Event Notification Report for January 15, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/14/2025 - 01/15/2025
Agreement State
Event Number: 57441
Rep Org: NJ Rad Prot And Rel Prevention Pgm
Licensee: Camden Metal Company
Region: 1
City: Camden State: NJ
County:
License #: 506558
Agreement: Y
Docket:
NRC Notified By: Jack Tway
HQ OPS Officer: Ian Howard
Notification Date: 11/25/2024
Notification Time: 14:28 [ET]
Event Date: 01/01/2018
Event Time: 00:00 [EST]
Last Update Date: 01/14/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
EN Revision Imported Date: 1/15/2025
EN Revision Text: AGREEMENT STATE REPORT - LOST SOURCE
The following information was provided by the New Jersey Bureau of Environmental Radiation (BER) via email:
"On 11/22/2024, BER staff called the licensee for an update on their termination process for device serial number 13823, and was informed that the device was transferred to a sister company that was looking to start a site in New York State in 2018. While the device was in New York, it was either lost or stolen. The licensee did not notify BER staff that the device was lost or stolen until 2024, when staff was requesting more information for their request to terminate their general license registration."
Source Information:
Manufacturer: Thermo NITON Analyzers LLC
Model: XLP Series
Serial Number: 13823
Isotope and Activity: Am-241, 30mCi
State Event Report ID Number: TBD
* * * UPDATE ON 01/14/2025 AT 0953 EST FROM CHRISTOPHER GIAQUINTO TO ERIC SIMPSON * * *
The following information was provided by the New Jersey Bureau of Environmental Radiation (BER) via email:
BER would like to close this event. The device was not found and is unlikely to be recovered.
Notified R1DO (Carfang), NMSS Events Notification (email), and ILTAB (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
Power Reactor
Event Number: 57491
Facility: Farley
Region: 2 State: AL
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Roosevelt Scott
HQ OPS Officer: Eric Simpson
Notification Date: 01/13/2025
Notification Time: 10:12 [ET]
Event Date: 12/06/2024
Event Time: 21:06 [CST]
Last Update Date: 01/13/2025
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 |
2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
60-DAY NOTIFICATION OF INVALID SPECIFIED SYSTEM ACTUATION
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 2104 CST, on December 6, 2024, while at 100 percent power, an invalid actuation of the B2G load sequencer (B Train) occurred due to a human performance error during maintenance. The B2G load sequencer initiated a complete actuation of the 'B' Train which included auxiliary feedwater (AFW) and closing the 2B diesel generator (DG) output breaker as designed. All systems started successfully. The 2B DG was not running at the time nor was it required to be. The DG breaker protective relay actuated and the 2B DG was declared inoperable.
"Operators immediately recognized the invalid signal and immediately secured the AFW system at 2106 CST. The auto start of the AFW system had negligible effects on plant systems and reactor power.
"Following event investigation and equipment inspections, the 2B DG was returned to operable status in approximately 24 hours.
"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.
"This event did not result in any adverse impact to the health and safety of the public. The Resident Inspector was immediately notified."