Event Notification Report for December 23, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/22/2022 - 12/23/2022
Agreement State
Event Number: 56273
Rep Org: PA Bureau of Radiation Protection
Licensee: N/A
Region: 1
City: Greencastle State: PA
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Ian Howard
Licensee: N/A
Region: 1
City: Greencastle State: PA
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Ian Howard
Notification Date: 12/15/2022
Notification Time: 09:46 [ET]
Event Date: 12/02/2022
Event Time: 00:00 [EST]
Last Update Date: 12/16/2022
Notification Time: 09:46 [ET]
Event Date: 12/02/2022
Event Time: 00:00 [EST]
Last Update Date: 12/16/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Henrion, Mark (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Henrion, Mark (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - FOUND GAUGE
The following information was provided by the Pennsylvania Bureau of Radiation Protection (the Department) via email:
"On December 14, 2022, a consultant health physicist informed the Department that a Troxler Model 104-117 nuclear density gauge, serial number 433, containing 3 millicuries of radium-226 beryllium (Ra:Be) had been found. The gauge was found in a trash transfer trailer entering Waste Management, Mountain View Reclamation Landfill on December 2, 2202. This load originated from West Virginia. The load was isolated until consultant health physicist was able to respond on December 13, 2022, to resurvey the trailer. A gamma radiation measurement made at contact with the source housing was 18 milliroentgens/hour. At 1 foot from the approximate location of the source, the gamma dose rate was 5 mrem/hour. No evaluation was made of the neutron dose rate. The device was placed in a locked storage shed posted with a Caution - Radioactive Material sign. The Department was onsite during the recovery of the gauge and continues to investigate its origin.
"The Department will update this event as soon as more information is provided."
Event Report ID No.: PA220030
The following information was provided by the Pennsylvania Bureau of Radiation Protection (the Department) via email:
"On December 14, 2022, a consultant health physicist informed the Department that a Troxler Model 104-117 nuclear density gauge, serial number 433, containing 3 millicuries of radium-226 beryllium (Ra:Be) had been found. The gauge was found in a trash transfer trailer entering Waste Management, Mountain View Reclamation Landfill on December 2, 2202. This load originated from West Virginia. The load was isolated until consultant health physicist was able to respond on December 13, 2022, to resurvey the trailer. A gamma radiation measurement made at contact with the source housing was 18 milliroentgens/hour. At 1 foot from the approximate location of the source, the gamma dose rate was 5 mrem/hour. No evaluation was made of the neutron dose rate. The device was placed in a locked storage shed posted with a Caution - Radioactive Material sign. The Department was onsite during the recovery of the gauge and continues to investigate its origin.
"The Department will update this event as soon as more information is provided."
Event Report ID No.: PA220030
Agreement State
Event Number: 56275
Rep Org: Arizona Dept of Health Services
Licensee: Radiation Physics and Engineering
Region: 4
City: Scottsdale State: AZ
County:
License #: 07-651
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Bill Gott
Licensee: Radiation Physics and Engineering
Region: 4
City: Scottsdale State: AZ
County:
License #: 07-651
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Bill Gott
Notification Date: 12/15/2022
Notification Time: 15:32 [ET]
Event Date: 12/14/2022
Event Time: 00:00 [MST]
Last Update Date: 12/15/2022
Notification Time: 15:32 [ET]
Event Date: 12/14/2022
Event Time: 00:00 [MST]
Last Update Date: 12/15/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Drake, James (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Drake, James (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - LEAKING SOURCE
The following information was provided by the the Arizona Department of Health Services (the Department) via email:
"The Department received notification from the licensee of a leak test that exceeded the regulatory limit of 0.005 microcuries. The licensee is going to return the vial to the manufacturer and exchange it for a new vial source. The Department has requested additional information and continues to investigate the event."
[Source information:]
"Cs-137 Vial
"Serial number: 788-3-11
"Assay date: 11/1/2001
"Additional information will be provided as it is received in accordance with SA-300."
