ML23174A165

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Cert Decommissioning Plan Overview Presentation
ML23174A165
Person / Time
Site: 07000925
Issue date: 06/14/2023
From:
Environmental Properties Management
To:
NRC Region 4, Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
Download: ML23174A165 (1)


Text

Cimarron Environmental Response Trust Decommissioning Plan - Rev 3 Overview PRESENTED TO:

U.S. NUCLEAR REGULATORY COMMISSION U.S. NUCLEAR REGULATORY COMMISSION - REGION IV OKLAHOMA DEPARTMENT OF ENVIRONMENTAL QUALITY JUNE 14, 2023

Section 1 - Facility History License history Previous decommissioning activities Equipment & Buildings Impoundments Soil Spills & releases 10 CFR 302 buried waste

Section 2 - Facility Description Location Subareas Surface water

Section 2 - Facility Description

Section 2 - Upland Area Geology

Section 2 - Burial Area #1 Geology

Section 3 - Radiological Status Uranium in groundwater

Section 3 - Radiological Status Uranium enrichment in groundwater

(% U-235 by weight)

Section 3 - Radiological Status Currently licensed area

Section 4 - Decommissioning Criteria Facilities & equipment 1,000/5,000/15,000 dpm/100 cm2 or 5 µR/hr above background at 1 meter Soil - 30 pCi/g uranium above background (Volumetric averaging applies to Subarea O)

Groundwater 180 pCi/L total uranium 3,790 pCi/L Tc-99

Section 5 - Environmental Information Proposed action Alternatives Affected environment Environmental impacts

Section 6 - Revisions to the License Possession limits for uranium in packaged resin and Tc-99 Redefinition of the licensed area Delete requirements for final survey & onsite disposal Radiation Protection Plan Tie-downs related to completed decommissioning activities

Section 7 - ALARA Analysis Introduction to SDMP vs. LTR ALARA analysis based on 10 CFR 20.1402 (LTR)

Cost benefit analysis based on $2,000 per man-rem avoided by decommissioning further Cost to achieve DCGL is > $200,000 per man-rem avoided Decommissioning to 180 pCi/L is ALARA

Section 8 - Planned Decommissioning Activities Groundwater extraction Groundwater treatment Treated water injection & discharge In-process monitoring Waste management & disposal Post-remediation monitoring License termination activities

Section 8.2 - Groundwater Extraction

Section 8.3 -

Western Area Treatment Facility (WATF)

Section 8.3 -

Burial Area #1 Remediation Facility (BARF)

Section 8.3 - Ion Exchange Treatment Train

Section 8.4 - Treated Water Injection

Section 8.5 -

Treated Water Discharge OPDES Permitted Outfall

Section 8.6 - In-Process Monitoring Treatment System

Section 8.6 - In-Process Monitoring Groundwater

Section 8.7 - Waste Management & Disposal Scrolling Centrifuge Ribbon Blender Disposal Drum Fresh Resin Tank Ion Exchange Vessel Absorbent Hopper

Section 8.8 - Post-Remediation Monitoring

Section 8.9 - License Termination Demobilize processing equipment Treatment and resin processing systems Tanks, piping, instrumentation, utilities Wells & vaults Conduct final status survey WATF building (furnishings?)

Concrete slabs Emergency generators Apply for license termination

Section 9 - Schedules Pre-Construction D-Plan - To February 2025 NRC - To end of 2024 Construction - 9 months - To November 2025 Remediation - 12 1/2 years - To Q2 2038 License Termination - To end of 2040

Section 9 - Remediation Schedule

Section 10 - Project Mgt. & Organization

Section 11 - Radiation Protection D-Plan Section 11 summarizes:

D-Plan Appendix M - Radiation Protection Plan RPP Appendix A - Potential Intake Calculation RPP Appendix B - Dose Rate Near Uranium Treatment Train D-Plan Appendix H - Exemption from U-235 Limit D-Plan Appendix N - Criticality and Uranium Loading Calculations

Section 12 - Environmental Monitoring &

Control Per NUREG - 1757 Environmental ALARA evaluation Effluent monitoring Effluent control Stormwater control Also addressed in previous sections

Section 13 - Radioactive Waste Management Solid Radioactive Waste Spent Resin Potentially Contaminated Material Volumetrically Contaminated Material Storage of Solid Radioactive Waste Liquid Radioactive Waste - None Anticipated Mixed Waste - None Anticipated

Section 14 - Quality Assurance D-Plan Appendix O - Quality Assurance Program Plan Complies with:

NUREG-1757 Reg Guide 4.15 License SNM-928, Condition 27.e

Section 15 - Radiation Surveys Release survey criteria Characterization - complete In-process surveys Groundwater Influent & effluent Shipping Routines In-process accumulation of U and U-235 in RPP

Section 16 - Cost Estimate (w/ Fees)

Section 16 - Cost Estimate (w/o Fees)

Summary Well characterized site, mostly releasable Simple remediation process, but a complex hydrogeological environment Little potential for dose to workers or public Numerous amendments to the license needed Unique regulatory scenario (SDMP vs. LTR) poses regulatory challenges Expediency is critical

QUESTIONS?