Event Notification Report for March 27, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/26/2005 - 03/27/2005
Power Reactor
Event Number: 41530
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2005
Notification Time: 00:35 [ET]
Event Date: 03/27/2005
Event Time: 22:00 [EST]
Last Update Date: 03/28/2005
Notification Time: 00:35 [ET]
Event Date: 03/27/2005
Event Time: 22:00 [EST]
Last Update Date: 03/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN ROGGE (R1)
JOHN ROGGE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Startup | 0 | Startup |
PLANT SHUTDOWN TO REPAIR SMALL REACTOR COOLANT SYSTEM LEAK
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"While in OPCON 2 with the Main Turbine secured, Hope Creek personnel performed a Primary Containment entry to determine the source of slightly elevated unidentified leakage. This leakage has slowly trended up since plant start-up in February to approximately 0.73 gpm. With the current unidentified leak rate at 0.436 gpm, personnel identified a steam leak from an insulated decontamination port, sealed via a bolted flange, within the isolable boundary of the 'B' Reactor Recirculation pump. This was the only source of reactor coolant system leakage identified although some minor leakage (totaling approximately 250ml/min) from two drywell recirculation fans was also identified. This is a voluntary/courtesy Emergency Notification System (ENS) notification that Hope Creek is proceeding to Cold Shutdown to precisely identify and repair the leakage source. At the time of this notification, Hope Creek Generating Station is in OPCON 3 with plant cooldown in process."
The licensee reported this event under 10 CFR 50.72(b)(2) as a 4-Hour Non-Emergency Voluntary notification. The NRC Resident Inspector has been notified and the licensee plans to notify LAC Township.
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"While in OPCON 2 with the Main Turbine secured, Hope Creek personnel performed a Primary Containment entry to determine the source of slightly elevated unidentified leakage. This leakage has slowly trended up since plant start-up in February to approximately 0.73 gpm. With the current unidentified leak rate at 0.436 gpm, personnel identified a steam leak from an insulated decontamination port, sealed via a bolted flange, within the isolable boundary of the 'B' Reactor Recirculation pump. This was the only source of reactor coolant system leakage identified although some minor leakage (totaling approximately 250ml/min) from two drywell recirculation fans was also identified. This is a voluntary/courtesy Emergency Notification System (ENS) notification that Hope Creek is proceeding to Cold Shutdown to precisely identify and repair the leakage source. At the time of this notification, Hope Creek Generating Station is in OPCON 3 with plant cooldown in process."
The licensee reported this event under 10 CFR 50.72(b)(2) as a 4-Hour Non-Emergency Voluntary notification. The NRC Resident Inspector has been notified and the licensee plans to notify LAC Township.
Power Reactor
Event Number: 41531
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: TOM OSELAND
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: TOM OSELAND
HQ OPS Officer: BILL HUFFMAN
Notification Date: 03/28/2005
Notification Time: 01:12 [ET]
Event Date: 03/27/2005
Event Time: 19:30 [CST]
Last Update Date: 03/28/2005
Notification Time: 01:12 [ET]
Event Date: 03/27/2005
Event Time: 19:30 [CST]
Last Update Date: 03/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
LAURA KOZAK (R3)
LAURA KOZAK (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 85 | Power Operation | 85 | Power Operation |
ELECTRICAL SAFETY BUS TRIP DURING QUAD CITIES UNIT 1 REFUELING OUTAGE
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"At 1930, Unit 1 experienced a loss of 480 VAC busses 18 and 19. This caused a loss of power to the Control Room Emergency Ventilation System (CREVS) and the CREVS Air Conditioning System (CREVS AC). This event also caused a loss of power to the U1 equipment that was supporting the Alternate Decay Heat Removal (ADHR) mode of operation.
"Power was restored to Bus 19 at 2001 and Bus 18 at 2013. The restoration of Bus 18 also restored power to CREVS and CREVS AC. All systems supporting ADHR were restored by 2015. At the time of the occurrence, the estimated time to boil without decay heat removal capability was 571 minutes. All isolations and actuations occurred as expected. The cause of the bus trips is being investigated.
"This Event is being reported under 50.72 (b)(3)(v)(B) and 50.72 (b)(3)(v)(D)."
The licensee stated at the time of the event, Busses 18 and 19 were cross-tied and the feeder breaker to Bus 18 tripped open. The breaker was changed out and power to Busses 18 and 19 restored. The cause of the Bus 18 feeder breaker trip has not yet been determined.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM THE LICENSEE (OSELAND) TO NRC (HUFFMAN) AT 0312 EST ON 3/28/05 * * *
The licensee stated that the Alternate Decay Heat Removal pumps from Unit 2 remained in service so that all decay heat removal was not lost. The Unit 1 primary coolant system temperature increase during the 45 minute duration of this event was approximately 1 degree. R3DO (Kozak) has been notified.
The following information was obtained from the licensee via facsimile (licensee text in quotes):
"At 1930, Unit 1 experienced a loss of 480 VAC busses 18 and 19. This caused a loss of power to the Control Room Emergency Ventilation System (CREVS) and the CREVS Air Conditioning System (CREVS AC). This event also caused a loss of power to the U1 equipment that was supporting the Alternate Decay Heat Removal (ADHR) mode of operation.
"Power was restored to Bus 19 at 2001 and Bus 18 at 2013. The restoration of Bus 18 also restored power to CREVS and CREVS AC. All systems supporting ADHR were restored by 2015. At the time of the occurrence, the estimated time to boil without decay heat removal capability was 571 minutes. All isolations and actuations occurred as expected. The cause of the bus trips is being investigated.
"This Event is being reported under 50.72 (b)(3)(v)(B) and 50.72 (b)(3)(v)(D)."
The licensee stated at the time of the event, Busses 18 and 19 were cross-tied and the feeder breaker to Bus 18 tripped open. The breaker was changed out and power to Busses 18 and 19 restored. The cause of the Bus 18 feeder breaker trip has not yet been determined.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM THE LICENSEE (OSELAND) TO NRC (HUFFMAN) AT 0312 EST ON 3/28/05 * * *
The licensee stated that the Alternate Decay Heat Removal pumps from Unit 2 remained in service so that all decay heat removal was not lost. The Unit 1 primary coolant system temperature increase during the 45 minute duration of this event was approximately 1 degree. R3DO (Kozak) has been notified.