Event Notification Report for February 28, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/27/2012 - 02/28/2012
Power Reactor
Event Number: 47707
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JOSEPH STODOLA
HQ OPS Officer: VINCE KLCO
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: JOSEPH STODOLA
HQ OPS Officer: VINCE KLCO
Notification Date: 02/28/2012
Notification Time: 17:59 [ET]
Event Date: 02/28/2012
Event Time: 15:44 [CST]
Last Update Date: 02/28/2012
Notification Time: 17:59 [ET]
Event Date: 02/28/2012
Event Time: 15:44 [CST]
Last Update Date: 02/28/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION RELATED TO CERTAIN POSTULATED FIRE CONDITIONS
"At 1544 CST on February 28. 2012, it was identified that under certain fire conditions, the ability to meet the performance criteria of the approved Fire Protection Program may be challenged. Specifically the cabling within the Dedicated Fire Zone may be affected under certain fire conditions resulting in fire induced spurious operation of valves RC-46 (pressurizer/reactor head vent), PR-33A (pressurizer head vent) and RC-45A (reactor head vent). The ability to maintain pressurizer level within the indicated range may be challenged due to these spurious valve openings during these postulated conditions.
"Contingency actions per the Fire Protection Program to address the fire in the area of concern have been established (hourly fire watch). This condition is reported pursuant to 10CFR50.72 (b)(3)(ii)(B).
"Similar conditions have been previously reported by the licensee in EN #44482 and EN #47686. The compensatory measures that had been put in place for those earlier conditions remain applicable to this current condition."
The licensee notified the NRC Resident Inspector
"At 1544 CST on February 28. 2012, it was identified that under certain fire conditions, the ability to meet the performance criteria of the approved Fire Protection Program may be challenged. Specifically the cabling within the Dedicated Fire Zone may be affected under certain fire conditions resulting in fire induced spurious operation of valves RC-46 (pressurizer/reactor head vent), PR-33A (pressurizer head vent) and RC-45A (reactor head vent). The ability to maintain pressurizer level within the indicated range may be challenged due to these spurious valve openings during these postulated conditions.
"Contingency actions per the Fire Protection Program to address the fire in the area of concern have been established (hourly fire watch). This condition is reported pursuant to 10CFR50.72 (b)(3)(ii)(B).
"Similar conditions have been previously reported by the licensee in EN #44482 and EN #47686. The compensatory measures that had been put in place for those earlier conditions remain applicable to this current condition."
The licensee notified the NRC Resident Inspector
Power Reactor
Event Number: 47708
Facility: BYRON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS COTE
HQ OPS Officer: CHARLES TEAL
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS COTE
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/28/2012
Notification Time: 19:03 [ET]
Event Date: 02/28/2012
Event Time: 17:31 [CST]
Last Update Date: 02/29/2012
Notification Time: 19:03 [ET]
Event Date: 02/28/2012
Event Time: 17:31 [CST]
Last Update Date: 02/29/2012
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANN MARIE STONE (R3DO)
SAMSON LEE (NRR)
CYNTHIA PEDERSON (R3RA)
BRUCE BOGER (NRR)
SCOTT MORRIS (IRD)
ANN MARIE STONE (R3DO)
SAMSON LEE (NRR)
CYNTHIA PEDERSON (R3RA)
BRUCE BOGER (NRR)
SCOTT MORRIS (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 99 | Power Operation |
UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER
Byron Unit 1 declared an Unusual Event due to a loss of offsite power for greater than 15 minutes (EAL MU-1). The 1A and 1B emergency diesel generators auto-started and automatically restored power to ESF (Engineered Safety Feature) Busses 141 and 142. The 1A Auxiliary Feedwater pump auto-started due to an undervoltage signal to ESF bus 141. The 6.9 KV Busses (Non-ESF) and 4.16 KV Busses (Non-ESF) auto transferred to the Unit Auxiliary Transformers and Unit 1 remained online. The ESF reserve feed breakers are available and in the process of transferring ESF loads over to Unit 2 via the ESF cross-ties. This will allow shutdown of the 1A and 1B diesel-generators and allow alignment to standby status. Switchyard repairs are being initiated.
The licensee notified the State of Illinois, Ogle County, Oregon and Byron municipalities and the NRC Resident Inspector. The licensee plans on issuing a news release. Unit 2 remained online and was unaffected throughout the event.
Notified Nuclear SSA and NICC vie email.
* * * UPDATE FROM CHRISTOPHER COTE TO CHARLES TEAL ON 2/29/12 AT 2222 EST * * *
"Termination of Unusual Event. Repairs to switchyard components are complete. Offsite power has been restored to Unit One System Auxiliary Transformers. Unit One 4 KV ESF busses have been re-energized from Unit One System Auxiliary Transformers and are no longer cross tied to Unit Two System Auxiliary Transformers. This restores the normal electrical lineup to the ESF busses. The entry conditions for MU-1 are no longer met."
The licensee has notified the NRC Resident Inspector, the State of Illinois, Ogle County, Oregon and Byron municipalities.
Notified R3DO (Stone), NRR EO (Lee), IRD (Morris), and other FEDS (DHS SWO, DHS NICC, FEMA, and NuclearSSA via email).
Byron Unit 1 declared an Unusual Event due to a loss of offsite power for greater than 15 minutes (EAL MU-1). The 1A and 1B emergency diesel generators auto-started and automatically restored power to ESF (Engineered Safety Feature) Busses 141 and 142. The 1A Auxiliary Feedwater pump auto-started due to an undervoltage signal to ESF bus 141. The 6.9 KV Busses (Non-ESF) and 4.16 KV Busses (Non-ESF) auto transferred to the Unit Auxiliary Transformers and Unit 1 remained online. The ESF reserve feed breakers are available and in the process of transferring ESF loads over to Unit 2 via the ESF cross-ties. This will allow shutdown of the 1A and 1B diesel-generators and allow alignment to standby status. Switchyard repairs are being initiated.
The licensee notified the State of Illinois, Ogle County, Oregon and Byron municipalities and the NRC Resident Inspector. The licensee plans on issuing a news release. Unit 2 remained online and was unaffected throughout the event.
Notified Nuclear SSA and NICC vie email.
* * * UPDATE FROM CHRISTOPHER COTE TO CHARLES TEAL ON 2/29/12 AT 2222 EST * * *
"Termination of Unusual Event. Repairs to switchyard components are complete. Offsite power has been restored to Unit One System Auxiliary Transformers. Unit One 4 KV ESF busses have been re-energized from Unit One System Auxiliary Transformers and are no longer cross tied to Unit Two System Auxiliary Transformers. This restores the normal electrical lineup to the ESF busses. The entry conditions for MU-1 are no longer met."
The licensee has notified the NRC Resident Inspector, the State of Illinois, Ogle County, Oregon and Byron municipalities.
Notified R3DO (Stone), NRR EO (Lee), IRD (Morris), and other FEDS (DHS SWO, DHS NICC, FEMA, and NuclearSSA via email).