Event Notification Report for June 05, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/04/2023 - 06/05/2023
Fuel Cycle Facility
Event Number: 56550
Facility: Louisiana Energy Services
Region: 2 State: NM
Unit: [] [] []
RX Type:
NRC Notified By: Dirk Lundgren
HQ OPS Officer: Brian P. Smith
Region: 2 State: NM
Unit: [] [] []
RX Type:
NRC Notified By: Dirk Lundgren
HQ OPS Officer: Brian P. Smith
Notification Date: 06/01/2023
Notification Time: 20:16 [ET]
Event Date: 06/01/2023
Event Time: 02:39 [MDT]
Last Update Date: 06/01/2023
Notification Time: 20:16 [ET]
Event Date: 06/01/2023
Event Time: 02:39 [MDT]
Last Update Date: 06/01/2023
Emergency Class: Non Emergency
10 CFR Section:
70.50(b)(2) - Safety Equipment Failure
10 CFR Section:
70.50(b)(2) - Safety Equipment Failure
Person (Organization):
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
PARTIAL LOSS OF CRITICALITY ACCIDENT ALARM SYSTEM
The following information was provided by the licensee via email:
"On June 1, 2023, during inclement weather, a Phase 2 CAAS [Criticality Accident Alarm System] detector fault was received. Troubleshooting efforts indicated two CAAS nodes are impacted and SBM1005 [Process Services Corridor] was evacuated. The affected detectors are located in the north end of the SBM1005 Process Services Corridor. Compensatory measures are implemented in the affected area to support maintenance troubleshooting efforts.
"UUSA is reporting this event per 10 CFR 70.50(b)(2)."
The following information was provided by the licensee via email:
"On June 1, 2023, during inclement weather, a Phase 2 CAAS [Criticality Accident Alarm System] detector fault was received. Troubleshooting efforts indicated two CAAS nodes are impacted and SBM1005 [Process Services Corridor] was evacuated. The affected detectors are located in the north end of the SBM1005 Process Services Corridor. Compensatory measures are implemented in the affected area to support maintenance troubleshooting efforts.
"UUSA is reporting this event per 10 CFR 70.50(b)(2)."
Power Reactor
Event Number: 56551
Facility: Palo Verde
Region: 4 State: AZ
Unit: [2] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Lukas Knight
HQ OPS Officer: Adam Koziol
Region: 4 State: AZ
Unit: [2] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Lukas Knight
HQ OPS Officer: Adam Koziol
Notification Date: 06/02/2023
Notification Time: 10:44 [ET]
Event Date: 06/02/2023
Event Time: 04:05 [MST]
Last Update Date: 06/02/2023
Notification Time: 10:44 [ET]
Event Date: 06/02/2023
Event Time: 04:05 [MST]
Last Update Date: 06/02/2023
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):
Gepford, Heather (R4DO)
Gepford, Heather (R4DO)
| 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 |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via email:
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS [Emergency Notification System] or under the reporting requirements of 10 CFR 50.73.
"At 0405 MDT on June 2, 2023, the Unit 2 reactor automatically tripped on low steam generator water levels due to degraded flow from the A main feedwater pump. Steam generator water levels reached the automatic Auxiliary Feedwater Actuation System (AFAS) setpoint resulting in automatic AFAS-1 and AFAS-2 actuations and subsequent start of both class auxiliary feedwater pumps.
"Steam Generator water levels are being restored to normal band with the class 1E powered motor driven auxiliary feedwater pump.
"Following the reactor trip, all control element assemblies inserted fully into the core. No emergency plan classification was required per the Emergency Plan. Safety related buses remained powered from offsite power during the event and the offsite power grid is stable. Both emergency diesel generators automatically started on the AFAS-1 and AFAS-2 actuations as designed and are currently running unloaded. This event is being reported as a reactor protection system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and a specified system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"The NRC Senior Resident Inspector has been informed. Unit 1 and 3 are in Mode 1 at 100 percent power."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Decay heat is being removed to main condenser via automatic steam bypass and B auxiliary feedwater pump.
The following information was provided by the licensee via email:
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS [Emergency Notification System] or under the reporting requirements of 10 CFR 50.73.
"At 0405 MDT on June 2, 2023, the Unit 2 reactor automatically tripped on low steam generator water levels due to degraded flow from the A main feedwater pump. Steam generator water levels reached the automatic Auxiliary Feedwater Actuation System (AFAS) setpoint resulting in automatic AFAS-1 and AFAS-2 actuations and subsequent start of both class auxiliary feedwater pumps.
"Steam Generator water levels are being restored to normal band with the class 1E powered motor driven auxiliary feedwater pump.
