Event Notification Report for September 12, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/11/2001 - 09/12/2001
Power Reactor
Event Number: 38279
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN SCHIPIOUR
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN SCHIPIOUR
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/12/2001
Notification Time: 16:36 [ET]
Event Date: 09/12/2001
Event Time: 08:00 [CDT]
Last Update Date: 09/12/2001
Notification Time: 16:36 [ET]
Event Date: 09/12/2001
Event Time: 08:00 [CDT]
Last Update Date: 09/12/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 90 | Power Operation | 90 | Power Operation |
| 2 | N | Y | 96 | Power Operation | 96 | Power Operation |
ACCESS DENIED
A contract employee was determined to be under the influence of alcohol during a for-cause test. The employee's access to the plant has been denied.
The NRC Resident Inspector was notified of this event by the licensee.
Contact the Headquarters Operation Center for further details.
A contract employee was determined to be under the influence of alcohol during a for-cause test. The employee's access to the plant has been denied.
The NRC Resident Inspector was notified of this event by the licensee.
Contact the Headquarters Operation Center for further details.
Power Reactor
Event Number: 38280
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: ROBERT SHERMAN
HQ OPS Officer: BOB STRANSKY
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: ROBERT SHERMAN
HQ OPS Officer: BOB STRANSKY
Notification Date: 09/12/2001
Notification Time: 19:57 [ET]
Event Date: 09/12/2001
Event Time: 08:17 [PDT]
Last Update Date: 09/12/2001
Notification Time: 19:57 [ET]
Event Date: 09/12/2001
Event Time: 08:17 [PDT]
Last Update Date: 09/12/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MARK SHAFFER (R4)
MARK SHAFFER (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY REPORT
A licensed employee was determined to be under the influence of alcohol during a for-cause test. The employee's access to the plant has been terminated. The NRC resident inspector has been informed of this event by the licensee.
Contact the NRC Operations Center for additional details.
A licensed employee was determined to be under the influence of alcohol during a for-cause test. The employee's access to the plant has been terminated. The NRC resident inspector has been informed of this event by the licensee.
Contact the NRC Operations Center for additional details.
Power Reactor
Event Number: 38281
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: PHILLIP NORTH
HQ OPS Officer: FANGIE JONES
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: PHILLIP NORTH
HQ OPS Officer: FANGIE JONES
Notification Date: 09/12/2001
Notification Time: 20:53 [ET]
Event Date: 09/12/2001
Event Time: 18:13 [EDT]
Last Update Date: 09/12/2001
Notification Time: 20:53 [ET]
Event Date: 09/12/2001
Event Time: 18:13 [EDT]
Last Update Date: 09/12/2001
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):
JOHN MONNINGER (R2)
JOHN MONNINGER (R2)
| 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 |
AUTOMATIC REACTOR TRIP DUE TO TURBINE/GENERATOR TRIP
The plant sustained a turbine/generator trip resulting in a reactor trip, all rods inserted fully, all systems functioned as required unless otherwise noted, and the plant is stable in MODE 3 (Hot Standby). Main feedwater was lost due to a loss of power to the secondary pumps. Power is being supplied from the startup transformer, reactor coolant system is in forced circulation, emergency feedwater is supplying the steam generators, and turbine bypass valves to the condensers are providing a heat sink.
The licensee is investigating the cause of the turbine/generator trip and the loss of power to the secondary pumps.
The licensee notified the NRC Resident Inspector.
The plant sustained a turbine/generator trip resulting in a reactor trip, all rods inserted fully, all systems functioned as required unless otherwise noted, and the plant is stable in MODE 3 (Hot Standby). Main feedwater was lost due to a loss of power to the secondary pumps. Power is being supplied from the startup transformer, reactor coolant system is in forced circulation, emergency feedwater is supplying the steam generators, and turbine bypass valves to the condensers are providing a heat sink.
The licensee is investigating the cause of the turbine/generator trip and the loss of power to the secondary pumps.
The licensee notified the NRC Resident Inspector.