Event Notification Report for December 13, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/12/2024 - 12/13/2024
Agreement State
Event Number: 57455
Rep Org: NJ Rad Prot And Rel Prevention Pgm
Licensee: Nazha Cancer Center
Region: 1
City: Newfield State: NJ
County:
License #: 468826
Agreement: Y
Docket:
NRC Notified By: Richard Peros
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/05/2024
Notification Time: 11:32 [ET]
Event Date: 12/02/2024
Event Time: 00:00 [EST]
Last Update Date: 12/07/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - SOURCE LOST IN TRANSIT
The following information was provided by the New Jersey Department of Environmental Protection (NJDEP) via email:
"The licensee reported to NJDEP on December 3, 2024, that a Ge-68 pin source that they sent for disposal has been lost in transit on December 2, 2024. The source is a Eckert & Ziegler model HEGL-0132, with current approximate activity of 0.267 mCi. The shipping container arrived at its destination damaged and empty. The licensee has filed a claim with the shipper. If the source is not located within the 30 days, the licensee will follow-up with a full written report to include root cause(s) and corrective actions.
"This event is reportable under 10 CFR 20.2201(a)(1)(ii)."
New Jersey Event Report ID number: To be determined
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: 57456
Rep Org: NJ Rad Prot And Rel Prevention Pgm
Licensee: Phillips 66
Region: 1
City: Linden State: NJ
County:
License #: 506897-RAD240003
Agreement: Y
Docket:
NRC Notified By: Jack Tway
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/06/2024
Notification Time: 12:55 [ET]
Event Date: 12/05/2024
Event Time: 00:00 [EST]
Last Update Date: 12/06/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - STUCK SHUTTER
The following information was provided by the New Jersey Department of Environmental Protection via email:
"On December 5, 2024, the licensee became aware of a shutter that could not fully close but was able to return to the fully open, operative position. The shutter failure was identified while performing a routine six-month fixed gauge shutter check. The fixed gauge is located eight feet above a walking platform which is only accessible to licensee staff via ladder, scaffolding or other means. No members of the public have access to this location.
"The shutter is currently in its normal, open position. No maintenance activities are scheduled which would require closure of the shutter.
"The licensee has a contract with the manufacturer and has scheduled them to assess this situation and make any necessary repairs.
"The shutter holder contains a Cs-137 sealed source (model A-2102) with maximum activity of 300 mCi.
"This event is reportable under 10 CFR 30.50(b)(2) [NJAC 7:28-51.1]"
Equipment information:
Model number: SH-F2
Serial number: 0362CG
Manufacturer: Vega Americas, Inc.
New Jersey Event Report ID number: To be determined
Agreement State
Event Number: 57457
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: Alton Steel
Region: 3
City: Alton State: IL
County:
License #: IL-01738-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/06/2024
Notification Time: 15:51 [ET]
Event Date: 12/05/2024
Event Time: 00:00 [CST]
Last Update Date: 12/06/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Learn, Matthew (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - STUCK SOURCES
The following information was provided by the Illinois Emergency Management Agency (the Agency) via phone and email:
"On December 5, 2024, two 1.53 mCi Co-60 sources were removed from their casting molds for an outage and placed into shielded source holders. At that time, it was discovered that one source could not be fully placed into its shielded configuration. The cause was believed to be a bend or steel prohibiting the source from being fully inserted. The active portion of the source was shielded, but the inactive portion extended beyond the shutter. It was also discovered that the shutter for the second source was inoperable.
"The sources were oriented to minimize exposure rates and secured in the licensee's source storage room. Exposure rates within the source storage room were 2 mR per hour and the exterior wall (unrestricted area) was maximumly 1.6 mR/hour. These measurements were confirmed by Chase Environmental consulting staff on December 6, 2024.
"The Agency staff will respond to the facility and assess the sources and shields when being removed for use on Monday, December 9, 2024.
"There are no anticipated exposures in excess of regulatory limits as a result of this incident. The matter is reportable to the Agency under 32 Ill. Adm. Code 340.1220(c)(2)."
Equipment information:
Device: Gauge shutter
Manufacturer: Berthold
Model number: LB 300 IRL ML
Illinois Item Number: IL240031
Agreement State
Event Number: 57458
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: St. Francis Medical Center
Region: 3
City: Peoria State: IL
County:
License #: IL-01361-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/06/2024
Notification Time: 15:51 [ET]
Event Date: 12/04/2024
Event Time: 00:00 [CST]
Last Update Date: 12/06/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Learn, Matthew (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Allen, Logan (NMSS)
Event Text
AGREEMENT STATE REPORT - MEDICAL EVENT
The following information was provided by the Illinois Emergency Management Agency (the Agency) via phone and email:
"On December 4, 2024, while administering Y-90 microspheres to a patient for radioembolization of the liver, a portion was shunted to the gastrointestinal tract. The shunting was not identified in the licensee's pre-administration macroaggregated albumin (MAA) mapping. The shunting is estimated to have resulted in approximately 100 cGy (rem) to the patient's stomach. The patient and physician have been notified. The licensee has not been reachable for additional details and a site visit is being coordinated."
