Event Notification Report for October 07, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/06/2022 - 10/07/2022
Agreement State
Event Number: 56154
Rep Org: Virginia Rad Materials Program
Licensee: Quinn Consulting Services, Incorporated
Region: 1
City: Chantilly State: VA
County:
License #: 600-496-1
Agreement: Y
Docket:
NRC Notified By: Asfaw Fenta
HQ OPS Officer: Lloyd Desotell
Licensee: Quinn Consulting Services, Incorporated
Region: 1
City: Chantilly State: VA
County:
License #: 600-496-1
Agreement: Y
Docket:
NRC Notified By: Asfaw Fenta
HQ OPS Officer: Lloyd Desotell
Notification Date: 10/07/2022
Notification Time: 16:48 [ET]
Event Date: 10/07/2022
Event Time: 11:30 [EDT]
Last Update Date: 10/07/2022
Notification Time: 16:48 [ET]
Event Date: 10/07/2022
Event Time: 11:30 [EDT]
Last Update Date: 10/07/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGE TO PORTABLE DENSITY GAUGE
The following information was provided by the Virginia Department of Health via email:
"On October 7, 2022 at 1500 EDT, the Virginia Radioactive Materials Program (VRMP) received a report from a licensee's Radiation Safety Officer (RSO) via telephone that a portable nuclear moisture/density gauge was damaged by a dump truck at a jobsite located near the intersection of I-66 and I-28 in Chantilly, VA. The incident occurred on October 7, at about 1130 EDT. The report indicated that a Troxler density gauge (Model 3440, Serial # 77069, containing 8.0 millicuries of Cesium-137 and 40.0 millicuries of Am-241) was being used at the road construction site when a dump truck drove into and hit the gauge. During the incident, the gauge housing (the plastic cover and electronic system) was damaged, but the source appeared to remain intact within the housing. The site was cordoned off with a 15 foot radius. The licensee's survey of the gauge yielded readings of background at 15 feet and 0.5 mR/hr at about 3 feet from the gauge. The gauge was taken to the licensee's storage facility located at the project site. The RSO mentioned that wipe samples taken for leakage will be sent for analysis. The VRMP is working with the licensee to obtain additional information. This report will be updated once the licensee's investigation is complete, and the information is received. According to the RSO, no public exposure occurred."
Virginia Event Report ID No.: VA220003
The following information was provided by the Virginia Department of Health via email:
"On October 7, 2022 at 1500 EDT, the Virginia Radioactive Materials Program (VRMP) received a report from a licensee's Radiation Safety Officer (RSO) via telephone that a portable nuclear moisture/density gauge was damaged by a dump truck at a jobsite located near the intersection of I-66 and I-28 in Chantilly, VA. The incident occurred on October 7, at about 1130 EDT. The report indicated that a Troxler density gauge (Model 3440, Serial # 77069, containing 8.0 millicuries of Cesium-137 and 40.0 millicuries of Am-241) was being used at the road construction site when a dump truck drove into and hit the gauge. During the incident, the gauge housing (the plastic cover and electronic system) was damaged, but the source appeared to remain intact within the housing. The site was cordoned off with a 15 foot radius. The licensee's survey of the gauge yielded readings of background at 15 feet and 0.5 mR/hr at about 3 feet from the gauge. The gauge was taken to the licensee's storage facility located at the project site. The RSO mentioned that wipe samples taken for leakage will be sent for analysis. The VRMP is working with the licensee to obtain additional information. This report will be updated once the licensee's investigation is complete, and the information is received. According to the RSO, no public exposure occurred."
Virginia Event Report ID No.: VA220003
Power Reactor
Event Number: 56152
Facility: Cooper
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Scott Johnson
HQ OPS Officer: Ernest West
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Scott Johnson
HQ OPS Officer: Ernest West
Notification Date: 10/07/2022
Notification Time: 05:41 [ET]
Event Date: 10/07/2022
Event Time: 00:50 [CDT]
Last Update Date: 11/04/2022
Notification Time: 05:41 [ET]
Event Date: 10/07/2022
Event Time: 00:50 [CDT]
Last Update Date: 11/04/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
Person (Organization):
Dixon, John (R4DO)
Crouch, Howard (IR)
Miller, Chris (NRR EO)
Dixon, John (R4DO)
Crouch, Howard (IR)
Miller, Chris (NRR EO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
EN Revision Imported Date: 11/4/2022
EN Revision Text: POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO HOSPITAL
The following information was provided by the licensee via fax:
"On 10/7/2022 at 0050 CDT, a potentially contaminated individual was transported off-site via ambulance to a local hospital. Due to the nature of the medical condition, an initial on-site survey for radioactive contamination was not performed prior to transport. Prior to arrival at the hospital, it was confirmed the individual and [the individual's] clothing were not radiologically contaminated. Follow-up surveys performed by radiation technicians identified no radiological contamination of the ambulance and response personnel. This event is being reported per 50.72(b)(3)(xii) - 'Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.' The NRC Resident Inspector has been notified."
