DRC-2024-007485

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INSPECTION REPORT
Inspection Module: RADMOD-SSS: Surveys, Sources and Security

Inspection Location: Energy Fuels - White Mesa Uranium Mill, Blanding Utah.

Inspection Items: Radiological Release Surveys, Check Sources and Facility Security

Inspection Dates: October 28 through 30, 2024
Inspectors: Ryan Johnson, Utah Division Waste Management and Radiation Control
(DWMRC)

Personnel Contacted: Garrin Palmer, Radiation Safety Officer (RSO)

Governing Documents:
UAC R313-15
Radioactive Materials License (RML) UT1900479
Applicable Mill procedures and manuals

Opening Meeting
Energy Fuels Resources:
Garrin Palmer, RSO
Utah DWMRC:
Ryan Johnson (Health Physics Inspector)
Adam Wingate (Uranium Recovery Manager)
Heather Mickelson (Engineer Inspector)
During the opening meeting, the inspectors discussed the inspection items and documentation to be
reviewed during the inspection. The Mill staff reminded the inspectors of the safety requirements
for the Mill. The Mill is processing ore for uranium.

DRC Meters Used Model Serial Number Calibration Due Date
Dose Rate Bicron B789W 5/21/2025
Contamination Ludlum 3002 25017719 4/10/2025
Inspection Summary

The inspection consisted of reviewing documentation, interviewing the RSO and RSTs and a mill
tour. The following discussion provides more detail of the specific items reviewed.
Item 1. Mill Tour:The inspectors walked through the restricted area on a general site tour. The
tour included the ore pad, the mill, and solvent the extraction building. It had rained the night
before so everything was wet.
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Observations:The DWMRC inspector also observed:
Ore (natural ore and alternate feed) being stockpiled on the ore pad;
OSL badges were appropriately being used by all observed employees at the Mill; and
OSL badges are properly being stored.
Radiological readings observed during Mill Tour
Location Dose Rate (µrem/hr)
Chemours 6,000
Japan Ore 500
Solvent Extraction Building 40
Product Yard 25
Ore Pad 50-200
Silmet 300-5,000
Yellowcake packaging 100
Mill 200
Tank #5 8,000
Deficiencies: None
Item 2. Radiological Surveys
Observations:
The inspector reviewed completed release survey forms and observed:
The Intermodal Container Unrestricted surveys documented:
o The Mill uses the release criterial for NRC Regulatory Guide 8.30 Table 2;
o Used the Mill’s release limits 0.2 mR/hr @1 cm
o The survey forms were complete and legible;
o Appropriate units were used;
o Meter information such as efficiency, calibration, background was recorded on
each form; and
o The survey included 30 locations inside and outside the container.

The Daily Vehicle Scan for Vehicles Leaving the Restricted Area surveys documented;
o The Mill uses the release criterial for 49 CFR 173.443 for exterior of truck;
o
readings;
o The survey forms were complete and legible;
o Appropriate units were used; and
o Meter information such as efficiency, calibration, background was recorded on
each form.

The Equipment Unrestricted surveys documented:
o The Mill uses the release criterial for NRC Regulatory Guide 8.30 Table 2;
o Used the Mill’s release limits 0.2 mR/hr @1 cm
readings;
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o The survey forms were complete and legible;
o Appropriate units were used; and
o Meter information such as efficiency, calibration, background was recorded on
each form.

The Ore truck restricted surveys documented:
o The Mill uses the release criterial for 49 CFR 173.443 for exterior of truck;
o Used the Mill’s release limits 0.2 mR/hr @1 cm
readings;
o The survey forms were complete and legible;
o Appropriate units were used; and
o Meter information such as efficiency, calibration, background was recorded on
each form.

Restricted Release Surveys documented:
o The survey forms were complete and legible;
o Appropriate units were used;
o Meter information such as efficiency, calibration, background was recorded on
each form.

The inspector observed one of the RSTs perform a radiological survey on an outgoing ore truck.
The inspector observed the following:
The RST scanned the floor and walls of the trailer with a alpha scintillator and side window
GM probe; and
The RST also collected wipe samples with a disc smear and counted them on a Ludlum
3030.

The inspector performed an independent radiological surveys on the truck that the RST surveyed.
The inspector used a microrem meter to perform a dose rate measurement.
The inspector also collected large are swipes;
Dose rate reading were below the Mill’s release limits; and
Contamination were below background.

Meter Location Model Meter Serial
#
Cal. Due
West Gate Ludlum 3 235288 12/14/2024
West Gate Ludlum3 12658 7/29/2025
East Gate Ludlum 3 158587 8/5/2025
East Gate Ludlum 3 12859 12/14/2024
Rad Tech Office Ludlum 2929 216270 9/10/2025
Rad Tech Office Ludlum 3030 363474 8/23/2024
At each gate one meter was set up with a scintillation probe for measuring alpha radiation and one
was set up with a GM hotdog probe for measuring beta/gamma radiation.
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Deficiencies: None
Item 3. Calibration Sources
Observations: The DWMRC inspector observed:
The check sources are exempt sources;
The check sources are kept in a locked safe in the rad tech office;
Checked sources are checked out and checked in using a checkout form; and
The inventory list of the check sources is kept up-to-date as an attachment to the Mill’s
Radiation Safety plan.

Deficiencies: None

Item 4. Site Security (10CFR37.11(c))

Observations: The DWMRC inspector observed:
A short-circuit camera system that record activities at each of the gates, the product yard
and other locations scattered throughout the Mill;
Gates were closed and locked except when being used; and
Exterior doors are lock and require a badge to open them.

Deficiencies: None

Item 5.Department of Energy (DOE) Visit

On October 29, 2024, DOE personnel visited the Mill. During their visit they:
Went to the cover test pad on tailing impoundment 2;
Saw tailing impoundments 1, 2, 3, 4A and 4B;
Went to the control areas north of the Mill ; and
Discussed with Division Staff and Mill personnel tailing impoundment cover design.
Item 6.Breathing Zone Sampling (Left over from previous inspection)
The DWMRC inspector reviewed the following documents:
Calibration sheets for general area and breathing zone sample pumps; and
Breathing zone sampling worksheets.
While reviewing the paperwork for breathing zone sampling, the inspector noticed that the derived
air concentration (DAC) values being recorded were about the same as previous years. The DAC
values observed in 2023 ranged between 0 and 1,775% DAC. These DAC values are higher than
last year but lower than years when the Mill is processing ore. The Mill did not process a lot of ore
(natural and alternate feed) in 2023.

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Closeout Meeting
Energy Fuels:
Terry Slade. RST
Tanner Holiday, Environmental Technician

Utah DWMRC:
Ryan Johnson, Health Physics Inspector
Adam Wingate, Uranium Recovery Manager
Heather Mickelson, Engineering Inspector

Findings:
None
Recommendations
None
Prepared By: Ryan Johnson 11/12/2024
(Print Name) (Signature) (Date)
Reviewed By: Heather Mickelson 11/12/2024
(Print Name) (Signature) (Date)
Reviewed By: Adam Wingate 11/12/2024
(Print Name) (Signature) (Date)