Event Notification Report for May 29, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/28/2020 - 05/29/2020
EVENT NUMBERS
54731
Power Reactor
Event Number: 54731
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Jack Connolly
HQ OPS Officer: Brian P. Smith
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Jack Connolly
HQ OPS Officer: Brian P. Smith
Notification Date: 05/29/2020
Notification Time: 16:41 [ET]
Event Date: 05/29/2020
Event Time: 14:03 [EDT]
Last Update Date: 05/29/2020
Notification Time: 16:41 [ET]
Event Date: 05/29/2020
Event Time: 14:03 [EDT]
Last Update Date: 05/29/2020
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):
JOSEPH DEBOER (R1DO)
JOSEPH DEBOER (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 TRIP DUE TO ROD BANK UNEXPECTEDLY INSERTING
"At 1403 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' unexpectedly inserting. All systems responded normally post-trip. Operations stabilized the plant in Mode 3 at 557 degrees Fahrenheit. 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 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified."
"At 1403 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' unexpectedly inserting. All systems responded normally post-trip. Operations stabilized the plant in Mode 3 at 557 degrees Fahrenheit. 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 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified."