Event Notification Report for May 12, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/11/2006 - 05/12/2006
EVENT NUMBERS
42571
Power Reactor
Event Number: 42571
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JOHN DAMPF
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JOHN DAMPF
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/12/2006
Notification Time: 05:11 [ET]
Event Date: 05/12/2006
Event Time: 00:53 [CDT]
Last Update Date: 05/12/2006
Notification Time: 05:11 [ET]
Event Date: 05/12/2006
Event Time: 00:53 [CDT]
Last Update Date: 05/12/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DALE POWERS (R4)
DALE POWERS (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 12 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP ON HIGH STEAM GENERATOR LEVEL
"While lowering turbine load to 45% for planned maintenance to replace an RCS Loop flow transmitter, Callaway Plant experienced high vibration on two main turbine bearings. The main turbine was manually tripped at 0047 in accordance with off-normal procedures. At 0052, received a Steam Generator High-High Level (P-14) on the "A" S/G resulting in a Feed Water Isolation Signal (FWIS) and Auxiliary Feed Water Actuation (AFAS). The reactor was manually tripped at 0053. Emergency Operating Procedures were completed and exited at 0115."
After receiving the main turbine high vibration alarm, the plant reduced power to below the reactor trip/turbine trip setpoint and manually tripped the main turbine. Steam generator level rose to the P-14 feedwater isolation setpoint at which time, the reactor was manually tripped.
All rods fully inserted on the trip. Decay heat is being removed by condenser steam dumps. Steam generator level is being maintained with the startup feed pump. The electrical grid is stable. No relief valves or safety valves lifted. The cause of the high vibration is being investigated.
The licensee notified the NRC Resident Inspector.
"While lowering turbine load to 45% for planned maintenance to replace an RCS Loop flow transmitter, Callaway Plant experienced high vibration on two main turbine bearings. The main turbine was manually tripped at 0047 in accordance with off-normal procedures. At 0052, received a Steam Generator High-High Level (P-14) on the "A" S/G resulting in a Feed Water Isolation Signal (FWIS) and Auxiliary Feed Water Actuation (AFAS). The reactor was manually tripped at 0053. Emergency Operating Procedures were completed and exited at 0115."
After receiving the main turbine high vibration alarm, the plant reduced power to below the reactor trip/turbine trip setpoint and manually tripped the main turbine. Steam generator level rose to the P-14 feedwater isolation setpoint at which time, the reactor was manually tripped.
All rods fully inserted on the trip. Decay heat is being removed by condenser steam dumps. Steam generator level is being maintained with the startup feed pump. The electrical grid is stable. No relief valves or safety valves lifted. The cause of the high vibration is being investigated.
The licensee notified the NRC Resident Inspector.