12/19/2024
Event Notification Report for December 12, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/11/2024 - 12/12/2024
EVENT NUMBERS
57455 57464
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 tohttp://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 57464
Facility: Arkansas Nuclear
Region: 4 State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: John Lindsey
HQ OPS Officer: Jordan Wingate
Notification Date: 12/10/2024
Notification Time: 18:02 [ET]
Event Date: 12/10/2024
Event Time: 10:30 [CST]
Last Update Date: 12/10/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Azua, Ray (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 67 Power Operation 100 Power Operation
Event Text
SECONDARY CONTAINMENT INOPERABLE
The following information was provided by the licensee via phone and email:
"At 0930 CST on 12/10/2024, Arkansas Nuclear One, Unit 1, discovered both isolation valves open in a one-inch breathing air line containment (reactor building) pe*******on. This resulted in inoperable reactor building isolation valves in a required mode of applicability per Unit 1 Technical Specification 3.6.3 and an inoperable reactor building per Unit 1 Technical Specification 3.6.1. Unit 1 had recently entered the modes of applicability for both Technical Specifications at 0556 CST on 12/8/2024 following a planned maintenance outage.
"The outside isolation valve was locked closed at 0950 CST on 12/10/2024, restoring operability of the reactor building. The inside valve was locked closed at 1345 CST on 12/10/2024, restoring operability of both isolation valves.
"This condition is being reported under 10 CFR 50.72(b)(3)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. This condition is also being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.
"There was no impact to 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 cause of the out-of-position valves is under investigation. No evolutions were in progress besides a plant startup at the time of the event.
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