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Event Notification Report for February 28, 2022

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/25/2022 - 02/28/2022

EVENT NUMBERS
55756 55757 55758
Power Reactor
Event Number: 55756
Facility: Brunswick
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Richard Barrett
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 02/24/2022
Notification Time: 14:35 [ET]
Event Date: 01/04/2022
Event Time: 13:16 [EST]
Last Update Date: 02/24/2022
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Miller, Mark (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
EN Revision Imported Date: 2/28/2022

EN Revision Text: 60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR 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 1316 Eastern Standard Time [EST] on January 4, 2022, during performance of isolation logic periodic testing associated with Primary Containment Isolation System Groups 2 and 6, an invalid actuation of Group 6 Primary Containment Isolation Valves (PCIVs) (i.e., Containment Atmospheric Control/Monitoring (CAC/CAM) and Post Accident Sampling (PASS) isolation valves) occurred. This resulted in a Division I CAC isolation signal, a full CAM isolation, and a full PASS isolation. Reactor Building Ventilation isolated and Standby Gas Treatment started per design. No manipulations associated with the isolation or reset logic were ongoing at the time.

"Troubleshooting determined that the Group 6 isolation signal resulted from a high resistance contact on a relay associated with the main stack radiation high-high isolation logic. This condition interrupted electrical continuity and prevented the Group 6 logic from resetting. Following cleaning of the relay contacts, the isolation logic remained in the reset state.

"The main stack radiation monitor is a shared component that sends isolation signals to Unit 1 and Unit 2. It was verified that the radiation monitor was not in trip electrically and there were no Unit 2 actuations. Therefore, 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. As a result, this event has been determined to be an invalid actuation.

"This event did not result in any adverse impact to the health and safety of the public."

The NRC Resident Inspector was notified.


Power Reactor
Event Number: 55757
Facility: Turkey Point
Region: 2     State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Humberto Benitez
HQ OPS Officer: Ossy Font
Notification Date: 02/25/2022
Notification Time: 14:53 [ET]
Event Date: 02/24/2022
Event Time: 16:50 [EST]
Last Update Date: 02/25/2022
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Miller, Mark (R2)
FFD Group, (EMAIL)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
Event Text
FITNESS FOR DUTY

The following information was provided by the licensee via telephone:

A non-licensee contractor supervisor had a confirmed positive for a controlled substance during a fitness for duty test. The employee's access to the plant has been terminated.

The NRC Resident Inspector has been notified.


Power Reactor
Event Number: 55758
Facility: McGuire
Region: 2     State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Justin Black
HQ OPS Officer: Ossy Font
Notification Date: 02/25/2022
Notification Time: 16:10 [ET]
Event Date: 02/25/2022
Event Time: 11:33 [EST]
Last Update Date: 02/25/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xiii) - Loss Comm/Asmt/Response
Person (Organization):
Miller, Mark (R2)
Power Reactor Unit Info
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
Event Text
LOSS OF TECHNICAL SUPPORT CENTER (TSC)

The following information was provided by the licensee:

"On 2/25/22, at 1133 EDT, the Technical Support Center (TSC) high temperature alarm annunciated in the Control Room due to an equipment malfunction that resulted in an unplanned loss of the TSC for greater than seventy-five minutes.

"If an emergency had been declared requiring TSC activation during this period, the TSC would have been staffed and activated using existing emergency planning procedures. If relocation of the TSC had been necessary, the Emergency Coordinator would have relocated the TSC staff to an alternate location in accordance with applicable site procedures.

"This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the equipment malfunction affected the functionality of an emergency response facility.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."