ML25329A001
| ML25329A001 | |
| Person / Time | |
|---|---|
| Site: | 07007004 |
| Issue date: | 11/25/2025 |
| From: | Nicholas Peterka NRC/RGN-II/DFRSS/FOB1 |
| To: | Snider M American Centrifuge Operating |
| References | |
| IR 2025003 | |
| Download: ML25329A001 (0) | |
Text
Matt Snider General Manager American Centrifuge Operating, LLC (ACO)
P.O. Box 628 Mail Stop 7560 Piketon, OH 45661
SUBJECT:
AMERICAN CENTRIFUGE PLANT (ACP) - CORE INSPECTION REPORT 07007004/2025003
Dear Matt Snider:
This letter refers to the U.S. Nuclear Regulatory Commission (NRC) inspection activities conducted from July 1, 2025 to September 30, 2025 at American Centrifuge Plant (ACP). On September 11, 2025, NRC inspectors discussed the results of the inspection activities 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.
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 25, 2025
M. Snider 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. 07007004 License No. SNM-2011
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV Signed by Peterka, Nicholas on 11/25/25
SUNSI Review X
Non-Sensitive
Sensitive X
Publicly Available
Non-Publicly Available OFFICE RII/DFRSS RI/DFRSS NAME L. Pitts N. Peterka DATE 11/25/2025 11/25/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
07007004 License Number:
SNM-2011 Report Number:
07007004/2025003 Enterprise Identifier:
I-2025-003-0062 Licensee:
American Centrifuge Operating, LLC (ACO)
Facility:
American Centrifuge Plant (ACP)
Location:
Piketon, OH Inspection Dates:
September 08, 2025 to September 12, 2025 Inspectors:
P. Startz, Fuel Facilities 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 a core inspection at American Centrifuge Plant (ACP), 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 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.
RADIOLOGICAL CONTROLS 88030 - Radiation Protection The inspectors evaluated selected aspects of the licensee's radiation protection (RP) program to verify compliance with 10 CFR 19, 20, and 70, Chapter 4 "Radiation Protection" of the facility's license application, and applicable licensee procedures.
Radiation Protection Program Review (IP Sections 02.01, 02.02, 02.03, 02.23)
The inspectors interviewed licensee staff and reviewed licensee procedures and other documentation related to the implementation of the RP program, radiological aspects of the radioactive waste programs, and the as low as reasonably achievable (ALARA) programs to verify compliance with 10 CFR 20.1101(a), 20.1101(b), 20.1101(c), 20.2102, 70.72, and the license application.
Radiation Protection/Waste Program Implementation and Procedures (IP Section 02.01 & 02.03) completed production area walkdowns to verify that components of the airborne radioactivity measurement and control systems were functional and maintained in accordance with licensee procedure Measurement of Airborne Activity, ACD2-HP-010, Rev. 12, and Operation of Low Volume Air Samplers, ACD4-HP-009, Rev. 4 interviewed the RP Manager, walked down the production areas, visually verified breathing-zone air samplers were supplied, maintained, and used as directed by Radiation Work Permits in accordance with Use of Personal Air Sampling Pumps, ACD4-SH-004, Rev. 7 Shipment and Receipt Surveys of Radioactive Material Packages, ACP4-HP-002, Rev. 0 Procedure Radiological Surveys, ACD4-HP-001, Rev. 6, continuous-use low volume air samplers for airborne radionuclide concentrations within the production area, with associated filter media counted by Ludlum 3030E in accordance with procedure Ludlam 2020E Dual Channel Scaler, ACP4-HP-102, Rev. 3 Ludlum 3030E calibrated by Energy Solutions, in compliance with licensee procedure ACP4-HP-102, Rev. 3
