ML25350C345
| ML25350C345 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 01/13/2026 |
| From: | Nicholas Peterka NRC/RGN-II/DFRSS/FOB1 |
| To: | Lorskulsint P Louisiana Energy Services, URENCO USA |
| References | |
| EN57989 IR 2025004 | |
| Download: ML25350C345 (0) | |
Text
EN57989 Paul Lorskulsint Chief Nuclear Officer Louisiana Energy Services (LES) dba Urenco USA Urenco USA P.O. Box 1789 Eunice, NM 88231
SUBJECT:
URENCO USA - INTEGRATED INSPECTION REPORT 07003103/2025004
Dear Paul Lorskulsint:
On December 31, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at URENCO USA. On December 4, 2025, the NRC inspectors discussed the results of this inspection with Barry Love and other members of your staff. The results of this inspection are documented in the enclosed report.
No violations of more than minor significance were identified during this inspection.
Due to the temporary cessation of government operations, which commenced on October 01, 2025, the NRC began operating under its Office of Management and Budget-approved plan for operations during a lapse in appropriations. Consistent with that plan, the NRC operated at reduced staffing levels throughout the duration of the shutdown. However, the NRC continued to perform critical health and safety functions and make progress on other high-priority activities associated with the ADVANCE Act and Executive Order 14300. 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 NRC modified the facilitys inspection plan (ML25344A465) considering inspection of partial samples, previously inspected, and deferred inspections in accordance with IMC 2600.
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 Fuels Oversight Branch 1 Division of Fuels, Radiological Safety, and Security January 13, 2026 Signed by Peterka, Nicholas on 01/13/26
P. Lorskulsint 2
Docket No. 07003103 License No. SNM-2010
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFRSS RII/DFRSS RII/DFRSS NAME TSippel CUbben NPeterka DATE 12/17/25 12/17/25 1/13/26
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07003103 License Number:
SNM-2010 Report Number:
07003103/2025004 Enterprise Identifier:
I-2025-004-0032 Licensee:
Louisiana Energy Services (LES) dba Urenco USA Facility:
URENCO USA Location:
Eunice, NM Inspection Dates:
October 1, 2025 to December 31, 2025 Inspectors:
T. Sippel, Sr. Fuel Facility Project Inspector C. Ubben, Fuel Facilities Inspector Approved By:
Nicholas E. Peterka, Acting Chief Fuels Oversight 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 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 Type Issue Number Title Report Section Status WER 07003103/2025-004-00 Concurrent Report of Discharge (EN57989) 88072 Closed
3 PLANT STATUS The URENCO USA (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 6.7.
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.
FACILITY SUPPORT IP 88051 - Evaluation of Exercises and Drills The inspectors were unable to conduct an onsite inspection of the emergency exercise due to the government shutdown, therefore, after the exercise, the inspectors reviewed documents related to the licensees graded biennial exercise conducted on October 8, 2025, involving both on-site and off-site participants, to verify compliance with 10 CFR 70.32(i), the Emergency Plan, and Chapter 8, "Emergency Management" of the license application (Safety Analysis Report (SAR)). The scenario included a bomb threat, fire impinging on 48Y cylinders, a release from a 48Y cylinder, and three injured personnel with potential hydrogen fluoride (HF) exposure and radiological contamination.
Exercise Planning (IP Section 02.01)
The inspectors reviewed the emergency exercise documentation to verify compliance with the Emergency Plan, Emergency Plan Implementing Procedures and 10 CFR 70.32(i).
