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| Entered date | Event description | |
|---|---|---|
| ENS 57214 | 8 July 2024 18:24:00 | The following information was provided by the licensee via phone and email: At 1521 EDT on July 8, 2024, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The (reactor) trip was not complex with all systems responding normally post trip. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the steam dump system and the auxiliary feedwater (AFW) system. Unit 2 is not affected. 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). The expected actuation of the AFW system (an engineered safety feature) is being reported as an eight-hour report under 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. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The specific cause of the turbine trip is under investigation by the licensee. |
| ENS 57126 | 13 May 2024 16:40:00 | The following information was provided by the licensee via phone and email: At 0917 EDT on May 13, 2024, a control room operator erroneously rendered the `B train of the Unit 2 residual heat removal (RHR) system inoperable. This occurred while the `A train of the Unit 2 RHR system was out of service for preplanned maintenance. RHR serves as the low head safety injection (LHSI) subsystem for the emergency core cooling system (ECCS) and because of this, Unit 2 was without a required train of ECCS from 0917 EDT to 0921 EDT. No other equipment issues were identified. The LHSI subsystem is credited by the analysis for a large break loss of coolant accident at full power. This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D). The NRC resident inspector has been notified. There is no release of radioactive material associated with this event. |
| ENS 56593 | 27 June 2023 19:04:00 | The following information was provided by the licensee via phone and email: At 1626 EDT, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The (reactor) trip was not complex with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed using the auxiliary feedwater and steam dump systems. Unit 1 is not affected. 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). The expected actuation of the auxiliary feedwater system (an engineered safety feature) is being reported as an eight hour report under 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. All control rods are fully inserted. The cause of the turbine trip is being investigated. |