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The following information was provided by … The following information was provided by the licensee via email:</br>At 0651 EDT on April 5, 2023, with Unit 1 in mode 1 at 85 percent power, the reactor was manually tripped due to loss of main feedwater pump 'C'. The trip was not complex, with all systems responding normally post-trip. Main feedwater pump 'B' had previously been removed from service in preparation for a planned shutdown as a part of refueling outage RF27.</br>Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system.</br>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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) resulting from valid actuation of the reactor protection and emergency feedwater systems. </br>There was no impact on the health and safety of the public or plant personnel.</br>The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:</br>The licensee continues to investigate the loss of main feedwater pump 'C'.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector. +
10:51:00, 5 April 2023 +
10:25:00, 5 April 2023 +
10:51:00, 5 April 2023 +
The following information was provided by … The following information was provided by the licensee via email:</br>At 0651 EDT on April 5, 2023, with Unit 1 in mode 1 at 85 percent power, the reactor was manually tripped due to loss of main feedwater pump 'C'. The trip was not complex, with all systems responding normally post-trip. Main feedwater pump 'B' had previously been removed from service in preparation for a planned shutdown as a part of refueling outage RF27.</br>Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system.</br>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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) resulting from valid actuation of the reactor protection and emergency feedwater systems. </br>There was no impact on the health and safety of the public or plant personnel.</br>The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:</br>The licensee continues to investigate the loss of main feedwater pump 'C'.</br>The licensee notified the NRC Resident Inspector.ensee notified the NRC Resident Inspector. +
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