DRC-2009-008041 - 0901a06880140a1d

PROPOSED DEVELOPMENT OF NEW TAILINGS CELL
4B FOR THE WHITE MESA URANIUM MILL
Prepared for:
Denison Mines (USA)Corp.(DUSA)
Prepared by:
SENES Consultants Limited
121 Granton Drive,Unit 12
Richmond Hill,Ontario
L4B3N4
April 2008
Printed on Recycled Paper Containing Post~Consumer Fibre
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
EXECUTIVE SUMMARY
Denison Mines (USA)Corp.(DUSA)operates the White Mesa Uranium Mill (hereafter refelTed
to as the "mill")in San Juan County,Utah,approximately 6 miles (9.6 km)south of the city of
Blanding.The mill is located on a parcel of land and mill site claims covering approximately
5,415 acres (2,191 hal.The mill is licensed by the State of Utah Division of Radiation Control
(DRC)to process uranium ore and selected alternate feed materials.
In February 2007,SENES prepared a dose assessment for DUSA in support of the license
renewal application for the mill (SENES 2007,also referred to as the previous report).
MILDOS-AREA was used to estimate the dose commitments that could potentially be received
by individuals and the general population within a 50 mile (80 km)radius for processing of
conventional ores.The assessment was prepared for scenarios in which Colorado Plateau
(0.25%U30 S and 1.5%V20S)or Arizona Strip (0.637%U30s and no V20S)ores are processed at
the mill.
This dose assessment extends the analyses ofthe previous report of February 2007 to incorporate
the dose from the proposed development of new tailings Cell 4B,anticipated to be completed for
use in 2009,in support of a license amendment application by DUSA for construction and
operation of that cell.In doing the dose assessment for Cell 4B,we have updated the
assumptions we used in February 2007 for modeling tailings Cells 1,2,3 and 4A to reflect the
cun'ent operational status ofthe site,including the re-commissioning of Cell 4A for use in 2008.
For purposes of modeling mill operations,we have separated operations into two phases.Phase
1 involves the continued use of Cell 1 for solution evaporation,the continued use of Cell 3 for
solution evaporation and the disposal of tailings solids,and the use of Cell 4A for disposal of
tailings solids and solution evaporation.Phase 2 occurs after Cell 3 is full and is no longer an
active cell.During Phase 2,Cells 4A and 4B are used for disposal of tailings solids and solution
evaporation,and Cell 1 is used for solution evaporation.In each Phase,Cell 2,with interim soil
cover over the entire cell area,is included in the model,and in Phase 2,Cell 3,with interim soil
cover over the entire cell area,is included in the model.
The United States Nuclear Regulatory Commission (NRC)-approved MILDOS-AREA was used
to estimate the dose commitments received by individuals and the general population within a 50
mile (80 km)radius of the site for the processing of either Colorado Plateau or Arizona Strip ore
separately.In each scenario,the doses arising from emissions of dust and radon from the mill
area (excluding the tailings cells)and ore pads were assumed to be the same as the previous 2007
report since the scenarios both involve the processing of Colorado Plateau and Arizona Strip
ores.Therefore,MILDOS-AREA runs fi'om the previous report were revised to exclude the
tailings cells.The doses from the tailings cells were estimated in separate MILDOS-AREA runs
34489-10··FINAL-April200S ES-l SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
and added to the dose from the mill area and ore pads.Table ES-I provides a summary of the
source terms included in Phases I and 2 ofthe development ofnew tailings cells.
TABLE ES-l
SOURCE TERMS INCLUDED IN PHASES 1 AND 2
Source Term Phase 1 Phase 2
Mill area included included
Ore Pads included included
Tailings Cell 2 with Interim Soil Cover included included
Tailings Cell 3 active interim soil cover
Tailings Cell 4A active active
Tailings Cell4B excluded active
The wind erosion and radon release rates from the tailings cells (active and with interim soil
cover)were modelled by using a maximal worst case approach.
Each active tailings cell was modelled to have an active exposed (non-solution)tailings solids
area of 10 acres (i.e.,the maximum uncovered tailings solids area at any time allowed under
NESHAPs Regulation 40 CFR 61.252(b),Subpart W)since it is not possible to predict the
distribution of uncovered tailings between the active cells at any given time.As a result,the
release rate of wind-eroded tailings dust was estimated at 10 acres at all times for each active
cell.We understand that during the active life of each cell,the average exposed tailings solids
will be less than 10 acres,so this assumption is considered to be conservative.The total annual
radon release rate was estimated by assuming a radon release rate of20 pCi/m2s (i.e.,maximum
radon-222 emissions to ambient air from an existing uranium mill pile)over the entire area of
each cell consistent with NESHAPs.Actual radon emission rates from the tailings cells have
historically been well below 20 pCi/m2s,so this assumption is also considered to be
conservative.
Emissions fi'om the tailings cells (2 and 3)with interim soil cover were assumed to occur over
the entire area of each cell;however,only radon is released at a rate of 10 pCi/m2s after the
application of the soil cover.
The calculated total annual effective dose commitments (including radon)calculated using
MILDOS-AREA were compared to the Utah Administrative Code R313-15-30I(1)(a)
requirement that the dose to individual members of the public shall not exceed 100 mrcm/yr
(radon included).For the processing of Colorado Plateau ore,the maximum total annual
effective dose commitments was calculated to be a maximum of 1.4 mrem/yr for an infant at the
nearest potential resident,BHY-l (Tables 6.1-1 and 6.1-3)(i.e.,effective dose)and is about
1.4%ofthe R313-l5-30l(1)(a)limit of 100 mrem/yr (radon included)to an individual member
34489-10-FINAL -April 2008 ES-2 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
of the public,for Phases I and 2.For the processing of Arizona Strip ore,the total annual
effective dose commitments were calculated to be a maximum of 3.1 mrem/yr for an infant at the
nearest potential resident,BHV-I (Tables 6.2-1 and 6.2-3)(i.e.,effective dose)and is about
3.1 %of the 100 mrem/yr limit (radon included)to an individual member of the public,for
Phases I and 2.Overall,using conservative assumptions,the predicted annual effective dose
commitments for Phases I and 2 comply with R313-15.
In addition,our MILDOS-AREA calculated 40 CFR 190 annual dose commitments (excluding
radon)were compared to the 40 CFR 190 criterion,which is 25 mrem/yr to the whole body
(excluding the dose due to radon)and 25 mrem/yr to any other organ to any member of the
public (EPA 2002).The 40 CFR 190 doses were also used to demonstrate compliance with the
ALARA (As Low As Reasonably Achievable)goal set out in R313-15-101(4)(10 CFR
20.1101(d»(i.e.,the ALARA goal is to demonstrate that total effective dose equivalent to the
individual member of the public likely to receive the highest total effective dose equivalent will
not exceed 10 mrem/yr (absent of the radon dose».For the processing of Colorado Plateau ore,
the 40 CFR 190 annual dose commitments were calculated to be a maximum of 4.8 mrem/yr for
a teenager at the nearest potential resident,BHV-I (Tables 6.1-5 and 6.1-8)(i.e.,dose to the
bone)and is about 19%of the 40 CFR 190 dose criterion of 25 mrem/yr,for Phases I and 2.
Further,the 40 CFR 190 annual effective dose commitments demonstrate compliance with the
R313-15-101(4)(10 CFR 20.IIOI(d»ALARA goal of 10 mremlyr to the individual member of
the public likely to receive the highest total effective dose equivalent (the maximum total
effective dose equivalent (radon excluded)during Phases I and 2 was 0.545 mrem/yr for an
infant at BHV-I.).For Arizona Strip ore,the 40 CFR 190 annual dose commitments were at
most 12 mrem/yr for a teenager at the nearest potential resident,BHV-I (Tables 6.2-5 and 6.2-8)
(i.e.,dose to the bone)and is about 49%of the 40 CFR 190 dose criterion of 25 mrem/yr for
Phases I and 2.Further,the 40 CFR 190 annual effective dose commitments demonstrate
compliance with the R313-15-101(4)(10 CFR 20.IIOI(d»ALARA goal of 10mrem/yr to the
individual member of the public likely to receive the highest total effective dose equivalent (the
maximum total effective dose equivalent (radon excluded)during Phases I and 2 was
1.39 mrem/yr for an infant at BHV-I).Overall,using conservative assumptions,ore processing
in Phases I and 2 comply with the requirements of40 CFR 190 and the ALARA goal set out in
R313 -15-101(4).
34489-10 -FINAL -Apl'il2008 ES-3 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE OF CONTENTS
Page No.
EXECUTIVE SUMMARY ES-I
ACRONYMS &ABBREViATIONS AC-I
1.0 INTRODUCTION I-I
1.1 Background ,I-I
1.2 Objective 1-2
1.3 Approach 1-2
1.4 Contents OfThis Report 1-3
2.0 REGULATORY COMPLIANCE 2-I
3.0 RADIATION DOSE ASSESSMENT 3-1
3.1 General Information About MILDOS-AREA 3-1
3.2 The Use ofMILDOS-AREA In This Assessment..3-1
4.0 SOURCE TERMS 4-1
4.1 Point Sources 4-3
4.I.I Grinder 4-3
4.1.2 Grizzly 4-3
4.1.3 Yellowcake Stacks 4-4
4.1.4 Vanadium Stack 4-4
4.2 Area Sources 4-5
4.2.1 Ore Pads 4-5
4.2.2 Tailings Cells 4-6
4.3 Meteorological Data 4-8
4.4 Population Data 4-8
4.5 Uranium Mill Source Emission Rates 4-9
4.5.1 Colorado Plateau Ore 4-9
4.5.2 Arizona Strip Ore 4-9
5.0 RECEPTORS 5-1
6.0 RADIATION DOSE ESTIMATES 6-I
6.1 MILDOS-AREA Results For Colorado Plateau Ore 6-2
6.1.1 R313-15-30I(l)(a)Regulatory Compliance 6-2
6.1.2 40 CFR 190 Regulatory Compliance 6-9
6.2 MILDOS-AREA Results for Arizona Strip Ore 6-19
6.2.1 R313-15-301 (l)(a)Regulatory Compliance 6-19
6.2.2 40 CFR 190 Regulatory Compliance 6-26
7.0 KEY OBSERVATIONS 7-1
8.0 REFERENCES 8-1
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LIST OF APPENDICES
Page No.
