| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/14/2008 - 03/17/2008 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 43802 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/21/2007
Notification Time: 18:55 [ET]
Event Date: 11/21/2007
Event Time: 14:08 [CST]
Last Update Date: 03/14/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARK RING (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 96 | Power Operation | 96 | Power Operation | Event Text SAFETY PARAMETER DISPLAY SYSTEM DEGRADATION
"On 11/21/2007 at 1408 hours, the Clinton Power Station lost a portion of the Safety Parameter Display System in support of Process Computer replacement. These portions are not expected to be restored to service until Process Computer replacement activities are completed. The Plant Process Computer is expected to be fully operational by February 1, 2008.
"This event is reportable due to the major loss of emergency assessment capability per 10CFR50.72 (b)(3)(xiii) (when the SPDS has been unavailable for 8 hours or greater).
"The NRC Resident Inspector has been notified."
The alarm for secondary containment sump level has been lost to the SPDS. Compensatory measures are in effect.
* * * UPDATE ON 3/14/08 AT 1526 EDT FROM KISS TO HUFFMAN * * *
The system upgrade has been completed along with full confidence run testing. The SPDS is now considered operational and emergency assessment capability restored.
The licensee notified the NRC Resident Inspector and State authorities.
R3DO (Ring) was notified. |
| General Information or Other | Event Number: 44052 | Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: TEAM INDUSTRIAL SERVICES, INC.
Region: 4
City: NEBRASKA CITY State: NE
County:
License #: IL-011396-01
Agreement: Y
Docket:
NRC Notified By: HOWARD SHUMAN
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/11/2008
Notification Time: 14:21 [ET]
Event Date: 03/10/2008
Event Time: [CDT]
Last Update Date: 03/11/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TROY PRUETT (R4)
MARK RING (R3)
MICHELE BURGESS (FSME)
| Event Text NEBRASKA AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE
The State of Nebraska Department of Health & Human Services, Radiation Control Program, Radioactive Materials Branch reported that a radiographer employed by Team Industrial Services, Inc. was potentially overexposed while performing radiography at a Nebraska City, NE facility. Team Industrial Services, Inc. is performing work in Nebraska under reciprocity of their Illinois license.
On March 7, 2008, while at the job site, the radiographer noticed that his direct-reading pocket dosimeter was off-scale. He reported this to the regional Team Industrial Services RSO and stated that he believed he just bumped the dosimeter to cause the off-scale condition. The RSO directed him to send his TLD to Landauer Laboratories for processing.
On March 10, 2008, Landauer informed the RSO that the TLD indicated that the radiographer received 7.753 REM Deep Dose Equivalent.
The Team Industrial RSO notified his corporate RSO, who then notified the State of Nebraska. The radiographer has been restricted from radiation areas while Team Industrial and the State of Nebraska investigates this incident. |
| General Information or Other | Event Number: 44053 | Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: APPLIED TECHNOLOGY SERVICES
Region: 1
City: JESSUP State: GA
County: WAYNE
License #: GA-0896-1
Agreement: Y
Docket:
NRC Notified By: JOEL MIMS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/11/2008
Notification Time: 16:16 [ET]
Event Date: 03/11/2008
Event Time: [EDT]
Last Update Date: 03/11/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAYMOND LORSON (R1)
MICHELE BURGESS (FSME)
| Event Text GEORGIA AGREEMENT STATE REPORT
The State of Georgia reported that one of their licensees, Applied Technical Services, was conducting radiography at the Rayonier Paper Mill in Jessup, GA. While filming a tank weld, the radiography camera fell approximately 24 feet to the ground. The licensee was unable to retract the source back into the camera.
The licensee isolated the area and covered the source with temporary lead shielding. Additionally, they established a 2 mR/hr boundary around the source which will be continuously manned until the manufacturer (QSA Global) representative arrives to secure the source and camera.
The licensee reports that no overexposures occurred during this incident. |
| General Information or Other | Event Number: 44058 | Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee: UNKNOWN
Region: 4
City: PORTLAND State: OR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TERRY LINDSEY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 03/12/2008
Notification Time: 18:22 [ET]
Event Date: 03/12/2008
Event Time: 11:30 [PDT]
Last Update Date: 03/13/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
TROY PRUETT (R4)
ANNA BRADFORD (FSME)
| Event Text AGREEMENT STATE - UNIDENTIFIED RADIOACTIVE MATERIAL RECEIVED AT METAL RECYCLING FACILITY
The State of Oregon Radiation Services Section reported that they had sent an inspector to Schnitzer Steel in Portland, Oregon due to unidentified radioactive material that had been received by the facility. A barge of metal for recycling had been received from Amix Recycling of Vancouver, British Columbia that set off a radioactive portal alarm. The radioactive material has not yet been specifically identified. The State inspectors have determined that one of the radioactive sources appears to be a process gauge with a Cesium source. There is also indication of a Radium or Cesium source in a scrap metal pipe. The State will ensure that the sources are adequately secured and will be following the licensees interactions with the originator of the shipment in terms of long term disposition of the sources.
