ML26026A300

Nuclear Fuel Services (Nfs), Inc. - Integrated Inspection Report 07000143/2025004

ML26026A300
Person / Time
Site:	Erwin
Issue date:	01/27/2026
From:	Nicholas Peterka NRC/RGN-II/DFRSS/FOB1
To:	Dailey R Nuclear Fuel Services
References
IR 2025004
Download: ML26026A300 (0)

Text

Ronald Dailey President Nuclear Fuels Services, Inc.

P.O. Box 337 Erwin, TN 37650-0337

SUBJECT:

NUCLEAR FUELS SERVICES - INTEGRATED INSPECTION REPORT 07000143/2025004

Dear Ronald Dailey:

This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from October 01, 2025, to December 31, 2025, at Nuclear Fuel Services (NFS). On January 15, 2026, the NRC inspectors discussed the results of this inspection with Danielle Rodgers and other members of your staff. The results of this inspection are documented in the enclosed report.

No violations of more than minor significance were identified during this inspection.

Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations.

However, due to the 43-day lapse in normal operations, the NRC modified the facilitys inspection plan (ML25344A465) considering inspection of partial samples, previously inspected, and deferred inspections in accordance with IMC 2600.

January 27, 2026

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Nicholas E. Peterka, Acting Chief Fuels Oversight Branch 1 Division of Fuels, Radiological Safety, and Security Docket No. 07000143 License No. SNM-124

Enclosure:

As stated cc w/ encl: Distribution via GovDelivery Signed by Peterka, Nicholas on 01/27/26

ML26026A300

SUNSI Review

Non-Sensitive

Sensitive

Publicly Available

Non-Publicly Available OFFICE DFRSS NAME N. Peterka DATE 1/27/2026

Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:

07000143 License Number:

SNM-124 Report Number:

07000143/2025004 Enterprise Identifier:

I-2025-004-0033 Licensee:

Nuclear Fuels Services, Inc.

Facility:

Nuclear Fuels Services Location:

Erwin, TN Inspection Dates:

October 01, 2025, to December 31, 2025 Inspectors:

G. Goff, Fuel Facilities Inspector R. Skokowski, Senior Resident Inspector Approved By:

Nicholas E. Peterka, Acting Chief Fuels Oversight Branch 1 Division of Fuels, Radiological Safety, and Security

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SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Nuclear Fuels Services, in accordance with the fuel cycle facility inspection program. This is the NRCs program for overseeing the safe operation of licensed fuel cycle facilities. Refer to https://www.nrc.gov/materials/fuel-cycle-fac.html for more information.

List of Violations No violations of more than minor significance were identified.

Additional Tracking Items None.

3 INSPECTION SCOPES Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Inspections were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2600, Fuel Cycle Facility Operational Safety and Safeguards Inspection Program. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

SAFETY OPERATIONS 88135.02 - Plant Status During this inspection period, routine fuel manufacturing operations, as well as maintenance and testing activities were conducted by the licensee.

The inspectors routinely conducted walkdowns of licensee areas, observed operators, material control and accounting and security force personnel, inspected postings and licensee guidance documents, interviewed plant personnel, and discussed the results of operational and shift turnover meetings to gain insight into the status of facility activities, risk-inform the selection and implementation of the appropriate core inspection procedures, and ensure compliance with license and regulatory requirements.

Plant Tours (IP Section 03.01)

The inspectors performed weekly tours of plant operating areas housing special nuclear material to verify that licensed activities were conducted safely and in compliance with the license and Title 10 of the Code of Federal Regulations (10 CFR) 70, Domestic Licensing of Special Nuclear Material."

Status Meetings (IP Section 03.02)

The inspectors, on a routine basis, attended and reviewed the results of scheduled licensee meetings to determine plant status and awareness of site activities so that inspection resources were appropriately focused on those activities with the higher safety significance. Those licensee meetings included:

Plan of the Day Meetings Safety and Security Review Council Meetings Problem Resolution Meetings Technical Review Board Meetings Scheduled meetings with licensing, security, and facility management Corrective Action Review Board Meetings Identification and Resolution of Problems (IP Section 03.05)

4 The inspectors reviewed the selected issues below to determine if the licensee was entering equipment, human performance, and other performance issues in a formalized program to identify, track and assure correction of safety and safeguard significant problems in accordance with 10 CFR 70.62(a)(3) and applicable license requirements.

PIRC 106804, Valve Separating from Process Off-Gas Line, October 18, 2025 PIRC 106805, Inoperable Pressure Indicator, October 18, 2025 PIRC 106806, SRE Test N307H2DILXXX800 Failure, October 19, 2025 PIRC 106809, Pressure Indicator Drawing Incorrect, October 19, 2025 PIRC 106811, As-found Condition of Pressure Indicator Non-Functional, October 20, 2025 PIRC 106954, Material Found in Sight Glass of Area G Evaporator, November 03, 2025 Investigation 41780, Use Every Time (UET)Compliance - Common Factors Analysis, November 04, 2025 Event Review (IP Section 03.06)

The inspectors reviewed the plant event listed below to determine if the event warranted the use of formal event review criteria and to evaluate whether the licensees response was in accordance with 10 CFR Parts 40.60 (source material), 70.50 (mainly radiological events),

70.52 (criticality and safeguards events), 71.95 (transportation events), 73.71 (safeguards events) and 20.2201, 20.2202, and 20.2203 (radiological and environmental events):

PIRC 106548, Recovery Column BJ01 broke at the reducer on September 18, 2025. The material spilled into the dike below the column, and an operator isolated the column to stop the leak. Subsequently, the material was recovered in accordance with licensee procedures. During the cleanup activities, the licensee identified that the leak material damaged FireTrace detection tubing in the proximity of the broken column. The licensee evaluated the impact of the damaged FireTrace tubing on the associated items relied on for safety (IROFS) (FIRE-44) and concluded that the site still met their performance criteria without FIRE-44. The inspector walkdown the area and reviewed the licensee's IROFS Evaluation Record for the impact on FIRE-44.

