Event Notification Report for October 08, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/07/2024 - 10/08/2024
Agreement State
Event Number: 57368
Rep Org: Texas Dept of State Health Services
Licensee: Bayport Polymers LLC
Region: 4
City: Pasadena State: TX
County:
License #: L06922
Agreement: Y
Docket:
NRC Notified By: Art Tucker
HQ OPS Officer: Brian P. Smith
Licensee: Bayport Polymers LLC
Region: 4
City: Pasadena State: TX
County:
License #: L06922
Agreement: Y
Docket:
NRC Notified By: Art Tucker
HQ OPS Officer: Brian P. Smith
Notification Date: 10/08/2024
Notification Time: 11:53 [ET]
Event Date: 10/08/2024
Event Time: 00:00 [CDT]
Last Update Date: 10/09/2024
Notification Time: 11:53 [ET]
Event Date: 10/08/2024
Event Time: 00:00 [CDT]
Last Update Date: 10/09/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - STUCK OPEN SHUTTER
The following report was received via phone and email from the Texas Department of State Health Services (the Department):
"On October 8, 2024, the Department was notified by the licensee that the shutter on a Vega model SH-F2 nuclear gauge containing a 200 millicurie [source] (original activity) was stuck in the open position. Open is the normal operation position of the shutter. The licensee reported there is no risk of additional radiation exposure to members of the general public or radiation workers due to this on/off mechanism failure. The licensee reported that the current plan is to dispose of the source. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: 10133
Texas NMED Number: TX240033
The following report was received via phone and email from the Texas Department of State Health Services (the Department):
"On October 8, 2024, the Department was notified by the licensee that the shutter on a Vega model SH-F2 nuclear gauge containing a 200 millicurie [source] (original activity) was stuck in the open position. Open is the normal operation position of the shutter. The licensee reported there is no risk of additional radiation exposure to members of the general public or radiation workers due to this on/off mechanism failure. The licensee reported that the current plan is to dispose of the source. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: 10133
Texas NMED Number: TX240033
Power Reactor
Event Number: 57369
Facility: Arkansas Nuclear
Region: 4 State: AR
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Keith Duke
HQ OPS Officer: Brian P. Smith
Region: 4 State: AR
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Keith Duke
HQ OPS Officer: Brian P. Smith
Notification Date: 10/08/2024
Notification Time: 18:12 [ET]
Event Date: 10/08/2024
Event Time: 14:31 [CDT]
Last Update Date: 10/08/2024
Notification Time: 18:12 [ET]
Event Date: 10/08/2024
Event Time: 14:31 [CDT]
Last Update Date: 10/08/2024
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):
Gaddy, Vincent (R4DO)
Gaddy, Vincent (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Defueled |
DEGRADED CONDITION
The following information was provided by the licensee via phone and email:
"At 1431 CDT, on October 8, 2024, Arkansas Nuclear One, Unit 2 (ANO-2) completed the analysis related to an indication revealed on head penetration '71' during reactor vessel closure head inspections. It was determined that the indication is not acceptable under the American Society of Mechanical Engineers (ASME) code requirements. The indication displays characteristics of abnormal degradation of a barrier that requires taking corrective actions to ensure the barriers capability. No leak path signal was identified during ultrasonic testing or bare metal visual inspections.
"The plant was in cold shutdown at zero percent power and defueled for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. 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. This is the only indication that is currently present; however, if additional indications are found, they will also be repaired prior to the plant startup.
"The NRC Senior Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 1431 CDT, on October 8, 2024, Arkansas Nuclear One, Unit 2 (ANO-2) completed the analysis related to an indication revealed on head penetration '71' during reactor vessel closure head inspections. It was determined that the indication is not acceptable under the American Society of Mechanical Engineers (ASME) code requirements. The indication displays characteristics of abnormal degradation of a barrier that requires taking corrective actions to ensure the barriers capability. No leak path signal was identified during ultrasonic testing or bare metal visual inspections.
"The plant was in cold shutdown at zero percent power and defueled for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. 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. This is the only indication that is currently present; however, if additional indications are found, they will also be repaired prior to the plant startup.
"The NRC Senior Resident Inspector has been notified."
Part 21
Event Number: 57370
Rep Org: North Anna Power Station
Licensee: North Anna Power Station
Region: 2
City: Mineral State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Robert Page
HQ OPS Officer: Kerby Scales
Licensee: North Anna Power Station
Region: 2
City: Mineral State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Robert Page
HQ OPS Officer: Kerby Scales
Notification Date: 10/09/2024
Notification Time: 17:07 [ET]
Event Date: 10/08/2024
Event Time: 17:53 [EDT]
Last Update Date: 10/09/2024
Notification Time: 17:07 [ET]
Event Date: 10/08/2024
Event Time: 17:53 [EDT]
Last Update Date: 10/09/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Suber, Gregory (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Suber, Gregory (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
PART 21 - DEGRADED VOLTAGE DUE TO A LOOSE TERMINAL CONNECTION SCREW
The following information was provided by the licensee via phone and email:
"This is a non-emergency notification submitted in accordance with 10 CFR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 20 days.
"On October 8, 2024, North Anna Power Station (NAPS) determined a manufacturing defect affecting the normal AC supply molded case switch for the Unit 1, 1-IV battery charger was reportable under Part 21. On July 29, 2024, the 1-IV battery charger was declared inoperable due to the AC input voltage reading approximately 250 VAC on the B-C phases and A-C phases. The A-B phase voltage was normal at 480 VAC. Troubleshooting determined the normal AC supply molded case switch was the cause of the degraded voltage due to a loose terminal connection screw on the 'C' phase load side of the contacts.
"The NRC Senior Resident Inspector has been notified."
Battery Manufacturer: Ametek Solidstate Solutions
Switch Manufacturer / Model: Eaton / J250K
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee plans to inspect all battery chargers on both units to verify they don't have loose terminal screws. They are unaware of this issue affecting any other site.
The following information was provided by the licensee via phone and email:
"This is a non-emergency notification submitted in accordance with 10 CFR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 20 days.
"On October 8, 2024, North Anna Power Station (NAPS) determined a manufacturing defect affecting the normal AC supply molded case switch for the Unit 1, 1-IV battery charger was reportable under Part 21. On July 29, 2024, the 1-IV battery charger was declared inoperable due to the AC input voltage reading approximately 250 VAC on the B-C phases and A-C phases. The A-B phase voltage was normal at 480 VAC. Troubleshooting determined the normal AC supply molded case switch was the cause of the degraded voltage due to a loose terminal connection screw on the 'C' phase load side of the contacts.
"The NRC Senior Resident Inspector has been notified."
Battery Manufacturer: Ametek Solidstate Solutions
Switch Manufacturer / Model: Eaton / J250K
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee plans to inspect all battery chargers on both units to verify they don't have loose terminal screws. They are unaware of this issue affecting any other site.