Event Notification Report for May 30, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/29/2011 - 05/30/2011
Power Reactor
Event Number: 46905
Facility: SURRY
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: THOMAS OLIVER
HQ OPS Officer: JOE O'HARA
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: THOMAS OLIVER
HQ OPS Officer: JOE O'HARA
Notification Date: 05/30/2011
Notification Time: 14:59 [ET]
Event Date: 05/30/2011
Event Time: 08:08 [EDT]
Last Update Date: 05/30/2011
Notification Time: 14:59 [ET]
Event Date: 05/30/2011
Event Time: 08:08 [EDT]
Last Update Date: 05/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Intermediate Shutdown | 0 | Intermediate Shutdown |
SPECIFIED SYSTEM ACTUATION - AFW INITIATION
"Surry Unit 2 is in Intermediate Shutdown and was supplying steam generators with a main feed pump. The second main feed pump is tagged out for maintenance. The running main feed pump exhibited a low oil flow condition. The operating team took the deliberate action to secure the running main feed pump to prevent bearing damage with the knowledge that an Auxiliary Feedwater actuation signal would be generated. The plant was realigned to flow to the steam generators with the condensate pumps and the auxiliary feed pumps were then secured [at] 0821.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(iv)(A) for 8-hour notification of automatic actuation of AFW. Plant responded as expected. The NRC Resident Inspector has been notified of this event and is on site.
"There were no radiation releases due to this event, nor were there any personnel injuries or contamination events."
Offsite power is normal and emergency diesel generators are operable and available. There was no increase in plant risk as a result of this event.
"Surry Unit 2 is in Intermediate Shutdown and was supplying steam generators with a main feed pump. The second main feed pump is tagged out for maintenance. The running main feed pump exhibited a low oil flow condition. The operating team took the deliberate action to secure the running main feed pump to prevent bearing damage with the knowledge that an Auxiliary Feedwater actuation signal would be generated. The plant was realigned to flow to the steam generators with the condensate pumps and the auxiliary feed pumps were then secured [at] 0821.
"This notification is being made pursuant to 10 CFR 50.72(b)(3)(iv)(A) for 8-hour notification of automatic actuation of AFW. Plant responded as expected. The NRC Resident Inspector has been notified of this event and is on site.
"There were no radiation releases due to this event, nor were there any personnel injuries or contamination events."
Offsite power is normal and emergency diesel generators are operable and available. There was no increase in plant risk as a result of this event.
Power Reactor
Event Number: 46906
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: JOE O'HARA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PAUL MARVEL
HQ OPS Officer: JOE O'HARA
Notification Date: 05/30/2011
Notification Time: 15:46 [ET]
Event Date: 05/30/2011
Event Time: 11:50 [EDT]
Last Update Date: 05/30/2011
Notification Time: 15:46 [ET]
Event Date: 05/30/2011
Event Time: 11:50 [EDT]
Last Update Date: 05/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GLENN DENTEL (R1DO)
GLENN DENTEL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Startup | 0 | Hot Shutdown |
SPECIFIED SYSTEM ACTUATION - MANUAL REACTOR SCRAM DUE TO DUAL RECIRC PUMP TRIP DURING STARTUP
"Limerick Unit 2 was 'manually scrammed' from 0% power on 5/30/11 at 1150 hours in accordance with plant procedure OT-112 'Recirculation Pump Trip', when both the '2A' and '2B' Recirculation Pumps tripped. The cause of the pump trip is currently under investigation at this time.
"At the time of the 'manual' SCRAM: The Reactor Mode Switch was in 'Startup' Mode 2. All control rods were inserted to 'full-in' position (00). Reactor Shutdown was in-progress in accordance with Plant procedure GP-3 'Normal Plant Shutdown'. No primary or secondary containment isolations occurred.
"The plant is currently in HOT SHUTDOWN maintaining normal Reactor level with Control Rod Drive (CRD) hydraulic and Reactor Water Cleanup (RWCU) systems."
Licensee is investigating a potential issue with the relay logic associated with the scram bypass feature. Offsite power circuits and emergency diesel generators are operable and available. There was no increase in plant risk associated with this event.
The NRC Resident Inspector has been notified.
"Limerick Unit 2 was 'manually scrammed' from 0% power on 5/30/11 at 1150 hours in accordance with plant procedure OT-112 'Recirculation Pump Trip', when both the '2A' and '2B' Recirculation Pumps tripped. The cause of the pump trip is currently under investigation at this time.
"At the time of the 'manual' SCRAM: The Reactor Mode Switch was in 'Startup' Mode 2. All control rods were inserted to 'full-in' position (00). Reactor Shutdown was in-progress in accordance with Plant procedure GP-3 'Normal Plant Shutdown'. No primary or secondary containment isolations occurred.
"The plant is currently in HOT SHUTDOWN maintaining normal Reactor level with Control Rod Drive (CRD) hydraulic and Reactor Water Cleanup (RWCU) systems."
Licensee is investigating a potential issue with the relay logic associated with the scram bypass feature. Offsite power circuits and emergency diesel generators are operable and available. There was no increase in plant risk associated with this event.
The NRC Resident Inspector has been notified.