Event Notification Report for October 18, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/17/2010 - 10/18/2010
General Information or Other
Event Number: 46343
Rep Org: COLORADO DEPT OF HEALTH
Licensee: UTAH INSPECTION LLC
Region: 4
City: DE BEQUE State: CO
County:
License #: 1043-01
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JOE O'HARA
Licensee: UTAH INSPECTION LLC
Region: 4
City: DE BEQUE State: CO
County:
License #: 1043-01
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/19/2010
Notification Time: 13:07 [ET]
Event Date: 10/18/2010
Event Time: 00:00 [MDT]
Last Update Date: 10/19/2010
Notification Time: 13:07 [ET]
Event Date: 10/18/2010
Event Time: 00:00 [MDT]
Last Update Date: 10/19/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
VIVIAN CAMPBELL (R4DO)
MICHELE BURGESS (FSME)
VIVIAN CAMPBELL (R4DO)
MICHELE BURGESS (FSME)
AGREEMENT STATE REPORT - STUCK SOURCE
The following report was received via fax:
"This memo is to serve as a preliminary report for an incident with a Colorado radiography licensee. Utah Inspection, LLC (Colorado license 1043-01) reported to the [Colorado Department of Health (CDH)] on October 18, 2010 a stuck source/source disconnect for a radiography source. The job site was at a gas compressor station in De Beque, Colorado. Initial reports indicate the source was approximately 60 Ci of Ir-I92.
"Utah Inspection contacted the CDH at approximately 2:30 pm on October 18,2010 to report the incident. The licensee reported that while performing a radiography shot, the camera slipped off a wet pipe and landed on the guide tube causing a crimp in the tube which prevented the source from being retracted. The licensee extended the boundaries around the source and maintained surveillance of the source. The licensee contracted with a local Radiation Safety Officer trained in source retrieval activities and was able to retract the source to the shielded position at approximately 7:15 pm on October 18, 2010.
"A member of the CDH responded to the incident scene as the retraction efforts were being completed. The RSO contracted for the source retrieval reported an estimated 138 mrem whole body, and the radiographer estimated doses at 50 mrem whole body for himself and 25 mrem whole body for his assistant. Individual overexposure does not appear to be an issue at this point for this incident. The individual from the CDH confirmed that the area was very isolated and the radiographer and assistant were able to maintain their distance from the source."
Colorado Incident I10-13.
The following report was received via fax:
"This memo is to serve as a preliminary report for an incident with a Colorado radiography licensee. Utah Inspection, LLC (Colorado license 1043-01) reported to the [Colorado Department of Health (CDH)] on October 18, 2010 a stuck source/source disconnect for a radiography source. The job site was at a gas compressor station in De Beque, Colorado. Initial reports indicate the source was approximately 60 Ci of Ir-I92.
"Utah Inspection contacted the CDH at approximately 2:30 pm on October 18,2010 to report the incident. The licensee reported that while performing a radiography shot, the camera slipped off a wet pipe and landed on the guide tube causing a crimp in the tube which prevented the source from being retracted. The licensee extended the boundaries around the source and maintained surveillance of the source. The licensee contracted with a local Radiation Safety Officer trained in source retrieval activities and was able to retract the source to the shielded position at approximately 7:15 pm on October 18, 2010.
"A member of the CDH responded to the incident scene as the retraction efforts were being completed. The RSO contracted for the source retrieval reported an estimated 138 mrem whole body, and the radiographer estimated doses at 50 mrem whole body for himself and 25 mrem whole body for his assistant. Individual overexposure does not appear to be an issue at this point for this incident. The individual from the CDH confirmed that the area was very isolated and the radiographer and assistant were able to maintain their distance from the source."
Colorado Incident I10-13.
Other Nuclear Material
Event Number: 46341
Rep Org: ARCELORMITTAL BURNS HARBOR
Licensee: ARCELORMITTAL BURNS HARBOR
Region: 3
City: BURNS HARBOR State: IN
County:
License #: 13-32670-01
Agreement: N
Docket:
NRC Notified By: CHRIS SARVANIDIS
HQ OPS Officer: ERIC SIMPSON
Licensee: ARCELORMITTAL BURNS HARBOR
Region: 3
City: BURNS HARBOR State: IN
County:
License #: 13-32670-01
Agreement: N
Docket:
NRC Notified By: CHRIS SARVANIDIS
HQ OPS Officer: ERIC SIMPSON
Notification Date: 10/18/2010
Notification Time: 13:38 [ET]
Event Date: 10/18/2010
Event Time: 07:00 [EDT]
Last Update Date: 10/18/2010
Notification Time: 13:38 [ET]
Event Date: 10/18/2010
Event Time: 07:00 [EDT]
Last Update Date: 10/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
STEVE ORTH (R3DO)
MICHELE BURGESS (FSME)
STEVE ORTH (R3DO)
MICHELE BURGESS (FSME)
STUCK GAUGE SHUTTER
On 10/18/10 at approximately 8:32 am, the site Radiation Safety Officer (RSO) was contacted by a radiation worker at the 80" Hot Strip Mill location, indicating that the shutter on one of the slab detection radiation gauges would not close. The worker was in the process of performing a semi-annual wipe test when the situation was noticed.
