ML25204A048
| ML25204A048 | |
| Person / Time | |
|---|---|
| Site: | Erwin |
| Issue date: | 07/23/2025 |
| From: | Bradley Davis NRC/RGN-II/DFRSS/FOB1 |
| To: | Dailey R Nuclear Fuel Services |
| References | |
| IR 2025002 | |
| Download: ML25204A048 (1) | |
Text
Ronald Dailey President Nuclear Fuel Services, Inc.
P.O. Box 337 Erwin, TN 37650-0337
SUBJECT:
NUCLEAR FUEL SERVICES - INTEGRATED INSPECTION REPORT 07000143/2025002
Dear Ronald Dailey:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from April 01, 2025, to June 30, 2025, for the Nuclear Fuel Services (NFS) facility.
On July 09, 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.
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, Bradley J. Davis, 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 July 23, 2025 Signed by Davis, Bradley on 07/23/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFRSS RII/DFRSS NAME N. Peterka B. Davis DATE 7/23/2025 7/23/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07000143 License Number:
SNM-124 Report Number:
07000143/2025002 Enterprise Identifier:
I-2025-002-0033 Licensee:
Nuclear Fuel Services, Inc.
Facility:
Nuclear Fuel Services Location:
Erwin, TN Inspection Dates:
April 01, 2025 to June 30, 2025 Inspectors:
N. Peterka, Sr. Fuel Facility Project Inspector T. Sippel, Sr. Fuel Facility Project Inspector R. Skokowski, Senior Resident Inspector Approved By:
Bradley J. Davis, 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 Fuel 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 PLANT STATUS The following facility process areas were operating during the inspection period: Fuel Manufacturing Facility (FMF) and the Blended Low Enriched Uranium (BLEU) Preparation Facility (BPF), which includes the Uranium-Oxide (U-Oxide), solvent extraction and the down blending lines. Normal support services and departments were operational during the inspection period.
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 88015 - Nuclear Criticality Safety The inspectors evaluated selected aspects of the licensees Nuclear Criticality Safety (NCS) program to verify compliance with selected portions of 10 CFR 70, including 70.50, 70.61, 70.62, and Appendix A, Chapter 5, Nuclear Criticality Safety, of the facilitys license application, and applicable licensee procedures.
Criticality Analysis (IP Section 02.01)
The inspectors interviewed licensee staff and reviewed nuclear criticality safety evaluations (NCSEs), and associated assumptions and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.1.1, 5.5.2, 5.5.3, and 5.5.4. Specifically, the inspectors interviewed licensee staff and reviewed the following:
54T-14-0014, "Nuclear Criticality Safety Evaluation for the Can Cleaning System," Revision (Rev.) 3, including the review of what-if analysis, credible abnormal, and non-credible accident sequences 54T-25-0003, "Nuclear Criticality Safety Analysis for Glovebox Solution Wave Modeling," Rev. 0, which was reviewed because it contained a variety of calculations and information supporting the licensee's evaluation of criticality in gloveboxes 54X-22-0012, "Nuclear Criticality Safety Evaluation for the PSL Area 600 and 700A Operations," Rev. 1, including the review of the what-if analysis, calculations, credible abnormal, and non-credible accident sequences 54X-24-0007, "Nuclear Criticality Safety Evaluation for Area 500 and Area 400 Discard Columns of the Production Fuel Facility," Rev. 3, focusing on the changes made to the current revision
4 54X-97-0010, "Nuclear Criticality Safety Evaluation Report to Determine the Most Reactive Contents," Rev. 0, which was reviewed because it contained a variety of calculations and information supporting the licensee's evaluation of criticality accident sequences and IROFS in 54X-22-0012 70X-97-0008, "Density of Uranium," dated August 15, 1997, which was reviewed because it contained information supporting the licensee's evaluation of criticality accident sequences and IROFS in 54X-22-0012 Criticality Implementation (IP Section 02.02)
The inspectors selected engineered and administrative controls from the licensees integrated safety analysis (ISA) summary to verify proper implementation through a review of process and system descriptions, plant walkdowns, and operator interviews to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.3.5 and 5.3.7. Specifically, the inspectors interviewed licensee staff and reviewed the following controls, and their management measures, associated with the NCSEs listed above:
FA6C-7, administrative control in Area 600 through review of a logsheet in the field, interviews, and review of training material (27X-22-0013) and procedures (SOP 401-06A-303)
FA6C-8, administrative control in Area 600 through walkdown, interviews, and review of procedures (SOP 401-06A-303)
FA6C-12, active engineered control in Area 600 through walkdown, interviews, review of SRE Tests and training material (27X-22-0013)
FA6C-29, administrative control in Area 600 through walkdown, interviews, and review of procedures (SOP 401-06A-303)
FA6C-37, administrative control in Area 600 through interviews, and review of procedures (SOP 401-06A-303)
FA6C-41, passive engineered control in Area 600 through walkdowns and interviews FLW-8, passive engineered control in Can Cleaning through walkdowns FCC-2, administration control in Can Cleaning through walkdowns, review of procedures, and NDA scan results FCC-9, administration control in Can Cleaning through walkdowns and station limit cards the inspectors also reviewed Control Flowdown 54X-24-0005 and 54T 0006 the inspectors walked down uranium recovery and observed SRE test of safety related valves and level switch.
Criticality Operational Oversight (IP Section 02.03)
The inspectors assessed the NCS staffs oversight of plant operators, procedures, and operations of systems involving special nuclear material to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.3.2, 5.3.4, 11.3.2, and 11.5.
Specifically, the inspectors performed the following activities:
5 reviewed the annual NCS refresher training material for operators: SA-NCSREFRESH, "How to Avoid a Criticality;" including reviewing the blank tests reviewed training material for operators (27X-22-0013) which included training on NCS controls in Area 600 reviewed area specific training material for operators (IROFS 303-PSL600700A) which included training on NCS IROFS in Area 600 reviewed training material for operators that was created as a corrective action from a recent event (OPR-TB-MAR25-10, "Hand Carried Containers," dated March 19, 2025) interviewed NCS engineer concerning criticality hazards and control methods, including monitoring for long-term accumulations in the Can Cleaning reviewed NDA logsheet in Can Cleaning (management measure for IROFS FLW-8) reviewed recent NCS audit reports, including NCS-2025-07, NCS-2025-08, and NCS-2025-10 reviewed the annual NCS audit of training: NCS-2025-03, "2024 Nuclear Criticality Safety (NCS) Audit of the Training Program," dated January 16, 2025 interviewed several Area 600 operators concerning criticality hazards and control methods, including the use of IROFS FA6C-7, -8, -29, -37 Criticality Programmatic Oversight (IP Section 02.04)
The inspectors reviewed NCS program procedures and NCS staff qualifications to verify compliance with 10 CFR 70 and applicable sections of the license application, including 2.3.5.1, 5.2, 5.3.3, 5.3.5, and 5.3.6. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:
reviewed quarterly NDA scan results for equipment in the can cleaning area to detect a slow accumulation of uranium in process equipment discussed training and qualification of status of the criticality safety engineers with NCS management the most recent revision to licensee procedures NFS-NCS-DESIGN and NFS-HS-A-67 Criticality Incident Response and Corrective Action (IP Section 02.05)
The inspectors reviewed the licensees criticality accident alarm system (CAAS) and corrective action program (CAP) to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.3.9, 5.4 and 11.6. Specifically, the inspectors reviewed documents and interviewed licensee staff concerning the following:
recent NCS-related CAP entries, and associated documents, including PIRCS 104177, 104236, 104391, 104799, these include CAP items opened as a result of licensee NCS audits of operations 88135.02 - Plant Status
6 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 (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:
1.
Plan of the Day Meetings 2.
Safety and Security Review Council 3.
Problem Resolution Meetings 4.
Technical Review Board Meetings 5.
Scheduled meetings with licensing, security, and facility management 6.
Corrective Action Review Board Meetings Record and Log Reviews (IP Section 03.03)
The inspectors reviewed selected records and logs to assure they were developed, maintained, and reported as required by applicable license and regulatory requirements.
Posting of Notices (IP Section 03.04)
The inspectors reviewed the following notices to determine if they were posted in accordance with 10 CFR 19.11, specifically: NRC Form 3 - NOTICE TO EMPLOYEES: Standards for Protection Against Radiation (Part 20); Notices, Instructions and Reports to Workers; Inspections (Part 19); Employee Protection.
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
7 applicable license requirements.
PIRC 105205, Inhalation Exposure during Filter Replacement, PIRC 105311, Inadvertent Cutting a Plant Air Line During the Removal of Abandoned Utilities, PIRC 105382, Equipment Difficulty, NDA Equipment, Inline Monitor, PIRC 105522, Radiation Worker Training for Contractors, PIRC 105447, Operations during Discard Evolution, PIRC 105596, Processing Near Miss.
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 that 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); as well as 20.2201, 20.2202, and 20.2203 (radiological and environmental events):
SOG-OC-001, Attachment C, Operations Center Response Guide 002, Earthquake. On May 10, 2025, a 4.1 magnitude earthquake originating in Greenback, TN (near Alcoa) occurred at 9:04 a.m. No individuals on the site reported feeling the effects of the quake. The Senior Resident Inspector reported to the site and completed a physical inspection of the major areas and reviewed the licensee's response. No issues identified.
PIRC105557, Electrical power problem resulting in a loss of laboratory ventilation, May 23, 2025. No issues identified.
Audits (IP Section 03.07)
The inspectors reviewed the internal audit listed below to determine whether it had been performed in accordance with 10 CFR 70.22(h)(1) and the license application, specifically: ISAUD-20250011, ISA Chemical Accident Consequence Evaluation. 110 Laboratories - 2nd Quarter 2025.
Procedures (IP Section 03.08)
The inspectors reviewed and observed implementation of the procedure(s) listed below to ensure that safety-significant procedures were developed and/or maintained in accordance with Chapter 11, Management Measures, of the license application, the Change Management System, and implementing procedures: SOP401-09B, Area 900, Rev 35.C - based on issues documented in PIRC 105596, Processing Near Miss.
Radiation Work Permit (RWP) (IP Section 03.09)
The inspectors reviewed and observed the safety work permits (SWPs) (An SWP is NFS's term that includes radiation work permit(s) (RWPs)) listed below to determine whether the RWP contains the information required by Chapter 4, Radiation Safety of the license application, the Radiation Protection Manual; and implementing procedures:
8 SWP 25-29-011, 333 - Complex SWP 25-32-006, Replace Valve 333 HV3B22A 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 evolution listed below to determine they were being implemented in accordance with 10 CFR 73.46(b)(9).
1.
Security FOF tactical response exercise conducted the evening of April 1, 2025.
2.
Security FOF tactical response exercise conducted the evening of May 13, 2025.
3.
Security FOF tactical response exercise conducted the evening of May 14, 2025.
The inspectors observed an emergency response training exercise involving a simulated criticality alarm, evacuation and accounting of personnel during dayshift hours on May 20, 2025.
The inspectors observed a quarterly emergency exercise for the first shifts, on May 20, 2025. The exercise simulated a confirmed criticality event. The emergency operations center (EOC) was activated and the scenario exercised simulated transport of exposed individuals to the local hospital, event classification, and notification of offsite organizations.
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 items relied on for safety (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; and 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 listed processes associated with:
304-CONV IROFs and SREs 304-LA IROFs 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 licensee's procedures. Also, the inspectors evaluated onsite fire brigade performance in response to a fire
9 alarm that was determined to be a false alarm due to a failed detector. The licensee's response was consistent with their procedures.
Fire Area Walkdown (IP Section 03.01)
The inspectors walked down and evaluated the two fire areas listed below:
303 Area 600 o
Fire 6C-001 - 003 o
Fire 6C-010 - 017 o
Fire 6C-019 o
Fire 6C-021 o
Fire 6C-027 - 031 o
Fire 6C-037 - 040 o
Fire 6C-044 o
Fire 6C-046 302-303 Area 600 o
Fire 6 3 o
Fire 6 11 o
Fire 6-13 o
Fire 6-15 Fire Brigade Drill Performance Sample (IP Section 03.02)
On March 31, 2025, The inspectors the observed and evaluated the fire brigade's response to a fire alarm for Building 302 Area F (PIRC 105085). The inspectors evaluated the Fire Brigade's assessment of the situation and follow up actions to implement a fire impairment to remove a failed detector from service. The licensee response was consistent with their procedures.
PIRC 105085: Fire Alarm for Building 302 Area F 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 reviewed the post-maintenance tests listed below. Tests were either observed directly and/or test results were reviewed.