Arizona Incident Number: 22-015
The following information was provided by the the Arizona Department of Health Services (the Department) via email:
"The Department received notification from the licensee of a leak test that exceeded the regulatory limit of 0.005 microcuries. The licensee is going to return the vial to the manufacturer and exchange it for a new vial source. The Department has requested additional information and continues to investigate the event."
[Source information:]
"Cs-137 Vial
"Serial number: 788-3-11
"Assay date: 11/1/2001
"Additional information will be provided as it is received in accordance with SA-300."
Arizona Incident Number: 22-015
Agreement State
Event Number: 56276
Rep Org: Texas Dept of State Health Services
Licensee: ECS Southwest LLP
Region: 4
City: Carrollton State: TX
County:
License #: L05384
Agreement: Y
Docket:
NRC Notified By: Randall Redd
HQ OPS Officer: Ernest West
Licensee: ECS Southwest LLP
Region: 4
City: Carrollton State: TX
County:
License #: L05384
Agreement: Y
Docket:
NRC Notified By: Randall Redd
HQ OPS Officer: Ernest West
Notification Date: 12/16/2022
Notification Time: 18:28 [ET]
Event Date: 12/16/2022
Event Time: 00:00 [CST]
Last Update Date: 12/16/2022
Notification Time: 18:28 [ET]
Event Date: 12/16/2022
Event Time: 00:00 [CST]
Last Update Date: 12/16/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Drake, James (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Drake, James (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - UNABLE TO RETRACT SOURCE
The following information was provided by the Texas Department of State Health Services (the Department) via email:
"On December 16, 2022, the Department received calls from a licensee reporting an equipment failure with a moisture density gauge. The licensee has been unable to retract the rod with cesium-137 back to the fully shielded position and the source is sticking out about 4 inches. This is for a Humboldt 5001 gauge with 40 millicuries (mCi) of americium [-241] and 10 mCi of cesium-137. The rod is presently in the ground to maintain shielding and will be transported back to the storage site with the rod in a bucket of sand. The licensee plans to transport the gauge the same way to a repair facility tomorrow morning. The dose to personnel has not been above normal working conditions but there may be some dose during transportation. The licensee was reminded to minimize dose as much as possible. Further information will be provided per SA-300."
Texas Incident Number: 9974
The following information was provided by the Texas Department of State Health Services (the Department) via email:
"On December 16, 2022, the Department received calls from a licensee reporting an equipment failure with a moisture density gauge. The licensee has been unable to retract the rod with cesium-137 back to the fully shielded position and the source is sticking out about 4 inches. This is for a Humboldt 5001 gauge with 40 millicuries (mCi) of americium [-241] and 10 mCi of cesium-137. The rod is presently in the ground to maintain shielding and will be transported back to the storage site with the rod in a bucket of sand. The licensee plans to transport the gauge the same way to a repair facility tomorrow morning. The dose to personnel has not been above normal working conditions but there may be some dose during transportation. The licensee was reminded to minimize dose as much as possible. Further information will be provided per SA-300."
Texas Incident Number: 9974
Power Reactor
Event Number: 56283
Facility: Limerick
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Richard Wagner
HQ OPS Officer: Jeffrey Whited
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Richard Wagner
HQ OPS Officer: Jeffrey Whited
Notification Date: 12/21/2022
Notification Time: 13:32 [ET]
Event Date: 11/02/2022
Event Time: 18:29 [EST]
Last Update Date: 12/21/2022
Notification Time: 13:32 [ET]
Event Date: 11/02/2022
Event Time: 18:29 [EST]
Last Update Date: 12/21/2022
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
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 |
60-DAY TELEPHONIC NOTIFICATION - INVALID SPECIFIC SYSTEM ACTUATION
The following information was provided by the licensee via email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid specific system actuation of the Emergency Service Water System (ESW).
