ML063040261

Correction of Amendment, Rod Position Indication

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

Text

November 3, 2006 Mr. David A. Christian Senior 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 to Facility 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 TS page 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 to contact me at 301-415-1439 if you have any further questions.

Sincerely,

/RA/

David H. Jaffe, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

As stated cc w/encl: See next page

Mr. David A. Christian November 3, 2006 Senior 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 to Facility 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 TS page 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 to contact me at 301-415-1439 if you have any further questions.

Sincerely,

/RA/

David H. Jaffe, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC LPL3-1 r/f RidsNrrDorlLple RidsNrrPMDJaffe RidsNrrLATHarris RidsOgcRp G. Hill, OIS (2) RidsNrrDirsltsb RidsAcrsAcnwMailCenter RidsRgn3MailCenter ADAMS ACCESSION NO: ML063040261 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC NAME DJaffe THarris LRaghavan DATE 10/31/06 10/31/06 11/3/06 OFFICIAL RECORD COPY

Kewaunee Power Station cc:

Resident Inspectors Office Ms. Lillian M. Cuoco, Esq.

U.S. Nuclear Regulatory Commission Senior Counsel N490 Hwy 42 Dominion Resources Services, Inc.

Kewaunee, WI 54216-9510 Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III Rope Ferry Road U.S. Nuclear Regulatory Commission Waterford, CT 06385 Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Ms. Leslie N. Hartz Dominion Energy Kewaunee, Inc.

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

Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216

g. Inoperable Rod Limitations

1. An inoperable rod is a rod which does not trip or which is declared Inoperable under 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 potential ejected 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 Time At OPERATING temperature and full flow, the drop time of each full length rod cluster 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 Monitor If the rod position deviation monitor is inoperable, individual rod positions shall be logged 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 Monitor If one or both of the quadrant power tilt monitors is inoperable, individual upper and lower 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 Temperature During steady-state power operation, Tavg, shall be maintained within the limits specified in the COLR, except as provided by TS 3.1 0.n.

l. Reactor Coolant System Pressure During steady-state power operation, Reactor Coolant System pressure shall be maintained within the limits specified In the COLR, except as provided by TS 3.1 0.n.

TS 3.10-7 Amendment No. 181