N303XIGNTBSS671, N303XIGNTBSS672, N303XIGNTBSS673 and N303DOORSEAL652, flammable gas igniters and door seals, 06/16/2025 N302XWOGNT0A03, WOG section replacement following SRE failure, 06/11/2025
10 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 and/or calibration tests listed below. Tests were either observed directly or test results were reviewed.
N000CAASSEMIANN, Criticality System Detector Calibration, 04/26/2025, N000CRITDETSYS, Criticality Alarms System Operational Test, 04/26/2025 N302FURDOOR600A, Charge Doors Interlock, 06/13/2025, N302FLAMDETECTR, Flame Detector. 06/13/2025 INSPECTION RESULTS No issues were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On July 9, 2025, the inspectors presented the integrated inspection results to Ronald Dailey and other members of the licensee staff.
On April 24, 2025, the inspectors presented the NCS inspection results to Albert Onley and other members of the licensee staff.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 54T-14-0014 Nuclear Criticality Safety Evaluation for the Can Cleaning System Rev. 3 54T-16-0006 Control Flowdown and Field Verification for the Can Clean System, Revision 3 of NCSE Issued March 12, 2015 Rev. 2 54T-24-0018 Nuclear Criticality Safety Analysis for Seismic Events at Nuclear Fuel Services Rev. 2 54T-25-0003 Nuclear Criticality Safety Analysis for Glovebox Solution Wave Modeling Rev. 0 54X-24-0005 Control Flowdown and Field Verification For PSL Area 600 and 700A Rev. 2 Engineering Evaluations 71T-090028 Glovebox Drain Study 03/05/2009 27T-24-2190 Nuclear Criticality Safety Refresher Training 27X-22-0013 PSL 600/700A Processing 27X-27X-24-0020 Operator Training for Building 302 Common IROFS 303-PSL600700A Items Relied on For Safety (IROFS) and Safety-Related Equipment (SRE) - Building 303 PSL 600 and 700A Rev. 12 NFS-HS-A-108 Miscellaneous NDA Scan Sheet 11/20/2024 Miscellaneous NFS-HS-A-108 Miscellaneous NDA Scan Sheet 03/21/2025 N303VALVEBAE525 SRE Test 02/25/2022 N303VALVEBAE601 SRE Test 03/12/2025 N303VALVEBAF525 SRE Test 03/12/2025 N303VALVEBAF601 SRE Test 03/12/2025 N303VALVEBAG601 SRE Test 03/04/2025 NFS-HS-A-67 Documenting the Safety & Regulatory Review of Facility Changes Rev. 18, 03/04/2025 NFS-NCS-DESIGN Nuclear Criticality Safety Design Considerations Rev. 7, 12/18/2024 Procedures SOP 401-06A-303 Area 600 PSL Rev. 5.c 88015 Self-Assessments NCS-2025-07 Nuclear Criticality Safety Audit of the Nuclear Criticality Safety Evaluation for Area A of the Uranium Recovery Facility, Twelfth Audit 02/24/2025
12 Inspection Procedure Type Designation Description or Title Revision or Date NCS-2025-08 Nuclear Criticality Safety Audit of the Nuclear Criticality Safety Evaluation for the 800-Gallon Liquid Discard Tanks (TANKXX-WF03/WF04 and TANKXX-WD01/WD02), Thirteenth Audit 03/12/2025 NCS-2025-10 Fifth Nuclear Criticality Safety Audit of the Operations Covered Under the Nuclear Criticality Safety Evaluation for PSL Area 700 and 700A 04/15/2025 Fact Finding 105447 303-400, Block and Bleed Valve 05/19/2025 Investigation 138647 Event 98845, reported 1/13/24 02/19/2024 PIRC 104665 Uses Every Time (UET) Procedure for Discard Evolutions 02/07/2025 PIRC 105148 Event 04/06/2025 PIRC 105165 Security Audits and Inspections 04/08/2025 PIRC 105205 Inhalation Exposure during Filter Replacement 04/14/2025 PIRC 105311 Inadvertent cutting a plant air line during the removal of abandoned utilities.
