| | Site | Start date | Title | Description |
|---|
| ENS 58100 | LaSalle | 28 December 2025 22:06:00 | Manual Reactor Scram Due to RCS Leak | The following information was provided by the licensee via phone and email:
At 1606 CST with Unit 1 in mode 1 at 93 percent power, the reactor was manually tripped due to degrading containment parameters associated with a leak from the 'B' reactor recirculation pump line, which has been isolated. The trip was not complex, however the 'A' reactor recirculation pump tripped to OFF instead of down-shifting to slow speed. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
Operations responded using emergency operations procedures and stabilized the unit in plant mode 3 (hot shutdown). Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 is not affected.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
| IR 05000416/2025003 | Grand Gulf | 22 December 2025 | And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000416/2025003 and 07200050/2025001 | |
| IR 05000259/2025003 | Browns Ferry | 18 December 2025 | Integrated Inspection Report 05000259/2025003, 05000260/2025003, 05000296/2025003 and 07200052/2024001 and Exercise of Enforcement - Revised | |
| IR 05000321/2025003 | Hatch
07200036 | 12 December 2025 | Integrated Inspection Report 05000321/2025003 and 05000366/2025003 Independent Spent Fuel Installation 07200036/2024001 Exercise of Enforcement Discretion | |
| 05000366/LER-2025-003, Manual Reactor Scram Due to Trip of Both Reactor Recirculation Pumps | Hatch | 11 November 2025 | Manual Reactor Scram Due to Trip of Both Reactor Recirculation Pumps | |
| ML25296A020 | Susquehanna | 9 October 2025 | Technical Requirements Manual | |
| ML25296A019 | Susquehanna | 9 October 2025 | Technical Requirements Manual | |
| 05000259/LER-2025-001, Reactor Scram Due to Low Reactor Water Level | Browns Ferry | 30 September 2025 | Reactor Scram Due to Low Reactor Water Level | |
| ENS 57928 | Hatch | 13 September 2025 21:04:00 | Manual Reactor Scram | The following information was provided by the licensee via phone and email:
On September 13, 2025, at 1704 EDT, with Unit 2 in mode 1 at 70 percent power performing main turbine testing, the Unit 2 reactor was manually tripped due to loss of both reactor recirculation pumps. Due to the power level at the time, closure of containment isolation valves (CIVs) in multiple systems occurred, as a result of reaching the actuation setpoint on reactor water level, as designed. The trip was not complex, with all safety systems responding normally post-trip. Operations responded and stabilized the plant. Normal reactor level and pressure control systems are controlling as expected. Decay heat is being removed by discharging steam to the main condenser using turbine bypass valves. Unit 1 is not affected.
The reactor protection system actuation while critical is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, the event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of CIVs.
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:
Main turbine control valve testing was in progress when the reactor recirculation pumps tripped. |
| ML25253A274 | | 12 September 2025 | TLR-RES/DE/REB-2025-018 Assessment of Condition Monitoring Methods and Technologies for Inservice Inspection and Testing of Nuclear Power Plant Components | |