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The licensee experienced a feedwater trans … The licensee experienced a feedwater transient which initiated the event. All safety systems are available. All control rods fully inserted. The electrical lineup is normal. The decay heat path is through the condenser steam dumps. No relief valves or safety valves lifted during the transient. Primary plant temperature is 533 degrees Fahrenheit and primary plant pressure is 2256 psia. The licensee is investigating the cause of the feed transient.</br>The licensee notified the NRC Resident Inspector, the Waterford Dispatch, and the State Department of Environmental Protection.</br>Earlier, the licensee was experiencing oscillations in the feedwater regulating valve (FRV) for the #2 steam generator when the valve was in automatic control. Troubleshooting planning was underway but no troubleshooting activities were in progress at the time of the trip. When the operator placed the #2 steam generator FRV in manual control, the steam generator water level began to increase and could not be recovered. The operator then manually tripped the reactor prior to reaching the high steam generator level trip setpoint. An Auxiliary Feed Water system actuation did occur during the transient. The trip and plant response was considered uncomplicated.ant response was considered uncomplicated. +
20:45:00, 22 May 2010 +
45,945 +
17:46:00, 22 May 2010 +
20:45:00, 22 May 2010 +
The licensee experienced a feedwater trans … The licensee experienced a feedwater transient which initiated the event. All safety systems are available. All control rods fully inserted. The electrical lineup is normal. The decay heat path is through the condenser steam dumps. No relief valves or safety valves lifted during the transient. Primary plant temperature is 533 degrees Fahrenheit and primary plant pressure is 2256 psia. The licensee is investigating the cause of the feed transient.</br>The licensee notified the NRC Resident Inspector, the Waterford Dispatch, and the State Department of Environmental Protection.</br>Earlier, the licensee was experiencing oscillations in the feedwater regulating valve (FRV) for the #2 steam generator when the valve was in automatic control. Troubleshooting planning was underway but no troubleshooting activities were in progress at the time of the trip. When the operator placed the #2 steam generator FRV in manual control, the steam generator water level began to increase and could not be recovered. The operator then manually tripped the reactor prior to reaching the high steam generator level trip setpoint. An Auxiliary Feed Water system actuation did occur during the transient. The trip and plant response was considered uncomplicated.ant response was considered uncomplicated. +
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20:45:00, 22 May 2010 +
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