"Following the reactor trip, all control element assemblies inserted fully into the core. No emergency plan classification was required per the Emergency Plan. Safety related buses remained powered from offsite power during the event and the offsite power grid is stable. Both emergency diesel generators automatically started on the AFAS-1 and AFAS-2 actuations as designed and are currently running unloaded. This event is being reported as a reactor protection system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B) and a specified system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A).
"The NRC Senior Resident Inspector has been informed. Unit 1 and 3 are in Mode 1 at 100 percent power."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Decay heat is being removed to main condenser via automatic steam bypass and B auxiliary feedwater pump.
Non-Power Reactor
Event Number: 56553
Rep Org: North Carolina State University (NCSU)
Licensee: North Carolina State University
Region: 0
City: Raleigh State: NC
County: Wake
License #: R-120
Agreement: Y
Docket: 05000297
NRC Notified By: Gerald Wicks
HQ OPS Officer: Brian Lin
Licensee: North Carolina State University
Region: 0
City: Raleigh State: NC
County: Wake
License #: R-120
Agreement: Y
Docket: 05000297
NRC Notified By: Gerald Wicks
HQ OPS Officer: Brian Lin
Notification Date: 06/02/2023
Notification Time: 13:17 [ET]
Event Date: 06/02/2023
Event Time: 08:18 [EDT]
Last Update Date: 06/02/2023
Notification Time: 13:17 [ET]
Event Date: 06/02/2023
Event Time: 08:18 [EDT]
Last Update Date: 06/02/2023
Emergency Class: Non Emergency
10 CFR Section:
10 CFR Section:
Person (Organization):
Duane Hardesty (NRR)
Andy Waugh (NPR COOR)
Duane Hardesty (NRR)
Andy Waugh (NPR COOR)
UNSCHEDULED SHUTDOWN
The following information was provided by the licensee via fax or email:
"An unscheduled shutdown of the reactor occurred on 6/2/23 at 0818 EDT due to an abnormal response of the Safety Power Level channel during the approach to power of 1 MW at 150 kW. The Reactor Operator observed a discrepancy in power indications by the Linear Power Level and Safety Power Level channels and took immediate actions required by procedure NRP-OP-105, Response to SCRAMS, Alarms, and Abnormal Conditions. The reactor was shut down and secured immediately. The Designated Senior Reactor Operator was immediately notified.
"The Safety Power Level channel is required to be operable per Technical Specification 3.3.b Table 3.3-1 while the reactor is being operated. During the startup checklist, the channel performed satisfactorily. The Safety Power Level channel is part of the reactor safety system and has two automatic shutdowns (SCRAMs) associated with it. Reactor power was correctly monitored by all other operable power monitoring channels which have redundant SCRAM capabilities. No SCRAM occurred or was needed due to the power level of the reactor. Following the reactor shutdown, the reactor staff investigated and determined that the high voltage power supply in the Safety Power channel was faulty. The power supply was replaced and a channel calibration of the Safety Power channel will be performed using procedure PS 1-05-03A:S1 to verify the channel is operable. Maintenance Log #0888 has been opened. There was no safety issue with this event. Procedures were followed during reactor operation, shutdown, and the investigation.
"This unscheduled shutdown is a reportable event per TS 6.7.1 based on the circumstances and as defined in the facility Technical Specification (TS 1.2.24.d) for reportable events from operation in violation of Limiting Conditions for Operation (LCO) established in TS. TS 1.2.24.d, does not allow for an exception for taking prompt remedial action.
"A report to the NRC is required within one working day and will be made by 1700 EDT by phone on 6/2/23, as required by TS 6.7.1. Also as required by TS 6.7.1, a written report to the NRC is due in 14 days (6/16/23)."
The following information was provided by the licensee via fax or email:
"An unscheduled shutdown of the reactor occurred on 6/2/23 at 0818 EDT due to an abnormal response of the Safety Power Level channel during the approach to power of 1 MW at 150 kW. The Reactor Operator observed a discrepancy in power indications by the Linear Power Level and Safety Power Level channels and took immediate actions required by procedure NRP-OP-105, Response to SCRAMS, Alarms, and Abnormal Conditions. The reactor was shut down and secured immediately. The Designated Senior Reactor Operator was immediately notified.
