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Event Notification Report for October 29, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
10/28/2024 - 10/29/2024

Part 21
Event Number: 57243
Rep Org: RSSC 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: 10/28/2024
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: 10/29/2024

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:
RSSC 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).


Agreement State
Event Number: 57392
Rep Org: California Radiation Control Prgm
Licensee: Sequoia Consultants Inc.
Region: 4
City: Carlsbad   State: CA
County:
License #: 7597-30
Agreement: Y
Docket:
NRC Notified By: Robert Greger
HQ OPS Officer: Bill Nytko
Notification Date: 10/21/2024
Notification Time: 00:46 [ET]
Event Date: 10/20/2024
Event Time: 03:30 [PDT]
Last Update Date: 10/21/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Taylor, Nick (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

The following information was provided by the California Radiologic Health Branch via email:

"Sequoia Consultants were using a moisture density gauge on a construction site on the south of on-ramp to the I-5 freeway in the early morning on Sunday, October 20, 2024. The on-ramp was closed with cones and a California Highway Patrol vehicle stationed at the site. At approximately 0330 PDT, a car drove through the cones and hit the Sequoia technician carrying the moisture-density gauge.

"The moisture density gauge was severely damaged with the source rod broken off. The Cs-137 source was in the shielded position and the impact jammed it in place. The remainder of the gauge was in multiple pieces. No radioactive contamination was detected at the site, and radiation levels were indicative of a shielded source. The damaged gauge parts, including the two sources, were transported to the Sequoia office."

California 5010 Number: 102024


Power Reactor
Event Number: 57401
Facility: Oconee
Region: 2     State: SC
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Sam Morton
HQ OPS Officer: Brian P. Smith
Notification Date: 10/28/2024
Notification Time: 13:23 [ET]
Event Date: 10/28/2024
Event Time: 13:23 [EDT]
Last Update Date: 10/28/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Suber, Gregory (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
LOSS OF BOTH TRAINS OF CONTROL ROOM VENTILATION

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

"On October 28, 2024, at 0533 EDT, it was discovered both trains of the unit 1 and unit 2 control room ventilation system booster fans were simultaneously inoperable due to trip of the supply breaker to the motor control center (MCC) supplying the normally closed motor operated intake dampers for both trains. Therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). At 1059 EDT, one train of the unit 1 and unit 2 control room ventilation system booster fans was restored to operable. 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:

Although the control room ventilation affects both units 1 and 2, unit 1 is currently defueled and outside the mode of applicability during the timeframe of this event.

For clarification regarding train separation, both trains for control room ventilation have separate power supplies for their booster fans. However, power for both of their inlet dampers and one of the booster fans are all fed from the same MCC supply breaker that tripped. Therefore, both trains were simultaneously inoperable at 0533 EDT. The loss of power to the MCC is still under investigation. Procedurally, Oconee was able to restore one train to service, the train that still had power to its booster fan, at 1059 EDT, by manually opening its inlet damper in the fail-safe position.


Power Reactor
Event Number: 57402
Facility: Catawba
Region: 2     State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Ari Tuckman
HQ OPS Officer: Natalie Starfish
Notification Date: 10/28/2024
Notification Time: 13:55 [ET]
Event Date: 08/20/2024
Event Time: 00:00 [EDT]
Last Update Date: 10/28/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
Person (Organization):
Suber, Gregory (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Startup 0 Startup
2 N Y 100 Power Operation 100 Power Operation
Event Text
PART 21 INTERIM REPORT - POTENTIAL DEFECT WITH CIRCUIT BOARD

The following is a summary of information provided by the licensee via email:

The licensee received two alarms due to direct current (DC) output voltage fluctuating between 127.4 to 131.3 volts. After troubleshooting, the DC output voltage fluctuations were caused by the battery charger printed circuit board. The part has been sent to the vendor, Ametek, for evaluation. Catawba is the only plant known to have this issue at this time.

The evaluation is expected to be completed on January 31, 2025.

Catawba condition report 02526388

Ametek Part Number: 80-921-4031-90
Ametek failure analysis number: 24-006


Agreement State
Event Number: 57393
Rep Org: PA Bureau of Radiation Protection
Licensee: Geisinger Health System
Region: 1
City: Danville   State: PA
County:
License #: PA-0006
Agreement: Y
Docket:
NRC Notified By: John S. Chippo
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/23/2024
Notification Time: 07:57 [ET]
Event Date: 10/22/2024
Event Time: 00:00 [EDT]
Last Update Date: 10/23/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - MEDICAL UNDERDOSE

The following information was provided by the Pennsylvania Department Bureau of Radiation Protection (the Department) via email:

"On October 23, 2024, the licensee informed the Department of a medical event involving a treatment with SirSpheres. It is reportable per 10 CFR 35.3045.

"On October 22, 2024, a patient was receiving a SirSphere treatment. During the course of administration of the Y-90 spheres, the microcatheter became blocked, and the procedure was stopped. The remaining dose/waste was assessed, and it was calculated that the patient received approximately 30 mCi out of a prescribed 50 mCi. This represents an approximate 40 percent underdose. The authorized user (AU) was satisfied with that amount, believing it to be therapeutic and does not expect any harmful effects to the patient. Both the patient and AU were notified.

"The Department will perform a reactive inspection. More information will be provided as received."

Event Report ID No: PA240020

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.


