Event Notification Report for September 26, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/25/2018 - 09/26/2018
EVENT NUMBERS
53623536245362553626
Power Reactor
Event Number: 53623
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PATRICK SELZER
HQ OPS Officer: VINCE KLCO
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: PATRICK SELZER
HQ OPS Officer: VINCE KLCO
Notification Date: 09/26/2018
Notification Time: 15:10 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018
Notification Time: 15:10 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018
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):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 98 | Power Operation | 98 | Power Operation |
UNDERVOLTAGE CONDITION INITIATES AN AUTOMATIC START OF THE DIESEL GENERATOR
"At 0946 CDT on 9/26/2018, a disruption in power to the offsite 138 kV line and the subsequent trip of the Emergency Reserve Auxiliary Transformer (ERAT) Static VAR Compensator (SVC) resulted in a degraded voltage signal on the Division 1- 4.16 kV safety bus. The degraded voltage signal resulted in a trip of the ERAT feed to the bus, blocking closure of the 345 kV Reserve Auxiliary Transformer (RAT) feed to the bus and auto start of the Division 1 Emergency Diesel Generator (EDG). The Division 1 EDG successfully started and re-energized the Division 1- 4.16 kV bus as designed. The unit is stable with the Division 1 EDG carrying the Division 1- 4.16 kV bus.
"The Ameren Transmission System Operator in St. Louis, MO informed the station that they had received a report that a 138 kV to 13.8 kV transformer at Clinton Route 54 substation was on fire and the South feed to the Tabor substation cycled as a result of this fault.
"The NRC Resident Inspector and Illinois Emergency Management Agency Resident Inspector have been notified."
"At 0946 CDT on 9/26/2018, a disruption in power to the offsite 138 kV line and the subsequent trip of the Emergency Reserve Auxiliary Transformer (ERAT) Static VAR Compensator (SVC) resulted in a degraded voltage signal on the Division 1- 4.16 kV safety bus. The degraded voltage signal resulted in a trip of the ERAT feed to the bus, blocking closure of the 345 kV Reserve Auxiliary Transformer (RAT) feed to the bus and auto start of the Division 1 Emergency Diesel Generator (EDG). The Division 1 EDG successfully started and re-energized the Division 1- 4.16 kV bus as designed. The unit is stable with the Division 1 EDG carrying the Division 1- 4.16 kV bus.
"The Ameren Transmission System Operator in St. Louis, MO informed the station that they had received a report that a 138 kV to 13.8 kV transformer at Clinton Route 54 substation was on fire and the South feed to the Tabor substation cycled as a result of this fault.
"The NRC Resident Inspector and Illinois Emergency Management Agency Resident Inspector have been notified."
Fuel Cycle Facility
Event Number: 53624
Facility: NUCLEAR FUEL SERVICES INC.
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: KENNETH GREER
HQ OPS Officer: OSSY FONT
Region: 2 State: TN
Unit: [] [] []
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
NRC Notified By: KENNETH GREER
HQ OPS Officer: OSSY FONT
Notification Date: 09/26/2018
Notification Time: 16:29 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018
Notification Time: 16:29 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
NICOLE COOVERT (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
FFD GROUP (EMAIL)
FUELS OUO (EMAIL)
NICOLE COOVERT (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
FFD GROUP (EMAIL)
FUELS OUO (EMAIL)
FITNESS FOR DUTY - DISCOVERY OF KOMBUCHA TEA INSIDE THE PROTECTED AREA
"An unopened (sealed) container of Herbal Tea (Kombucha) was found in a refrigerator located within a common office break area inside the protected area. Kombucha Tea is a fermented tea, which contains at least 0.5 percent alcohol by volume. Alcohol is a prohibited item per the requirements of 10 CFR Part 26.719(1).
"The incident was entered into the NFS corrective action program and an investigation is in progress
"The licensee notified the NRC Resident Inspector."
NFS Event (PIRCS) Number: 67184.
"An unopened (sealed) container of Herbal Tea (Kombucha) was found in a refrigerator located within a common office break area inside the protected area. Kombucha Tea is a fermented tea, which contains at least 0.5 percent alcohol by volume. Alcohol is a prohibited item per the requirements of 10 CFR Part 26.719(1).
