| ENS 58163 | Columbia | 12 February 2026 10:49:00 | Manual Reactor Trip Due to a Loss of Both Reactor Recirculation Pumps | The following information was provided by the licensee via phone and email:
At 0249 PST, on February 12, 2026, with the unit in Mode 1 at 100 percent power, the reactor was manually tripped due to a loss of both reactor recirculation pumps because of abnormal pump drive parameters. Following reset of the reactor trip signal, operators observed erratic automatic operation of the reactor feed pumps with an associated reactor water level transient to less than plus 13 inches resulting in an additional reactor trip signal. Operators took manual control of the reactor feed pumps and recovered reactor water level, stabilizing water level at above plus 13 inches. The reactor trip signal was reset, and reactor water level was raised to support natural circulation flow of the reactor.
Decay heat is being removed via natural circulation in the reactor with steam to the main condenser.
Due to the valid reactor protection system actuations, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B), and eight-hour, non-emergency notification, per 10 CFR 50.72(b)(3)(iv)(A).
There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified. |
| 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. |