Event Notification Report for May 09, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/08/2024 - 05/09/2024
Non-Agreement State
Event Number: 57121
Rep Org: Screaming Eagle Coal
Licensee: Screaming Eagle Coal
Region: 1
City: Bickmoore State: WV
County:
License #: 16-35383-01
Agreement: N
Docket:
NRC Notified By: Brandt Elkens
HQ OPS Officer: Brian P. Smith
Licensee: Screaming Eagle Coal
Region: 1
City: Bickmoore State: WV
County:
License #: 16-35383-01
Agreement: N
Docket:
NRC Notified By: Brandt Elkens
HQ OPS Officer: Brian P. Smith
Notification Date: 05/10/2024
Notification Time: 08:15 [ET]
Event Date: 05/09/2024
Event Time: 12:00 [EDT]
Last Update Date: 05/10/2024
Notification Time: 08:15 [ET]
Event Date: 05/09/2024
Event Time: 12:00 [EDT]
Last Update Date: 05/10/2024
Emergency Class: Non Emergency
10 CFR Section:
30.50(b)(2) - Safety Equipment Failure
10 CFR Section:
30.50(b)(2) - Safety Equipment Failure
Person (Organization):
Young, Matt (R1DO)
NMSS_Events_Notification, (EMAIL)
Young, Matt (R1DO)
NMSS_Events_Notification, (EMAIL)
DAMAGED GAUGE
The following synopsis of the event was provided by the licensee via phone:
On the afternoon of May 9, 2024, during a leak test, the licensee identified a damaged shutter on a gauge (Serial Number - SH-F180) with a cesium (Cs-137) source of 100 millicuries at their facility. The licensee determined that no exposures or injuries occurred as a result of the damaged shutter since the gauge is located twenty feet off the ground in a primarily inaccessible location. No surveys are known to have been performed at this time. The shutter was determined to be unworkable, and is scheduled to be replaced at a later date.
* * * Additional information provided on 5/10/24 at 1327 EDT from B. Elkins to T. Herrity * * *
The license number was originally reported as 373525501 but it should actually be 16-35383-01. Unit is 10 feet above the floor not 20 feet. Survey readings have been taken: 25.65 mR/hr at the surface; 1.73 mR/hr at 1 foot; 0.32 mR/hr at 3 feet; 0.05 mR/hr at 4 feet. Based on the survey readings, it is believed that the shutter is closed. The mine is now looking to repair the shutter control unit, not replace the gauge.
Notified R1DO (Young) and NMSS Events via email.
The following synopsis of the event was provided by the licensee via phone:
On the afternoon of May 9, 2024, during a leak test, the licensee identified a damaged shutter on a gauge (Serial Number - SH-F180) with a cesium (Cs-137) source of 100 millicuries at their facility. The licensee determined that no exposures or injuries occurred as a result of the damaged shutter since the gauge is located twenty feet off the ground in a primarily inaccessible location. No surveys are known to have been performed at this time. The shutter was determined to be unworkable, and is scheduled to be replaced at a later date.
* * * Additional information provided on 5/10/24 at 1327 EDT from B. Elkins to T. Herrity * * *
The license number was originally reported as 373525501 but it should actually be 16-35383-01. Unit is 10 feet above the floor not 20 feet. Survey readings have been taken: 25.65 mR/hr at the surface; 1.73 mR/hr at 1 foot; 0.32 mR/hr at 3 feet; 0.05 mR/hr at 4 feet. Based on the survey readings, it is believed that the shutter is closed. The mine is now looking to repair the shutter control unit, not replace the gauge.
Notified R1DO (Young) and NMSS Events via email.
Agreement State
Event Number: 57118
Rep Org: New Mexico Rad Control Program
Licensee: National Inspection Services
Region: 4
City: Eunice State: NM
County: Lea
License #: IR510-06
Agreement: Y
Docket:
NRC Notified By: Victor Diaz
HQ OPS Officer: Natalie Starfish
Licensee: National Inspection Services
Region: 4
City: Eunice State: NM
County: Lea
License #: IR510-06
Agreement: Y
Docket:
NRC Notified By: Victor Diaz
HQ OPS Officer: Natalie Starfish
Notification Date: 05/09/2024
Notification Time: 17:21 [ET]
Event Date: 05/09/2024
Event Time: 12:30 [MDT]
Last Update Date: 05/14/2024
Notification Time: 17:21 [ET]
Event Date: 05/09/2024
Event Time: 12:30 [MDT]
Last Update Date: 05/14/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
Crouch, Howard (IR)
NMSS INES Coordinator (EMAIL) (NMSS)
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
Crouch, Howard (IR)
NMSS INES Coordinator (EMAIL) (NMSS)
AGREEMENT STATE REPORT - LOST CAMERA
The following synopsis was received via phone and email from the New Mexico Radiation Control Bureau:
At 1230 MDT on 05/09/2024, a Delta 880 industrial radiography camera containing an activity of 74 curies of iridium (Ir-192) has been determined to be lost on a closed non-public road on an oil field lease. The camera serial number is D15729. The sealed source serial number is 93189M.
