ML21116A114

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Westinghouse Columbia Fuel Fabrication Facility, U.S. Nuclear Regulatory Commission Inspection Report Number 0701151/2021001
ML21116A114
Person / Time
Site: Westinghouse
Issue date: 04/26/2021
From: Eric Michel
NRC/RGN-II/DFFI
To: Annacone M
Westinghouse
References
IR 2021001
Download: ML21116A114 (21)
v • d • e


Text

April 26, 2021 Mr. Mike Annacone Vice President, Columbia Fuel Operations and Manager, Columbia Plant Westinghouse Electric Company 5801 Bluff Road Hopkins, SC 29061

SUBJECT:

WESTINGHOUSE ELECTRIC COMPANY - INTEGRATED INSPECTION REPORT 07001151/2021001

Dear Mr. Annacone:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Westinghouse Electric Company. On February 25, March 25, and April 20, 2021, 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,

/RA/

Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection Docket No. 07001151 License No. SNM-1107

Enclosure:

As stated cc w/ encl: Distribution via LISTSERV

ML21116A114 SUNSI Non-Sensitive Publicly Available Review Sensitive Non-Publicly Available OFFICE RII:DFFI/PB2 RII:DFFI/PB2 RII:DFFI/PB2 RII:DFFI/PB2 RII:DFFI/PB2 NAME T. Vukovinsky M. Ruffin N. Pitoniak N. Peterka P. Startz DATE 4/16/2021 4/16/2021 4/16/2021 4/16/2021 4/16/2021 OFFICE RII:DFFI/PB2 NAME E. Michel DATE 4/26/2021 U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT REGION II Docket Number: 07001151 License Number: SNM-1107 Report Number: 07001151/2021001 Enterprise Identifier: I-2021-001-0114 Licensee: Westinghouse Electric Company Facility: Columbia Fuel Fabrication Facility Location: Hopkins, SC Inspection Dates: February 22, 2021 to April 20, 2021 Inspectors: N. Peterka, Fuel Facility Inspector N. Pitoniak, Sr. Fuel Facility Project Inspector M. Ruffin, Fuel Facility Inspector P. Startz, Fuel Facilities Inspector T. Vukovinsky, Sr. Fuel Facility Project Inspector Approved By: Eric C. Michel, Chief Projects Branch 2 Division of Fuel Facility Inspection Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Westinghouse Electric Company, 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.

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REPORT DETAILS PLANT STATUS The Westinghouse Facility converts uranium hexafluoride (UF6) into uranium dioxide using a wet conversion process and fabricated fuel assemblies for use in commercial nuclear power reactors. During the inspection period, normal production activities were ongoing.

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 program to verify compliance with selected portions of 10 CFR 70 including 70.24, 70.61, and 70.62; Chapter 6, Nuclear Criticality Safety Program, of the facilitys license application; and applicable licensee procedures.

Criticality Analysis (IP Section 02.01)

The inspectors interviewed licensee NCS staff and reviewed criticality safety evaluations (CSEs), and supporting documents, to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee NCS engineers and reviewed the following documents related to the Scrap Cage, Pelleting Lines, Pellet Grinder Lines, and other operations:

  • CSE-3-E, "Criticality Safety Evaluation for the Conversion Line Decanter System and Associated Vessels," Revision (Rev.) 12, including the review of normal, credible abnormal, and non-credible accident sequences
  • CSE-3-M, "Criticality Safety Evaluation for the Conversion Quarantine Tank System," Rev. 8, which was reviewed because it contained a variety of calculation and information supporting the licensee's evaluation of accident sequences and IROFS ADUQFLT-128 for backflow prevention
  • CSE-8-C, "Criticality Safety Evaluation for the ADU and Erbia Pellet Sintering Lines," Rev. 11, including the review of what-if analysis, normal, credible abnormal, and non-credible accident sequences
  • CSE-8-D, "Criticality Safety Evaluation for the Pellet Grinder Lines," Rev. 22, including the review of accident scenarios 1 and 2 which cover various potential mass accumulation scenarios 2

Criticality Implementation (IP Section 02.02)

The inspectors selected engineered and administrative controls from the licensees integrated safety analysis (ISA) summary and reviewed process and system descriptions, drawings, plant walkdowns, and operator interviews to verify that the controls were implemented in accordance with applicable requirements in the license application. Specifically, the inspectors interviewed licensee staff and reviewing the following controls associated with the CSEs listed above:

