Event Notification Report for November 07, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/06/2023 - 11/07/2023
Agreement State
Event Number: 56823
Rep Org: Wisconsin Radiation Protection
Licensee: Payne and Dolan Inc.
Region: 3
City: Waukesha State: WI
County:
License #: 133-1220-01
Agreement: Y
Docket:
NRC Notified By: Charles Adams III
HQ OPS Officer: John Russell
Licensee: Payne and Dolan Inc.
Region: 3
City: Waukesha State: WI
County:
License #: 133-1220-01
Agreement: Y
Docket:
NRC Notified By: Charles Adams III
HQ OPS Officer: John Russell
Notification Date: 10/30/2023
Notification Time: 21:10 [ET]
Event Date: 10/30/2023
Event Time: 14:35 [CDT]
Last Update Date: 10/31/2023
Notification Time: 21:10 [ET]
Event Date: 10/30/2023
Event Time: 14:35 [CDT]
Last Update Date: 10/31/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dickson, Billy (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSC (Canada), - (EMAIL)
Dickson, Billy (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSC (Canada), - (EMAIL)
AGREEMENT STATE - STOLEN SOURCE
The following information was provided by the Wisconsin Department of Health Services (the Department) via email and telephone:
"On October 30, 2023, at 1830 CDT, the Department received a notification from the licensee that a CPN MC1DRP gauge containing up to 10 mCi of Cesium-137 and 50 mCi of Americium-241 had been out of their control since 1435 CDT when the vehicle containing the gauge was stolen. Local law enforcement has been notified. The Department will monitor and update."
Event Report Number: WI230019
* * * UPDATE FROM MEGAN SHOBER TO DAN LIVERMORE BY EMAIL ON 10/31/2023 * * *
"The missing gauge was recovered around 0800 [CDT] on October 31, 2023 and is now in the custody of the licensee. The gauge had no visual damage. The Department will follow up with the licensee."
Notified R3DO (Dickson), ILTAB and NMSS Events notification by email.
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following information was provided by the Wisconsin Department of Health Services (the Department) via email and telephone:
"On October 30, 2023, at 1830 CDT, the Department received a notification from the licensee that a CPN MC1DRP gauge containing up to 10 mCi of Cesium-137 and 50 mCi of Americium-241 had been out of their control since 1435 CDT when the vehicle containing the gauge was stolen. Local law enforcement has been notified. The Department will monitor and update."
Event Report Number: WI230019
* * * UPDATE FROM MEGAN SHOBER TO DAN LIVERMORE BY EMAIL ON 10/31/2023 * * *
"The missing gauge was recovered around 0800 [CDT] on October 31, 2023 and is now in the custody of the licensee. The gauge had no visual damage. The Department will follow up with the licensee."
Notified R3DO (Dickson), ILTAB and NMSS Events notification by email.
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Agreement State
Event Number: 56824
Rep Org: Texas Dept of State Health Services
Licensee: Midwest NDT Services
Region: 4
City: Cotulla State: TX
County: LaSalle
License #: L 07043
Agreement: Y
Docket:
NRC Notified By: Karen Blanchard
HQ OPS Officer: Dan Livermore
Licensee: Midwest NDT Services
Region: 4
City: Cotulla State: TX
County: LaSalle
License #: L 07043
Agreement: Y
Docket:
NRC Notified By: Karen Blanchard
HQ OPS Officer: Dan Livermore
Notification Date: 10/31/2023
Notification Time: 10:45 [ET]
Event Date: 10/27/2023
Event Time: 00:00 [CDT]
Last Update Date: 10/31/2023
Notification Time: 10:45 [ET]
Event Date: 10/27/2023
Event Time: 00:00 [CDT]
Last Update Date: 10/31/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State 30.50(b)(2) - Safety Equipment Failure
10 CFR Section:
Agreement State 30.50(b)(2) - Safety Equipment Failure
Person (Organization):
Roldan-Otero, Lizette (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Roldan-Otero, Lizette (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - BROKEN CABLE ON EXPOSURE DEVICE
The following information was provided by the Texas Department of State Health Services via email:
"On October 30, 2023, the licensee reported that on October 27, 2023, they had an industrial radiography source disconnect when the drive cable broke at the connector while the crew was working at a temporary job site. The exposure device was an INC IR-100 [containing a 92.1 curie Iridium-192 source]. The source was retrieved and secured in the exposure device by trained personnel. Self reading pocket dosimeters for the radiographers and retriever involved indicate there were no overexposures as a result of this event. Dosimetry badges are being sent for processing. The licensee is re-inspecting and re-servicing all of its crank and cable assemblies. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."
