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The following information was provided by … The following information was provided by the licensee via phone and email:</br>On 8/1/2025, at 2350 CDT, Browns Ferry Unit 1 experienced an automatic scram due to low reactor water level. A low reactor water level of `+2' inches resulted in a valid actuation of the reactor protection system which caused all of the rods to insert. During the scram response, there was a valid actuation of the primary containment isolations systems groups 2, 3, 6 and 8. Upon receipt of these signals, all components actuated as required. Following the scram, reactor water level lowered below the '-45' inches setpoint, actuating high pressure coolant injection and reactor core isolation coolant and tripped both reactor recirculation pumps as required. Operations responded and stabilized the plant. Reactor water level is being maintained via the condensate system. Decay heat is being removed by bypass valves to the main condenser. There was no impact on Units 2 and 3. </br>This event requires a 4-hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.</br>This event requires a 4-hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(A), any event that results or should have resulted in emergency core cooling system (ECCS) discharge into the reactor coolant system as a result of a valid signal except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.</br>This event requires an 8-hour non-emergency report per 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B): 1) Reactor protection system including: reactor scram or reactor trip. 2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). </br>All safety systems operated as expected. At no time were public health and safety at risk. The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.
04:50:00, 2 August 2025 +
04:29:00, 2 August 2025 +
04:50:00, 2 August 2025 +
The following information was provided by … The following information was provided by the licensee via phone and email:</br>On 8/1/2025, at 2350 CDT, Browns Ferry Unit 1 experienced an automatic scram due to low reactor water level. A low reactor water level of `+2' inches resulted in a valid actuation of the reactor protection system which caused all of the rods to insert. During the scram response, there was a valid actuation of the primary containment isolations systems groups 2, 3, 6 and 8. Upon receipt of these signals, all components actuated as required. Following the scram, reactor water level lowered below the '-45' inches setpoint, actuating high pressure coolant injection and reactor core isolation coolant and tripped both reactor recirculation pumps as required. Operations responded and stabilized the plant. Reactor water level is being maintained via the condensate system. Decay heat is being removed by bypass valves to the main condenser. There was no impact on Units 2 and 3. </br>This event requires a 4-hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.</br>This event requires a 4-hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(A), any event that results or should have resulted in emergency core cooling system (ECCS) discharge into the reactor coolant system as a result of a valid signal except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.</br>This event requires an 8-hour non-emergency report per 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B): 1) Reactor protection system including: reactor scram or reactor trip. 2) General containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). </br>All safety systems operated as expected. At no time were public health and safety at risk. The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.
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