  • administrative mass control IROFS for the pelleting and pellet grinder lines
  • passive engineered geometry control IROFS in the pelleting lines
  • active engineered control IROFS for scrap cage operations 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. Specifically, the inspectors performed the following activities:

  • observed a licensee NCS engineer conduct a weekly audit of the pelleting line operations and reviewed the resulting audit report
  • interviewed licensee operations and maintenance personnel on the maintenance and operation of the criticality accident alarm system
  • interviewed licensee pelleting engineer on the setpoints and maintenance of the active engineered controls Criticality Programmatic Oversight (IP Section 02.04)

The inspectors reviewed NCS program procedures, and audits to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:

  • the most recent triennial external audit of the licensee's NCS program which was documented in the EHS Audit for the Nuclear Criticality Safety Program, dated November 12, 2020
  • the most recent revision to the licensee's procedure for maintaining and testing their criticality accident alarm system, MCP-202037, "GA-6M Criticality Alarm Calibration and SSC Verification (AC-Plant-1-01)," Rev. 32 4

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. Specifically, the inspectors reviewed documents, and interviewed licensee staff concerning the following:

  • recent NCS events, their associated corrective actions, and the reportability determination documented by licensee NCS staff including IR-2020-1192, IR-2020-9312, IR-2020-13859, IR-2020-13903
  • recent CAAS maintenance records and issues including preventative maintenance PM20852a
  • recent NCS evacuation drill records and performance for 2020 88020 - Operational Safety The inspectors evaluated selected aspects of the licensees Operational Safety program to verify compliance with selected portions of 10 CFR 70.24, 70.61, 70.62, and Chapter 3, "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, the description of plant changes submitted to the NRC, and past plant performance documentation. For the process areas of interest, the inspectors selected a sample of accident sequences in nuclear criticality safety, radiation safety, fire safety, and/or chemical 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:

  • ISA-3, Conversion
  • ISA-4, Safe Geometry Dissolver (SGD)
  • CSE-4-A, Criticality Safety Evaluation for Safe Geometry Dissolver System
  • CSE-4-B, Criticality Safety Evaluation for the URRS Sifting/Cleaning Hood
  • CSE-4-D, Criticality Safety Evaluation for the URRS Dirty Dissolver Centrifuge
  • CSE-3-D, Criticality Safety Evaluation for the ADU Conversion Hydrolysis Column with Passive Overflow, Nitrate Vessel and Precipitator
  • CSE-3-M, Criticality Safety Evaluation for the Conversion Quarantine Tank System
  • CSE-3-N, Criticality Safety Evaluation for the UF6 Cylinder Receipt and Handling
  • Conversion Area
  • East Lagoon and Cylinder Removal Area 5

Review of Safety Controls and Related Programs (IP Section 02.02)

The inspectors reviewed process safety controls or items relied on for safety (IROFS) for the above selected accident sequences, including the identification of the licensees assumptions and bounding cases as they 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.

  • CSE-4-A, Criticality Safety Evaluation for Safe Geometry Dissolver System
  • CSE-4-B, Criticality Safety Evaluation for the URRS Sifting/Cleaning Hood
  • CSE-4-D, Criticality Safety Evaluation for the URRS Dirty Dissolver Centrifuge
  • IROFS SGD-114, 122, 123, 124, 125, 126, 127, 141, 142, 143, 117, 150, 121, 128, 129, 144, 118, 119, 120, 155, 161, 162, 163, 164, 165, 130, 147, 131, 158, 159, 160, 113
  • DPH-101, 102, 113
  • SGDCENT-101, 102, 104, 109, 110
  • Cylinder Storage Area
  • CSE-3-D, Criticality Safety Evaluation for the ADU Conversion Hydrolysis Column with Passive Overflow, Nitrate Vessel and Precipitator
  • CSE-3-M, Criticality Safety Evaluation for the Conversion Quarantine Tank System
  • CSE-3-N, Criticality Safety Evaluation for the UF6 Cylinder Receipt and Handling
  • Quarantine Tanks System
  • IROFS ADUHYD-101, 103,104, 105, 106, 908, 910, 911, 912
  • IROFS ADUQTNK-103, 107, 108, 114 Implementation of Safety Controls (IP Section 02.03)

For the selected safety controls listed above, the inspectors reviewed management measures to verify proper implementation in accordance with 10 CFR 70 and Section 3.0 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:

