ML25209A359
| ML25209A359 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 07/29/2025 |
| From: | Eric Michel NRC/RGN-II/DFRSS/FOB2 |
| To: | Stutts R Westinghouse |
| References | |
| IR 2025002 | |
| Download: ML25209A359 (19) | |
Text
Roy Stutts Site Director Westinghouse Electric Company 5802 Bluff Road Hopkins, SC 29061
SUBJECT:
WESTINGHOUSE ELECTRIC COMPANY - INTEGRATED INSPECTION REPORT 07001151/2025002
Dear Roy Stutts:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from April 1, 2025, to June 30, 2025. On June 12 and June 26, 2025, the NRC inspectors discussed the results of these inspections with you and other members of your staff.
The results of the inspections 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, Eric C. Michel, Chief Fuels Oversight Branch 2 Division of Fuels, Radiological Safety, and Security Docket No. 07001151 License No. SNM-1107
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV July 29, 2025 Signed by Michel, Eric on 07/29/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE R2/DFRSS R2/DFRSS NAME T. Vukovinsky E. Michel DATE 07/29/2025 07/29/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07001151 License Number:
SNM-1107 Report Number:
07001151/2025002 Enterprise Identifier:
I-2025-002-0063 Licensee:
Westinghouse Electric Company Facility:
Westinghouse Electric Company Location:
Hopkins, SC Inspection Dates:
June 9-12, 2025, and June 23-26, 2025 Inspectors:
N. Peterka, Sr. Fuel Facility Project Inspector T. Shewmaker, Fuel Facilities Inspector P. Startz, Fuel Facilities Inspector C. Ubben, Fuel Facilities Inspector Approved By:
Eric C. Michel, Chief Fuels Oversight Branch 2 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 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 Type Issue Number Title Report Section Status WER 07001151/2025-002-00 EN 57664 - Contaminated Injured Worker 88050 Closed
3 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, 70.62, and Chapter 6, Nuclear Criticality Safety (NCS) Program, 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 (CSEs), and associated assumptions and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application. Specifically, the inspectors interviewed licensee staff and reviewed the following CSEs:
CSE-7-A, "Criticality Safety Evaluation for the Solvent Extraction System,"
Rev. 15, including the review of what-if analysis, normal, credible abnormal, and non-credible accident sequences, including the basis for why certain accident sequences were considered non-credible, and items relied on for safety (IROFS) associated with the system CSE-18-A, "Criticality Safety Evaluation for VIPER/Product Engineering Development Lab, Rev. 12, including the review of what-if analysis, normal, credible abnormal, and non-credible accident sequences CSE-18-B, "Criticality Safety Evaluation for the Analytical Services Laboratory, Rev. 27, including the review of what-if analysis, normal, credible abnormal, and non-credible accident sequences, including the basis for why certain accident sequences were considered non-credible CSE-18-C, "Criticality Safety Evaluation for the Metallurgical Laboratory," Rev.
3, including the review of what-if analysis, normal, credible abnormal, and non-credible accident sequences
4 ISA-07, "URRS Solvent Extraction System," Rev. 19, which was reviewed because it contained supporting documentation for CSE-7-A ISA-18, "Laboratories System," Rev. 19, which was reviewed because it contained supporting documentation for CSEs 18-A, B, and C Additionally, the inspectors conducted walkdowns in the areas covered by these CSEs, and other areas of the plant (e.g., conversion)
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. Specifically, the inspectors reviewed the following IROFS:
