Event Notification Report for June 07, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/06/2008 - 06/07/2008
EVENT NUMBERS
44276
Power Reactor
Event Number: 44276
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PAUL CHRISTIANSEN
HQ OPS Officer: PETE SNYDER
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PAUL CHRISTIANSEN
HQ OPS Officer: PETE SNYDER
Notification Date: 06/07/2008
Notification Time: 11:19 [ET]
Event Date: 06/07/2008
Event Time: 08:18 [EDT]
Last Update Date: 06/07/2008
Notification Time: 11:19 [ET]
Event Date: 06/07/2008
Event Time: 08:18 [EDT]
Last Update Date: 06/07/2008
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):
ROBERT HAAG (R2)
ROBERT HAAG (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP FOLLOWING THE TRIP OF A CONDENSATE PUMP
"On 6/7/08 at 0818 hours, an unplanned manual reactor trip was initiated on St. Lucie Unit 2 from 100% power due to a trip of the 2B Condensate Pump, which led to a trip of the 2B Main Feedwater Pump (MFP) and decreasing Steam Generator (S/G) levels. The reactor was manually tripped due to decreasing S/G levels.
"Following the reactor trip, EOP-1, Standard Post Trip Actions and EOP-2, Reactor Trip Recovery procedures were completed and Unit 2 was stabilized in Mode 3. All control rods fully inserted. The Main Steam Safety Valves lifted as expected. Feedwater to the S/Gs was initially supplied by the 2A [MFP] until Auxiliary Feedwater Actuation System (AFAS) actuated as expected on low S/G level. Subsequently, the Auxiliary Feedwater Pumps restored S/G levels. Unit 2 electrical requirements were provided from offsite power. Other than the trip of the 2B Condensate Pump (initiating event) there were no major equipment failures. Unit 1 was not affected by this event. The grid is stable."
Decay heat is being removed by the Auxiliary Feedwater Pumps feeding the S/Gs steaming to the bypass valves in the Condenser.
The licensee notified the NRC Resident Inspector.
"On 6/7/08 at 0818 hours, an unplanned manual reactor trip was initiated on St. Lucie Unit 2 from 100% power due to a trip of the 2B Condensate Pump, which led to a trip of the 2B Main Feedwater Pump (MFP) and decreasing Steam Generator (S/G) levels. The reactor was manually tripped due to decreasing S/G levels.
"Following the reactor trip, EOP-1, Standard Post Trip Actions and EOP-2, Reactor Trip Recovery procedures were completed and Unit 2 was stabilized in Mode 3. All control rods fully inserted. The Main Steam Safety Valves lifted as expected. Feedwater to the S/Gs was initially supplied by the 2A [MFP] until Auxiliary Feedwater Actuation System (AFAS) actuated as expected on low S/G level. Subsequently, the Auxiliary Feedwater Pumps restored S/G levels. Unit 2 electrical requirements were provided from offsite power. Other than the trip of the 2B Condensate Pump (initiating event) there were no major equipment failures. Unit 1 was not affected by this event. The grid is stable."
Decay heat is being removed by the Auxiliary Feedwater Pumps feeding the S/Gs steaming to the bypass valves in the Condenser.
The licensee notified the NRC Resident Inspector.