04/28/2025 PIRC 105382 Equipment Difficulty, NDA Equipment, Inline Monitor 05/06/2025 PIRC 105418 ISA Audit results 05/09/2025 PIRC 105421 Earthquake Greenback TN 05/10/2025 PIRC 105447 Operations during Discard Evolution 05/14/2025 PIRC 105522 Radiation Worker Training for Contractors 05/20/2025 PIRC 105585 Emergency Preparedness Exercise Critique 05/28/2025 PIRC 105586 Surface Contamination - pipe bridge from Building 111 to Building 111.
05/28/2025 PIRC 105596 Processing Near Miss 05/29/2025 PIRC 91960 Uses Every Time (UET) Procedure for Discard Evolutions 03/14/2023 PIRC105557 Electrical power problem resulting in a loss of laboratory ventilation, 05/23/2025 Corrective Action Documents PIRC92409 Uses Every Time (UET) Procedure for Discard Evolutions 04/28/2023 Corrective Action Documents Resulting from Inspection PIRC 105194 Corrective Action Document 04/11/2025 303-F0126-D Area 400 Rev. W 88135.02 Drawings 303-F0902-D Area 600 Rev. T
13 Inspection Procedure Type Designation Description or Title Revision or Date Engineering Evaluations 21X-23-0009 IROFS and SRE - Buildings 302 and 303 Area 900 Rev. 21 Miscellaneous ACE000009 Occupational/Environmental Chemical Accident Consequence Evaluation, 110 Laboratories Rev. 8 EP-01 SOG for Evaluation of Unusual Incidents Rev. 5 HFS-GH-39 Radiological Safety Training Rev. 11 N303DOORSEAL652 SRE Test 06/16/2025 N303VALVETWA463 SRE Test 12/30/2024 NFS-CAP-007 Trend Analysis Rev. 4 NFS-CAP-009 The NFS Corrective Action Program Rev. 10 NFS-CAP-009-01 Corrective Action Program (CAP) Screening Process 04/22/2013 NFS-GH-03 Safety Work Permits Rev. 24 NFS-GH-903 Emergency Plan Rev. 30 NFS-HS-A-21-04 Implementing Storm Compensatory Measures Rev. 3 NFS-OE-001 Operating Experience (OE) Program Rev. 3 SOG-OC-001 NFS Operations Center - SOG for Response Guides Rev. 1 SOG-OC-001 Attachment C Operations Center Response Guide 02 - Earthquakes 05/10/2025 SOP 409-SEC-42 304 Processing System Rev. 23 Procedures SOP401-09B Area 900 35.C Drawings 304-F0250-D BPF Four Reactor System L
Engineering Evaluations IROFS 304-CONV IROFS and SRE - 304 CONV Rev. 15 Miscellaneous BPF-PO-003 BPF 304 Processing System Process Outline Rev. 1 LOA-2328Z-057 Processing of JZD-XTI-004 04/15/2025 N304XFILTER6F14 SRE Test 05/13/2025 N304XFILTER6F15 SRE Test 05/13/2025 N304XFILTERVL02 SRE Test 01/21/2025 N304XXXXPCV3J01 SRE Test 03/14/2025 N304XXXXPCV3K01 SRE Test 03/14/2025 N304XXXXPSV3J01 SRE Test 03/14/2025 NFS-GH-43 Safety-Related Equipment Control Program Rev. 34 88135.04 Procedures SOP 401-41 Fuel Manufacturing Process Area LA Rev. 25
14 Inspection Procedure Type Designation Description or Title Revision or Date Self-Assessments 3rd Quarter 2024 ISA Risk Assessment Audit - RA-304-CONV 09/09/2024 Corrective Action Documents PIRC 105085 Fire Alarm for Building 302 Area F 03/31/2025 21X-21-0017 ISA Safety Basis Risk Assessment Support and Justification for 302 Area 600 and 303 Area 600 PSL Rev. 2 21X-24-0019 IROFS and SRE Building 303 PSL 600 and 700A Rev. 12 21X-24-0025 IROFS and SRE Building 302 Areas 600 and 700A Rev. 