| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/09/2010 - 02/10/2010 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45680 | Rep Org: COLORADO DEPT OF HEALTH
Licensee: Public Service Company of Colorado
Region: 4
City: State: CO
County:
License #: 032-01
Agreement: Y
Docket:
NRC Notified By: JAMES JARVIS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/04/2010
Notification Time: 18:17 [ET]
Event Date: 11/12/2009
Event Time: [MST]
Last Update Date: 02/04/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VINCENT GADDY (R4DO)
MARK SHAFFER (FSME)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE EXPOSURE INCIDENT
The following information was received via E-mail:
"On November 12, 2009, two Public Service Company of Colorado (PSCo) employees removed a fixed gauge (including the source and detector) that was mounted on a pipe to measure scrubber slurry flow. The detector was not working correctly and needed to be repaired. During the process, the employees left the shutter on the source open and received a radiation exposure. Removing the source from the pipe and leaving the shutter open are not allowed by company procedures or the radioactive materials license.
"The Colorado Department of Public Health and Environment (CDPHE) was contacted about the November 12, 2009 incident by the PSCo Radiation Safety Officer (RSO) on November 12, 2009. At the time CDPHE was contacted it was believed that the shutter had been closed during the work and that there was no unplanned employee exposure. CDPHE was informed that PSCo employees would perform no further work on the source holder and that it was secured at the location where it was taken down. Also, any further work to reinstall the source would be performed by an NRC certified entity. Public Service Company of Colorado (License #032-01) is a specific licensee of the State of Colorado Agreement State Program.
"On January 29, 2010 while talking to the instrument and control technician employees that had performed the (November 12, 2009) gauge removal, the PSCo RSO learned that the shutter had in fact been open during the work, and the shutter was locked after the source was taken down from its operating location. This was the first time the employee working on the gauge had informed anyone about the shutter being open while the employees removed the detector. On the afternoon of January 29, 2010 the PSCo RSO notified CDPHE via email to provide initial notification of the potential radiation exposure incident.
"On February 4, 2010 the RSO for PSCo submitted additional information to CDPHE regarding the incident including exposure estimates for the employees involved. The licensee estimated that employee #1 received an exposure of approximately 25 mrem, while employee #2 received an exposure of approximately 0.9 mrem.
"The gauge involved in the incident was an Ohmart model SR-A, Source Holder Serial #2690CG, containing approximately 50 mCi (1.85 GBq) of Cs-137 (source mfg date is April 2002). The gauge was originally installed in the licensee's facility in October, 2002.
"The Colorado Department of Public Health and Environment has assigned incident number I10-02 to this incident and is continuing to investigate. The licensee (PSCo) has started an incident investigation to evaluate the incident and determine appropriate corrective actions." |
| General Information or Other | Event Number: 45681 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: GEORGIA PACIFIC TOLEDO
Region: 4
City: TOLEDO State: OR
County:
License #: ORE-90708
Agreement: Y
Docket:
NRC Notified By: KEVIN SIEBERT
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/04/2010
Notification Time: 18:30 [ET]
Event Date: 02/04/2010
Event Time: 14:20 [PST]
Last Update Date: 02/04/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
VINCENT GADDY (R4DO)
MARK SHAFFER (FSME)
| Event Text AGREEMENT STATE REPORT - FAULTY SHUTTER ON FIXED GUAGE
Licensee, Georgia Pacific Toledo, notified the Agency [Oregon Department of Health and Radiation Protection] that the 6 month inspection on their K-Ray fixed gauge (model 7062B) revealed the shutter would not close correctly. The gauge was still able to perform it's function as a level indicator on a coal bin. Licensee called the manufacturer for repairs. Source is 50 mCi of Cs-137.
Incident Report # 10-0005 |
| Power Reactor | Event Number: 45687 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RAY SWAFFORD
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/08/2010
Notification Time: 18:52 [ET]
Event Date: 02/08/2010
Event Time: 12:00 [CST]
Last Update Date: 02/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
DAVID AYRES (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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY - CONFIRMED POSITIVE ALCOHOL TEST FOR A NON-LICENSED SUPERVISOR
A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access has been suspended. Contact the Headquarters Operations Officer for additional details.
