Event Notification Report for July 19, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/18/2019 - 07/19/2019
EVENT NUMBERS
54175
Power Reactor
Event Number: 54175
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNY MCKAY
HQ OPS Officer: RICHARD SMITH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNY MCKAY
HQ OPS Officer: RICHARD SMITH
Notification Date: 07/19/2019
Notification Time: 13:05 [ET]
Event Date: 07/19/2019
Event Time: 09:45 [EDT]
Last Update Date: 07/19/2019
Notification Time: 13:05 [ET]
Event Date: 07/19/2019
Event Time: 09:45 [EDT]
Last Update Date: 07/19/2019
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 MAIN STEAM ISOLATION VALVE FAILING SHUT
"At 0945 [EDT] on July 19, 2019, with Unit 2 in Mode 1 and 100 percent power, the reactor automatically tripped due to Loop 2 'B' Main Steam Isolation Valve failing shut. The Auxiliary Feedwater system (AFW) started automatically as a result of the automatic reactor trip. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.
"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). Due to the valid AFW actuation from the reactor trip, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"Unit 1 was not affected.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspectors have been notified."
All control rods fully inserted.
"At 0945 [EDT] on July 19, 2019, with Unit 2 in Mode 1 and 100 percent power, the reactor automatically tripped due to Loop 2 'B' Main Steam Isolation Valve failing shut. The Auxiliary Feedwater system (AFW) started automatically as a result of the automatic reactor trip. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.
"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). Due to the valid AFW actuation from the reactor trip, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"Unit 1 was not affected.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspectors have been notified."
All control rods fully inserted.