Specifically, the inspectors:
reviewed the URENCO USA Emergency Preparedness Exercise Report, "2025-Full-Scale Exercise," dated October 23, 2025 and LES-25-100-NRC, "Emergency Preparedness 2025 Full Scale Exercise package," to verify that:
o the emergency exercise was conducted by the licensee at the required frequency o
the emergency exercise scenario tested all elements of the Emergency Plan o
the emergency exercise scenario was based on scenarios that were identified as credible or probable for the facility o
exercise personnel, including controllers and players, were briefed on their duties and responsibilities prior to the exercise
4 Exercise Execution and Emergency Plan Implementation (IP Section 02.02)
The inspectors reviewed the URENCO USA Emergency Preparedness Exercise Report, and 2025-S-10-003, "UUSA Emergency Preparedness 2025 Full Scale Exercise Surveillance" to verify compliance with the Emergency Plan, Emergency Plan Implementing Procedure and 10 CFR 70.32(i). Specifically, the inspectors reviewed documented evidence of:
the licensees assessment and classification of the exercise scenario emergency operations center (EOC) staffing off site response organizations' participation drafting of timely offsite notifications response to emerging situations to address the exercise scenario and meet the exercise objectives press release approval and issuance the emergency response teams actions including securing the scene of the incident Additionally, while onsite for another inspection in December, the inspectors:
observed six licensee staff members receiving training on, and demonstrate their capability to use a fire extinguisher to fight an incipient fire Critiques, Exercise Control, and Identification and Resolution of Problems (IP Section 02.03)
The inspectors reviewed the licensees corrective action program (CAP) entry that resulted from the emergency preparedness exercise to verify compliance with the Emergency Plan, Emergency Plan Implementing Procedure and 10 CFR 70.32(i):
EVENT-2025-6378, "October 8, 2025 Full Scale Exercise," created October 22, 2025; which documented 17 actions for improvement that the licensee identified during the exercise documentation of critiques conducted by the licensee in the URENCO USA Emergency Preparedness Exercise Report documentation of comments and suggestions for improvement by licensee evaluators in the URENCO USA Emergency Preparedness Exercise Report IP 88072 - Plant Modifications (Triennial)
The inspectors conducted an extensive review into the licensees configuration management system for plant modifications to ensure that safety-related systems and components (i.e., items relied on for safety (IROFS) or credited safety controls) could adequately perform their intended safety function and that system changes had not adversely impacted plant safety and operability. The inspectors review focused on verifying compliance with the applicable requirements in 10 CFR 70 and the SAR, Chapter 11, Management Measures.
Selection of Modifications (IP Section 02.01)
The inspectors selected the following processes for an in-depth review of historical modifications:
The Small Component Decontamination Train (SCDT)
5 MOD-18-0012C, "SCDT Boiler Replacement with Tankless Water Heater Unit," dated May 8, 2024 Change to IROFS54a Boundary Definition Document for 70.72(c) Review 2024-018, dated January 30, 2024 Change to IROFS54b Boundary Definition Document for 70.72(c) Review 2024-018, dated January 30, 2024 The Multi-Function Decontamination Train (MFDT)
MOD-21-0007, "MFDT Crane Hoist Uprating for Additional Capacity," dated May 26, 2023 Rev. 19 to RW-3-4000-02, "Startup, Operation, and Shutdown of MFDT" for 70.72(c) review 2021-374, dated October 1, 2021 Rev. 20 to RW-3-4000-02, "Startup, Operation, and Shutdown of MFDT" for 70.72(c) review 2023-057, dated July 17, 2023 The Liquid Effluent Collection and Transfer System (LECTS), including the Slab Tanks, and the Bulk Storage Tanks (BSTs)
ECR-8226, "Building 1100 LECTS Piping System 2AC Labeling," dated July 31, 2013 ECR-9466, "DCN-2014-001 - CRDB Slab Tanks," dated September 27, 2016 MOD-16-0051, "QL-3 Designation for 681 and 684 System Components,"
dated August 30, 2016 MOD-17-0190, "Replace pH probe 3800VP-01 with pH probe HX338-01 in MFDT/LECTS," dated August 9, 2017 MOD-22-0040, "Slab Tanks Recirculation Pump Alternative," Rev. 0 MOD-24-0017A, "Removal of pH Probes from the LECTS," dated August 8, 2025 Rev. 13 to RW-3-2000-01, "LECTS Operations" for 70.72(c) review 2019-088, dated April 4, 2019 Rev. 18 to RW-3-2000-01, "LECTS Operations" for 70.72(c) review 2024-001, dated January 3, 2024 Design Process Review (IP Section 02.02)
For the selected modifications listed above, the inspectors reviewed the design process to verify the licensee followed the applicable configuration management requirements in the SAR and 10 CFR 70. Specifically, the inspectors conducted the inspection activities listed below:
interviewed licensee staff, performed walk-downs, and reviewed configuration management packages and supporting documentation to verify that plant modifications were developed, reviewed, classified, approved, and implemented in accordance with 10 CFR 70.72, Facility Changes and Change Process, and 70.62(d), Management Measures, and the baseline design criteria of 10 CFR 70.64, as applicable.