Audits (IP Section 03.07)

The inspectors reviewed the external audit listed below to determine whether they have been performed in accordance with implementing procedures and license requirements. The inspectors also ensured that deficiencies and weaknesses identified were entered into the Corrective Action Program (CAP) and assessed whether the corrective actions were appropriate and effective.

NCS-2025-15, Twelfth Nuclear Criticality Safety Audit of the Nuclear Criticality Safety Evaluation for Handling Fissile Material in Portable Containers, September 15, 2025 Radiation Work Permit (RWP) (IP Section 03.09)

5 The inspectors reviewed and observed RWPs to determine whether the RWPs contained the information required by Chapter 4, Radiation Safety of the license application, the Radiation Protection Manual; and implementing procedures. Nuclear Fuels Services uses the term safety work permits (SWP) to include the requirements of an RWP. The inspectors assessed the SWPs listed below:

SWP 25-04-16. Area D Replace Valves & Liners PM which included the activities under WO 1181619, Replace 302-FW-0D37 & Spool Piece 3 Month PM completed on October 04, 2025.

Annual Security and Emergency Preparedness Drills/Exercises (IP Section 03.10)

The inspectors observed the licensees performance during the security Force-on-Force (FOF) tactical response exercise/training evolutions listed below to determine if they were being implemented in accordance with 10 CFR 70.22(I)(3) and/or 10 CFR 73.46(b)(9):

Security FOF tactical response exercise with Local Law Enforcement Agencies conducted the evening of October 7, 2025 Security FOF tactical response exercise conducted the evening of November 4, 2025 88135.04 - Resident Inspection Program Operational Safety The inspectors evaluated whether the material condition and as-found configuration of selected site structures, systems, and components, documentation, personnel, and IROFS to verify compliance with 10 CFR Part 70, the license, the safety analysis report (SAR) and/or license application, and licensee policies and procedures; to determine whether they are appropriate, available, and reliable to protect worker and public safety during normal, off-normal, and accident conditions.

Operations Safety Walkdown (IP Section 03.01)

The inspectors evaluated the operational safety of the systems and sub-systems of the process listed below:

Building 333 Solvent Extraction IROFSs and SREs 88135.05 - Resident Inspection Program Fire Protection (Annual/Quarterly)

The inspectors evaluated the operational status and material condition of fire protection systems, structures, and components (SSCs) to verify compliance with the fire protection program as described in Chapter 7, Fire Safety of the license application, and the National Fire Protection Association (NFPA) 801, Standard for Fire Protection for Facilities Handling Radioactive Materials, as required. Also, the inspectors evaluated onsite fire brigade training and drill performance to verify compliance with standard/procedure/license application chapter that identifies drill/training requirements (i.e. NFPA 600, Standard on Industrial Fire Brigades).

Fire Area Walkdown (IP Section 03.01)

The inspectors walked down and evaluated the fire area listed below:

6 Building 303 Fire Brigade Drill Performance Sample (IP Section 03.02)

On October 23, 2025, the inspectors observed and evaluated the fire brigade's response to a fire alarm as listed below. The inspectors evaluated the fire brigade's assessment of the situation and follow up actions. The inspectors also evaluated whether the fire brigades performance was consistent with the licensees procedures.

PIRC 106852, Fire Alarm Building 302 Area D 88135.17 - Permanent Plant Modifications The inspectors evaluated implementation of the configuration management system (CMS) for facility changes or modifications to ensure that items relied on for safety (IROFS) or other credited safety controls) could adequately perform their intended safety function and that changes did not adversely impact the operability and safety of the facility.

Facility Change/Modifications (IP Section 03.01)

The inspectors reviewed the Buildings 302 and 303 fire suppression system modification to determine whether it was implemented in accordance with 10 CFR 70.72, Facility changes and change process. Specifically, the inspectors reviewed the following:

FireTrace replacement of CO2 in Buildings 302 and 303. The review Included 10 CFR 70.72 Evaluations, change evaluation packages, Nuclear Criticality Safety Evaluations (NCSEs), fire safety evaluations, piping and instrumentation diagrams (P&IDs), operating procedures, Integrated Safety Analyses (ISA) change packages, corrective action reports and system walkdowns.

Management Measures (IP Section 03.02)

The inspectors reviewed the following management measures to ensure that IROFS or other credited safety controls affected by the facility change identified in Section 03 and 07 remained available and reliable to perform their function when needed to comply with the performance requirements of 10 CFR 70.61 or applicable conditions of the license:

FireTrace replacement of the CO2 fire suppression system in Buildings 302 and 303. The review included identified management measures, associated IROFS and safety controls, as well as the licensee's modification and configuration control procedures.

