Event Notification Report for March 28, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/27/2019 - 03/28/2019
Power Reactor
Event Number: 53961
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DEREK WATSON
HQ OPS Officer: JEFF HERRERA
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DEREK WATSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 03/28/2019
Notification Time: 15:07 [ET]
Event Date: 03/28/2019
Event Time: 14:50 [EDT]
Last Update Date: 03/29/2019
Notification Time: 15:07 [ET]
Event Date: 03/28/2019
Event Time: 14:50 [EDT]
Last Update Date: 03/29/2019
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
JOEL MUNDAY (R2)
HO NIEH (NRR)
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
JOEL MUNDAY (R2)
HO NIEH (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 58 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO RCS UNIDENTIFIED LEAKAGE
At 1450 EDT on March 28, 2019, the licensee observed that the Unit 1 unidentified Reactor Coolant System (RCS) leakage was greater than 10 gallons per minute (gpm) for greater than or equal to 15 minutes. The licensee declared an Unusual Event in accordance with their EAL SU 5.1. The licensee initiated a unit shutdown in accordance with their procedures and the unit was approximately 58 percent reactor power at 1507 EDT, with unit shutdown in progress. The licensee also received an alarm due to increasing Drywell Pressure at 1.7 pounds drywell pressure.
At 1600 EDT the licensee called with an update. Unit 1 was still in an Unusual Event with the unit at 37 percent power with the shutdown continuing. Drywell Pressure had decreased to 0.8 pounds. At 1603 the licensee scrammed Unit 1.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 3/28/2019 AT 1808 EDT FROM MARK TURKAL TO THOMAS KENDZIA * * *
"At 1437 EDT on March 28, 2019, with Unit 1 in Mode 1 at approximately 100 percent power, a Technical Specification-required shutdown was initiated due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.
"It is expected that the leakage would not have been reduced to within limits within the required Technical Specification
completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 03/29/19 AT 0302 EDT FROM TOM FIENO TO BETHANY CECERE * * *
At 0259 EDT on March 29, 2019, the Unusual Event was terminated because RCS leakage was reduced to less than 10 gallons per minute. The most recent leakage rate measured at 0225 EDT was 3.9 gpm. The source of the leak will be identified when plant conditions allow containment entry. No elevated radiation levels were observed during this event. Drywell pressure is currently 0.0 psig. Unit 1 is in Mode 4.
The licensee notified the NRC Resident Inspector.
Notified R2DO (Bonser), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
At 1450 EDT on March 28, 2019, the licensee observed that the Unit 1 unidentified Reactor Coolant System (RCS) leakage was greater than 10 gallons per minute (gpm) for greater than or equal to 15 minutes. The licensee declared an Unusual Event in accordance with their EAL SU 5.1. The licensee initiated a unit shutdown in accordance with their procedures and the unit was approximately 58 percent reactor power at 1507 EDT, with unit shutdown in progress. The licensee also received an alarm due to increasing Drywell Pressure at 1.7 pounds drywell pressure.
At 1600 EDT the licensee called with an update. Unit 1 was still in an Unusual Event with the unit at 37 percent power with the shutdown continuing. Drywell Pressure had decreased to 0.8 pounds. At 1603 the licensee scrammed Unit 1.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
* * * UPDATE ON 3/28/2019 AT 1808 EDT FROM MARK TURKAL TO THOMAS KENDZIA * * *
"At 1437 EDT on March 28, 2019, with Unit 1 in Mode 1 at approximately 100 percent power, a Technical Specification-required shutdown was initiated due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.
"It is expected that the leakage would not have been reduced to within limits within the required Technical Specification
completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
* * * UPDATE ON 03/29/19 AT 0302 EDT FROM TOM FIENO TO BETHANY CECERE * * *
At 0259 EDT on March 29, 2019, the Unusual Event was terminated because RCS leakage was reduced to less than 10 gallons per minute. The most recent leakage rate measured at 0225 EDT was 3.9 gpm. The source of the leak will be identified when plant conditions allow containment entry. No elevated radiation levels were observed during this event. Drywell pressure is currently 0.0 psig. Unit 1 is in Mode 4.
The licensee notified the NRC Resident Inspector.
Notified R2DO (Bonser), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).
Power Reactor
Event Number: 53962
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: THOMAS FIENO
HQ OPS Officer: ANDREW WAUGH
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: THOMAS FIENO
HQ OPS Officer: ANDREW WAUGH
Notification Date: 03/28/2019
Notification Time: 20:55 [ET]
Event Date: 03/28/2019
Event Time: 16:54 [EDT]
Last Update Date: 03/28/2019
Notification Time: 20:55 [ET]
Event Date: 03/28/2019
Event Time: 16:54 [EDT]
Last Update Date: 03/28/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
AUTOMATIC ACTUATION OF THE PRIMARY CONTAINMENT ISOLATION SYSTEM AND THE REACTOR PROTECTON SYSTEM
"At 1654 EDT on March 28, 2019, with Unit 1 in Mode 3 at 0 percent power, an actuation of the Primary Containment Isolation System occurred, closing the outboard Main Steam Isolation Valves (MSIVs) due to a low condenser vacuum signal. The MSIVs had been manually closed, per procedure, during the shutdown evolution to address drywell leakage. The inboard MSIVs had not been reopened when the isolation occurred.
"Subsequently, at 1658 EDT a Reactor Protection System (RPS) actuation occurred due to reactor water level dropping below the actuation setpoint. All control rods were inserted at the time of the actuation.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System and the Reactor Protection System.
"There was no impact on the health and safety of the public or plant personnel. The safety function of both the MSIVs and the RPS had already been completed at the time of the event.
"The NRC Resident Inspector has been notified."
"At 1654 EDT on March 28, 2019, with Unit 1 in Mode 3 at 0 percent power, an actuation of the Primary Containment Isolation System occurred, closing the outboard Main Steam Isolation Valves (MSIVs) due to a low condenser vacuum signal. The MSIVs had been manually closed, per procedure, during the shutdown evolution to address drywell leakage. The inboard MSIVs had not been reopened when the isolation occurred.
"Subsequently, at 1658 EDT a Reactor Protection System (RPS) actuation occurred due to reactor water level dropping below the actuation setpoint. All control rods were inserted at the time of the actuation.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System and the Reactor Protection System.
"There was no impact on the health and safety of the public or plant personnel. The safety function of both the MSIVs and the RPS had already been completed at the time of the event.
"The NRC Resident Inspector has been notified."