Event Notification Report for May 14, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/13/2013 - 05/14/2013
EVENT NUMBERS
4903749028490294903049031490324903349044
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State
Event Number: 49037
Rep Org: NV DIV OF RAD HEALTH
Licensee: ST. MARY'S REGIONAL MEDICAL CENTER
Region: 4
City: RENO State: NV
County:
License #: 16-12-0244-02
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: PETE SNYDER
Licensee: ST. MARY'S REGIONAL MEDICAL CENTER
Region: 4
City: RENO State: NV
County:
License #: 16-12-0244-02
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: PETE SNYDER
Notification Date: 05/15/2013
Notification Time: 16:54 [ET]
Event Date: 05/14/2013
Event Time: 09:45 [PDT]
Last Update Date: 05/16/2013
Notification Time: 16:54 [ET]
Event Date: 05/14/2013
Event Time: 09:45 [PDT]
Last Update Date: 05/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (EMAI)
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - WRONG DOSE ADMINISTERED TO PATIENT
The following information was obtained from the State of Nevada via email:
"The patient was to undergo a HIDA [hepatobiliary] scan for abdominal pain (Tc-99m; 5mCi, abdomen), but given syringe for MDP [bone scan] (Tc-99m; 30mCi; bone). A wrong dose of Tc-99m (600% the prescribed dose) was administered to the patient due to human error.
"Corrective action: Better training in cross-checking and confirming patient identity with prescribed dose information."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Item Number: NV130006
* * * RETRACTION FROM SNEHA RAVIKUMAR VIA E-MAIL ON 5/16/13 AT 1329 EDT * * *
"This is with regard to the wrong dose administration that was reported yesterday. [The State of Nevada] heard back from the RSO regarding the Effective Dose Equivalent:
"What should have been administered was 5 mCi of HIDA (Mebrofenin) = (3E-02) x 5 rem = 0.15 rem.
"What was administered was 30 mCi of MDP = (2E-02) x 30 rem = 0.60 rem.
"So, this would not be reportable."
Notified R4DO (Walker) and FSME Events Resource via E-mail.
The following information was obtained from the State of Nevada via email:
"The patient was to undergo a HIDA [hepatobiliary] scan for abdominal pain (Tc-99m; 5mCi, abdomen), but given syringe for MDP [bone scan] (Tc-99m; 30mCi; bone). A wrong dose of Tc-99m (600% the prescribed dose) was administered to the patient due to human error.
"Corrective action: Better training in cross-checking and confirming patient identity with prescribed dose information."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Item Number: NV130006
* * * RETRACTION FROM SNEHA RAVIKUMAR VIA E-MAIL ON 5/16/13 AT 1329 EDT * * *
"This is with regard to the wrong dose administration that was reported yesterday. [The State of Nevada] heard back from the RSO regarding the Effective Dose Equivalent:
"What should have been administered was 5 mCi of HIDA (Mebrofenin) = (3E-02) x 5 rem = 0.15 rem.
"What was administered was 30 mCi of MDP = (2E-02) x 30 rem = 0.60 rem.
"So, this would not be reportable."
Notified R4DO (Walker) and FSME Events Resource via E-mail.
Power Reactor
Event Number: 49028
Facility: MILLSTONE
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARK STROLLO
HQ OPS Officer: CHARLES TEAL
Region: 1 State: CT
Unit: [1] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MARK STROLLO
HQ OPS Officer: CHARLES TEAL
Notification Date: 05/14/2013
Notification Time: 09:31 [ET]
Event Date: 05/14/2013
Event Time: 09:07 [EDT]
Last Update Date: 05/14/2013
Notification Time: 09:31 [ET]
Event Date: 05/14/2013
Event Time: 09:07 [EDT]
Last Update Date: 05/14/2013
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):
DAN SCHROEDER (R1DO)
DAN SCHROEDER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Decommissioned | 0 | Decommissioned |
RADIATION MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE
The licensee is taking the spent fuel pool island radiation monitor out of service for pre-planned maintenance to change the air filter. The maintenance is expected to take approximately 5 minutes.
The licensee notified the NRC Resident Inspector, state and local authorities.
The licensee is taking the spent fuel pool island radiation monitor out of service for pre-planned maintenance to change the air filter. The maintenance is expected to take approximately 5 minutes.
The licensee notified the NRC Resident Inspector, state and local authorities.