EN Revision Text: POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO HOSPITAL
The following information was provided by the licensee via fax:
"On 10/7/2022 at 0050 CDT, a potentially contaminated individual was transported off-site via ambulance to a local hospital. Due to the nature of the medical condition, an initial on-site survey for radioactive contamination was not performed prior to transport. Prior to arrival at the hospital, it was confirmed the individual and [the individual's] clothing were not radiologically contaminated. Follow-up surveys performed by radiation technicians identified no radiological contamination of the ambulance and response personnel. This event is being reported per 50.72(b)(3)(xii) - 'Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.' The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 56153
Facility: Braidwood
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Vincent Roddy
HQ OPS Officer: Ian Howard
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Vincent Roddy
HQ OPS Officer: Ian Howard
Notification Date: 10/07/2022
Notification Time: 08:35 [ET]
Event Date: 10/07/2022
Event Time: 01:19 [CDT]
Last Update Date: 12/13/2022
Notification Time: 08:35 [ET]
Event Date: 10/07/2022
Event Time: 01:19 [CDT]
Last Update Date: 12/13/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Betancourt-Roldan, Diana (R3DO)
Betancourt-Roldan, Diana (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
EN Revision Imported Date: 12/14/2022
EN Revision Text: CONTROL ROD DRIVE MECHANISM (CRDM) PENETRATION DEGRADED
The following information was provided by the licensee via fax:
"Control Rod Drive Mechanism (CRDM) penetration 69 degraded.
"At 0119 [CDT] on October 7, 2022, it was determined that the CRDM penetration 69 was degraded because examination identified unacceptable indications in accordance with ASME Code Case N-729-6. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
* * * UPDATE ON 12/13/22 AT 1825 EST FROM KRYSTIAN JARONCZYK TO ADAM KOZIOL * * *
"The notification is being corrected to state:
"At 0119 [CDT] on October 7, 2022, it was determined that the Control Rod Drive Mechanism (CRDM) penetration 69 was degraded because liquid penetrant testing, performed on the seal weld, identified unacceptable indications in accordance with ASME Section III and NRC approved licensee relief request for a previously performed embedded flaw repair. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel."
Notified R3DO (Ruiz).
EN Revision Text: CONTROL ROD DRIVE MECHANISM (CRDM) PENETRATION DEGRADED
The following information was provided by the licensee via fax:
"Control Rod Drive Mechanism (CRDM) penetration 69 degraded.
"At 0119 [CDT] on October 7, 2022, it was determined that the CRDM penetration 69 was degraded because examination identified unacceptable indications in accordance with ASME Code Case N-729-6. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
* * * UPDATE ON 12/13/22 AT 1825 EST FROM KRYSTIAN JARONCZYK TO ADAM KOZIOL * * *
"The notification is being corrected to state:
"At 0119 [CDT] on October 7, 2022, it was determined that the Control Rod Drive Mechanism (CRDM) penetration 69 was degraded because liquid penetrant testing, performed on the seal weld, identified unacceptable indications in accordance with ASME Section III and NRC approved licensee relief request for a previously performed embedded flaw repair. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel."
Notified R3DO (Ruiz).
Agreement State
Event Number: 56233
Rep Org: Arkansas Department of Health
Licensee: GTS, Inc.
Region: 4
City: Little Rock State: AR
County:
License #: ARK-0995-03121
Agreement: Y
Docket:
NRC Notified By: Susan Elliot
HQ OPS Officer: Ernest West
Licensee: GTS, Inc.
Region: 4
City: Little Rock State: AR
County:
License #: ARK-0995-03121
Agreement: Y
Docket:
NRC Notified By: Susan Elliot
HQ OPS Officer: Ernest West
Notification Date: 11/18/2022
Notification Time: 16:31 [ET]
Event Date: 10/07/2022
Event Time: 09:15 [CST]
Last Update Date: 11/18/2022
Notification Time: 16:31 [ET]
Event Date: 10/07/2022
Event Time: 09:15 [CST]
Last Update Date: 11/18/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The following information was provided by the The Arkansas Department of Health (The Department) via email:
"The Department received notification on October 7, 2022, from licensee GTS, Inc., that a Troxler gauge model 3430 had been rolled over by a bulldozer while performing routine measurements at a construction site. As a result of the incident, the source was pulled from its testing position and exposed.
