Event Notification Report for August 27, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/26/2006 - 08/27/2006
Power Reactor
Event Number: 42806
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CECIL H. WILLIAMS
HQ OPS Officer: MIKE RIPLEY
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CECIL H. WILLIAMS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 08/27/2006
Notification Time: 09:20 [ET]
Event Date: 08/27/2006
Event Time: 06:31 [EDT]
Last Update Date: 08/27/2006
Notification Time: 09:20 [ET]
Event Date: 08/27/2006
Event Time: 06:31 [EDT]
Last Update Date: 08/27/2006
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):
MALCOLM WIDMANN (R2)
MALCOLM WIDMANN (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 |
AUTOMATIC REACTOR TRIP DUE TO REACTOR COOLANT PUMP TRIP
"On Sunday, August 27, 2006 at 0631 EDST, Unit Two was at 99.7% RTP when RCP #4 tripped generating a Low Flow Reactor Trip. All systems functioned as required. AFWAS [Aux Feedwater Actuation Signal] was actuated as expected due to lo-lo Steam Generators levels. RCS Letdown isolated on a momentary low level signal on one channel of Pressurizer level, and has since been restored. The reactor is currently stable in Mode 3 while the cause of the trip of the RCP is investigated."
Decay heat is being rejected to the condenser via the steam dumps. ESF systems remain operable and the electrical grid is stable. The licensee notified the NRC Resident Inspector.
"On Sunday, August 27, 2006 at 0631 EDST, Unit Two was at 99.7% RTP when RCP #4 tripped generating a Low Flow Reactor Trip. All systems functioned as required. AFWAS [Aux Feedwater Actuation Signal] was actuated as expected due to lo-lo Steam Generators levels. RCS Letdown isolated on a momentary low level signal on one channel of Pressurizer level, and has since been restored. The reactor is currently stable in Mode 3 while the cause of the trip of the RCP is investigated."
Decay heat is being rejected to the condenser via the steam dumps. ESF systems remain operable and the electrical grid is stable. The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 42807
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: E. TIEDEMANN
HQ OPS Officer: JOHN KNOKE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: E. TIEDEMANN
HQ OPS Officer: JOHN KNOKE
Notification Date: 08/27/2006
Notification Time: 21:35 [ET]
Event Date: 08/27/2006
Event Time: 17:05 [CDT]
Last Update Date: 08/27/2006
Notification Time: 21:35 [ET]
Event Date: 08/27/2006
Event Time: 17:05 [CDT]
Last Update Date: 08/27/2006
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):
ERIC DUNCAN (R3)
ERIC DUNCAN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 96 | Power Operation | 0 | Hot Shutdown |
REACTOR TRIP DUE TO REACTOR HIGH WATER LEVEL
"At 1705 CDT on August 27, 2006, a high water level trip occurred resulting in a reactor scram. All control rods fully inserted on the scram signal. Reactor water level is being controlled in the normal operating band and reactor pressure is being controlled in a normal band.
"The apparent cause of the high level trip was a High Pressure Core Spray (HPCS) system initiation. There is no indication that the HPCS initiation was caused by an actual parameter reaching a trip setpoint. Division four nuclear system protection system (NSPS) is the current focus of troubleshooting activities.
"The Reactor Core Isolation Cooling (RCIC) system isolated after the scram. Troubleshooting is in progress to determine the cause. Both offsite power sources are operable and emergency diesel generators are operable and available if required. All safety related systems are available if required."
The licensee notified the NRC Resident Inspector.
"At 1705 CDT on August 27, 2006, a high water level trip occurred resulting in a reactor scram. All control rods fully inserted on the scram signal. Reactor water level is being controlled in the normal operating band and reactor pressure is being controlled in a normal band.
"The apparent cause of the high level trip was a High Pressure Core Spray (HPCS) system initiation. There is no indication that the HPCS initiation was caused by an actual parameter reaching a trip setpoint. Division four nuclear system protection system (NSPS) is the current focus of troubleshooting activities.
"The Reactor Core Isolation Cooling (RCIC) system isolated after the scram. Troubleshooting is in progress to determine the cause. Both offsite power sources are operable and emergency diesel generators are operable and available if required. All safety related systems are available if required."
The licensee notified the NRC Resident Inspector.