4 Radiation Program Review and ALARA (IP Section 02.02 & 02.23) reviewed licensee audit Annual Radiation Protection Report for ACO Piketon for 2024, Management Assessment ACP-MA-2025-09, ALARA annual report per Chapter 4 of the license application and per ACD2-HP-001, 2025 ALARA Program X3001 North Uranium Processing area, CR12550 for ACD2-HP-010 reviewed Management Assessment of Effluents and Public Dose, Radiation Safety Audit (ACP-MA-2025-05), dated 4/1/2025 reviewed requirements of licensee audit 3-year rotating audit schedule as specified in ACD2-HP-013, Rev. 2 licensee audit 3-year rotating audit schedule per ACD2-HP-013, Rev. 2 reviewed licensee audit 2025 Annual Health Physics Routine Survey Program Review, per ACD2-HP-004, dated 5/28/2025, including Condition Notification (CN) #11656 to establish Monday thru Friday surveys visually inspected the new Ludlum 3030 Alpha Beta Sample Counter and corresponding Computer Software reviewed the radiation workers training course on the new Ludlum 3030 Alpha Beta Sample Counter and corresponding Computer Software, correct operation of the Ludlum 3030E in accordance with procedure Ludlum 2020E Dual Channel Scaler, ACP4-HP-102, Rev. 3, and reviewed first shift calibration and normal in-process operations within the RP laboratory reviewed radiological waste packaging operations for compliance with Waste Management, ACD2-EC-0007, Rev. 15 Training (IP Section 02.04)
The inspectors interviewed licensee staff and reviewed RP and radioactive waste related training records to verify compliance with 10 CFR 19.12, 19.13, 70.61(f)(2), and the license application. Specifically, the inspectors reviewed training records and documents, and interviewed licensee staff as follows:
interviewed licensee staff and confirmed a sample of personnel were up to date for radiation protection and industrial health training requirements reviewed training records for technicians ES and WH, compliant with Radiological Protection Training and Qualification, ACD2-HP-002, Rev. 4 reviewed new Thermo Scientific iPCM training reviewed RAD worker 1 is the initial training reviewed RAD worker 2 is the secondary Safety-Significant Events (IP Section 02.05)
The inspectors reviewed the licensee's safety-significant events, and RP, and radioactive waste related Corrective Action Program (CAP) CN entries to verify compliance with 10 CFR 20.2201, 20.2202, 20.2203, 70.50, 70.52, 70.74, and Part 70 Appendix A and Chapters 4 and 11 (Training) of the license application. Specifically, the inspectors reviewed documents and interviewed licensee staff concerning the following:
CN #11407, identified radiological removable contamination above limits, on pump down cart #1
5 CN #11629, four 5B cylinders, clean & empty, were radiologically contaminated CN #12529, visible contamination during maintenance activity Radiation Exposure Controls (IP Sections 02.06, 02.18)
The inspectors reviewed licensee's measures such as radiological work permits to control the concentration of radioactive material in air or limiting intake to keep doses ALARA to verify compliance with 10CFR 20.1101(b), 20.1701, 20.1702, and license application chapter 4. Specifically, the inspectors interviewed licensee staff, observed activities, and/or reviewed records related to the following:
observed maintenance activities, mass spectrometers #1 & #2, radioactive material (RAM) contamination, under Radiation Work Permit (RWP) 2025-X-2001-0034-G observed testing activities, contamination control area, new 5B/12B cylinder pressure checks, uranium contamination in pump cart, under RWP 2025-X-3001-0049-G observed storage of contaminated equipment, and used UF6 pigtails observed one 30-gallon RAM storage drum and four B-25 RAM storage boxes used to store low level contaminated waste such as personal protective equipment observed activities conducted by operations in the X3001 North Uranium Processing area, under RWP 2025-X-2002-6298-G "Respiratory Protection Program," ACD2-SH-007, Rev. 7 Reviewed PAPR vendor training reviewed the storage of U-Material Vacuum Cleaner Instrument Calibration and Surveys (IP Sections 02.07, 02.08, 02.14, 02.15)