88135.19 - Post Maintenance Testing The inspectors evaluated post-maintenance test activities to verify compliance with license application Chapter 11, Management Measures, and test procedures and/or work order (WO) instructions to confirm functional capability of the IROFS and/or safety control(s) following maintenance.

7 Post-Maintenance Testing (IP Section 03.01)

The inspectors reviewed the post-maintenance tests listed below. Tests were observed directly, in part, and all the test results were reviewed for the following activity:

Blended Low-Enriched Uranium Preparation Facility (BPF) Dissolution and Solvent Extraction PLC Upgrade completed in October and November 2025 88135.22 - Surveillance Testing The inspectors evaluated IROFS and safety controls that required periodic surveillance and/or calibration tests to ensure they were available and reliable to perform their function when needed, to comply with license application Chapter 11, Management Measures, and the performance requirements of 10 CFR 70.61 and 70.62, and to maintain their operational readiness consistent with the Integrated Safety Analysis.

Surveillance and Calibration Testing (IP Section 03.01)

The inspectors reviewed the surveillance tests listed below. Tests were observed directly, and the test results were reviewed.

Safety Related Equipment (SRE) Tests N333XXXXTE2018A, N333XXXXTE2P18A, N333XXXXTIT2O22, N333XXXXTIT2P22, N333XXXXPSH2O17, and N333XXXXPSH2P17 associated with Solvent Extraction IROFS, completed October 30, 2025 RADIOLOGICAL CONTROLS 88030 - Radiation Protection The inspectors evaluated selected aspects of the licensees radiation protection (RP) program to verify compliance with selected portions of 10 CFR 19, 20, and 70, Chapter 4, Radiation Protection, of the facilitys license application, and applicable licensee procedures.

Radiation Protection Program Review (IP Sections 02.01, 02.02, 02.03, 02.23)

The inspectors interviewed licensee staff and reviewed licensee procedures and other documentation related to the implementation of the RP and the As Low As Reasonably Achievable programs to verify compliance with 10 CFR 20.1101(a), 20.1101(b), 20.1101(c),

20.2102 and sections 4.1, 4.3, 4.4, 4.8.2, and Chapter 11 of the license application. Specifically, the inspectors:

Radiation Protection Program Implementation and Procedures (IP Section 02.01 &

02.03) reviewed procedure NFS-GH-908, "Radiation Protection Program," Revision 8 reviewed several other RP-related procedures (see the Documents Reviewed section below) reviewed the NFS-MGT-15-046, "Radiation Safety Policy," Revision 2 interviewed the RP manager to verify the RP program's independence from

8 operations Radiation Program Review and ALARA (IP Section 02.02 & 02.23) reviewed the 2023 and 2024 4th quarter ALARA Occupational Performance Reports reviewed the 2025 second quarter ALARA Occupational Performance Reports reviewed ALARA goals document for calendar years 2024 and 2025 reviewed the triennial assessment/audit of the RP program (November 2024) reviewed the monthly audits performed by RP personnel in various areas of the site (see the "Documents Reviewed" section of this inspection report) reviewed the annual audits of the RP program for 2023 and 2024 reviewed the Safety and Safeguards Review Council minutes for various months from September 2023 - September 2025 reviewed the following corrective actions: PIRCS 106237, 106249, and 106355 walked down the demolition and decontamination (D&D) area for Building 111 observed that the D&D area was roped off with yellow and magenta rope observed workers were wearing the appropriate PPE for D&D area reviewed three pre-job briefs for the D&D area; one each for Monday, Tuesday, and Wednesday of the week of the inspection Training (IP Section 02.04)

The inspectors interviewed licensee staff and reviewed training records to verify compliance with 10 CFR 19.12, 19.13 and the license application (sections 4.5 and 11.3). Specifically, the inspectors:

reviewed training records for initial training and refresher training records for selected licensee employees through the Training & Qualification System reviewed position description requirements against qualifications for personnel changes in RP management since the last RP inspection Radiation Exposure Controls (IP Sections 02.06, 02.18)

The inspectors reviewed licensee's measures such as radiological work permits to keep doses ALARA to verify compliance with 10 CFR 20.1101(b), 20.1702, and sections 4.4.6, 4.6, 4.7.7, and 4.7.9 of the license application. Specifically, the inspectors:

reviewed the safety work permit (SWP 19161) associated with the D&D area for Building 111 observed that gloveboxes, fume/vapor hoods, and other open face enclosures were under proper vacuum during a walkdown of the Material Access Areas (MAAs) observed the airflow direction being from areas of less contamination to areas of higher contamination (i.e., negative pressure) observed stationery air filter change-outs and reviewed results from previous change-outs walked down the respirator supply and cleaning building and examined select respirators for damage

9 Instrument Calibration and Surveys (IP Sections 02.07, 02.08, 02.14, 02.15)

The inspectors reviewed licensees use of radiation detecting instruments and equipment to verify compliance with 10 CFR 20.1501 and 70.24, 20.1902, 20 and sections 4.7.11, 4.8.1, and 4.12 of the license application. Specifically, the inspectors:

Instrument and Equipment/Calibration (IP Sections 02.07 & 02.08) reviewed procedure NFS-HS-A-05, "Calibrating Radiation Monitoring Instruments," Revision 22 observed alpha, beta, and gamma detectors and neutron detectors were within calibration observed response checks for select alpha, beta, and gamma detectors Radiation Surveys & Contamination Control (IP Sections 02.14 & 02.15) observed a radiation survey in Area 333 (hot side) observed a contamination survey in the Waste Water Treatment Facility (WWTF) reviewed records of radiation and contamination surveys performed in 2024 and in 2025 Postings and Labeling (IP Sections 02.09, 02.10, 02.16)

The inspectors observed the licensees storage and control of NRC-licensed sealed sources and reviewed records to verify compliance with 10 CFR 20.1903(c) and section 4.8.3 of the license application. Specifically, the inspectors:

Sealed Sources (IP Section 02.16)

• reviewed the latest records for NRC-licensed sealed sources and observed that none were at an activity level that required leak testing

• reviewed procedure NFS-HS-B-46, "Performing Sealed Source Leak Checks," Rev.

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• observed storage of sealed sources and the associated certificates of authenticity from the supplier

• observed usage of sealed sources for response checks and calibrations of survey instruments and contamination monitors Posting of Notices (IP Section 02.11)

The inspectors observed the Posting of Notices to verify compliance with 10 CFR 19.11.

Omitted due to being covered by routine Senior Resident Inspector activities.

Access Control (IP Section 02.12)

The inspectors observed the licensees access control measures to radiation areas to verify compliance with sections 4.4.2 and 4.4.4 of the license application. Specifically, the inspectors:

observed badge-in and badge-out stations for access to/from MAAs

10 observed that access to MAAs was also controlled by security guards observed the D&D area was roped off with yellow and magenta rope and had personnel stationed to monitor the personnel entering and exiting the area Licensed Material Control (IP Section 02.13)

The inspectors observed the licensees measures to secure stored material and control and maintain constant surveillance of licensed material not in storage to verify compliance with 10 CFR 20.1801 and 20.1802. Specifically, the inspectors:

observed that a sample of radiological material outside of vaults was stored with measures to prevent unauthorized removal or access observed that radiological material outside of vaults was stored in geometrically favorable containers Dose Assessment Program (IP Sections 02.17, 02.22)

The inspectors interviewed licensee staff, and reviewed records and calculations related to the licensee's assessment and assignment of doses to workers to verify compliance with 10 CFR 20.1201, 20.1202, 20.1203, 20.1204, 20.1502(b), 20.2106 and sections 4.7 and 4.8 of the license application. Specifically, the inspectors:

reviewed internal, external, and total dose records for employees who had received the highest doses from 2023 and 2024 to confirm compliance with regulatory requirements discussed the new employee radiological exposure computer software, REMCON, implemented in 2023. The review included in-depth discussions of software data and accuracy of dose calculations.

observed a calculation by hand for an employee's total dose to verify accuracy of the REMCON calculation interviewed the licensee regarding how internal (bioassay) and external dose data is obtained and the quality control check to verify accuracy Dosimetry Program (IP Sections 02.19, 02.20, 02.21)

The inspectors interviewed licensee staff and reviewed the implementation and documentation of the internal and external dosimetry programs including bioassay, whole body counting, and use of dosimetry in the field to verify compliance with 10 CFR 20.1502(a), 20.1502(b), 10 CFR 20.2103(b)(3), and sections 2.3.5.2., 4.7.5, 4.7.4.2, and 4.7.9.2 of the license application. Specifically:

Bioassay Program & Whole Body Counting (IP Section 02.19 & 02.20) interviewed licensee staff regarding onsite processing of internal bioassay and air sampling data for internal dose measurements reviewed procedures NFS-GH-26, "NFS In Vivo Counting Program," Rev. 6 and NFS-HS-A-01, "Plant Action Limits & Investigation for Bioassay Measurements," Rev. 9 reviewed internal bioassay records (REMCON) reviewed stationary air sampling survey records and personal lapel sampler

11 records (REMCON) reviewed in vivo (lung counting) records (REMCON) reviewed QAS-06, "Quality Assurance Vendor Evaluation for GEL Laboratories," 07/18/2024, the quality control document for the vendor who processes bioassay samples Dosimetry (IP Section 02.21) reviewed external dosimetry records reviewed the National Voluntary Laboratory Accreditation Program (NVLAP) accreditation for the licensee's dosimeter processor reviewed procedures NFS-HS-A-06, "Determining Dosimetry Frequencies,"

Rev. 14 observed licensee employees wearing dosimetry in radiologically controlled areas during normal work activities interviewed the licensee regarding the change in dosimeter processors and how the external results are utilized into the total effective dose equivalent (TEDE) calculations INSPECTION RESULTS No issues were identified.

EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.

On January 15, 2026, the inspectors presented the integrated inspection results to Danielle Rodgers and other members of the licensee staff.

On December 11, 2025, the inspectors debriefed the Radiation Protection inspection to Mr. Jason Faddis and other members of the licensee staff.