26 Engineering Evaluations 21X-25-0003 300 Complex Production Areas - Integrated Safety Analysis Summary Rev. 21 Fire System Impairment Permit 2025-17 302-FRDOOR-D328 02/05/2025 Fire System Impairment Permit 2025-18 303-FRDOOR-D372 02/05/2025 Miscellaneous Work Request Number 315962 Fire System Impairment Permit 03/31/2025 FB-001 Standard Operating Guidelines (SOG) for Fire Brigade Operations Rev. 0 N302FLAMDETECTR SRE Test 06/13/2025 N302FURDOOR600A SRE Test 06/13/2025 N302FURDOOR600B SRE Test 02/04/2025 N302N2INDFI0625 SRE Test 12/09/2024 N302N2INDFI0628 SRE Test 08/21/2024 N302N2INDFI0630 SRE Test 08/27/2024 N302NITPURGE605 SRE Test 01/02/2025 N302STRDOORSEAL SRE Test 03/19/2025 N302XFLAREX0601 SRE Test 02/04/2025 N302XFLAREX0602 SRE Test 02/04/2025 N302XX600MAXONS SRE Test 02/04/2025 N303DOORSEAL652 SRE Test 06/16/2025 88135.05 Procedures N303DOORSEAL653 SRE Test 02/27/2025
15 Inspection Procedure Type Designation Description or Title Revision or Date N303DOORSEAL653 SRE Test 02/21/2025 N303FURDOORS601 SRE Test 02/06/2025 N303FURDOORS601 SRE Test 05/19/2024 N303FURDOORS601 SRE Test 05/19/2021 N303FURDOORS602 SRE Test 02/27/2025 N303FURDOORS602 SRE Test 09/18/2018 N303H2DETPSL600 SRE Test 01/29/2025 N303XFURPSLR772 SRE Test 05/05/2025 06:16 N303xFURPSLR772 SRE Test 05/09/2025 01:30 N303XIGNTBSS671 SRE Test 06/16/2025 N303XIGNTBSS671 SRE Test 08/02/2021 N303XIGNTBSS673 SRE Test 06/16/2025 N303XINIGNTBSS672 SRE Test 06/16/2025 N303XX600MAXONS SRE Test 05/01/2020 N303XXXFICS601A SRE Test 09/15/2015 N303XXXFICS601A SRE Test 01/06/2025 N303XXXFICS610A SRE Test 01/06/2025 N303XXXFICS620A SRE Test 01/06/2025 N303XXXFICS630A SRE Test 01/06/2025 N303XXXXFICS671 SRE Test 01/06/2025 N303XXXXFICS672 SRE Test 01/06/2025 N303XXXXXPIS681 SRE Test 01/29/2025 N303XXXXXPIS682 SRE Test 01/29/2025 N393XXXXFICS673 SRE Test 01/06/2025 NFS-GH-27 Impairments to Fire Protection Systems Rev. 19 NFS-GH-62 Control of Combustibles Rev. 16 Corrective Action Documents PIRC 105706 SRE Test 06/10/2025 Engineering Changes ECR-20250742 Replacement of section of clogged WOG (302XWOGVNT0A03) and installation of coupling Rev. 0.0 88135.19 Engineering 2IT-25-0513 IROFS Evaluation Record N302XWOGVNT0A03 06/11/2025
16 Inspection Procedure Type Designation Description or Title Revision or Date Evaluations N302XWOGVNT0A03 SRE Test 06/10/2025 N302XWOGVNT0A03 SRE Test 06/11/2025 N303XIGNTBSS671 SRE Test 06/16/2025 Procedures N303XIGNTBSS673 SRE Test 06/16/2025 Work Orders WR315366 WOG Line Replacement 06/10/2025 Engineering Evaluations SA-00322 Setpoint Analysis for Gamm Detector Calibration
Response
12/18/2019 FM-NFS-HS-05-A Attachment C Gamma Source Exposure Rate Certificate 09/24/2024 HFS-HS-A-21 Operations and Testing of the Criticality, Fire and CO2 Alarm Systems Rev. 41 N000CAASSEMIANN SRE Test 04/26/2025 N000CAASSEMIANN SRE Test 11/16/2024 N000XCRITDETSYS SRE Test 11/16/24 N000XCRITDETSYS SRE Test 04/26/2025 N302FLAMDETECTR SRE Test 06/13/2025 N302FURDOOR600A SRE Test 06/13/2025 88135.22 Procedures NFS-HS-A-05 Calibrating Radiation Monitoring Instruments Rev. 22