The inspectors reviewed licensee procedures and documentation for RP instrument calibration, radiation surveys, contamination control measures; use of radiation detecting instruments and equipment and interviewed licensee staff to verify compliance with 10 CFR.0.1501, 20.1902, 20.2103, 70.24, and Chapter 4 of the license application. Specifically, the inspectors observed activities, reviewed documents, and/or interviewed licensee staff concerning the following:
Instrument and Equipment/Calibration (IP Sections 02.07 & 02.08) radiological instrumentation calibration services generally provided by Department of Energy contractors: Fluor-BWXT Portsmouth, LLC (FPB) calibration quality assurance: Triennial Supplier Evaluation Report, Fluor-BWXT Portsmouth, LLC (FPB), ACP-SE-2023-28, July 10-20, 2023 Supplier Annual Evaluation, Fluor-BWXT Portsmouth, LLC, ACP-SE-2024-20, 08/12/2024 Expanded Scope Evaluation of Fluor-BWXT Portsmouth, LLC, ACP-SE-2025-02, Rev. 1, March 17-20, 2025 Ludlum model 3030E, procedure Ludlam 2020E Dual Channel Scaler, ACP4-HP-102, Rev. 3 Ludlum model 17 Frisker procedure Ludlum Model 177 Frisker Operation, ACP2-HP-002, Rev. 0
6 Ludlum model 12 procedure Operation of Ludlum Model 12 Survey Meter with Ludlum Model 44-9 or Ludlum Model 43-5 Probe, ACD2-HP-011, Rev. 4 Eberline Teletector 6112B procedure Operation of the Eberline Teletector 6112B, Rev 2 Ludlum RO-20 procedure Operation of the RO-20 Survey Meter, ACD4-HP-005, Rev. 4 Radiation Surveys & Contamination Control (IP Sections 02.14 & 02.15) reviewed functional testing of the two new Thermo Scientific iPCMs gas/source/alarm functional checks for 8/28/25 and 9/2/25 reviewed weekly source check of the new Thermo Scientific iPCMs posted at the PCM machines, for 2025 and on-going reviewed procedure Monitoring and Decontamination of Personnel for Radioactive Contamination, ACD2-HP-009, Rev. 3 reviewed survey of incoming uranium hexafluoride (UF6) Cylinders reviewed surface contamination limits listed in Appendix E, Conduct of Operations, ACD2 HP 004, Rev. 15 reviewed a sample of weekly and monthly contamination survey records reviewed "Routine Surveys" listed in section 4.10 of Conduct of Radiological Operations, ACD2-HP-004, Rev. 15 Postings and Labeling (IP Sections 02.09, 02.10, 02.16)
The inspectors observed the posting and labeling of radiation areas, radioactive material storage areas, radioactive containers, and control of licensed sealed sources to verify compliance with 10CFR 20.1902, 20.1903, 20.1904, 20.1905, and Chapter 4 of the license application. Specifically, the inspectors observed the following area posting and reviewed the following records:
Posting/ Container Labeling (IP Sections 02.09 & 02.10) 1.
"Radiation Area" posting in controlled access areas defined in Conduct of Radiological Operations, ACD2-HP-004, Rev. 15 2.
every container in this area may contain radioactive materials posted in controlled access areas 3.
respiratory protection required per RWP's in posted areas, related to potential for airborne radioactivity Sealed Sources (IP Section 02.16) 1.
observed storage of sealed sources 2.
discussed inventory and source leak tests conducted every 6 months, records kept in eDocs 3.
reviewed ACD2-HP-12, Radioactive State Licensed Sources and Standards Posting of Notices (IP Section 02.11)
The inspectors observed the posting of notices to verify compliance with 10 CFR 19.11 Specifically; the inspectors observed the following notice:
NRC Form 3 posted in the plant entrance office wall bulletin boards
7 Access Control (IP Section 02.12)
The inspectors observed the licensee's access control measures for radiation areas to verify compliance to 10 CFR 20.1502(a)(4), 20.1601, 20.1602, and Chapter 4 of the license application. Specifically, the inspectors observed controls, reviewed documents, and/or interviewed licensee staff concerning the following:
1.