12 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date PIRC 106124 Rule Not Followed - Respirator Requirement as per SWP 07/31/2025 PIRC 106176 Rule Not Followed - Respirator Requirement as per SWP 08/05/2025 PIRC 106237 Rule Not Followed - Shoe Covers 08/08/2025 PIRC 106249 Adverse Condition - Trend 08/12/2025 PIRC 106298 Rule Not Followed - Contamination Event 08/18/2025 Corrective Action Documents PIRC 106355 Personal Protective Equipment (PPE) 08/25/2025 Corrective Action Documents Resulting from Inspection PIRC 106636 Observation 09/25/2025 Sealed Source Leak Test Report 03/20/2024 Sealed Source Leak Test Report 07/30/2024 Pre-Job Briefs for the D&D project for Building 111 (three briefs total) 09/22-24/2025 Safety and Safeguards Review Council (SSRC) Meeting Minutes 09/07/2023 Safety and Safeguards Review Council (SSRC) Meeting Minutes 11/16/2023 Safety and Safeguards Review Council (SSRC) Meeting Minutes 03/07/2024 Safety and Safeguards Review Council (SSRC) Meeting Minutes 06/06/2024 Safety and Safeguards Review Council (SSRC) Meeting Minutes 09/05/2024 Safety and Safeguards Review Council (SSRC) Meeting Minutes 12/05/2024 Safety and Safeguards Review Council (SSRC) Meeting Minutes 01/09/2025 Safety and Safeguards Review Council (SSRC) Meeting Minutes 03/06/2025 88030 Miscellaneous Safety and Safeguards Review Council (SSRC) Meeting Minutes 06/05/2025

13 Inspection Procedure Type Designation Description or Title Revision or Date Safety and Safeguards Review Council (SSRC) Meeting Minutes 08/28/2025 Safety and Safeguards Review Council (SSRC) Meeting Minutes 09/04/2025 2025 ALARA Goals Presentation 2nd Quarter 2025 - ALARA Occupational Performance Report 2024 ALARA Goals Presentation 4th Quarter 2024 - ALARA Occupational Performance Report 4th Quarter 2023 - ALARA Occupational Performance Report Sealed Source Leak Test Report 08/27/2025 Certificate of Calibration - for Alpha, Beta, and Gamma Standard Sources 09/08/2021 2023 and 2024 Dose Reports Sealed Source Leak Test Report 08/27/2025 Sealed Source Leak Test Report 09/05/2024 Organizational Chart for Licensing and Compliance 09/08/2025 Training curriculums/qualification requirements for radiation technicians, health physicists, and supervisors in each of these areas September 2025 Process Enclosure Face Air Velocity Reports for 105 Labs and 110B Lab (September 2025 - November 2025)

NFS-MGT-15-046 Radiation Safety Policy Rev. 2 QAS-06 Quality Assurance Vendor Evaluation for GEL Laboratories 07/18/2024 NFS-CAP-009-01 Corrective Action Program (CAP) Screening Process Rev. 8 NFS-GH-03 Safety Work Permits Rev. 25 NFS-GH-21 Process Enclosure and Exhaust Ventilation Systems Rev. 7 NFS-GH-26 NFS In Vivo Counting Program Rev. 6 NFS-GH-39 Radiological Safety Training Rev. 11 NFS-GH-79 Sealed Source Program Rev. 4 Procedures NFS-GH-900 Safety & Safeguards Review Council (SSRC) Program Rev. 23

14 Inspection Procedure Type Designation Description or Title Revision or Date NFS-GH-908 Radiation Protection Program Rev. 8 NFS-GH-919 Radiological Safety Training Program Rev. 3 NFS-HPL-001-01 Guidance Document for Pre-Job Brief Rev. 0 NFS-HS-A-01 Plant Action Limits & Investigation for Bioassay Measurements Rev. 9 NFS-HS-A-05 Calibrating Radiation Monitoring Instruments Rev. 22 NFS-HS-A-06 Determining Dosimetry Frequencies Rev. 14 NFS-HS-A-12 Radiation Technician Training Procedure Rev. 15 NFS-HS-A-16 Safety Audits, Assessments, and Inspections Rev. 16 NFS-HS-A-33 Verification of Representativeness of Work Area Air Sampling Rev. 8 NFS-HS-B-17 Radiological Lapel Air Sample Surveys Rev. 21 NFS-HS-B-32 High Volume Air Samples and Loss of Ventilation Rev. 16 NFS-HS-B-44 Process Enclosure Face Air Velocity Measurements Rev. 17 NFS-HS-B-51 Operation of the Cleaning Process in Building 104 Rev. 11 NFS-HS-B-54 Operation of Portable Contamination Monitoring Instruments Rev. 11 SOP 401-03-303 Area 300 - Building 303 (U)

Rev. 24.A Radiation Work Permits (RWPs)

SWP# 19161 Building 111 Decontamination and Demolition 09/22/2025 Monthly Audits of Various Work Areas by the RP Group 2024-20025 2024 Triennial Audit of the Radiation Protection Program for Nuclear Fuel Services, Inc.