PETLAB-121, an administrative control on enrichment <1% U-235 for the product engineering development lab, and associated procedures/records PETLAB-122, an independent administrative control on enrichment <1% U-235 for the product engineering development lab, and associated procedures/records PETLAB-127, an administrative control on enrichment for the product engineering development lab via tamper seal verification, and associated procedures/records PETLAB-128, an independent administrative control on enrichment for the product engineering development lab via tamper seal verification, and associated procedures/records METLAB-101, an administrative control on mass via a mass balance form for the metallurgical laboratory, and associated postings METLAB-102, an independent administrative control on mass via a mass balance form for the metallurgical laboratory, and associated postings SOLX-101, a passive engineered control on geometry for the columns, and associated receipt inspections SOLX-102, a passive engineered control on spacing for the SOLX columns, and field verification measurements COOL-101, an administrative control on concentration for the Uranium Recovery and Recycle Services (URRS) cooling towers via sampling, and associated records COOL-100, an administrative control on concentration for URRS cooling towers via gamma monitor, and associated calibration records 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:
interviewed NCS engineering staff concerning criticality hazards and control methods, including monitoring and control of concentration and geometry in the Solvent Extraction and Uranium Recovery Recycle Services areas
5 interviewed NCS engineering staff concerning criticality hazards and control methods, including mass and enrichment controls for the various onsite laboratories reviewed the documentation of selected NCS weekly facility walkthrough assessments (FWAs) performed by the licensee over the last six months interviewed Solvent Extraction and Outside Uranium recovery recycle services operators on implementation of administrative controls through the applicable operating procedures for their areas reviewed NCS safety training 2025 for operators Criticality Programmatic Oversight (IP Section 02.04)
The inspectors reviewed NCS program procedures, audits, and NCS staff qualifications 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:
ROF-05-062-10, quarterly ventilation survey of scrubber S-958 ROF-05-062-9, quarterly ventilation survey of scrubber S-1008 interviewed NCS staff concerning the NCS review of changes, including changes to operating procedures that may affect NCS, and changes to the facility review of licensee procedure/calc CN-CRI-20-003, "NCS Manual," Rev. 9, which contains guidance on implementing various aspects of the sites criticality safety program 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 Section 6.1.8. Specifically, the inspectors observed activities, reviewed documents, and interviewed licensee staff concerning the following:
reviewed selected issues entered in the CAP pertaining to IROFS and audit findings reviewed criticality safety evacuation drill records for 2024 reviewed select testing records for the CAAS detector calibrations and horn checks for the last year reviewed CAAS detector placement calculations for the Final Assembly below grade pits walked down CAAS detectors in the Final Assembly area of the mechanical side 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 3, Management Measures, of the facilitys license application, and applicable licensee procedures.
6 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 NCS based on the information provided in the ISA summary. The inspectors conducted a general plant tour of each major plant operating area. The process area and accident sequences selected for review are listed below:
Safe Geometry Dissolver System (SGDS) o CSE-4-A-3, Solution Back-up Into the Motor Enclosure from Contactor o
CSE-4-A-5, Special Nuclear Material (SNM) Enters the Tower Cooling System o
CSE-4-A-6, Solution Back-up Into the Deionized (DI) Water, Nitric Acid, and/or Dissolver Feed Hood o
CSE-4-A-7, Solution Back-up Into the Plant Air System from the Candle Filter Process o
CSE-4-B-2, Criticality in the Hood Ventilation System o
CSE-4-D-1 Fissile Material Accumulates in Centrifuge Housing o
CSE-4-D-3, Fissile Material Backflows from V-754A/B to Centrifuge Housing o
CSE-4-E-1, Moderated SNM in Drum Causes Criticality o
CSE-4-E-2, Water Floods Hood Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative, engineered, and passive safety controls or IROFS for the accident sequences selected above, 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. The specific safety controls selected for review are listed below:
SGD-127, first drain hole in motor enclosure, passive engineered control (PEC)