  • Conducted walk-downs to verify implementation of IROFS listed above
  • Reviewed passive IROFS design characteristics to verify IROFS were capable to perform their design function o Independent Technical Review (ITR) for CCF 14573, "Install Additional Drain Holes in Safe Geometry Dissolver Motor Enclosures" o Drawing 301F0EQ02.05. r02 o IROFS DPH-113 Calculation o Product Hold Tanks Passive Overflow Calculation (SGD-130) o Passive IROFS Basis Documentation Extent of Condition Review
  • Reviewed postings and operator aids associated with the clean and dirty dissolvers 6
  • Reviewed procedures associated with the Safe Geometry Dissolver System (procedures listed in document list)
  • East Lagoon Closure Work Plan o US Ecology, Inc., East Lagoon Closure Work Plan and Cylinder Cutting Plan (Attachment G) o CA-002, Columbia Plant Electronic Training and Procedure System (ETAPS) o CSE-9-B, Cylinder Wash o CSE-9-C, UF6 Cylinder Recertification o CA-134, Columbia Plant Significant Event Response Guidelines
  • Reviewed procedures associated with the Hydrolysis Operation
  • Reviewed procedures associated with the Quarantine Tanks System
  • Conducted walk-downs to verify the field conditions matched the design basis assumptions Safety Control Support Programs (IP Section 02.04)

The inspectors assessed additional management measures and license conditions that support the availability and reliability of the selected safety controls to verify these were implemented in accordance with 10 CFR 70 and License Application Chapter 3, "Management Measures," and Chapter 6, "Nuclear Criticality Safety (NCS)

Program." Additionally, the inspectors followed-up on the East Lagoon Closure Plan. Specifically, the inspectors conducted the following:

  • Reviewed the following OMs o OM81012: Q-Tank Raschig Ring Inspection, Ring Level Check and Volume Check o OM81201: ADU Line 1 o OM81202: ADU Line 2 o OM81205: ADU Line 5 o OM81204: ADU Line 4 o OM81203: ADU Line 3 o OM81030: Hydrolysis Column Passive Overflow o OM81051: Precipitation Column Passive Overflow
  • Reviewed the following Corrective Action Program (CAP) entries/documents:

o IRs 2020-10329, 2020-9875, 2020-12844, 2020-13034, 2020-14028, 2020-14081, o IRs 2021-135, 2021-1231, 2021-3461

  • Reviewed the following audits/self-assessments:

o RAF-316-1, "Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments" for SOLX Operator o RAF-316-1, "Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments" for Conversion - Bulk Blending and Containers o RAF-316-1, "Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments" for Conversion - Chief Operator 7

o RAF-316-1, "Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments" for Conversion - Line Operations o RAF-316-1, "Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments" for Scrap Cage Operator -

Ventilation/Common Containers

  • Observed activities associated with operation of the Safe Geometry Dissolver
  • Observed activities associated with operation of the Conversion Lines and Quarantine Tanks.
  • Interviewed conversion operators regarding their job functions on the Conversion Lines and Quarantine Tanks.

88055 - Fire Protection The inspectors evaluated selected aspects of the licensees fire protection program to determine whether the operational status, material condition and design of fire protection systems met the applicable requirements of 10 CFR 70, Chapter 8, "Fire Safety Program, of the facilitys license application, and applicable licensee procedures.

Selection of Inspection Samples (IP Section 02.01)

The inspectors reviewed licensing documents to select a sample of fire protection features in risk-significant areas/processes, including items relied on for safety (IROFS) and their respective management measures (where applicable). The inspectors also selected licensee activities that support the implementation of the fire protection program based on the program description included in the license application. Specifically, the inspectors performed reviews of building construction, select fire safety IROFS, select ventilation systems, fire detection and alarm systems, fire suppression equipment and systems, pre-fire plans, basic firefighting equipment, emergency response team training and qualifications, and audits and assessments of the fire safety program:

  • CHEM-407H, UF6FIRE-901, SBG-401, SGB-901, AREAFIRE-901
  • Review of records for Fire Brigade training and qualification proficiency Preventative Controls (IP Section 02.02)

The inspectors interviewed licensee staff, reviewed documentation, and conducted plant walk-downs to verify the licensees controls for combustibles, ignition sources, and inert atmospheres met the license requirements and applicable requirements in 10 CFR