"On 11/2/2022, during normal reactor operations, multiple main control room alarms were received for D12 Emergency Diesel Generator (EDG) running and Unit 1 Division 2 Safeguard Battery Ground. The D12 EDG did not start; however, the 'B' ESW Pump auto started. Subsequent troubleshooting determined that the cause of the D12 EDG running alarms and the inadvertent auto start of the 'B' ESW Pump was a malfunction on the D12 EDG speed switch. This event is considered an invalid system actuation because the 'B' ESW Pump started in response to a false signal that the D12 EDG was running when D12 EDG did not start. This was a complete actuation of the ESW System and the system functioned as expected in response to the actuation. The affected ESW Pump was shut down in accordance with plant procedures and the degraded D12 EDG speed switch was replaced. There was no impact on the health and safety of the public or plant personnel. The licensee notified the NRC Resident Inspector."
The following information was provided by the licensee via email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A) to describe an invalid specific system actuation of the Emergency Service Water System (ESW).
"On 11/2/2022, during normal reactor operations, multiple main control room alarms were received for D12 Emergency Diesel Generator (EDG) running and Unit 1 Division 2 Safeguard Battery Ground. The D12 EDG did not start; however, the 'B' ESW Pump auto started. Subsequent troubleshooting determined that the cause of the D12 EDG running alarms and the inadvertent auto start of the 'B' ESW Pump was a malfunction on the D12 EDG speed switch. This event is considered an invalid system actuation because the 'B' ESW Pump started in response to a false signal that the D12 EDG was running when D12 EDG did not start. This was a complete actuation of the ESW System and the system functioned as expected in response to the actuation. The affected ESW Pump was shut down in accordance with plant procedures and the degraded D12 EDG speed switch was replaced. There was no impact on the health and safety of the public or plant personnel. The licensee notified the NRC Resident Inspector."
Agreement State
Event Number: 56279
Rep Org: NC Div of Radiation Protection
Licensee: Humboldt Scientific, Inc.
Region: 1
City: Raleigh State: NC
County:
License #: 092-0750-1
Agreement: Y
Docket:
NRC Notified By: Travis Cartoski
HQ OPS Officer: Lloyd Desotell
Licensee: Humboldt Scientific, Inc.
Region: 1
City: Raleigh State: NC
County:
License #: 092-0750-1
Agreement: Y
Docket:
NRC Notified By: Travis Cartoski
HQ OPS Officer: Lloyd Desotell
Notification Date: 12/19/2022
Notification Time: 08:59 [ET]
Event Date: 12/13/2022
Event Time: 00:00 [EST]
Last Update Date: 12/19/2022
Notification Time: 08:59 [ET]
Event Date: 12/13/2022
Event Time: 00:00 [EST]
Last Update Date: 12/19/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
MacDonald, Mark (ILTAB)
AGREEMENT STATE REPORT - MISSING SOURCE
The following is a summary information was provided by the North Carolina Division of Radiation Protection via email:
On 12/13/2022, the licensee discovered that a source from a shipment of sources received on 9/1/2022, was missing from their inventory. The licensee conducted surveys of the area and did not detect the source. None of the shipping containers or bags were damaged, indicating that the source was not lost during shipping and was either not included in the original shipment from the shipper or was lost after the licensee received the shipment. The original shipper of the source was contacted and informed of the missing source; they are performing checks to verify if the source was indeed shipped to the licensee.
Source: Am-241/Be
Activity: 40 mCi
Manufacturer: Eckert & Ziegler
Model: K Model, Batch
S/N: K364-22
NC Event Number: NC220016
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 is a summary information was provided by the North Carolina Division of Radiation Protection via email:
On 12/13/2022, the licensee discovered that a source from a shipment of sources received on 9/1/2022, was missing from their inventory. The licensee conducted surveys of the area and did not detect the source. None of the shipping containers or bags were damaged, indicating that the source was not lost during shipping and was either not included in the original shipment from the shipper or was lost after the licensee received the shipment. The original shipper of the source was contacted and informed of the missing source; they are performing checks to verify if the source was indeed shipped to the licensee.
