Event Notification Report for August 22, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/21/2018 - 08/22/2018
Power Reactor
Event Number: 53557
Facility: WATTS BAR
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BAKER
HQ OPS Officer: BETHANY CECERE
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BAKER
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/22/2018
Notification Time: 11:23 [ET]
Event Date: 08/22/2018
Event Time: 09:43 [EDT]
Last Update Date: 08/22/2018
Notification Time: 11:23 [ET]
Event Date: 08/22/2018
Event Time: 09:43 [EDT]
Last Update Date: 08/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
"At 0943 EDT on August 22, 2018, the Watts Bar Unit 2 reactor automatically tripped while operating at 100 percent power. All control and shutdown bank rods inserted properly in response to the automatic reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems.
"The reactor automatically tripped due to a main turbine trip signal. An investigation is in progress.
"The automatic actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50.72 (b)(2)(iv)(B).
"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"The NRC Senior Resident Inspector has been notified for this event."
"At 0943 EDT on August 22, 2018, the Watts Bar Unit 2 reactor automatically tripped while operating at 100 percent power. All control and shutdown bank rods inserted properly in response to the automatic reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems.
"The reactor automatically tripped due to a main turbine trip signal. An investigation is in progress.
"The automatic actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50.72 (b)(2)(iv)(B).
"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"The NRC Senior Resident Inspector has been notified for this event."
Power Reactor
Event Number: 53558
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: CHRIS BENNETT
HQ OPS Officer: OSSY FONT
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: CHRIS BENNETT
HQ OPS Officer: OSSY FONT
Notification Date: 08/22/2018
Notification Time: 19:35 [ET]
Event Date: 08/22/2018
Event Time: 18:03 [CDT]
Last Update Date: 08/22/2018
Notification Time: 19:35 [ET]
Event Date: 08/22/2018
Event Time: 18:03 [CDT]
Last Update Date: 08/22/2018
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):
BRIAN BONSER (R2DO)
CATHY HANEY (RII RA)
BRIAN MCDERMOTT (ET RX)
WILLIAM GOTT (IRD)
BRIAN BONSER (R2DO)
CATHY HANEY (RII RA)
BRIAN MCDERMOTT (ET RX)
WILLIAM GOTT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 79 | Power Operation | 79 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO FIRE
"On 08/22/2018 at 1803 hours CDT, Browns Ferry Nuclear Plant declared an Unusual Event per EAL HU4, a fire potentially degrading the level of safety of the plant.
"At 1748 CDT Unit 1 received a call reporting smoke coming from the 480V Condensate Demineralizer Panel 3 in the Unit 3 turbine building elevation 557'. At approximately 1803 [CDT], the incident commander on the scene confirmed a fire inside the panel and all three units entered 0-AOI-26-1, Fire Response. The board was subsequently de-energized by operations personnel and the fire was extinguished at 1806 CDT. SM [Shift Manager] exited EAL HU4 and all three units exited 0-AOI-26-1 at 1840 CDT.
"Fire operations remain on scene to monitor. A team is being assembled for damage assessment and recovery.
"The fire did not affect any safety systems, no plant transients resulted, and no injuries were reported.
"This event is reportable within 1 hour IAW 10 CFR 50.72(a)(1)(i).
"The NRC Resident inspector has been notified."
Notified DHS SWO, FEMA Ops, DHS NICC, FEMA NWC (email) and NuclearSSA (email).
"On 08/22/2018 at 1803 hours CDT, Browns Ferry Nuclear Plant declared an Unusual Event per EAL HU4, a fire potentially degrading the level of safety of the plant.
"At 1748 CDT Unit 1 received a call reporting smoke coming from the 480V Condensate Demineralizer Panel 3 in the Unit 3 turbine building elevation 557'. At approximately 1803 [CDT], the incident commander on the scene confirmed a fire inside the panel and all three units entered 0-AOI-26-1, Fire Response. The board was subsequently de-energized by operations personnel and the fire was extinguished at 1806 CDT. SM [Shift Manager] exited EAL HU4 and all three units exited 0-AOI-26-1 at 1840 CDT.
"Fire operations remain on scene to monitor. A team is being assembled for damage assessment and recovery.
"The fire did not affect any safety systems, no plant transients resulted, and no injuries were reported.
"This event is reportable within 1 hour IAW 10 CFR 50.72(a)(1)(i).
"The NRC Resident inspector has been notified."
Notified DHS SWO, FEMA Ops, DHS NICC, FEMA NWC (email) and NuclearSSA (email).