Event Notification Report for January 09, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/08/2019 - 01/09/2019
EVENT NUMBERS
53819
Power Reactor
Event Number: 53819
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DAN GEERLINGS
HQ OPS Officer: KARL DIEDERICH
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DAN GEERLINGS
HQ OPS Officer: KARL DIEDERICH
Notification Date: 01/09/2019
Notification Time: 13:23 [ET]
Event Date: 01/09/2019
Event Time: 10:34 [EST]
Last Update Date: 01/09/2019
Notification Time: 13:23 [ET]
Event Date: 01/09/2019
Event Time: 10:34 [EST]
Last Update Date: 01/09/2019
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):
DAVID HILLS (R3DO)
DAVID HILLS (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP FROM FULL POWER DUE TO RPS TESTING
"At 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing.
"All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve.
"This condition has no impact to the health and safety of the public."
The licensee notified the NRC Resident Inspector.
"At 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing.
"All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve.
"This condition has no impact to the health and safety of the public."
The licensee notified the NRC Resident Inspector.