ML25350C194
| ML25350C194 | |
| Person / Time | |
|---|---|
| Site: | Erwin |
| Issue date: | 12/16/2025 |
| From: | Nicholas Peterka NRC/RGN-II/DORS |
| To: | Dailey R Nuclear Fuel Services |
| References | |
| IR 2025003 | |
| Download: ML25350C194 (0) | |
Text
Ronald Dailey President Nuclear Fuels Services, Inc.
P.O. Box 337 Erwin, TN 37650-0337
SUBJECT:
NUCLEAR FUELS SERVICES - INTEGRATED INSPECTION REPORT 07000143/2025003
Dear Ronald Dailey:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from July 1, 2025 to September 30, 2025 at Nuclear Fuel Services (NFS). On November 20, 2025, the NRC inspectors discussed the results of this inspection with you 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. 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 Office of Nuclear Materials Safety and Safeguards granted the Regional Offices an extension on the issuance of the calendar year 2025, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.
December 16, 2025
R. Dailey 2
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 Projects Branch 1 Division of Fuels, Radiological Safety, and Security Docket No. 07000143 License No. SNM-124
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Peterka, Nicholas on 12/16/25
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available OFFICE RII / DFRSS NAME N. Peterka DATE 12/16/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07000143 License Number:
SNM-124 Report Number:
07000143/2025003 Enterprise Identifier:
I-2025-003-0033 Licensee:
Nuclear Fuels Services, Inc.
Facility:
Nuclear Fuels Services Location:
Erwin, TN Inspection Dates:
July 01, 2025 to September 30, 2025 Inspectors:
G. Goff, Fuel Facilities Inspector J. Grice, Fuel Facilities Inspector L. Pitts, Sr. Fuel Facility Project Inspector T. Sippel, Sr. Fuel Facility Project Inspector R. Skokowski, Senior Resident Inspector C. Ubben, Fuel Facilities Inspector T. Vukovinsky, Sr. Fuel Facility Project Inspector Approved By:
Nicholas E. Peterka, Acting Chief Projects Branch 1 Division of Fuels, Radiological Safety, and Security
2
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 Type Issue Number Title Report Section Status WER 07000143/2024-002-00 10 CFR 71.95 - 60 Day Report, Presence of Water In ES-3100 Shipping Package 86740 Closed WER 07000143/2023-001-00 10 CFR 71.95 - 60 Day Report, Corrosion on LR-230 86740 Closed
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 88020 - Operational Safety The inspectors evaluated selected aspects of the licensees Operational Safety program to verify compliance with selected portions of 10 CFR 70, including 70.61 and 70.62, as well as Chapter 11, Management Measures, of the facilitys license application, and applicable licensee procedures.
Identification of Safety Controls and Related Programs (IP Section 02.01)
The inspectors selected specific process areas for inspection based on the safety basis information of the facility, the risk/safety significance of the process areas, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety (NCS), radiation safety, and fire safety based on the information provided in the integrated safety analysis (ISA) summary.
The process areas and accident sequences selected for review are listed below:
The Blended Low-Enriched Uranium (BLEU) Production Facility (BPF) 4-Burner system, the BPF Condensate Discard system, and the BPF Scrubber, including accident sequences:
BPF-RWC-10, BPF-RWC-29, BPF-RWC-33, BPF-RWC-51, BPF-RWC-64, BPF-RWC-73 for radiological releases, and 4.1.2.4.1, 4.1.2.4.2, 4.1.2.4.3, 4.1.2.4.4, 4.1.3.4, 4.1.4.4, 4.1.4.4.1, 4.1.5.4.2, 4.1.7.4.1, 4.1.7.4.2, 4.1.7.4.3, 4.1.9.4.1, 4.1.9.4.2, 4.1.12.4, 4.1.14.4.1, 4.1.14.4.2 for criticality.
Additionally, the inspectors reviewed the basis, and assumptions, associated with selected accident sequences (e.g., BPF-RWC-35 for a fire) that the licensee screened as Low Consequence. The inspectors also reviewed accident sequences and conducted walkdowns of portions of the licensee's plant air supply system.
Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative, engineered, and passive safety controls or items relied on for safety (IROFS) for the accident sequences selected above, including the identification of the licensees assumptions and bounding cases as they
4 apply to each of the selected accident sequences, safety controls, or IROFS. This review was performed to verify that the controls or IROFS were available and reliable to perform their intended safety functions and that the design-basis assumptions were reflected in the actual conditions in the field. The specific safety controls selected for review are listed below:
BRC-1, an Administrative Control (AC) IROFS for NCS BRC-3, an AC IROFS for NCS BRC-4, an AC IROFS for NCS BRC-8, an AC IROFS for NCS BRC-9, an AC IROFS for NCS BRC-10, an AC IROFS for NCS BRC-12, an AC IROFS for NCS BRC-16, an AC IROFS for NCS BRC-17, an AC IROFS for NCS BRC-20, an AC IROFS for NCS BRC-23, an Active Engineered Control (AEC) IROFS for radiation safety BRC-24, an AEC IROFS for radiation safety BRC-26, an AEC IROFS for radiation safety BRC-27, an AEC IROFS for radiation safety BRC-28, an administrative IROFS for radiation safety BRC-29, an administrative IROFS for radiation safety BRC-33, an AC IROFS for NCS BLW-2, an AC IROFS for NCS BLW-4, an AEC IROFS for NCS BPF-15, a passive engineered control sole IROFS for radiation safety BPV-1, a passive engineered control IROFS for NCS BPV-2, an AC IROFS for NCS BPV-3, an AC IROFS for NCS BPV-21, an AC IROFS for NCS FMF-24, an AEC IROFS for NCS FMF-25, an AEC IROFS for NCS Implementation of Safety Controls (IP Section 02.03)
For the selected safety controls listed above, the inspectors reviewed a sample of the applicable management measures to verify proper implementation in accordance with 10 CFR 70 and applicable sections of the license application. This review was performed to verify that selected safety controls or IROFS were present, available, and reliable to perform their safety function and that the design-basis assumptions were reflected in the actual conditions in the field. The inspectors conducted the following activities to verify the implementation of selected safety controls:
Walked down the processes and controls in the BPF 4-Burner system, the BPF Condensate Discard system, the BPF Scrubber and portions of the plant air supply system Reviewed Standard Operating Procedure (SOP) 402 Sections 11, 25, and 42 for the AC IROFS listed above
5 Reviewed IROFS BPV-2 weekly non-destructive assay (NDA) results of scrubber and blowdown tank for July 2025 Reviewed IROFS BPV-2 bimonthly NDA results for process off-gas ductwork for February, April, and June 2025 Reviewed IROFS BPV-3 weekly samples of uranium concentration in the scrubber blowdown tank for July 2025 Reviewed IROFS BLW-2 dual samples of uranium concentration in solvent extraction condensate hold columns Reviewed NCS postings on enclosures in the 4-Burner system for IROFS BRC-10 and other NCS IROFS Reviewed assumptions for accident sequences and IROFS (e.g. that fire walls are present, conservative assumptions related to flow through pipes, evacuation time)
Safety Control Support Programs (IP Section 02.04)
The inspectors assessed additional management measures that support the availability and reliability of the selected safety controls to verify these were implemented in accordance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors conducted the following:
Reviewed WR 309294 and 318203 related to IROFS FMF-24 and 25 maintenance Reviewed calibration records for pressure instruments, weight scales, and other components associated with IROFS BRC-1, 3, 16, 17, 20, 23, 26, 28, and 29 Reviewed run sheets documenting processing in the four burner system on June 16-18, 2025 Interviewed calibration supervisor regarding calibration of weight scales and pressure instruments for IROFS BRC-1, 3, 16, 17, 20, 23, 26, 28, and 29 Review setpoint analyses related to IROFS BRC-23, 24, 26, 27, 28, 29, BLW-4, and BPF-15 Interviewed various licensee staff regarding set point analysis for the pressure instruments related to IROFS BRC-23, 26, 28, and 29 Reviewed IROFS Evaluation Records documenting recent IROFS and management measure failures and degradations Reviewed recent problem identification, resolution, and correction system (PIRCS) entries, and associated documents, related to process upsets, unusual conditions, and IROFS and management measure failures and degradations related to operational safety Reviewed four licensee audits of the following:
o Radiological IROFS o
The waste discards radiological accident consequence evaluation o
The risk assessment RA-333-UGENER o
Fuel production fire IROFS Reviewed lesson plans and training material (e.g., 27T-23-0064) related to IROFS for operators in the four burners area and waste handlers Reviewed lesson plans and training material for personnel with responsibility for performing Safety Related Equipment (SRE) testing
6 Observed and reviewed NCS postings in the four burner area, which are listed in NFS-HW-CL-26-08, "Nuclear Criticality Safety BPF Starting Material Processing," Rev. 8 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 IPs, 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 (SNM) 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)
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 106061, Training and Qualifications of an Individual Handling SNM PIRC 106105, Radiological Release of Equipment Fact Finding 106448 and 106453, Use Every Time Runsheet Non-Compliance PIRCs 106493 and 106313, Supervisor Qualifications
7 Event Review (IP Section 03.06)
The inspectors reviewed the plant events listed below to determine if the event warranted the use of formal event review criteria and to evaluate 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):
On May 28, 2025, radiological contamination was identified during the cutting and removal of an abandoned natural gas pipe. The inspectors monitored the response at the location of the contamination including establishing the Safety Work Permit (SWP), controlling the source of the contamination by sealing the pipe ends and the packaging and storage of the material. The inspectors also monitored the licensee's event response in accordance with their Standard Operating Guidance (SOG) for Evaluation of Unusual Incidents, as well as the assessment through their Corrective Action Program (CAP). In addition, the inspectors confirmed that the incident did not meet the threshold for reportability. This pipe had been abandoned for over 25 years and ran between two buildings that date back to 1957 and have historical uses of Low Enriched Uranium, which was consistent with the contaminated material found. No violations more than minor were identified.
On September 18, 2025, a spill of radioactive liquid occurred within the plant process areas. Operators isolated the spill, secured the area around the spill, and cleaned the material from the spill. The inspectors monitored portions of the licensee's response at the location of the spill. The inspectors also monitored the licensee's event response in accordance with their SOG for Evaluation of Unusual Incidents. In addition, the inspectors also confirmed that the incident did not meet the threshold for reportability. The spill posed no challenge to the health and safety of the public or on-site personnel, nor the protection of the environment. No violations of NRC requirements were identified.
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 deficiencies and weakness identified were entered into the CAP and assessed whether the corrective actions were appropriate and effective.
Hazardous Waste Compliance Evaluation completed by the State of Tennessee's Department of Environment and Conservation (TND 00-309-5635 Permit TNHW-157) issued August 4, 2025 Radiation Work Permit (RWP) (IP Section 03.09)
The inspectors reviewed and observed the radiation work permits 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:
8 The inspectors reviewed and observed the Safety Work Permits (SWPs) (An SWP is Nuclear Fuels Service's term that includes RWPs) listed below:
SWP 19104, Work Package 318001, Removal of 303-HV-A568 for Examination of Piping, then Reinstallation, conducted on July 2, 2025.
SWP 19043, Work Package 31313258, Removal of Abandoned Boiler Stack, conducted on July 2, 2025.
