Event Notification Report for February 22, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/21/2025 - 02/22/2025
EVENT NUMBERS
57567
57567
Power Reactor
Event Number: 57567
Facility: Hatch
Region: 2 State: GA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: John Campbell
HQ OPS Officer: Karen Cotton-Gross
Region: 2 State: GA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: John Campbell
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 02/22/2025
Notification Time: 13:15 [ET]
Event Date: 02/22/2025
Event Time: 11:11 [EST]
Last Update Date: 02/22/2025
Notification Time: 13:15 [ET]
Event Date: 02/22/2025
Event Time: 11:11 [EST]
Last Update Date: 02/22/2025
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):
Penmetsa, Ravi (R2DO)
Penmetsa, Ravi (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
PRIMARY CONTAINMENT DEGRADED
The following information was provided by the licensee via phone and email:
"At 1111 EST on 02/22/2025, while in mode 5 at 0 percent power, it was determined during local leak rate testing (LLRT) that the Unit 2 primary containment leakage rate exceeded the allowable limit (La) as defined in 10 CFR 50, Appendix J, `Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors' due to both primary containment isolation valves in a penetration failing LLRT requirements. 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."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The valves that failed the LLRT are located in the torus purge line. The licensee's corrective action is to remove and repair the valves.
The following information was provided by the licensee via phone and email:
"At 1111 EST on 02/22/2025, while in mode 5 at 0 percent power, it was determined during local leak rate testing (LLRT) that the Unit 2 primary containment leakage rate exceeded the allowable limit (La) as defined in 10 CFR 50, Appendix J, `Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors' due to both primary containment isolation valves in a penetration failing LLRT requirements. 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."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The valves that failed the LLRT are located in the torus purge line. The licensee's corrective action is to remove and repair the valves.