APPENDIX A HISTORY OF MILDOS A-I
APPENDIX 8 EMISSION CALCULAnONS 8-1
8.1 Calculation ofAnnual Dust Loss 8-1
8.2 Emission Calculations 8-2
APPENDIX C MILDOS-AREA RESULTS C-I
C.I MILDOS-AREA Results for Colorado Plateau Ore C-I
C.I.!R313-15-301 (l)(a)RegulatoryCompliance C-1
C.2 MILDOS-AREA Results for Arizona Strip Ore C-7
C.2.1 R313-15-301 (l)(a)Regulatory Compliance C-7
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LIST OF TABLES
Page No.
ES-l Source Terms Included in Phases 1 and 2 ES-2
1.3-1 Source Terms Included in Phases 1 and 2 1-3
4.2-1 Characteristics ofTailings Cells in Phase 1 4-6
4.2-2 Characteristics ofTailings Cells in Phase 2 4-6
4.5-1 Radioactive Patticulate and Radon Emission Rates (Colorado Plateau Ore)4-9
4.5-2 Radioactive Particulate and Radon Emission Rates (Arizona Strip Ore)4-10
6.1-1 Phase I-Comparison ofAnnual Dose Commitments with Applicable Radiation
Protection Standards (Colorado Plateau Ore)6-3
6.1-2 Phase I-Total Annual Dose Commitments for Meat Ingestion Pathway
(Colorado Plateau Ore)(mrem/yr)6-6
6.1-3 Phase 2-Comparison ofAnnual Dose Commitments with Applicable Radiation
Protection Standards (Colorado Plateau Ore)6-6
6.1-4 Phase 2-Total Annual Dose Commitments for Meat Ingestion Pathway
(Colorado Plateau Ore)(mrem/yr)6-9
6.1-5 Phase I-Comparison of40 CFR190 Annual Dose Commitments with Applicable
Radiation Protection Standards (Colorado Plateau Ore)6-10
6.1-6 Phase 1-40 CFR190 Annual Dose Commitments for Meat Ingestion
Pathway (Colorado Plateau Ore)(mrem/yr)6-13
6.1-7 Phase 2-Annual Population Dose Commitments within 50 miles (80 km)of the
Mill for Colorado Plateau Ore 6-13
6.1-8 Phase 2-Comparison of40 CFR190 Annual Dose Commitments with Applicable
Radiation Protection Standards (Colorado Plateau Ore)6-15
6.1-9 Phase 2-40 CFR190 Annual Dose Commitments for Meat Ingestion
Pathway (Colorado Plateau Ore)(mrem/yr)6-18
6.1-10 Phase 2-Annual Population Dose Commitments within 50 miles (80 km)ofthe
Mill for Colorado Plateau Ore 6-18
6.2-1 Phase I-Comparison ofAnnual Dose Commitments with Applicable Radiation
Protection Standards (Arizona Strip Ore)6-20
6.2-2 Phase I-Total Annual Dose Commitments for Meat Ingestion Pathway
(Arizona Strip Ore)(mrem/yr)6-23
6.2-3 Phase 2-Comparison ofAnnual Dose Commitments with Applicable Radiation
Protection Standards (Arizona Strip Ore)6-23
6.2-4 Phase 2-Total Annual Dosc Commitments for Meat Ingestion Pathway
(Arizona Strip Ore)(mrem/yr)6-26
6.2-5 Phase I-Comparison of40 CFR190 Annual Dose Commitments with Applicable
Radiation Protection Standards (Arizona Strip Ore)6-27
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LIST OF TABLES
Page No.
6.2-6 Phase 1-40 CFR 190 Annual Dose Commitments for Meat Ingestion
Pathway (Arizona Strip are)(mrem/yr)6-30
6.2-7 Phase I-Annual Population Dose Commitments within 50 miles (80 km)ofthe
Mill for Arizona Strip are 6-30
6.2-8 Phase 2-Comparison of40 CFR190 Annual Dose Commitments with Applicable
Radiation Protection Standards (Arizona Strip are)6-3 I
6.2-9 Phase 2-40 CFR190 Annual Dose Commitments for Meat Ingestion
Pathway (Arizona Strip are)(mrem/yr)6-34
6.2-10 Phase 2-Annual Population Dose Commitments within 50 miles (80 km)ofthe
Mill for Arizona Strip are 6-34
7-1 Source Teillis Included in Phases I and 2 7-1
B.I Parameter Values for Calculation ofAnnual Dusting Rate for Exposed Tailings 8-I
C.I-I Annual Dose Commitments (Colorado Plateau Ore)C-I
C.I-2 40 CFR 190 Annual Dose Commitments (Colorado Plateau are)C-4
C.2-1 Annual Dose Commitments (Arizona Strip Ore)C-7
C.2-2 40 CFR 190 Annual Dose Commitments (Arizona Strip Ore)C-IO
LIST OF FIGURES
Page No.
4.I Source Locations 4-2
5.1 Receptor Locations 5-2
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Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
ACRONYMS &ABBREVIATIONS
ALC
ANL
ALARA
Avg.
ASCII
Bi-210
Bi-2l4
CCD
CFR
Ci
DCF
DRC
DUSA
EPA
Ew
F
FES
Fs
ft
ft3
g
gore
GPS
GUI
ha
hI'
lCRP
ID
lbs
km
kts
NESHAPs
NRC
NUREG
m
m2
mrem
MPC
Allowable Concentration
Argonne National Laboratory
As Low As Reasonably Achievable
average
American Standard Code for Information Interchange
bismuth-210
bismuth-2l4
Counter Current Decantation
Code ofFederal Regulations
cune
Dose Conversion Factor
State ofUtah Division of Radiation Control
Denison Mines (USA)Corp.
United States Environmental Protection Agency
Process Emission Factor
Radon Release Rate
Final Environmental Statement
annual fi'equency ofoccurrence ofwind group S
feet
cubic feet
grams
grams ofore
Global Positioning System
Graphical User Interface
hectares
hours
International Commission on Radiological Protection
Induced Draft
pounds
kilometers
knots
National Emission Standards for Hazardous Air Pollutants
United States Nuclear Regulatory Commission
Regulatory Guide
meters
square meters
millirem
Maximum Pelmissible Concentration
34489·10···FINAL·April 2008 AC-l SENES Consultants Limited
___-"-P_r0-!C'Posed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
Pb-21 0
Pb-214
pCi
Po-210
Po-218
Ra-226
Rn-222
Rs
s
S
SENES
TGLM
Th-230
tpy
U30g
Unat
U-234
U-235
U-238
V20S
yd3
yr
lead-210
lead-214
picocurie
polonium-210
polonium-218
radium-226
radon-222
Resuspension rate for wind group S
seconds
Radionuclide Emission Rate
Specialists in Energy,Nuclear and Environmental Sciences
Task Group on Lung Dynamics Lung Model
thorium-230
tons per year
triuranium octoxide ("Yellowcake")
natural uraniurn
uranium-234
uranium-235
uranium-238
vanadium pentoxide
cubic yards
year
34489-10·FINAL·April 2008 AC-2 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
1.0 INTRODUCTION
1.1 BACKGROUND
Denison Mines (USA)Corp.(DUSA)operates the White Mesa Uranium Mill (hereafter referred
to as the "mill")in San Juan County,Utah,approximately 6 miles (9.6 km)south of the city of
Blanding.The mill is located on a parcel of land and mill site claims covering approximately
5,415 acres (2,191 ha).The mill was built in 1979 and licensed by the United States Nuclear
Regulatory Commission (NRC)to process uranium ore and selected alternate feed materials.
The mill began operations in July 1980.In August 2004,the State of Utah became an
Agreement State for the regulation of uranium mills,and primary regulatory authOlity over the
mill was assumed by the State ofUtah Division of Radiation Control (DRC)at that time.
The mill is a standard design with both uranium and vanadium circuits and uses the acid leach-
solvent extraction process for uranium recovery from uranium ores and uranium/vanadium ores.
Vanadium in uranium/vanadium-bearing ores is partially solubilized during leaching,and the
dissolved vanadium present in uranium raffinate is fuliher processed for recovery of vanadium
before recycling (NRC1979).
In the early 1990s,the mill began receiving "alternate feed material"(uranium-bearing materials
other than conventionally mined ores)for processing.From 1999 to present,the mill has relied
solely on alternate feed materials.The mill goes on standby for periods of time and then it
processes the stockpiled alternate feeds for the recovery of uranium.The residual tailings from
these processes are stored in the tailings cells on-site.DUSA has commenced mining activities
in the Colorado Plateau district and conventional ores are being hauled and stockpiled at the mill.