SWP 19143, SOP 266-GA Operations of 300 Complex Scrubber, conducted September 6, 2025 SWP 19147, SOP 401-11 Monitoring and Servicing of the Area Process Ventilation System, conducted September 6, 2025 Annual Security and Emergency Preparedness Drills/Exercises (IP Section 03.10)
The inspectors observed the licensees performance during the Emergency Preparedness (EP) and/or security Force-on-Force (FOF) tactical response exercise/training evolutions listed below to determine they were being implemented in accordance with 10 CFR 70.22(I)(3) and/or 10 CFR 73.46(b)(9):
The inspectors observed a quarterly emergency exercise for the first shifts on July 29, 2025. The exercise simulated an earthquake and liquid release. The emergency control operations center (ECC) was activated and the scenario exercised simulated locating and treating of injured individuals with chemical contamination, as well as controlling and containing of the liquid radiological, event classification, and notification of off-site organizations. The inspector evaluated the licensee's performance from the Operations Center, the ECC, and the in plant command post.
On September 9, 2025, the inspectors observed an NRC-graded emergency drill. The exercise simulated a fire in a radiologically controlled area. The ECC was activated and the scenario exercised a live-fire scenario, decontamination of a contaminated victim and transportation to the local hospital, event classification, and notification of off-site organizations.
Security FOF tactical response exercise conducted the evening of August 19, 2025.
Security FOF tactical response exercise conducted the evening of September 22, 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 process listed below:
9 Building 333 U-Oxide IROFS and SREs 88135.05 - Resident Inspection Program Fire Protection (Annual/Quarterly)
The inspectors evaluated the operational status and material condition of fire protection (FP) systems, structures, and components (SSCs) to verify compliance with the FP 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.
Fire Area Walkdown (IP Section 03.01)
The inspectors walked down and evaluated the fire area listed below:
Building 302 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 controls following maintenance.
Post-Maintenance Testing (IP Section 03.01)
The inspectors directly observed and reviewed the post-maintenance test listed below:
Work Request 319262: Replace Solenoid HV-5A01B - SRE Tests N333VALHV5A01A and N333VALHV5A01B 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 ISAs.
Surveillance and Calibration Testing (IP Section 03.01)
The inspectors directly observed and reviewed the surveillance tests listed below:
N333XDRAINH3A26, N333XDRAINH3A27, N333XDRAINH3A, system drains on July 30, 2025.
RADIOLOGICAL CONTROLS 86740 - Inspection of Transportation Activities
10 The inspectors evaluated select aspects of the licensees Transportation Activities program to determine whether the licensee has established and is maintaining an effective, management-controlled program; to ensure radiological and nuclear safety in the receipt, packaging, delivery to a carrier and, as applicable, the private carriage of licensed radioactive materials; and to determine whether transportation activities are in compliance with the applicable NRC 10 CFR Parts 20 and 71 regulations and Department of Transportation (DOT) (49 CFR Parts 171-178) transport regulations.
Preparation of Packages for Shipment (IP Section 02.01)
The inspectors examined the licensees procedures and shipment records and observed actual package preparations and operations to verify compliance with the regulations above.
Specifically, the inspectors reviewed, verified, and observed the following:
NFS-WST-026 NFS-WST-036 SOP 409-SEC 45 Three completed Versa-Pac shipping packages Three completed LR-230 shipping packages Walkdown of LR-230 shipment Walkdown to observe ES-3100 receipt Walkdown of building 440 to observe all packages Delivery of Completed Packages to Carriers (IP Section 02.02)
The inspectors examined the licensees procedures and shipment records and observed actual transport operations and activities to determine that the licensee met package delivery requirements. Specifically, the inspectors reviewed or observed the following:
NFS-WST-026, Handling/Shipping Instructions for the ES-3100 Drum NFS-WST-036, Handling and Packaging of the Versa-PAC SOP 409-SEC 45, BPF, Loading and Staging LR-230 Containers Observed loading, leak testing, and radiation survey of LR-230 shipment Receipt of Packages (IP Section 02.03)
The inspectors examined the licensees procedures and records of incoming shipments to verify compliance with 10 CFR 20.1906 and applicable license requirements. Specifically, the inspectors reviewed the following:
NFS-WST-026, Handling/Shipping Instructions for the ES-3100 Drum NFS-WST-036, Handling and Packaging of the Versa-PAC SOP 409-SEC 45, BPF, Loading and Staging LR230 Containers Three completed Versa-Pac shipping packages Three completed LR-230 shipping packages Walkdown of Shipping and Receiving (S&RV) to observe receipt of ES-3100 packages One completed ES-3100 receipt documentation Records and Reports (IP Section 02.04)
11 The inspectors examined the licensees procedures and records for recordkeeping and reports to verify compliance with the regulations above. Specifically, the inspectors reviewed the following:
10 CFR 71.95 Day Report, Corrosion on LR-230 (Liquid-Rad Transport Unit) 10 CFR 71.95 Day Report, Presence of Water in ES-3100 Shipping Package General License Requirements (IP Section 02.05)
The inspectors reviewed the license utilized for shipment of radioactive material packages to verify compliance with 10 CFR 71, Subpart C. Specifically, the inspectors reviewed:
Certificate of Compliance (CoC) -9342, Versa-Pac Certificate of Compliance - 9291, Liqui-Rad Transport Unit Package (LR-230)
Certificate of Compliance - 9315, ES-3100 User Registration for Certificate of Compliance for No. 9342 User Registration for Certificates of Compliance for Nos. 9288 and 9291 56T-24-0170, Quality Assurance Program for Shipping Packages for Radioactive Material Management Controls (IP Section 02.06)
The inspectors reviewed the system of management controls for transportation activities to verify compliance with licensee instructions and procedures. Specifically, the inspectors reviewed:
Letter of Authorization, Loading Waste Items into Versa-Pac without Aluminum Hydroxide Fill Indoctrination and Training Program (IP Section 02.07)
The inspectors conducted interviews, reviewed training and indoctrination documentation, and observed activities for workers involved in transport activities to verify compliance with Chapter 11 of the licensee application. Specifically, the inspectors:
Reviewed Samples of personnel training documents Interviewed the following personnel about training:
o T&WM Shipping Unit Manager o
T&WM Operation Manager o
Waste Engineer Observed LR-230 loading and interviewed operators about training Quality Assurance Program (IP Section 02.08)
The inspectors reviewed the quality assurance document to verify compliance with the licensees quality assurance (QA) program. Specifically, the inspectors reviewed:
12 56T-24-0170, Quality Assurance Program for Shipping Packages for Radioactive Material Audit Program (IP Section 02.09)
The inspectors reviewed the latest audit and/or assessment reports to verify compliance with 10 CFR 71.137. Specifically, the inspectors reviewed:
Transportation Quality Assurance Program - Quality Assurance Audit (QA 11)
Transportation Quality Assurance Program - Quality Assurance Audit (QA 08)
Transportation Quality Assurance Program - Quality Assurance Audit (QA 08)
Procurement and Selection of Packagings (IP Section 02.10)
The inspectors examined the licensees packaging, including those provided from a vendor and reviewed procedures and records to verify compliance with the Federal regulations above. Specifically, for packaging that is used by the licensee to transport or to deliver licensed material to a carrier for transport, the inspectors reviewed the following:
Walkdown of area 310 to observe LR-230 packages Walkdown of S&RV to observe ES-3100 packages Certificate of Compliance - 9291, Liqui-Rad Transport Unit Package (LR-230)
Certificate of Compliance - 9315, ES-3100 Preparation of Packages for Shipment (IP Section 02.11)
The inspectors examined the licensees package markings, documentation, and records to verify compliance with applicable parts of the Federal regulations above. Specifically, the inspectors reviewed:
LR-230 package marking ES-3100 package markings Soft-sided package markings Versa-Pac Markings Three completed Versa-Pac shipping packages Three completed LR-230 shipping packages Periodic Maintenance of Packagings (IP Section 02.12)
The inspectors examined the licensees procedures and records to verify compliance with applicable parts of the Federal regulations above. Specifically, the inspectors reviewed the following:
NFS-WST-022, Waste Packaging Selection, Procurement, and Inspection NFS-WST-026, Handling/Shipping Instructions for the ES-3100 Drum NFS-WST-036, Handling and Packaging of the Versa-PAC SOP 409-SEC 45, BPF, Loading and Staging LR230 Containers
13 No maintenance activities were observed Records, Reports, and Notifications (IP Section 02.13)
The inspectors reviewed the licensees records and procedures for recordkeeping and reports to verify that a system is in place to verify compliance with the Federal regulations above. Additionally, the inspectors followed-up on event notifications related to two separate 10 CFR 71.95 60-day reports. Specifically, the inspectors reviewed the following:
Three completed Versa-Pac shipping packages Three completed LR-230 shipping packages Reviewed 10 CFR 71.95 60 Day Report, Corrosion on LR-230 (Liquid-Rad Transport Unit) and the following corrective actions:
o P103101 o
P105329 Reviewed 10 CFR 71.95 Day Report, Presence of Water in ES-3100 Shipping Package and the following corrective actions:
o P92103 o
P92156 o
P92157 FACILITY SUPPORT 88051 - Evaluation of Exercises and Drills The inspectors observed and evaluated the licensees graded biennial exercise conducted on September 9, 2025, as well as briefings and critiques involving both on-site and off-site participants to verify compliance with 10 CFR 70.22(i)(3)(xii) and the Nuclear Fuel Services Emergency Plan, Rev. 30. The scenario involved a fire, vehicle explosion, and potentially contaminated personnel with injuries.
Exercise Planning (IP Section 02.01)
The inspectors reviewed the emergency exercise scenario, discussed the exercise objectives with licensee personnel, observed controller meetings, and walked down the plant areas before the exercise to verify compliance with the EP, Emergency Plan Implementing Procedures (EPIPs), and 10 CFR 70.22(i)(3)(xii). The inspectors reviewed or observed the following:
The frequency of exercises conducted by the licensee The scenario as it related to testing all elements of the EP No pre-staging of equipment in preparation for the exercise Duties and responsibilities for exercise personnel including controllers, evaluators, and observers The controllers' meeting for the emergency exercise The objectives of the exercise and the expectations from responders/participants The post-drill critiques for the emergency exercise
14 Exercise Execution and Emergency Plan Implementation (IP Section 02.02)
The inspectors observed the initiation of the emergency exercise, the activation of the ECC and Emergency Response Organization, classification of the event, notification of off-site response organizations, establishment of the incident command post, implementation of field response teams, reviewed on-site and off-site communications, and releases and notifications to verify compliance with the EP, EPIPs, and 10 CFR 70.22(i)(3)(xii). The inspectors observed and reviewed the following:
The licensees analysis of plant conditions including assessment and classification of the accident scenario within the allowable time limits Staffing for all ECC/emergency organization positions Drafting of off-site notifications including a review of content and time of issuance On-site communication to occupational workers as it related to protective actions Occupational workers participation in protective actions and the process to conduct personnel accountability Press release approval and issuance Emergency Control Director (ECD) control of the ECC/emergency organization and drill Dose assessor use of dose software Response coordinators recommendations regarding conditions for terminating the event and restarting normal operations Recovery and re-entry recommendations implemented by the ECC/emergency organization Members of the licensees emergency response team assembly at designated assembly areas and the arrival of off-site emergency responders to include the Erwin Fire Department, local ambulance providers, and a medical helicopter Establishment of boundaries for triage and contamination control Treatment of contaminated and injured personnel Performance of surveys after processing out the injured personnel Response to emerging situations to address the exercise scenario and meet the exercise objectives The On-Scene Commander's control of the emergency response team and coordination of actions with off-site emergency responders Critiques, Exercise Control, and Identification and Resolution of Problems (IP Section 02.03)
The inspectors observed the staff critiques of the emergency exercise and reviewed the licensees related CAP entries to verify compliance with the EP, EPIPs, and 10 CFR 70.22(i)(3)(xii). The inspectors reviewed and observed the following:
Critiques conducted by the licensee in which both licensee participants and off-site responders provided comments Discussions pertaining to whether exercise objectives were met Documented deficiencies identified during critiques including items planned for entry into the licensees CAP
15 INSPECTION RESULTS WER 10 CFR 71.95 - 60 Day Report, Presence of Water In ES-3100 Shipping Package WER 07000143/2024-002-00 86740
==
Description:==
On October 14, 2024, NFS submitted its 60 day report that water had been found on August 14, 2024, upon receipt of two ES-3100 shipping packages (USA/9315/B(U)F-96) that had been shipped from NFS.
