Event Notification Report for May 24, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/23/2021 - 05/24/2021
Fuel Cycle Facility
Event Number: 55276
Facility: American Centrifuge Plant
Region: 2 State: OH
Unit: [] [] []
RX Type: Uranium Enrichment Facility
Comments:
NRC Notified By: Brian Summers
HQ OPS Officer: Jeffrey Whited
Region: 2 State: OH
Unit: [] [] []
RX Type: Uranium Enrichment Facility
Comments:
NRC Notified By: Brian Summers
HQ OPS Officer: Jeffrey Whited
Notification Date: 05/26/2021
Notification Time: 18:10 [ET]
Event Date: 05/24/2021
Event Time: 11:00 [EDT]
Last Update Date: 05/26/2021
Notification Time: 18:10 [ET]
Event Date: 05/24/2021
Event Time: 11:00 [EDT]
Last Update Date: 05/26/2021
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
MILLER, MARK (R2DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
MILLER, MARK (R2DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
EN Revision Imported Date: 6/25/2021
EN Revision Text: REPORT OF OFFSITE NOTIFICATION
"Event meets ACD2-RG-044 App. B N.1 'The licensee shall notify the NRC Operations Center of any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'
"Received preliminary notification from TestAmerica Colorado that there was an exceedance of the Total Suspended Solids NPDES [National Pollution Discharge Elimination System] permit limit at Outfall 013. This was not unexpected with the current state of the settling pond above Outfall 013. An Ohio EPA [OEPA] 24 Hour non-compliance notification form was filled out and sent it to our OEPA NPDES inspector.
"Notification concurrent to the OEPA notification."
EN Revision Text: REPORT OF OFFSITE NOTIFICATION
"Event meets ACD2-RG-044 App. B N.1 'The licensee shall notify the NRC Operations Center of any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made. Such an event may include an on-site fatality or inadvertent release of radioactively contaminated materials.'
"Received preliminary notification from TestAmerica Colorado that there was an exceedance of the Total Suspended Solids NPDES [National Pollution Discharge Elimination System] permit limit at Outfall 013. This was not unexpected with the current state of the settling pond above Outfall 013. An Ohio EPA [OEPA] 24 Hour non-compliance notification form was filled out and sent it to our OEPA NPDES inspector.
"Notification concurrent to the OEPA notification."
Power Reactor
Event Number: 55272
Facility: Sequoyah
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Tim Wood
HQ OPS Officer: Donald Norwood
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Tim Wood
HQ OPS Officer: Donald Norwood
Notification Date: 05/24/2021
Notification Time: 12:01 [ET]
Event Date: 05/24/2021
Event Time: 09:16 [EDT]
Last Update Date: 05/25/2021
Notification Time: 12:01 [ET]
Event Date: 05/24/2021
Event Time: 09:16 [EDT]
Last Update Date: 05/25/2021
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):
MILLER, MARK (R2)
MILLER, MARK (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | N | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 6/25/2021
EN Revision Text: "On 5/24/21 at 0916 EDT, an Automatic Reactor Trip on Unit 1 occurred. All safety systems responded normally and the plant is currently stable in Mode 3 (Hot Standby) at normal operating temperature and pressure. Preliminary indications are that the unit trip was caused by a High Neutron Flux Rate detected by the Power Range Nuclear Instruments. Troubleshooting and investigation are ongoing to determine the initiating cause.
"Unit 2 is not impacted and remains stable in Mode 1 at 100 percent power.
"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) and in accordance with 10 CFR 50.72 (b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
No relief valves opened. All Rods fully inserted. Decay heat is being removed by Auxiliary Feedwater via the steam dumps. The plant is in a normal post-trip electrical line-up.
EN Revision Text: "On 5/24/21 at 0916 EDT, an Automatic Reactor Trip on Unit 1 occurred. All safety systems responded normally and the plant is currently stable in Mode 3 (Hot Standby) at normal operating temperature and pressure. Preliminary indications are that the unit trip was caused by a High Neutron Flux Rate detected by the Power Range Nuclear Instruments. Troubleshooting and investigation are ongoing to determine the initiating cause.
"Unit 2 is not impacted and remains stable in Mode 1 at 100 percent power.
"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) and in accordance with 10 CFR 50.72 (b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
No relief valves opened. All Rods fully inserted. Decay heat is being removed by Auxiliary Feedwater via the steam dumps. The plant is in a normal post-trip electrical line-up.