observed badge reader and turnstile for accessing production area potential radiation areas 2.
reviewed logging time in area for Standing RWPs 3.
reviewed Radiation Protection Program requirements Licensed Material Control (IP Section 02.13)
The inspectors observed the licensee's measures to secure stored material and control and maintain constant surveillance of licensed material not in storage to verify compliance with 10CFR 20.1801, 20.1802, and Chapter 4 of the license application. Specifically, the inspectors reviewed the following:
1.
storage of sealed sources in limited access/secure area 2.
radiation source inventory & leak checks conducted bi-annually Dose Assessment Program (IP Sections 02.17, 02.22)
The inspectors interviewed licensee staff and reviewed records and calculations from 2024 related to the licensees assessment and assignment of doses to workers to verify compliance with 10 CFR 20.1201, 20.1204, 20.1207, 20.1208, 20.1502(b), 20.2104, 20.2106 and the license application. Specifically, the inspectors interviewed licensee staff and/or reviewed records related to the following:
2024 workforce dose assessments, final "NRC Form 5" Oak Ridge Institute Radiation Exposure Information and Reporting System (REIRS), "Data Verification" for 2024 monitoring year, memo dated 4/20/2025 practices, policies, and dose assessments regarding pregnant employees per procedure Reproductive Hazards, ACD2-SH-002, Rev. 6; and procedure, Dosimetry Program Standards, ACD2-HP-006, Rev. 10 Dosimetry Program (IP Sections 02.19, 02.20, 02.21)
The inspectors interviewed licensee staff and reviewed the implementation and documentation of the internal and external dosimetry programs including bioassay, whole body counting, and use of dosimetry in the field to verify compliance with 10 CFR 20.1502(a), 20.1502(b), 10 CFR 20.2103(b)(3), and the license application. Specifically, inspectors interviewed licensee staff and/or reviewed records related to the following:
Bioassay Program & Whole-Body Counting (IP Section 02.19 & 02.20) no exceedances of uranalysis results exceeding the action level of 0.5 ug/L occurred in 2024 nor 2025
8 procedure Urinalysis Program, ACD2-HP-007, Rev. 13, specifies what personnel will receive uranalysis, generally for personnel going into RWPs, these personnel are required to have an analysis at least quarterly commercial laboratory GEL performs urinalysis Dosimetry (IP Section 02.21) verified National Voluntary Laboratory Accreditation Program (NVLAP) accreditation for the licensee's dosimetry contractor, Marion Technologies Inc, certificate ISO/IEC17025, applicable to 6/30/2026 reviewed dosimetry used including badge-type Marion thermoluminescent dosimeter (TLD) in accordance with ACD2-HP-6, and electronic dosimeters used for special activities in accordance with ACP2-HP-001 quarterly dosimetry change-out periodicity for RP entries respiratory protection fit testing to verify compliance with licensee procedure ACD2-SH-007 FACILITY SUPPORT 88070 - Permanent Plant Modifications The inspectors conducted a review to verify the licensee had established and implemented a configuration management system to evaluate, implement, and track changes to the facility in accordance with the applicable requirements in Title 10 of the U.S. Code of Federal Regulations (10 CFR) Section 70.72 and the License Application, Chapter 11, Management Measures/Configuration Management The inspectors review also verified the licensee had established management measures for changes to the facility in accordance with 10 CFR 70, Subpart H and the License Application, and that modifications involving new processes met the requirements in 10 CFR 70.64.