"The Safety Power Level channel is required to be operable per Technical Specification 3.3.b Table 3.3-1 while the reactor is being operated. During the startup checklist, the channel performed satisfactorily. The Safety Power Level channel is part of the reactor safety system and has two automatic shutdowns (SCRAMs) associated with it. Reactor power was correctly monitored by all other operable power monitoring channels which have redundant SCRAM capabilities. No SCRAM occurred or was needed due to the power level of the reactor. Following the reactor shutdown, the reactor staff investigated and determined that the high voltage power supply in the Safety Power channel was faulty. The power supply was replaced and a channel calibration of the Safety Power channel will be performed using procedure PS 1-05-03A:S1 to verify the channel is operable. Maintenance Log #0888 has been opened. There was no safety issue with this event. Procedures were followed during reactor operation, shutdown, and the investigation.
"This unscheduled shutdown is a reportable event per TS 6.7.1 based on the circumstances and as defined in the facility Technical Specification (TS 1.2.24.d) for reportable events from operation in violation of Limiting Conditions for Operation (LCO) established in TS. TS 1.2.24.d, does not allow for an exception for taking prompt remedial action.
"A report to the NRC is required within one working day and will be made by 1700 EDT by phone on 6/2/23, as required by TS 6.7.1. Also as required by TS 6.7.1, a written report to the NRC is due in 14 days (6/16/23)."
Power Reactor
Event Number: 56520
Facility: Wolf Creek
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: David Christiansen
HQ OPS Officer: Sam Colvard
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: David Christiansen
HQ OPS Officer: Sam Colvard
Notification Date: 05/16/2023
Notification Time: 17:20 [ET]
Event Date: 05/16/2023
Event Time: 11:27 [CDT]
Last Update Date: 06/05/2023
Notification Time: 17:20 [ET]
Event Date: 05/16/2023
Event Time: 11:27 [CDT]
Last Update Date: 06/05/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Azua, Ray (R4DO)
Azua, Ray (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 6/6/2023
EN Revision Text: EMERGENCY EXHAUST INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1127 CDT on 5/16/2023, during the reperformance of test procedure 'STS PE-006, Charcoal Adsorber In-Place Leak Test' due to a failure from the previous day, both trains of emergency exhaust were rendered inoperable due to incorrect performance of the procedure. Performers incorrectly de-energized the humidity control heating coil for the unit not under test, rendering it inoperable. This issue was identified and rectified at 1138 CDT on 5/16/2023, exiting the LCO [limiting condition of operation] for both trains inoperable at that time. There was no impact to the health and safety of the public."
* * * RETRACTION ON 6/5/2023 AT 1132 EDT FROM JASON KNUST TO HOWIE CROUCH * * *
"The initial failure of the STS PE-006 test was caused by a malfunction of the test equipment which initially injected excessive amounts of tracer gas and caused saturation of the charcoal. Using test equipment sourced from Callaway, and following guidance from the vendor, STS PE-006 test was successfully passed on 5/17/2023. No maintenance or intrusive testing was performed on the unit between initial test failure and satisfactory completion of the test. Because this train of emergency exhaust was not actually inoperable at the time the second train was rendered inoperable due to incorrect procedure performance, there was no loss of safety function. Therefore, this event notification is being retracted."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Gepford).
EN Revision Text: EMERGENCY EXHAUST INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1127 CDT on 5/16/2023, during the reperformance of test procedure 'STS PE-006, Charcoal Adsorber In-Place Leak Test' due to a failure from the previous day, both trains of emergency exhaust were rendered inoperable due to incorrect performance of the procedure. Performers incorrectly de-energized the humidity control heating coil for the unit not under test, rendering it inoperable. This issue was identified and rectified at 1138 CDT on 5/16/2023, exiting the LCO [limiting condition of operation] for both trains inoperable at that time. There was no impact to the health and safety of the public."
* * * RETRACTION ON 6/5/2023 AT 1132 EDT FROM JASON KNUST TO HOWIE CROUCH * * *
"The initial failure of the STS PE-006 test was caused by a malfunction of the test equipment which initially injected excessive amounts of tracer gas and caused saturation of the charcoal. Using test equipment sourced from Callaway, and following guidance from the vendor, STS PE-006 test was successfully passed on 5/17/2023. No maintenance or intrusive testing was performed on the unit between initial test failure and satisfactory completion of the test. Because this train of emergency exhaust was not actually inoperable at the time the second train was rendered inoperable due to incorrect procedure performance, there was no loss of safety function. Therefore, this event notification is being retracted."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Gepford).
