Event Notification Report for March 30, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/29/2019 - 03/30/2019
Power Reactor
Event Number: 53966
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRIAN MOSCHET
HQ OPS Officer: THOMAS KENDZIA
Region: 2 State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRIAN MOSCHET
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 03/30/2019
Notification Time: 21:06 [ET]
Event Date: 03/30/2019
Event Time: 17:47 [EDT]
Last Update Date: 03/30/2019
Notification Time: 21:06 [ET]
Event Date: 03/30/2019
Event Time: 17:47 [EDT]
Last Update Date: 03/30/2019
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):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 23 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM AND SPECIFIED SYSTEM ACTUATION
"At 17:47 Eastern Daylight Time (EDT) on March 30, 2019, with Unit 2 in Mode 1 at approximately 23 percent reactor power and main turbine startup in progress coming out of a refuel outage, a high temperature was sensed at main turbine bearing #9. As a result of and to arrest the high temperature condition, the main control room inserted a manual reactor scram.
"All control rods inserted as expected during the scram. When the scram was inserted, reactor water level dropped below the Low Level 1 actuation setpoint. 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 main control room manually closed all Main Steam Isolation Valves (MSIVs), in anticipation of a low vacuum prior to the Group 1 automatic closure signal being received. High Pressure Coolant Injection (HPCI) was aligned for pressure control and Reactor Coolant Isolation System (RCIC) was aligned for level control. The Reactor Coolant Sample Line Isolation valves closed as expected on low main condenser vacuum.
"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."
At the time of notification, decay heat was being removed by the condenser through one open MSIV and a feedwater pump running.
"At 17:47 Eastern Daylight Time (EDT) on March 30, 2019, with Unit 2 in Mode 1 at approximately 23 percent reactor power and main turbine startup in progress coming out of a refuel outage, a high temperature was sensed at main turbine bearing #9. As a result of and to arrest the high temperature condition, the main control room inserted a manual reactor scram.
"All control rods inserted as expected during the scram. When the scram was inserted, reactor water level dropped below the Low Level 1 actuation setpoint. 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 main control room manually closed all Main Steam Isolation Valves (MSIVs), in anticipation of a low vacuum prior to the Group 1 automatic closure signal being received. High Pressure Coolant Injection (HPCI) was aligned for pressure control and Reactor Coolant Isolation System (RCIC) was aligned for level control. The Reactor Coolant Sample Line Isolation valves closed as expected on low main condenser vacuum.
"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."
At the time of notification, decay heat was being removed by the condenser through one open MSIV and a feedwater pump running.
Power Reactor
Event Number: 53967
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNY MCKAY
HQ OPS Officer: CATY NOLAN
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNY MCKAY
HQ OPS Officer: CATY NOLAN
Notification Date: 03/31/2019
Notification Time: 00:17 [ET]
Event Date: 03/30/2019
Event Time: 21:30 [EDT]
Last Update Date: 03/31/2019
Notification Time: 00:17 [ET]
Event Date: 03/30/2019
Event Time: 21:30 [EDT]
Last Update Date: 03/31/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 30 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO MSIV FAILING CLOSED
"At 2130 [EDT] on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.
"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"Unit 1 was not affected.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspectors have been notified."
"At 2130 [EDT] on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.
"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).
"Unit 1 was not affected.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspectors have been notified."