70. Specifically, the inspectors conducted the inspection activities listed below:
  • Conducted walkdowns of established welding areas
  • Reviewed records associated with shop hot work permits
  • Conducted walkdowns of flammable material cabinets to verify compliance with SYP-207
  • Verified Cutting, Welding, and Hot Work permit compliance 8
  • Conducted walkdowns for compliance with housekeeping requirements per SYP-300, Housekeeping, Rev. 28
  • Conducted walkdowns, and reviewed hydrogen gas valve test data to verify compliance with SYP-122, Hydrogen and Natural Gas Safety, Rev. 0 Fire and Gas Detection and Alarm Systems (IP Section 02.03)

The inspectors reviewed selected fire or gas detection devices to verify that detection and alarm systems were able to detect the minimal fire within the required time and initiate the safety function credited in the license application, fire hazard analysis (FHA-13-001), and the ISA Summary. Specifically, the inspectors conducted the inspection activities listed below:

  • Reviewed fire alarm test results and observed site fire alarm test activities
  • Reviewed drawing 510F08EL05, Electrical Emergency Panel Schedules, Rev.

83 to verify backup power source to alarms system panels

  • Conducted walkdowns, interviewed operators, and reviewed work order 877569 CHEM-407 IROFS H2 Valve annual maintenance activities
  • Reviewed CHEM-407 IROFS H2 Valve annual testing to verify compliance with the ISA summary Suppression Systems and Activities (IP Section 02.04)

The inspectors interviewed license staff, reviewed fire protection program documents, and conducted plant walk-downs to verify that suppression systems were capable of performing the safety function credited in the license application and the ISA Summary. Specifically, the inspectors performed the following activities:

  • Interviewed the facility sprinkler engineer, mechanical maintenance supervisor, facility systems program engineer, and the vendor suppression system test and maintenance specialist
  • Reviewed the sprinkler system inspection and replacement plan; reviewed sprinkler system test data and results
  • Selected a sample various fire suppression systems to walkdown and inspect
  • Conducted walkdowns of various hose stations and fire extinguishers to verify the adequate locations, accessibility, and test requirements
  • Conducted walkdowns to ensure adequate emergency coverage was in accordance with licensee procedures
  • Reviewed PM20511/20512/20513, Monthly Emergency Light Test (various) to verify compliance with NFPA 101
  • Conducted walkdowns of the fire-water pumps and tanks; reviewed inspection and test data for the fire pumps and tanks
  • Reviewed modification packages CCF 16388 and 14414, #1 Fire-water Pump and #2 Fire-water replacement pumps, respectively 9

Passive Fire Protection Features (IP Section 02.05)

The inspectors reviewed selected passive fire protection features to verify these were in a proper material condition to perform the safety function credited in the license application, fire hazard analysis and the ISA Summary. Specifically, the inspectors performed the following activities:

  • Conducted walkdowns of various areas to verify passive fire wall barriers and fire wall penetrations were maintained
  • Conducted walkdown of the hot oil room to review passive fire wall structures were maintained
  • Reviewed hot oil room ventilation ductwork features to ensure the required fire rating was maintained
  • Conducted interviews to verify that licensee surveillance inspections are being conducted to ensure the functionality of fire walls, fire wall penetrations, fire wall dampers, and fire doors Fire Protection Program Elements (IP Section 02.06)

The inspectors reviewed selected fire protection program elements to verify compliance with the license requirements. Specifically, the inspectors completed the following activities:

  • Reviewed samples of active and closed fire system impairment log entries to verify compensatory measure per procedure SYP-306, CFFF Fire/Criticality System Impairments, Revision 21
  • Reviewed detailed training and qualification records for four fire brigade members and interviewed the on shift fire brigade team leader
  • Conducted walkdowns of emergency lights and reviewed monthly and annual emergency light test results to verify compliance with NFPA 101
  • Conducted walkdowns of the hot oil room, solvent extraction, and the UF6 pad and reviewed associated pre-fire plans to verify compliance with SYP-311, Pre-Fire Plans, Revision 1 Identification and Resolution of Problems (IP Section 02.07)

The inspectors reviewed the licensees identification and resolution of fire protection issues to verify compliance with the license requirements. Specifically, the inspectors reviewed the following corrective action program entries, audits, and self-assessments:

  • IR-2020-119, 2020-345, 2020-2734, 2020-7716, 2020-9749, 2020-10498, 2020-10499, 2020-10502, 2020-10503, 2020-11181, 2020-11309, 2020-12934, 2020-13694

INSPECTION RESULTS No violations of more than minor significance were identified.