In addition,DUSA has mining assets in the Arizona Strip,and mining of those ores is expected
to commence in 2008.Milling of conventional ore is scheduled for Spring 2008,when the
milling ofcUlTently available alternate feed material is completed (DUSA 2007a).
In Febmary 2007,SENES prepared a dose assessment for DUSA in support of the license
renewal application for the mill (SENES 2007,also referred to as the previous repoli).
MILDOS-AREA was used to estimate the dose commitments that could potentially be received
by individuals and the general population within a 50 mile (80 km)radius for the processing of
Colorado Plateau or Arizona Strip ores separately.(MILDOS-AREA is an NRC approved code
designed as a tool to provide input on regulatory and compliance evaluations for various uranium
recovery operations.)The following assumptions were used in the previous report:
•Colorado Plateau ore contains an average of 0.25%U30 8 and 1.5%V20 S (NRC 1980).
The vanadium content in the ore is fuliher processed for recovery before recycling.
•Arizona Strip ore contains 0.637%U30 8 and no vanadium (Landau 2007).
34489·10-FINAL -Apri12008 I-I SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
•The activity concentrations of U-238 in Colorado Plateau and AJizona Strip ore were
700 and 1783 pCi U-238/g ore,respectively.
•The proposed ore process rate was assumed to be 730,000 tons per year (tpy)(an average
of2,000 tons per day).Therefore,assuming that the average uranium recovery would be
at the historical recovery yield of94%,approximately 1,715 tons (3,431,000 Ibs)ofU308
per year would be recovered fi·om Colorado Plateau ore at the proposed ore process rate.
Similarly,approximately 4,371 tons (8,742,000 Ibs)ofU30 8 per year would be recovered
fi·om Arizona Strip ore at the proposed ore process rate.
1.2 OBJECTIVE
The objective of this report is to extend the analyses ofthe previous report of February 2007 to
incorporate the dose from the proposed development of new tailings Cel!4B,anticipated to be
completed for use in 2009,in support of a license amendment application by DUSA for
construction and operation of that cell.In doing the dose assessment for Cel!4B,we have
updated the assumptions we used in February 2007 for modeling tailings Cells 1,2,3 and 4A to
reflect the CutTent operational status of the site,including the re-commissioning of Cel!4A for
use in 2008.Otherwise,we have made as few changes to the 2007 calculations as possible.
MILDOS-AREA was used to estimate the dose commitments that could potential!y be received
by individuals and the general population within a 50 mile (80 km)radius of the site for the
processing of Colorado Plateau or Arizona Strip ores using the assumptions provided in
Section 1.1.
1.3 ApPROACH
The approach used for this assessment was to extend the previous report to incorporate the dose
fi·om the proposed development of Cell 4B,with as few changes to the calculations as possible.
For purposes of modeling mill operations,we have separated operations into two phases.
Phase 1 involves the continued use of Cell 1 for solution evaporation,the continued use ofCel!3
for solution evaporation and the disposal of tailings solids and the use of Cell 4A for disposal of
tailings solids and solution evaporation.Phase 2 occurs after Cell 3 is full and is no longer an
active cell.Phase 2 involves the use of Cell 1 for solution evaporation and Cells 4A and 4B for
disposal of tailings solids and solution evaporation.In each Phase,Cell 2,with interim soil
cover over the entire cell area,is included in the model,and in Phase 2,Cell 3,with interim soil
cover over the entire cell area,is included in the model.
Since there are two types of ore,MILDOS-AREA runs were created to assess the dose from
processing of the Colorado Plateau and Arizona Strip ores separately (hereafter refelTed to as
Scenario 1 and 2,respectively).Each scenari%re was analyzed with the following separate
MILDOS-AREA runs:
34489-10 -FINAL -April 2008 1-2 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
•Tailing Cell 2 with Interim Soil Cover;
•Tailings Cell 3 with Interim Soil Cover;
•Tailings Cell 3;
•Tailings Cell 4A;
•Tailings Cell 4B;and
•All source terms (at the mill including the ore pads)except for tailings cells (hereafter
referred to as the mill area).
The dose from each tailings cell was calculated in separate MILDOS-AREA runs to allow for the
flexibility of calculating the incremental doses from the different combination oftailings cells to
the mill area and ore pads for the two anticipated development Phases.Table 1.3-1 provides a
summary ofthe source terms included in Phases I and 2 ofthe development ofnew tailings cells.
TABLE 1.3-1
SOURCE TERMS INCLUDED IN PHASES 1 AND 2
Source Term Phase I Phase 2
Mill area included included
Ore Pads included included
Tailings Cell 2 with Interim Soil Cover included included
Tailings Cell 3 active interim soil cover
Tailings Cell4A active active
Tailings Cell4B excluded active
1.4 CONTENTS OF THIS REPORT
The remainder of this report is alTanged into seven sections.
Section 2.0,Regulatory Compliance,provides a description of the regulatory framework
peliaining to the applicable dose limits to members of the public from licensed activities at the
mill.
Section 3.0,Radiation Dose Assessment,describes the method used to estimate the radiation
doses to members ofthe public and how MILDOS-AREA was used.
Section 4.0,Source Terms,describes the source telms and source emission rates related to the
ore processing operations and other input parameters required (i.e.,meteorological data and
population data)for the MILDOS-AREA runs.The source emission rates were calculated for
processing Colorado Plateau and Arizona Strip ores based on the ore grade,ore process rate and
uranium recovery yield described in Section 1.1.
34489-10-FINAL -April 2008 1-3 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
Section 5.0,Receptors,describes the receptors used in the MILDOS-AREA mns.
Section 6.0,Radiation Dose Estimates,provides the dose results from the MILDOS-AREA
runs using the parameters described in Sections 4.0 and 5.0.
Section 7.0,Overviews,provides a summary of the dose estimates for the two Phases in each
scenano.
Section 8.0,References,provides a list of reference material used to prepare this report.
Appendix A:History of MILDOS-AREA,describes how the MILDOS-AREA software has
evolved,highlighting some ofthe key differences between the updated version,MILDOS-AREA
(ANL 1998a),and the original version ofMILDOS.
Appendix B:Emissions Calculations,describes the basis of the emission estimates for each
source.
Appendix C:MILDOS-AREA Results,provides the dose estimates for MILDOS-AREA runs
for the mill area (induding the ore pads)and each tailings cell.
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Proposed Development ofNew Tailings Ce1l4Bfor White Mesa Uranium Mill
2.0 REGULATORY COMPLIANCE
DRC has the regulatory authority over the license issued for the site.As required by Utah
Administrative Code R313-15-101(2),the mill shall,to the extent practical,employ procedures
and engineering controls based upon sound radiation protection principles to achieve
occupational doses and doses to members ofthe public that are as low as reasonably achievable
(ALARA).Under R313-15-30I(l)(a),the licensee is required to demonstrate that the total dose
equivalent to individual members of the public from the licensed operation does not exceed
0.1 rem (100 mrem)in a year (including radon),exclusive ofthe dose contribution fj'01TI natural
background and medical sources.Under 10 CFR 20.1301 (NRC 1991),NRC has adopted the
provisions ofthe United States Environmental Protection Agency (EPA)environmental radiation
standards in 40 CFR 190 (EPA 2002).This subpart requires that the licensee provide reasonable
assurance that the radiation attributed to mill operations does not exceed the annual dose of
25 mrem/yr to the whole body,75 mrem/yr to the thyroid and 25 mrem/yr to any other organ of
any member of the public (radon and it daughters excepted).In addition,10 CFR 20.1301 (d)
(R313-15-IOI(4))sets an ALARA goal on air emissions of radioactive material to the
environment,excluding radon-222 and its daughters such that the individual member of the
public likely to receive the highest total effective dose equivalent will not exceed 10 mrem/yr.
34489-10-FINAL-April 2008 2-1 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
3.0 RADIAnON DOSE ASSESSMENT
3.1 GENERAL INFORMATION ABOUT MILDOS-AREA
MILDOS-AREA only considers airborne releases of radioactive materials;releases to surface
water and groundwater are not addressed.The U-238 decay chain was assumed to be the only
significant source of radiation fi'om uranium milling operations (the radioactivity contribution
from the U-235 chain is less than 5%of that from the U-238 chain).The pmticulate releases
include U-238,Th-230,Ra-226 and Pb-210.The gaseous releases are defined for Rn-222 with
in-growth of short-lived daughter products also considered.These Rn-222 daughters include
Po-218,Pb-214,Bi-214,Pb-21 0 and Po-21 O.The model accounts for the releases and in-growth
ofother radionuclides using the assumption ofsecular equilibrium within the U-238 decay chain.
The transport ofmodel radiological emissions from the point and area sources is predicted using
a sector-averaged Gaussian plume dispersion model.The dispersion model uses the
meteorological data provided by the user and also includes mechanisms of dry deposition of
pmticulates,re-suspension,radioactive decay and progeny in-growth and plume reflection.
Deposition build-up and in-growth of radioactive progeny are considered in estimating ground
concentrations.
The impacts to humans through various pathways are estimated based on the calculated annual
average air concentrations of radionuclides.The pathways considered in this analysis include:
inhalation,external exposure from ground concentrations,external exposure from cloud
immersion,and ingestion ofmeat and vegetables.
3.2 THE USE OF MILDOS-AREA IN THIS ASSESSMENT
As described in Section 1.3,the approach for this assessment was to extend the previous report
(SENES 2007)to incorporate the dose from the proposed development of Cell 4B,with as few
changes to the calculations as possible.MILDOS-AREA (version 2.20[3 (ANL 1998a»was used
to estimate potential radiation doses to members of the public estimated from the processing of
Colorado Plateau or Arizona Strip ores,with separate runs for each scenari%re.(Information
about the history of MILDOS-AREA is provided in Appendix A).In Scenario I,1,715 tons
(3,430,100 Ibs)ofUJOs per year of Colorado Plateau ore would be recovered at the proposed ore
process rate of 730,000 tpy (assuming that the average uranium recovery is 94%).Similarly in
Scenario 2,4,371 tons (8,742,000 Ibs)ofU30s per year of Arizona Strip ore would be recovered.
In order design a conceptual model of the mill,MILDOS-AREA requires the user to define
source and receptor locations and source emissions.The locations of sources and receptors are
defined in MILDOS-AREA by providing Cartesian coordinates of the source/receptor relative to
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a reference point.The coordinates ofa point source are entered directly while the user must enter
vertex coordinates for an area source.
In this assessment,the location of all sources (except for the tailings cells)and receptors were
taken from the previous report.The coordinates relative to the vanadium stack (i.e., the
reference point for the site)were determined by plotting the GPS coordinates (provided by
DUSA (Turk 2007a»in Google Earth Pro (Google 2005).A description of the tailings cells is
provided in Section 4.0.The source emissions were calculated using guidance from NRC
Regulatory Guide 3.59 (NRC 1987)and NUREG-0706 (NRC 1980).Radionuclide emission for
radioactive particulates and radon are entered directly for point sources.For area sources,
MILDOS-AREA calculates the radionuclide emission for radioactive particulates and radon
based on the release rates and source area.
Since all source terms except for the tailings cells were taken £i'om the previous report,the
MILDOS-AREA run (from the previous report)for each scenario was revised to include all
source terms except for the tailings cells.(Descriptions and emission rates for each source are
provided in Section 4.0,and detailed emission estimates can be found in Appendix B.)The
tailings cells were re-modelled individually in MILDOS-AREA as large area sources.
Descriptions and emission rates for each cell are provided in Section 4.0,and detailed emission
estimates are provided in Appendix B.
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4.0 SOURCE TERMS
The radionuclides of concern for the MILDOS-AREA model include:U-238 and its daughters
Th-230,Ra-226,Pb-210 and Rn-222,which were assumed to be in secular equilibrium with the
ore.The radioactive particulates and radon are emitted from airborne radioactive releases related
to dust generation during ore handling (unloading ore from truck to ore pads and loading ore to
the grizzly),point sources (grinder,yellowcake stacks and vanadium stack (only Scenario 1))
and area source dusting from ore pad stockpiles and the tailings cells.As mentioned in Section
3.2,all source telms except for the tailing cells were taken from the previous report.The
locations of all point sources except for the grinder were determined by plotting the GPS
coordinates (provided by DUSA (Turk 2007a))in Google Earth Pro;and then using the
measuring tool to measure the easting,nOithing and elevation of each source relative to a
reference point at the mill (i.e.,the vanadium stack).
The tailings cells were modelled as large area sources in MILDOS-AREA and located at the top
centre of each cell.Figure 4.1 shows the locations (plotted in Google Emth)of all sources used
in this assessment.
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FIGURE 4.1
SOURCE LOCATIONS
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The doses to members of the public were estimated for the processing of Colorado Plateau or
Arizona Strip ore in separate scenarios/runs.Therefore,the emission calculations are provided
for each ore type based on the activity concentration of U-238 in the ore,expected ore grade,
average uranium recovery and the proposed ore process rate.The MILDOS-AREA model for
Colorado Plateau ore has an additional point source (i.e.,vanadium stack)since the ore may
contain vanadium (assumed at 1.5%V20 S).The approaches used to calculate the emissions from
the point and area sources are described in Sections 4.1 and 4.2,respectively.Detailed source
emissions calculations for al1 source terms are provided in Appendix B.
4.1 POINT SOURCES
Mill point sources used in this assessment include the grinder,loading ore to the grizzly and
yel10wcake stacks (north and south).The vanadium stack described in Section 4.1.4 is exclusive
to the processing of Colorado Plateau ore.A description of the approach used to calculate the
emissions from point sources is provided in this section.
4.1.1 Grinder
There is no on-site crushing ofthe ore,only a wet grinding operation.The ore dust emissions are
control1ed because the material is wet during the grinding operations.The particulate emission
control from the grinding operation was assumed to be 99.9%(EnecoTech 1991a and 1991b).
With these assumptions,U-238 and its decay daughters (assuming secular equilibrium)would be
emitted at a rate of 9.27E-05 and 2.36E-04 Ci/yr for Colorado Plateau and Arizona Strip ore,
respectively.The emission rates for Rn-222 released during wet grinding was calculated
assuming that only 20%of the radon is available for release or emanation from the mineral
grains in which it is produced (NRC 1980).The Rn-222 concentration in the ore was assumed to
be equal to the U-238 concentration.The Rn-222 released during wet grinding is 92.7 and 236
Cilyr for Colorado Plateau and Arizona Strip ore,respectively.
4.1.2 Grizzly
The emissions fi'om !lucks dumping ore onto the gtizzly are highly control1ed;the truck dump
area is enclosed on three sides and has a negative pressure on it during dumping activities.The
ore is delivered wet with an average moisture content of 10%.The exhaust fi'om the induced
draft (ID)fans used on the grizzly is ducted through a baghouse (EnecoTech 1991a and 199Ib).
The combined particulate dust control on this operation was assumed to be 99.9%(EnecoTech
1991a and 1991b).With these assumptions,U-238 and its decay daughters (assuming secular
equilibrium)would be emitted at a rate of 9.27E-05 and 2.36E-04 Ci/yr for Colorado Plateau and
Arizona Strip ore,respectively.
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4.1.3 Yellowcake Stacks
The mill has two yellowcake dryers (north and south yellowcake dryers).From the EnecoTech
analysis,stack tests on the yellowcake dryer yielded a yellowcake emission rate of 0.06 Ibs/hr
U30 8 when the process rate was 1300 Ibs/hr.This yields an emission rate of 0.092 Ibs/hr of
yellowcake per ton of feed (EnecoTech 1991a and 1991b).The emission rate is with all the
particulate emissions controls.Since there are north and south yellowcake dryers,the stack
emissions from U-238 and its decay daughters are assumed to be divided equally between the
two (i.e.,north and south yellowcake stacks).With these assumptions,U-238 would be emitted
at a rate of 1.01 E-02 and 2.36E-04 Ci/yr for Colorado Plateau and Arizona Strip ore,
respectively.
Based on field measurements,the decay daughters of U-238 (Th-230,Ra-226 and Pb-2IO)are
processed along with yellowcake at 0.22%,0.13%and 0.78%ofU-238,respectively (EnecoTech
1991a and 199Ib).Therefore,the decay daughters Th-230,Ra-226 and Pb-210 are emitted at a
rate of2.22E-05,1.31E-05 and 7.88E-05 Ci/yr,respectively for Colorado Plateau ore.Similarly,
the decay daughters Th-230,Ra-226 and Pb-21O are emitted at a rate of5.67E-05,3.35E-05 and
2.01 E-04 Ci/yr,respectively for Arizona Strip ore.
Since the ore processing steps reject nearly all the radium to the tailings,very little radon is
released during the production of yellowcake.No significant radon releases occur during
yellowcake drying and packaging,since only about 0.1 %of the original Ra-226 in the ore is
found in yellowcake.Therefore,the amount of Rn-222 emitted from the yellowcake stack was
assumed to be negligible.
4.1.4 Vanadium Stack
The vanadium stack source term was only used in the MILDOS-AREA run for Colorado Plateau
ore.The vanadium present in the Colorado Plateau ore is partially solubilized during leaching.
The dissolved vanadium is present in uranium raffinate.Depending on its vanadium content,the
uranium raffinate will either be recyeled to the counter-current decantation step or further
processed for recovery of vanadium before recyeling.The product from the vanadium recovery
contains less than 0.005%U30 8 (NRC 1980).Therefore,the emission rate for the vanadium
stack was calculated to be 0.005%of the total emission rate from the yellowcake stacks (north
and south yellowcake stack)and U-238 was assumed to be emitted at a rate of 1.01E-06 Ci/yr.
Based on the EnecoTech (l99la and 1991b)measurements for the decay daughters of U-238
(Th-230,Ra-226 and Pb-21O)processed along with yellowcake of 0.22%,0.13%and 0.78%of
U-238,respectively,the emissions from the remaining radionuclides were assumed to be
negligible and in any event would likely be discharged to the tailings cells.
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4.2 AREA SOURCES
Mill area sources used in this assessment include the ore pads and the tailings cells.A
description ofthe approach used to calculate the emissions from area sources is provided in this
section.
4.2.1 Ore Pads
The ore pad storage operation has two different sources ofemissions,namely unloading ore from
trucks to the ore pad and wind emissions.Approximately 300,000 tons ofore were assumed to
be temporarily stockpiled at the mill's ore pads at any given time.Using a bulk ore density of
1.47 tons/yd3 (DUSA,Feb.6/07),the quantity of ore would create a pile 30 ft.(9.1 m)tall
covering approximately 4 acres (17,000 m2)stockpile area.
With respect to the truck unloading emissions,a process emission factor of 0.04 lbs of ore is
emitted per cubic yard handled (for a truck end and assuming no control (NRC 1987))and a bulk
ore density of 1.47 tons/yd3 was used in the calculations.With these assumptions,U-238 and its
decay daughters (assuming secular equilibrium)would be emitted at a rate of 1.58E-02 and
4.02E-02 Ci/yr for Colorado Plateau and Arizona Strip ore,respectively.
