Event Notification Report for July 07, 2025

OFFSITE NOTIFICATION

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

"At 1502 [EDT on 6/26/2025] Oyster Creek notified the New Jersey Department of Environmental Protection (NJDEP) due to spill of approximately 50 gallons of water from a chill water system that contained low levels of Cs-137 and Co-60. The spill was stopped, and the system was drained. The spill did not meet reportability requirements under 10 Code of Federal Regulations (CFR) 20, 40 CFR 302, 40 CFR 355, and NUREG-1022.

"No personnel were injured.

"Pursuant to 10 CFR 50.72(b)(2)(xi), this report is being made due to contacting the state of New Jersey (other government agency)"

The NRC Resident will be notified.

AGREEMENT STATE REPORT - OVEREXPOSURE

The following information was provided by the Maryland Department of the Environment (MDE) via phone and email:

"On Friday, June 27, 2025, at 1249 EDT, MDE Program Manager received an email from the radiation safety officer (RSO) at Johns Hopkins University Radiation Control Unit, regarding a radiation overexposure incident involving a declared pregnant worker at the Johns Hopkins Bethesda PET facility.

"The RSO reported that a PET technician received the following radiation doses over the past three months:

"Fetal dose: 13.149 rem
"Whole body dose: 29.966 rem
"Extremity (ring) dose: 6329 rem

"Following the notification, the MDE contacted the RSO by phone to obtain additional details about the incident.

"The RSO explained that the employee's radiation exposure levels remained within acceptable limits until mid-March 2025. At that time, the technician began receiving higher-than-typical doses. The employee was informed when elevated exposure levels were initially observed in April 2025 dosimetry records.

"Upon reviewing the May 2025 dosimetry reports, the Radiation Control Office observed that the exposure levels were significantly elevated. As a result, the June 2025 dosimetry was expedited, which confirmed doses exceeding investigation thresholds. The employee was promptly notified of the dose results and was immediately removed from any work involving radioactive materials. The RSO has initiated a root cause investigation and will notify the MDE as required. This communication serves as a preliminary notification; MDE will follow up on the case and will provide further updates as appropriate."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The overexposure was limited to one worker as two other workers' dosimetry indicate normal exposures. It is unknown at this time what radiopharmaceutical was involved or if there is an indication of spread of contamination. MDE does plan to perform a reactive inspection.

* * * UPDATE ON 6/27/2025 AT 1858 EDT FROM KRISHNAKUMAR NANGEELIL TO SAMUEL COLVARD * * *

The following summary of information was provided by the Maryland Department of the Environment (MDE) via phone and email:

The facility and license number is Johns Hopkins Imaging, Bethesda (RAML #31-314-01). The radiopharmaceuticals used contains F-18 and G-68. MDE called the facility RSO and the RSO determined that there is no indication of a spill or spread of contamination at the facility.

Notified R1DO (Arner), NMSS Events (email), NMSS (Silberfeld).

60-DAY NOTIFICATION OF INVALID SPECIFIED SYSTEM ACTUATION

The following is a summary of information that was provided by the licensee via phone and fax:

"Millstone Power Station Unit 3 is submitting a 60-day telephonic notification in lieu of a licensee event report (LER) submittal as allowed by 10 CFR 50.73 (a)(1) for an invalid system actuation reportable under 10 CFR 50.73(a)(2)(iv)(A).

"On May 6, 2025, at approximately 2108 EDT, while Millstone Power Station Unit 3 was in mode 5 during a refueling outage, an invalid safety injection (SI) signal was initiated. The actuation was not the result of intentional manual actuation and not in response to actual plant conditions requiring safety system operation. This resulted in the automatic start of both emergency diesel generators (EDGs), and the complete initiation on both trains of the following: main steam line isolation, containment isolation phase 'A', and safety injection signal. No injection into the reactor coolant system occurred, and the EDGs remained unloaded. All equipment not administratively locked out responded as designed, and the plant remained stable throughout the event. Control room operators responded in accordance with appropriate operating procedures and restored the affected systems. 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)- including safety injection signal, containment isolation signal, and start of both emergency diesel generators.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector was notified of the event."

AUTOMATIC ACTUATION OF ENGINEERED SAFETY FEATURES ACTUATION SYSTEM

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

"At 0842 EDT on 7/2/25 with Unit 2 in mode 1 at 100 percent reactor power, an actuation of the emergency safety features actuation system (ESFAS) undervoltage (UV) occurred on the safety related 4kV bus '21' during steady state conditions. The cause of the UV actuation was the loss of the 13/4 kV transformer 'U-4000-12' due to its feeder breaker tripping open. The '2A' emergency diesel generator automatically started as designed when the UV signal was received and re-powered 4kV bus '21'.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the ESFAS.

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

LOSS OF SEISMIC MONITORING FOR EMERGENCY PLAN ASSESSMENT

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

"At 1922 CDT on 07/02/2025, the Farley Unit 1 and Unit 2 seismic monitoring panel experienced a fault, rendering the panel nonfunctional.

"Compensatory measures for seismic event classification have been implemented in accordance with Farley procedures.

"This report is being submitted as an eight-hour, non-emergency notification for a loss of emergency assessment capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the seismic monitoring panel is the method for evaluating if an operational basis earthquake (OBE) threshold has been exceeded following a seismic event. This is in accordance with the initiating condition for a seismic event greater than OBE levels and emergency action level HU2. 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 licensee confirmed alternative means of recognizing a seismic event for emergency plan entry are available.