Local law enforcement has been informed, details to follow.
NM Event number: ENTS 18002
Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center, Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email)
* * * UPDATE ON 5/14/2024 AT 1723 EDT FROM VICTOR DIAZ TO SAMUEL COLVARD * * *
The following is a summary of information received from the New Mexico Radiation Control Bureau via phone and email:
The Delta 880 camera has been found by a member of the public and is in process of being transferred to a representative of the Department of Energy (DOE) Radiological Assistance Program for inspection and transfer to a DOE facility. The device has an automatic locking mechanism and there is no indication of public exposure at this time.
Notified R4DO (Josey), NMSS Regional Coordinator (Williams), IRMOC (Grant), ILTAB (MacDonald), INES National Officer (email), NMSS Events Notification (email), NMSS INES Coordinator (email).
Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center (email), Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email), CNSNS-Mexico (email).
THIS MATERIAL EVENT CONTAINS A 'Category 2' LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following synopsis was received via phone and email from the New Mexico Radiation Control Bureau:
At 1230 MDT on 05/09/2024, a Delta 880 industrial radiography camera containing an activity of 74 curies of iridium (Ir-192) has been determined to be lost on a closed non-public road on an oil field lease. The camera serial number is D15729. The sealed source serial number is 93189M.
Local law enforcement has been informed, details to follow.
NM Event number: ENTS 18002
Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center, Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email)
* * * UPDATE ON 5/14/2024 AT 1723 EDT FROM VICTOR DIAZ TO SAMUEL COLVARD * * *
The following is a summary of information received from the New Mexico Radiation Control Bureau via phone and email:
The Delta 880 camera has been found by a member of the public and is in process of being transferred to a representative of the Department of Energy (DOE) Radiological Assistance Program for inspection and transfer to a DOE facility. The device has an automatic locking mechanism and there is no indication of public exposure at this time.
Notified R4DO (Josey), NMSS Regional Coordinator (Williams), IRMOC (Grant), ILTAB (MacDonald), INES National Officer (email), NMSS Events Notification (email), NMSS INES Coordinator (email).
Notified the following external agencies: DHS Senior Watch Officer, FEMA Operations Center, USDA Operations Center, HHS Operations Center, DOE Operations Center, CISA Central, EPA Emergency Operations Center, FDA Emergency Operations Center (email), Nuclear SSA (email), FEMA National Watch Center (email), CWMD Watch Desk (email), CNSNS-Mexico (email).
THIS MATERIAL EVENT CONTAINS A 'Category 2' LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 57120
Facility: FitzPatrick
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Michael Lewis
HQ OPS Officer: Natalie Starfish
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Michael Lewis
HQ OPS Officer: Natalie Starfish
Notification Date: 05/09/2024
Notification Time: 21:10 [ET]
Event Date: 05/09/2024
Event Time: 16:29 [EDT]
Last Update Date: 06/20/2024
Notification Time: 21:10 [ET]
Event Date: 05/09/2024
Event Time: 16:29 [EDT]
Last Update Date: 06/20/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Young, Matt (R1DO)
Young, Matt (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 |
EN Revision Imported Date: 6/21/2024
EN Revision Text: HIGH PRESSURE COOLANT INJECTION INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1629 EDT on 05/09/2024, the high pressure coolant injection (HPCI) system was declared inoperable due to a pinhole through-wall leak identified on the seal drain line for 23HOV-1 (HPCI trip throttle valve) downstream of the restricting orifice 23RO-137A. The location of the defect is in the class 2 safety related piping. HPCI is a single train safety system and this notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D)."
The NRC Senior Resident Inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This pinhole leak was discovered during normal operator rounds. Although HPCI is declared inoperable and in a 14-day limited condition of operation, the system function remains available. In addition, all other ECCS systems are currently operable. Compensatory measures (walkdowns) have been implemented to ensure the leak rate does not significantly increase.
* * * RETRACTION ON 06/20/2024 AT 1423 EDT FROM CAMERON KELLER TO ROBERT THOMPSON * * *
"FitzPatrick performed an additional technical evaluation of the steam leak identified on May 9, 2024. The evaluation concluded that the HPCI system would have remained operable and performed its specified safety function with a postulated complete failure of this pipe, considering its size, location, and impact of the leak. Additionally, all components in the vicinity would have retained their required safety functions. Based on this conclusion, EN 57120 is being retracted.