SGD-142, second drain hole in motor enclosure, PEC SGD-143, length and width of motor enclosure, PEC SGD-158, structural integrity of the heat exchanger wall servicing the cooling loop for the dissolver channels, PEC COOL-100, gamma monitoring system of tower cooling water, administrative control (AC)
COOL-101, sampling on tower cooling water hot well, AC SGD-141, internal dimensions of the dissolver feed hood, PEC SGD-166, drain path(s) in dissolver feed hoods, PEC SGD-167, second set of independent drain path(s) in dissolver feed hoods, PEC
7 CANFIL-101, differential pressure interlock on the plant air line to FL-754A/B candle filters, active engineered control (AEC)
CANFIL-102, backflow prevention valve in plant air supply to FL-754A/B candle filters, AEC CANFIL-103, redundant backflow prevention valve in plant air supply to FL-754A/B candle filters, AEC DPH-103, dissolver area roof integrity, PEC DPH-104, dissolver area piping integrity, PEC DPH-113, height of bottom lip of grating at the entrance to the hood ventilation system, PEC SGDFIRE-901, fire protection program, AC SGDFIRE-902, proper fire-fighting methods in vicinity of SNM, AC SGDCENT-101, drain at bottom of dirty dissolver centrifuge outer housing, PEC SGDCENT-102, redundant drain at bottom of dirty dissolver centrifuge outer housing, PEC SGDCENT-104, vacuum break installed to prevent backflow from V-754A/B vessels to dirty dissolver centrifuge, PEC SGDCENT-106, operator inspect centrifuge housing drain after each centrifuge bowl cleanout, AC SGDCENT-109, redundant vacuum break installed to prevent backflow from V-754A/B vessels to dirty dissolver centrifuge, PEC SGD-138, nitric acid feed to dirty dissolvers initiated prior to introduction of feed material, AC URSSCRP-139, NCS engineering approve material content prior to adding to waste drum, AC URSSCRP-141, drain in 706 hood, PEC URSSCRP-143, drum port covered with lid when unattended, AC URSSCRP-166, second, independent drain in 706 hood, PEC 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 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:
performed walkdowns of SGDS to verify implementation of selected IROFS reviewed operating procedures for clean and dirty dissolvers reviewed operating procedure for low level waste solids processing reviewed fire protection program implementing procedure reviewed NCS postings on 706 hood reviewed Criticality Safety Evaluations (CSEs) for the selected IROFS interviewed operators and area supervisor in SGDS regarding safety controls and process
8 reviewed CSE implementation plans for IROFS:
o CANFIL-104/105/106/107/108 o
DPH-113 o
SGDCENT-104/109 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 preventive maintenance (PM) records for dissolver area roof inspections (IROFS DPH-103) reviewed PM records for dissolver area piping inspections (IROFS DPH-104) reviewed Operator Maintenance (OM) records for dissolver centrifuge drainpipe inspections (IROFS SGDCENT-101 and 102) reviewed OM records for housekeeping and flammable storage cabinet inspections (IROFS SGDFIRE-901) observed operators collecting chemical cooling tower sample for uranium content (IROFS COOL-100) reviewed calibration records for chemical cooling tower gamma monitors (IROFS COOL-101) reviewed chemical cooling tower sample results against acceptance criteria (IROFS COOL-100) reviewed logs of uranium content added to waste drum from 706 hood (IROFS URSSCRP-139) reviewed failure and degradation records for Safe Geometry Dissolver System IROFS reviewed samples of IROFS-related CAP entries for the past six months reviewed licensee audits of Chemical Safety Program and ISA reviewed training and qualification records of two operators in the SGDS interviewed training manager regarding qualification records and training database reviewed seven recent personnel changes and qualifications in engineering and operations departments reviewed post-installation inspections for passive engineering controls interviewed NCS Engineer regarding NCS system walkdowns interviewed NCS Manager regarding initial NCS IROFS inspections and engineering calculations observed the operation of the clean and dirty dissolvers FACILITY SUPPORT 88050 - Emergency Preparedness The inspectors evaluated selected aspects of the licensees emergency preparedness program to determine whether the program is maintained as required by the Emergency Plan, the license and license application, and NRC requirements in 10 CFR Part 70 or 10 CFR Part 40.
9 Emergency Preparedness Program Review and Implementation (IP Section 02.01)
The inspectors selected the following elements that support the implementation of the licensees emergency preparedness program to verify compliance with 10 CFR 70.22(i)(3),
Chapter 9, "Emergency Management Program" of the license application, and the Emergency Plan. Specifically, the inspectors conducted the following inspection activities:
reviewed SEP-002, "Classification," Revision (Rev.) 8, focusing on recent changes to natural phenomenon hazard classification and a sample of other Emergency Plan implementing procedures reviewed training records, including certificates and attendance rosters, for three incident commanders (ICs) including a new IC currently completing training reviewed training records, including certificates and attendance rosters, for a sample of emergency response team members reviewed the current offsite support agreements that the licensee has with the Columbia-Richland Fire Department, the Richland County Sheriff's Department and other offsite support agencies interviewed the Columbia-Richland Fire Department, hazardous materials (HAZMAT) Chief, to verify that the licensee provided effective information exchange, training opportunities, current Emergency Plan, and opportunities to enhance interoperability knowledge reviewed records from the June 2024 Tabletop, the January 2025 Tabletops, and the March 2025 Evacuation drill walked down emergency equipment storage locations and interviewed emergency team members, and the site nurse, about the procedures, supplies, and equipment inspected the licensee's emergency response facilities and equipment; and discussed changes with the confined space rescue training area, emergency response station, the emergency operations center (EOC), the fire truck, and HAZMAT truck inspected multiple emergency response supply cabinets within the conversion production area, interviewed licensee staff, and reviewed completed forms to verify that licensee staff were monitoring supplies as required by CF-81-230, "1st Shift Conversion Weekly Safety Checklist," Rev. 8 reviewed the last two annual audits of the emergency preparedness program that were conducted by a licensee contractor, EHS-AUDIT-21-02 and EHS-AUDIT-22-02 Identification and Resolution of Problems (IP Section 02.02)
The inspectors reviewed the licensees identification and resolution of emergency preparedness issues to verify compliance with the license requirements. Specifically, the inspectors reviewed the following corrective action program entries, audits, and self-assessments:
IR-2025-2125, IR-2025-958, IR-2024-6526, IR-2024-4808, IR-2024-5662; includes CAP entries that resulted from audits, entries that resulted from drill performance, and entries that resulted from events
10 EHS-AUDIT-24-03 "All Clear Fire Training and Consulting," dated 02/23/2024 reviewed annual audit of the emergency preparedness program, IR-2025-2104, 2025 Program Audit reviewed Check List for Health Physics Response to Contaminated Injury/Ill Victim ROF-07-001-2, Rev 7 Dated 4/13/2025, from event notice (EN) 57664 Event Review (IP Section 02.03)
The inspectors reviewed the licensees safety-significant and internal events related to emergency preparedness to verify compliance with 10 CFR 70.32(i), Chapter 9 of the license application, and the Emergency Plan. Additionally, the inspectors followed up on a WER related to Event Report 57664, production employee exposure to a uranium-nitric acid solution, sent to a medical facility for skin inflammation, to verify compliance with 10 CFR 70.50(b)(3). Specifically, the inspectors performed the following activities:
reviewed SEP-002, "Classification," Rev. 8, revised for clarity for determining a correct classification of a severe natural phenomenon event classification as well as other emergency plans reviewed job qualifications prerequisites, training certificates and attendance rosters to date for one new incident commander followed up Event Notice 57664, where a production employee experienced a splash of a uranium-nitric acid solution to a portion of their arm, causing skin inflammation and radionuclide contamination. Review of EN detailed below.
INSPECTION RESULTS WER EN 57664 - Contaminated Injured Worker WER 2025-002 88050
==
Description:==
At approximately 2:15 a.m. on April 13, 2025, a Uranium Recovery and Recycle Services (URRS) operator was performing a pressure check of a dissolver system filter housing following change out of the filter cartridges. Uranyl nitrate solution discharged from the housing lid / housing body interface onto the operators coveralls in the upper left arm area. In accordance with the operating procedure, the operator was wearing a full-face shield, safety glasses, chemical gloves, and a chemical apron that covers the torso area, however, the chemical apron did not cover the arm area.
The operator reported the exposure to a URRS Chief Operator and the skin area on the upper left arm was rinsed for approximately 15 minutes. The incident commander, a medical first responder from the Columbia Fuel Fabrication Facility (CFFF) emergency brigade, and a Health Physics (HP) technician were contacted to respond to the event. After decontamination efforts on the affected area of the arm, HP direct surveys results were 500 disintegrations per minute (dpm)/100 cm2 alpha for the left bicep area, and all smear survey results of the exposed skin area were below clean area limits (less than 200 dpm/100 cm2).
As a precaution to ensure comprehensive evaluation and treatment for uranyl nitrate/nitric acid exposure to the skin, CFFF directed the operator to be transported by ambulance to an offsite medical facility. The affected portion of the employee's arm was bandaged and wrapped in gauze and tape, and the employee was accompanied by a CFFF HP technician for evaluation. Contamination surveys were performed for the ambulance and the gurney used to transport the employee, and all results were below clean area limits indicating no
11 spread of contamination during care for the employee. All potentially contaminated materials associated with the transport were collected and returned to the CFFF for disposal. The employee was provided with a prescription for a topical ointment and released from the offsite medical facility at 7:35 a.m. on April 13, 2025.
