Current Event Notification Report for July 03, 2025

EN Revision Imported Date: 7/3/2025

EN Revision Text: PART 21 REPORT - NON-COMPLAINT INSULATED CONDUCTOR

The following is a synopsis of information received via fax:
A reel of insulated conductor was found non-compliant due to failure of insulation tensile and elongation at break test following air oven aging. Wire from the non-compliant reel was delivered to nine plants.
Affected plants: Wolf Creek, Dresden, LaSalle, Limerick, Peach Bottom, Arkansas Nuclear One, Waterford, Susquehanna, and Davis Besse.

Reporting company point of contact:
RSCC Wire and Cable LLC
dba Marmon Industrial Energy and Infrastructure
20 Bradley Park Road
East Granby, CT 06026

Phillip Sargenski - Quality Assurance Manager
Phone: 860-653-8376
Fax: 860-653-8301
Phillip.sargenski@marmoniei.com

* * * UPDATE ON 08/23/24 AT 1315 EDT FROM PHILLIP SARGENSKI TO JOSUE RAMIREZ * * *

The vendor provided the final report for this event listing corrective actions and the estimated completion dates.
Notified R1DO (Lilliendahl), R3DO (Skokowski), R4DO (Vossmar), and Part 21 group (Email).

* * * UPDATE ON 09/04/24 AT 1044 EDT FROM PHILLIP SARGENSKI TO NESTOR MAKRIS * * *

The vendor notified the NRC that they plan to send additional finding data regarding this notification via fax and/or email within the next day or two.
Notified R1DO (Ferdas), R3DO (Hills), R4DO (Drake), and Part 21 group (Email).

* * * UPDATE ON 09/06/24 AT 1327 EDT FROM PHILLIP SARGENSKI TO ADAM KOZIOL * * *

The vendor identified an additional non-compliant shipment of insulated conductor.
Affected plant: Calvert Cliffs
Notified R1DO (Ferdas), R3DO (Hills), R4DO (Drake), and Part 21 group (Email).

* * * UPDATE ON 9/17/24 AT 1641 EDT FROM PHILLIP SARGENSKI TO ROBERT THOMPSON * * *

The vendor identified an additional non-compliant shipment of insulated conductor.
Affected customer: Curtiss-Wright Nuclear Division.
Notified R1DO (Werkheiser), R3DO (Ziolkowski), R4DO (Azua), and Part 21 group (Email).

* * * UPDATE ON 9/26/24 AT 1030 EDT FROM PHILLIP SARGENSKI TO ADAM KOZIOL * * *

The vendor is continuing to conduct inventory sampling which involves a 14 day aging test. Due to the length of testing, the vendor plans on submitting their final report the week of October 7, 2024.
Notified R1DO (Dimitriadis), R3DO (Havertape), R4DO (Young), and Part 21 group (Email).

* * * UPDATE ON 10/28/24 AT 1121 EDT FROM PHILLIP SARGENSKI TO BRIAN P. SMITH * * *

The vendor has decided to expand the scope and breadth of the review to ensure they have identified and corrected for the full extent of the matter. Additional time is needed to complete this review.
Notified R1DO (Eve), R3DO (Edwards), R4DO (Warnick), and Part 21 group (Email).

* * * UPDATE ON 02/13/25 AT 1125 EDT FROM CAROL GROSSO TO IAN HOWARD * * *

The vendor has decided to expand the scope and breadth of the review to ensure they have identified and corrected for the full extent of the matter. RSCC is reviewing shipments from the past 18 months to ensure it has accounted for all non-conforming products. Additional cables related to this scope have been identified and impacted customers have been notified.

***UPDATE ON 03/28/2025 AT 1039 EDT FROM CAROL GROSSO TO RODNEY CLAGG***

The vendor has identified cable(s) that could be affected and have advised customers of the issue and requested that samples be returned to the vendor facility for further verification testing, which is a process that remains ongoing. This testing will confirm the cable's safety related function. Once the testing is complete, the vendor will notify the NRC with an updated and final Part 21 report.

Notified R1DO (Arner), R3DO (Gilliam), R4DO (Deese), and Part 21 group (Email).

* * * UPDATE ON 05/06/2025 AT 0935 EDT FROM CAROL GROSSO TO JOSUE RAMIREZ * * *

The vendor provided an update on their ongoing evaluation. The vendor continues to receive product from their customers and perform their evaluations. The process is still ongoing.

