Event Notification Report for June 27, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/26/2023 - 06/27/2023
Power Reactor
Event Number: 56592
Facility: Sequoyah
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Christopher Blackwell
HQ OPS Officer: Ernest West
Region: 2 State: TN
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Christopher Blackwell
HQ OPS Officer: Ernest West
Notification Date: 06/27/2023
Notification Time: 11:52 [ET]
Event Date: 06/27/2023
Event Time: 08:31 [EDT]
Last Update Date: 06/27/2023
Notification Time: 11:52 [ET]
Event Date: 06/27/2023
Event Time: 08:31 [EDT]
Last Update Date: 06/27/2023
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):
Suggs, LaDonna (R2DO)
Suggs, LaDonna (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 6/29/2023
EN Revision Text: OFFSITE NOTIFICATION
The following information was provided by the licensee via phone and email:
"At 0831 [EDT] on June 27, 2023, Sequoyah Nuclear Plant reported an oil discharge into the plant intake located on the Tennessee River to the [Department of Transportation] National Response Center (report number 1371356). The source of oil was from a broken hydraulic hose from equipment in use on the intake. This oil spill is minor and did not exceed 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."
EN Revision Text: OFFSITE NOTIFICATION
The following information was provided by the licensee via phone and email:
"At 0831 [EDT] on June 27, 2023, Sequoyah Nuclear Plant reported an oil discharge into the plant intake located on the Tennessee River to the [Department of Transportation] National Response Center (report number 1371356). The source of oil was from a broken hydraulic hose from equipment in use on the intake. This oil spill is minor and did not exceed 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."
Power Reactor
Event Number: 56593
Facility: Watts Bar
Region: 2 State: TN
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Paul Blakely
HQ OPS Officer: Ernest West
Region: 2 State: TN
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Paul Blakely
HQ OPS Officer: Ernest West
Notification Date: 06/27/2023
Notification Time: 19:04 [ET]
Event Date: 06/27/2023
Event Time: 16:26 [EDT]
Last Update Date: 06/27/2023
Notification Time: 19:04 [ET]
Event Date: 06/27/2023
Event Time: 16:26 [EDT]
Last Update Date: 06/27/2023
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):
Suggs, LaDonna (R2DO)
Suggs, LaDonna (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 6/29/2023
EN Revision Text: AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1626 EDT, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The [reactor] trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed using the auxiliary feedwater and steam dump systems. Unit 1 is not affected.
"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). 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).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"All control rods are fully inserted. The cause of the turbine trip is being investigated."
EN Revision Text: AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 1626 EDT, with Unit 2 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The [reactor] trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed using the auxiliary feedwater and steam dump systems. Unit 1 is not affected.
"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). 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).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"All control rods are fully inserted. The cause of the turbine trip is being investigated."