Texas Incident Number: 10063
Texas NMED Number: TX230049
The following information was provided by the Texas Department of State Health Services via email:
"On October 30, 2023, the licensee reported that on October 27, 2023, they had an industrial radiography source disconnect when the drive cable broke at the connector while the crew was working at a temporary job site. The exposure device was an INC IR-100 [containing a 92.1 curie Iridium-192 source]. The source was retrieved and secured in the exposure device by trained personnel. Self reading pocket dosimeters for the radiographers and retriever involved indicate there were no overexposures as a result of this event. Dosimetry badges are being sent for processing. The licensee is re-inspecting and re-servicing all of its crank and cable assemblies. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."
Texas Incident Number: 10063
Texas NMED Number: TX230049
Power Reactor
Event Number: 56834
Facility: Waterford
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Kevin Hale
HQ OPS Officer: Donald Norwood
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: Kevin Hale
HQ OPS Officer: Donald Norwood
Notification Date: 11/05/2023
Notification Time: 17:52 [ET]
Event Date: 11/05/2023
Event Time: 10:33 [CST]
Last Update Date: 11/05/2023
Notification Time: 17:52 [ET]
Event Date: 11/05/2023
Event Time: 10:33 [CST]
Last Update Date: 11/05/2023
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):
Roldan-Otero, Lizette (R4DO)
Roldan-Otero, Lizette (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | N | 0 | Defueled | 0 | Defueled |
DEGRADED CONDITION - TWO STEAM GENERATOR TUBE FAILURES IDENTIFIED
The following information was provided by the licensee via email:
"At 1033 CST on November 5, 2023, while in a refueling outage, it was determined that Waterford Steam Electric Station, Unit 3, did not meet the performance criteria for steam generator structural integrity in accordance with Technical Specification 6.5.9.b.1, Steam Generator Program, due to two tube failures in the number 1 steam generator. The condition was identified during performance of in-situ pressure testing.
"The affected tubes will be plugged.
"The plant is currently stable with all fuel in the spent fuel pool. Decay heat is being removed by normal spent fuel cooling system operation.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"At 1033 CST on November 5, 2023, while in a refueling outage, it was determined that Waterford Steam Electric Station, Unit 3, did not meet the performance criteria for steam generator structural integrity in accordance with Technical Specification 6.5.9.b.1, Steam Generator Program, due to two tube failures in the number 1 steam generator. The condition was identified during performance of in-situ pressure testing.
"The affected tubes will be plugged.
"The plant is currently stable with all fuel in the spent fuel pool. Decay heat is being removed by normal spent fuel cooling system operation.
"This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A) as a degraded condition.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Hospital
Event Number: 56686
Rep Org: West Virginia University Hospital
Licensee: West Virginia University Hospital
Region: 1
City: Morgantown State: WV
County:
License #: 47-23066-02
Agreement: N
Docket:
NRC Notified By: Stephen Root
HQ OPS Officer: Karen Cotton-Gross
Licensee: West Virginia University Hospital
Region: 1
City: Morgantown State: WV
County:
License #: 47-23066-02
Agreement: N
Docket:
NRC Notified By: Stephen Root
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 08/21/2023
Notification Time: 15:16 [ET]
Event Date: 08/17/2023
Event Time: 00:00 [EDT]
Last Update Date: 11/07/2023
Notification Time: 15:16 [ET]
Event Date: 08/17/2023
Event Time: 00:00 [EDT]
Last Update Date: 11/07/2023
Emergency Class: Non Emergency
10 CFR Section:
35.3045(a)(1) - Dose <> Prescribed Dosage
10 CFR Section:
35.3045(a)(1) - Dose <> Prescribed Dosage
Person (Organization):
Gray, Mel (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Gray, Mel (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
EN Revision Imported Date: 11/8/2023
EN Revision Text: MEDICAL EVENT - PATIENT UNDERDOSE
The following information was provided by West Virginia University Hospital via telephone and email:
"It was determined on 8/21/2023, that during a Y-90 (yttrium-90) Thera Sphere treatment performed on 8/17/2023, the delivered dose differed from the prescribed dose by more than 20 percent. The prescribed activity was 101.5 mCi and the administered activity was 3.4 mCi.
