Event Notification Report for June 06, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/05/2020 - 06/06/2020
EVENT NUMBERS
54740
54740
Power Reactor
Event Number: 54740
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Mike Taylor
HQ OPS Officer: Howie Crouch
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Mike Taylor
HQ OPS Officer: Howie Crouch
Notification Date: 06/06/2020
Notification Time: 12:25 [ET]
Event Date: 06/06/2020
Event Time: 09:20 [EDT]
Last Update Date: 06/06/2020
Notification Time: 12:25 [ET]
Event Date: 06/06/2020
Event Time: 09:20 [EDT]
Last Update Date: 06/06/2020
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):
MATT YOUNG (R1DO)
MATT YOUNG (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP WHEN GROUP ONE, BANK 'B' CONTROL RODS INSERTED INTO THE CORE
"At 0920 [EDT], with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT [normal operating pressure and temperature]. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser.
"Emergency feedwater actuated due to low low steam generator level as expected.
"This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)
"The senior NRC Resident Inspector has been notified."
The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient.
The licensee manually tripped eight days ago for the same condition. See EN #54731.
"At 0920 [EDT], with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT [normal operating pressure and temperature]. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser.
"Emergency feedwater actuated due to low low steam generator level as expected.
"This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A)
"The senior NRC Resident Inspector has been notified."
The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient.
The licensee manually tripped eight days ago for the same condition. See EN #54731.