"The incident was entered into the NFS corrective action program and an investigation is in progress
"The licensee notified the NRC Resident Inspector."
NFS Event (PIRCS) Number: 67184.
Power Reactor
Event Number: 53625
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: LAURA MYERS
HQ OPS Officer: VINCE KLCO
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: LAURA MYERS
HQ OPS Officer: VINCE KLCO
Notification Date: 09/26/2018
Notification Time: 21:43 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018
Notification Time: 21:43 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
FRANK ARNER (R1DO)
FRANK ARNER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE CORE INJECTION (HPCI) SYSTEM INOPERABLE
"On 9/26/2018 at 1530 EDT, it was discovered that the HPCI system was inoperable due to a blown fuse in the 10C617 Panel, E21-F15A. Therefore, this condition Is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The blown fuse also impacts 'A' channel Residual Heat Removal (RHR) subsystem and 'A' Core Spray (CS) subsystem. These Emergency Core Cooling subsystems have been declared inoperable. Remaining Emergency Core Cooling subsystems and the Reactor Core Isolation Cooling (RCIC) system remain OPERABLE.
"There was no impact on the health and safety of the public or plant personnel."
The licensee notified the NRC Resident Inspector and will notify the local authorities.
"On 9/26/2018 at 1530 EDT, it was discovered that the HPCI system was inoperable due to a blown fuse in the 10C617 Panel, E21-F15A. Therefore, this condition Is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The blown fuse also impacts 'A' channel Residual Heat Removal (RHR) subsystem and 'A' Core Spray (CS) subsystem. These Emergency Core Cooling subsystems have been declared inoperable. Remaining Emergency Core Cooling subsystems and the Reactor Core Isolation Cooling (RCIC) system remain OPERABLE.
"There was no impact on the health and safety of the public or plant personnel."
The licensee notified the NRC Resident Inspector and will notify the local authorities.
Power Reactor
Event Number: 53626
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MATT SEELEY
HQ OPS Officer: VINCE KLCO
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: MATT SEELEY
HQ OPS Officer: VINCE KLCO
Notification Date: 09/26/2018
Notification Time: 23:25 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018
Notification Time: 23:25 [ET]
Event Date: 09/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/26/2018
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):
LAURA KOZAK (R3DO)
LAURA KOZAK (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC SCRAM DUE TO GENERATOR OUTPUT BREAKER TRIP
"On September 26, 2018 at 1908 CDT. an automatic scram was received on U1 following main generator 345 kV output breaker 7-8 trip with 345 kV output breaker 6-7 already opened for maintenance on line 0401. Following the reactor scram, reactor water level decreased to approximately minus 15 inches, which resulted in automatic Group II and Group Ill isolations (expected response). Reactor pressure rose to approximately 1083 psig, and the 3B and 3C low set relief valves opened briefly to control reactor pressure. Reactor water level and reactor pressure have been restored to their normal bands. All systems responded properly to the event. Unit 1 remains in Mode 3, with reactor pressure being controlled on the turbine bypass valves. The cause and details of the event are under investigation.
"Unit 2 was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
All control rods inserted. Decay heat is being removed via the main condenser.
The licensee notified the NRC Resident Inspector.
"On September 26, 2018 at 1908 CDT. an automatic scram was received on U1 following main generator 345 kV output breaker 7-8 trip with 345 kV output breaker 6-7 already opened for maintenance on line 0401. Following the reactor scram, reactor water level decreased to approximately minus 15 inches, which resulted in automatic Group II and Group Ill isolations (expected response). Reactor pressure rose to approximately 1083 psig, and the 3B and 3C low set relief valves opened briefly to control reactor pressure. Reactor water level and reactor pressure have been restored to their normal bands. All systems responded properly to the event. Unit 1 remains in Mode 3, with reactor pressure being controlled on the turbine bypass valves. The cause and details of the event are under investigation.
"Unit 2 was unaffected by the event and remains at 100% power.
"This report is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."
All control rods inserted. Decay heat is being removed via the main condenser.
The licensee notified the NRC Resident Inspector.