Power Reactor
Event Number: 49029
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DANIEL COLEMAN
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DANIEL COLEMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 05/14/2013
Notification Time: 17:20 [ET]
Event Date: 05/14/2013
Event Time: 12:15 [EDT]
Last Update Date: 05/14/2013
Notification Time: 17:20 [ET]
Event Date: 05/14/2013
Event Time: 12:15 [EDT]
Last Update Date: 05/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAN SCHROEDER (R1DO)
DAN SCHROEDER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 3 | Startup | 3 | Startup |
HIGH STEAM FLOW ISOLATION CAPABILITY IDENTIFIED AS NON-FUNCTIONAL
"Emergency Cooling Loop 11 High Steam Flow Isolation capability not functional due to inadequate water level in differential pressure transmitter reference legs.
"Emergency Cooling Loop 11 High Steam Flow transmitter for channel 11 alarmed due to gross failure at 0840 hours [EDT] on May 14, 2013. At 1154 hours channel 12 Emergency Cooling Loop 11 High Steam Flow transmitter experienced a gross failure. With both transmitters failed, the isolation capability of Emergency Condenser Loop 11 on high steam flow is not available.
"At 1215 hours, a manual isolation of Emergency Cooling Loop 11 was initiated fulfilling the safety function.
"Subsequent troubleshooting has revealed that the reference legs of the differential pressure transmitters for high steam flow were not filled properly.
"This is an 8 hour notification per 10 CFR 50.72(b)(3)(v) for a condition could have prevented the mitigation of the consequences of an accident."
The licensee notified the NRC Resident Inspector and will notify the State of New York.
"Emergency Cooling Loop 11 High Steam Flow Isolation capability not functional due to inadequate water level in differential pressure transmitter reference legs.
"Emergency Cooling Loop 11 High Steam Flow transmitter for channel 11 alarmed due to gross failure at 0840 hours [EDT] on May 14, 2013. At 1154 hours channel 12 Emergency Cooling Loop 11 High Steam Flow transmitter experienced a gross failure. With both transmitters failed, the isolation capability of Emergency Condenser Loop 11 on high steam flow is not available.
"At 1215 hours, a manual isolation of Emergency Cooling Loop 11 was initiated fulfilling the safety function.
"Subsequent troubleshooting has revealed that the reference legs of the differential pressure transmitters for high steam flow were not filled properly.
"This is an 8 hour notification per 10 CFR 50.72(b)(3)(v) for a condition could have prevented the mitigation of the consequences of an accident."
The licensee notified the NRC Resident Inspector and will notify the State of New York.
Power Reactor
Event Number: 49030
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CHRIS ROBINSON
HQ OPS Officer: PETE SNYDER
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: CHRIS ROBINSON
HQ OPS Officer: PETE SNYDER
Notification Date: 05/14/2013
Notification Time: 18:22 [ET]
Event Date: 05/14/2013
Event Time: 10:44 [CDT]
Last Update Date: 05/14/2013
Notification Time: 18:22 [ET]
Event Date: 05/14/2013
Event Time: 10:44 [CDT]
Last Update Date: 05/14/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MICHAEL HAY (R4DO)
MICHAEL HAY (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 |
FAILED FITNESS-FOR-DUTY TEST
A licensed operator had a confirmed positive for alcohol during a for cause fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
A licensed operator had a confirmed positive for alcohol during a for cause fitness-for-duty test. The employee's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 49031
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: RICK GARCIA
HQ OPS Officer: PETE SNYDER
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: RICK GARCIA
HQ OPS Officer: PETE SNYDER
Notification Date: 05/14/2013
Notification Time: 18:37 [ET]
Event Date: 05/14/2013
Event Time: 15:02 [PDT]
Last Update Date: 05/31/2013
Notification Time: 18:37 [ET]
Event Date: 05/14/2013
Event Time: 15:02 [PDT]
Last Update Date: 05/31/2013
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):
MICHAEL HAY (R4DO)
MICHAEL HAY (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
PLANNED POWER OUTAGE AT TSC AND OSC
"During Refueling Outage 21, at 1502 PDT on 5/14/13, power to the Technical Support Center (TSC) and Operations Support Center (OSC) was removed as part of transferring the facility to temporary power during a bus outage impacting the normal facility power supply. The TSC and OSC will be unavailable for use for several hours until temporary power has been established.
"Established compensatory measures direct ERO members normally responding to either of the two impacted centers to respond to alternate locations. No other emergency response facilities are impacted by the bus outage.
