Event Notification Report for June 26, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/25/2008 - 06/26/2008
Power Reactor
Event Number: 44318
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THAD REAMES
HQ OPS Officer: JEFF ROTTON
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THAD REAMES
HQ OPS Officer: JEFF ROTTON
Notification Date: 06/26/2008
Notification Time: 18:10 [ET]
Event Date: 06/26/2008
Event Time: 17:32 [EDT]
Last Update Date: 06/26/2008
Notification Time: 18:10 [ET]
Event Date: 06/26/2008
Event Time: 17:32 [EDT]
Last Update Date: 06/26/2008
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):
KATHLEEN O'DONOHUE (R2)
KATHLEEN O'DONOHUE (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 |
REACTOR TRIP DUE TO LOSS OF 1B REACTOR COOLANT PUMP
"Loss of 1B Reactor Coolant Pump caused Reactor Trip from 100%. 50G (Overcurrent relays) were picked up on the Safety Breaker and the 6900V supply breaker. Automatic actuation of the motor driven [and turbine driven] Auxiliary Feed Pumps occurred as expected."
All control rods fully inserted on the reactor trip. The steam generators water level is being maintained by the AFW system. Decay heat is being removed to the main condenser via the turbine dump valves. RCS PORV lifted and reseated. The electrical plant is in a normal shutdown lineup and the EDGs are available. There is no affect on Unit 2 due to this event.
The licensee notified the NRC Resident Inspector.
"Loss of 1B Reactor Coolant Pump caused Reactor Trip from 100%. 50G (Overcurrent relays) were picked up on the Safety Breaker and the 6900V supply breaker. Automatic actuation of the motor driven [and turbine driven] Auxiliary Feed Pumps occurred as expected."
All control rods fully inserted on the reactor trip. The steam generators water level is being maintained by the AFW system. Decay heat is being removed to the main condenser via the turbine dump valves. RCS PORV lifted and reseated. The electrical plant is in a normal shutdown lineup and the EDGs are available. There is no affect on Unit 2 due to this event.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 44319
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: THOMAS JESSESSKY
HQ OPS Officer: JOHN KNOKE
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: THOMAS JESSESSKY
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/26/2008
Notification Time: 21:34 [ET]
Event Date: 06/26/2008
Event Time: 11:33 [CDT]
Last Update Date: 06/26/2008
Notification Time: 21:34 [ET]
Event Date: 06/26/2008
Event Time: 11:33 [CDT]
Last Update Date: 06/26/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DAVE PASSEHL (R3)
DAVE PASSEHL (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
10 CFR 26.719 FITNESS-FOR-DUTY - SITE ACCESS SUSPENDED
A random FFD drug and alcohol test on a licensee supervisor indicated the presence of alcohol, although the blood alcohol content was below the limit of a positive test. As a prudent measure the Medical Review Officer recommended that the individual be further evaluated. The individual's site access to the plant has been suspended pending completion of that evaluation. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.
A random FFD drug and alcohol test on a licensee supervisor indicated the presence of alcohol, although the blood alcohol content was below the limit of a positive test. As a prudent measure the Medical Review Officer recommended that the individual be further evaluated. The individual's site access to the plant has been suspended pending completion of that evaluation. Contact the Headquarters Operations Officer for additional details.
The licensee informed the NRC Resident Inspector.