Wind erosion from the ore pad was assumed to have a 50%control factor due to the active
watering program in place (EnecoTech 1991a and 199Ib).This is conservative,in that actual
dust control on the ore pads may be better than this.The annual dust loss from the ore pad is
21.29 glm2yr;this was calculated using the method fi'om NRC Regulatory Guide 3.59 (NRC
1987)on the basis of the meteorological data (provided by DUSA (Turk 2007b))presented in
Appendix B;the annual dust loss from the ore pads is 10%that of the tailings piles since the
pmticulates in the ore pads are coarse material (I to 6 inch)because the ore has not yet been
ground.U-238 and its decay daughters (assuming secular equilibrium)were all assumed to be
emitted at a rate of 3.17E-04 and 8.07E-04 Ci/yr for Colorado Plateau and Arizona Strip ore,
respectively.Therefore,the total emission rate of U-238 and its daughter from truck dumping
and wind erosion is 1.61E-02 and 4.l0E-02 Ci/yr for Colorado Plateau and Arizona Strip ore,
respectively.
Rn-222 will be produced in the ore pads from the decay of Ra-226.The estimated annual radon
release rate from the ore pads is 375 and 956 Ci/yr for Colorado Plateau and Arizona Strip ore,
respectively.
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4.2.2 Tailings Cells
The characteristics of each tailings cell included in Phases 1 and 2 ofthe proposed development
ofnew tailings cell 4B are provided in Tables 4.2-1 and 4.2-2,respectively.
TABLE 4.2-1
CHARACTERISTICS OF TAILINGS CELLS IN PHASE I
Tailings Cell Interim Soil Cover (Inactive)Active
2 •0
3 0 •
4A 0 •
4B 0 0
TABLE 4.2-2
CHARACTERISTICS OF TAILINGS CELLS IN PHASE 2
Tailings Cell Interim Soil Cover (Inactive)Active
2 •0
3 •0
4A 0 •
4B 0 •
Active Tailings Cells
Wind erosion of tailings and radon release rates from the active tailings cell were estimated using
a maximal worst cast approach.However,since it is not possible to predict the distribution of
uncovered tailings between active cells at any given time,the active tailings cells were modelled
by using a maximal worst case approach.The following assumptions were used for the active
tailings cells:
•Each tailings cell was assumed to have a maximum area of 10 acres for uncovered
tailings material (this assumptions is considered to be conservative,because the average
area ofuncovered tailings in a cell is expected to be less than 10 acres).
•Wind-eroded tailings dust would arise from the 10 acres ofuncovered tailings.
•The total annual radon release rate for each tailings cell was calculated by assuming a
radon release rate of 20 pei/m2s (i.e.,maximum radon-222 emissions to ambient air from
an existing uranium mill pile that is allowed under the regulations)over the entire area of
each cell.However,this total annual radon release rate was assumed to be released from
the 10 acre area that was modelled.The area of tailings cell 3 was assumed to be 70
acres while tailing cells 4A and 4B were assumed to be 40 acres each.
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Using the onsite wind data generated over the last three years (provided by DUSA (Turk
2007b»,the annual dust loss fi'om the tailings cells was estimated to be approximately
213 g/m2yr;this was calculated using the method fi'om NRC Regulatory Guide 3.59 (NRC
1987).An average uranium recovery rate of 94%was assumed.In addition,a process emission
control factor of 70%was assumed,based on I)the active watering (tailings solutions spraying)
program on exposed areas of tailings beaches in active areas;2)solutions cover other tailings
areas;and 3)clUsting agents from the sprayed solutions act to minimize the erosion of the
tailings beaches by wind (EnecoTech 1991a and 199Ib).
With these assumptions and the particulate emission factor,U-238 would be emitted at a rate of
2.71 E-04 Ci/yr and the decay daughters Th-230,Ra-226 and Pb-21 0 would be emitted at a rate
of 4.52E-03 Ci/yr fi'om each active cell for Colorado Plateau are.These total annual emission
rates assume operation at the proposed are process rate of 730,000 tpy and an are specific
activity of 700 pCi/g.Similarly,for Arizona Strip ore,U-238 is emitted at a rate of 6.9IE-04
Ci/yr and the decay daughters Th-230,Ra-226 and Pb-21 0 are emitted at a rate of 1.15E-02 Ci/yr
fi'om each active cell.These total annual emission rates assume the proposed ore process rate of
730,000 tpy and an ore specific activity of 1783 pCi/g.
In this assessment,the total annual radon release rates for active tailings cell 3 and 4A and 48
were estimated to be 179 Ci/yr for tailings cell 3 and 102 Ci/yr for each of tailings cells 4A and
48.These estimates are extremely conservative because it was assumed that the radon release
rate of 20 pCi/m2s (i.e.,maximum radon-222 emissions to ambient air from an existing uranium
mill tailings impoundment)occurred over the entire area of each cell.Actual measurements
collected annually at the tailings cells to determine compliance with the NESHAPs radon
emanation standard have confinned that the 20 pCi/m2s release rate utilized for this assessment is
a conservative estimate.
Interim Soil Cover (Inactive Tailings Cells)
The tailings cells (2 and 3)with interim soil cover were assumed to be the entire areas of each
cell.The following assumptions were used for the tailings cells with interim soil covers:
•The area of tailings cell 2 with interim soil cover is 66.8 acres;
•The area of tailings cell 3 with interim soil cover is 70 acres;
• A nominal value of 10 pCi/m2s was used for radon flux based on historical values for the
Mill's tailings cells;and,
•No tailings dust will be released.
Using the assumptions above,the total annual radon release from the tailings cells 2 and 3 with
interim soil covers were 85.3 and 89.4 Ci/yr,respectively.
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4.3 METEOROLOGICAL DATA
Meteorological conditions influence re-suspension and dispersion of radionuclides from point
sources and area sources.The mill has an on-site weathering monitoring station that records
wind speed,wind direction and stability class.This data is used to formulate a joint frequency
distribution which is a required input for MlLDOS-AREA.The joint frequency distribution used
in this assessment was provided by DUSA (Turk 2007b)using the most recent three years (2004
to 2006)ofrecorded data.
4.4 POPULATION DATA
The population data was obtained from the year 2000 U.S.census and was used to complete
demographic and population dose projections.Census data is only available in 10 year intervals
for population centers of less than 65,000 residents,and local demographics have experienced
little change since the 2000 census.
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4.5 URANIUM MILL SOURCE EMISSION RATES
4.5.1 Colorado Plateau Ore
The calculated mill radioactive particulate and radon emission rates from point sources and area sources described in Sections 4.1 and
4.2,respectively for Colorado Plateau ore are provided in Table 4.5-1.
TABLE 4.5-1
RADIOACTIVE PARTICULATE AND RADON EMISSION RATES
(COLORADO PLATEAU ORE)
Ore Dump North YC South YC Interim Soil Cover Active VanadiumGrindingtoGrizzlyOrePadsStackStackTailingsTailingsTailingsTailingsTailingsStack'Cell 2 Cell 3 Cell 3 Ce1l4A Ce1l4B
U-238 9.27E-05 9.27E-05 L61E-02 LOIE-02 LOIE-02 O.OOE+OO O.OOE+OO 2.71E-04 2.7IE-04 2.71E-04 LOIE-06
Emission Th-230 9.27E-05 9.27E-05 L61E-02 2.22E-05 2.22E-05 O.OOE+OO O.OOE+OO 4.52E-03 4.52E-03 4.52E-03 2.22E-09
Rate Ra-226 9.27E-05 9.27E-05 L61E-02 l.31E-05 L31E-05 O.OOE+OO I O.OOE+OO 4.52E-03 4.52E-03 4.52E-03 l.31E-09
(Cilyr)Pb-210 9.27E-05 9.27E-05 L6IE-02 7.88E-05 7.88E-05 O.OOE+OO I O.OOE+OO 4.52E-03 4.52E-03 4.52E-03 7.88E-09
Rn-222 9.27E+Ol Note a 3.75E+02 Note a Note a 8.53E+Ol I 8.94E+OI L79E+02 L02E+02 L02E+02 Note a
Notes:
a)No significant release during this process.
b)Source is exclusive to the processing ofColorado Platean ore.
4.5.2 Arizona Strip Ore
The calculated mill radioactive particulate and radon emission rates from point sources and area sources described in Sections 4.1 and
4.2,respectively for Arizona Strip ore are provided in Table 4.5-2.
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TABLE 4.5-2
RADIOACTIVE PARTICULATE AND RADON EMISSION RATES
(ARIZONA STRIP ORE)
Ore Dump North YC South YC Interim Soil Cover Active
Griuding to Grizzly Ore Pads Stack Stack
Tailings Tailings Tailings Tailings Tailings
Cell 2 Cell3 Cell 3 CeIl4A CeIl4B
U-238 2.36E-04 2.36E-04 4.IOE-02 2.58E-02 2.58E-02 O.OOE+OO 0.00£+00 6.9 IE-04 6.91E-04 6.91E-04
Emission Th-230 2.36E-04 2.36E-04 4.1OE-02 5.67E-05 ,5.67E-05 O.OOE+OO 0.00£+00 1.15E-02 1.15E-02 1.15E-02
Rate Ra-226 2.36E-04 2.36E-04 4.IOE-02 3.35E-05 3.35E-05 O.OOE+OO O.OOE+OO 1.15E-02 1.15E-02 I 1.15E-02
(Cilyr)Pb-2IO 2.36E-04 2.36E-04 4.IOE-02 2.01E-04 2.01E-04 O.OOE+OO O.OOE+OO ,1.15E-02 1.15E-02 I 1.15E-02
Ro-222 2.36E+02 Note a 9.56E+02 Note a Note a .8.53E+OI 8.94£+01 1.79£+02 1.02E+02 I 1.02E+02
Note:
a)No significant release during this process.
