ML063040261

Kewaunee, Correction of Amendment, Rod Position Indication

ML063040261
Person / Time
Site:	Kewaunee
Issue date:	11/03/2006
From:	Jaffe D H NRC/NRR/ADRO/DORL/LPLIII-1
To:	Christian D A Dominion, Dominion Energy Kewaunee
D. Jaffe
References
TAC MC3278
Download: ML063040261 (4)

Text

November 3, 2006Mr. David A. ChristianSenior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION - CORRECTION OF AMENDMENT RE: ROD POSITION INDICATION (TAC NO. MC3278)

Dear Mr. Christian:

On March 24, 2005, the Nuclear Regulatory Commission (NRC) issued Amendment No. 181 toFacility Operating License No. DPR-43 for Kewaunee Power Station, to revise the technical specifications (TSs) by adding the demand step counters to the TSs and adding a note to allow for a soak time subsequent to substantial rod motion for the rods that exceed their position limits before invoking the TS requirements. Due to an administrative error, TS page 3.10-7 had a missing word in paragraph i. A new TSpage 3.10-7 is enclosed with a marginal line indicating the change.The NRC staff regrets any inconvenience this error may have caused. Please feel free tocontact me at 301-415-1439 if you have any further questions.Sincerely,/RA/David H. Jaffe, Senior Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-305

Enclosure:

As statedcc w/encl: See next page Mr. David A. ChristianNovember 3, 2006Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION - CORRECTION OF AMENDMENT RE: ROD POSITION INDICATION (TAC NO. MC3278)

Dear Mr. Christian:

On March 24, 2005, the Nuclear Regulatory Commission (NRC) issued Amendment No. 181 toFacility Operating License No. DPR-43 for Kewaunee Power Station, to revise the technical specifications (TSs) by adding the demand step counters to the TSs and adding a note to allow for a soak time subsequent to substantial rod motion for the rods that exceed their position limits before invoking the TS requirements. Due to an administrative error, TS page 3.10-7 had a missing word in paragraph i. A new TSpage 3.10-7 is enclosed with a marginal line indicating the change.The NRC staff regrets any inconvenience this error may have caused. Please feel free tocontact me at 301-415-1439 if you have any further questions.Sincerely,/RA/David H. Jaffe, Senior Project ManagerPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-305

Enclosure:

As stated cc w/encl: See next pageDISTRIBUTION:PUBLICLPL3-1 r/fRidsNrrDorlLpleRidsNrrPMDJaffeRidsNrrLATHarrisRidsOgcRp G. Hill, OIS (2)RidsNrrDirsltsbRidsAcrsAcnwMailCenter RidsRgn3MailCenterADAMS ACCESSION NO: ML063040261OFFICENRR/LPL3-1/PMNRR/LPL3-1/LANRR/LPL3-1/BC NAMEDJaffeTHarrisLRaghavanDATE10/31/0610/31/0611/3/06OFFICIAL RECORD COPY Kewaunee Power Station cc:

Resident Inspectors OfficeU.S. Nuclear Regulatory Commission N490 Hwy 42 Kewaunee, WI 54216-9510Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351Ms. Leslie N. HartzDominion Energy Kewaunee, Inc.

Kewaunee Power Station N 490 Highway 42 Kewaunee, WI 54216Mr. Chris L. FunderburkDirector, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. Thomas L. BreeneDominon Energy Kewaunee, Inc.

Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216Ms. Lillian M. Cuoco, Esq.Senior Counsel Dominion Resources Services, Inc.

Millstone Power Station Building 475, 5th Floor Rope Ferry Road Waterford, CT 06385 g.Inoperable Rod Limitations1.An inoperable rod is a rod which does not trip or which is declared Inoperableunder TS 3.1 0.e or TS 3.1 0.h.2.Not more than one inoperable full length rod shall be allowed at any time.

3.If reactor operation is continued with one inoperable full length rod, the potentialejected rod worth and associated transient power distribution peaking factors shall be determined by analysis within 30 days unless the rod is made OPERABLE earlier. The analysis shall include due allowance for nonuniform fuel depletion in the neighborhood of the inoperable rod. If the analysis results in a more limiting hypothetical transient than the cases reported in the safety analysis, the plant power level shall be reduced to an analytically determined part power level which is consistent with the safety analysis. h.Rod Drop TimeAt OPERATING temperature and full flow, the drop time of each full length rodcluster control shall be no greater than 1.8 seconds from loss of stationary gripper coil voltage to dashpot entry. If drop time is > 1.8 seconds, the rod shall be declared inoperable.i.Rod Position Deviation MonitorIf the rod position deviation monitor is inoperable, individual rod positions shall belogged at least once per eight hours and after a load change > 10% of rated power or after > 24 steps of control rod motion.j.Quadrant Power Tilt MonitorIf one or both of the quadrant power tilt monitors is inoperable, individual upper andlower excore detector calibrated outputs and the quadrant tilt shall be logged once per shift and after a load change > 10% of rated power or after > 24 steps of control rod motion. The monitors shall be set to alarm at 2% tilt ratio.k.Core Average TemperatureDuring steady-state power operation, Tavg, shall be maintained within the limits specifiedin the COLR, except as provided by TS 3.1 0.n.l.Reactor Coolant System PressureDuring steady-state power operation, Reactor Coolant System pressure shall bemaintained within the limits specified In the COLR, except as provided by TS 3.1 0.n.TS 3.10-7Amendment No. 181