CFFF notified the NRC of the event based on 10 CFR 70.50(b)(3), "An event that requires unplanned medical treatment at a medical facility of an individual with spreadable radioactive contamination on the individual's clothing or body," which is a required 24-hour notification.
NRC inspectors followed up on EN 57664 and noted that the arm was promptly decontaminated to a level below clean area limits and the employee was transferred to a local hospital where the individual was treated for skin inflammation and released. The licensee entered the event into their corrective action program (CAP) and implemented additional procedural and physical safety corrective actions to prevent recurrence. No violations were identified and EN 57664 is closed.
EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On June 12 and June 26, 2025, the inspectors presented the integrated inspection results to Roy Stutts and other members of the licensee staff.
12 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date CN-CRI-05-16 Determination of Keff for Solvent Extraction Area with All Tanks Filled with TBP Saturated with Uranyl Nitrate and mixed with Kerosene Rev. 0 CN-CRI-10-5 Investigate the reactivity of various vessel arrays to bound operations in the Solvent Extraction Area Rev. 1 CN-CRI-20-003 NCS Manual Rev. 9 CN-CRI-25-001 CAAS Coverage for the Final Assembly Below Grade Pits Rev. 0 Calculations CN-SB-18-001 Integrated Safety Analysis and ISA Summary Handbook Rev. 01 Corrective Action Documents IR-2025-1692, 2024-9709, 2025-2995, 2025-908, 2024-1061, 2024-6724, 2025-3084, 2024-9856 NCS Related Corrective Action Program Entries Various CSE-18-A Criticality Safety Evaluation for VIPER/Product Engineering Development Lab Rev. 12 CSE-7-A Criticality Safety Evaluation for the Solvent Extraction System Rev. 15 Engineering Evaluations RAF-120-26-1 Identical IROFS Verification for SOLX glass dated 03/24/2025 2024 TRN-001-2 Radiation Protection, Criticality Safety, SSCs and Safeguards Training for 2025 TAF-502-1 Transport Test Assembly "EPR1" to Product Testing Lab, Special Routing Log Number 16913 dated 01/08/2024 TAF-502-1 Transport Test Assembly "EMR1" to Product Testing Lab, Special Routing Log Number 16941 dated 05/07/2025 Miscellaneous TRN-062 Criticality Sign Posting Training CA-220 Safety Basis Qualification Training Rev. 16 COP-830110 SOLX and Product Concentrator System 1 -
Startup and Operation Rev. 46 88015 Procedures COP-830111 SOLX and Product Concentrator System 2 -
Startup and Operation Rev. 35
13 Inspection Procedure Type Designation Description or Title Revision or Date COP-835512 General Safety Requirements - URRS Rev. 18 MCP-203445 GA-7M Criticality Accident Alarm System and SSC Rev. 4 TA-506 Fabrication and Scrapping of Test, Replica, or Display Rods/Assemblies Rev. 17 ROF-05-062-10 Ventilation Systems Equipment Radiation Survey, Quarterly S-7159 Survey dated 05/31/2025 ROF-05-062-11 Ventilation Systems Equipment Radiation Survey, Quarterly S-958 Survey dated 05/31/2025 ROF-05-062-12 Ventilation Systems Equipment Radiation Survey, Quarterly FL-973 Survey dated 05/31/2025 Radiation Surveys ROF-05-062-9 Ventilation Systems Equipment Radiation Survey, Quarterly S-1008 Survey dated 05/31/2025 RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments, Scrap Cage Operator -