December 2024 HP Audit of the Radiation Protection Program for 2023 03/08/2024 HP Audit of the Radiation Protection Program for 2024 03/12/2025 Self-Assessments Triennial Review of Radiation Worker Training Radiation Worker Training Audit 2nd Quarter 2025 06/27/2025 Corrective Action 51129 Corrective Actions for PIRC 104391 03/20/2025 Corrective Action 51130 Corrective Actions for PIRC 104391 03/24/2025 88135.02 Corrective Action Documents Corrective Action 51133 Corrective Actions for PIRC 104391 06/18/2025

15 Inspection Procedure Type Designation Description or Title Revision or Date Fact Finding Documentation 106176 Entrance into SWP Area without Required Respirators 08/05/2025 Fact Finding Documentation 106298 Personal Contamination Event 08/21/2025 Investigation 41627 Failure to Establish SWP 11/05/2025 Investigation 41694 Entrance into SWP Area without Required Respirators 10/13/2025 Investigation 41695 Entrance into SWP Area without Required Respirators 11/05/2025 Investigation 41713 Personal Contamination Event 10/07/2025 Investigation 41715 Personal Contamination Event 09/18/2025 Investigation 41780 Use Every Time (UET)Compliance - Common Factors Analysis 11/04/2025 PIRC 104145 Inappropriate Container Spacing Prior to NDA Scanning 12/12/2024 PIRC 104391 Inappropriate Container Storage 01/12/2025 PIRC 106113 Troubleshooting Area 200 07/30/2025 PIRC 106124 Failure to Establish an SWP 07/31/2025 PIRC 106176 Entrance into SWP area without required Respirators 08/05/2025 PIRC 106298 Personal Contamination Event 08/18/2025 PIRC 106325 Safety Shower not Used 08/18/2025 PIRC 106390 Trend Analysis of Safety Work Permit Non-compliance Issues 08/27/2025 PIRC 106548 302-COLUMN-BJ01 Broke at the Reducer and Spilled into the Associated Dike 09/18/2025 PIRC 106804 Valve Separating from Process Off-Gas Line, 10/18/2025 PIRC 106805 Inoperable Pressure Indicator 10/18/2025 PIRC 106806 SRE Test N307H2DILXXX800 Failure 10/19/2025 PIRC 106809 Pressure Indicator Drawing Incorrect 10/19/2025 PIRC 106811 As-found Condition of Pressure Indicator Non-Functional 10/20/2025 PIRC 106954 Material Found in Sight Glass of Area G Evaporator 11/03/2025 Restart Instructions/Restart Checklist PIRC Material Found in Sight Glass of Area G Evaporator

16 Inspection Procedure Type Designation Description or Title Revision or Date 106954 PIRC 107129 Missing Signatures on Use Every Time Procedures 11/21/2025 Corrective Action Documents Resulting from Inspection PIRC 107130 Supervisors' Qualification 11/21/2025 302-F0335-D Area G P&ID Sheet 2 Rev. YY 302-F0337-D Area G P&ID Sheet 1 Rev. AQ Drawings 306-F0115-D Area 800 Piping and Instrumentation Diagram Sheet 6 Rev. UU 21X-25-0002 Items Relied on For Safety and Safety-Related Equipment (SRE) - Buildings 306 and 307 Area 800 Rev. 39 54T-14-0001 Nuclear Criticality Safety Evaluation for Uranium Recovery Solvent Extraction Area G, H, and J Rev. 3 54X-17-00006 Control Flowdown and Field Verification for Handling Fissile Materials in Portable Containers NCSE Rev. 1 54X-22-0003 NCSE for Area 800 of the Production Facility Rev. 13 IER-02250020 IROFS Evaluation Record for PIRC 106548 09/18/2025 Engineering Evaluations IER-20250002 IROFS Evaluation Record for Container Spacing 01/14/2025 NFS-GH-03 Safety Work Permits Rev. 25 NFS-HPL-001-01 Guidance Document for Pre-job Briefs Rev. 0 NFS-NCS-AUDITWG Nuclear Criticality Safety Audit Writer's Guide Rev. 6 NFS-OPS-001 Conduct of Operations Rev. 24 Procedures PIRC 106954 Restart Instructions/Restart Checklist for Material Found in Sight Glass of Area G Evaporator 11/07/2025 Radiation Work Permits (RWPs)

SWP 25-04-16 Area D Replace Valves & Liners PM 10/04/2025 Self-Assessments NCS-2025-15 Twelfth Nuclear Criticality Safety Audit of the Nuclear Criticality Safety Evaluation for Handling Fissile Material in Portable Containers 09/15/2025 Work Orders 1181619 Replace 302-FW-0D37 & Spool Piece 3 Month PM 10/04/2025 333-F0052-D Utility Distribution Diagram Nitric Acid Rev. X 333-F0450-D BPF Solvent Extraction Feed Column P&ID Rev. AA 333-F0453-D BPF First Pass Evaporator P&ID Rev. DD 88135.04 Drawings 333-F0454-D BPF SX Interface Solids Filtering P&ID Rev. N

17 Inspection Procedure Type Designation Description or Title Revision or Date 333-F0458-D BPF First Pass Raffinate Storage P&ID Rev. T 333-F0459-D BPF Second Pass Raffinate P&ID Rev. Q 333-F0460-D BPF SX Sump Columns P&ID Rev. Q 333-F0464-D BPF SX Chemical Makeup Area P&ID Rev. M 333-F0603-D BPF Raffinate Treatment & Disposal PI&ID Rev. N 2IT-25-0370 IROFS 333-USVXTR, Items Relied on for Safety (IROFS) and Safety-Related Equipment (SRE) - Building 333 Solvent Extraction Rev. 36 54T-09-0064 Nuclear Criticality Safety Evaluation for Blended Low Enriched Uranium Preparation Facility Solvent Extraction Rev. 11 54T-09-0064 Nuclear Criticality Safety Evaluation for the Blended Low Enriched Uranium Preparation Facility Solvent Extraction Rev. 11 N333VALVHV5C03B Approval for Use of Test Grace Period 09/04/2025 SA-00131 Setpoint Analysis for RTD -004 09/28/2015 Engineering Evaluations Setpoint Analysis SA-000049 BSX-013 & BSX-017 Rev. 4 N333MONITR4RAFF SRE Test 01/11/2023 (Test Failed)