"This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The resident inspector has been notified. A follow up notification will be made when temporary power has been established and the facility is available for use."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SANDRA CHRISTIANSON TO PETE SNYDER AT 1637 EDT ON 5/15/13 * * *
"This is a follow-up courtesy notification to EN# 49031. Temporary power has been established to the TSC and OSC, and both are available for emergency response. Normal power to TSC and OSC is expected to be restored on or about June 2, 2013 at 0600 PDT and will require a similar removal of power to the facility. A separate notification will be made when swapping off of temporary power."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Hay).
* * * UPDATE AT 1735 EDT ON 5/31/2013 FROM SANDRA CHRISTIANSON TO MARK ABRAMOVITZ * * *
"On 5/31/13, power to the Technical Support Center (TSC) and the Operations Support Center (OSC) was removed as part of transferring the facility from temporary power back to the normal facility power supply. The duration of the power outage will last approximately 90 minutes. The TSC and OSC are unavailable for use during this time for support of emergency response activities. Established compensatory measures direct Emergency Response Organization (ERO) members to respond to alternate locations. No other emergency response facilities are impacted. This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. A follow up notification will be made when normal power has been reestablished and the facility is available for use."
Notified the R4DO (Azua).
* * * UPDATE AT 2050 EDT ON 5/31/2013 FROM LISA WILLIAMS TO MARK ABRAMOVITZ * * *
"At 1700 hours [PDT] on 5/31/13, normal power has been reestablished to the TSC and OSC, and both are available for emergency response. The licensee has notified the NRC Resident Inspector."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Azua).
"During Refueling Outage 21, at 1502 PDT on 5/14/13, power to the Technical Support Center (TSC) and Operations Support Center (OSC) was removed as part of transferring the facility to temporary power during a bus outage impacting the normal facility power supply. The TSC and OSC will be unavailable for use for several hours until temporary power has been established.
"Established compensatory measures direct ERO members normally responding to either of the two impacted centers to respond to alternate locations. No other emergency response facilities are impacted by the bus outage.
"This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The resident inspector has been notified. A follow up notification will be made when temporary power has been established and the facility is available for use."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SANDRA CHRISTIANSON TO PETE SNYDER AT 1637 EDT ON 5/15/13 * * *
"This is a follow-up courtesy notification to EN# 49031. Temporary power has been established to the TSC and OSC, and both are available for emergency response. Normal power to TSC and OSC is expected to be restored on or about June 2, 2013 at 0600 PDT and will require a similar removal of power to the facility. A separate notification will be made when swapping off of temporary power."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Hay).
* * * UPDATE AT 1735 EDT ON 5/31/2013 FROM SANDRA CHRISTIANSON TO MARK ABRAMOVITZ * * *
"On 5/31/13, power to the Technical Support Center (TSC) and the Operations Support Center (OSC) was removed as part of transferring the facility from temporary power back to the normal facility power supply. The duration of the power outage will last approximately 90 minutes. The TSC and OSC are unavailable for use during this time for support of emergency response activities. Established compensatory measures direct Emergency Response Organization (ERO) members to respond to alternate locations. No other emergency response facilities are impacted. This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified. A follow up notification will be made when normal power has been reestablished and the facility is available for use."
Notified the R4DO (Azua).
* * * UPDATE AT 2050 EDT ON 5/31/2013 FROM LISA WILLIAMS TO MARK ABRAMOVITZ * * *
"At 1700 hours [PDT] on 5/31/13, normal power has been reestablished to the TSC and OSC, and both are available for emergency response. The licensee has notified the NRC Resident Inspector."
The licensee notified the NRC Resident Inspector.
Notified the R4DO (Azua).
Power Reactor
Event Number: 49032
Facility: CATAWBA
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WALTER HUNNICUTT
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WALTER HUNNICUTT
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/15/2013
Notification Time: 02:52 [ET]
Event Date: 05/14/2013
Event Time: 23:23 [EDT]
Last Update Date: 05/15/2013
Notification Time: 02:52 [ET]
Event Date: 05/14/2013
Event Time: 23:23 [EDT]
Last Update Date: 05/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JONATHAN BARTLEY (R2DO)
JONATHAN BARTLEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO LEAK FROM TURBINE BUILDING SUMP CONTAINING TRITIUM
"Sample exceeding the industry groundwater protection initiative related to radioactivity in groundwater for which a news release is planned and notification to other government agencies will be made."
"A leak greater than 100 gallons containing tritium has the potential to reach groundwater. The source has been identified. Actions to isolate this source are being initiated."
