1.99, Rev. 2). Wisconsin Electric had previously committed in a response to Generic Letter 88-11 dated November 29,1988, to use the fluence attenuation function contained in RG 1.99, Rev. 2 in the determination of pressure-temperature limits.

Please find attached our Calculation 96-0273, Revision 1, which determines neutron fluence attenuation in accordance with RG 1.99, Rev. 2. Use of this neutron attenuation methodology does not alter any of the conclusions of the previous revision to our calculation. Furthermore, no additional changes are required to the supplement to TSCR 194 that was submitted on January 13, i 1997.  !

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Document Control Desk NFL 97-0025

. Page 2 TSCR 194 to implement these revised Technical Specifications is required prior to the start of Point Beach Unit 2 reactor vessel head tensioning which is currently scheduled to begin on February 10, 1997. Failure to receive approval of this TSCR by that date will delay the scheduled February 25, 1997, start-up of Point Beach Unit 2 from its current maintenance and refueling outage. We believe that this submittal is timely and could not have been avoided and thus meets the criteria of 10 CFR 50.91 for processing as an exigent change. As such, we request that this change be processed as an exigent Technical Specification Change Request and be issued before February 9,1997. Please contact us if you have any questions regarding this submittal.

Sincerely, D. - ohnson Manager Regulatory Services & Licensing JRP/kmc Attachment cc: NRC Regional Administrator I NRC Resident Inspector i Public Service Commission of Wisconsin bec: Adams, Anthony, Cayia, Gorecki, licefert, Krieser, Patuiski, Pfefferle, Reimer, Ulmer, Walther, (OSRC), File

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