interviewed licensee staff, performed walk-downs, and reviewed configuration management packages and supporting documentation to verify that safety systems and components impacted by the modification, including interactions with other systems, would perform their intended safety function as described
6 in the integrated safety analysis (ISA) and other safety program documentation reviewed portions of FPE-REV-001 and CALC-F-00001, for fire areas 6 and 8, reviewed applicable transient combustible permits for these areas, and performed walkdowns to verify that the current facility configuration was reflected in the fire hazard analysis documents interviewed licensee staff, performed walk-downs, and reviewed documentation to verify the licensee applied management measures to the IROFS affected by the modifications in accordance with 10 CFR 70.62 interviewed licensee staff, performed walk-downs, and reviewed operator workaround and corrective action documents for plant modification issues, including configuration management audits and associated corrective actions, to verify compliance with Chapter 11 of the SAR. The scope of the corrective action review included outstanding design and operational issues (e.g., leaks, plugs) for the processes selected for in-depth review.
System Condition and Capability Review (IP Section 02.03)
For the selected modifications, the inspectors reviewed the system condition to verify they were consistent with the applicable design requirements and licensing basis. Specifically, the inspectors conducted the inspection activities listed below:
interviewed licensee staff, reviewed modification packages, and walked down the SCDT, MFDT, LECTS and their connecting piping to verify the modification was adequately implemented consistent with the configuration management package interviewed licensee staff, reviewed records, and walked down the SCDT, MFDT, LECTS and their connecting piping to verify the ISA or safety basis applicable to the systems modifications were consistent with the actual configuration and operation interviewed engineering and waste/recycle staff and reviewed records to verify that management measures were properly implemented to ensure that IROFS (e.g., IROFS55a/b, IROFS165a/b, IROFS166a/b) were available and reliable to perform their intended function interviewed licensee staff, reviewed records, and walked down the SCDT, MFDT, LECTS and their connecting piping to verify that administrative controls that involve operator action could be accomplished as assumed in the licensee's ISA interviewed licensee staff, reviewed procedure, and observed autoclave leak check surveillance for IROFS10 (Note: this test was not performed as a result of a modification, but is a routine maintenance activity associated with IROFS10)
Post-Modification Testing (IP Section 02.04)
For selected modifications, the inspectors interviewed licensee staff and reviewed post-modification testing records to determine whether the plant was in a safe configuration during post-modification testing. The inspectors reviewed the following post-modification tests to determine whether post-modification testing ensured adequate implementation of the design and safety system functionality.
7 The inspectors interviewed staff concerning the ongoing post maintenance testing for the installation and initial startup of Cascade 6.7 and observed licensee staff perform testing and calibration of associated systems for IROFSC23 Documentation Review (IP Section 02.05)
The inspectors reviewed a sample of plant documents impacted by the modifications selected for review to verify the licensee had either updated or was in the process of updating such documents to reflect the modifications in accordance with the SAR requirements and 10 CFR 70.72. Additionally, the inspectors followed-up on a Written Event Report (WER) related to a discharge that was reported to the State of New Mexico. The inspection sample included:
NEF-BD-24c, "Administrative Establishment of Airflow Away from the Worker,"
Rev. 0, 1, and 2 NEF-BD-54b, "Administratively Limit the Calculated SCDT Uranic Mass Inventory," Rev. 0, 2, 3, and 5 NEF-BD-55a, "Limit Liquid Effluent Collection and Transfer System (LECTS)
Tank and Tote Uranium Enrichment Inventory," Rev. 1 and 6 NEF-BD-56b, "Administratively Limit Uranic Mass in the Disassembly and Spray Stations of the MFDT," Rev. 0 and 2 NEF-BD-57a, "Administratively Limit Uranic Mass in the Degreaser, Citric Acid, Neutralization, and Demineralization Baths of the MFDT," Rev. 0 and 2 RW-3-4000-01, "Startup, Shutdown, and Operation of the SCDT," Rev. 13, dated October 1, 2025 RW-3-4000-02, "Startup, Operation and Shutdown of the Multi-Functional Decontamination Train," Rev. 23, dated October 1, 2025 RW-3-2000-01, "LECTS Operations," Rev. 19, dated November 4, 2024 selected Piping and Instrumentation Diagrams (P&IDs) for SCDT, MFDT, and LECTS reviewed Rev. 49 through 52 of the SAR (license application) reviewed Rev. 45 through 45c of the Quality Assurance Program Description (QADP)
INSPECTION RESULTS WER Concurrent Report of Discharge (EN57989)
WER 2025-004 88072
==
Description:==
On October 15, 2025, the licensee provided a concurrent report to the NRC (EN57989) as required by 10 CFR 70 Appendix A (c), due to submitting a required report to the State of New Mexico. "On 10/14/2025, work to empty laboratory rinse water into an approved discharge route commenced in accordance with procedure. This routes the rinse water to a lined retention pond, as approved in Urenco USA's discharge permit. During transfer of the rinse water, it was identified that the rinse water was not being put into the intended location. It was determined that it was being put into a cement vault for a domestic water flowmeter. The contents of the tote are approximately 330 gallons of rinse waster from non-radiological labware for reagent preparation from the chemistry laboratory, containing
8 primarily deionized water with dilute acids, detergents, and neutralized with sodium bicarbonate. It was analyzed to be within allowable limits for uranium concentration and pH in accordance with the discharge permit and NMAC 20.6.2.3103, prior to removal from the laboratory. This event has been put into the corrective action program and corrective actions are ongoing."