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.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 57459
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Jason Wiley
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 12/06/2024
Notification Time: 17:00 [ET]
Event Date: 12/05/2024
Event Time: 23:58 [EST]
Last Update Date: 12/12/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Suber, Gregory (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
EN Revision Imported Date: 12/13/2024
EN Revision Text: EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE
The following information was provided by the licensee via phone and email:
"At 2358 Eastern Standard Time (EST) on December 5, 2024, emergency diesel generator (EDG) '1' was declared inoperable due to a failure in the standby lube oil temperature control circuit. At this time, EDG '2' was already inoperable due to failure of a relay in the starting air circuity. As a result, both EDGs were simultaneously inoperable; therefore, this condition is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could have prevented fulfillment of a safety function.
"Offsite power, EDG '3', and EDG '4' were operable during the entire time period that EDGs '1' and '2' were inoperable. The effective safety function was restored at time 0148 on December 6, 2024, when lube oil temperature was restored and EDG '1' was declared operable. EDG '1' was inoperable concurrently with EDG '2' for approximately 1 hour and 50 minutes.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The inoperability of two EDGs placed the plant in LCO 3.8.1.
* * * RETRACTION ON 12/12/2024 AT 1738 EST FROM SABRINA SALAZAR TO ERNEST WEST * * *
"The purpose of this Notification is to retract EN 57459 which was made on December 6, 2024, at 1700 EST.
"At 2358 EST on December 5, 2024, emergency diesel generator (EDG) '1' was declared inoperable due to low lube oil temperature. At this time, EDG '2' was already inoperable. The condition of EDG `1' and EDG `2' being inoperable at the same time was reported as a non-emergency notification per 10 CFR 50.72(b)(3)(v)(D).
"Subsequent to this, it was determined that the identified EDG `1' low lube oil temperature reading was not representative of the temperature of the lube oil in the crankcase and sump, and therefore had no impact on EDG `1' operability. A component failure in the standby lube oil flow control circuit resulted in lube oil flow bypassing the lube oil circuit leg where temperature is sensed, allowing this uncirculated oil in the temperature sensing leg to stagnate and cool. Lube oil flow continued to recirculate through the heater circuit leg to the EDG and remained above the operability limit.
"The operability determination for EDG `1' has been updated indicating that EDG `1' operability was never lost for this event. As a result, there was not a condition that could have prevented the system from fulfilling the safety function. Offsite power, EDG `1', EDG '3', and EDG '4' were operable during this time.
"The NRC Resident Inspector has been notified."
Notified R2DO (Franke)
Agreement State
Event Number: 57460
Rep Org: Utah Division of Radiation Control
Licensee: Earth Tec, LLC d.b.a. Earthtec Engineering
Region: 4
City: Orem State: UT
County:
License #: UT 2900300
Agreement: Y
Docket:
NRC Notified By: Philip Griffin
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/06/2024
Notification Time: 17:33 [ET]
Event Date: 09/16/2024
Event Time: 00:00 [MST]
Last Update Date: 12/06/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Gepford, Heather (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The following report was received by the Utah Department of Environmental Quality, Division of Waste Management and Radiation Control (the Division) via email:
"On September 16, 2024, one of the licensee's portable gauge users was performing a measurement on asphalt using a Troxler 3430 moisture density gauge (serial number 25688) containing a cesium-137 source (serial number 75-8566, presumably 8 mCi) and an americium-241 source (serial number 47-22058, presumably 40 mCi). The operator had his back to the paving vehicle, and the vehicle did not have a functioning back-up alarm. The vehicle struck the operator in the shoulder, and the vehicle's right rear tire impacted and damaged the gauge. The operator sustained minor injuries, but the gauge suffered serious damage. The licensee's radiation safety officer (RSO) surveyed the vehicle's right rear tire using a calibrated instrument and found no evidence of contamination. The highest exposure rate reading from the damaged gauge was approximately 1 mR/hr at 1 meter from the gauge. The RSO was able to return the source rod to the shielded position, secure the damaged source rod from moving using duct tape, and place the gauge in the transportation case. The transport index of the transport case with the damaged gauge inside was 0.3. The RSO contacted Troxler for instructions to return the gauge to Troxler and to order a replacement gauge.
"This event was discovered during a routine license inspection by the Division on December 6, 2024. At the time of the inspection the transport case with the damaged gauge was still in the licensee's possession."
Power Reactor
Event Number: 57470
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Charles Brookshire
HQ OPS Officer: Ernest West
Notification Date: 12/12/2024
Notification Time: 12:22 [ET]
Event Date: 11/03/2024
Event Time: 19:17 [EST]
Last Update Date: 12/12/2024
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Franke, Mark (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES
The following information was provided by the licensee via phone and email:
"This 60-day optional telephone notification is being made in lieu of a licensee event report (LER) submittal as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).
"At approximately 1917 Eastern Standard Time (EST) on November 3, 2024, an invalid actuation of group 6 primary containment isolation valves (PCIVs) (i.e., containment atmospheric control/monitoring (CAC/CAM) and post accident sampling system (PASS) isolation valves) occurred. Reactor building ventilation isolated and standby gas treatment started, per design.
"The group 6 isolation resulted from a spurious signal from the reactor building ventilation radiation monitor `A' channel. No manipulations associated with the isolation or reset logic were ongoing at the time, and no abnormalities were noted in the reactor building ventilation radiation values. The readings for both reactor building ventilation radiation monitor channels remained consistent with each other, with no readings approaching the isolation setpoint.
"The actuation was not initiated in response to actual plant conditions, it was not an intentional manual initiation, and there were no parameters satisfying the requirements for initiation of the system. Therefore, this event has been determined to be an invalid actuation.
"During this event the PCIVs functioned successfully, and the actuations were complete. This event did not result in any adverse impact to the health and safety of the public."