Event Notification Report for March 24, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/23/2019 - 03/24/2019
Power Reactor
Event Number: 53953
Facility: HATCH
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RUSSELL LEWIS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RUSSELL LEWIS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/24/2019
Notification Time: 05:23 [ET]
Event Date: 03/24/2019
Event Time: 01:59 [EDT]
Last Update Date: 03/24/2019
Notification Time: 05:23 [ET]
Event Date: 03/24/2019
Event Time: 01:59 [EDT]
Last Update Date: 03/24/2019
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):
JONATHAN MONTGOMERY (R2DO)
JONATHAN MONTGOMERY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 25 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO DEGRADING CONDENSER VACUUM
"At 0159 [EDT], with Unit 2 in Mode 1 at 25 percent power, the reactor was manually tripped due to degrading condenser vacuum. After the turbine was tripped, the station service electrical buses did not transfer to alternate supply resulting in loss of the condensate feedwater system and level being controlled by the RCIC system.
"Operators responded and stabilized the plant. Reactor water level is being maintained via the RCIC system.
"Pressure is being controlled and decay heat is being removed by the HPCI system in pressure control mode. Unit 1 is not affected.
"Additionally, an actuation of the primary containment isolation system occurred during the reactor scram. The reason for the actuation was a group II isolation signal was received on reactor water level and a group I isolation was received on decreasing vacuum.
"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). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation 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."
"At 0159 [EDT], with Unit 2 in Mode 1 at 25 percent power, the reactor was manually tripped due to degrading condenser vacuum. After the turbine was tripped, the station service electrical buses did not transfer to alternate supply resulting in loss of the condensate feedwater system and level being controlled by the RCIC system.
"Operators responded and stabilized the plant. Reactor water level is being maintained via the RCIC system.
"Pressure is being controlled and decay heat is being removed by the HPCI system in pressure control mode. Unit 1 is not affected.
"Additionally, an actuation of the primary containment isolation system occurred during the reactor scram. The reason for the actuation was a group II isolation signal was received on reactor water level and a group I isolation was received on decreasing vacuum.
"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). Additionally, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation 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."
Power Reactor
Event Number: 53954
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN DIGNAM
HQ OPS Officer: OSSY FONT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: JOHN DIGNAM
HQ OPS Officer: OSSY FONT
Notification Date: 03/24/2019
Notification Time: 17:40 [ET]
Event Date: 03/24/2019
Event Time: 14:45 [EDT]
Last Update Date: 03/24/2019
Notification Time: 17:40 [ET]
Event Date: 03/24/2019
Event Time: 14:45 [EDT]
Last Update Date: 03/24/2019
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):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 96 | Power Operation | 0 | Hot Standby |
REACTOR AUTOMATIC TRIP ON TURBINE TRIP
"On March 24, 2019, at 1445 EDT, Indian Point Unit 2 automatically tripped on a turbine trip due to a loss of excitation. All control rods fully inserted and plant equipment responded normally to the unit trip. This RPS [reactor protection system] actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B).
"The auxiliary feedwater system actuated following the automatic trip as expected. This specified system actuation is reportable under 10 CFR 50.72(b)(3)(iv)(A). During the event offsite power remained available and stable. No primary or secondary reliefs lifted. Unit 2 is in Mode 3 at normal operating temperature and pressure. Decay heat removal is via the steam generators to the atmospheric steam dumps. No radiation was released.
"Indian Point Unit 3 was unaffected by this event and remains defueled in a scheduled refueling outage.
"A post trip investigation is in progress.
"The licensee has notified the NRC Resident Inspector"
The New York State Public Service Commission, Consolidated Edison System Operator, and New York State Independent System Operator were also notified.
"On March 24, 2019, at 1445 EDT, Indian Point Unit 2 automatically tripped on a turbine trip due to a loss of excitation. All control rods fully inserted and plant equipment responded normally to the unit trip. This RPS [reactor protection system] actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B).
"The auxiliary feedwater system actuated following the automatic trip as expected. This specified system actuation is reportable under 10 CFR 50.72(b)(3)(iv)(A). During the event offsite power remained available and stable. No primary or secondary reliefs lifted. Unit 2 is in Mode 3 at normal operating temperature and pressure. Decay heat removal is via the steam generators to the atmospheric steam dumps. No radiation was released.
"Indian Point Unit 3 was unaffected by this event and remains defueled in a scheduled refueling outage.
"A post trip investigation is in progress.
"The licensee has notified the NRC Resident Inspector"
The New York State Public Service Commission, Consolidated Edison System Operator, and New York State Independent System Operator were also notified.