* * * UPDATE FROM RAY SWAFFORD TO DONALD NORWOOD AT 1556 ON 2/9/2010 * * *
Updated information provided by the licensee. Contact the Headquarters Operations Officer for additional details. |
| Other Nuclear Material | Event Number: 45689 | Rep Org: AMERICAN ELECTRIC POWER
Licensee: PHILIP SPORN PLANT
Region: 1
City: NEW HAVEN State: WV
County: MASON
License #: CL-655015-13
Agreement: N
Docket:
NRC Notified By: JERI MACKNIGHT
HQ OPS Officer: DONG HWA PARK | Notification Date: 02/09/2010
Notification Time: 09:50 [ET]
Event Date: 02/08/2010
Event Time: 10:30 [EST]
Last Update Date: 02/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
RAY POWELL (R1DO)
MARK SHAFFER (FSME)
| Event Text SHUTTER ON NUCLEAR GAUGE FAILED TO CLOSE
"Ash hopper nuclear level detector (NLD) on Unit 2 hoppers 9 and 13 (dual source) has its shutter failed in the open position. The gauge is a TN 5197, serial number B8031. The gauge manufacturer (Thermo Electron) had been notified and requested to assess and repair the gauge."
"Isotope: Cs-137
"Activity: 100 mCi"
No exposure to personnel occurred during this event and the detector is not easily accessible. |
| Power Reactor | Event Number: 45690 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BOB MEIXELL
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/09/2010
Notification Time: 09:57 [ET]
Event Date: 02/09/2010
Event Time: 09:00 [EST]
Last Update Date: 02/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
DAVID AYRES (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 | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION TO SOUTH CAROLINA DHEC CONCERNING TRITIUM FOUND IN GROUND WATER
"Event Description: Ground water monitoring wells were installed on the Oconee site and initially sampled in 2008 in support of the Nuclear Energy Institute (NEI) Ground Water Protection Initiative (NEI 07-07). As part of an on-going investigation, a number of new monitoring wells have been installed and additional wells are in progress at Oconee. On February 8, 2010, Oconee was notified by the Duke Energy Environmental Lab that samples taken on January 26, 2010, from monitoring wells GM-7R and GM-7DR displayed tritium levels of 24,400 pCi/l and 35,400 pCi/l respectively, triggering the communication protocol of the NEI initiative. The threshold for initiating the communication protocol is 20,000 pCi/l. There is no public or plant worker risk associated with the GM-7R and GM-7DR well samples. Wells GM-7R and GM-7DR are not drinking water sources and therefore, there is no potential dose to the public or plant workers. Samples from surrounding monitoring wells indicate that tritium in ground water has not migrated off the plant site. Duke is continuing to investigate the source of tritium in wells GM-7R and GM-7DR. Tritium levels in samples from the remaining wells are below the communication protocol threshold. The licensee plans to notify the South Carolina DHEC state officials and local stakeholders of the sample results.
"Initial Safety Significance: There is no safety significance due to the tritium identified in ground water at Oconee. The subject wells are not drinking water sources, and there is no indication tritium has migrated off the Oconee site in the ground water.
"Corrective Action(s): The source of tritium in the ground water at Oconee is not understood at this time. Duke is continuing an investigation to identify the source and implement a corrective action plan."
The licensee will issue a press release and has informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 45692 | Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: BILL STUCKER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/09/2010
Notification Time: 22:49 [ET]
Event Date: 02/09/2010
Event Time: 18:00 [CST]
Last Update Date: 02/09/2010 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
WILLIAM JONES (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text POTENTIAL POST FIRE SAFE SHUTDOWN UNANALYZED CONDITION
"A potential Post-Fire Safe Shutdown issue associated with the 'B' Emergency Diesel Generator Voltage Control Circuitry has been discovered, should a Control Room fire cause a hot short in the 'B' EDG Voltage Control Circuitry. A fire in the control circuit that renders the 'B' EDG inoperable and is large enough to require the Control Room to be evacuated during a loss of offsite power is an unanalyzed condition. This condition was discovered during a planned maintenance outage for the 'B' EDG. Compensatory measures are being established for early detection and extinguishment of a fire associated with this circuit in the Control Room.
"The NRC Resident Inspector has been notified." | |