"The technician created a thirty (30) foot containment barrier and notified his company's Radiation Safety Officer (RSO). The RSO mobilized to the event location and contacted the Department.
"The Department's inspectors visited the licensee on October 7, 2022, to investigate the event. Surveys at the exterior of the transport container were determined to be 3 to 5 mR per hour. Surveys performed inside of the transport container were measured to be a maximum of 27 mR per hour at a location close to the surface of the shielded source.
"The RSO returned the handle to the 'safe position' and both radiation sources were placed in the transport box. The gauge was transported back to the designated radiation storage area located at the GTS Little Rock Office in Alexander, Arkansas. The gauge was swabbed for a leak test and then sealed in its transport case and secured in the storage area. Sand and additional temporary screening were installed surrounding the area. GTS then contacted Instrotek Companies for disposal options. On November 9, 2022, the gauge was shipped back to the manufacturer. The licensee performed leak tests of the sources, surveys of the gauge transport container, and surveys of the storage location.
"The Occupational Radiation Exposure Report from October 1, 2022, through December 31, 2022, shows 0 mrem for the RSO and technicians. Leak test certificates showed no leakage.
"Upon review of the licensee's 30 day report, received November 16, 2022, it was noted that the dosimetry badge worn by the RSO during the retraction and transportation of the source showed no measurable dose.
"The report contained leak test results for the sources both on the day of the event, October 7, 2022, and after the event on November 1, 2022. The results for the leak tests in both instances were measured to be below 185 becquerel (0.005 microcuries).
"On October 10, 2022, the company conducted a thorough review of the incident and a safety session was held with the gauge operator involved in the incident prior to the operator returning to field work using a nuclear density gauge. The session included collaborative thinking and planning in performing nuclear density testing safety on unique job sites, especially those with confined work environments.
"Additional topics discussed included utilizing verbal communication with equipment operators prior to accessing a work area, utilizing a 'spotter' while performing testing, and always maintaining possession and visual observation of a nuclear density gauge while the gauge is not inside the transport case in the vehicle.
"The Department considers this event to be closed."
Arkansas Event Number: AR-2022-008
The following information was provided by the The Arkansas Department of Health (The Department) via email:
"The Department received notification on October 7, 2022, from licensee GTS, Inc., that a Troxler gauge model 3430 had been rolled over by a bulldozer while performing routine measurements at a construction site. As a result of the incident, the source was pulled from its testing position and exposed.
"The technician created a thirty (30) foot containment barrier and notified his company's Radiation Safety Officer (RSO). The RSO mobilized to the event location and contacted the Department.
"The Department's inspectors visited the licensee on October 7, 2022, to investigate the event. Surveys at the exterior of the transport container were determined to be 3 to 5 mR per hour. Surveys performed inside of the transport container were measured to be a maximum of 27 mR per hour at a location close to the surface of the shielded source.
"The RSO returned the handle to the 'safe position' and both radiation sources were placed in the transport box. The gauge was transported back to the designated radiation storage area located at the GTS Little Rock Office in Alexander, Arkansas. The gauge was swabbed for a leak test and then sealed in its transport case and secured in the storage area. Sand and additional temporary screening were installed surrounding the area. GTS then contacted Instrotek Companies for disposal options. On November 9, 2022, the gauge was shipped back to the manufacturer. The licensee performed leak tests of the sources, surveys of the gauge transport container, and surveys of the storage location.
"The Occupational Radiation Exposure Report from October 1, 2022, through December 31, 2022, shows 0 mrem for the RSO and technicians. Leak test certificates showed no leakage.
"Upon review of the licensee's 30 day report, received November 16, 2022, it was noted that the dosimetry badge worn by the RSO during the retraction and transportation of the source showed no measurable dose.
"The report contained leak test results for the sources both on the day of the event, October 7, 2022, and after the event on November 1, 2022. The results for the leak tests in both instances were measured to be below 185 becquerel (0.005 microcuries).
"On October 10, 2022, the company conducted a thorough review of the incident and a safety session was held with the gauge operator involved in the incident prior to the operator returning to field work using a nuclear density gauge. The session included collaborative thinking and planning in performing nuclear density testing safety on unique job sites, especially those with confined work environments.
"Additional topics discussed included utilizing verbal communication with equipment operators prior to accessing a work area, utilizing a 'spotter' while performing testing, and always maintaining possession and visual observation of a nuclear density gauge while the gauge is not inside the transport case in the vehicle.
"The Department considers this event to be closed."
Arkansas Event Number: AR-2022-008