The NRC did not perform a documented reactive inspection determination for this event, as due to its low safety significance it did not trigger any thresholds for reactive inspection, and was obviously appropriate for routine inspection follow-up.
The inspectors walked down Lift Station 4 and the vault, which is located immediately next to Lift Station 4 and looks similar from the outside. The inspectors reviewed the following documents and interviewed licensee staff about them:
EVENT-2025-6179, "Lift Station 4 Markings," dated November 24, 2025 EVENT-2025-6187, "Environmental: Unauthorized Discharge," reviewed December 4, 2025 Quantitative Analysis - Summary Report, for IBK 0618 TOTE, dated March 6, 2025 RW-3-2000-07, "Handling of Miscellaneous Liquid Effluent," Rev. 3 The Quantitative Analysis, dated March 6, 2025, contained the results of the licensee's analysis of the uranium content of the tote that is required by RW-3-2000-07 to be conducted before the tote can be approved for disposal. The inspectors confirmed that the uranium concentration was much less than the 10 CFR 20 Appendix B limits for releases of uranium; and much less than the licensee's internal limits for release. Specifically, the tote contained water with a uranium concentration of 1.39 parts per billion, which is less than the concentration of uranium in seawater.
The licensee's immediate corrective actions after discovering this spill was to pump the liquid out of the cement vault, which they completed the next day, October 15, 2025. However, they could not discount that a small amount may have leaked from the cement vault before it was pumped out. Other licensee corrective actions included labeling the lift stations and vaults to prevent any further mistakes by making it clear where to empty the totes. The inspectors noted that the licensee self-identified this event, and that they also self-identified that previous events of this type have occurred. Like this event, the previous events occurred when licensee staff emptied a tote that had been approved for release in the wrong location (in the same vault that is adjacent to Lift Station 4). However, in all cases, the contents of the totes had been sampled and verified by the licensee to meet the applicable release limits. The inspectors reviewed the following documentation demonstrating that the licensee was sampling the totes to ensure they were acceptable for release:
Quantitative Analysis - Summary Report, 300 gal lab tote, dated July 1, 2020 WO 1000320158, "CRDB: Empty Chemlab Tote Lift Station 4," performed December 20, 2017 Because of the very low concentrations of uranium for this disposal pathway, the inspectors considered these releases to be of very low, or no, safety and environmental significance.
No violations of more than minor significance were identified. Therefore, WER 07003103/2025-004-00, "Concurrent Report of Discharge (EN57989)" is closed.
9 EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On December 4, 2025, the inspectors presented the integrated inspection results to Barry Love and other members of the licensee staff.
