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Event Notification Report for March 23, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/22/2006 - 03/23/2006

** EVENT NUMBERS **


42427 42439 42443 42444

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General Information or Other Event Number: 42427
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: PROFESSIONAL INSPECTION AND TESTING INC
Region: 1
City: MT AIRY State: MD
County:
License #: MD-13-021-01
Agreement: Y
Docket:
NRC Notified By: RAY MANLEY
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/17/2006
Notification Time: 11:16 [ET]
Event Date: 03/17/2006
Event Time: [EST]
Last Update Date: 03/17/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1)
TOM ESSIG (NMSS)
ILTAB (email) (NSIR)

Event Text

MARYLAND AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

A Troxler model 3430 moisture density gauge was stolen from a locked storage trailer on a temporary jobsite on Reistertown Road in Pikesville, MD. The gauge serial number is #23191 and contained a 8 millicurie Cs-137 source and 40 millicurie Am-241 source. The Maryland State inspectors and the Baltimore City Police are on the scene to conduct their investigation. The Maryland Department of the Environment will be issuing a press release on 3/17/06.

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks.

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Power Reactor Event Number: 42439
Facility: CATAWBA
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDY HART
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/22/2006
Notification Time: 09:27 [ET]
Event Date: 03/22/2006
Event Time: 09:15 [EST]
Last Update Date: 03/22/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
CAROLYN EVANS (R2)
THOMAS BLOUNT (IRD)
GENE IMBRO (NRR)
MEL LEACH (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling

Event Text

ON-SITE FATALITY

"On March 22, 2006 at approximately 0341 hours the site medical response team responded to a notification that a Duke employee had collapsed due to personal illness in the Unit 2 Reactor Lower Containment. Unit 2 is currently shutdown in Mode 6 in a refueling outage. The site medical response team called for an ambulance to transport the individual offsite. After the ambulance arrived on site, the ambulance attendants were notified by radiation protection personnel that the individual was considered potentially contaminated because he could not be surveyed. The ambulance left the site at approximately 0459. Radiation Protection personnel accompanied the individual to the medical facility. Upon arrival at the medical facility, a complete survey of the individual was made and no radioactive contamination was found either on the individual or on his clothing. The individual did not survive the personal illness. This situation is determined to be reportable per 10 CPR 50.72 (b)(2)(xi) because this event will be reported to an offsite government agency, OSHA. At this time no press release is planned."

The individual was sitting down in containment because he was not feeling well. His co-worker started up a ladder, turned, and noticed the individual was slumped over. He was pronounced dead in the ambulance when it arrived at the hospital. Containment temperature at this time was in the upper 60s.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 42443
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JAMES JOHNSTONE
HQ OPS Officer: PETE SNYDER
Notification Date: 03/22/2006
Notification Time: 18:16 [ET]
Event Date: 03/22/2006
Event Time: 12:51 [EST]
Last Update Date: 03/22/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling Shutdown 0 Refueling Shutdown
2 N Y 100 Power Operation 100 Power Operation

Event Text

POTENTIAL LOSS OF COMMUNICATION SIRENS

"On March 22, 2006, an unscheduled poll of the North Anna sirens was initiated. During the period from 1251 to 1303 hours, actuation signals were not received at the transmitter and no outgoing signal was transmitted to the sirens. This event is a loss of the Emergency Notification System and is reportable per 10 CFR 50.72 (b)(3)(xiii).

"At 1303 hours, telecommunications notified [the plant staff] that the siren system was operational. The cause of the failure is being investigated."

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 42444
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAY WHITWORTH
HQ OPS Officer: PETE SNYDER
Notification Date: 03/22/2006
Notification Time: 19:49 [ET]
Event Date: 03/22/2006
Event Time: 16:24 [EST]
Last Update Date: 03/22/2006
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):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 0 Hot Standby

Event Text

TURBINE TRIP / REACTOR TRIP CAUSED BY MAIN GENERATOR TRIP

"This notification fulfills the 4-hr. non-emergency reporting requirement for Reactor Protection System actuation and the 8-hr. non-emergency reporting requirement for an ESF actuation (specifically Auxiliary Feedwater System start).

"At 1624 EST, Unit 2 reactor tripped from full power due to main generator trip caused by actuation of the main generator neutral overvoltage relay (the 100% stator ground fault relay also actuated). Safety Injection did not actuate and was not required to actuate.

"All automatic actions occurred as designed (e.g., steam dump operation, feedwater system, etc.).

"The operating crew responded to the trip using emergency procedures. The unit is being maintained in Mode 3 (Hot Standby) using General Operating Instructions.

"No primary steam or steam generator safety valves opened due to this trip.

"An investigation has been initiated to determine the cause of this unit trip. A recovery plan will be developed."

All control rods fully inserted on the reactor trip. Decay heat is being removed by auxiliary feedwater feeding the steam generators and steaming through the steam dump valves to the main condenser. Offsite power is stable and all emergency busses are being powered via offsite power. All Emergency Diesel Generators are available if required.

The licensee notified the NRC Resident Inspector.

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Friday, March 30, 2012