| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/17/2010 - 08/18/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 46170 | Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: CODER X-RAY SERVICE
Region: 4
City: McPHERSON State: KS
County:
License #: 21-B165-01
Agreement: Y
Docket:
NRC Notified By: AARON SHORT
HQ OPS Officer: PETE SNYDER | Notification Date: 08/12/2010
Notification Time: 12:22 [ET]
Event Date: 02/13/2010
Event Time: [CDT]
Last Update Date: 08/16/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
MICHELE BURGESS (FSME)
ILTAB via email ()
| Event Text AGREEMENT STATE REPORT - BREAK-IN AT RADIOGRAPHY SOURCE STORAGE LOCATION
On 2/13/2010, Coder X-Ray Services experienced a break-in at their of McPherson, KS business location. Local police responded within minutes. A laptop computer was stolen but there was no indication of attempted theft involving radioactive sources.
The licensee added additional security measures as part of their increased controls for radioactive materials.
The State of Kansas discovered this event on a recent inspection.
* * * UPDATE FROM AARON SHORT TO JOHN KNOKE AT 1603 EDT ON 8/16/10 * * *
The State of Kansas received a police report identifying the burglary at Coder X-ray and Welding in McPherson Kansas. The State also received a letter from the licensee outlining additional security measures they are taking at their facility.
Contact the Headquarters Operations Officer for further details.
Notified R4DO (Geoffrey Miller), FSME (Richard Turtil) and emailed ILTAB |
| General Information or Other | Event Number: 46172 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ALBEMARLE CATALYSTS LP
Region: 4
City: PASADENA State: TX
County:
License #: TX - 01743
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/13/2010
Notification Time: 10:40 [ET]
Event Date: 07/16/2010
Event Time: [CDT]
Last Update Date: 08/13/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANGELA MCINTOSH (FSME)
NEIL OKEEFE (R4DO)
| Event Text AGREEMENT STATE REPORT- TEXAS - STUCK OPEN SHUTTER ON A PROCESS GAUGE
The following report was received via e-mail from the State of Texas Department of State Health Services Radiation Branch:
"On August 13, 2010, the Agency [Texas Department of Health] was notified by the licensee that on July 16, 2010 they discovered that the shutter on a TN Technologies Model 5205 nuclear gauge containing 100 millicuries (original activity) of Cesium (Cs) - 137 was inoperable. The gauge shutter was stuck in the open position, which is the normal operating position. There was no additional exposure risk to any individual due to the failure. The licensee discontinued the use of the gauge and contacted the manufacturer to schedule the repair of the gauge shutter. On July 29, 2010, the manufacturer's technician arrived at the plant to repair the gauge. The technician found a build up of corrosion had occurred preventing the gauge shutter from operating properly. The technician advised the licensee that the gauge and source should be replaced due to the corrosion.
"The gauge was removed from the vessel on July 29, 2010. The technician secured shielding over the source. No significant exposures were received during the source/gauge removal. A leak test of the source was conducted and the results were below the limit. The licensee is making arrangements to dispose of the source and gauge. Additional information will be provided as it is received in accordance with SA 300."
Texas Incident #: I - 8771 |
| Power Reactor | Event Number: 46182 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: LEON RAFNER
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 13:56 [ET]
Event Date: 08/17/2010
Event Time: 03:00 [PDT]
Last Update Date: 08/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| 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 UNANALYZED CONDITION DUE TO POTENTIAL WIRING DISCREPANCY
"On August 16, 2010, at about 0100 PDT, SONGS Unit 2 Train 'A' Emergency Diesel Generator (EDG) 2G002 was removed from service for planned maintenance. Train 'A' EDG is the Appendix R protected Train.
"At about 1545 the same day, Southern California Edison (SCE) discovered a potential wiring discrepancy in the electronic governor. At 0300 on August 17, 2010, SCE determined two wires on a fire isolation fuse were confirmed to be terminated differently than specified in plant drawings and that the discrepancy would prevent the fuse and associated fire isolation switch from performing its Appendix R fire isolation function for the Train 'A' EDG. In accordance with NUREG-1022, Rev. 2, SCE is reporting this occurrence in accordance 10CFR50.72(b)(3)(ii)(B).
"While the incorrect wiring impacted the Appendix R qualifications of the Train 'A' EDG, it did not impact its other design functions and the EDG was capable to fulfill its safety function for all other Design Basis Events. Therefore, SCE considers the safety significance of the condition to be minimal.
"In accordance with LCS specification 3.7.113.1 Condition A, SCE will implement hourly Fire Watches for the impacted plant areas until such time that the wiring on the Unit 3 Train 'A' Emergency Diesel Generator 3G002 is conformed to be correct or has taken actions to correct any wiring discrepancy. An evaluation will be conducted to determine the cause of this condition.
"At the time of this occurrence, Unit 2 and Unit 3 were both at 100% power."
"The NRC Resident Inspector will be notified of this occurrence and will be provided with a copy of this report." |
| Power Reactor | Event Number: 46183 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOEL HOWARD
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 16:32 [ET]
Event Date: 08/17/2010
Event Time: 07:35 [EDT]
Last Update Date: 08/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
BINOY DESAI (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMPTY BEER CAN FOUND INSIDE THE PROTECTED AREA
"On August 17, 2010, an empty beer can was discovered in a recycle container inside the Protected Area (PA). The can has been removed from the PA. Further investigation as to how the can was introduced into the PA is in progress. No personnel fitness-for-duty issues related to the consumption of alcohol have been identified. The presence of alcohol with the PA is being reported in accordance with 10CFR26.719(b)(1)."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 46184 | Facility: QUAD CITIES
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: CURT STEFFES
HQ OPS Officer: JOE O'HARA | Notification Date: 08/17/2010
Notification Time: 16:54 [ET]
Event Date: 08/17/2010
Event Time: 14:14 [CDT]
Last Update Date: 08/17/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
NICK VALOS (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM INITIATED DUE TO RECIRCULATION PUMP TRIP
"On August 17, 2010, at 1414 hours, a manual scram was inserted on Unit 2 due to rising reactor water level. The water level increase was caused by a trip of the 2B Recirculation Pump. Restoration of the 2B Recirculation Pump Programmable Logic Controller (PLC) on the 2B Adjustable Speed Drive (ASD) was in progress at the time of the event. Following the reactor scram, reactor water level decreased to approximately minus 15 inches, which resulted in automatic Group II and III isolations as expected. All systems responded properly to the event. The cause of the event is still under investigation.
"Unit I was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)."
All control rods inserted on the scram. No ECCS initiations occurred. No safety or relief valves lifted. The unit is stable in Mode 3 at 926 psig and 530 degrees Fahrenheit. Pressure is being controlled on the turbine bypass system.
The licensee notified the NRC Resident Inspector and the Illinois Department of Nuclear Safety. | |