ML25241A036
| ML25241A036 | |
| Person / Time | |
|---|---|
| Site: | 07000925 |
| Issue date: | 09/17/2025 |
| From: | Vontill B NRC/NMSS/DDUWP/URMDB |
| To: | Cimarron Environmental Response Trust, Environmental Properties Management |
| Shared Package | |
| ML25241A034 | List: |
| References | |
| Download: ML25241A036 (1) | |
Text
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 1 OF 9 PAGES MATERIALS LICENSE Amendment 23 Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and the applicable parts of Title 10, Code of Federal Regulations, Chapter I, Parts 19, 20, 30, 31, 32, 33, 34, 35, 36, 39, 40, 51, 70, and 71, and in reliance on statements and representations heretofore made by the licensee, a licensee is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee 1 Cimarron Environmental Response Trust
- 3. License Number SNM-928
- 4. Expiration Date Until terminated 2.
c/o Environmental Properties Management, LLC 9400 Ward Parkway Kansas City, MO 64114
- 5. Docket or Reference Number 070-00925
- 6. Byproduct, Source, and/or Special Nuclear Material:
7.
Chemical and/or Physical Form:
8.
Maximum Amount that Licensee May Possess at Any One Time Under This License:
A.
Uranium enriched to A.
Any compound A.
1,200 grams of 5.0 wt. % in U-235 contained U-235 (Note 1)
B.
Natural and depleted B.
Any compound B.
2,000 kilograms of uranium source material uranium C.
Thorium source material D.
Any compound C.
6,000 kilograms of thorium D.
Uranium enriched to D.
Any compound as D.
(Notes 1 and 2) 5.0 wt. % in U-235 packaged waste in containers that meet the transportation requirements in 10 CFR 71.15 E.
Any compound as E.
5 grams a contaminant in special nuclear material Note 1: The total mass of U-235 possessed under Conditions 8A and 8E shall be limited to less than 0.5 effective kilogram of special nuclear material of low strategic significance. The requirements of 10 CFR 74.31 for nuclear material control and accounting are therefore not applicable.
Note 2: Special nuclear material packaged for transportation that meets the fissile exempt definition in10 CFR 71.15 (c) or (d) may be handled, stored, and transported for disposal without nuclear criticality safety controls, nuclear criticality monitoring systems, or mass-based limits and is exempt from special nuclear material security (physical protection) requirements of 10 CFR Part 73.
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 9.
Authorized Place of Use:
The licensees Cimarron Uranium Plant, located 1/2 mile North of Highway 33 and Highway 74 junction near Crescent, Oklahoma, with areas defined by the map in Figure 6-4, in Attachment 3 to EPMs July 3, 2024, comments on the draft Environmental Assessment (ML24185A228).
10.
For use in accordance with statements, representations, and conditions contained in letters dated,October 7, 2022, November 3, 2023, December 8, 2023, and April 25, 2025.
- 11. Deleted.
- 12. Deleted.
- 13. Deleted.
- 14. Deleted.
- 15. Deleted.
- 16. Deleted.
- 17. Deleted.
- 18. Deleted.
- 19. The licensee is exempt from the provisions of 10 CFR 70.24 insofar as this section applies to materials held under this license.
- 20. Deleted.
- 21. Deleted.
- 22. Deleted
- 23. Deleted 24.
Deleted.
25.
Deleted
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 26.
The licensee shall conduct a radiation protection program in accordance with the Radiation Protection Plan, Revision 5, with revisions made to address RAIs and /or revisions made in accordance with License Condition 27(e).
27.
Release Criteria a.
The licensee is authorized to remediate the Licensee facility in accordance with the letter dated April 19, 1995, and the Facility Decommissioning PlanRevision 3, October 17, 2022, with revisions made in accordance with responses to RAIs and/or revisions made in accordance with License Condition 27(e).
b.
The release criteria for groundwater at the Cimarron Site is 6.7 Bq/L (180 pCi/L) for total uranium and 3,790 pCi/L for Tc-99. NRC will not terminate Radioactive Material License SNM-928 until the following requirements are met:
i.
The concentration of uranium in the post-remediation monitor wells listed for uranium analysis in Table 8 Rev 1, of the letter dated December 8, 2023 (ML23346A262), remains below 180 pCi/L for eight consecutive calendar quarters.
ii.
The concentration of Tc-99 in the post-remediation monitor wells listed for Tc-99 analysis in Table 8 Rev 1, of the letter dated December 8, 2023 (ML23346A262), remains below 3,790 pCi/L for four consecutive calendar quarters.
c.
The Licensee shall use the unrestricted use criteria listed in the August 1987 Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of License for Byproduct, Source or Special Nuclear Materials for surfaces of buildings and equipment, and the October 23, 1981, BTP Disposal or Onsite Storage of Thorium or Uranium from Past Operations, for soils or soil-like materials.