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5.0 RECEPTORS
The receptors used in this assessment were provided by DUSA.The receptors used in this
assessment were as follows:
•Nearest Historical Resident (BHV-2);
•Nearest Actual Resident;
•Nearest Potential Resident (BHV-I);
•White Mesa Ute Community;
•Blanding,Utah.
In addition,two grazing locations I and 2 were considered as a possible source ofmeat.
As mentioned in Section 3.2,the receptor locations were detennined using GPS coordinates
provided by DUSA (Turk 2007a).The GPS coordinates were used for all the receptors except
for Grazing locations I and 2 where the easting and northing for Grazing locations I and 2 were
taken as nominal "mid-points"in Google Earth for these two receptor locations.
The receptor locations (plotted in Google Earth)with respect to the vanadium stack are shown in
Figure 5.1.
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FIGURE 5.1
RECEPTOR LOCAnONS
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At the time of the 1979 Final Environmental Statement (FES)(NRC 1979)for the mill,the
nearest resident lived approximately 4.8 miles (4.5)km north-north east of the mill building,near
the location of air monitoring station BHV-2 (also referred to as the historical nearest resident.)
Currently,the nearest "potential"resident is approximately 1.2 miles (1.9 km)north ofthe Mill,
near the location of air monitoring station BHV-I.The nearest actual resident is located
approximately 1.6 miles (2.5 km)north of the mill.Nearby population h'TOUPS include the
community of White Mesa,about 8.5 km south east and the city of Blanding,approximately
6 miles (10 km)from the mill.
The area to the immediate north of the mill (Grazing location I)is believed to be used only for
grazing of meat animals (beef)(NRC 1979).A second location (Grazing location 2)to the east
and south of the mill is also used for the grazing of meat animals (beef)as was assumed in the
EnecoTech analysis (EnecoTech 1991a and 199Ib).Although considered unlikely,in one worst
case scenario,it is possible that the meat animals grazed at Grazing location I and 2 would be
eaten by the residents near the mill.A scenario which suppolls dairy cattle grazing at Grazing
locations I and 2 was not included because the prospect of sUPPolling dairy cattle in those
locations is not credible,given the arid climate and the much larger feed requirements of dairy
cattle as opposed to beefcattle.DUSA has also indicated that there are no dairy cattle grazed in
Grazing locations I and 2.It should be noted,however,that in all of the MILDOS-AREA model
runs in this report,it was assumed,conservatively,that individuals at each receptor location
drink all of their milk from cows and eat all of their beef from cattle that graze at the receptor
locations (but not at Grazing locations I or 2).This is thought to be a very conservative
assumption.
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6.0 RADIATION DOSE ESTIMATES
This section describes the MILDOS-AREA results ofthe mill's potential radiological impacts on
the population in the vicinity of the Mill.This analysis was primarily based on the estimated
annual releases of radioactive materials and assumptions discussed in Sections 4.0 and 5.0.All
potential exposure pathways which are likely to impact individuals near the mill were included in
the MILDOS-AREA model.
MILDOS-AREA calculates the total annual effective dose commitment (including radon).The
calculated total annual effective dose commitments were compared to the 10 CFR 20 (R3 13-I5)
requiremcnts that the dose to individual mcmbcrs of the public shall not exceed 100 mrcm/yr
(radon ineluded).In addition,MILDOS-AREA calculates 40 CFR 190 doses (excludes radon).
The 40 CFR 190 Criterion is 25 mrem/yr to thc whole body (excluding the dose duc to radon)
and 25 mrem/yr to any othcr organ to any member of the public (EPA 2002).The 40 CFR 190
doses were also used to demonstrate compliance with 10 CFR 20.1 101(d)(R313-15-101(4».
Under 10 CFR 20.1 101(d)(R313-15-IOI(4)the licensee must demonstrate as an ALARA goal
that the total effective dose equivalcnt to the individual member of the public likely to receive
thc highest total effectivc dose cquivalent will not exceed 10 mrem/yr (absent ofthe radon dose).
In this assessment,a worst-case scenario in which there is a possibility that individuals near the
mill ingcst meat from cattle grown at Grazing Location 1 or 2 was considered.It was assumed
that thc cattle will graze at Grazing location 1 or 2 for two months of the year (due to the arid
nature of the rcgion and the lack of forage).Therefore,the meat ingestion dose to individuals
near the mill who might consumc beefi,rrazed at Grazing Location I or 2 was assumed to be onc-
sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations.
As mentioned in Section 1.3,MILDOS-AREA was run separately for Colorado Plateau and
Arizona Strip ore.Total annual dose commitments and 40 CFR 190 annual dosc commitments
were estimated for locations in which individual members of the public might reside (Nearest
Potential Resident (BHV-I),Nearest Historical Resident (BHV-2),Nearest Actual Resident,
White Mesa Ute Community and Blanding,Utah)for two development Phases of the new
tailings cells.The total annual dose commitments and 40 CFR 190 annual dose commitments for
Phases 1 and 2 are provided in Sections 6.1 and 6.2 for Colorado Platcau and Arizona Strip ore,
respectively.In addition,total annual dose commitments and 40 CFR 190 annual dose
commitments from the meat ingestion pathway that is estimated for Grazing location 1 and 2 are
provided in Sections 6.1 and 6.2,respectively.
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6.1 MILDOS-AREA RESULTS FOR COLORADO PLATEAU ORE
The potential annual doses to the people living close to the mill and to the population living
within 50 miles (80 km)as a result of processing Colorado Plateau ore was calculated using
MILDOS-AREA.
The MILDOS-AREA-calculated total annual dose commitments (including radon)and 40 CFR
190 total annual dose commitment for processing of Colorado Plateau ore are provided in
Sections 6.1.1 and 6.1.2,respectively
6.1.1 R313-15-301(1)(a)Regulatory Compliance
The MILDOS-AREA calculated total annual dose commitments (including radon)for Phases I
and 2 are provided in this section.These doses are regulated by R313-15-30I(l)(a)which
requires that the dose to an individual member of the public shall not exceed 100 mrem/yr (radon
included).
Phase 1
Table 6.1-1 presents a summary of the individual dose commitments for the residential receptors
for the age group of infant,child,teenage and adult for Phase 1.
34489-10 -FINAL -April 2008 6-2 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-1
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Groun (mrelll/vr)'(mrem/vr)ofLimit
Infant Effective 1.37E+00 100 1.37E-02
Bone 1.92E+00 --
Avg.Lung 5.3IE-Ol --
Bronchi 1.30E+OI --
Child Effective 1.05E+00 100 1.05E-02-Bone 1.37E+00 --
Avg.Lung 7.lOE-OI --
Nearest Potential Bronchi 1.30E+Ol --
Resident (BHV-I)Teenage Effective 1.I0E+00 100 1.I0E-02-
Bone 4.84E+00 --
Avg.Lung 5.68E-OI ----Bronchi 1.30E+Ol --
Adult Effective 9.84E-OI 100 9.84E-03
Bone 2.13E+OO --
Avg.Lung 3.97E-OI --
Bronchi 1.30E+OI --
Infant Effective 3.lOE-Ol 100 3.10E-03
Bone 3.05E-Ol --
Avg.Lung 1.06E-Ol --
Bronchi 3.52E+00 --
Child Effective 2.66E-OI 100 2.66E-03
Bone 2.33E-OI ---
Avg.Lung 1.29E-OI --
Nearest Historical Bronchi 3.52E+00 --
Resident (BHV-2)Teenage Effective 2.72E-Ol 100 2.72E-03---
Bone 7.63E-Ol ---
Avg.Lung 1.05E-Ol --
Bronchi 3.52E+00 --
Adult Effective 2.55E-Ol 100 2.55E-03
Bone 3.53E-01 --
Avg.Lung 7.69E-02 --
Bronchi 3.52E+00 ---
34489-10 -FINAL-April 2008 6-3 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-1 (Coot'd)
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Agc Organ Estimated Dose Applicable Limit Fraction
Groun Imrem/yr)-Imrem/vr)ofLimit
Infant Effective 8.78E-OI 100 8.78E-03
Bone 1.13E+00 --
Avg.Lung 3.17E-OI --
Bronchi 8.78E+00 --
Child Effective 6.95E-OI 100 6.95E-03_..