Source: Am-241/Be
Activity: 40 mCi
Manufacturer: Eckert & Ziegler
Model: K Model, Batch
S/N: K364-22
NC Event Number: NC220016
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
Power Reactor
Event Number: 56284
Facility: Davis Besse
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: Matthew Allan
HQ OPS Officer: Mike Stafford
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: Matthew Allan
HQ OPS Officer: Mike Stafford
Notification Date: 12/23/2022
Notification Time: 17:02 [ET]
Event Date: 12/23/2022
Event Time: 15:13 [EST]
Last Update Date: 12/23/2022
Notification Time: 17:02 [ET]
Event Date: 12/23/2022
Event Time: 15:13 [EST]
Last Update Date: 12/23/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
Person (Organization):
Kozak, Laura (R3DO)
Kozak, Laura (R3DO)
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
---|---|---|---|---|---|---|
1 | N | Y | 100 | Power Operation | 86 | Power Operation |
TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via email:
"At 1513 EST on 12/23/22, a Technical Specification required shutdown was initiated at the Davis-Besse Nuclear Power Station Unit 1. Technical Specification [TS] Action Limiting Condition of Operation [LCO] 3.7.9 for Ultimate Heat Sink water level minimum requirements was not met and condition 'A' was entered on 12/23/22 at 1412 EST with a required action to `Be in Mode 3' with a completion time of 6 hours and `Be Mode 5' with a completion time of 36 hours. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"At 1640 on 12/23/22, the NRC granted enforcement discretion for the shutdown requirements of TS LCO 3.7.9 and the shutdown was terminated with the unit remaining in Mode 1."
The following information was provided by the licensee via email:
"At 1513 EST on 12/23/22, a Technical Specification required shutdown was initiated at the Davis-Besse Nuclear Power Station Unit 1. Technical Specification [TS] Action Limiting Condition of Operation [LCO] 3.7.9 for Ultimate Heat Sink water level minimum requirements was not met and condition 'A' was entered on 12/23/22 at 1412 EST with a required action to `Be in Mode 3' with a completion time of 6 hours and `Be Mode 5' with a completion time of 36 hours. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"At 1640 on 12/23/22, the NRC granted enforcement discretion for the shutdown requirements of TS LCO 3.7.9 and the shutdown was terminated with the unit remaining in Mode 1."
Power Reactor
Event Number: 56286
Facility: Salem
Region: 1 State: NJ
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Edward Kane
HQ OPS Officer: Ernest West
Region: 1 State: NJ
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Edward Kane
HQ OPS Officer: Ernest West
Notification Date: 12/24/2022
Notification Time: 05:08 [ET]
Event Date: 12/24/2022
Event Time: 02:22 [EST]
Last Update Date: 12/24/2022
Notification Time: 05:08 [ET]
Event Date: 12/24/2022
Event Time: 02:22 [EST]
Last Update Date: 12/24/2022
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):
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 |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via email:
"At 0222 [EST] on 12/24/22, with Unit 2 at 100 percent power during steady state operation, the reactor automatically tripped and a safety injection actuated due to steam generator differential pressure. The trip and safety injection were not complex, with all systems responding normally post-trip. An actuation of the auxiliary feedwater system occurred following the reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. The turbine bypass steam dumps and auxiliary feedwater system are removing decay heat. Salem Unit 1 was not affected.
"Due to the actuation of the reactor protection system while critical, this event is being reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system.
"There was no impact to 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 0222 [EST] on 12/24/22, with Unit 2 at 100 percent power during steady state operation, the reactor automatically tripped and a safety injection actuated due to steam generator differential pressure. The trip and safety injection were not complex, with all systems responding normally post-trip. An actuation of the auxiliary feedwater system occurred following the reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. The turbine bypass steam dumps and auxiliary feedwater system are removing decay heat. Salem Unit 1 was not affected.
"Due to the actuation of the reactor protection system while critical, this event is being reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."