Specific values are as follows:
Surfaces of buildings and equipment 5,000 dpm alpha/100 cm2 (15.5 in2), averaged over 1 m2 (10.8 ft2);
5,000 dpm beta-gamma/100 cm2 (15.5 in2), averaged over 1 m2 (10.8 ft2);
15,000 dpm alpha/100 cm2 (15.5 in2), maximum over 1 m2 (10.8 ft2);
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 15,000 dpm beta-gamma/100 cm2 (15.5 in2), maximum over 1 m2 (10.8 ft2);
1,000 dpm alpha/100 cm2 (15.5 in2), removable 1,000 dpm beta-gamma/100 cm2 (15.5 in2), removable Soils Natural uranium 0.37 Bq/g (10 pCi/g) total uranium Enriched uranium 1.1 Bq/g (30 pCi/g) total uranium Depleted uranium 1.3 Bq/g (35 pCi/g) total uranium Natural thorium 0.37 Bq/g (10 pCi/g) total thorium Exposure rates are as follows:
Surfaces of buildings and equipment 1.3 pCi/kg (5 µR/hr) above background at 1 m (3.3 ft)
Soils 2.6 pCi/kg (10 µR/hr) average above background at 1 m (3.3 ft) 5.2 pCi/kg (20 µR/hr) maximum above background at 1 m (3.3 ft)
The licensee shall conduct a final survey and sampling program to ensure that residual contamination meets the unrestricted use criteria in this license. Buildings, equipment, and outdoor areas shall be surveyed in accordance with NUREG/CR-5849, Manual for Conducting Radiological Surveys in Support of License Termination. Radioactivity levels shall not exceed the averaging criteria in NUREG/CR-5849. Soils and soil-like materials with elevated activities exceeding the unrestricted use criteria shall be investigated to determine compliance with the averaging criteria in NUREG/CR-5849. These criteria address averaging concentrations over any 100 m2 (1070 ft2) area and use the (100/A)2 elevated area method.
For areas surveyed prior to the issuance of NUREG/CR-5849, in the applicable final survey report, the licensee shall describe the survey methods used and provide the applicable references.
d.
Deleted.
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 5 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 e.
The licensee is authorized to make certain changes to the NRC-approved Decommissioning Plan (DP) and Radiation Protection Plan (RPP) without NRCs approval, if these changes are consistent with the ALARA principle and the decommissioning process. All changes shall be approved by the Cimarron ALARA Committee, subject to the following:
i.
The licensee may, without prior NRC approval, and subject to the specified in Parts 2 and 3 of this condition:
ii.
Make changes in the facility or process, as presented in the NRC-approved DP and RPP; iii.
Conduct tests or experiments not present in the NRC-approved DP applicable license conditions.
iv.
The licensee shall not be required to file an application for an amendment to the license when the following conditions are satisfied; a) The change, test, or experiment does not conflict with requirements specifically stated in the license (excluding those aspects addressed in Part 1 of this condition), or impair the licensee=s ability to meet all applicable NRC regulations; b) There is no degradation in safety or environmental commitments addressed in the NRC-approved DP or RPP, or have a significant adverse effect on the quality of the work, the remediation objectives, or health and safety; and c) The change, test, or experiment is consistent with the conclusions of actions analyzed in the Environmental Assessment, dated November 29, 2024 (ML24334A062) and Safety Evaluation Report dated December 20, 2024 (ML24264A155).
v.
If any of these conditions are not met for the change, test, or experiment under consideration, the licensee is required to submit a license amendment application for NRC review and approval. The licensees determinations as to whether the above conditions are met will be made by the facilitys ALARA committee. All such determinations shall be documented. The licensee shall provide in an annual report to NRC, a description of all changes, tests, and experiments made or conducted pursuant to this condition, including a summary of the safety and environmental evaluation of each
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 such action. As part of this annual report, the licensee shall include any DP or RPP pages revised pursuant to this condition. The records shall be retained until license termination. The retained records shall include written safety and environmental evaluations, made by the ALARA committee, that provide the basis for determining whether or not the conditions are met.
vi.
The ALARA Committee shall consist of a minimum of three individuals, one of whom shall be designated as the ALARA Committee chairman. Of these three designees, one shall have expertise in management and shall have managerial and financial responsibility for the decommissioning of the site; one shall have expertise in decommissioning and shall be responsible for site decommissioning, and one shall be the site Radiation Safety Officer or equivalent and shall ensure conformance to radiation safety and environmental requirements. The designee with managerial and financial responsibility shall be employed by the licensees Trustee. The designees for decommissioning of the site and the Radiation Safety Officer or equivalent, shall be retained by the Trustee. Except for the representative of management, ALARA Committee members may be consultants.
vii.
The Radiation Safety Officer shall be named in the licensees Radiation Protection Plan viii.
Radiation protection program procedures or revisions to these procedures do not require review and approval by the ALARA Committee but do require review and approval by the Radiation Safety Officer.
f.
