Event Notification Report for August 24, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/23/2008 - 08/24/2008
EVENT NUMBERS
44438
Power Reactor
Event Number: 44438
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM KISNER
HQ OPS Officer: VINCE KLCO
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] B&W-L-LP
NRC Notified By: WILLIAM KISNER
HQ OPS Officer: VINCE KLCO
Notification Date: 08/24/2008
Notification Time: 18:03 [ET]
Event Date: 08/24/2008
Event Time: 15:57 [EDT]
Last Update Date: 08/24/2008
Notification Time: 18:03 [ET]
Event Date: 08/24/2008
Event Time: 15:57 [EDT]
Last Update Date: 08/24/2008
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):
STEVE ROSE (R2)
STEVE ROSE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO FEEDWATER FLOW OSCILLATIONS
"The 'A' Condensate Pump became uncoupled, lowering Condensate flow. Operators began to manually lower reactor power to maintain deaerator level. Reactor power was lowered to approximately 62 percent. At this power, [feedwater] flow oscillations began and were excessive. With these flow oscillations increasing the decision was made to manually trip the Reactor. The Reactor was manually tripped at 1557 hours. There were no safety system actuations other than RPS (Manual). The plant is stable in a normal post trip configuration."
All control rods inserted into the core during the reactor trip. Offsite power is available and powering safety loads. The steam generator safeties lifted during the transient and reseated. There is no known primary to secondary leakage. Decay heat is being removed via steam dumps to the condenser using normal feedwater to the steam generator. The emergency feedwater system was not initiated during the reactor trip.
The licensee notified the NRC Resident Inspector.
"The 'A' Condensate Pump became uncoupled, lowering Condensate flow. Operators began to manually lower reactor power to maintain deaerator level. Reactor power was lowered to approximately 62 percent. At this power, [feedwater] flow oscillations began and were excessive. With these flow oscillations increasing the decision was made to manually trip the Reactor. The Reactor was manually tripped at 1557 hours. There were no safety system actuations other than RPS (Manual). The plant is stable in a normal post trip configuration."
All control rods inserted into the core during the reactor trip. Offsite power is available and powering safety loads. The steam generator safeties lifted during the transient and reseated. There is no known primary to secondary leakage. Decay heat is being removed via steam dumps to the condenser using normal feedwater to the steam generator. The emergency feedwater system was not initiated during the reactor trip.
The licensee notified the NRC Resident Inspector.