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Wolf Creek experienced a reactor trip at 1 … Wolf Creek experienced a reactor trip at 1458 CST. The first out annunciator was Steam Generator Level Lo Lo Reactor Trip.</br>The trip was caused by the loss of the 'A' Main Feed Pump. The cause of the loss of the feed pump was due to the loss of 120 VAC non-safety instrument inverter PN09. PN09 supplies the Main Feed Pump Speed Control Circuitry.</br>The loss of the PN09 also resulted in the loss of the ability to dump steam to the main condenser. Initial post trip decay heat was being removed with the Steam Generator Atmospheric Relief Valves and Auxiliary Feed Water. The Atmospheric Relief Valves cycled from approximately 1458 CST until approximately 1504 CST. Primary to Secondary leakage is less than 2.68 gallons per day.</br>PN09 was re-energized at 1554 CST. </br>All systems functioned as designed with the exception of the instrumentation powered by PN09. At the time of the trip the 'A' Emergency Diesel Generator and the 'A' Class IE Air Conditioning Unit were out of service for maintenance.</br>The plant is being maintained at normal Mode 3 pressure and temperature.</br>The reactor trip was uncomplicated and decay heat is currently being removed by steam dumps to the main condensers. </br>The licensee has notified the NRC Senior Resident Inspector.otified the NRC Senior Resident Inspector. +
20:58:00, 2 March 2010 +
45,739 +
18:48:00, 2 March 2010 +
20:58:00, 2 March 2010 +
Wolf Creek experienced a reactor trip at 1 … Wolf Creek experienced a reactor trip at 1458 CST. The first out annunciator was Steam Generator Level Lo Lo Reactor Trip.</br>The trip was caused by the loss of the 'A' Main Feed Pump. The cause of the loss of the feed pump was due to the loss of 120 VAC non-safety instrument inverter PN09. PN09 supplies the Main Feed Pump Speed Control Circuitry.</br>The loss of the PN09 also resulted in the loss of the ability to dump steam to the main condenser. Initial post trip decay heat was being removed with the Steam Generator Atmospheric Relief Valves and Auxiliary Feed Water. The Atmospheric Relief Valves cycled from approximately 1458 CST until approximately 1504 CST. Primary to Secondary leakage is less than 2.68 gallons per day.</br>PN09 was re-energized at 1554 CST. </br>All systems functioned as designed with the exception of the instrumentation powered by PN09. At the time of the trip the 'A' Emergency Diesel Generator and the 'A' Class IE Air Conditioning Unit were out of service for maintenance.</br>The plant is being maintained at normal Mode 3 pressure and temperature.</br>The reactor trip was uncomplicated and decay heat is currently being removed by steam dumps to the main condensers. </br>The licensee has notified the NRC Senior Resident Inspector.otified the NRC Senior Resident Inspector. +
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20:58:00, 2 March 2010 +
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