Event Notification Report for February 18, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/17/2024 - 02/18/2024
Power Reactor
Event Number: 56975
Facility: Hatch
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Kenny Hunter
HQ OPS Officer: Thomas Herrity
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Kenny Hunter
HQ OPS Officer: Thomas Herrity
Notification Date: 02/18/2024
Notification Time: 16:02 [ET]
Event Date: 02/18/2024
Event Time: 11:33 [EST]
Last Update Date: 02/18/2024
Notification Time: 16:02 [ET]
Event Date: 02/18/2024
Event Time: 11:33 [EST]
Last Update Date: 02/18/2024
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Miller, Mark (R2DO)
FFD Group, (EMAIL)
Miller, Mark (R2DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
The following is a synopsis of information was provided by the licensee via email and phone call:
A non-licensed supervisor had a confirmed positive during a random fitness for duty test. The supervisor's access to the plant has been terminated.
The following is a synopsis of information was provided by the licensee via email and phone call:
A non-licensed supervisor had a confirmed positive during a random fitness for duty test. The supervisor's access to the plant has been terminated.
Power Reactor
Event Number: 56977
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Shawn Colameco
HQ OPS Officer: Ernest West
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Shawn Colameco
HQ OPS Officer: Ernest West
Notification Date: 02/19/2024
Notification Time: 03:34 [ET]
Event Date: 02/18/2024
Event Time: 23:25 [EST]
Last Update Date: 02/19/2024
Notification Time: 03:34 [ET]
Event Date: 02/18/2024
Event Time: 23:25 [EST]
Last Update Date: 02/19/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
AUTOMATIC START OF EMERGENCY DIESEL GENERATOR
The following information was provided by the licensee via phone and email:
"At approximately 2325 EST on February 18, 2024, with Unit 1 in Mode 5 at 0 percent power and Unit 2 in Mode 1 at 100 percent power, emergency diesel generator 2 automatically started due to the unexpected loss of AC power to emergency bus E2 during a planned transfer of E2 DC control power from normal to alternate for the 1B-1 battery. In addition, the unexpected loss of AC power to E2 resulted in Unit 1 primary containment isolation system (PCIS) partial Group 2 (i.e., drywell equipment and floor drain, residual heat removal (RHR), discharge to radioactive waste, and RHR process sample), Group 6 (i.e., containment atmosphere control/dilution, containment atmosphere monitoring, and post accident sampling systems), and partial Group 10 (i.e., air isolation to the drywell) isolations.
"Emergency diesel generator 2 automatically started and re-energized the E2 bus as designed when the loss of E2 signal was received. The PCIS actuations were as expected for the outage plant line up on Unit 1 at the time. The cause of the loss of electrical power to emergency bus E2 is under investigation at this time.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of emergency diesel generator 2 and PCIS.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This event will be entered into the plant's corrective action program.
The following information was provided by the licensee via phone and email:
"At approximately 2325 EST on February 18, 2024, with Unit 1 in Mode 5 at 0 percent power and Unit 2 in Mode 1 at 100 percent power, emergency diesel generator 2 automatically started due to the unexpected loss of AC power to emergency bus E2 during a planned transfer of E2 DC control power from normal to alternate for the 1B-1 battery. In addition, the unexpected loss of AC power to E2 resulted in Unit 1 primary containment isolation system (PCIS) partial Group 2 (i.e., drywell equipment and floor drain, residual heat removal (RHR), discharge to radioactive waste, and RHR process sample), Group 6 (i.e., containment atmosphere control/dilution, containment atmosphere monitoring, and post accident sampling systems), and partial Group 10 (i.e., air isolation to the drywell) isolations.
"Emergency diesel generator 2 automatically started and re-energized the E2 bus as designed when the loss of E2 signal was received. The PCIS actuations were as expected for the outage plant line up on Unit 1 at the time. The cause of the loss of electrical power to emergency bus E2 is under investigation at this time.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of emergency diesel generator 2 and PCIS.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This event will be entered into the plant's corrective action program.