Power Reactor
Event Number: 56556
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Andrew Corrette
HQ OPS Officer: Sam Colvard
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Andrew Corrette
HQ OPS Officer: Sam Colvard
Notification Date: 06/05/2023
Notification Time: 17:26 [ET]
Event Date: 06/02/2023
Event Time: 14:30 [EDT]
Last Update Date: 06/05/2023
Notification Time: 17:26 [ET]
Event Date: 06/02/2023
Event Time: 14:30 [EDT]
Last Update Date: 06/05/2023
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Werkheiser, Dave (R1DO)
FFD Group, (EMAIL)
Werkheiser, Dave (R1DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS-FOR-DUTY REPORT
The following information was provided by the licensee via email:
"On June 2, 2023, a blind specimen provided to a laboratory did not analyze as expected. The specimen reported a false negative for amphetamines and a false positive for opiates.
"This event is being reported pursuant to 10 CFR 26.719(c)(2) and 10 CFR 26.719(c)(3).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On June 2, 2023, a blind specimen provided to a laboratory did not analyze as expected. The specimen reported a false negative for amphetamines and a false positive for opiates.
"This event is being reported pursuant to 10 CFR 26.719(c)(2) and 10 CFR 26.719(c)(3).
"The NRC Resident Inspector has been notified."
Part 21
Event Number: 56557
Rep Org: Paragon Energy Solutions
Licensee:
Region: 1
City: York State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Richard Knott
HQ OPS Officer: Sam Colvard
Licensee:
Region: 1
City: York State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Richard Knott
HQ OPS Officer: Sam Colvard
Notification Date: 06/05/2023
Notification Time: 18:25 [ET]
Event Date: 04/05/2023
Event Time: 00:00 [EDT]
Last Update Date: 06/05/2023
Notification Time: 18:25 [ET]
Event Date: 04/05/2023
Event Time: 00:00 [EDT]
Last Update Date: 06/05/2023
Emergency Class: Non Emergency
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
Person (Organization):
Werkheiser, Dave (R1DO)
Part 21/50.55 Reactors, - (EMAIL)
Miller, Mark (R2DO)
Gepford, Heather (R4DO)
Werkheiser, Dave (R1DO)
Part 21/50.55 Reactors, - (EMAIL)
Miller, Mark (R2DO)
Gepford, Heather (R4DO)
PART 21 - RELAY CARD POTENTIAL DEFECT
The following information summary was provided by the licensee via email:
On April 5th, 2023, Duke Catawba Nuclear Station informed Paragon of a failure of a Trane External Auto/Stop and Emergency Stop relay card (Part Number: X13650728-06) in a chiller control system. Analysis of the failed relay card identified minor delamination and water intrusion of the microcontroller chip. Ongoing evaluation is expected to be completed by 7/15/23.
Potential plants affected: Nine Mile Point, Catawba, Riverbend, McGuire.
The following information summary was provided by the licensee via email:
On April 5th, 2023, Duke Catawba Nuclear Station informed Paragon of a failure of a Trane External Auto/Stop and Emergency Stop relay card (Part Number: X13650728-06) in a chiller control system. Analysis of the failed relay card identified minor delamination and water intrusion of the microcontroller chip. Ongoing evaluation is expected to be completed by 7/15/23.
Potential plants affected: Nine Mile Point, Catawba, Riverbend, McGuire.
Power Reactor
Event Number: 56559
Facility: Ginna
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Wade Weber
HQ OPS Officer: Sam Colvard
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Wade Weber
HQ OPS Officer: Sam Colvard
Notification Date: 06/05/2023
Notification Time: 21:58 [ET]
Event Date: 06/05/2023
Event Time: 18:23 [EDT]
Last Update Date: 06/05/2023
Notification Time: 21:58 [ET]
Event Date: 06/05/2023
Event Time: 18:23 [EDT]
Last Update Date: 06/05/2023
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):
Werkheiser, Dave (R1DO)
Werkheiser, Dave (R1DO)
| 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
The following information was provided by the licensee via email:
"At 1823 EDT, the shift manager was notified that one siren, part of the public notification system (siren number 10), spuriously activated for approximately one minute. Monroe County agencies were notified regarding the actuation. The cause of the actuation is being investigated and the ability for the siren to actuate has been removed until the cause is determined. There is no impact to the emergency planning zone.
"This event is a four-hour, non-emergency report for notification to other government agencies in accordance with 10 CFR 50.72(b)(2)(xi)."
The following information was provided by the licensee via email:
"At 1823 EDT, the shift manager was notified that one siren, part of the public notification system (siren number 10), spuriously activated for approximately one minute. Monroe County agencies were notified regarding the actuation. The cause of the actuation is being investigated and the ability for the siren to actuate has been removed until the cause is determined. There is no impact to the emergency planning zone.
"This event is a four-hour, non-emergency report for notification to other government agencies in accordance with 10 CFR 50.72(b)(2)(xi)."