Sample Selection (IP Section 02.01)
The inspectors reviewed licensing documents, changes the licensee determined did not require pre-NRC approval under 10 CFR 70.72, and changes that affected the integrated safety analysis summary (ISA) to select changes/modifications to review. To assess whether the licensee conducted evaluations according to their established configuration management system, the inspectors selected the following plant modifications for review:
reviewed ESO-3100-0145, Phase 2 Fissile Material Storage Area (FMSA)
Expansion, CFC5, and associated container storage racks, and a new cage performed walk-down of the new FMSA Expansion including new container storage racks and verified that critical separation dimensions match drawings DX-390-0044-M-Z, Rev. 0, 5 sheets, and X-3001-9591.18-ME-Z, Rev. B, 2 sheets reviewed project ESO-3501-0005, Vehicle Barrier Systems performed walk-downs of the new Vehicle Barrier Systems to verify general compliance with drawings X-2220N-2019.30 and 31 reviewed facility documentation associated with the selected changes to verify the affected documents were updated promptly in accordance with 10 CFR 70.72(e) or the timeframe outlined in the license
9 Facility Change/Modification Process (IP Section 02.02)
The inspectors reviewed the selected modifications listed above to verify the licensee established a configuration management system in accordance with 10 CFR 70.72 and the conditions of the license. Specifically, the inspectors performed the following:
reviewed configuration management package/Change Evaluation PCE 24-0165, Rev. 0, Vehicle Barrier System, to verify the licensees evaluation of changes provided valid technical bases to determine whether an amendment to the license was required based on the criteria in 10 CFR 70.72(c) reviewed procedure "Configuration Management Description," ACD2-EG-002, Rev. 12 reviewed procedure Change Evaluation, ACD2-RG-001, Rev. 28, walked down the new FMSA 2 cage and verified general construction characteristics and dimensions of the cage matched drawing FMSA 2 Cages Plan, X-3001-9505-A-Z, Rev. A walked down the new FMSA storage array and verified general construction assemblies and dimensions of the array matched drawing FMSA 2 5B Storage, X-3001-9807-ME-Z, Rev. A Management Measures (IP Section 02.03)
For the selected modifications, the inspectors reviewed the management measures established for affected items relied on for safety (IROFS) (or credited safety controls) to verify the management measures ensured the IROFS (or credited safety controls) were available and reliable to perform their intended function as required by 10 CFR 70.61 and the license. Specifically, the inspectors performed the following:
verified that Boundary Definition BDD-H-008, Rev. 1, of IROFS 7.3.3.2, Vehicle Access Control, limits the access of vehicles within the ACP Controlled Area, around and within process buildings, and from specified material storage areas verified procedure Vehicle Control Within ACP Facilities, ACD2-FO-003, Rev. 8, specifies comprehensive overall controls of vehicles within ACP Controlled Area, verifies compliance with IROFS 7.3.3.2 verified procedure Vehicle Control Within ACP Facilities, ACD2-FO-003 Rev.
8, Appendix B drawing shows comprehensive vehicle controls, to verify compliance with IROFS 7.3.3.2 observed the barrier gate, for the Vehicle Barrier Systems project was installed in specified locations verified that the barrier gate was designed and tested as required verified that an alternative vehicle barrier was designed and evaluated as an acceptable alternative to the barrier gates, for installation in specified locations, and was selected in accordance with a formal engineering evaluation EE-3501-001, that was in accordance with ACD3-EG-205 reviewed post-installation testing procedures and post-installation test results to verify adequate implementation of the design and functionality of the new equipment discussed maintenance and surveillance records of the above installations, spare parts where applicable, to verify the licensee established periodic
