Event Notification Report for November 04, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/03/2006 - 11/04/2006
Power Reactor
Event Number: 42963
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: STEVEN OAKLEY
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: STEVEN OAKLEY
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/04/2006
Notification Time: 20:37 [ET]
Event Date: 11/04/2006
Event Time: 16:30 [EST]
Last Update Date: 11/04/2006
Notification Time: 20:37 [ET]
Event Date: 11/04/2006
Event Time: 16:30 [EST]
Last Update Date: 11/04/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MONTE PHILLIPS (R3)
MONTE PHILLIPS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Startup | 0 | Startup |
AUXILIARY FEEDWATER NOT ALIGNED PROPERLY IN STARTUP MODE
"On 11/3/2006 at 1834 hours, it was discovered that, with the Plant in Mode 2, both trains of Auxiliary Feedwater were not in the required pump automatic start configuration. One pump was operating and performing the heat removal function. Both Auxiliary Feedwater train pump controls were immediately placed into the Automatic configuration. It was determined that the pump start controls had been placed in Manual on 11/1/2006 at about 2152 hours. Upon discovery, it was believed that the Auxiliary Feedwater heat removal function was satisfied because one train was operating and had been in operation since before 2152 hours on 11/1/2006.
"Subsequently, on 11/4/2006 at 1630 hours it was determined that, with the pump controls in manual, coincident with a postulated Loss of Offsite Power and an Auxiliary Feedwater Actuation Signal, the operating Auxiliary Feedwater pump would trip and neither train pump would automatically start.
"This situation would constitute a condition that could have prevented the fulfillment of the safety function to mitigate the consequences of a Loss Of Offsite Power event and is reportable under 50.72(b)(3)(v)D.
"Had such an event occurred, the Operators would have restored Auxiliary Feedwater flow in accordance with station procedures."
The licensee notified the NRC Resident Inspector.
"On 11/3/2006 at 1834 hours, it was discovered that, with the Plant in Mode 2, both trains of Auxiliary Feedwater were not in the required pump automatic start configuration. One pump was operating and performing the heat removal function. Both Auxiliary Feedwater train pump controls were immediately placed into the Automatic configuration. It was determined that the pump start controls had been placed in Manual on 11/1/2006 at about 2152 hours. Upon discovery, it was believed that the Auxiliary Feedwater heat removal function was satisfied because one train was operating and had been in operation since before 2152 hours on 11/1/2006.
"Subsequently, on 11/4/2006 at 1630 hours it was determined that, with the pump controls in manual, coincident with a postulated Loss of Offsite Power and an Auxiliary Feedwater Actuation Signal, the operating Auxiliary Feedwater pump would trip and neither train pump would automatically start.
"This situation would constitute a condition that could have prevented the fulfillment of the safety function to mitigate the consequences of a Loss Of Offsite Power event and is reportable under 50.72(b)(3)(v)D.
"Had such an event occurred, the Operators would have restored Auxiliary Feedwater flow in accordance with station procedures."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42964
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT BRUNS
HQ OPS Officer: JEFF ROTTON
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT BRUNS
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/04/2006
Notification Time: 21:01 [ET]
Event Date: 11/04/2006
Event Time: 18:10 [EST]
Last Update Date: 11/04/2006
Notification Time: 21:01 [ET]
Event Date: 11/04/2006
Event Time: 18:10 [EST]
Last Update Date: 11/04/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JOHN WHITE (R1)
JOHN WHITE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 20 | Power Operation | 20 | Power Operation |
HPCI INOPERABLE
"During HPCI testing with reactor pressure at 975 psig, HPCI flow and turbine speed oscillations occurred. The HPCI turbine was run for approximately one minute and was manually tripped by the operator when system conditions did not improve.
"A cause investigation is underway.
"All other ECCS and RCIC remain operable.
"The unit is in a 14 day LCO for this event.
"The NRC Resident Inspector has been notified."
"During HPCI testing with reactor pressure at 975 psig, HPCI flow and turbine speed oscillations occurred. The HPCI turbine was run for approximately one minute and was manually tripped by the operator when system conditions did not improve.
"A cause investigation is underway.
"All other ECCS and RCIC remain operable.
"The unit is in a 14 day LCO for this event.
"The NRC Resident Inspector has been notified."