Event Notification Report for March 18, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/17/2012 - 03/18/2012
EVENT NUMBERS
47752
Power Reactor
Event Number: 47752
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: FRED POLLAK
HQ OPS Officer: CHARLES TEAL
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: FRED POLLAK
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/19/2012
Notification Time: 02:24 [ET]
Event Date: 03/18/2012
Event Time: 23:36 [EDT]
Last Update Date: 03/19/2012
Notification Time: 02:24 [ET]
Event Date: 03/18/2012
Event Time: 23:36 [EDT]
Last Update Date: 03/19/2012
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):
EUGENE GUTHRIE (R2DO)
EUGENE GUTHRIE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 1 | Startup | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO CONTROL ELEMENT ASSEMBLY ANOMALOUS BEHAVIOR
"At 2336 EDT, during performance at Low Power Physics Testing, Unit 1 was manually tripped while the reactor was critical at less than 1% power due to Control Element Assembly (CEA) Regulating Group #3 exhibiting anomalous behavior (continued to insert with no operator action). The trip was uncomplicated and all CEAs fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause for the abnormal CEA performance is under investigation.
"The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Auxiliary Feedwater and Atmospheric Dump Valves. 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 manual RPS actuation with the reactor critical"
The NRC Resident Inspector has been informed.
"At 2336 EDT, during performance at Low Power Physics Testing, Unit 1 was manually tripped while the reactor was critical at less than 1% power due to Control Element Assembly (CEA) Regulating Group #3 exhibiting anomalous behavior (continued to insert with no operator action). The trip was uncomplicated and all CEAs fully inserted when the reactor was tripped. No automatic safety system actuations were required and none occurred. The cause for the abnormal CEA performance is under investigation.
"The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Auxiliary Feedwater and Atmospheric Dump Valves. 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 manual RPS actuation with the reactor critical"
The NRC Resident Inspector has been informed.