The Safety Analysis Report for Packaging (SARP), Chapter 7, "Operating Procedures," states incidents requiring notification include adverse conditions, such as entrapped moisture. NFS' subsequent investigation identified an overhead leak in the storage area that had resulted in water intrusion into the ES-3100 packages via the openings for the tamper indicating devices.
See ML24358A156.
During the transportation inspection the week of July 28, 2025 the NRC inspectors reviewed the above 10 CFR 71.95 60 Day Report, Presence of Water in ES-3100 Shipping Package and the corrective actions. As part of the inspection walkdowns of Shipping and Receiving and ES-3100 receipt process were observed to verify implementation of corrective actions. The review concluded that the corrective actions were being implemented and no further follow up is required.
WER 10 CFR 71.95 - 60 Day Report, Corrosion on LR-230 WER 07000143/2023-001-00 86740
==
Description:==
On May 22, 2023, NFS reported: "On March 28, 2023, NRC Inspection personnel identified corrosion on a Liquid Rad Transport Unit (LR-230) (USA/9291/B(U)F-96).
The Safety Analysis Report for Packaging (SARP), Chapter 7, "Operating Procedures," states the unit should not be used if corrosion is discovered on the exterior surface. The NFS operating procedure did not specifically include corrosion on the preload inspection checklist.
As a result, LR-230 units were shipped with corrosion present. NFS has determined that this event is reportable per 10 CFR.71.95(b). In accordance with 10 CFR 71.95(c), NFS is providing a written report within 60 days of the discovery of this event (Enclosure 1 )."
See ML23146A041 for the 60 day report.
See ML23171B104 for the HQ Transportation IR in which this issue was first identified by the NRC.
During the transportation inspection the week of July 28, 2025 the NRC inspectors reviewed the above 10 CFR 71.95 60 Day Report, Corrosion on LR-230 (Liquid-Rad Transport Unit) and the corrective actions. As part of the inspection walkdowns, a LR-230 shipment was observed to verify the corrective actions were being implemented by NFS personnel. The review concluded that the corrective actions were being implemented and no further follow up is required.
16 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On November 20, 2025, the inspectors presented the integrated inspection results to Ronald Dailey and other members of the licensee staff.
On September 09, 2025, the inspectors presented the emergency exercise evaluation results to Frank Kerns and other members of the licensee staff.
On July 31, 2025, the inspectors presented the operational safety and transportation activities inspection results to Jeff Messaros and other members of the licensee staff.
17 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date PIRC 103101 Water found in ES-3100 08/14/2024 PIRC 105329 Water found in bottom of ES-3100 04/30/2025 PIRC 92103 NRC Inspector Identified Potential LR-230 package integrity issue 03/29/2023 PIRC 92156 NRC Identified Procedure Difficulty 04/04/2023 Corrective Action Documents PIRC 92157 NRC Identified Procedure Difficulty 04/04/2023 Engineering Drawing for ES-3100 Package Drawings Engineering Drawing for Liqui-Rad Transport Unit Renewal of Certificate of Compliance No.93115 for the Model No. ES-3100 Package 01/05/2021 Engineering Evaluations DOE Safety Evaluation Report for CoC -9315 Amendment for the Model ES-3100 Package 04/22/2021 User Registration for Certificate of Compliance for No.
9342 09/15/2011 Training documents for Transportation and Waste Personnel Amendment and Renewal of Certificate of Compliance No. 9291 for the Model No. Liqui-Rad (LR) Transport Unit Package 02/13/2019 User Registration for Certificates of Compliance for No.
9288 and 9291 06/10/2025 10 CFR 71.95 - 60 Day Report, Presence of Water in ES-3100 Shipping Package 10/14/2024 10 CFR 71.95 60 Day Report, Corrosion on LR-230 (Liquid-Rad Transport Unit) 05/22/2023 Certificate of Compliance (CoC) -
9342 Versa - PAC Rev. 18 Certificate of Compliance - 9291 Liqui-Rad Transport Unit Package (LR-230)
Rev. 12 86740 Miscellaneous Certificate of Compliance - 9315 ES-3100 Rev. 14
18 Inspection Procedure Type Designation Description or Title Revision or Date LOA-WST-25-003 letter of Authorization, Loading Waste Items into Versa-Pac without Aluminum Hydroxide Fill 07/22/2025 56T-24-0170 Quality Assurance Program for Shipping Packages for Radioactive Material Rev. 21 NFS-WST-022 Waste Packaging Selection, Procurement, and Inspection Rev. 17 NFS-WST-026 Handling/Shipping Instructions for the ES-3100 Drum Rev. 19 NFS-WST-036 Handling and Packaging of the Versa-PAC Rev. 5 SOP 409-SEC 45 BPF, Loading and Staging LR230 Containers Rev. 18.E SOP-335-K NNSS Certification and Shipping Documentation Rev. 26 SOP-335-Q WCS Certification and Shipping Documentation Rev. 3 Procedures WST-SWI-24-037 Certification of Shipments going to Energy Solutions, LLC.
