ML25323A277
| ML25323A277 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 11/20/2025 |
| From: | Nicholas Peterka NRC/RGN-II/DFFI |
| To: | Lorskulsint P Louisiana Energy Services, URENCO USA |
| References | |
| IR 2025007 | |
| Download: ML25323A277 (1) | |
Text
Paul Lorskulsint Chief Nuclear Officer Louisiana Energy Services (LES) dba Urenco USA P.O. Box 1789 Eunice, NM 88231
SUBJECT:
URENCO USA - INTEGRATED ORR REPORT 07003103/2025007
Dear Paul Lorskulsint:
On September 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at URENCO USA, and discussed the results of this inspection with you and other members of your staff. The results of this inspection, that pertain to the operational readiness reviews for LEU+ and the startup of Cascade 6.6 are documented in the enclosed report.
No violations of more than minor significance were identified during this inspection.
Due to the temporary cessation of government operations, which commenced on October 1, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions. On November 13, 2025, following the passage of a continuing resolution, the NRC resumed normal operations. However, due to the 43-day lapse in normal operations, the Office of Nuclear Materials Safety and Safeguards granted the Regional Offices an extension on the issuance of the calendar year 2025, 3rd quarter integrated inspection reports normally issued by November 15, 2025, to December 31, 2025. The NRC will resume the routine cycle of issuing inspection reports on a quarterly basis beginning with the calendar year 2025, 4th quarter integrated inspection reports, which will be issued 45 days after the 4th quarter ends on December 31, 2025.
November 20, 2025
P. Lorskulsint 2
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Nicholas E. Peterka, Acting Chief Projects Branch 1 Division of Fuels, Radiological Safety, and Security Docket No. 07003103 License No. SNM-2010
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Peterka, Nicholas on 11/20/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFRSS RII/DFRSS RII/DFRSS RII/DFRSS NAME C. Taylor C. Oelstrom T. Sippel N. Peterka DATE 11/19/2025 11/19/2025 11/20/2025 11/20/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07003103 License Number:
SNM-2010 Report Number:
07003103/2025007 Enterprise Identifier:
I-2025-007-0002 Licensee:
Louisiana Energy Services (LES) dba Urenco USA Facility:
Urenco USA Location:
Eunice, NM Inspection Dates:
August 25, 2025 to August 29, 2025 Inspectors:
C. Oelstrom, Fuel Facilities Inspector T. Sippel, Sr. Fuel Facility Project Inspector C. Taylor, Sr. Fuel Facility Project Inspector Approved By:
Nicholas E. Peterka, Acting Chief Projects Branch 1 Division of Fuels, Radiological Safety, and Security
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an Operational Readiness Review at Urenco USA, 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 UUSA Facility in Eunice, New Mexico enriches uranium hexafluoride (UF6) using gas centrifuge technology. During the inspection period, normal production activities were ongoing.
The licensee also started up and introduced UF6 to Cascade 6.6.
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 IP 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 Appendix A, Chapter 5, Nuclear Criticality Safety, of the facilitys license application, and applicable licensee procedures as they pertain to the licensees Low Enriched Uranium plus (LEU+) project. LEU+ refers to Uranium enriched to between 5 and 10 wt. percent in U-235.
Criticality Analysis (IP Section 02.01)
The inspectors interviewed licensee staff and reviewed nuclear criticality safety evaluations (CSEs) and analyses (CSAs), and associated assumptions and calculations, to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.2.