10 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date Miscellaneous LES-25-100-NRC Emergency Preparedness 2025 Full Scale Exercise package 08/06/2025 88051 Self-Assessments 2025-S-10-003 UUSA Emergency Preparedness 2025 Full Scale Exercise Surveillance 11/18/2025 EVENT-2025-0221 HF Release from MFDT during Down-blending Operations EVENT-2025-0221, -0427, -
1483, -2068, -
2120, -4438, -
5366, -6154, -
6359, -6518, -
6541 EVENT-REACT-2024-EV164350,
-EV165015, -
EV166979, -
EV167886 LECTS, SCDT, and MFDT related CAP entries Various EVENT-2025-0727, -0896, -
0899, -0959, -
1151, -1345, -
1562, -1587, -
1592, -1626, -
1736, -2326, -
2341, -2943, -
2944, -2948, -
3053, -3482, -
5738, -5903, -
6033, -6259, -
- 6535, Modification and Configuration Control related CAP entries Various 88072 Corrective Action Documents EVENT-REACT-2016-EV113299 Tracking EV to ensure training on new revision of IROFS 55a/b was completed 10/16/2017
11 Inspection Procedure Type Designation Description or Title Revision or Date EVENT-REACT-2020-EV140553 MFDT Degreaser Bath Workaround 09/28/2020 EVENT-REACT-2020-EV151380 MFDT Degreaser Bath Workaround 01/12/2024 EVENT-REACT-2021-EV148529 Workaround for LECTS pH probes 12/01/2021 EVENT-REACT-2022-EV156798 Chem Lab Sink Workaround 01/10/2023 Drawings LES-1100-P-PID-628-001-02 P&ID Cylinder Receipt and Dispatch Building Small Component Decontamination Train Rev. 1 ECR 8113 Add flanges to the LECTS piping system 05/15/2013 ECR 8183A LECTS Slab Tank Vents to GEVS 07/12/2013 Engineering Changes ECR 9186 Replace bronze valve and copper piping with stainless steel in LECTS flush water system 04/08/2015 2019-088 10 CFR 70.72(c) Applicability Determination 04/11/2019 2020-428 10 CFR 70.72(c) Applicability Determinization 11/12/2020 2020-562 10 CFR 70.72(c) Applicability Determinization 11/10/2020 2021-374 10 CFR 70.72(c) Applicability Determination 10/01/2021 2022-047 10 CFR 70.72(c) Applicability Determinization 04/29/2022 2022-106 10 CFR 70.72(c) Applicability Determinization 09/02/2022 2023-032 10 CFR 70.72(c) Applicability Determinization 04/12/2023 2023-057 10 CFR 70.72(c) Applicability Determination 07/17/2023 51-2400537 LES Decontamination Workshop and Decontamination System HAZOP and Risk Determination Analysis Rev. 7, dated 02/09/2024 51-2400546 LES Liquid Effluent Collection and Transfer System HAZOP and Risk Determination Analysis Rev. 5, dated 02/13/2024 CALC-F-00001 Attachment C Fire Hazard Analysis Combustible Loading, CRDB 1100 Rev. 20, 03/10/2020 FPE-REV-001 Fire Hazards Analysis for URENCO USA Rev. 21, 03/10/2020 Engineering Evaluations ISA-IIE-0637-00 ISA Impact Evaluation for MOD-22-0040, "Slab Tanks Recirculation Pump Alternative" Rev. 0, dated
12 Inspection Procedure Type Designation Description or Title Revision or Date 03/03/2023 ISA-MEM-0032 Decontamination System HAZOP and Risk Determination Analysis, with Supplemental Information on LECTS Rev. 8 ISA-MEM-0037 Liquid Effluent Collection and Transfer System HAZOP and Risk Determination Analysis Rev. 4 AD-3-1000-02 Procedure Use and Adherence Rev. 24 AD-3-1000-10 Change Process Management Rev. 23 CH-3-1040-05 Liquid Waste Transfer Rev. 1 EG-3-4100-02 Plant Modifications Rev. 27 EG-3-4100-04 Temporary Modifications Rev. 8 LS-3-1000-04 10 CFR 70.72c Evaluations for Proposed Changes Rev. 28 MA-3-2470-01 Autoclave Leak Check Surveillance IROFS10 Rev. 12 Procedures WC-3-1000-02 Work Package Initiation through Closure (SAP Order Types PM1/PM3)
Rev. 54 2025-A-05-006 Plant Modifications, Configuration Management, Commercial Grade Dedication, and Design Program NQA-1 Audit 06/09/2025 MA-2025-005 Management Assessment of QA Activities 02/17/2025 Self-Assessments SA-2023-012 Plant Modifications Self-Assessment 12/22/2023 Work Orders WO 1000714933 CRDB: 861-OU52 Window Cable Broke *IPTE*
08/05/2025