"At the start of the infusion the authorized user (AU) was unable to deliver the microspheres due to a blood clot in the microcatheter. The AU then decided to abort the infusion and reschedule instead of chancing potential contamination that could occur by changing out the microcatheter.
"The AU had completed the pre-treatment safety checklist with no issues. The AU has made the notification to the referring physician."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
* * * RETRACTION ON NOVEMBER 7, 2023, AT 1207 EST FROM WEST VIRGINIA UNIVERSITY HOSPITAL TO KAREN COTTON * * *
It was determined that the dose of yttrium-90 Thera Spheres was not delivered according to the written directive due to an emergent patient condition. Therefore, the incident does not qualify as a reportable medical event.
The patient's blood formed a clot within the microcatheter which prevented the passage of Y-90 microspheres. At the onset of administration, the Authorized User (AU) encountered significant resistance in the microcatheter, and they could not flush forward. When troubleshooting the delivery set, the AU visually identified the blood clot within the microcatheter. After several unsuccessful attempts to clear the blood clot, and in consultation with representatives from Boston Scientific, the AU decided to terminate the procedure. On September 1st, the Y-90 prescribed activity, as stated on the written directive, was successfully administered to the patient's hepatic artery. There were no adverse effects to the patient because of the underdose incident. The details of this incident were discussed with NRC inspectors who were on site for a reactive inspection. During those discussions it was concluded that since the patient's blood clotted within the microcatheter, the inability to complete the administration was due to an emergent patient condition.
The blood clot within the microcatheter was confirmed by an analysis of the delivery set performed by Boston Scientific's Product Analysis Team.
Notified: R1DO (Elise), NMSS Events Notification (E-mail)
EN Revision Text: MEDICAL EVENT - PATIENT UNDERDOSE
The following information was provided by West Virginia University Hospital via telephone and email:
"It was determined on 8/21/2023, that during a Y-90 (yttrium-90) Thera Sphere treatment performed on 8/17/2023, the delivered dose differed from the prescribed dose by more than 20 percent. The prescribed activity was 101.5 mCi and the administered activity was 3.4 mCi.
"At the start of the infusion the authorized user (AU) was unable to deliver the microspheres due to a blood clot in the microcatheter. The AU then decided to abort the infusion and reschedule instead of chancing potential contamination that could occur by changing out the microcatheter.
"The AU had completed the pre-treatment safety checklist with no issues. The AU has made the notification to the referring physician."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
* * * RETRACTION ON NOVEMBER 7, 2023, AT 1207 EST FROM WEST VIRGINIA UNIVERSITY HOSPITAL TO KAREN COTTON * * *
It was determined that the dose of yttrium-90 Thera Spheres was not delivered according to the written directive due to an emergent patient condition. Therefore, the incident does not qualify as a reportable medical event.
The patient's blood formed a clot within the microcatheter which prevented the passage of Y-90 microspheres. At the onset of administration, the Authorized User (AU) encountered significant resistance in the microcatheter, and they could not flush forward. When troubleshooting the delivery set, the AU visually identified the blood clot within the microcatheter. After several unsuccessful attempts to clear the blood clot, and in consultation with representatives from Boston Scientific, the AU decided to terminate the procedure. On September 1st, the Y-90 prescribed activity, as stated on the written directive, was successfully administered to the patient's hepatic artery. There were no adverse effects to the patient because of the underdose incident. The details of this incident were discussed with NRC inspectors who were on site for a reactive inspection. During those discussions it was concluded that since the patient's blood clotted within the microcatheter, the inability to complete the administration was due to an emergent patient condition.
The blood clot within the microcatheter was confirmed by an analysis of the delivery set performed by Boston Scientific's Product Analysis Team.
