Event Notification Report for November 10, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/09/2018 - 11/10/2018
Power Reactor
Event Number: 53732
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: T. W. GATES
HQ OPS Officer: THOMAS KENDZIA
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: T. W. GATES
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 11/10/2018
Notification Time: 04:35 [ET]
Event Date: 11/10/2018
Event Time: 00:00 [CST]
Last Update Date: 11/10/2018
Notification Time: 04:35 [ET]
Event Date: 11/10/2018
Event Time: 00:00 [CST]
Last Update Date: 11/10/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MARK HAIRE (R4DO)
MARK HAIRE (R4DO)
| 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 SCRAM ON HIGH REACTOR PRESSURE
"At 0046 CST, River Bend Station experienced an automatic reactor scram on high reactor pressure. Initial indications are that the cause of the scram was an uncommanded closure of the #3 turbine control valve.
"The plant is stable with reactor water level in the normal level band of 10-51 inches being maintained with feedwater and condensate. Reactor pressure is in the prescribed band of 500-1090 psig, being maintained with turbine bypass valves and steam line drains.
"No injection systems were actuated either manually or automatically as a result of the event.
"The reactor scrammed on a Reactor Pressure High scram signal. A Reactor Level 3 signal resulted from the normal post-scram water level response. All systems responded as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an automatic RPS actuation with the reactor critical."
All control rods fully inserted. The Unit is in a normal shutdown electrical alignment. All control rods inserted properly and all systems functioned as designed. The licensee is investigating the cause of the event.
The licensee notified the NRC resident inspector.
"At 0046 CST, River Bend Station experienced an automatic reactor scram on high reactor pressure. Initial indications are that the cause of the scram was an uncommanded closure of the #3 turbine control valve.
"The plant is stable with reactor water level in the normal level band of 10-51 inches being maintained with feedwater and condensate. Reactor pressure is in the prescribed band of 500-1090 psig, being maintained with turbine bypass valves and steam line drains.
"No injection systems were actuated either manually or automatically as a result of the event.
"The reactor scrammed on a Reactor Pressure High scram signal. A Reactor Level 3 signal resulted from the normal post-scram water level response. All systems responded as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) as an automatic RPS actuation with the reactor critical."
All control rods fully inserted. The Unit is in a normal shutdown electrical alignment. All control rods inserted properly and all systems functioned as designed. The licensee is investigating the cause of the event.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 53733
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: PAUL E ADAMS
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: PAUL E ADAMS
HQ OPS Officer: DONG HWA PARK
Notification Date: 11/10/2018
Notification Time: 17:48 [ET]
Event Date: 11/10/2018
Event Time: 00:00 [EST]
Last Update Date: 11/10/2018
Notification Time: 17:48 [ET]
Event Date: 11/10/2018
Event Time: 00:00 [EST]
Last Update Date: 11/10/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN HANNA (R3DO)
JOHN HANNA (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
BORIC ACID IDENTIFIED ON REACTOR VESSEL HEAD PENETRATION
"On November 10, 2018, during a planned bare metal visual inspection of the reactor head, boric acid was discovered at a CRDM [Control Rod Drive Mechanism] nozzle to reactor head penetration. Investigation of the source of the boric acid is ongoing. The plant was in cold shutdown at 0% power and Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. All other reactor vessel head penetrations have had a bare metal visual inspection completed with no other indications identified.
"This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier.
"The licensee notified the NRC Senior Resident Inspector."
"On November 10, 2018, during a planned bare metal visual inspection of the reactor head, boric acid was discovered at a CRDM [Control Rod Drive Mechanism] nozzle to reactor head penetration. Investigation of the source of the boric acid is ongoing. The plant was in cold shutdown at 0% power and Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. All other reactor vessel head penetrations have had a bare metal visual inspection completed with no other indications identified.
"This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier.
"The licensee notified the NRC Senior Resident Inspector."