Ventilation/Common Containers 03/31/2025 RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments, Outside URRS 03/31/2025 RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments, SOLX Operator 03/31/2025 Self-Assessments RAF-316-1 Nuclear Criticality Safety Checklist for NCS Facility Walkthrough Assessments, Product Engineering Laboratory, Chemical Development Laboratory, Health Physic Laboratory, Chemical Process Engineering Laboratory, Archive Pellet Can Storage and Handling 03/26/2025 Dispatch #240053 52 Weeks PM20550, SI-Safety, Crit Horn Sound Check 03/28/2024 Dispatch #298825 52 Weeks PM20563, SI-Safety, Crit Horn Sound Check 01/09/2025 Dispatch #307083 Instrument Calibration - 17 week PM, RT-S-8351A Activity Monitor for Cooling Tower 02/18/2025 Work Orders Dispatch #307084 Instrument Calibration - 17 week PM, RT-S-8351B Activity Monitor for Cooling Tower 02/18/2025
14 Inspection Procedure Type Designation Description or Title Revision or Date PSEDoc-0006868-000 Oxidation Hood and Sifter Enclosure Drain Calculation Rev. 0 PSEDoc-0007355 Motor Enclosure and Hood Drain Calculations (SGD-127)
Rev. 0 Calculations PSEDoc-0007695 Dissolver Feed Hood Enclosure(s) Passive Drains (SGD-166, SGD-167)
Rev. 0 Calibration Records WO#20878/Dispatch#291805 Calibration of PDIT-S-754 (Candle Filter Plant Air Differential Pressure Indicator Transmitter 10/22/2024 Corrective Action Documents IRs 2024-9376, 2024-12359, 2024-13424, 2024-9676, 2024-8015, 2024-6960, 2025-706, 2025-1109 Various Corrective action records Various Corrective Action Documents Resulting from Inspection PIR-2025-553, 2025-562, 2025-1069, 2025-1073 Problem Identification and Resolutions submitted by the licensee for NRC observations 06/26/2025 301F08PI01 sheet 1 Solvent Extraction / Clean Scrap Safe / P Geometry Dissolver Process Flow Diagram Rev. 03 301F08PI02 Sheet 1 SOLX / Clean Scrap / Safe Geometry Dissolver /
Counter-Current Contactor CCC-730 Rev. 10 301F09PI01 sheet 1 Solvent Extraction / Dirty Scrap Safe / P Geometry Dissolver Process Flow Diagram Rev.03 301F09PI02 sheet 1 SOLX / Dirty Scrap Safe Geometry Dissolver /
Counter-Current Contactor CCC 750 Rev. 21 301F09PI02 sheet 4 Plant Air Flow Diagram to Candle Filters FL-754 A/B Rev. C5 Drawings 510F36PI04 sheet 1 Plant Utilities / Cooling Tower Water / Chemical Cooling Tower Rev. 15 CCF 08557 Install Centrifuge for Dirty Dissolvers 10/27/2010 CN-SB-11-031-002 Criticality Accident Potential for Safe Geometry Dissolver System Rev. 02 88020 Engineering Evaluations CSE-4-A Critical Safety Evaluation Implementation Plan for Safe Geometry Dissolver System, Acid Scrubber S-2A/2B, S-958 Solvent Extraction Scrubber Rev. 19
15 Inspection Procedure Type Designation Description or Title Revision or Date CSE-4-A Critical Safety Evaluation for Safe Geometry Dissolver System Rev. 19 CSE-4-B Criticality Safety Evaluation for URRS Sifting/Cleaning Hood Rev. 6 CSE-4-B Implementation Plan URRS Sifting/Cleaning Hood 11/07/2013 CSE-4-D Criticality Safety Evaluation for URRS Dirty Dissolver Centrifuge Rev. 5 CSE-4-D Implementation Plan URRS Dirty Dissolver Centrifuge 09/17/2009 CSE-4-E Criticality Safety Evaluation for the URRS 706 Hood Rev. 10 PSEDoc-0002284 Independent Technical Review for CCF 14573 Additional Drain Holes in the Safe Geometry Dissolver Motor Enclosures Rev. 0 PSEDoc-0006036 Design Basis Report and Calculation Scrubbers 2A, 2B, and S-0951 Rev. 0 PSEDoc-0007209 Passive IROFS Verification Rev. 0 Fire Plans SEPF-009-06 Command Check Sheet - Fire Response Westinghouse Nuclear Fuel Columbia, SC Rev. 11 Checklist for Nuclear Criticality Safety Facility Walkthrough Assessment - "SOLX Operator" 05/28/2025 Chemical Cooling Tower activity sampling results from 6/2/2025 to 6/25/2025 (Samples taken every Monday and Wednesday) 06/02/2025 thru 06/25/2025 CCF-D-22036 Install Candle Filters downstream of dirty dissolvers (Configuration Change) 05/22/2024 FWA CSE-4-B NCS staff facility walkthrough of CSE-4-B process areas and safety controls 03/20/2025 FWA CSE-4-D NCS staff facility walkthrough of CSE-4-D process areas and safety controls 10/17/2024 FWA CSE-4-E NCS staff facility walkthrough of CSE-4-E process areas and safety controls 2022 Miscellaneous URRS 33 Criticality Requirements 706 Hood Rev. 7