Fuel Cycle Facility
Event Number: 57394
Facility: Global Laser Enrichment
Region: 2     State: NC
Unit: [] [] []
RX Type: Uranium Enrichment
NRC Notified By: Tim Knowles
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/23/2024
Notification Time: 11:06 [ET]
Event Date: 10/22/2024
Event Time: 13:30 [EDT]
Last Update Date: 10/23/2024
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (b)(2) - Loss Or Degraded Safety Items
Person (Organization):
Suber, Gregory (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
LOSS OF ITEM RELIED ON FOR SAFETY

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

"Loss or degradation of items relied on for safety that results in failure to meet the performance requirement of 10 CFR 70.61.

"A temperature interlock, designated as item relied on for safety (IROFS), failed to actuate at setpoint.

"NRC Region II has been notified."

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

The licensee is troubleshooting the cause, and the system was placed in safe shutdown.


Agreement State
Event Number: 57395
Rep Org: Tennessee Div of Rad Health
Licensee: Eastman Chemical Company
Region: 1
City: Kingsport   State: TN
County:
License #: R-82007-K28
Agreement: Y
Docket:
NRC Notified By: Andrew Holcomb
HQ OPS Officer: Robert A. Thompson
Notification Date: 10/23/2024
Notification Time: 15:50 [ET]
Event Date: 10/22/2024
Event Time: 00:00 [EDT]
Last Update Date: 10/23/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - STUCK OPEN GAUGE SHUTTER

The following information was provided by the Tennessee Division of Radiological Health via email:

"During a scheduled six-month shutter check, it was discovered that a gauge shutter was stuck in the open position. The technician took surveys to verify the shutter was stuck in the open position. The open position is the normal operating position. No abnormal levels of radiation were detected. A VEGA field technician has been contacted to service the gauge.

"Corrective actions or reports, as well as additional information, will be updated with a NMED report within 30 days."

Manufacturer: Ohmart/Vega
Source Holder Model: SHF2
Source Holder SN: 99949B
Isotope: Cs-137, 24.4 mCi

Tennessee Event Report ID Number: TN-24-081


Power Reactor
Event Number: 57397
Facility: River Bend
Region: 4     State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Jason Fortenberry
HQ OPS Officer: Kerby Scales
Notification Date: 10/23/2024
Notification Time: 16:24 [ET]
Event Date: 10/23/2024
Event Time: 11:34 [CDT]
Last Update Date: 10/23/2024
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Taylor, Nick (R4DO)
FFD Group, (EMAIL)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
FITNESS FOR DUTY

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

A non-licensed contract supervisor violated the station's fitness-for-duty program. The employee's access to the plant has been terminated.


Power Reactor
Event Number: 57404
Facility: Prairie Island
Region: 3     State: MN
Unit: [2] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: Martin Cabiro
HQ OPS Officer: Ernest West
Notification Date: 10/29/2024
Notification Time: 13:50 [ET]
Event Date: 10/29/2024
Event Time: 10:23 [CDT]
Last Update Date: 10/29/2024
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):
Edwards, Rhex (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 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 1023 CDT, on 10/29/2024, with Unit 2 in Mode 1 at 100 percent [reactor] power, during the performance of surveillance procedure 2047, CONTROL ROD QUARTERLY EXERCISE, Unit 2 experienced an automatic reactor trip [followed by a] turbine trip. All control rods fully inserted into the core following the reactor trip. The cause of the Unit 2 reactor trip is being investigated.

"Operations responded and stabilized the plant. Auxiliary feedwater actuated as expected. Decay heat is being removed by the steam generators through the main steam dumps to the condenser. The Unit 2 reactor trip was not complex with all systems responding normally post trip.

"Due to the actuation of the reactor protection system (RPS) of Unit 2, this event is being reported as a RPS Actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(2)(iv)(B).

"Due to the actuation of the auxiliary feedwater system following the Unit 2 reactor trip, this event is being reported as a specified system actuation in accordance with the reporting criteria of 10 CFR 50.72(b)(3)(iv)(A).

"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: 57406
Facility: Perry
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Darin Smith
HQ OPS Officer: Ernest West
Notification Date: 10/29/2024
Notification Time: 17:32 [ET]
Event Date: 10/29/2024
Event Time: 11:52 [EDT]
Last Update Date: 10/29/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Edwards, Rhex (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
INOPERABILITY OF DIVISION 3 DIESEL GENERATOR SUPPORTING HIGH PRESSURE CORE SPRAY

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

"At 1152 EDT, on 10/29/2024, the division 3 diesel generator was declared inoperable due to variations in steady state voltage during a planned monthly surveillance run. Troubleshooting of the issue is in progress. This condition could prevent the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). All other emergency core cooling systems were operable during this time.

"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:

Limiting condition for operations (LCO) 3.8.1.b was entered as a result of this event.


Power Reactor
Event Number: 57407
Facility: Perry
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Robert Heil
HQ OPS Officer: Rodney Clagg
Notification Date: 10/29/2024
Notification Time: 18:07 [ET]
Event Date: 10/29/2024
Event Time: 17:30 [EDT]
Last Update Date: 10/29/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Edwards, Rhex (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
OFFSITE NOTIFICATION

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

"At 1730 [EDT], on 10/29/2024, Vistra authorized a report to the State of Ohio in accordance with NEI 07-07, 'Industry Groundwater Protection Initiative,' of a liquid spill to the plant's outdoor ground from an outdoor cask holding radioactive waste. This spill contained radionuclides cobalt-60 and manganese-54 with activities greater than the site procedural limits for state reporting. The outdoor cask has been removed from the onsite storage area; remediation and causal investigation activities are being performed. This exceedance did not exceed any NRC regulations or reporting criteria. There was no impact on the health and safety of the public or plant personnel.

"This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).

"The NRC Resident Inspector has been notified."

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

No EPA limits were exceeded