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On May 8, 2002, at 5:07 p.m., Wolf Creek e … On May 8, 2002, at 5:07 p.m., Wolf Creek experienced an automatic actuation of the Reactor Protection System (RPS) including an automatic reactor trip due to low water level in the "D" steam generator (SG). This actuation occurred following the closure of the "D" SG main feedwater regulating valve (FRV) during surveillance testing.</br></br>When the FRV closed, "D" SG level decreased below the reactor trip setpoint of 23.5 percent, initiating a reactor trip. The unit received a feedwater isolation and auxiliary feedwater actuation (both motor and turbine driven) because of the low-low SG levels. All control rods fully inserted, and the RPS and the Engineered Safety Features (ESF) Systems performed as expected.</br></br>The cause of the FRV closure was the failure of a Westinghouse 7300-series manual controller card for the "D" SG FRV. The failed controller card was replaced.</br></br>The safety significance of this event is low. This event is bounded by the current licensing basis analyses as reported in Wolf Creek Generating Station (WCGS) Updated Safety Analysis Report (USAR) section 15.2.7 "Loss of Normal Feedwater Flow." All safety related equipment performed as expected. There were no adverse effects on the health and safety of the public.ts on the health and safety of the public. +
May 8, 2002 +
On May 8, 2002, at 5:07 p.m., Wolf Creek e … On May 8, 2002, at 5:07 p.m., Wolf Creek experienced an automatic actuation of the Reactor Protection System (RPS) including an automatic reactor trip due to low water level in the "D" steam generator (SG). This actuation occurred following the closure of the "D" SG main feedwater regulating valve (FRV) during surveillance testing.</br></br>When the FRV closed, "D" SG level decreased below the reactor trip setpoint of 23.5 percent, initiating a reactor trip. The unit received a feedwater isolation and auxiliary feedwater actuation (both motor and turbine driven) because of the low-low SG levels. All control rods fully inserted, and the RPS and the Engineered Safety Features (ESF) Systems performed as expected.</br></br>The cause of the FRV closure was the failure of a Westinghouse 7300-series manual controller card for the "D" SG FRV. The failed controller card was replaced.</br></br>The safety significance of this event is low. This event is bounded by the current licensing basis analyses as reported in Wolf Creek Generating Station (WCGS) Updated Safety Analysis Report (USAR) section 15.2.7 "Loss of Normal Feedwater Flow." All safety related equipment performed as expected. There were no adverse effects on the health and safety of the public.ts on the health and safety of the public. +
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June 28, 2002 +
May 8, 2002 +
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