Oregon Report Number 08-0025
* * * UPDATE AT 1921EDT ON 03/13/08 FROM STATE OF OREGON (TERRY LINDSEY) TO STEVE SANDIN VIA EMAIL * * *
"Oregon Radiation Protection Services personnel have completed an initial survey of the empty barge that contained two radiation gauges with Cesium-137. One gauge (mat scanner) was sheared apart with scrap steel equipment and was leaking along both shear points. Both gauges have been secured and contamination has been contained at this time.
"The Oregon 102nd Civil Support Team also assisted with the final survey and decontamination evaluation onsite and the site has been secured for today.
"A U.S. EPA Region X team has been activated by U.S. EPA Duty Officer and is enroute to Oregon to assist with further site evaluation and investigation. Oregon RPS personnel will be coordinating with the U.S. EPA team tomorrow morning for any final survey work and evaluation of potential enforcement concerns related to removal of radiation warning labels from these gauges."
Notified R4DO (Pruett) and FSME (Bradford). |
| Power Reactor | Event Number: 44064 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JIM KONRAD
HQ OPS Officer: HOWIE CROUCH | Notification Date: 03/14/2008
Notification Time: 18:06 [ET]
Event Date: 03/14/2008
Event Time: 10:27 [EDT]
Last Update Date: 03/14/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| Person (Organization):
MARK RING (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 FITNESS FOR DUTY REPORT
A non-licensed employee supervisor had a confirmed positive for an illegal substance during a random fitness-for-duty test. The employee's access to the protected areas was suspended. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector and Greg Hansen in Region III. |
| Power Reactor | Event Number: 44066 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: KEVIN R. BOSTON
HQ OPS Officer: PETE SNYDER | Notification Date: 03/15/2008
Notification Time: 11:19 [ET]
Event Date: 03/15/2008
Event Time: 09:33 [EDT]
Last Update Date: 03/15/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
TROY PRUETT (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 85 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO TURBINE TRIP
"At 09:33 EDT the plant experienced a turbine trip which resulted in a reactor trip from 85%. Plant power was less than 100% due to a [turbine] control valve oscillating problem identified on 3/13/08.
"Post-trip [complications]: one of the four 4160 V busses, Bus 1A1, did not fast transfer from 22 KV to the 161 KV system as expected. This buss loss caused Reactor Coolant Pump RC-3A [to] trip off. Seals on RC-3A appear to be failed. The other 3 RC pumps remained in service for forced circulation through the Steam Generators
"Steam Generator levels are being maintained by Main Feedwater Pump FW-4C. Steaming is through the steam dump and bypass valves to the condensers.
"No primary or secondary relief valves lifted during this event.
"Standard post-trip actions were taken per EOP-00 , followed by a transition to EOP-2. Loss of Off-Site Power. During EOP-00 the plant computer indicated 8 rods not inserted into the reactor core. Secondary and primary rod indication showed all control rods inserted. In response to the difference of rod position indication, emergency boration was implemented. Emergency boration was secured after shutdown margin was verified.
"4160 V buss 1A was reenergized on the 161kv system at 10:31 EDT.
"A transition to plant procedure OP-3A, plant shutdown was made at 10:58 EDT.
"Reactor Coolant Pump RC-3A seal evaluation is in progress. The plant will remain in Mode 3."
The licensee notified the NRC Resident Inspector and plans a press release.
While RCP RC-3A seals indicate the same pressure across them there were no accompanying indications of containment sump water level increasing or high radiation levels in containment.
Decay heat is being removed by normal feedwater feeding the steam generators steaming to the condenser steam dumps. Nuclear Instruments indicated plant shutdown throughout the trip. Safety buses are powered by offsite power and emergency diesel generators are in standby. |
| Power Reactor | Event Number: 44067 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT MINAHAN
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/16/2008
Notification Time: 14:12 [ET]
Event Date: 03/16/2008
Event Time: 11:37 [CDT]
Last Update Date: 03/16/2008 | 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):
TROY PRUETT (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE TO BROKEN SENSING LINE
"At 1137 CDT, Comanche Peak NPP, Unit 2 reactor tripped due to a broken sensing line feeding the vacuum inputs to the 2/3 low vacuum turbine trip. With the reactor power steady at 100%, the turbine trip signal generated a valid RPS reactor trip signal. All control rods fully inserted. Both motor driven AFW pumps and the turbine driven AFW pump started as a result of low steam generator level following the trip.
"Currently Unit 2 is in Mode 3, stable with RCS temperature at no-load program temperature of 557 degree F being maintained on the steam dumps. All 4 steam generators are at program level, being maintained by the motor driven AFW pumps. The turbine driven AFW pump has been returned to standby."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 44068 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: GRANT MELIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/16/2008
Notification Time: 16:52 [ET]
Event Date: 03/16/2008
Event Time: 14:30 [EDT]
Last Update Date: 03/16/2008 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARK LESSER (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF PLANT PROCESS COMPUTER SYSTEM ERDADS
"The Plant Process Computer System (Emergency Response and Data Acquisition System, 'ERDADS') OPCONs for Unit 4 failed causing the NRC Emergency Response Data System Link to be non-functional.
"This is an eight hour NRC Notification for an ERDADS failure which is not corrected in 30 minutes and a loss of ability to supply ERDS data for greater than 30 minutes per 1OCFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector. | |