Event Notification Report for July 04, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/03/2022 - 07/04/2022
Power Reactor
Event Number: 55975
Facility: Quad Cities
Region: 3 State: IL
Unit: [2] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: Mike Maclennan
HQ OPS Officer: Donald Norwood
Region: 3 State: IL
Unit: [2] [] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: Mike Maclennan
HQ OPS Officer: Donald Norwood
Notification Date: 07/04/2022
Notification Time: 05:57 [ET]
Event Date: 07/04/2022
Event Time: 01:04 [CDT]
Last Update Date: 07/04/2022
Notification Time: 05:57 [ET]
Event Date: 07/04/2022
Event Time: 01:04 [CDT]
Last Update Date: 07/04/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Hanna, John (R3DO)
Hanna, John (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR MANUAL SCRAM DUE TO LOWERING REACTOR WATER LEVEL
The following information was received from the licensee via facsimile:
"On July 4, 2022 at 0104 CDT, with Unit 2 in Mode 1 at 100 percent power, a manual scram was inserted on U2 due to lowering reactor water level, which occurred following an unexpected closure of the 2A Feedwater Regulating Valve. Following the reactor scram, reactor water level decreased to approximately minus 16 inches, which resulted in an automatic Group II and Group III isolation (expected response). Following the scram, reactor water level rose to plus 75 inches resulting in a trip of all three Reactor Feedwater Pumps. At 0114 CDT, Reactor Water Level lowered to less than the Feedwater Pump High Level Trip setpoint and the 2C Reactor Feedwater Pump was restarted. Reactor Water Level control has been established in a normal band. The cause and details of the event are under investigation.
"The Unit 2 scram was not complicated. Operations responded using the Emergency Operating Procedure and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.
"Unit 1 was unaffected by the event and remains at 100 percent power.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee will notify the Illinois Emergency Management Agency.
The following information was received from the licensee via facsimile:
"On July 4, 2022 at 0104 CDT, with Unit 2 in Mode 1 at 100 percent power, a manual scram was inserted on U2 due to lowering reactor water level, which occurred following an unexpected closure of the 2A Feedwater Regulating Valve. Following the reactor scram, reactor water level decreased to approximately minus 16 inches, which resulted in an automatic Group II and Group III isolation (expected response). Following the scram, reactor water level rose to plus 75 inches resulting in a trip of all three Reactor Feedwater Pumps. At 0114 CDT, Reactor Water Level lowered to less than the Feedwater Pump High Level Trip setpoint and the 2C Reactor Feedwater Pump was restarted. Reactor Water Level control has been established in a normal band. The cause and details of the event are under investigation.
"The Unit 2 scram was not complicated. Operations responded using the Emergency Operating Procedure and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.
"Unit 1 was unaffected by the event and remains at 100 percent power.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee will notify the Illinois Emergency Management Agency.
Power Reactor
Event Number: 55976
Facility: Quad Cities
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: Craig Vroman
HQ OPS Officer: Donald Norwood
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: Craig Vroman
HQ OPS Officer: Donald Norwood
Notification Date: 07/04/2022
Notification Time: 09:53 [ET]
Event Date: 07/04/2022
Event Time: 01:30 [CDT]
Last Update Date: 07/04/2022
Notification Time: 09:53 [ET]
Event Date: 07/04/2022
Event Time: 01:30 [CDT]
Last Update Date: 07/04/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Hanna, John (R3DO)
Hanna, John (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 |
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
BOTH TRAINS OF STANDBY GAS TREATMENT INOPERABLE
The following information was received from the licensee via email:
"At 0130 CDT on July 4 2022, it was discovered both trains of Standby Gas Treatment System were simultaneously inoperable due to failure to reach required flow rates. Both trains were capable of starting but failed to reach the required flow of 4000 SCFM. Secondary Containment differential pressure was not able to be maintained at greater than or equal to 0.25 inches of vacuum water gauge, causing Secondary Containment to also be inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following information was received from the licensee via email:
"At 0130 CDT on July 4 2022, it was discovered both trains of Standby Gas Treatment System were simultaneously inoperable due to failure to reach required flow rates. Both trains were capable of starting but failed to reach the required flow of 4000 SCFM. Secondary Containment differential pressure was not able to be maintained at greater than or equal to 0.25 inches of vacuum water gauge, causing Secondary Containment to also be inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."