Event Notification Report for August 11, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/10/2019 - 08/11/2019
Power Reactor
Event Number: 54211
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PETER HARSH
HQ OPS Officer: JEFF HERRERA
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PETER HARSH
HQ OPS Officer: JEFF HERRERA
Notification Date: 08/11/2019
Notification Time: 11:40 [ET]
Event Date: 08/11/2019
Event Time: 08:14 [EDT]
Last Update Date: 08/11/2019
Notification Time: 11:40 [ET]
Event Date: 08/11/2019
Event Time: 08:14 [EDT]
Last Update Date: 08/11/2019
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):
DAN SCHROEDER (R1DO)
DAN SCHROEDER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 83 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO FEEDWATER REGULATING VALVE MALFUNCTION
"At 0814 EDT on 8/11/19, with Unit 2 at 83 percent power during a planned load reduction, the reactor was manually tripped due to degraded feedwater flow control to the 23 Steam Generator caused by a malfunction of the associated Feedwater Regulating Valve, 23BF19. The trip was not complex, with all systems responding normally post trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System.
"Due to the actuation of 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). This event is also being reported as an eight-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The licensee notified the State of New Jersey.
Unit 1 remains at 100 percent power.
"At 0814 EDT on 8/11/19, with Unit 2 at 83 percent power during a planned load reduction, the reactor was manually tripped due to degraded feedwater flow control to the 23 Steam Generator caused by a malfunction of the associated Feedwater Regulating Valve, 23BF19. The trip was not complex, with all systems responding normally post trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System.
"Due to the actuation of 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). This event is also being reported as an eight-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The licensee notified the State of New Jersey.
Unit 1 remains at 100 percent power.
Power Reactor
Event Number: 54212
Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH RHODES
HQ OPS Officer: BETHANY CECERE
Region: 2 State: SC
Unit: [2] [] []
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH RHODES
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/11/2019
Notification Time: 12:14 [ET]
Event Date: 08/11/2019
Event Time: 08:40 [EDT]
Last Update Date: 08/11/2019
Notification Time: 12:14 [ET]
Event Date: 08/11/2019
Event Time: 08:40 [EDT]
Last Update Date: 08/11/2019
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):
GERALD MCCOY (R2DO)
GERALD MCCOY (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 DUE TO TURBINE TRIP
"At 0840 EDT, on August 11, 2019, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post trip. Because of the reactor trip, the Auxiliary Feedwater (AFW) System actuated as expected due to low water levels in the steam generators. The AFW pumps started as designed when the valid system actuation was received.
"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.
"Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an 8-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the RPS and AFW.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The site remains in a normal electrical lineup.
"At 0840 EDT, on August 11, 2019, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post trip. Because of the reactor trip, the Auxiliary Feedwater (AFW) System actuated as expected due to low water levels in the steam generators. The AFW pumps started as designed when the valid system actuation was received.
"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves.
"Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a 4-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an 8-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the RPS and AFW.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The site remains in a normal electrical lineup.