12/01/2024 56T-23-0085 Transportation Quality Assurance Program - Quality Assurance Audit (QA-23-11) 06/08/2023 56T-24-0091 Transportation Quality Assurance Program - Quality Assurance Audit (QA-24-08) 06/06/2024 Self-Assessments 56T-25-0075 Transportation Quality Assurance Program - Quality Assurance Audit (QA-25-08) 04/22/2025 Multiple completed LR-230 shipping packages Multiple Completed Versa-Pac Shipping Packages Shipping Records ES-3100 receipt documentation.
SA-00031 Setpoint Analysis for BPF-15 04/05/2021 SA-00042 Setpoint Analysis for BRC-023, BRC-024 03/07/2022 SA-00044 Setpoint Analysis for BRC-026, BRC-027 03/27/2023 SA-00045 Setpoint Analysis for BRC-028, BRC-029 03/27/2023 Calculations SA-00307 Setpoint Analysis for BLW-004 06/23/2015 PIRC 104791 Operational Safety related PIRC Entry 02/02/2025 PIRC 105447 Operational Safety Related PIRC 05/14/2025 PIRC 105706 Operational Safety Related PIRC 06/10/2025 PIRC 105831 Operational Safety Related PIRC 06/22/2025 PIRC 105884 Operational Safety Related PIRC 06/29/2025 88020 Corrective Action Documents PIRC 105900 Operational Safety Related PIRC 07/02/2025
19 Inspection Procedure Type Designation Description or Title Revision or Date PIRC 106115 NRC Identified Observation 07/30/2025 PIRC 106195 NRC Identified Observation 08/07/2025 Corrective Action Documents Resulting from Inspection PIRC 106197 NRC Identified Observation 08/07/2025 21T-19-0773 Radiological Accident Consequence Evaluation BLEU Prep Facility Rev. 8 21T-22-0127 BPF Four Reactor System, Radiological Accident Consequence Evaluation Rev. 0 21T-25-0021 Blended Low-Enriched Uranium Preparation Facility Integrated Safety Analysis Summary Rev. 22 FHA-FRE B304 Fire Risk Evaluation for Building 304 Rev. 0 PHA-304-CONV BPF U-Metal Processing Systems Rev. 6 PHA-333-CONDENSATE DISCHARGE BPF Solvent Extraction Condensate Discharge Tank Rev. 1.0 Engineering Evaluations PHA-333-SCRUBBER BPF Process Scrubber Rev. 3 27T-22-2105 SRE Initial Training Lesson Plan 10/13/2022 27T-22-2362 SRE Refresher Training Lesson Plan 09/08/2022 27T-23-0064 BPF Four Reactor System 04/10/2023 27T-24-2117 TWM HEU Material Handler Initial Training Lesson Plan 07/25/2024 27T-25-0008 333 Downblending Commons 02/14/2025 IROFS 304-CONV Items Relied on for Safety (IROFS) and Safety-Related Equipment (SRE) - BPF Starting Material Processing Rev. 15 Miscellaneous SRE Test N333VALVHV5A01A and N333VALVHV5A01B SRE Test for isolation valves HV-5A01A and HV-5A01B associated with IROFS BLW-4 03/04/2025 IER-20250007 IROFS Evaluation Records 02/24/2025 IER-20250008 IROFs Evaluation Records 05/15/2025 IER-20250011 IROFs Evaluation Record 06/11/2025 IER-20250012 IROFs Evaluation Record 06/26/2025 IER-20250013 IROFs Evaluation Record 07/09/2025 IER-20250014 IROF Evaluation Records 07/07/2025 Operability Evaluations IER-20250015 IROFs Evaluation Record 07/28/2025
20 Inspection Procedure Type Designation Description or Title Revision or Date IER-20250016 IROFs Evaluation Record 07/28/2025 LOA 2328Z-052-02 Testing of the BPF Utility Backflow Prevention Skids 03/14/2025 N304XXXXPCV3J01 SRE Test Completed 03/14/2025 N304XXXXPCV3J02 SRE Test Completed 03/14/2025 N304XXXXPCV3K01 SRE Test Completed 03/14/2025 N304XXXXPCV3K02 SRE Test Completed 03/14/2025 N304XXXXPCV3L01 SRE Test Completed 03/14/2025 N304XXXXPCV3L02 SRE Test Completed 03/14/2025 N304XXXXPCV3M01 SRE Test Completed 03/14/2025 N304XXXXPCV3M02 SRE Test Completed 03/14/2025 N304XXXXPSV3J01 SRE Test Completed 03/14/2025 N333MONITR4COND SRE Test 07/15/2025 N333XFILTER6F10 SRE Test 01/08/2025 N333XFILTER6F16 SRE Test 01/06/2025 N333XFILTER6G21 SRE Test 09/19/2024 N333XFILTER6G22 SRE Test 09/19/2024 N333XFILTER6G24 SRE Test 01/06/2025 NFS-ACC-16 Procedure for NDA of 333 Building Scrubber System, Raffinate Tanks, and the Process Off-Gas Ductwork using a Portable NDA System Rev. 10 NFS-EC-01 Calibration of Weight or Mass Measuring Systems Rev. 14 NFS-EC-05 Calibration of Pressure Instruments Rev. 8 SOP 409 Section 11 BPF Condensate Discard Tank Transfer to WWTF Rev 20A SOP 409 Section 25 333 BPF Scrubber Blowdown Tank Rev. 7 Procedures SOP 409 Section 42 304 Processing System Rev. 23
