Event Notification Report for July 29, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/28/2024 - 07/29/2024

EVENT NUMBERS
57234 57249
Agreement State
Event Number: 57234
Rep Org: New York State Dept. of Health
Licensee: State University of New York (SUNY) at Stony Brook
Region: 1
City: Stony Brook   State: NY
County:
License #: 0455
Agreement: Y
Docket:
NRC Notified By: Nathaniel A. Kishbaugh
HQ OPS Officer: Josue Ramirez
Notification Date: 07/22/2024
Notification Time: 13:02 [ET]
Event Date: 07/18/2024
Event Time: 00:00 [EDT]
Last Update Date: 07/23/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Lilliendahl, Jon (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSC (Canada) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST SOURCE

The following information was provided by the New York State Department of Health (NYSDOH) via email:

"The NYSDOH received an email from the radiation safety officer (RSO) on July 22, 2024, to report a lost Fe-55 source. The make and model of the missing source was not disclosed; however, NYSDOH is requesting additional information and will provide this information once available. The source serial no. is 55-1.1-8 and was last assayed 10/1/2015. At the time of manufacture and distribution, this source was 10 mCi.

"The source in question was last seen during routine inventory on January 5, 2023. Following this inventory, this source was not accounted for on March 23, 2023. It was believed that this source may have been utilized by an authorized user between January 5, 2023, and March 23, 2023. However, after many discussions between the authorized user and Stony Brook University's radiation safety office, it was confirmed that the source in question was officially lost on 7/18/2024. Decay calculations suggest that the missing Fe-55 source is approximately 1.07 mCi to date. As this source was last inventoried on January 5, 2023, it is estimated that the Fe-55 source was approximately 1.58 mCi at the time it was last confirmed as present in the storage area. This activity is approximately 15.8 times the quantity for Fe-55 requiring labeling as stated in Appendix C to 10 CFR 20. The loss of this source meets the reportability criteria in 10 CFR 20.2201(a)(1)(ii).

"It is not believed that this source may cause any incidental doses which may exceed the limits in Subparts C or D of 10 CFR 20. Furthermore, the loss of this source would not be expected to have any negative implications on public health. NYSDOH is monitoring this incident and has assigned incident number 1493 to track this event. Additional information will be provided to NMED once available."

Event Report ID No. NY-24-06
NYSDOH Incident Number: 1493

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: 57249
Facility: Saint Lucie
Region: 2     State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Dave Young
HQ OPS Officer: Ian Howard
Notification Date: 07/28/2024
Notification Time: 21:58 [ET]
Event Date: 07/28/2024
Event Time: 18:37 [EDT]
Last Update Date: 07/28/2024
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
Person (Organization):
Coovert, Nicole (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

The following information was provided by the licensee via phone and email:

"At 1837 EDT on 7/28/24, with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped due to inadvertent closure of a main steam isolation valve. During the trip, auxiliary feedwater actuated. All other systems responded normally post-trip. Operations stabilized the plant in mode 3. Decay heat is being removed by atmospheric dump valves and auxiliary feedwater. Unit 2 is not affected.

"This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."

The NRC resident inspector has been notified.