The licensee has identified a leak in a fiberglass discharge pipe from the turbine building sump. The licensee estimates that greater than 100 gallons of water has been discharged through the leak at the present time. The licensee is in the process of installing a temporary sump pump in the turbine building sump in order to isolate the discharge path. Samples indicate a tritium concentration of 8.964 E-6 uCi/mL.
The licensee will notify state and local government agencies. A press release is planned. The licensee will notify the NRC Resident Inspector.
"Sample exceeding the industry groundwater protection initiative related to radioactivity in groundwater for which a news release is planned and notification to other government agencies will be made."
"A leak greater than 100 gallons containing tritium has the potential to reach groundwater. The source has been identified. Actions to isolate this source are being initiated."
The licensee has identified a leak in a fiberglass discharge pipe from the turbine building sump. The licensee estimates that greater than 100 gallons of water has been discharged through the leak at the present time. The licensee is in the process of installing a temporary sump pump in the turbine building sump in order to isolate the discharge path. Samples indicate a tritium concentration of 8.964 E-6 uCi/mL.
The licensee will notify state and local government agencies. A press release is planned. The licensee will notify the NRC Resident Inspector.
Research Reactor
Event Number: 49033
Rep Org: TEXAS A&M UNIVERSITY
Licensee: TEXAS A&M UNIVERSITY
Region: 4
City: COLLEGE STATION State: TX
County: BRAZOS
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: ESTEBAN BOTELLO
HQ OPS Officer: HOWIE CROUCH
Licensee: TEXAS A&M UNIVERSITY
Region: 4
City: COLLEGE STATION State: TX
County: BRAZOS
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: ESTEBAN BOTELLO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/15/2013
Notification Time: 11:03 [ET]
Event Date: 05/14/2013
Event Time: 22:09 [CDT]
Last Update Date: 05/15/2013
Notification Time: 11:03 [ET]
Event Date: 05/14/2013
Event Time: 22:09 [CDT]
Last Update Date: 05/15/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MICHAEL HAY-email (R4DO)
DUANE HARDESTY (NRR)
JESSE QUICHOCHO (NRR)
MICHAEL HAY-email (R4DO)
DUANE HARDESTY (NRR)
JESSE QUICHOCHO (NRR)
RESEARCH REACTOR REPORTABLE EVENT - CONTROL ROD DRIVE MECHANISM JAM
"This preliminary event report is in compliance with Technical Specification 6.6.2 Special Reports confirming in writing the initial report made by telephone to the USNRC Operations Center.
"During reactor shutdown after normal steady state operation on May 14, 2013 at 2209 CDT, shim safety 1 jammed at 30% withdrawn (70% inserted). Operators lowered the remaining rods with no other issues and after determining the reactor was shut down at 2250 CDT, operators began investigating the cause of the jam. The shutdown margin in this configuration was determined to be $2.91 [negative reactivity] with shim safety 1 jammed at 30%. The Technical Specification requirement for shutdown margin is $0.25 [negative reactivity] which meant the reactor was well within acceptable limits for shutdown.
"The reactor was determined to be in a safe shutdown state. During inspection a rope that was attached to an experiment was found to be caught inside the Control Rod Drive Mechanism (CRDM) for shim safety 1 about 10 feet from the surface of the pool. This caused a jam in the drive mechanism not allowing the rod to go below 29% and above 32%.
"A fuel handling team was assembled at 0945 CDT on 5/15/13 in order to remove the control rod assembly for shim safety 1. The rope connecting the experiment to the CRDM was cut in order to allow proper removal of the CRDM. The CRDM was successfully removed and the piece of rope caught inside the drive was removed. After further inspection of the CRDM no other issues were found and it was reinstalled into its normal position.
"Operability and scram time tests were performed and completed satisfactory at 1130 CDT. The fuel handling team was disbanded at 1137 CDT and the reactor was determined to be operational. At no point during this event was there any danger to the general public or Nuclear Science Center personnel."
"This preliminary event report is in compliance with Technical Specification 6.6.2 Special Reports confirming in writing the initial report made by telephone to the USNRC Operations Center.
"During reactor shutdown after normal steady state operation on May 14, 2013 at 2209 CDT, shim safety 1 jammed at 30% withdrawn (70% inserted). Operators lowered the remaining rods with no other issues and after determining the reactor was shut down at 2250 CDT, operators began investigating the cause of the jam. The shutdown margin in this configuration was determined to be $2.91 [negative reactivity] with shim safety 1 jammed at 30%. The Technical Specification requirement for shutdown margin is $0.25 [negative reactivity] which meant the reactor was well within acceptable limits for shutdown.