Specifically, the inspectors interviewed licensee staff and reviewed the following:
NCS-CSA-109, "Analysis of 30B Cylinder Array (LEU+)," Revision (Rev.) 0, including the review of accident sequences involving moderator intrusion, reflection, and other upsets NCS-CSA-118, "Nuclear Criticality Analysis of UUSA Process Gas Pipework (LEU+)," Rev. 0, including review of accident sequences and IROFS related to the Blending Receiver and Donor Hotboxes NCS-CSE-100, "Nuclear Criticality Safety Evaluation of Facility Rigs (LEU+),"
Rev. 0 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
4 5.1.2. Specifically, the inspectors interviewed licensee staff and reviewed the following controls, associated with the CSAs/CSEs listed above and selected areas:
IROFS102, a passive control on geometry, through review of CGDP-102-0001, Rev. 0 IROFS103, a passive control on geometry, volume and spacing, through review of CGDP-103-0001, Rev. 0, dated March 25, 2025 IROFS105, a passive control on geometry, through review of CGDP-105-0001, Rev. 0 IROFS108a/b, administrative controls on spacing, through observing NCS postings IROFS109, a passive control on geometry, through review of CGDP-109-0001, Rev. 0, dated March 27, 2025 IROFS110a/b, administrative controls on spacing and reflection, through observing NCS postings IROFS118a/b, administrative controls on spacing, through observing NCS postings and operator aids IROFS120a/b, administrative controls on spacing and volume, through observing NCS postings IROFS124a/b, administrative controls on contain type in array, through observing NCS postings IROFS165a/b and 166a/b, administrative controls on enrichment, through review of training material IROFS167a/b, administrative controls on spacing and piece count during movements, through observing NCS postings 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 11.5. Specifically, the inspectors performed the following activities:
observed licensee NCS engineers conduct a weekly NCS walkdown (inspection) and reviewed recent licensee NCS inspection report, including:
o NCSI-25-0026, "Hallowell Cabinet (South Wall of SBM1001)," dated July 13, 2025 o
NCSI-25-0027, "Hallowell Cabinets (several)," dated July 11, 2025 o
NCSI-25-0038, "LEU+ Process Gas Pipework and BLSA Out Gas Header," dated August 8, 2025 o
NCSI-25-0043, "LEU+ Storage and Movement of Misc Components (IROFS167ab)," dated August 7, 2025 Criticality Programmatic Oversight (IP Section 02.04)
The inspectors reviewed NCS self-assessments to verify compliance with 10 CFR 70 and applicable sections of the license application, including 11.5. Specifically, the inspectors interviewed licensee NCS staff and reviewed the following documents:
5 SA-2025-001, "Nuclear Criticality Safety Programmatic Self-Assessment,"
dated May 15, 2025; which is the most recent self-assessment of the licensee's NCS program, and which included documentation of the licensee's review of LEU+ IROFS106, 108, 110, 111, 118, 120, 121, 124, 165, 166, and 167 Criticality Incident Response and Corrective Action (IP Section 02.05)
The inspectors reviewed the licensees criticality accident alarm system (CAAS) to verify compliance with 10 CFR 70 and applicable sections of the license application, including 5.3.
Specifically, the inspectors:
reviewed CALC-S-00150, "Immediate Evacuation Zone Calculations at UUSA (LEU+)," Rev. 3 IP 88020 - Operational Safety The inspectors evaluated selected aspects of the licensees Operational Safety program to verify compliance with selected portions of 10 CFR 70, including 70.61 and 70.62, as well as Chapter 11, Management Measures, of the facilitys license application, and applicable licensee procedures, as they pertain to the licensees LEU+ project and the startup of Cascade 6.6.
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 nuclear criticality safety, radiation safety, fire safety, and/or chemical safety based on the information provided in the integrated safety analysis (ISA) summary. The inspectors conducted a general plant tour of each major plant operating area. For Cascade 6.6 in SBM 1005 the accident sequences selected for review include:
External Event (EE), Design Feature of Centrifuges EE-Tornado & High Wind, SBM-CRDB Shell-UBC Storage Pad -Design Feature of Centrifuges EE-Snow-SBM CRDB Shell, Design Feature of Centrifuges EE-LP-SBM CRDB Shell, Design Feature of Centrifuges Review of Safety Controls and Related Programs (IP Section 02.02)
The inspectors reviewed information related to administrative (AD), active engineered (AEC),
and passive engineered (PEC) safety controls that are items relied on for safety (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
6 reflected in the actual conditions in the field. Specifically, for Cascade 6.6 in SBM 1005, the IROFS selected for review included:
IROFSC23 - design feature of centrifuges to minimize releases as a result of an impact, design basis seismic, tornado, high wind, roof, snow load, and roof ponding due to local intense precipitation events to mitigate to consequences to a low category - PEC Implementation of Safety Controls (IP Section 02.03)
For the safety controls listed above, and other controls selected as appropriate, 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:
For Cascade 6.6 in SBM 1005:
walked down the cascade and the testing/monitoring equipment for IROFS C23 testing/validation observed run-up of the cascade and associated testing observed testing data collection interviewed operators, maintenance technicians, and deputy shift manager supporting IROFS C23 testing and validation activities attended pre-job briefing and IPTE challenge meeting For LEU+ activities:
interviewed senior nuclear training instructor to verify how LEU+ activities, specifically procedure development for current and new IROFS is incorporated into training lessons plans, interviewed operators and radiation staff for general knowledge of process areas and associated hazards, specifically those hazards associated with LEU+ activities 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:
LEU+ activities reviewed IROFS-TPE-QUAL, "Items Relied On For Safety (IROFS)
Surveillance - Qualification Standard," Rev. 1, to verify the addition of LEU+
training requirements and Memo for Initial Subject Matter Experts for LEU+
IROFS (Phase1) reviewed 2025-A-08-014, "LEU+ ORR Readiness Audit," dated August 15, 2025 reviewed LEU+ training lesson plans presentations (Passive and Administrative IROFS) for site workers (generic and department level), test
7 bank questions for operators and technicians assigned to work with LEU+,
and status of site-wide LEU+ training (generic and department level) in the licensee's Learning Management System (LMS) to verify LEU+ training had been developed and implemented sitewide reviewed configuration management process regarding procedures changes for LEU+ activities to include updates and addition of IROFS Cascade 6.6 - SBM 1005 reviewed quarterly surveillance OP-3-3300-01-F-6 for IROFSC23 verification reviewed CGDP-C23-0045 (Cascade 6.6), dated August 28, 2025, and interviewed licensee staff about the IROFS C23 verification reviewed CAP entries: related to IROFS C23: EVENT-2025-3785, and EVENT-2025-1782 reviewed IROFS C23 testing procedures, commissioning checklist, calculations, boundary documents, audits and final report testing for IROFS C23 to include the following:
o OP-3-1000-27, "IPTE Challenge Meeting, IROFS C23 Evolution for Cascade 6.6 Commissioning Checklist (ETC 4323029)," dated August 20, 2025 o
OP-3-1000-27-F-3, "IPTE Briefing Summary," dated August 25, 2025 o
OP-3-0450-03, "IROFS C23 Surveillance Procedure," Rev. 16 & 17, and "IROFS C23 Surveillance Pkg," dated August 27, 2025 o
Operating Requirement Manual (ORM) C23, "Design Feature of Centrifuges to Minimize Release," Rev. 8 o
NEF-BD-C23, "Design Feature to Centrifuges to Minimize Releases,"
Rev. 7 o
OP-3-0450-01, "Run up of a TC21 Cascade," Rev. 44 and Attachment 7, OP-3-0450-01, "Cascade System Run UP of a TC21 Cascade,"
Rev. 44 o
OP-3-0400-05, "Process Service Corridor (PSC) Operations," Rev. 22, including Attachment 4, "Centrifuge Crash or Idle Response,"
o M&TE Calibration documents related to IROFS C23 testing and validation o
Qualifications records for three operators and three maintenance individuals to verify training requirements as described in OSIROFSQC00100, "Operations Training Program" and OSIROFSQCOO100, "Items Relied On For Safety (IROFS) and Operating Requirements Manual (ORM)," Rev, 9 o
ORM change request for ORM IROFS C23, OP-3-1000-08-F-1, "Operating Requirements Manual Change Request," Rev. 10 dated August 27, 2024 to verify alignment with revised CALC-S-00136 INSPECTION RESULTS No violations of more than minor significance were identified.
8 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On August 28, 2025, the inspectors presented the operational safety and nuclear criticality safety inspection results to Paul Lorskulsint and other members of the licensee staff.
9 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date NCS-CSA-109 Analysis of 30B Cylinder Array (LEU+)
Rev. 0 Engineering Evaluations NCS-CSA-118 Nuclear Criticality Safety Analysis of UUSA Process Gas Pipework (LEU+)
Rev. 0 Miscellaneous NSR-2025-017 Nuclear Safety Release for Process Gas Pipework (NCS-CSA-118) 08/22/2025 EG-3-5300-10 LEU+ Passive Engineered Control IROFS105 Surveillance Rev. 0 Posting ARY-01 Linear Chemical Trap Array Rev. 0 Posting ARY-04 IROFS110ab and IROFS124ab Pump Arrays Rev. 0 Posting ARY-05 Miscellaneous Component Carts Rev. 0 Procedures Posting ARY-06 Low Boy Carts Rev. 0 WO 1000698672 CGDP Verification (CGDP-102-0001) 03/31/2025 88015 Work Orders WO 1000703282 CGD Verification (CGDP-105-001) 06/25/2025 Corrective Action Documents EVENT(s) 2025-3785, 2025-1782 Event reports related to IROFS C23 Various IROFSLEU+PDLILT LEU+ Passive IROFS Department Level 2022 Miscellaneous IROFSLEU=ADLILT LEU+ Administrative IROFS Department Level 2022 IROFS-TPE-QUAL Items Relied On For Safety (IROFS)
Surveillance - Qualification Standard Rev. 1 NEF-BD-C23 Design Feature of Centrifuges to Minimize Releases Rev. 7 OP-3-0450-03 IROFS C23 Surveillance Procedure Rev. 16 and 17 ORM C23 Design Feature of Centrifuges to Minimize Releases Rev. 8 TQ-3-0100-12 Training Guidelines Rev. 11 Procedures TQ-3-0100-13 Training and Qualification Guidelines Rev. 12 88020 Self-Assessments OP-3-3300-01-F-6 IROFS C23 Quarterly Surveillance Verification Rev. 45
10 Inspection Procedure Type Designation Description or Title Revision or Date UUSA Audit 2025-A-08-014 LEU+ ORR Readiness Audit 08/15/2025