Event Notification Report for April 21, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/20/2019 - 04/21/2019
Power Reactor
Event Number: 54015
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICHARD WAGNER
HQ OPS Officer: JEFF HERRERA
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICHARD WAGNER
HQ OPS Officer: JEFF HERRERA
Notification Date: 04/21/2019
Notification Time: 12:43 [ET]
Event Date: 04/21/2019
Event Time: 09:20 [EDT]
Last Update Date: 04/21/2019
Notification Time: 12:43 [ET]
Event Date: 04/21/2019
Event Time: 09:20 [EDT]
Last Update Date: 04/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BRICE BICKETT (R1DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR EO)
BRICE BICKETT (R1DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR EO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
LIMERICK ONSITE NON-WORK RELATED FATALITY
"Event of Public Interest performed to notify State and Local agencies for emergency vehicle response required due to an on-site non-work related illness. The individual was unresponsive and was unable to be resuscitated due to the medical issue. The individual was outside the Radiological Controlled Area (RCA) and no radioactive material or contamination was involved."
The NRC Resident Inspector was notified.
"Event of Public Interest performed to notify State and Local agencies for emergency vehicle response required due to an on-site non-work related illness. The individual was unresponsive and was unable to be resuscitated due to the medical issue. The individual was outside the Radiological Controlled Area (RCA) and no radioactive material or contamination was involved."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 54016
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALAN SCHULTZ
HQ OPS Officer: JEFFREY WHITED
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALAN SCHULTZ
HQ OPS Officer: JEFFREY WHITED
Notification Date: 04/22/2019
Notification Time: 01:51 [ET]
Event Date: 04/21/2019
Event Time: 23:07 [EDT]
Last Update Date: 04/22/2019
Notification Time: 01:51 [ET]
Event Date: 04/21/2019
Event Time: 23:07 [EDT]
Last Update Date: 04/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 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)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
FRANK EHRHARDT (R2DO)
FRANK EHRHARDT (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR TRIP AND SPECIFIED SYSTEM ACTUATION
"At 2307 EDT on April 21, 2019, in Mode 1 at approximately 100 percent reactor power, Unit 1 automatically tripped due to a Main Turbine Trip. The Main Turbine Trip was a result of two out of three level instruments sensing a false high reactor water level. All control rods inserted as expected during the scram. Safety Relief Valves G and K lifted per design. The same level instruments that failed also tripped both Reactor Feed Pumps. As a result, reactor water level dropped below the Low Level 1 and 2 actuation setpoints. Per design, the Low Level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. The Low Level 2 signals resulted in Group 3 (i.e. Reactor Water Cleanup) isolation, a secondary containment isolation signal, and an auto start of Standby Gas Treatment and Control Room Emergency Ventilation. Also, the Low Level 2 resulted in [high pressure coolant injection] HPCI and [reactor core isolation cooling system] RCIC automatically starting and injecting into the vessel.
"All systems responded as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for RPS actuation and 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Decay heat is currently being removed via the turbine bypass valves. Condensate and feed water are maintaining water level. The reactor is still at saturation temperature and 475 psi, lowering slowly. The reactor is still in a normal electrical lineup.
There was no impact to Unit 2 as a result of this event.
* * * UPDATE ON 04/22/19 AT 0220 EDT FROM ALAN SCHULTZ TO JEFFREY WHITED * * *
The licensee updated the event report to include a 4-Hr Non-Emergency Notification in accordance with 10 CFR 50.72(b)(2)(iv)(A) for Emergency Core Cooling System, HPCI, Discharge to the Reactor Coolant System.
Notified R2DO (Dickson), NRR EO (Miller) and IR MOC (Gott).
"At 2307 EDT on April 21, 2019, in Mode 1 at approximately 100 percent reactor power, Unit 1 automatically tripped due to a Main Turbine Trip. The Main Turbine Trip was a result of two out of three level instruments sensing a false high reactor water level. All control rods inserted as expected during the scram. Safety Relief Valves G and K lifted per design. The same level instruments that failed also tripped both Reactor Feed Pumps. As a result, reactor water level dropped below the Low Level 1 and 2 actuation setpoints. Per design, the Low Level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. The Low Level 2 signals resulted in Group 3 (i.e. Reactor Water Cleanup) isolation, a secondary containment isolation signal, and an auto start of Standby Gas Treatment and Control Room Emergency Ventilation. Also, the Low Level 2 resulted in [high pressure coolant injection] HPCI and [reactor core isolation cooling system] RCIC automatically starting and injecting into the vessel.
"All systems responded as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for RPS actuation and 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Decay heat is currently being removed via the turbine bypass valves. Condensate and feed water are maintaining water level. The reactor is still at saturation temperature and 475 psi, lowering slowly. The reactor is still in a normal electrical lineup.
There was no impact to Unit 2 as a result of this event.
* * * UPDATE ON 04/22/19 AT 0220 EDT FROM ALAN SCHULTZ TO JEFFREY WHITED * * *
The licensee updated the event report to include a 4-Hr Non-Emergency Notification in accordance with 10 CFR 50.72(b)(2)(iv)(A) for Emergency Core Cooling System, HPCI, Discharge to the Reactor Coolant System.
Notified R2DO (Dickson), NRR EO (Miller) and IR MOC (Gott).