"The NRC Senior Resident Inspector has been notified."
Notified R1DO (Elkhiamy).
EN Revision Text: HIGH PRESSURE COOLANT INJECTION INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1629 EDT on 05/09/2024, the high pressure coolant injection (HPCI) system was declared inoperable due to a pinhole through-wall leak identified on the seal drain line for 23HOV-1 (HPCI trip throttle valve) downstream of the restricting orifice 23RO-137A. The location of the defect is in the class 2 safety related piping. HPCI is a single train safety system and this notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D)."
The NRC Senior Resident Inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
This pinhole leak was discovered during normal operator rounds. Although HPCI is declared inoperable and in a 14-day limited condition of operation, the system function remains available. In addition, all other ECCS systems are currently operable. Compensatory measures (walkdowns) have been implemented to ensure the leak rate does not significantly increase.
* * * RETRACTION ON 06/20/2024 AT 1423 EDT FROM CAMERON KELLER TO ROBERT THOMPSON * * *
"FitzPatrick performed an additional technical evaluation of the steam leak identified on May 9, 2024. The evaluation concluded that the HPCI system would have remained operable and performed its specified safety function with a postulated complete failure of this pipe, considering its size, location, and impact of the leak. Additionally, all components in the vicinity would have retained their required safety functions. Based on this conclusion, EN 57120 is being retracted.
"The NRC Senior Resident Inspector has been notified."
Notified R1DO (Elkhiamy).
Power Reactor
Event Number: 57115
Facility: Beaver Valley
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Shawn Snook
HQ OPS Officer: Sam Colvard
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Shawn Snook
HQ OPS Officer: Sam Colvard
Notification Date: 05/09/2024
Notification Time: 11:48 [ET]
Event Date: 05/09/2024
Event Time: 08:00 [EDT]
Last Update Date: 05/09/2024
Notification Time: 11:48 [ET]
Event Date: 05/09/2024
Event Time: 08:00 [EDT]
Last Update Date: 05/09/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition 50.72(b)(3)(ii)(B) - Unanalyzed Condition 50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition 50.72(b)(3)(ii)(B) - Unanalyzed Condition 50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
Person (Organization):
Young, Matt (R1DO)
Young, Matt (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
CONTAINMENT BYPASS CONDITION DUE TO DEGRADED RIVER WATER PIPING
The following information was provided by the licensee via phone and email:
"At 0800 EDT on May 9, 2024, it was identified during leak rate testing that through-wall flaws existed on 'reactor plant river water' piping inside the containment building. This determination resulted in a containment bypass condition such that a gaseous release could have occurred at a location not analyzed for a release in the loss of coolant accident dose consequence analysis. This condition is not bounded by existing design and licensing documents. Evaluation of the condition of the piping is ongoing to support repair prior to startup.
"With the plant currently in cold shutdown, the containment, as specified in Technical Specification 3.6.1, is not required to be operable. There was no impact on the health and safety of the public or plant personnel.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A), 10 CFR 50.72(b)(3)(ii)(B), and 10 CFR 50.72(b)(3)(v)(C).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 0800 EDT on May 9, 2024, it was identified during leak rate testing that through-wall flaws existed on 'reactor plant river water' piping inside the containment building. This determination resulted in a containment bypass condition such that a gaseous release could have occurred at a location not analyzed for a release in the loss of coolant accident dose consequence analysis. This condition is not bounded by existing design and licensing documents. Evaluation of the condition of the piping is ongoing to support repair prior to startup.
"With the plant currently in cold shutdown, the containment, as specified in Technical Specification 3.6.1, is not required to be operable. There was no impact on the health and safety of the public or plant personnel.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A), 10 CFR 50.72(b)(3)(ii)(B), and 10 CFR 50.72(b)(3)(v)(C).
"The NRC Resident Inspector has been notified."
Part 21
Event Number: 57143
Rep Org: Paragon Energy Solutions
Licensee:
Region: 3
City: Bridgman State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: Richard Knott
HQ OPS Officer: Natalie Starfish
Licensee:
Region: 3
City: Bridgman State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: Richard Knott
HQ OPS Officer: Natalie Starfish
Notification Date: 05/24/2024
Notification Time: 15:47 [ET]
Event Date: 05/09/2024
Event Time: 00:00 [EDT]
Last Update Date: 06/21/2024
Notification Time: 15:47 [ET]
Event Date: 05/09/2024
Event Time: 00:00 [EDT]
Last Update Date: 06/21/2024
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):
Ziolkowski, Michael (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
Ziolkowski, Michael (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
EN Revision Imported Date: 6/24/2024
EN Revision Text: PART 21 - DEFECT WITH EMERGENCY DIESEL GENERATOR VOLTAGE REGULATOR
The following information was provided by Paragon Energy Solutions, LLC via email:
"Paragon has identified a defect in one voltage regulator supplied to AEP DC Cook with serial number NLI-3S7950GR751A1-1007.