Bone 8.12E-OI --
Avg.Lung 4.2IE-OI --
Nearest Actual Bronchi 8.78E+00 --
Resident Teenage Effective 7.2IE-OI 100 7.2 IE-03
Bone 2.83E+00 --
Avg.Lung 3.39E-OI --
Bronchi 8.78E+00 --
Adult Effective 6.55E-OI 100 6.55E-03
Bone 1.26E+00 --
Avg.Lung 2.40E-OI --
Bronchi 8.78E+00 --
Infant Effective 2.45E-OI 100 2.45E-03
Bone 1.45E-OI --
Avg.Lung 6.72E-02 --
Bronchi 3.18E+00 --
Child Effective 2.25E-OI 100 2.25E-03
Bone 1.08E-OI --
Avg.Lung 6.47E-02 --
White Mesa Bronchi 3.18E+00 --
Community Teenage Effective 2.26E-0I 100 2.26E-03
Bone 2.86E-OI --
Avg.Lung 5.26E-02 --
Bronchi 3.18E+00 --
Adult Effective 2.20E-OI 100 2.20E-03
Bone 1.48E-OI --
Avg.Lung 4.27E-02 --
Bronchi 3.18E+00 --
34489"10 -FINAL -April 2008 6-4 SENES Consultants Limited
Proposed Development ofNew Tailings Cel/4Bfor White Mesa Uranium Mill
TABLE 6.1-1 (Cont'd)
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applieable Limit Fraction
Group (mrem/vr\(mrem/vr)ofLimit
Infant Effective 1.07E-OI 100 1.07E-03
Bone 8.94E-02 --
Avg.Lung 3.36E-02 --._-
Bronchi l.25E+00 --
Child Effective 9.38E-02 100 9.38E-04
Bone 6.78E-02 --
Avg.Lung 3.91E-02 --
Blanding Bronchi l.25E+00 --1------EffectiveTeenage 9.55E-02 100 9.55E-04
Bone 2.10E-Ol --
Avg.Lung 3.23E-02 --
Bronchi 1.25E+00 --
Adult Effective 9.08E-02 100 9.08E-04---
Bone 1.00E-01 --
Avg.Lung 2.47E-02 --
Bronchi 1.25E+00 --
From Table 6.1-1,the total annual effective dose commitments are at most 1.4%(effective dose
for infant at SHY-I)of the R313-15-30I(l)(a)limit of 100 mrem/yr (radon included)to an
individual member of the public.Therefore,the predicted annual effective dose commitments
comply with R313-15-30I(l)(a).
In the worst case scenario in which there is a possibility that individuals near the mill ingest meat
fi-om cattle grown at Grazing Location I or 2.It was assumed that the cattle will graze at
Grazing location I or 2 for 2 months of the year.The meat ingestion dose to individuals near the
mill who might consume beefgrazed at Grazing Location I or 2 was assumed to be one-sixth of
the MILDOS-AREA calculated meat ingestion dose from these grazing locations.Table 6.1-2
presents a summary of the annual dose commitments from the meat ingestion pathway for
Grazing location I and 2.Even in the very unlikely event that a resident were to consume meat
fi'om one ofthe grazing locations,the total dose would remain well below regulatory limits.
34489-10 -FINAL -April 2008 6-5 SENES Consultants Limited
Proposed Deve[op"!ent ofNew Tailings Cell4Bfor White Mesa Uranium Mill
TABLE 6.1-2
PHASE I-TOTAL ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (COLORADO PLATEAU ORE)(mrem/yr)
Location Age Organh
Gronp Effective'Bonea Avg.Lnng'
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location I Child 1.08E-02 5.40E-02 4.91E-02-
Teenage 1.70E-02 2.80E-OI 4.30E-02
Adult 1.23E-02 1.52E-0 I 3.55E-02
Infant O.OOHOO O.OOE+OO O.OOE+OO
Grazing Location 2 Child 7.35E-04 3.65E-03 3.12E-03
Teenage 1.14E-03 1.92E-02 2.72E-03
Adult 8.13E-04 1.01E-02 2.25E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
Phase 2
Table 6.1-3 presents a summary ofthe individual dose commitments for the residential receptors
for the age group ofinfant,child,teenage and adult for Phase 2.
TABLE 6.1-3
PHASE 2-COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Agc Organ Estimated Dose Applicable Limit Fraction
Gronp (mrem/yr)(mrem/yr)ofLimit
Infant Effective l.35E+00 100 1.35E-02
Bone 1.90E+00 --
Avg.Lung 5.20E-OI --..._-
Bronchi 1.28E+OI --
Child Effective 1.04E+00 100 1.04E-02
Bone l.35E+00 --
Avg.Lung 6.93E-OI --
Ncarcst Potential Bronchi 1.28HOJ --
Resident (BHV-I)Teenage Effective 1.08E+00 100 1.08E-02
Bone 4.75E+00 --
Avg.Lung 5.54E-0I --
Bronchi 1.28E+OI --
Adult Effective 9.68E-OJ 100 9.68E-03
Bone 2.09E+00 --
Avg.Lung 3.87E-OJ --
Bronchi 1.28E+OJ --
34489-10-FINAL -April 2008 6-6 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
TABLE 6.1-3 (Cont'd)
PHASE 2-COMPARlSON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Gronn (mrem/yr)(mrem/yr)ofLimit
Infant Effective 3.IOE-OI 100 3.lOE-03-
Bone 3.03E-OI --
Avg.Lung 1.05E-OI ---
Bronchi 3.52E+00 --_.
Child Effective 2.66E-0 I 100 2.66E-03
Bone 2.3IE-OI --
Avg.Lung 1.28E-OI --.-
Nearest Historical Bronchi 3.52E+00 --
Resident (BHV-2)Teenage Effective 2.72E-OI 100 2.72E-03
Bone 7.57E-0 I --
Avg.Lung 1.04E-OI --
Bronchi 3.52E+00 --
Adult Effective 2.55E-OI 100 2.55E-03
Bone 3.50E-OI --
Avg.Lung 7.63E-02 --
Bronchi 3.52E+00 --
Infant Effective 8.70E-OI 100 8.70E-03
Bone 1.12E+00 --
Avg.Lung 3.IIE-OI ---
Bronchi 8.69E+00 --
Child Effective 6.88E-OJ 100 6.88E-03
Bone 7.98E-OI --
Avg.Lung 4.J3E-OI --
Nearest Actual Bronchi 8.69E+00 --
Resident -Teenage Effective 7.13E-OI 100 7.13E-03
--Bone 2.78E+00 --
Avg.Lung 3.32E-OI --
Bronchi 8.69E+00 --
Adult Effective 6048E-01 100 6048E-03
Bone 1.23E+00 --
--Avg.Lung 2.35E-OI --
Bronchi 8.69E+00 --
34489-10 ...FINAL -April 2008 6-7 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-3 (Cont'd)
PHASE 2-COMPARIS0N OF ANNUAL DOSE COMMITMENTS TO APPLICABLE
RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Grolln (mrem/vr)(mrem/vr)of Limit
Infant Effective 2.47E-01 100 2.47E-03
Bone 1.45E-01 --
Avg.Lung 6.69E-02 --
Bronchi 3.20E+00 --
Child Effective 2.26E-01 100 2.26E-03
Bone 1.07E-01 ---Avg.Lung 6.45E-02 --
White Mesa Bronchi 3.20E+00 --
Community Teenage Effective 2.28E-01 100 228E-03'--
Bone 2.85E-OI ---
Avg.Lung 5.25E-02 --
Bronchi 3.20E+00 --
Adult Effective 2.22E-01 100 2.22E-03
Bone 1.48E-01 --
Avg.Lung 4.27E-02 --
Bronchi 3.20E+00 --
Infant Effective 1.08E-01 100 1.08E-03
Bone 8.94E-02 --
Avg.Lung 3.36E-02 ------
Bronchi l.26E+00 ---Child Effective 9.46E-02 100 9,46E-04--
Bone 6.79E-02 --._-
Avg.Lung 3.92E-02 --
Blanding Bronchi 1.26E+00 --
Teenage Effective 9.62E-02 100 9.62E-04---Bone 2.10E-01 --.__.
Avg.Lung 3.23E-02 -----Bronchi 1.26E+00 --
Adult Effective 9.15E-02 100 9.15E-04
Bone 1.00E-01 --
Avg.Lung 2.48E-02 --f---.
Bronchi l.26E+00 --
From Table 6.1-3,the total annual effective dose commitments are at most 1.4%(effective dose
for infant at BHV-I)of the R313-15-30I(l)(a)limit of 100 mrem/yr (radon included)to an
individual member of the public.Therefore,the predicted annual effective dose commitments
comply with R313-15-301 (l)(a).
In addition,Table 6.1-4 presents a summary of the annual dose commitments from the meat
ingestion pathway for Grazing location I and 2.As before,in the very unlikely event that a
34489-10 -FINAL -April 2008 6-8 SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
resident were to consume meat from one of the grazing locations,the total do se would remain
well below regulatory limits.
TABLE 6.1-4
PHASE 2-TOTAL ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (COLORADO PLATEAU ORE)(mremlyr)
Location Age Organ"
Group Effectivea Ronca Avg.Lung'
Infant O.OOE+OO O.OOE+OO O.OOE+OO ..-
Grazing Location 1 Child l.07E-02 5.35E-02 4.87E-02
Teenage 1.68E-02 2.78E·Ol 4.26E-02
Adult 1.22E-02 1.50E-Ol 3.5IE-02}----...
O.OOHOOInfant O.OOE+OO O.OOHOO
Grazing Location 2 Child 6.73E-04 3.34E-03 2.82E-03
Teenage l.04E-03 1.76E-02 2.46E-03
Adult 7.4 IE-04 9.22E-03 2.03E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
6.1.2 40 CFR 190 Regulatory Compliance
MILDOS-AREA calculated 40 CFR 190 doses (excludes radon).These doses are regulated by
the 40 CFR 190 criterion of 25 mrem/yr to the whole body (excluding the dose due to radon)
(EPA 2002)or to any organ of the body.The 40 CFR 190 doses are also used to demonstrate
compliance with R313-15-IOI(4)(10 CFR 20.1101(d)).The licensee must demonstrate as an
ALARA goal,that total effective dose equivalent to the individual member ofthe public likely to
receive the highest total effective dose equivalent will not exceed 10 mrem/yr (absent of the
radon dose).
