Event Notification Report for April 23, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/22/2022 - 04/23/2022
Power Reactor
Event Number: 55856
Facility: Catawba
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Wil Fowler
HQ OPS Officer: Thomas Herrity
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Wil Fowler
HQ OPS Officer: Thomas Herrity
Notification Date: 04/23/2022
Notification Time: 06:04 [ET]
Event Date: 04/23/2022
Event Time: 02:24 [EDT]
Last Update Date: 04/23/2022
Notification Time: 06:04 [ET]
Event Date: 04/23/2022
Event Time: 02:24 [EDT]
Last Update Date: 04/23/2022
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 (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DURING CONTROL ROD TESTING
The following information was provided by the licensee via fax or email:
"On April 23, 2022, at 0224 [EDT] hours, with Unit 2 in Mode 1 at 100 percent power, two control rods dropped during control rod testing resulting in misalignment, which required a manual reactor trip in accordance with plant procedure. All safety systems functioned as expected. The Auxiliary Feedwater system actuated as designed to provide makeup flow to the steam generators. Operations responded and stabilized the plant. Decay heat is being removed by the steam generator power operated relief valves. 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 automatic start of the Auxiliary Feedwater system is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The cause of the dropped rods is being investigated. Unit 1 is not affected.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Electrical power is in normal off-site arrangement. All emergency electrical supplies are available.
The following information was provided by the licensee via fax or email:
"On April 23, 2022, at 0224 [EDT] hours, with Unit 2 in Mode 1 at 100 percent power, two control rods dropped during control rod testing resulting in misalignment, which required a manual reactor trip in accordance with plant procedure. All safety systems functioned as expected. The Auxiliary Feedwater system actuated as designed to provide makeup flow to the steam generators. Operations responded and stabilized the plant. Decay heat is being removed by the steam generator power operated relief valves. 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 automatic start of the Auxiliary Feedwater system is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A). The cause of the dropped rods is being investigated. Unit 1 is not affected.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Electrical power is in normal off-site arrangement. All emergency electrical supplies are available.
Power Reactor
Event Number: 55857
Facility: Byron
Region: 3 State: IL
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Bryan Lykkebak
HQ OPS Officer: Kerby Scales
Region: 3 State: IL
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Bryan Lykkebak
HQ OPS Officer: Kerby Scales
Notification Date: 04/23/2022
Notification Time: 16:27 [ET]
Event Date: 04/23/2022
Event Time: 08:54 [CDT]
Last Update Date: 04/29/2022
Notification Time: 16:27 [ET]
Event Date: 04/23/2022
Event Time: 08:54 [CDT]
Last Update Date: 04/29/2022
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):
Pelke, Patricia (R3DO)
Pelke, Patricia (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
EN Revision Imported Date: 5/2/2022
EN Revision Text: ULTRASONIC EXAMINATION RESULTS - REACTOR VESSEL HEAD PENETRATION
The following information was provided by the licensee via email:
"At 0854 [CDT] on April 23, 2022, while performing volumetric inspections required by ASME Code Case N-729-6, a rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) was identified. The indication is located inboard of the J-groove weld and is OD-initiated [outer diameter - initiated]. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The repair is scheduled during the refueling outage.
* * * UPDATE ON 04/29/22 AT 1112 EDT FROM BRYAN LYKKEBAK TO OSSY FONT * * *
The following information was provided by the licensee via telephone and email:
"The rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) initiated on the outside diameter (OD) of the nozzle in an area that was not surface stress mitigated (peened). The indication was found to be acceptable for continued operation under CFR and ASME requirements and will not be repaired during this outage.
"The licensee notified the NRC Resident Inspector."
Notified R3DO (Ziolkowski).
EN Revision Text: ULTRASONIC EXAMINATION RESULTS - REACTOR VESSEL HEAD PENETRATION
The following information was provided by the licensee via email:
"At 0854 [CDT] on April 23, 2022, while performing volumetric inspections required by ASME Code Case N-729-6, a rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) was identified. The indication is located inboard of the J-groove weld and is OD-initiated [outer diameter - initiated]. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The repair is scheduled during the refueling outage.
* * * UPDATE ON 04/29/22 AT 1112 EDT FROM BRYAN LYKKEBAK TO OSSY FONT * * *
The following information was provided by the licensee via telephone and email:
"The rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) initiated on the outside diameter (OD) of the nozzle in an area that was not surface stress mitigated (peened). The indication was found to be acceptable for continued operation under CFR and ASME requirements and will not be repaired during this outage.
"The licensee notified the NRC Resident Inspector."
Notified R3DO (Ziolkowski).