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At 1704 CDT, Braidwood Unit 1 experienced … At 1704 CDT, Braidwood Unit 1 experienced an automatic reactor trip. The reactor trip red first out was Over Temperature Delta Temperature (OTDT). At the time of the reactor trip, the Instrument Maintenance Department was performing a calibration of Power Range Channel N-43 and a calibration of the 1C S/G Narrow Range Level Channel 1L-0538. The cause of the trip is unknown at this time.</br>After the reactor trip occurred, all four Steam Generators reached their Low-2 reactor trip setpoint and Pressurizer pressure reached its low pressure reactor trip setpoint which is an expected response on a trip from full power. Steam Generator levels and Pressurizer pressure have been restored. Both the 1A and 1B Auxiliary Feedwater pumps auto started on the Low-2 Steam Generator levels as expected. All control rods fully inserted into the core.</br>Train B Main Control Room Filtration system shifted to makeup mode and the Train B Fuel Handling Building ventilation shifted to Emergency Mode due to a spurious actuation signal.</br>No secondary relief valves lifted and no secondary steam (was) released as a result of the reactor trip. The Main Steam Dumps are in service to the Main Condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. This report is being made per 10CFR50.72(b)(2)(iv)(B) for RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for automatic actuation of the Auxiliary Feedwater system, 8-hr. notification.</br>AC power is being provided by offsite power with the Diesel Generators in standby and all safety systems available. There is no Unit 2 impact.</br>The licensee notified the NRC Resident Inspector. The licensee also anticipates that there will be a press release issued regarding this event.press release issued regarding this event. +
22:04:00, 20 September 2010 +
46,262 +
19:37:00, 20 September 2010 +
22:04:00, 20 September 2010 +
At 1704 CDT, Braidwood Unit 1 experienced … At 1704 CDT, Braidwood Unit 1 experienced an automatic reactor trip. The reactor trip red first out was Over Temperature Delta Temperature (OTDT). At the time of the reactor trip, the Instrument Maintenance Department was performing a calibration of Power Range Channel N-43 and a calibration of the 1C S/G Narrow Range Level Channel 1L-0538. The cause of the trip is unknown at this time.</br>After the reactor trip occurred, all four Steam Generators reached their Low-2 reactor trip setpoint and Pressurizer pressure reached its low pressure reactor trip setpoint which is an expected response on a trip from full power. Steam Generator levels and Pressurizer pressure have been restored. Both the 1A and 1B Auxiliary Feedwater pumps auto started on the Low-2 Steam Generator levels as expected. All control rods fully inserted into the core.</br>Train B Main Control Room Filtration system shifted to makeup mode and the Train B Fuel Handling Building ventilation shifted to Emergency Mode due to a spurious actuation signal.</br>No secondary relief valves lifted and no secondary steam (was) released as a result of the reactor trip. The Main Steam Dumps are in service to the Main Condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. This report is being made per 10CFR50.72(b)(2)(iv)(B) for RPS actuation, 4-hr. notification, and per 10CFR50.72(b)(3)(iv)(A) for automatic actuation of the Auxiliary Feedwater system, 8-hr. notification.</br>AC power is being provided by offsite power with the Diesel Generators in standby and all safety systems available. There is no Unit 2 impact.</br>The licensee notified the NRC Resident Inspector. The licensee also anticipates that there will be a press release issued regarding this event.press release issued regarding this event. +
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