"Pursuant to 10CFR Part 21 21.21(d)(3)(i), Paragon is providing initial notification of a defect associated with the emergency diesel generator (EDG) voltage regulator. The voltage regulator was refurbished under the client purchase order 01600229, project number 351030025. Part of the refurbishment involved complete replacement of the units wiring, physical inspection and testing of the unit to Paragon approved acceptance testing instructions. The refurbished unit was supplied to the customer in December 2023. Prior to installation (March 2024), the unit successfully passed bench testing at the plant. During post installation testing, the EDG was started, and the output voltage pegged high and was not controllable. DC Cook subsequently removed the voltage regulator and documented the non-conformance. DC Cook troubleshooting determined the unit was mis-wired. The unit [voltage regulator] was returned to Paragon, and inspection confirmed the plant's diagnosis. The identified mis-wire affects the system circuitry by placing silicon controlled rectifier 5CD in a reverse biased position. The reversed biased rectifier blocks the flow of current which creates an open circuit condition. This open circuit condition causes the output voltage to max out, and does not allow the output voltage to be adjusted. This condition, if left uncorrected, could contribute to a substantial safety hazard and is reportable in accordance with 10CFR Part 21.
"Date of Discovery: May 9, 2024
"Reportability Determined: May 23, 2024
"Paragon has entered this condition in our corrective action program, and we have custody of the effected unit. The extent of condition is limited to this unit supplied to DC Cook. Paragon has determined there is no action necessary for DC Cook at this time."
Affected plant: DC Cook
* * * UPDATE ON 06/21/2024 AT 1655 EDT FROM RICHARD KNOTT TO ROBERT THOMPSON * * *
Paragon Energy Solutions submitted a final report for this event documenting the cause of the mis-wire and corrective actions to prevent recurrence.
Paragon contact: Richard Knott, Vice President Quality Assurance, Paragon Energy Solutions, LLC, 7410 Pebble Drive, Ft. Worth, TX 76118, 817-284-0077, rknott@paragones.com.
Notified R3DO (Havertape), R4DO (Josey), and Part 21 (email).
EN Revision Text: PART 21 - DEFECT WITH EMERGENCY DIESEL GENERATOR VOLTAGE REGULATOR
The following information was provided by Paragon Energy Solutions, LLC via email:
"Paragon has identified a defect in one voltage regulator supplied to AEP DC Cook with serial number NLI-3S7950GR751A1-1007.
"Pursuant to 10CFR Part 21 21.21(d)(3)(i), Paragon is providing initial notification of a defect associated with the emergency diesel generator (EDG) voltage regulator. The voltage regulator was refurbished under the client purchase order 01600229, project number 351030025. Part of the refurbishment involved complete replacement of the units wiring, physical inspection and testing of the unit to Paragon approved acceptance testing instructions. The refurbished unit was supplied to the customer in December 2023. Prior to installation (March 2024), the unit successfully passed bench testing at the plant. During post installation testing, the EDG was started, and the output voltage pegged high and was not controllable. DC Cook subsequently removed the voltage regulator and documented the non-conformance. DC Cook troubleshooting determined the unit was mis-wired. The unit [voltage regulator] was returned to Paragon, and inspection confirmed the plant's diagnosis. The identified mis-wire affects the system circuitry by placing silicon controlled rectifier 5CD in a reverse biased position. The reversed biased rectifier blocks the flow of current which creates an open circuit condition. This open circuit condition causes the output voltage to max out, and does not allow the output voltage to be adjusted. This condition, if left uncorrected, could contribute to a substantial safety hazard and is reportable in accordance with 10CFR Part 21.
"Date of Discovery: May 9, 2024
"Reportability Determined: May 23, 2024
"Paragon has entered this condition in our corrective action program, and we have custody of the effected unit. The extent of condition is limited to this unit supplied to DC Cook. Paragon has determined there is no action necessary for DC Cook at this time."
Affected plant: DC Cook
* * * UPDATE ON 06/21/2024 AT 1655 EDT FROM RICHARD KNOTT TO ROBERT THOMPSON * * *
Paragon Energy Solutions submitted a final report for this event documenting the cause of the mis-wire and corrective actions to prevent recurrence.
Paragon contact: Richard Knott, Vice President Quality Assurance, Paragon Energy Solutions, LLC, 7410 Pebble Drive, Ft. Worth, TX 76118, 817-284-0077, rknott@paragones.com.
Notified R3DO (Havertape), R4DO (Josey), and Part 21 (email).