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| Entered date | Event description | |
|---|---|---|
| ENS 56645 | 30 July 2023 18:20:00 | The following information was provided by the licensee via email: On July 30, 2023 at 1526 EDT, with unit 1 in mode 1 at 100 percent power, the reactor was manually tripped due to low main turbine electro-hydraulic control oil level. The trip was uncomplicated with all systems responding normally post-trip. Operations stabilized the plant in mode 3. Decay heat removal is being accomplished using the steam dumps in steam pressure mode to the main condenser. Emergency Feedwater actuated due to low-low steam generator level as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. |
| ENS 56565 | 8 June 2023 09:37:00 | The following information was provided by the licensee via email: On 05/06/2023, at 1552 (EDT) with Seabrook Unit 1 in Mode 3 at zero percent power, while performing digital rod position indication system surveillance testing, shutdown bank 'E' stopped withdrawing. In response, the reactor trip breakers were manually opened, initiating a valid actuation of the reactor protection system (RPS). Subsequently, at 2253 while continuing to perform digital rod position indication system surveillance testing, shutdown bank 'C 'stopped inserting. Reactor trip breakers were manually opened, initiating a valid actuation of the RPS. The RPS responded as designed during both events, and both actuations are being reported pursuant to 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. |
| ENS 56564 | 8 June 2023 09:37:00 | The following information was provided by the licensee via email: On April 12, 2023, with Seabrook Station Unit 1 in Mode 6 at zero percent power, a valid actuation of the 'B' emergency diesel generator (EDG) emergency power sequencer occurred due to a loss of power to the 'B' train emergency bus. The 'B' EDG was removed from service for scheduled maintenance during this time. This event is being reported pursuant to 10 CFR 50.72(b)(3)(iv)(A) for a valid actuation of the 'B' EDG emergency power sequencer. The NRC Resident Inspector has been notified. |