Event Notification Report for July 09, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/08/2006 - 07/09/2006
General Information or Other
Event Number: 42697
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: BURNS COOLEY DENNIS, INC.
Region: 4
City: RIDGELAND State: MS
County:
License #: MS-619-01
Agreement: Y
Docket:
NRC Notified By: B.J. SMITH
HQ OPS Officer: JOHN KNOKE
Licensee: BURNS COOLEY DENNIS, INC.
Region: 4
City: RIDGELAND State: MS
County:
License #: MS-619-01
Agreement: Y
Docket:
NRC Notified By: B.J. SMITH
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/10/2006
Notification Time: 14:11 [ET]
Event Date: 07/09/2006
Event Time: 21:45 [CDT]
Last Update Date: 07/13/2006
Notification Time: 14:11 [ET]
Event Date: 07/09/2006
Event Time: 21:45 [CDT]
Last Update Date: 07/13/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
LINDA SMITH (R4)
GREG MORELL (NMSS)
LINDA SMITH (R4)
GREG MORELL (NMSS)
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The State provided the following information via email:
"Received notification on 7-9-06 from Mississippi Emergency Management (MEMA) that a Troxler 3440 moisture/density gauge, Serial # 31576, had been involved in a fire at a residential location. The gauge was chained and locked in its approved DOT transportation container to the bed of the pick-up truck. A neighbor had seen the fire and called 911. Ridgeland Fire Department extinguished the truck fire and secured the area. DRH responded to the incident and removed the melted gauge from the truck bed. Survey readings were taken at the truck after the gauge was removed and determined to be background (9 microR/hr).
"DRH responded to the scene and removed the gauge from the bed of the pickup. Gauge was secured in a plastic garbage bag and placed in DRH vehicle. Cesium-137 source rod was shielded with a lead pig. Gauge was brought to DRH office where leak tests were performed and gauge was stored until pick-up by disposal contractor.
"Isotopes: Cesium-137 (9 mCi) and Americium-241/Be (40 mCi)
"Survey readings were 95 mR/hr near the end of the Cesium-137 source rod. Survey readings of the Americium-241/Be source were 5 mR/hr. Survey readings of the sources in the bed of the DRH vehicle after shielding them were 15 mR/hr. Sources were leak tested by DRH and appear not to be leaking."
* * * UPDATE FROM S. SMITH TO W. GOTT AT 1006 ON 7/13/06 * * *
Updated to correct units of the background radiation levels and the survey readings.
The State provided the following information via email:
"Received notification on 7-9-06 from Mississippi Emergency Management (MEMA) that a Troxler 3440 moisture/density gauge, Serial # 31576, had been involved in a fire at a residential location. The gauge was chained and locked in its approved DOT transportation container to the bed of the pick-up truck. A neighbor had seen the fire and called 911. Ridgeland Fire Department extinguished the truck fire and secured the area. DRH responded to the incident and removed the melted gauge from the truck bed. Survey readings were taken at the truck after the gauge was removed and determined to be background (9 microR/hr).
"DRH responded to the scene and removed the gauge from the bed of the pickup. Gauge was secured in a plastic garbage bag and placed in DRH vehicle. Cesium-137 source rod was shielded with a lead pig. Gauge was brought to DRH office where leak tests were performed and gauge was stored until pick-up by disposal contractor.
"Isotopes: Cesium-137 (9 mCi) and Americium-241/Be (40 mCi)
"Survey readings were 95 mR/hr near the end of the Cesium-137 source rod. Survey readings of the Americium-241/Be source were 5 mR/hr. Survey readings of the sources in the bed of the DRH vehicle after shielding them were 15 mR/hr. Sources were leak tested by DRH and appear not to be leaking."
* * * UPDATE FROM S. SMITH TO W. GOTT AT 1006 ON 7/13/06 * * *
Updated to correct units of the background radiation levels and the survey readings.
Power Reactor
Event Number: 42830
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL R MARVEL
HQ OPS Officer: JASON KOZAL
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL R MARVEL
HQ OPS Officer: JASON KOZAL
Notification Date: 09/06/2006
Notification Time: 16:23 [ET]
Event Date: 07/09/2006
Event Time: 18:49 [EDT]
Last Update Date: 09/06/2006
Notification Time: 16:23 [ET]
Event Date: 07/09/2006
Event Time: 18:49 [EDT]
Last Update Date: 09/06/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
WILLIAM COOK (R1)
WILLIAM COOK (R1)
| 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 |
INVALID ACTUATION OF THE B ESW PUMP
"This 60-day ENS report is being made per 10CFR 50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1) to report an invalid automatic actuation of systems listed in paragraph (a)(2)(iv)(B), namely emergency service water (ESW).
"On Sunday July 9, 2006, at 18:49 hours, an invalid actuation of the B ESW pump occurred. The B ESW loop start was a partial actuation and the loop functioned successfully following the invalid actuation. The A ESW loop was not affected.
"An investigation identified that corrosion on the D12 emergency diesel generator (EDG) jacket water pump discharge pressure switch caused the invalid partial actuation. The cause of the pressure switch failure was due to a cracked supply tube, which allowed moisture to enter the cabinet causing the corrosion. EDG jacket water pump discharge pressure is utilized to initiate logic that starts the ESW pump when the EDG is running. ESW is the cooling medium for the EDG. The switch failure also caused inoperability of D12 EDG since it defeated the capability for the EDG to start. The failed pressure switch and associated tubing were replaced and successfully tested. D12 EDG was declared operable on Monday July 10, 2006 at 12:46 hours.
"An inspection of the other seven EDGs identified that the D11 EDG pressure switch was also corroded. The D11 EDG pressure switch was replaced. The inspection determined that the jacket water pressure switches on the other six EDGs were not degraded.
"This event is reportable per 10CFR50.73(a)(2)(iv)(A) since B ESW pump automatically actuated on an invalid signal.
"Component data:
"Equipment number: PSH-GA-110B
"Manufacturer: A160 Allen-Bradley Co.
"Model number: 636-C3"
The licensee notified the NRC Resident Inspector.
"This 60-day ENS report is being made per 10CFR 50.73(a)(2)(iv)(A) and 10CFR50.73(a)(1) to report an invalid automatic actuation of systems listed in paragraph (a)(2)(iv)(B), namely emergency service water (ESW).
"On Sunday July 9, 2006, at 18:49 hours, an invalid actuation of the B ESW pump occurred. The B ESW loop start was a partial actuation and the loop functioned successfully following the invalid actuation. The A ESW loop was not affected.
"An investigation identified that corrosion on the D12 emergency diesel generator (EDG) jacket water pump discharge pressure switch caused the invalid partial actuation. The cause of the pressure switch failure was due to a cracked supply tube, which allowed moisture to enter the cabinet causing the corrosion. EDG jacket water pump discharge pressure is utilized to initiate logic that starts the ESW pump when the EDG is running. ESW is the cooling medium for the EDG. The switch failure also caused inoperability of D12 EDG since it defeated the capability for the EDG to start. The failed pressure switch and associated tubing were replaced and successfully tested. D12 EDG was declared operable on Monday July 10, 2006 at 12:46 hours.
"An inspection of the other seven EDGs identified that the D11 EDG pressure switch was also corroded. The D11 EDG pressure switch was replaced. The inspection determined that the jacket water pressure switches on the other six EDGs were not degraded.
"This event is reportable per 10CFR50.73(a)(2)(iv)(A) since B ESW pump automatically actuated on an invalid signal.
"Component data:
"Equipment number: PSH-GA-110B
"Manufacturer: A160 Allen-Bradley Co.
"Model number: 636-C3"
The licensee notified the NRC Resident Inspector.
Other Nuclear Material
Event Number: 42745
Rep Org: ACUREN INSPECTION, INC.
