Event Notification Report for December 11, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/10/2008 - 12/11/2008
EVENT NUMBERS
44714
Power Reactor
Event Number: 44714
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: A. LEE YOUNG
HQ OPS Officer: VINCE KLCO
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: A. LEE YOUNG
HQ OPS Officer: VINCE KLCO
Notification Date: 12/12/2008
Notification Time: 01:12 [ET]
Event Date: 12/11/2008
Event Time: 23:01 [CST]
Last Update Date: 12/12/2008
Notification Time: 01:12 [ET]
Event Date: 12/11/2008
Event Time: 23:01 [CST]
Last Update Date: 12/12/2008
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):
JACK WHITTEN (R4)
JACK WHITTEN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO A FEEDWATER TRANSIENT
"The 'C' condensate pump tripped due to an electrical problem which caused a feedwater transient. The unit [automatically] tripped on high steam generator level at approximately 2301 CST. The unit is in mode 3 and stable. The reactor trip procedures are in progress at this time."
All control rods fully inserted into the core during the reactor trip. Offsite power is available and powering safety loads. The steam generator atmospheric steam dumps lifted momentarily during the transient and reseated. There is no known primary to secondary leakage. Decay heat is being removed via steam dumps to the condenser with makeup provided by auxiliary feedwater to the steam generator. The standby diesel generators and safety systems are available.
The licensee notified the NRC Resident Inspector.
"The 'C' condensate pump tripped due to an electrical problem which caused a feedwater transient. The unit [automatically] tripped on high steam generator level at approximately 2301 CST. The unit is in mode 3 and stable. The reactor trip procedures are in progress at this time."
All control rods fully inserted into the core during the reactor trip. Offsite power is available and powering safety loads. The steam generator atmospheric steam dumps lifted momentarily during the transient and reseated. There is no known primary to secondary leakage. Decay heat is being removed via steam dumps to the condenser with makeup provided by auxiliary feedwater to the steam generator. The standby diesel generators and safety systems are available.
The licensee notified the NRC Resident Inspector.