Event Notification Report for June 28, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/27/2007 - 06/28/2007
Power Reactor
Event Number: 43455
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBERT MCLAUGHLIN
HQ OPS Officer: JASON KOZAL
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ROBERT MCLAUGHLIN
HQ OPS Officer: JASON KOZAL
Notification Date: 06/28/2007
Notification Time: 10:56 [ET]
Event Date: 06/28/2007
Event Time: 09:55 [EDT]
Last Update Date: 06/28/2007
Notification Time: 10:56 [ET]
Event Date: 06/28/2007
Event Time: 09:55 [EDT]
Last Update Date: 06/28/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (R1)
RAY POWELL (R1)
| 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 |
LOSS OF GREATER THAN 25% OF THE EPZ SIRENS FOR GREATER THAN 1 HOUR
"This eight hour notification is being made per 10 CFR 50.72(b)(3)(xiii) to report a loss of >25% of the EPZ sirens for greater than one hour. 44 of 165 offsite sirens are not functioning due to loss of power/equipment problems because of a recent storm. Efforts are in progress to restore the affected sirens.
"At 1000 6/28/07 less than 25% of sirens are unavailable."
The licensee notified the NRC Resident Inspector, the State of Pennsylvania, and local governments.
"This eight hour notification is being made per 10 CFR 50.72(b)(3)(xiii) to report a loss of >25% of the EPZ sirens for greater than one hour. 44 of 165 offsite sirens are not functioning due to loss of power/equipment problems because of a recent storm. Efforts are in progress to restore the affected sirens.
"At 1000 6/28/07 less than 25% of sirens are unavailable."
The licensee notified the NRC Resident Inspector, the State of Pennsylvania, and local governments.
Power Reactor
Event Number: 43457
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: MIKE FERRY
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: MIKE FERRY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/28/2007
Notification Time: 21:53 [ET]
Event Date: 06/28/2007
Event Time: 17:17 [PDT]
Last Update Date: 06/28/2007
Notification Time: 21:53 [ET]
Event Date: 06/28/2007
Event Time: 17:17 [PDT]
Last Update Date: 06/28/2007
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):
GREG PICK (R4)
GREG PICK (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 70 | Power Operation | 0 | Hot Shutdown |
REACTOR TRIP DUE TO CONDENSATE PUMP TRIP
"Reactor trip at 1717 hrs PDT due to [condensate pump] COND-P-2B trip. Reactor power was at 70% with [condensate pump] COND-P-2A secured. Reactor vessel level reached -50 inches and was restored with High Pressure Core Spray and Reactor Core Isolation Cooling. Main Steam Isolation Valves closed as expected due to the reaching -50 inches. All systems operated as expected. Further investigation into COND-P-2B trip is underway. Plant is stable in mode three, heat removal is being maintained by RHR-P-2B and Safety Relief Valves."
All rods fully inserted on the automatic reactor scram. All safety systems were available at the time of the trip. The trip was considered uncomplicated. The reactor pressure is currently being maintained between 500 to 600 psi and water level between 60 to 80 inches. The licensee was at 70% power at the time of the trip due to maintenance of condensate pump P-2A.
The licensee will notify the NRC Resident Inspector.
"Reactor trip at 1717 hrs PDT due to [condensate pump] COND-P-2B trip. Reactor power was at 70% with [condensate pump] COND-P-2A secured. Reactor vessel level reached -50 inches and was restored with High Pressure Core Spray and Reactor Core Isolation Cooling. Main Steam Isolation Valves closed as expected due to the reaching -50 inches. All systems operated as expected. Further investigation into COND-P-2B trip is underway. Plant is stable in mode three, heat removal is being maintained by RHR-P-2B and Safety Relief Valves."
All rods fully inserted on the automatic reactor scram. All safety systems were available at the time of the trip. The trip was considered uncomplicated. The reactor pressure is currently being maintained between 500 to 600 psi and water level between 60 to 80 inches. The licensee was at 70% power at the time of the trip due to maintenance of condensate pump P-2A.
The licensee will notify the NRC Resident Inspector.