21 Inspection Procedure Type Designation Description or Title Revision or Date 21T-23-0725 Third quarter 2023 ISA Audit - IROFS All Radiological 09/23/2023 21T-25-0282 Second quarter 2025 ISA risk assessment audit - RA-333-UGENER 04/07/2025 21T-25-0396 Second quarter 2025 ISA audit for waste discards radiological ACE 04/30/2025 Self-Assessments 21T-25-0497 Second quarter 2025 ISA IROFS audit for fuel production fire IROFS 06/05/2025 WR 309294 Work Request to repair component of IROFS FMF-25 07/06/2023 Work Orders WR 318203 Work Request to repair component of IROFS FMF-24 06/30/2025 Corrective Action Documents PIRC 106638 Emergency Preparedness Graded Exercise Critique Items 09/25/2025 Emergency Exercise/Scenario 08/15/2025 Miscellaneous NFS-GH-903 Emergency Plan Rev. 30 NFS-HS-E-03 Emergency Response Organization Rev. 40 NFS-HS-E-04 Fire Reporting and Response Rev. 44 NFS-HS-E-07 On-Site Radiological Emergency Assessment Rev. 38 NFS-HS-E-08 Off-Site Radiological Emergency Assessment Rev. 35 88051 Procedures NFS-HS-E-09 Off-Site Dose Projection for Radiological Emergency Rev. 35 Fact Finding PIRCS 106448 & 106453 Use Every Time Runsheet Non-Compliance 09/09/2025 Investigation 39866 Supervisor Qualifications 05/24/2024 Investigation 41436 Evaluate Cause of Use Every Time Procedure Issues and Corrective Actions 07/18/2025 Investigation 41454 Radiological contamination identified during cutting and removal of abandoned natural gas pipe 06/04/2025 PIRC 105447 Use Every Time Procedure Usage 05/14/2025 PIRC 105586 Radiological contamination identified during cutting and removal of abandoned natural gas pipe 05/28/2025 PIRC 105825 TEDC Inspection Item 06/20/2025 PIRC 105826 TEDC Inspection Item 06/20/2025 PIRC 105827 TEDC Inspection Item 06/20/2025 88135.02 Corrective Action Documents PIRC 106061 Training and Qualifications of an Individual Handling Special Nuclear Material 07/23/2025
22 Inspection Procedure Type Designation Description or Title Revision or Date PIRC 106061 Fact Finding Evaluation Training and Qualifications of an Individual Handling Special Nuclear Material Rev. 1 PIRC 106105 Radiological Release of Equipment 07/29/2025 PIRC 106105 Fact Finding Evaluation Radiological Release of Equipment 08/06/2025 PIRC 106127 Critique for Emergency Preparedness Exercise Conducted July 29, 2025 07/31/2025 PIRC 106313 Supervisor Qualifications 08/19/2025 PIRC 106448 Use Every Time Procedure Usage 09/04/2025 PIRC 106449 Use Every Time Procedure Issues 09/04/2025 PIRC 106453 Use Every Time Procedure Usage 09/04/2025 PIRC 106460 Damaged Gasket Material in POG Line 09/06/2025 PIRC 106493 Supervisor Qualifications 08/26/2025 PIRC 106548 Recovery Column Broken Reducer 09/18/2025 PIRC 106638 Emergency Preparedness Graded Exercise Critique Items 09/25/2025 PIRC 1196313 Supervisor Qualifications 08/19/2025 PIRC 106079 Use Every Time Procedure for Discards not Completed Correctly 07/24/2025 Corrective Action Documents Resulting from Inspection PIRC 106080 Incorrect Container Added to Process 07/24/2025 Emergency Exercise/Scenario 08/15/2025 2IT-25-0621 Justification of Release of Concrete Saw from Protected Area 07/31/2025 Fire Impairment 2025-060 Fire Trace 30A 09/08/2025 Fire Impairment 2025-061 Fire Trace 30B 09/08/2025 Fire Impairment 2025-062 Fire Trace 31A 09/08/2025 Fire Impairment 2025-063 Fire Trace 31B 08/09/2025 Miscellaneous Fire Impairment 2025-064 Fire Trace 32A 09/08/2025
23 Inspection Procedure Type Designation Description or Title Revision or Date Fire Impairment 2025-065 Fire Trace 32B 09/08/2025 OPR-TB-SEP25-07 Supervisor Position Requirements 09/29/2025 SOG for Evaluation of Unusual Incident -
Attachment A Unusual Incident Evaluation Flow Chart Spill from broken column 09/18/2025 SOG for Evaluation of Unusual Incident -
Attachment A Unusual Incident Evaluation Flow Chart Radiological contamination identified during cutting and removal of abandoned natural gas pipe 05/28/2025 NFS-ACC-010 Procedure for Tamper Sealing Rev. 41 NFS-ACC-026 Item Control of Special Nuclear Material Rev. 17 NFS-GH-63 Unrestricted Equipment/Item Release Rev. 4 NFS-GH-903 Emergency Plan Rev. 30 NFS-HS-A-50 Guidelines for Government Agency Notifications Rev. 28 NFS-OPS-001 Conduct of Operations Rev. 24 SOG EP-01 SOG for Evaluation of Unusual Incidents Rev. 5 SOP 266-GA Operations of 300 Complex Scrubber Rev. 32.B SOP 387, Section 1 Documentation and Work Processes for the Development Lab Rev. 13 Procedures SOP-401-11 Monitoring and Servicing of the Area Process Ventilation System Rev. 26.E SWP 19043 Work Package 31313258, Removal of Abandoned Boiler Stack 06/30/2025 Radiation Work Permits (RWPs)
SWP 19104 Work Package 318001, Removal of 303-HV-A568 for Examination of Piping, then Reinstallation 07/02/2025 Self-Assessments TND 00-309-5636 Permit TNHW-157 Hazardous Waste Compliance Evaluation Inspection Notice of Violation - Nuclear Fuels Services, Inc.