Notified R1DO (Eve), R3DO (Ruiz), R4DO (Dodson), and Part 21 group (Email).

***UPDATE ON 06/03/2025 AT 1605 EDT FROM CAROL GROSSO TO ERNEST WEST***

The vendor provided an update on their ongoing evaluation. The vendor continues to receive product from their customers and is performing evaluations. Test results for completed testing have been forwarded to customers. The process is still ongoing.

Notified R1DO (Dimitriadis), R3DO (Orlikowski), R4DO (Dodson), and Part 21 group (Email).

* * * UPDATE ON 07/02/2025 AT 1634 EDT FROM CAROL GROSSO TO TENISHA MEADOWS * * *

The vendor provided an update on their ongoing evaluation. The vendor continues to receive product from their customers to perform evaluations. Test results for completed testing have been forwarded to customers. The process is still ongoing.

Notified R1DO (Carfang), R3DO (Havertape), R4DO (Warnick), and Part 21 group (Email).

AGREEMENT STATE REPORT - LOST GAUGE

The following information was provided by the North Carolina Radioactive Materials Branch (NC RMB) via email:

"The NC RMB reports the loss of a generally licensed fixed nuclear gauge source (Manufacturer: Industrial Dynamics Co. Ltd. (Filtec), Model: 06110, SN: 2234, 100 mCi, Am-241).

"The licensee believes the entire device may have accidentally been thrown into the trash or scrap. The device was stored in a maintenance trailer and was being used for spare parts. The device was last seen on June 17, 2024, during routine preventive maintenance by a field service engineer. Upon discovering the missing source, the licensee searched the site, and the device could not be found. The licensee does not possess a survey meter. The incident was reported to the NC RMB on June 10, 2025. On June 24, 2025, an NC RMB inspector conducted an on-site search for the source and the source could not be located.

"Licensee believes the device was accidentally thrown away due to staff not understanding the radiological importance of the device. A thorough search was performed by both the licensee and agreement state staff and the source could not be located."

NC Event Number: NC250008

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 REPORT - UNPLANNED CONTAMINATION

The following information was provided by the Illinois Emergency Management Agency via phone and email:

"On 6/25/2025, the associate radiation safety officer at Northwestern Memorial Healthcare (IL-01037-02) called to advise that following a successful Sir Spheres therapy procedure at Central DuPage Hospital, the nuclear medicine technologist dropped the residual dose vial containing 72 mCi of Y-90 Sir Spheres on the floor within the nuclear medicine hot lab (restricted area). Nuclear medicine personnel followed emergency procedures and promptly notified radiation safety staff. Contamination of personnel was limited to clothing and booties which were immediately removed and placed in storage for decay. Subsequent personnel surveys were conducted and confirmed contamination was limited to clothing and booties with no contamination to the skin. The licensee met reporting requirements of 32 Ill. Adm. Code 340.1220(a)(2). Inspectors will conduct a reactive inspection on 6/26/2025, to verify appropriate surveys were conducted and confirm adequate decontamination of personnel and the hot lab."

Illinois NMED Number: IL250026

AGREEMENT STATE REPORT - STOLEN GAUGE

The following information was provided by the Texas Department of State Health Services (the Department) via email:

"On June 25, 2025, the licensee notified the Department of the theft of a moisture density gauge. The gauge, a Troxler 3430, contains an 8 millicurie (mCi) cesium-137 sealed source and a 40 mCi americium-241/beryllium sealed source. The theft occurred in Fort Bend County on June 24, 2025. The radiation safety officer (RSO) stated that a technician, after completing his work at a job site, placed the gauge in the back of his pickup truck. The technician placed the gauge in its transport container which was then secured with double locks. The RSO stated that the technician left the job site and drove to a gas station. It was at the gas station that he noticed that the gauge was missing. The locks securing the gauge transport container had been broken, and the container, including the gauge, stolen. The technician reported the theft to the RSO and the Harris County Sheriff's department. The licensee stated that the source rod was in the secured and locked position at the time of the incident. The licensee also stated that no unintended exposure to the public exceeding dose limits is expected due to this incident.

"Additional information will be provided in accordance with SA 300 reporting requirements."

Texas incident report number: 10205
Texas NMED number: TX250030


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

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.

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."