Event Notification Report for December 29, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/28/2018 - 12/29/2018
Power Reactor
Event Number: 54341
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW SLOUKA
HQ OPS Officer: OSSY FONT
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW SLOUKA
HQ OPS Officer: OSSY FONT
Notification Date: 10/21/2019
Notification Time: 15:52 [ET]
Event Date: 12/29/2018
Event Time: 02:20 [CDT]
Last Update Date: 10/21/2019
Notification Time: 15:52 [ET]
Event Date: 12/29/2018
Event Time: 02:20 [CDT]
Last Update Date: 10/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BRADLEY DAVIS (R2DO)
BRADLEY DAVIS (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID ACTUATION OF A SIGNAL AFFECTING MORE THAN ONE SYSTEM
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a general containment isolation signal affecting more than one system. On December 29, 2018, at approximately 0220 Central Standard Time (CST), Browns Ferry Nuclear Plant (BFN), Unit 3 experienced an unexpected loss of power to the 3A Reactor Protection System (RPS) Bus due to the trip of the 3A RPS motor generator (MG) set. This resulted in Primary Containment Isolation System (PCIS) groups 2, 3, 6, and 8 isolations, and initiation of Standby Gas Treatment Trains A, B, and C and Control Room Emergency Ventilation System Train A. All affected safety systems responded as expected.
"This event is being reported as a late 60 day non-emergency notification. This missed notification was identified on August 23, 2019.
"Plant conditions which initiate PCIS Group 2 actuations are Reactor Vessel Low Water Level (Level 3) or High Drywell Pressure. The PCIS Group 3 actuations are initiated by Reactor Vessel Low Water Level (Level 3) or Reactor Water Cleanup Area High Temperature. The PCIS Group 6 actuations are initiated by Reactor Vessel Low Water Level (Level 3), High Drywell Pressure, or Reactor Building Ventilation Exhaust High Radiation (Reactor Zone or Refuel Zone). The PCIS Group 8 actuations are initiated by Low Reactor Vessel Water Level (Level 3) or High Drywell Pressure. At the time of the event, these conditions did not exist; therefore, the actuation of the PCIS was invalid.
"The cause of the trip of the RPS MG Set was a failure of the motor winding insulation of all three phases.
"There were no safety consequences or impact to the health and safety of the public as a result of this event.
"This event was entered into the Corrective Action Program as Condition Reports 1478564 and 1543534.
"The NRC Resident Inspector has been notified of this event."
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of a general containment isolation signal affecting more than one system. On December 29, 2018, at approximately 0220 Central Standard Time (CST), Browns Ferry Nuclear Plant (BFN), Unit 3 experienced an unexpected loss of power to the 3A Reactor Protection System (RPS) Bus due to the trip of the 3A RPS motor generator (MG) set. This resulted in Primary Containment Isolation System (PCIS) groups 2, 3, 6, and 8 isolations, and initiation of Standby Gas Treatment Trains A, B, and C and Control Room Emergency Ventilation System Train A. All affected safety systems responded as expected.
"This event is being reported as a late 60 day non-emergency notification. This missed notification was identified on August 23, 2019.
"Plant conditions which initiate PCIS Group 2 actuations are Reactor Vessel Low Water Level (Level 3) or High Drywell Pressure. The PCIS Group 3 actuations are initiated by Reactor Vessel Low Water Level (Level 3) or Reactor Water Cleanup Area High Temperature. The PCIS Group 6 actuations are initiated by Reactor Vessel Low Water Level (Level 3), High Drywell Pressure, or Reactor Building Ventilation Exhaust High Radiation (Reactor Zone or Refuel Zone). The PCIS Group 8 actuations are initiated by Low Reactor Vessel Water Level (Level 3) or High Drywell Pressure. At the time of the event, these conditions did not exist; therefore, the actuation of the PCIS was invalid.
"The cause of the trip of the RPS MG Set was a failure of the motor winding insulation of all three phases.
"There were no safety consequences or impact to the health and safety of the public as a result of this event.
"This event was entered into the Corrective Action Program as Condition Reports 1478564 and 1543534.
"The NRC Resident Inspector has been notified of this event."
Power Reactor
Event Number: 53809
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: CASEY WOODS
HQ OPS Officer: ANDREW WAUGH
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: CASEY WOODS
HQ OPS Officer: ANDREW WAUGH
Notification Date: 12/29/2018
Notification Time: 10:27 [ET]
Event Date: 12/29/2018
Event Time: 09:04 [CST]
Last Update Date: 12/29/2018
Notification Time: 10:27 [ET]
Event Date: 12/29/2018
Event Time: 09:04 [CST]
Last Update Date: 12/29/2018
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
NICK TAYLOR (R4DO)
WILLIAM GOTT (IRD)
KRISS KENNEDY (R4RA)
HO NIEH (NRR)
NICK TAYLOR (R4DO)
WILLIAM GOTT (IRD)
KRISS KENNEDY (R4RA)
HO NIEH (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
NOTICE OF UNUSUAL EVENT DUE TO TOXIC GAS AND FIRE
At 0904 CST, on December 29, 2018, Cooper declared a Notice of Unusual Event under emergency action level HU 3.1. The emergency declaration was due to a toxic gas asphyxiant as a result of a fire. The fire is contained and the fire brigade continues to extinguishing the fire. Offsite support has not been requested.
The licensee notified the NRC Resident Inspector. Additionally, State and Local government agencies were also notified.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 12/29/2018 AT 1655 EST FROM JIM FLORENCE TO JEFFREY WHITED * * *
At 1544 CST, on December 29, 2018, Cooper terminated the Notice of Unusual Event under emergency action level HU 3.1. The fire was verified to be extinguished and the flammable material was removed. The plant remained at 100% power for the duration of the event.
The licensee issued a press release regarding the event at 1202 CST, on December 29, 2018.
The license notified the NRC Resident Inspector.
Notified R4DO (Taylor), NRR EO (Groom), IRD MOC (Gott), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
At 0904 CST, on December 29, 2018, Cooper declared a Notice of Unusual Event under emergency action level HU 3.1. The emergency declaration was due to a toxic gas asphyxiant as a result of a fire. The fire is contained and the fire brigade continues to extinguishing the fire. Offsite support has not been requested.
The licensee notified the NRC Resident Inspector. Additionally, State and Local government agencies were also notified.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 12/29/2018 AT 1655 EST FROM JIM FLORENCE TO JEFFREY WHITED * * *
At 1544 CST, on December 29, 2018, Cooper terminated the Notice of Unusual Event under emergency action level HU 3.1. The fire was verified to be extinguished and the flammable material was removed. The plant remained at 100% power for the duration of the event.
The licensee issued a press release regarding the event at 1202 CST, on December 29, 2018.
The license notified the NRC Resident Inspector.
Notified R4DO (Taylor), NRR EO (Groom), IRD MOC (Gott), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).