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Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for December 27, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/23/2005 - 12/27/2005

** EVENT NUMBERS **


42214 42223 42224 42229

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General Information or Other Event Number: 42214
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: CBC ENGINEERS AND ASSOCIATES, LTD.
Region: 3
City: CENTERVILLE State: OH
County:
License #: 31210580000
Agreement: Y
Docket:
NRC Notified By: STEPHEN JAMES
HQ OPS Officer: JOHN MacKINNON 		Notification Date: 12/21/2005
Notification Time: 12:06 [ET]
Event Date: 12/19/2005
Event Time: 12:00 [EST]
Last Update Date: 12/21/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
 Person (Organization):
HIRONORI PETERSON (R3)
GREG MORELL (NMSS)

Event Text

OHIO AGREEMENT STATE REPORT: DAMAGED TROXLER MOISTURE DENSITY GAUGE


"ODH was notified on 12/19/05 by the licensee that a Troxler moisture density gauge received extensive damage when it was run over by a construction vehicle at a job site. The gauge was a Troxler Model 3430, serial number 31068, containing 8 mCi (millicuries) of Cs-137 and 40 mCi (millicuries) of Am-241. Preliminary notification by the licensee is that the gauge was left unattended but is still in site of the operator, who had gone back to their truck to verify information for the next analysis. While the operator was away from the gauge, the construction vehicle approached the location and ran over the gauge. The gauge user was unable to get back to the gauge and wave away the truck driver before the gauge was run over. The gauge casing was destroyed but initial surveys performed on site indicate that the sources remained intact. The gauge was packed into the transport case and transported to a gauge service provider for leak testing and packaging for return to the manufacturer. An investigation is being conducted by ODH."

ITEM NUMBER: OH050010

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General Information or Other Event Number: 42223
Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: CARDINAL HEALTH
Region: 4
City: LAWRENCE State: KS
County:
License #: 20-B-708-01
Agreement: Y
Docket:
NRC Notified By: KIM STEVES
HQ OPS Officer: BILL HUFFMAN 		Notification Date: 12/22/2005
Notification Time: 17:38 [ET]
Event Date: 12/22/2005
Event Time: 06:30 [CST]
Last Update Date: 12/22/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
 Person (Organization):
MARK SHAFFER (R4)
HIRONORI PETERSON (R3)
LARRY CAMPER (NMSS)

Event Text

AGREEMENT STATE REPORT OF TRAFFIC ACCIDENT INVOLVING RADIOACTIVE MATERIAL

A truck carrying 600 millicuries of Technetium-99m (150 ml in two containers) was involved in a traffic accident in Lawrence Kansas. The containers were undamaged by the accident and a survey of the containers and truck determined that the was no leakage or radioactive contamination. The Technetium has been secured and taken into possession by representatives of Cardinal Health.

Kansas Report # 7831227

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Power Reactor Event Number: 42224
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: MICHAEL HIMEBAUCH
HQ OPS Officer: MARK ABRAMOVITZ 		Notification Date: 12/23/2005
Notification Time: 02:22 [ET]
Event Date: 12/22/2005
Event Time: 22:25 [EST]
Last Update Date: 12/23/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
 Person (Organization):
HIRONORI PETERSON (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

EECW TEMPERATURE CONTROL VALVE NOT FULLY OPEN

"While performing Div. 1 & 2 Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) Valve Lineup Verification surveillance on 12/22/05, the temperature control valve (TCV) on both divisions of EECW were found to be approximately 95% open rather than their required full open position. The system design requires that the TCV, or the associated TCV bypass valve, be in the full open position during system startup to avoid a potentially damaging pressure transient from occurring. Both divisions of EECW and all supported systems (including HPCl, both divisions Core Spray, and both divisions of RHR) were declared INOPERABLE at 2225 EST. Multiple LCO Required Actions were entered, including entry into LCO 3.0.3. At 2250 EST, Div. 1 EECW was restored to OPERABLE status by fully opening the TCV bypass valve and isolating the TCV, and LCO 3.0.3 was exited. At 2252 EST, Div. 2 EECW was restored to OPERABLE status by fully opening the TCV bypass valve and isolating the TCV, and all associated LCO Required Actions were exited. Reactor power remained at 100% throughout the event. The NRC resident inspector has been notified. This report is being made pursuant to 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition and 10CFR50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident."

The licensee is investigating the cause of the valve not being fully open. The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42229
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: JAMES CRABILL
HQ OPS Officer: BILL HUFFMAN 		Notification Date: 12/26/2005
Notification Time: 15:35 [ET]
Event Date: 12/26/2005
Event Time: 10:47 [CST]
Last Update Date: 12/26/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
 Person (Organization):
MARK SHAFFER (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 95 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP FOLLOWING TURBINE TRIP

" A reactor trip occurred due to a Reactor Protective System (RPS) actuation from probable Main Turbine problems. The Emergency Feedwater Initiation and Control System (EFIC) actuated on the 'A' Steam Generator only due to a momentary level spike post trip. The RPS and EFIC performed as designed. Unit 1 will remain in mode 3 for troubleshooting efforts. No significant equipment issues observed. This report is being made in compliance with the 4 hour and 8 hour non-emergency notifications required by 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A), respectively."

The licensee notified the NRC Resident Inspector and State authorities.

All rods fully inserted. The trip was characterized as uncomplicated and all systems functioned as required. Electrical conditions are stable. The reactor is currently at no load temperature and pressure with decay heat being removed via the turbine bypass valves and cooling to the steam generators from the non-safety related auxiliary feedwater system. The trip had no impact on Unit 2. The licensee was in no significant LCO at the time of the trip. The licensee noted that one of the main steam code safeties did stick open for a short period of time but closed after secondary pressure was reduced without any overcooling. The cause of the turbine trip is under investigation.

Page Last Reviewed/Updated Thursday, March 25, 2021

Page Last Reviewed/Updated Thursday, March 25, 2021