Event Notification Report for June 08, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/07/2020 - 06/08/2020
Power Reactor
Event Number: 54742
Facility: Summer
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Nick Okimosh
HQ OPS Officer: Howie Crouch
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Nick Okimosh
HQ OPS Officer: Howie Crouch
Notification Date: 06/08/2020
Notification Time: 18:52 [ET]
Event Date: 06/08/2020
Event Time: 13:55 [EDT]
Last Update Date: 06/08/2020
Notification Time: 18:52 [ET]
Event Date: 06/08/2020
Event Time: 13:55 [EDT]
Last Update Date: 06/08/2020
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):
MARK MILLER (R2DO)
MARK MILLER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION - TRANSMISSION FLUID SPILL
"At 1725 EDT on 6/8/2020, V.C. Summer Nuclear Station reported a transmission fluid spill to the South Carolina Department of Health and Environmental Control. The spill was the result of a hydraulic hose leak during equipment testing. This spill did not violate any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The spill resulted in 1 - 2 ounces of transmission fluid being released into the Monticello Reservoir."
"At 1725 EDT on 6/8/2020, V.C. Summer Nuclear Station reported a transmission fluid spill to the South Carolina Department of Health and Environmental Control. The spill was the result of a hydraulic hose leak during equipment testing. This spill did not violate any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The spill resulted in 1 - 2 ounces of transmission fluid being released into the Monticello Reservoir."
Power Reactor
Event Number: 54820
Facility: Peach Bottom
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Dan Dullum
HQ OPS Officer: Andrew Waugh
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: Dan Dullum
HQ OPS Officer: Andrew Waugh
Notification Date: 08/06/2020
Notification Time: 13:10 [ET]
Event Date: 06/08/2020
Event Time: 04:24 [EDT]
Last Update Date: 08/06/2020
Notification Time: 13:10 [ET]
Event Date: 06/08/2020
Event Time: 04:24 [EDT]
Last Update Date: 08/06/2020
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
FRANK ARNER (R1DO)
FRANK ARNER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
INVALID SPECIFIED SYSTEM ACTUATION
"This report is being made as required by 10 CFR 50.73(a)(2)(iv)(A) to describe an automatic actuation of containment isolation valves in more than one system. Because the actuation was invalid, this 60-day telephone notification is being made instead of a written LER [licensee event report], in accordance with 10 CFR 50.73(a)(1).
"On 06/08/2020, at approximately 0424 EDT, a trip of the Unit 3 'A' reactor protection system (RPS) MG-Set resulted in a partial activation of the primary containment isolation system and inboard containment isolation valves closed in multiple systems. All affected Group III containment isolation valves were verified to be closed. It was determined that the normal power supply for the Unit 3 'A' RPS had failed. Power was transferred from the normal to the alternate source and the RPS 'A' channel was reset.
"Investigation determined that the 3A RPS MG Set motor contactor coil winding had failed due to an internal short circuit. The motor contactor has been replaced.
"The containment isolation was not due to actual plant conditions or parameters meeting design criteria for containment isolation. Therefore, this is considered to be an invalid actuation.
"The NRC Resident Inspector has been informed of this notification."
"This report is being made as required by 10 CFR 50.73(a)(2)(iv)(A) to describe an automatic actuation of containment isolation valves in more than one system. Because the actuation was invalid, this 60-day telephone notification is being made instead of a written LER [licensee event report], in accordance with 10 CFR 50.73(a)(1).
"On 06/08/2020, at approximately 0424 EDT, a trip of the Unit 3 'A' reactor protection system (RPS) MG-Set resulted in a partial activation of the primary containment isolation system and inboard containment isolation valves closed in multiple systems. All affected Group III containment isolation valves were verified to be closed. It was determined that the normal power supply for the Unit 3 'A' RPS had failed. Power was transferred from the normal to the alternate source and the RPS 'A' channel was reset.
"Investigation determined that the 3A RPS MG Set motor contactor coil winding had failed due to an internal short circuit. The motor contactor has been replaced.
"The containment isolation was not due to actual plant conditions or parameters meeting design criteria for containment isolation. Therefore, this is considered to be an invalid actuation.
"The NRC Resident Inspector has been informed of this notification."