"The reactor was determined to be in a safe shutdown state. During inspection a rope that was attached to an experiment was found to be caught inside the Control Rod Drive Mechanism (CRDM) for shim safety 1 about 10 feet from the surface of the pool. This caused a jam in the drive mechanism not allowing the rod to go below 29% and above 32%.
"A fuel handling team was assembled at 0945 CDT on 5/15/13 in order to remove the control rod assembly for shim safety 1. The rope connecting the experiment to the CRDM was cut in order to allow proper removal of the CRDM. The CRDM was successfully removed and the piece of rope caught inside the drive was removed. After further inspection of the CRDM no other issues were found and it was reinstalled into its normal position.
"Operability and scram time tests were performed and completed satisfactory at 1130 CDT. The fuel handling team was disbanded at 1137 CDT and the reactor was determined to be operational. At no point during this event was there any danger to the general public or Nuclear Science Center personnel."
Agreement State
Event Number: 49044
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MISTRAS GROUP INC
Region: 4
City: DEER PARK State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOHN SHOEMAKER
Licensee: MISTRAS GROUP INC
Region: 4
City: DEER PARK State: TX
County:
License #: 06369
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 05/16/2013
Notification Time: 16:47 [ET]
Event Date: 05/14/2013
Event Time: 00:00 [CDT]
Last Update Date: 05/16/2013
Notification Time: 16:47 [ET]
Event Date: 05/14/2013
Event Time: 00:00 [CDT]
Last Update Date: 05/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
WAYNE WALKER (R4DO)
FSME EVENTS RESOURCE (EMAI)
AGREEMENT STATE REPORT - UNABLE TO RETRACT SOURCE INTO RADIOGRAPHY CAMERA
The following information was obtained from the State of Texas via E-mail:
"On May 15, 2013, the licensee's Radiation Safety Officer (RSO) reported to the Agency [Texas Department of State Health Services] that on May 14, 2013, one of its radiography crews had been unable to retract the source back into the QSA Model 880 camera they were using. The radiography crew had dropped and damaged the crank assembly when it was moving the equipment between shots. The crew apparently failed to thoroughly check the crank assembly prior to the next shot. Following the next shot, the source could not be retracted. The RSO was notified and he and another licensee employee, with assistance from the radiographers, performed the source retrieval (the camera and equipment had to be lowered to the ground from 40 feet inside a tank where the radiography was being performed in order to retrieve the source). The RSO reported that the connector at the end of the cable, which connects the cable to the pigtail, had come off of the cable. [The connector] was apparently damaged in the crank assembly accident. Readings from the pocket dosimeters were: RSO received 240 mrem; other employee performing source retrieval received 40 mrem; and, the 3 [other] radiography crew members received 300 mrem, 110 mrem, and 80 mrem, respectively. No member of the public received any exposure from this event. Further information will be provided as it is obtained, per SA-300.
"Radiography Camera: QSA Model 880, SN: D11097, Source: SN: 93674B"
Texas Incident #: I-9079
The following information was obtained from the State of Texas via E-mail:
"On May 15, 2013, the licensee's Radiation Safety Officer (RSO) reported to the Agency [Texas Department of State Health Services] that on May 14, 2013, one of its radiography crews had been unable to retract the source back into the QSA Model 880 camera they were using. The radiography crew had dropped and damaged the crank assembly when it was moving the equipment between shots. The crew apparently failed to thoroughly check the crank assembly prior to the next shot. Following the next shot, the source could not be retracted. The RSO was notified and he and another licensee employee, with assistance from the radiographers, performed the source retrieval (the camera and equipment had to be lowered to the ground from 40 feet inside a tank where the radiography was being performed in order to retrieve the source). The RSO reported that the connector at the end of the cable, which connects the cable to the pigtail, had come off of the cable. [The connector] was apparently damaged in the crank assembly accident. Readings from the pocket dosimeters were: RSO received 240 mrem; other employee performing source retrieval received 40 mrem; and, the 3 [other] radiography crew members received 300 mrem, 110 mrem, and 80 mrem, respectively. No member of the public received any exposure from this event. Further information will be provided as it is obtained, per SA-300.
"Radiography Camera: QSA Model 880, SN: D11097, Source: SN: 93674B"
Texas Incident #: I-9079