10 inspections, maintenance and surveillance activities in accordance with the license interviewed licensee staff and reviewed change management procedures to verify the licensee implemented the aspects described in configuration management system procedures and the license application interviewed licensee staff and reviewed a sample of training records to verify the staff involved in facility changes were qualified in accordance with the license and plant procedures reviewed IROFS Surveillance Evaluation No. IS-H-001, Post modification Inspection Activities, Form AC-721, IROFS Surveillance Form, X-3001 FMSA Safe Geometry Container (SGC) Racks, 3 each, completed/dated 6/12/2025 reviewed Modification Master Checklist Signatures, ESO-3100-0145, Full Nuclear, 6/12/2025, Form AC-021A of ACD2-EG-003 reviewed Statement of Work, SOW-3101-0082, Rev. 0, ESO-3100-0145, Fabricate and Install SGC Racks, QL-1, approved/signed 2/26/2025 reviewed Purchase/Fabrication Package ESDS-AC-0311, for SGC/Mass Spec racks, QL-2, signed/dated 7/6/2021 reviewed Inspection Report QA-2025-06-03, SOW-3101-0082 Rev. 1, SGC Storage Racks/Fabricated by Geiger Brothers for X-3100 South FMSA Area, per drawing DX-390-0044-M-Z, Rev. 1, dated 6/16/2025 reviewed Audit, "Annual Fissile Material Operations Management Assessment, ACP-MA-2025-02, dated 5/29/2025, verifies compliance with procedure "Management Assessment Program," ACD2-QM-001, Rev. 39 reviewed procedure "Quality Assurance/Independent Audit and Assessment Program," ACD2-QM-002, Rev. 22 reviewed procedure "Corrective Action Program," ACD2-RG-004, Rev. 31 License Application Changes (IP Section 02.04)
For the selected modifications, the inspectors interviewed licensee staff and reviewed applicable sections of the license application to verify the licensee evaluated license application changes and conducted NRC pre-approval screenings in accordance with the license requirements. Specifically, the inspectors performed the following:
interviewed licensee staff to verify the licensee properly implemented their configuration management system procedures for determination for NRC pre-approval of the following license application change implemented in 2024:
o License Amendment Request (L-2023-LLA-00240), application supplemental proposed changes for LA-3605-0001, in part, to establish and maintain a Vehicle Barrier System, dated March 7, 2024 New Processes at Existing Facilities (IP Section 02.05)
The inspectors reviewed the configuration management packages of facility physical changes related to a revision of their license application regarding operational parameters, to verify the licensee addressed the requirements of 10 CFR 70.64 and evaluated whether prior NRC approval was needed for the change in accordance with 10 CFR 70.72 and the license conditions. Specifically, the inspectors performed the following:
11 reviewed the licensees configuration management procedures used to determine whether NRC pre-approval of license application changes is required to verify the licensee correctly evaluated license application changes reviewed a sample of the most recent revisions made to license application to verify the licensee followed their approved change process and reached the correct conclusions verified that the licensee submitted a License Amendment Request (L-2023-LLA-00240), application supplemental proposed changes for LA-3605-0001, in part, to establish and maintain a Vehicle Barrier System, dated March 7, 2024 Records Retention (IP Section 02.06)
The inspectors reviewed a sample of plant documents impacted by the selected modifications to verify the licensee appropriately maintained records of facility changes in accordance with the license requirements and 10 CFR 70.72. The sample documents included:
reviewed operating procedure Security Access Control and Alarm System, ACD2-SP-046, Rev. 18, was revised to include operational aspects of the Vehicle Barrier System, and verifies that the procedure was revised to accommodate the new barrier systems reviewed CNs #12388, 12351, 12634, 12594, 12389, 12574 and 12650for compliance with procedure Corrective Action Program, ACD2-RG-004, Rev.
31 License Amendment Request (L-2023-LLA-00240), application supplemental proposed changes for LA-3605-0001 Integrated Safety Analysis Summary, LA-3605-0003, Rev. 50, June 2025 Addendum 1 of the Integrated Safety Analysis Summary, Summary for the American Centrifuge Plant, LA-3605-0003A, Rev. 44, June 2025 INSPECTION RESULTS No issues were identified.
EXIT MEETINGS AND DEBRIEFS The inspectors verified that no proprietary information was retained or documented in this report.
On September 11, 2025, the inspectors presented the core inspection results to Matt Snider and other members of the licensee staff.