Event Notification Report for December 20, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/19/2003 - 12/20/2003
EVENT NUMBERS
40403
Power Reactor
Event Number: 40403
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: BILL GOTT
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: BILL GOTT
Notification Date: 12/20/2003
Notification Time: 13:00 [ET]
Event Date: 12/20/2003
Event Time: 09:49 [EST]
Last Update Date: 01/08/2004
Notification Time: 13:00 [ET]
Event Date: 12/20/2003
Event Time: 09:49 [EST]
Last Update Date: 01/08/2004
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):
THOMAS DECKER (R2)
THOMAS DECKER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
RPS ACTUATION DUE TO LOSS OF TURBINE GENERATOR EXCITATION
On December 20, 2003, at 0949 hours, an automatic reactor trip occurred due to a loss of excitation of the turbine generator. All plant safety functions were maintained throughout the event. The plant was stabilized in Mode 3. All plant safety systems responded normally with the exception of the 2C Auxiliary Feedwater Pump (steam driven) which tripped on mechanical overspeed. The 2A and 2B Auxiliary Feedwater Pumps (electric driven) functioned normally to restore the 2A and 2B Steam Generator levels. Post trip system anomalies include RCS Letdown isolated, Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, and the Fuel Handling Building ventilation system swapped to the Shield Building. An Emergency Response Team has been formed to review these conditions prior to plant restart. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the automatic RPS Reactor Trip.
All controls inserted properly. Decay heat is being removed using the turbine bypass valves.
The Licensee notified the NRC Resident Inspector.
* * * UPDATE ON 1/08/04 @ 0625 B Y BRADY TO GOULD * * *
This update is provided to include the 10CFR50.72(b)(3)(iv)(A) notification criterion for the auxiliary feedwater actuation.
The NRC Resident Inspector was notified.,
Reg 2 RDO(Fredrickson) was informed.
On December 20, 2003, at 0949 hours, an automatic reactor trip occurred due to a loss of excitation of the turbine generator. All plant safety functions were maintained throughout the event. The plant was stabilized in Mode 3. All plant safety systems responded normally with the exception of the 2C Auxiliary Feedwater Pump (steam driven) which tripped on mechanical overspeed. The 2A and 2B Auxiliary Feedwater Pumps (electric driven) functioned normally to restore the 2A and 2B Steam Generator levels. Post trip system anomalies include RCS Letdown isolated, Steam Generator Blowdown isolation valves closed, Control Room ventilation system swapped to recirculation mode, and the Fuel Handling Building ventilation system swapped to the Shield Building. An Emergency Response Team has been formed to review these conditions prior to plant restart. This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to the automatic RPS Reactor Trip.
All controls inserted properly. Decay heat is being removed using the turbine bypass valves.
The Licensee notified the NRC Resident Inspector.
* * * UPDATE ON 1/08/04 @ 0625 B Y BRADY TO GOULD * * *
This update is provided to include the 10CFR50.72(b)(3)(iv)(A) notification criterion for the auxiliary feedwater actuation.
The NRC Resident Inspector was notified.,
Reg 2 RDO(Fredrickson) was informed.