The RSO directed site workers to barricade the area until he arrived. Upon arrival, the RSO conducted a survey of the area, compared the levels to a prior survey and found no significant difference in radiation levels. The RSO also performed a wipe test on the gauge and checked it with a survey meter and pancake probe, finding no detectable contamination. The radiation worker was directed to check the device counts using a survey meter and to compare them to counts on an adjacent gauge. The counts were similar, indicating proper function.
A melted metallic material was noted adjacent to the gauge whose shutter would not close. The material was analyzed and it showed to be 90-95% lead. As a result, it is believed some shielding may have overheated and blocked the shutter open or debris entered the shutter arm blocking it from closing. Although radiation levels in the area are normal, the RSO will attempt to safely remove the gauge to a secure location until the device can be serviced by the manufacturer.
The Cs-137 source is S/N 6326CM of a slab detection device manufactured by Ronan Engineering.
On 10/18/10 at approximately 8:32 am, the site Radiation Safety Officer (RSO) was contacted by a radiation worker at the 80" Hot Strip Mill location, indicating that the shutter on one of the slab detection radiation gauges would not close. The worker was in the process of performing a semi-annual wipe test when the situation was noticed.
The RSO directed site workers to barricade the area until he arrived. Upon arrival, the RSO conducted a survey of the area, compared the levels to a prior survey and found no significant difference in radiation levels. The RSO also performed a wipe test on the gauge and checked it with a survey meter and pancake probe, finding no detectable contamination. The radiation worker was directed to check the device counts using a survey meter and to compare them to counts on an adjacent gauge. The counts were similar, indicating proper function.
A melted metallic material was noted adjacent to the gauge whose shutter would not close. The material was analyzed and it showed to be 90-95% lead. As a result, it is believed some shielding may have overheated and blocked the shutter open or debris entered the shutter arm blocking it from closing. Although radiation levels in the area are normal, the RSO will attempt to safely remove the gauge to a secure location until the device can be serviced by the manufacturer.
The Cs-137 source is S/N 6326CM of a slab detection device manufactured by Ronan Engineering.
Power Reactor
Event Number: 46339
Facility: COOK
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: PETE SNYDER
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: PETE SNYDER
Notification Date: 10/18/2010
Notification Time: 09:34 [ET]
Event Date: 10/18/2010
Event Time: 10:00 [EDT]
Last Update Date: 10/18/2010
Notification Time: 09:34 [ET]
Event Date: 10/18/2010
Event Time: 10:00 [EDT]
Last Update Date: 10/18/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
STEVE ORTH (R3DO)
STEVE ORTH (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
UNAVAILABILITY OF EMERGENCY RESPONSE DATA SYSTEM (ERDS) FOR SCHEDULED MAINTENANCE
"At approximately 10:00 a.m. on Monday, October 18, 2010, the Cook Nuclear Plant (CNP) Unit 2 Plant Process Computer (PPC) will be removed from service for scheduled power supply distribution panel preventive maintenance. This will remove Unit 2 PPC data input to ERDS rendering the system non functional for providing data to the NRC Operations Center. The scheduled maintenance will also affect the Safety Parameter Display System (SPDS), the Real Time Data Repository (RDR), and PPC data to Emergency Response Facilities at CNP.
"The scheduled maintenance is expected to take up to 6 hours to complete.
"Compensatory measures exist within the CNP Emergency Response procedure to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)."
CNP Unit 2 is currently defueled.
* * * UPDATE FROM DEAN BRUCK TO JOE O'HARA AT 1518 EDT ON 10/18/10 * * *
"Functionality has been restored to ERDS following restoration of the Unit 2 PPC at 1422. SPDS, RDR, and PPC data to Emergency Response Facilities at CNP have also been restored to service at 1422."
The NRC Resident Inspector has been notified.
Notified R3DO(Orth).
"At approximately 10:00 a.m. on Monday, October 18, 2010, the Cook Nuclear Plant (CNP) Unit 2 Plant Process Computer (PPC) will be removed from service for scheduled power supply distribution panel preventive maintenance. This will remove Unit 2 PPC data input to ERDS rendering the system non functional for providing data to the NRC Operations Center. The scheduled maintenance will also affect the Safety Parameter Display System (SPDS), the Real Time Data Repository (RDR), and PPC data to Emergency Response Facilities at CNP.
"The scheduled maintenance is expected to take up to 6 hours to complete.
"Compensatory measures exist within the CNP Emergency Response procedure to provide plant data via the Emergency Notification System to the NRC Operations Center until the ERDS can be returned to service.
"The licensee has notified the NRC Senior Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72 (b)(3)(xiii) due to any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)."
CNP Unit 2 is currently defueled.
* * * UPDATE FROM DEAN BRUCK TO JOE O'HARA AT 1518 EDT ON 10/18/10 * * *
"Functionality has been restored to ERDS following restoration of the Unit 2 PPC at 1422. SPDS, RDR, and PPC data to Emergency Response Facilities at CNP have also been restored to service at 1422."
The NRC Resident Inspector has been notified.
Notified R3DO(Orth).