N333MONITR4RAFF SRE Test 01/11/2023 (Test Passed)

N333MONITR4RAFF SRE Test 05/13/2025 N333VALVEBA2A25 SRE Test 02/26/2025 N333VALVEBA2G39 SRE Test 09/16/2024 N333VALVEBA2H33 SRE Test 09/04/2025 N333VALVEBA2I52 SRE Test 09/25/2025 N333VALVEBA2J30 SRE Test 06/19/2025 N333VALVEBA2J35 SRE Test 06/19/2025 N333VALVEBA2L45 SRE Test 07/02/2025 N333VALVEBA2L95 SRE Test 07/02/2025 N333VALVEBA2O53 SRE Test 09/05/2025 N333VALVHV5C03A SRE Test 03/04/2025 Procedures N333VALVHV5C03A SRE Test 09/04/2024

18 Inspection Procedure Type Designation Description or Title Revision or Date N333VALVHV5C03B SRE Test 03/04/2025 N333VALVHV5C03B SRE Test 09/05/2024 N333XXXXPSV2K08 SRE Test 09/15/2025 N333XXXXPSV2K08 SRE Test 09/15/2025 PIRC 106714 SRE tagging 10/06/2025 PIRC 106761 Fire Plan Out of Date 10/14/2025 PIRC 106822 Standing Heat Sealer Overheated 10/20/2025 PIRC 106852 Fire Alarm Building 302 Area D 10/23/2025 PIRC 106878 Fire Brigade Staffing 10/25/2025 PIRC 106965 Incorrectly Written SRE Test 11/04/2025 PIRC 106976 Pre-Fire Plan Out-of-Date 11/05/2025 PIRC 107136 Fire Alarm in Building 302 Area F due to Failing Detector 11/21/2025 Corrective Action Documents PIRC 107276 Fire Alarm Building 302 Area D 12/09/2025 013-A10000-D 300 Complex Fire Safety Layout Rev. L 013-F0168-D BLDG 303 PSL-600 Feed Liquid Hydron System P&ID Rev. F 302-F-0924-D 300 Complex Isopropyl Alcohol P&ID Rev. K 303-E0209-D Building 303 Area 600 Smoke Detector System Rev. B 303-E0211-D Building 303 Area 900 Smoke Detector System Rev. A 303-F0110-D Area 900 Piping and Instrumentation Diagram Sheet 1 Rev. HH Drawings 312-F0026-D Bulk Chemical Storage, Isopropyl Alcohol and Hydroxide Tanks P&ID Rev. BB 21X-2-0024 Fire Hazards Analysis Building 303 Rev. 2 21X-23-00009 IROFS 302/303 - 900, Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) Buildings 302 and 303 Area 900 Rev. 21 21X-23-0025 IROFS 303-BURECOV, Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building 303 Uranium Recovery facility Area B Rev. 9 21X-23-0034 IROFS 303-100200, Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building 303 Areas 100 and 200 Rev. 11 88135.05 Engineering Evaluations 21X-24-0019 IROFS 303-PSL:600700A, Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building Rev. 12

19 Inspection Procedure Type Designation Description or Title Revision or Date 303 PSL 600 and 700A 21X-25-0018 IROFS 303-300400500, Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building 303 300, 400 and 500 Rev. 22 N302WIRES33ZON4 Approval for Use of Test Grace Period 09/18/2025 SA-00371 Setpoint Calculation for FIRE6C-001, FIRE6C-002 12/10/2020 Fire Brigade Response Log, 10/23/2025 Fire Brigade Guide Sheet 10/23/2025 Fire Brigade Debrief 10/23/2025 Miscellaneous Fire System Impairment Permit 2025-017 Fire-19, 302-FRDOOR-D328 02/05/2025 N302WIRES33ZON4 SRE Test 11/14/2.25 N302WIRES33ZON4 SRE Test 09/18/2024 N303H2DETPSL600 SRE Test 01/29/2025 N303HS2903XAL15 SRE Test 08/25/2025 N303VALVEHV2904 SRE Test 02/05/2025 N303WIRES33ZON3 SRE Test 09/18/2024 N303WIRES33ZON3 SRE Test 11/14/2025 N303XFRDAMP0001 SRE Test 06/03/2025 N303XFRDAMP0002 SRE Test 06/03/2025 N303XFRDAMP0003 SRE Test 07/22/2024 N303XFRDAMP0004 SRE Test 07/22/2024 NFS-GH-43 Safety-Related Equipment Control Program Rev. 34 Procedures NFS-GH-43-04 SRE Operational Testing Guide Rev. 3 PIRC 105380 FireTrace Cylinder Lost Pressure 05/06/2025 PIRC 105810 FireTrace Cylinder Inadvertently Discharged 06/19/2025 PIRC 106518 FireTrace Cylinder with Slow Leak 09/12/2025 PIRC 106550 FireTrace Cylinder Lost Pressure 09/18/2025 PIRC 106824 FireTrace Cylinder Inadvertent Discharge 10/20/2025 PIRC 106832 FireTrace Detection Tubing Degraded 10/21/2025 PIRC 106832 FireTrace Tubing Degraded 10/21/2025 88135.17 Corrective Action Documents PIRC 106865 FireTrace Cylinder Line Damaged 10/24/2025

