Event Notification Report for March 31, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/28/2025 - 03/31/2025
Part 21
Event Number: 57243
Rep Org: RSCC dba Marmon
Licensee:
Region: 1
City: East Granby State: CT
County:
License #:
Agreement: N
Docket:
NRC Notified By: Phillip Sargenski
HQ OPS Officer: Adam Koziol
Notification Date: 07/25/2024
Notification Time: 11:05 [ET]
Event Date: 07/23/2024
Event Time: 00:00 [EDT]
Last Update Date: 03/28/2025
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Lilliendahl, Jon (R1DO)
Feliz-Adorno, Nestor (R3DO)
Azua, Ray (R4DO)
Part 21/50.55 Reactors, - (EMAIL)
Event Text
EN Revision Imported Date: 3/31/2025
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).
Agreement State
Event Number: 57621
Rep Org: New York City Bureau of Rad Health
Licensee: Mount Sinai Medical Center
Region: 1
City: New York City State: NY
County:
License #: 75-2909-04
Agreement: Y
Docket:
NRC Notified By: Erik Finkelstein
HQ OPS Officer: Robert A. Thompson
Notification Date: 03/24/2025
Notification Time: 10:49 [ET]
Event Date: 02/26/2025
Event Time: 00:00 [EDT]
Last Update Date: 03/24/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Arner, Frank (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - MEDICAL EVENT
The following is a summary of information provided by the New York City Department of Health via email:
On February 26, 2025, the licensee reported a dose administered differed by more than 20 percent of the prescribed dose. During an administration of Lu-177-PSMA [lutetium-177-prostate specific membrane antigen], the administration was stopped because it was determined that the patient's creatine level was significantly elevated. The administered activity was estimated as 49 mCi, out of an intended/prescribed activity of 162 mCi.
New York Identification Number: NYC-25-0226.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Power Reactor
Event Number: 57633
Facility: Palo Verde
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Arthur Tadiar
HQ OPS Officer: Jon Lilliendahl
Notification Date: 03/28/2025
Notification Time: 07:38 [ET]
Event Date: 03/28/2025
Event Time: 01:06 [MST]
Last Update Date: 03/28/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Deese, Rick (R4DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
N |
Y |
100 |
|
100 |
|
Event Text
HIGH PRESSURE SAFETY INJECTION PUMP INOPERABLE
The following information was provided by the licensee via phone or email:
"On 3/28/2025 at 0106 MST, Palo Verde Generating Station Unit 1 entered Technical Specification Limiting Condition for Operation (LCO) 3.0.3 due to discovering `A' essential chiller (EC) oil temperature at 80 degrees Fahrenheit, which is below the operability limit of 120 degrees Fahrenheit. `A' EC inoperable rendered the `A' high pressure safety injection (HPSI) pump inoperable. At the time of discovery, `B' HPSI was inoperable due to recirculating the refueling water tank for chemistry purposes (LCO 3.5.3 condition B entered on 3/27/2025 at 2127 MST). This resulted in inoperability for both trains of HPSI, leading to a loss of the HPSI safety function.
"On 3/28/2025 at 0115 MST, `B' HPSI was restored to operable condition, LCO 3.0.3 was exited, and the loss of safety function was restored.
"There were no power reductions (control rod insertions or boron concentration changes). The event did not result in any challenges to the fission product barrier or result in any release of radioactive materials. Unit 2 and 3 remained at 100%.
"NRC resident has been notified of the event."
Power Reactor
Event Number: 57636
Facility: Brunswick
Region: 2 State: NC
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Charlie Brookshire
HQ OPS Officer: Rodney Clagg
Notification Date: 03/28/2025
Notification Time: 19:07 [ET]
Event Date: 03/28/2025
Event Time: 14:09 [EDT]
Last Update Date: 03/28/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Pearson, Laura (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
2 |
N |
Y |
1 |
|
1 |
|
Event Text
AUTOMATIC ACTUATION OF CONTAINMENT ISOLATION VALVES
The following information was provided by the licensee via phone or email:
"At approximately 1409 EDT on March 28, 2025, with Unit 2 in mode 2 at approximately 1 percent power during reactor startup, an actuation of group 1 primary containment isolation valves (PCIVs) (i.e., main steam line, main steam line drain, and reactor water sample line isolation valves) occurred during performance of the Unit 2 turbine control/stop valves tightness test procedure. The group 1 PCIV actuation resulted when the turbine stop valves were opened (with control valves remaining closed) while main condenser vacuum was below 10 inches Hg [inches of Mercury]. The PCIVs automatically closed as designed when the group 1 actuation signal was received.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of containment isolation valves in more than one system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57638
Facility: Perry
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Robert McClary
HQ OPS Officer: Kerby Scales
Notification Date: 03/29/2025
Notification Time: 16:16 [ET]
Event Date: 03/29/2025
Event Time: 09:15 [EDT]
Last Update Date: 03/29/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Gilliam, Jasmine (R3DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
N |
N |
0 |
|
0 |
|
Event Text
AUTOMATIC ACTUATION OF DIVISION 3 DIESEL GENERATOR
The following information was provided by the licensee via phone and email:
"At 0915 EDT, on March 29, 2025, with Unit 1 in mode 5 at zero percent power, an actuation of the emergency diesel generator system occurred during Unit 2 startup transformer testing. The reason for the auto-start was the loss of an electrical bus during testing. The division 3 diesel generator automatically started as designed on low safety bus voltage.
"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 emergency diesel generator system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."