Event Notification Report for June 02, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/01/2012 - 06/02/2012
EVENT NUMBERS
47987
Power Reactor
Event Number: 47987
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/02/2012
Notification Time: 21:52 [ET]
Event Date: 06/02/2012
Event Time: 19:35 [EDT]
Last Update Date: 06/02/2012
Notification Time: 21:52 [ET]
Event Date: 06/02/2012
Event Time: 19:35 [EDT]
Last Update Date: 06/02/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
STEVEN VIAS (R2DO)
STEVEN VIAS (R2DO)
| 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 |
REACTOR TRIP DUE TO A TURBINE CONTROL SYSTEM FAILURE
"At 1935 during normal full power operations, Unit 1 automatically tripped due to a loss of load caused by an instantaneous failure of the turbine control system. The trip was uncomplicated and all CEAs [control rods] fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause and details of the turbine control system failure are under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Steam Bypass Control Systems with condenser vacuum. The offsite power grid is available and stable.
"This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to RPS actuation with the reactor critical."
The licensee notified the NRC Resident Inspector.
"At 1935 during normal full power operations, Unit 1 automatically tripped due to a loss of load caused by an instantaneous failure of the turbine control system. The trip was uncomplicated and all CEAs [control rods] fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause and details of the turbine control system failure are under investigation. The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Steam Bypass Control Systems with condenser vacuum. The offsite power grid is available and stable.
"This non-emergency notification is being made pursuant to 10 CFR 50.72(b)(2)(iv)(B) due to RPS actuation with the reactor critical."
The licensee notified the NRC Resident Inspector.