20 Inspection Procedure Type Designation Description or Title Revision or Date PIRC 106911 FireTrace Cylinder Line Damaged 10/30/2025 PIRC 107192 FireTrace Cylinder 83A 12/02/2025 PIRC 107249 FireTrace Cylinder Lost Pressure 12/08/2025 DSPK-JA0657 Design Package for JA0657 - Bldg. 302 Areas (F/G/H/J)

Fire Suppression Rev. 0 ECR-20212623 Replace Bldg. 302 CO2 System with FireTrace Suppression System Rev. 0 ECR-20220825 Add 2 FireTrace Cylinders to the east end of Bldg. 303 Area 500 Skid Rev. 0.0 ECR-20220877-01 B302 Areas (F/G/H/J) Fire Suppression Rev. 0 ECR-20220877-02 Sleeve Bldg. 302 FireTrace detection tubing with PFA tubing Rev. 0 Engineering Changes J-A0657 B302 Fire Suppression Scope Document Version 1 21T-25-0785 ISA Safety Basis Risk Assessment Support and Justification For Building 302 Areas F, G, H, I and J (RA-302-AREAS F-J)

Rev. 5 21X-24-0059 Fire Hazard Analysis Building 302 Rev. 2 21X-25-0004 300 Complex Recovery Integrated Safety Analysis Summary Rev. 20 21X-25-0022 PHA - Area F - Process Hazards Analysis Table Building 302 Area F Rev. 3 Engineering Evaluations 21X-25-0050 ISA Safety Basis Risk Assessment Support and Justification For Buildings 302 and 303, Areas 200, 300-500 and 900 Rev. 8 Fire Trace Cylinder Receipt Weights Models 936603, 939903 FireTrace - Design, Installation, Operations Indirect Foam Extinguisher Unit 09/14/2011 TP-JA0657-001 Factory Acceptance Test Criteria B302 CO2 Replacement 01/16/2024 Miscellaneous TP-JA0657-001 Factory Acceptance Test Criteria B302 CO2 Replacement Completed Attachments 04/09/2024 NFS-CM-004 NFS Change Control Process Rev. 24 Procedures NFS-HA-A-67 Documenting the Safety & Regulatory Review of Facility Changes Rev. 18 PIRC 105382 Solvent Extraction Raffinate and Condensate In-Line Monitoring Alarm, 05/06/2025 88135.19 Corrective Action Documents PIRC 106499 Alarm during PLC Testing 09/10/2025

21 Inspection Procedure Type Designation Description or Title Revision or Date PIRC 106736 PLC Upgrade Issues Related to Scrubber 10/09/2025 PIRC 106871 SRE Test N333LVLALRM3F04 Failure 10/26/2025 PIRC 107083 PLC Upgrade Issues with Density Transmitter 11/17/2025 Corrective Action Documents Resulting from Inspection PIRC 106887 Valves Out of Position and Not Locked Per Testing Procedure 10/27/2025 71T-24-0055 TP-JA0000-001, Installation Qualification Test Criteria BPF PLC Upgrade 10/07/2025 71T-24-0056 TP-JA0000-002, Operational Qualification Test Criteria BPF PLC Upgrade 11/07/2025 71T-24-0057 TP-JA0000-003, Performance Qualification Test Criteria BPF PLC Upgrade 11/19/2025 JA0000 BPF PLC Upgrade Test Plan Results Review and Approval 11/24/2025 Engineering Evaluations TP-JA0000-003 Performance Qualification Test Criteria BPF PLC Upgrade 09/11/2025 LOA-BPF-25-001 BPF Dissolution and SX PLC Upgrade Testing 09/02/2025 Procedures LOA-BPF-25-002 BPF Solvent Extraction PLC Upgrade Testing 08/25/2025 Corrective Action Documents Resulting from Inspection PIRC 107055 Observation During SRE Test N333XXXXPSH2017 11/13/2025 333-F0453-D BPF First Pass Evaporator P&ID Rev. DD Drawings 333-F0457-D BPF Second Pass Evaporator P&ID Rev. DD 2IT-25-0370 IROFS 333-USVXTR, Items Relied on for Safety (IROFS) and Safety-Related Equipment (SRE) - Building 333 Solvent Extraction Rev. 36 Set Point Analysis, SA-00048 BSX-012, 016, Heating Steam Pressure Heater Shutdown Rev. 8 Engineering Evaluations Set Point Analysis, SA-00049 BSX-013, 017, Solution Temperature Heater Shutdown Rev. 4 N333XXXXPSH2O17 SRE Test 10/30/2025 N333XXXXPSH2P17 SRE Test 10/30/2025 88135.22 Procedures N333XXXXTE2018A SRE Test 10/30/2025

22 Inspection Procedure Type Designation Description or Title Revision or Date N333XXXXTE2P18A SRE Test 10/30/2025 N333XXXXTIT2O22 SRE Test 10/30/2025 N333XXXXTIT2P22 SRE Test 10/30/2025