Event Notification Report for November 09, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/08/2022 - 11/09/2022
Power Reactor
Event Number: 56214
Facility: Waterford
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Jeff Bradley
HQ OPS Officer: Brian Lin
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Jeff Bradley
HQ OPS Officer: Brian Lin
Notification Date: 11/09/2022
Notification Time: 15:37 [ET]
Event Date: 11/09/2022
Event Time: 08:46 [CST]
Last Update Date: 11/09/2022
Notification Time: 15:37 [ET]
Event Date: 11/09/2022
Event Time: 08:46 [CST]
Last Update Date: 11/09/2022
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Azua, Ray (R4DO)
FFD Group, (EMAIL)
Azua, Ray (R4DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY REPORT
A non-licensed supervisor had a confirmed positive during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The NRC Resident Inspector has been notified.
A non-licensed supervisor had a confirmed positive during a random fitness-for-duty test. The employee's access to the plant has been terminated.
The NRC Resident Inspector has been notified.
Agreement State
Event Number: 56230
Rep Org: Colorado Dept of Health
Licensee: Bimbo Bakeries USA
Region: 4
City: Commerce City State: CO
County:
License #: General License
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Karen Cotton-Gross
Licensee: Bimbo Bakeries USA
Region: 4
City: Commerce City State: CO
County:
License #: General License
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/17/2022
Notification Time: 18:28 [ET]
Event Date: 11/09/2022
Event Time: 00:00 [MST]
Last Update Date: 11/17/2022
Notification Time: 18:28 [ET]
Event Date: 11/09/2022
Event Time: 00:00 [MST]
Last Update Date: 11/17/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
AGREEMENT STATE REPORT - LOST EXIT SIGNS
The following summary was received from the Colorado Department of Public Health and Environment via email:
The Colorado Department of Public Health and Environment reported two exit signs (Manufacturer: Isolite Corp, Models 2000 and SLX60), containing 16.2 curies of tritium total, lost by the licensee. The incident occurred November 9, 2022.
Event Report ID No.: CO220038
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following summary was received from the Colorado Department of Public Health and Environment via email:
The Colorado Department of Public Health and Environment reported two exit signs (Manufacturer: Isolite Corp, Models 2000 and SLX60), containing 16.2 curies of tritium total, lost by the licensee. The incident occurred November 9, 2022.
Event Report ID No.: CO220038
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 56287
Facility: Brunswick
Region: 2 State: NC
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Sabrina Salazar
HQ OPS Officer: Brian P. Smith
Region: 2 State: NC
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Sabrina Salazar
HQ OPS Officer: Brian P. Smith
Notification Date: 12/28/2022
Notification Time: 09:18 [ET]
Event Date: 11/09/2022
Event Time: 09:06 [EST]
Last Update Date: 12/28/2022
Notification Time: 09:18 [ET]
Event Date: 11/09/2022
Event Time: 09:06 [EST]
Last Update Date: 12/28/2022
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):
Miller, Mark (R2DO)
Miller, Mark (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 |
INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES
The following information was provided by the licensee via email:
"This 60-day optional telephone notification is being made in lieu of an LER [Licensee Event Report] submittal as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).
"At approximately 0906 Eastern Time (EST) on November 9, 2022, an invalid actuation of Group 6 Primary Containment Isolation Valves (PCIVs) (i.e., Containment Atmospheric Control/Monitoring and Post Accident Sampling isolation valves) occurred. In addition, per design, Reactor Building Ventilation isolated and Standby Gas Treatment started. It was determined that this condition was caused by faulty test equipment that was being used during preparation for the Main Stack Radiation Monitor High Radiation Response Time test. This test requires connecting a recording device to monitor for the test start signal on a Unit 2 relay associated with the Main Stack High Radiation signal. The recorder faulted which caused the associated fuse to blow and resulted in Unit 2 receiving a Main Stack High Radiation signal and Group 6 PCIV actuation. It was verified that the radiation monitor was not in trip electrically (i.e., there was no high radiation condition).
"The actuation was not initiated in response to actual plant conditions, it was not an intentional manual initiation, and there were no parameters satisfying the requirements for initiation of the system. Therefore, this event has been determined to be an invalid actuation.
"During this event the PCIVs functioned successfully, and the actuations were complete. This event did not result in any adverse impact to the health and safety of the public."
The NRC Resident Inspector was notified.
The following information was provided by the licensee via email:
"This 60-day optional telephone notification is being made in lieu of an LER [Licensee Event Report] submittal as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).
"At approximately 0906 Eastern Time (EST) on November 9, 2022, an invalid actuation of Group 6 Primary Containment Isolation Valves (PCIVs) (i.e., Containment Atmospheric Control/Monitoring and Post Accident Sampling isolation valves) occurred. In addition, per design, Reactor Building Ventilation isolated and Standby Gas Treatment started. It was determined that this condition was caused by faulty test equipment that was being used during preparation for the Main Stack Radiation Monitor High Radiation Response Time test. This test requires connecting a recording device to monitor for the test start signal on a Unit 2 relay associated with the Main Stack High Radiation signal. The recorder faulted which caused the associated fuse to blow and resulted in Unit 2 receiving a Main Stack High Radiation signal and Group 6 PCIV actuation. It was verified that the radiation monitor was not in trip electrically (i.e., there was no high radiation condition).
"The actuation was not initiated in response to actual plant conditions, it was not an intentional manual initiation, and there were no parameters satisfying the requirements for initiation of the system. Therefore, this event has been determined to be an invalid actuation.
"During this event the PCIVs functioned successfully, and the actuations were complete. This event did not result in any adverse impact to the health and safety of the public."
The NRC Resident Inspector was notified.