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

  • On March 25, 2021, the inspectors presented the integrated inspection results to Mike Annacone and other members of the licensee staff.
  • On February 25, 2021, the inspectors presented the Exit Meeting inspection results to Anette Pope and other members of the licensee staff.
  • On April 20, 2021, the inspectors presented the Operational Safety inspection results to Annette Pope and other members of the licensee staff.

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DOCUMENTS REVIEWED Inspection Type Designation Description or Title Revision or Procedure Date 88015 Engineering RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 02/02/2021 Evaluations Walkthrough Assessments, Pelleting - Pellet Grinding /

D&V Operator RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 02/03/2021 Walkthrough Assessments, Conversion - Conversion Operations and Various Containers RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility 02/02/2021 Walkthrough Assessments, IFBA FA1 Miscellaneous TRN-001-2 Radiation Protection Criticality Safety SSCs Safeguards 2020 Procedures CN-SB-18-001 Integrated Safety Analysis Handbook 4 COP-815412 Changing Wet Filters in the Conversion/Scrap Area (CSA) 26 MCP-202037 Criticality Alarm Calibration and SSC Verification (AC- 32 Plant-1-01)

Self-Assessments RAF-106-1-00017 NCS Triennial Audit 11/12/2020 Work Orders CFFF-Dispatch 26 Weeks PM20852a SI-Safety, Instrument Calibration, 02/01/2021

  1. 25958 STA-6B Nuclear Incident Alarm STA-6B CFFF-Dispatch 26 Weeks PM20852a SI-Safety, Instrument Calibration, 02/01/2021
  1. 26396 STA-12A Nuclear Incident Alarm STA-12A 88020 Corrective Action CAP IR 2017-881, 12/20/2020 Documents Passive IROFS Basis Documentation Extent of Condition Review IR-2021-3461 3/22/2021 Corrective Action 2021-3688, SGD- 3/26/2021 Documents 142 As-Built Design Resulting from 2021-3713, Passive 3/26/2021 Inspection IROFS Observation 2021-3714, 3/26/2021 Housekeeping Issues 2021-3818, 3/30/2021 Records of 8

Inspection Type Designation Description or Title Revision or Procedure Date 10CFR70.72 review of "Activities of Personnel" on site Engineering PSEDoc-007355, 10/2/2020 Evaluations Motor Enclosure and Hood Drain Calculations (SGD-127)

Miscellaneous PM85042, 52 10/20/2020 Weeks PM85042 SI-Safety, Water Backflow Prevention Verification WEC1022 Move 3/17/2021 Report Procedures CA-002, Columbia 67 Plant Electronic Training and Procedure System (ETAPS)

CA-134, Columbia 2 Plant Significant Event Response Guidelines CF-20-030, 3 Backflow Device Test Report Form CF-81-015, 74 Conversion Field Data Checklist for Conversion Line CF-81-201, Glass 14 Raschig Ring Measurements Conversion Line Q-Tanks 9

Inspection Type Designation Description or Title Revision or Procedure Date CF-81-941, 60 Conversion Line 5:

Safety Significant Interlocks, Alarms &

Passive Engineered Controls Functionality Verification Form COP-801201, 44 Hydrolysis Operation COP-810093, 15 Chemical Operating Procedure Conversion Area COP-810705, Glass 26 Volume Check and Inspection of Conversion Line Q-Tanks COP-811601, 46 Quarantine Tanks System:

Operations, Bank Switching, Online Gamma Activity Monitors COP-811602, Acid 29 Wash of Conversion Line Q-Tanks COP-816001, 23 Pressure Test of UF6 Supply and Eduction Lines COP-816022, 1 Chemical Operating Procedure 10

Inspection Type Designation Description or Title Revision or Procedure Date Conversion Area COP-836025, C-4 44 Dissolvers - Clean Dissolver Startup and Operation COP-836027, C-4 39 Dissolvers - Dirty Dissolver Startup and Operation COP-836051, 1 Activity Monitors on Chemical Area Cooling Tower Operation CSE-3-D, Criticality 5 Safety Evaluation for the ADU Conversion Hydrolysis Column with Passive Overflow, Nitrate Vessel and Precipitator CSE-3-M, Criticality 8 Safety Evaluation for the Conversion Quarantine Tank System CSE-3-N, Criticality 11 Safety Evaluation for the UF6 Cylinder Receipt and Handling CSE-4-A, Criticality 15 Safety Evaluation for the Safe Geometry Dissolver 11

