Event Notification Report for December 26, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/25/2005 - 12/26/2005
General Information or Other
Event Number: 42227
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: HNTB CORP
Region: 1
City: GAINESVILLE State: FL
County:
License #: 3387-1
Agreement: Y
Docket:
NRC Notified By: STEVEN FURNACE
HQ OPS Officer: JEFF ROTTON
Licensee: HNTB CORP
Region: 1
City: GAINESVILLE State: FL
County:
License #: 3387-1
Agreement: Y
Docket:
NRC Notified By: STEVEN FURNACE
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/26/2005
Notification Time: 11:33 [ET]
Event Date: 12/26/2005
Event Time: 08:30 [EST]
Last Update Date: 12/27/2005
Notification Time: 11:33 [ET]
Event Date: 12/26/2005
Event Time: 08:30 [EST]
Last Update Date: 12/27/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
BRIAN MCDERMOTT (R1)
LARRY CAMPER (NMSS)
JIM WHITNEY (EMAIL) (TAS)
BRIAN MCDERMOTT (R1)
LARRY CAMPER (NMSS)
JIM WHITNEY (EMAIL) (TAS)
AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
Licensee reported that a model 3440 Troxler moisture density gauge containing 8 millicuries of Cs-137 and 40 millicuries of Am/Be-241 was stolen from a trailer located next to a highway construction site in Lakeland, FL. The gauge was located in the locked trailer, and the gauge was locked in the transportation case with the source in the stored position. The site was surrounded by a chain link fence and the trailer was pried open. Also stolen were vehicles and equipment. Lakeland Police have been notified.
The licensee noticed the theft at 0830 12/26/2005. A reward will be offered.
Troxler Serial Number 33567
Cs-137 Source #750-9252
Am/Be-241 Source #47-15619
Lakeland Police Report Number 2005-100863
* * * UPDATE PROVIDED BY STATE TO JEFF ROTTON AT 1035 EST ON 12/27/05 * * *
The State provided the following information via email:
"Licensee reported that their worksite had been vandalized on December 25. Many items plus a contractor's vehicle were stolen. Incident was reported to this office [Florida Bureau of Radiation Control] on 1130 December 26. On December 27, licensee reported that police had discovered the stolen vehicle with the gauge at Providence & Griffin road, less than two miles from the worksite. Gauge was still locked in case and that there was no damage to case/gauge. The licensee has taken possession of the gauge and will perform a leak test. Florida continues it's investigation.
FL Incident Number: FL05-183
Notified R1DO (Sykes) and NMSS EO (Holahan), and TAS (Whitney via E-mail)
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.
Licensee reported that a model 3440 Troxler moisture density gauge containing 8 millicuries of Cs-137 and 40 millicuries of Am/Be-241 was stolen from a trailer located next to a highway construction site in Lakeland, FL. The gauge was located in the locked trailer, and the gauge was locked in the transportation case with the source in the stored position. The site was surrounded by a chain link fence and the trailer was pried open. Also stolen were vehicles and equipment. Lakeland Police have been notified.
The licensee noticed the theft at 0830 12/26/2005. A reward will be offered.
Troxler Serial Number 33567
Cs-137 Source #750-9252
Am/Be-241 Source #47-15619
Lakeland Police Report Number 2005-100863
* * * UPDATE PROVIDED BY STATE TO JEFF ROTTON AT 1035 EST ON 12/27/05 * * *
The State provided the following information via email:
"Licensee reported that their worksite had been vandalized on December 25. Many items plus a contractor's vehicle were stolen. Incident was reported to this office [Florida Bureau of Radiation Control] on 1130 December 26. On December 27, licensee reported that police had discovered the stolen vehicle with the gauge at Providence & Griffin road, less than two miles from the worksite. Gauge was still locked in case and that there was no damage to case/gauge. The licensee has taken possession of the gauge and will perform a leak test. Florida continues it's investigation.
FL Incident Number: FL05-183
Notified R1DO (Sykes) and NMSS EO (Holahan), and TAS (Whitney via E-mail)
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.
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
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
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
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)
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 |
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.
" 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.