Licensee: ACUREN INSPECTION, INC
Region: 4
City: LAPORTE State: TX
County:
License #: 42-27593-01
Agreement: Y
Docket:
NRC Notified By: KRISTI KENNEDY
HQ OPS Officer: MIKE RIPLEY
Licensee: ACUREN INSPECTION, INC
Region: 4
City: LAPORTE State: TX
County:
License #: 42-27593-01
Agreement: Y
Docket:
NRC Notified By: KRISTI KENNEDY
HQ OPS Officer: MIKE RIPLEY
Notification Date: 07/31/2006
Notification Time: 16:13 [ET]
Event Date: 07/09/2006
Event Time: 20:50 [CDT]
Last Update Date: 07/31/2006
Notification Time: 16:13 [ET]
Event Date: 07/09/2006
Event Time: 20:50 [CDT]
Last Update Date: 07/31/2006
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):
KENNETH O'BRIEN (R3)
JEFFREY CLARK (R4)
EDWIN HACKETT (NMSS)
KENNETH O'BRIEN (R3)
JEFFREY CLARK (R4)
EDWIN HACKETT (NMSS)
RADIOGRAPHY CAMERA SOURCE UNABLE TO RETRACT
Acuren Inspection, Inc, a Texas corporation doing inspection work in Michigan, provided the following information via email:
"Description of Equipment Problem: The RT crew was using a 'pill stand' (a vertical metal pipe inserted into a coupling on a magnetic tripod with the source guide tube attached to a horizontal cross pipe) used to set up for an exposure. The 'pill stand' fell over during the exposure, thus crimping the source guide tube.
"Cause of Incident: The 'pill stand' was not stabilized on a flat and clean surface prior to exposure.
"Equipment: INC Exposure Device, Model IR-100, SN #4339, loaded with an 83 curie Iridium-192 source (Model 87703, SN #27923B).
"Place, Date, and Time of Incident: Filer City, Michigan, 8:50 PM CST, July 09,2006."
The technicians tried to retract the source assembly into the exposure device, but could not get the drive cable to move either way. Lead blankets were placed over the collimator and part of the guide tube. The technician located the crimp in the source tube and cut approximately a 1 1/2 inch piece of source tube out and freed up the drive cable and slowly cranked the source back in slowly. At 3:10 am, the source was back in the camera. The three licensee technicians involved in the retrieval received 181 mR, 60 mR, and 95 mR respectively by pocket dosimeter. The RSO stated that results for July film badge readings for the technicians will be available in early August. The RSO also stated that there was no damage to the camera or source, and that the guide tube has been replaced.
Acuren Inspection, Inc, a Texas corporation doing inspection work in Michigan, provided the following information via email:
"Description of Equipment Problem: The RT crew was using a 'pill stand' (a vertical metal pipe inserted into a coupling on a magnetic tripod with the source guide tube attached to a horizontal cross pipe) used to set up for an exposure. The 'pill stand' fell over during the exposure, thus crimping the source guide tube.
"Cause of Incident: The 'pill stand' was not stabilized on a flat and clean surface prior to exposure.
"Equipment: INC Exposure Device, Model IR-100, SN #4339, loaded with an 83 curie Iridium-192 source (Model 87703, SN #27923B).
"Place, Date, and Time of Incident: Filer City, Michigan, 8:50 PM CST, July 09,2006."
The technicians tried to retract the source assembly into the exposure device, but could not get the drive cable to move either way. Lead blankets were placed over the collimator and part of the guide tube. The technician located the crimp in the source tube and cut approximately a 1 1/2 inch piece of source tube out and freed up the drive cable and slowly cranked the source back in slowly. At 3:10 am, the source was back in the camera. The three licensee technicians involved in the retrieval received 181 mR, 60 mR, and 95 mR respectively by pocket dosimeter. The RSO stated that results for July film badge readings for the technicians will be available in early August. The RSO also stated that there was no damage to the camera or source, and that the guide tube has been replaced.