Inspection Type Designation Description or Title Revision or Procedure Date System CSE-4-B, Criticality 5 Safety Evaluation for the URRS Sifting/Cleaning Hood CSE-4-D, Criticality 4 Safety Evaluation for the URRS Dirty Dissolver Centrifuge CSE-9-B, Cylinder 7 Wash CSE-9-C, UF6 2 Cylinder Recertification EHS Letter-21-12, Revision G East Lagoon Closure Work Plan MCP-108241, 2 Backflow Preventers -

Inspection and Testing Procedure MCP-202225, 3 Chomical Cooling Tower 8351A/B Gamma Activity Monitor Calibration and COOL-100 Alarm Verification MCP-203350, 8 Verification of Instrumented Safety Function ADUHYD-910: V-X02 High Temperature MCP-203351, 10 12

Inspection Type Designation Description or Title Revision or Procedure Date Maintenance and Calibration Operating Procedure Calibration Area MCP-203355, 11 Verification of Instrumented Safety Function ADUHYD-105, ADUHYD-106:

V-X02 Recirculation Flow Low MCP-203356, 12 Verification of Instrumented Safety Function ADUPCP-901: Precipitator V-X05 High Level MCP-203395, 0 Maintenance and Calibration Operating Procedure Calibration Area MCP-203676, 13 Verification of Instrumented Safety Functions ADUHYD-913: UF6 Maintenance Mode and ADUHYD-914:

UF6 Line Nitrogen Purge Mode SOI-C-0636, 7/12/2013 Cutting WEC0996 (UF6 Cylinder) in the URRS Decon 13

Inspection Type Designation Description or Title Revision or Procedure Date Room SOI-U-287, Cylinder 11/27/19 Recertification Building Downgrade TR-303, Move UF6 0 and 15 Cylinders TR-303, US 15 Transport Operations Procedure Self-Assessments RAF-316-1, Bulk 8/25/2020 Blending Operations RAF-316-1, 8/25/2020 Conversion - Chief Operator RAF-316-1, 8/25/2020 Conversion Line Operator RAF-316-1, Scrap 8/26/2020 Cage Operator -

Ventilation/Common Containers RAF-316-1, URRS 12/10/2020 SOLX Operator RAF-316-1, URRS 3/31/2020 SOLX Operator Work Orders CF-81-932, 3/2/2021 Conversion Line 1:

Safety Significant Interlocks, Alarms and Passive Engineered Controls Functionality Verification Form 88055 Drawings 347F04HV01 Hot Oil Room HVAC 6 14

Inspection Type Designation Description or Title Revision or Procedure Date 510F01EL03 Fire Protection Overall Plan Major Cabinet Locations 17 510F08EL05 Electrical Emergency Panel Schedules 83 Fire Plans Fire Pre-Plan 72: UF6 Bay and Hot Oil Room Fire Pre-Plan 77: URRS SOLX, Incinerator, Dissolver Miscellaneous Integrated Safety Analysis of the CFFF Site and Structures 15.1 Site Emergency Plan for the Columbia Fuel Fabrication 21 Facility CCF 14414 Replace #2 Diesel Fire Pump 08/05/2014 CFF 16388 Replace # Diesel Driven Fire Pump 06/29/2016 CHEM-04 Fire Hazard Analysis, Appendix CHEM-04 UF6 Bay 0 PM20009 Monthly Sprinkler System Preventive Maintenance PM20209 Preventive Maintenance for CHEM-407 SNM-1107 License Renewal Application 01/22/2021 Procedures SYP-122 Hydrogen and Natural Gas Safety 0 SYP-207 Cutting, Welding, and Hot Work 38 SYP-300 Housekeeping 28 SYP-301 Handling and Storage of Zirconium and Its Alloys 17 SYP-303 Portable Fire Extinguisher Inspection and Maintenance 12 SYP-305 Fire Watch Safety 10 SYP-306 CFFF Fire/Criticality System Impairment 21 SYP-311 Pre-Fire Plans 1 Self-Assessments EHS-AUDIT-20-8 Regulatory Component Audit for the Fire Protection 02/11/2021 Program Work Orders WO884609 877569 52-Week PM - H2 Valve Replacement 03/04/2020 CFFF Dispatch 52-Week Sprinkler PM 9182 15

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