During the remediation operations, liquid and airborne effluents shall be sampled and analyzed to ensure that releases meet the requirements of 10 CFR Part 20, Appendix B.
28.
Deleted 29.
Deleted 30.
Deleted 31.
Reporting a.
The licensee will submit a quarterly construction progress report during construction. It needs to include the following major activities:
i.
Mobilization and installation of stormwater controls.
ii.
Installation of groundwater extraction, treated water injection, and discharge components, including the trench and extraction well geologic and construction logs;
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 7 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 iii.
Construction of the Western Area Treatment Facility and Burial Area 1 Remediation Facility; iv.
Installation of groundwater treatment and resin processing systems and all ancillary equipment (e.g., influent and effluent tanks, injection skids, utilities and piping);
v.
A summary of permits obtained to date and an update on the status of the OPDES discharge permit; vi.
A summary of work completed to date as compared with the baseline construction schedule; vii.
Issues encountered and corresponding changes, if any; viii.
A summary of the results of radiological surveys performed; and ix.
Anticipated impacts to construction cost.
- b. Startup of Remediation and Groundwater Treatment The licensee will prepare and submit a System Startup Report to the NRC within 6 months following startup and commissioning activities. The system startup report will include the following:
i.
Static (prior to system startup) groundwater elevation data and potentiometric surface maps; ii.
Baseline (prior to system startup) in-process monitor well groundwater sampling results; iii.
Daily, weekly, and monthly groundwater elevation data, and potentiometric surface maps based on groundwater elevation data collected during the startup of remedial system operations (at the end of the first day, one week, two weeks, one month, and at the end of three months);
iv.
Treatment process water sampling results for the first three months of system operations; v.
Groundwater sampling results for the groundwater monitoring events conducted during the third month of system operations; vi.
A description of the operation of groundwater extraction systems, treatment systems, discharge and injection systems, facilities, etc.;
vii.
A summary of data collected from system operations components such as overall system run time, individual well and trench extraction/injection flow rates, influent
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 8 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 and effluent water concentrations, total volumes of groundwater treated in WA and BA1, resin usage and status, etc. for the first three months of system operations; and viii.
A summary of the results of radiological surveys.
c.
Remediation Progress Report The licensee will prepare and submit a Remediation Progress Report to the NRC 1 year following system startup and annually thereafter. Remediation Progress Reports will generally include the following:
i.
Summary of activities performed during the reporting period; ii.
Groundwater sampling activities, results, and analysis (including depictions of groundwater potentiometric surface maps (quarterly), groundwater uranium concentration maps (quarterly), groundwater concentration trend charts, etc.);
iii.
Remediation system operational summary (including system operational times; individual and cumulative groundwater recovery, treatment, and injection rates/volumes; water treatment media usage, inventory, and treatment efficiency; influent/effluent water concentration data and trends; etc.);
iv.
Treatment material control (resin usage, inventory, and deliveries, pre-treatment chemical usage, inventory, and deliveries, etc.);
v.
Waste material management and control (spent resin inventory, quantities/frequencies of waste shipments, waste uranium and Tc-99 concentration data, etc.); and vi.
Contingency measures implemented (as applicable).
vii.
The remediation schedule provided in the DP (Figure 9-3, ML22284A145) is estimated based on the groundwater flow projection and uranium partitioning coefficient and other input parameters. If it is determined that decommissioning cannot be completed as outlined in the DP, Rev.3 approved by Amendment 22, dated December 20, 2024), the licensee will provide an updated schedule to the NRC and the ODEQ.
NRC FORM 374 (3-2000)
U.S. NUCLEAR REGULATORY COMMISSION PAGE 9 OF 9 PAGES MATERIALS LICENSE License Number: SNM-928 Docket or Reference Number: 070-00925 MATERIALS LICENSE SUPPLEMENTARY SHEET Amendment No. 23 32.
Protection of Cultural Resources a.
If archaeological artifacts are discovered during ground-disturbing activities, EPM must cease all work within 15 m (50 ft) of the discovery and secure the location against further disturbance. EPM must notify the NRC, SHPO, and OAS of the discovery before the close of business the next working day after the discovery. If human remains, funerary objects, sacred objects, or objects of cultural patrimony are encountered, EPM must cease all activities within 15 m (50 ft) of the discovery and secure the location. EPM must notify the NRC, SHPO, and OAS within one working day.
b.
Upon completion of the groundwater remediation project, and except for the permanent WATF building and associated utilities and ancillary equipment, the site must be returned to pre-construction condition. For example, for any monitoring wells not required to remain in place by the Oklahoma DEQ, concrete pads must be removed, filled, and revegetated. This is to ensure that the project has no lasting visual effect on the NRHP-eligible properties.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Date: September 17, 2025 Bill Von Till, Branch Chief Uranium Recovery and Materials Decommissioning Branch Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards Signed by VonTill, Randolph on 09/17/25