16 Inspection Procedure Type Designation Description or Title Revision or Date URRS 62 Criticality Requirements 706 Hood Drum Port Rev. 4 COP 836027 C-4 Dissolvers - Dirty Dissolver Startup and Operation Rev. 44 COP 836028 Low Level Waste Solids Processing Rev. 26 COP-830404-1 Waste Treatment Sample Frequency Schedule Rev. 10 COP-835101 Monitoring the Chemical Area Cooling Tower Rev. 12 COP-836025 C-4 Dissolvers - Clean Dissolver Startup and Operation Rev. 47 COP-836051 Activity Monitors on Chemical Area Cooling Tower Operation Rev. 01 MCP-202225 Chemical Cooling Tower 8351 A/B Gamma Activity Monitor Calibration and COOL-100 Alarm Verification Rev. 04 MCP-203688 Candle Filter Plant Air Backflow Preventers -
Inspection and Testing Procedure Rev. 0 MCP-203689 Verification of SSC CANFIL-101 PDIT-S-754 Differential Pressure Interlock Rev. 0 RA-316 NCS Facility Walkthrough Assessments Rev. 12 SYP-300 Combustible and Ignition Control Rev. 33 TA-500 Columbia Manufacturing Plant Configuration Control Rev. 43 Procedures TA-500-11 Facility Change Request Control Procedure Rev. 1 EHS Audit 24-12 2024 Regulatory Component ISA Compliance Audit 09/10/2024 Self-Assessments EHS Audit 25-6 SNM 1107 Chemical Safety Program Audit 06/11/2025 Dispatch # 281446 4 months PM20851a SI-SAFETY, INSTRUMENT CALIBRATION (and alarm checks) - 17 WEEK PM 10/22/2024 Dispatch # 307083 4 months PM20851a SI-SAFETY, INSTRUMENT CALIBRATION (and alarm checks) - 17 WEEK PM 02/18/2025 OM 85164 URRS Housekeeping and Flammable Storage Cabinet Inspections 06/17/2025 OM 85164 URRS Housekeeping and Flammable Storage Cabinet Inspection 06/26/2025 Work Orders OM 85164 URRS Housekeeping and Flammable Storage 05/20/2025
17 Inspection Procedure Type Designation Description or Title Revision or Date Cabinet Inspection OM 85164 URRS Housekeeping and Flammable Storage Cabinet Inspection 04/24/2025 OM 85250 Dirty Dissolver Centrifuge Drain Pipe Inspection 09/11/2023 OM 85250 Dirty Dissolver Centrifuge Drain Pipe Inspection 09/09/2024 OM 85250 Dirty Dissolver Centrifuge Drain Pipe Inspection 09/12/2022 OM8516 (Dispatch #
320463/320450/320446)
Monthly Powder Hood Drain Inspection 05/02/2025 OM85161 (Dispatch #
314609/314611/314610)
Monthly Powder Hood Drain Inspection 04/01/2025 OM85161 (Dispatch #
325565/325566/325564)
Monthly Powder Hood Drain Inspection 05/28/2025 PM 85066 Dissolver Area Water Piping Inspections 03/03/2025 PM 85066 Dissolver Area Water Piping Inspections 03/04/2024 PM 85066 Dissolver Area Water Piping Inspections 03/06/2023 PM 85067 Dissolver Area Roof Inspections 01/25/2024 PM 85067 Dissolver Area Roof Inspections 01/31/2023 PM 85067 Dissolver Area Roof Inspections 01/15/2025 WO#20314 / Dispatch
- 283808 PM85076 Testing Candle Filter backflow preventers 10/16/2024 WO#20315 /
Dispatch#283810 PM85077 CANFIL-102/103 Differential Pressure Interlock Testing 10/16/2024 ROF-07-001-2 Check List for Health Physics Response to Contaminated Injury/Illness (Form)
Rev. 7 ROP-05-028 Employee Work Restriction Rev. 23 88050 Procedures ROP-07-001 Health Physics Response to Emergency Events Rev. 14