08/04/2025 WR 313367 POG - Drain and Remove Tee and Replace with a Straight Spool Piece 09/05/2025 Work Orders WR 318403 Remove and Replace Damaged Gasket 09/06/2025
24 Inspection Procedure Type Designation Description or Title Revision or Date WR 318436 POG Connection Cleanout 09/07/2025 Corrective Action Documents PIRC 101728 SRE equipment failed to operate as designed 07/12/2025 333-F0052-D Utility Distribution Nitric Acid Diagram Rev. X 333-F0074-D BPF Plant Air Instrument Tree Sheet 2 Rev. Q 333-F0398-D BPF U-Oxide P&ID Sheet 1 Rev. Z 333-F0399-D BPF U-Oxide P&ID Sheet 2 Rev. W 333-F0400-D BPF U-Oxide Dissolution P&ID Sheet 1 Rev. QQ 333-F0401-D BPF U-Oxide Dissolution P&ID Sheet 2 Rev. OO 333-F0402-D BPF U Oxide 3 Day Test Columns P&ID Sheet 3 Rev. Y 333-F0418-D BPF U-Oxide Interlock Narrative Rev. N Drawings 333-F0469-D BPF Bag Filter 3F01 and 3F02 P&ID Rev. N 21T-25-0386 Items Relied on for Safety (IROFS) and Safety Related Equipment (SRE) - Building 333 U-Oxide Rev. 41 54T-13-0019 Nuclear Criticality Safety Evaluation for the Dissolution of Uranium and High Enriched Uranium Storage Columns Rev. 20 CES-00013 BUM-052, BUM-053, BUM-054 and BUM-055, N333DISSLVLSYSA and N333DISSLVLSYSB - Complex Electrical SRE Narrative Rev. 0 CES-00013 BUM-052, BUM-053, BUM-054 and BUM-055, N333DISSLVLSYSA and N333DISSLVLSYSB - Complex Electrical SRE Checklist Rev. 0 SA-00306 Setpoint Analysis for BUM -045 08/05/2014 Engineering Evaluations SA-00385 Setpoint Analysis for BUM-052, BUM-053, BUM 054, and BUM-055 03/09/2015 N333DISSLVLSYSA SRE Test 06/16/2025 N333DISSLVLSYSB SRE Test 06/16/2025 N333LVLALRM3F04 SRE Test 02/10/2025 N333VALVEBA3A25 SRE Test 02/10/2025 N333VALVEBA3A29 SRE Test 07/25/2025 N333VALVEBA3B25 SRE Test 02/26/2025 N333VALVEBA3B29 SRE Test 07/12/2024 88135.04 Procedures N333VALVEBA3B29 SRE Test 07/14/2025
25 Inspection Procedure Type Designation Description or Title Revision or Date 013-E0070-D Protection Facility Fire Protection Smoke Detector Installation Rev. N 302-F0125-D Area 900 P&ID Sheet 1 Rev. NN 302-F0331-D Area F P&ID Sheet 2 Rev. KK 302-F0337-D Area G P&ID Sheet 1 Rev. AQ 302-F0924-D 300 Complex Isopropyl Alcohol P&ID Rev. K Drawings 312-F0026-D Bulk Chemical Storage, Isopropyl Alcohol & Hydroxide Tanks P&ID Rev. BB 21X-23-0009 Items Relief on For Safety (IROFS) and Safety-Related Equipment (SRE) - Buildings 302and 303 Area 900 Rev. 21 21X-24-0059 Fire Hazard Analysis Building 302 Rev. 2 21X-25-0033 Items Relief on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building 302 Uranium Recovery Facility Areas F, G, H, I and J Rev. 25 Engineering Evaluations CES-00004 Complex Electrical SRE Narrative for N302HS2903XAL15, N302WIRES33ZON4, N303HS2903XAL15, N303WIRES33ZON3 11/14/2022 N302HS2903XAL15 SRE Test 08/25/2025 N302TEMPGAG0G04 SRE Test 05/10/2025 N302TEMPGAG0G08 SRE Test 05/10/2025 N302VAVLEHV2904 SRE Test 02/06/2025 N302WIRES333ZON4 SRE Test 09/18/2024 N302WIRES33ZON4 SRE Test 09/18/2024 N302WOGVNT0G02A SRE Test 07/29/2023 N302XCOLUMN0F14 SRE Test 05/22/2025 N302XFLOWFS0F10 SRE Test 04/25/2025 N302XFRDAMP002 SRE Test 03/10/2025 N302XFRDAMP003 SRE Test 03/10/2025 N302XFRDAMP004 SRE Test 03/10/2025 88135.05 Procedures N302XWOGVNT0G01 SRE Test 06/30/2025 Corrective Action Documents PIRC 106447 Failure of SRE Test N333VALVHV5A01A 09/04/2025 88135.19 Drawings 333-F0600-D BPF Condensate Discharge Tank P&ID Rev. S3
26 Inspection Procedure Type Designation Description or Title Revision or Date Engineering Evaluations 2IT-25-0387 Items Relied on for Safety (IROFS) and Safety-Related Equipment *SRE) - Building 333 Liquid Discards Rev. 11 N333VALHV5A01A SRE Test 09/09/2025 Procedures N333VALHV5A01B SRE Test 09/09/2025 Work Orders Work Request 319262 Replace Solenoid HV-5A01B 09/05/2025 333-F0398-D BPF U-Oxide P&ID Sheet 1 Rev. Z 333-F0400-D 333-U-Oxide Dissolution P&ID, Sheet 1 Rev. QQ Drawings 333-F0404-D BPF Nitric Knockout Colum P&ID Rev. Y IROFS-333-U-OXIDE Items Relied on for Safety (IROFS) and Safety Related Equipment (SRE) - Building 333 U-Oxide Rev. 41 SA-00301 Setpoint Analysis for BUM-036, BUM-037, BUM-038, BUM-039 02/10/2010 Engineering Evaluations SA-00384 Setpoint Analysis for BUM-050 and BUM-051 12/15/2021 N333XDRAINH3A26 SRE Test 07/30/2025 N333XDRAINH3A27 SRE Test 07/30/2025 88135.22 Procedures N333XDRAINH3A28 SRE Test 07/30/2025