Notified: R1DO (Elise), NMSS Events Notification (E-mail)
Power Reactor
Event Number: 56838
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ED Kotkowski
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: ED Kotkowski
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/07/2023
Notification Time: 18:18 [ET]
Event Date: 11/07/2023
Event Time: 12:00 [EST]
Last Update Date: 11/07/2023
Notification Time: 18:18 [ET]
Event Date: 11/07/2023
Event Time: 12:00 [EST]
Last Update Date: 11/07/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop
Person (Organization):
Eve, Elise (R1DO)
Eve, Elise (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 |
AUXILIARY FEEDWATER SYSTEM INOPERABLE
The following information was provided by the licensee via email:
"On November 07, 2023 at 1200 EST, it was discovered that all pumps in the Auxiliary Feedwater system were inoperable due to the loss of control power to the 'B' train Emergency Feedwater (EFW) flow control valve which supplies the 'D' steam generator. The redundant 'A' train EFW control valve for the 'D' steam generator remains functional, as well as the capability of the Auxiliary Feedwater system to supply all steam generators.
"The"A" and "B" EFW Flow Control Valves are arranged in a series configuration for each Steam Generator. Failure of any of the 8 EFW Flow Control Valves to meet its Surveillance Requirements will render all EFW
Pumps inoperable per tech specs.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(B).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On November 07, 2023 at 1200 EST, it was discovered that all pumps in the Auxiliary Feedwater system were inoperable due to the loss of control power to the 'B' train Emergency Feedwater (EFW) flow control valve which supplies the 'D' steam generator. The redundant 'A' train EFW control valve for the 'D' steam generator remains functional, as well as the capability of the Auxiliary Feedwater system to supply all steam generators.
"The"A" and "B" EFW Flow Control Valves are arranged in a series configuration for each Steam Generator. Failure of any of the 8 EFW Flow Control Valves to meet its Surveillance Requirements will render all EFW
Pumps inoperable per tech specs.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(B).
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 56839
Facility: Calvert Cliffs
Region: 1 State: MD
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Ervin Lyson
HQ OPS Officer: Sam Colvard
Region: 1 State: MD
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Ervin Lyson
HQ OPS Officer: Sam Colvard
Notification Date: 11/07/2023
Notification Time: 18:42 [ET]
Event Date: 11/07/2023
Event Time: 16:17 [EST]
Last Update Date: 11/07/2023
Notification Time: 18:42 [ET]
Event Date: 11/07/2023
Event Time: 16:17 [EST]
Last Update Date: 11/07/2023
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):
Eve, Elise (R1DO)
Eve, Elise (R1DO)
| 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 |
REACTOR TRIP DUE TO NON-SAFETY RELATED BUS UNDER VOLTAGE
The following information was provided by the licensee via email:
"At 1617 on 11/7/2023, Calvert Cliffs Unit 2 experienced an automatic trip from a Reactor Protection System (RPS) based on reactor trip bus under voltage (UV). At that time a loss of U-4000-22 caused a loss of 22, 23, and 24 4kV busses. This resulted in a loss of both motor generator (MG) sets causing the reactor trip bus UV condition. The loss of 22 and 23 4kV non-safety related busses resulted in a loss of main feedwater. Auxiliary feedwater (AFW) was manually initiated and is feeding both steam generators. The 2B diesel generator (DG) started and restored the 24 4kV safety related bus. Heat removal is via the normal turbine bypass valves to the main condenser.
"RPS actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B) - 4-hour report.
"ESFAS actuation (2B DG start on UV) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"ESFAS actuation (AFW manual initiation) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"Site Senior NRC resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was unaffected. Estimation of duration of shutdown is 24 hours.
The following information was provided by the licensee via email:
"At 1617 on 11/7/2023, Calvert Cliffs Unit 2 experienced an automatic trip from a Reactor Protection System (RPS) based on reactor trip bus under voltage (UV). At that time a loss of U-4000-22 caused a loss of 22, 23, and 24 4kV busses. This resulted in a loss of both motor generator (MG) sets causing the reactor trip bus UV condition. The loss of 22 and 23 4kV non-safety related busses resulted in a loss of main feedwater. Auxiliary feedwater (AFW) was manually initiated and is feeding both steam generators. The 2B diesel generator (DG) started and restored the 24 4kV safety related bus. Heat removal is via the normal turbine bypass valves to the main condenser.
"RPS actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B) - 4-hour report.
"ESFAS actuation (2B DG start on UV) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"ESFAS actuation (AFW manual initiation) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"Site Senior NRC resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was unaffected. Estimation of duration of shutdown is 24 hours.