Phase 1
Table 6.1-5 presents a summary of the 40 CFR 190 individual dose commitments for residential
receptors for the age group ofinfant,child,teenage and adult for Phase 1.
34489·10 -FINAL·April 2008 6-9 SENES Consultants Limited
____P'--ro2,'P_o-'-se.d Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
TABLE 6.1-5
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
Group (mrem/yr) (mrem/yr)Limitf--
Iufant Effective 5,45E-Ol 25 2.18E-02
Bone l.86E+OO 25 7,45E-02._-
--Avg.Lung 4.85E-Ol 25 l.94E-02
Bronchi 9.73E-04 no limit given -
Child Effective 2.32E-Ol 25 9.28E-03
Bone 1.33E+OO 25 5.30E-02
Avg,Lung 6.62E-Ol 25 2.65E-02
Nearest Potential Bronchi 9.73E-04 no limit given -
Resident (BHV-1)---
Teenage Effective 2.76E-Ol 25 1.l0E-02
Bone 4.79E+OO 25 l.92E-OI
Avg.Lung 5.22E-Ol 25 2.09E-02
Bronchi 9.73E-04 no limit given -
Adult Effective l.63E-Ol 25 6.50E-03
Bone 2.09E+OO 25 8.35E-02
Avg.Lung 3.5IE-OI 25 l.40E-02
Bronchi 9.73E-04 no limit given -
Infant Effective 8.07E-02 25 3.23E-03
Bone 2.82E-Ol 25 1.l3E-02
Avg.Lung 8.56E-02 25 3,42E-03
Bronchi 1.39E-04 no limit given -
Child Effective 3.6IE-02 25 1,44E-03
Bone 2.09E-Ol 25 8.37E-03
Avg.Lung l.07E-Ol 25 4.29E-03--
Nearest Historical Bronchi 1.39E-04 no limit given -
Resident (BHV-2)--
Teenage Effective 4.26E-02 25 l.71E-03
Bone 7.30E-Ol 25 2.92E-02
Avg.Lung 8.31E-02 25 3.32E-03
Bronchi 1.39E-04 no limit given -
Adult Effective 2.55E-02 25 l.02E-03
Bone 3.26E-Ol 25 l.30E-02
Avg.Lung 5.62E-02 25 2.25E-03
Bronchi 1.39E-04 no limit given -
34489-10 -FINAl.-April 2008 6-10 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE 6.1-5 (Cont'd)
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
Group (mrem/yr)(mrem/yrj Limit
Infant Effective 3.I7E-OI 25 I.27E-02
-_._._---_.-Bone I.09E+OO 25 4.37E-02
Avg.Lung 2.8IE-OI 25 !.l2E-02 -_.
Bronchi 5.62E-04 no limit given -
Child Effective 1.35E-OI 25 5.40E-03
Bone 7.73E-OI 25 3.09E-02-
Avg.Lung 3.84E-OI 25 I.54E-02------_.__.._..._.
Nearest Actual Resident Bronchi 5.62E-04 no limit given -
Teenage Effective I.60E-OI 25 6.42E-03
Bone 2.78E+OO 25 !.lIE-OI
Avg.Lung 3.02E-OI 25 I.2IE-02
Bronchi 5.62E-04 no limit given -
Adult Effective 9.46E-02 25 3.78E-03
Bone I.2IE+OO 25 4.86E-02
Avg.Lung 2.03E-OI 25 8.12E-03
Bronchi 5.62E-04 no limit given -
Infant Effective 3.36E-02 25 1.35E-03-
Bone !.l9E-OI 25 4.74E-03
Avg.Lung 4.55E-02 25 I.82E-03.-
Bronchi 4.25E-05 no limit given -
Child Effective 1.3 IE-02 25 5.22E-04
----Bone 7.80E-02 25 3.12E-03
Avg.Lung 3.85E-02 25 I.54E-03
White Mesa Community Bronchi 4.25E-05 no limit given -
Teenage Effective 1.38E-02 25 5.5IE-04
Bone 2.3IE-OI 25 9.26E-03
1---._--_._--Avg.Lung 2.72E-02 25 I.09E-03
Bronchi 4.25E-05 no limit given -
Adult Effective 8.69E-03 25 3.48E-04
Bone !.lIE-OI 25 4.42E-03
Avg.Lung I.9IE-02 25 7.63E-04
Bronchi 4.25E-05 no limit given -
34489-10 -FINAL -April 2008 6-11 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-5 (Cont'd)
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
Groll»(mrem/vr)Imrem/vr)Limit
Infant Effective 2.21E-02 25 8.84E-04
Bone 7.69E-02 25 3.08E-03
Avg.Lung 2.39E-02 25 9.57E-04-
Bronchi 3,49E-05 no limit given -
Child Effective 9.23E-03 25 3.69E-04
Bone 5.38E-02 25 2.15E-03
Avg.Lung 2.69E-02 25 l.08E-03
Blanding Bronchi 3.49E-05 no limit given -
Teenage Effective l.06E-02 25 4.24E-04
f----------Bone l.81E-Ol 25 7.25E-03
Aw.Lung 2.05E-02 25 8.19E-04
Bronchi 3,49E-05 no limit given -
Adult Effective 6.38E-03 25 2.55E-04
Bone 8.16E-02 25 3.27E-03
Avg.Lung l.39E-02 25 5.57E-04
Bronchi 3.49E-05 no limit given -
From Table 6.1-5,the 40 CFR 190 annual dose commitments are at most 19.2%(dose to the
bone for the teenage at SHV-I)ofthe 40 CFR 190 dose criterion of25 mrem/yr.In addition,the
40 CFR 190 annual effective dose commitments demonstrate compliance with the R313-15-
101(4)(10 CFR 20.1101(d»ALARA goal of 10 mrem/yr to the individual member of the public
likely to receive the highest total effective dose equivalent.The maximum total effective dose
equivalent was 0.545 mrem/yr (infant at SHV-I),or 5.45%of the 10 mrem/yr goal.
In addition,Table 6.1-6 presents a summary of the 40 CFR 190 annual dose commitments from
the meat ingestion pathway for Grazing Locations I and 2.As before,in the unlikely event a
receptor were to eat meat from cattle grazing in areas I or 2,the total dose would remain well
below regulatory limits.
34489-10 -FINAL-April 2008 6-12 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE 6.1-6
40 CFR 190 ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION PATHWAY
(COLORADO PLATEAU ORE)(mremlyr)
Location Age Group Or~anb
Effeetive'Bonca Avg.Lung'
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location I Child 1.08E-02 5.40E-02 4.9IE-02
Teenage l.70E-02 2.80E-OI 4.30E-02
Adult 1.23E-02 1.52E-0 I 3.55E-02
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 2 Child 7.33E-04 3.63E-03 3.IOE-03
Teenage 1.13E-03 1.91E-02 2.72E-03
Adult 8.IOE-04 1.01 E-02 __2.24E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
b)Exclusive ofradon.
The annual doses to the population estimated within 50 miles (80 km)of the site are provided in
Table 6.1-7.
TABLE 6.1-7
PHASE I-ANNUAL POPULATION DOSE COMMITMENTS WITHIN SO MILES
(80 km)OF THE MILL FOR COLORADO PLATEAU ORE
ANNUAL POPULATION DOSE COMMITMENTS,
Organ PERSON-REM PER YEAR
Mill Operations
Effective 1.47E-OI
Bone 1.12E+00
Avg.Lung 1.53E-OI
Bronchi 8.60E+00
The population dose arising from processing Colorado Plateau ore during Phase 1 is estimated at
0.15 person-rem.This can be compared to the dose from natural background sources of
radiation.
In the United States,nominal average levels of natural background radiation are as follows
(NCR?1987):
Cosmic and Cosmogenic
Terrestrial
Inhaled (Radon)
Ingested
Total (Average)
28 mrem/yr
28 mrcm/yr
200mrem/yr
40 mrem/yr
296 mrern/yr (96 mremlyr excluding radon)
34489-10-FINAL -April 2008 6-13 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
In the area of the White Mesa Mill,natural background radiation was measured at two sites in
1977:the project site (Blanding)and the Hanksville site.At the Blanding site,the average dose
equivalent from external radiation was about 142 mrem/yr.Of this 142 mrem/yr,68 mrem/yr
came from cosmic radiation,while 74 mrem/yr came fi'om telTestrial radiation.
(Dames &Moore 1978).At the Hanksville site,the corresponding average dose equivalent was
about 122 mrem/yr (68 mrem/yr fi'om cosmic radiation and 54 mrem/yr from telTestrial
radiation).(Dames &Moore 1978).
Ingested radionuclides would contribute (about)a further 18 mrem/yr (NRC 1979).This brings
the total background dose from external radiation and ingested radioactivity,but exclusive ofthe
dose from radon-222,to about 161 mrem/yr;which is higher than both the U.S.averages of
96 mrem/yr.
If the nominal U.S.dose fi'om radon of about 200 mrem per year is added,then the total dose
from natural background in the area ofthe mill is 360 mrem/yr (or more assuming the dose from
radon would increase along with that from telTestrial source).
The cun'ent population ofSan Juan County is about 14,400 people.Assuming everyone living in
San Juan County receives an annual dose of (about)360 mrem/yr,then the total dose due to
natural background is approximately 5184 person-rem.The theoretical incremental dose of
0.15 person-rem is clearly inconsequential by comparison.
Phase 2
Table 6.1-8 presents a summary of the 40 CFR 190 individual dose commitments for the
residential receptors for the age group ofinfant,child,teenage and adult for Phase 2.
34489-10 --FINAL -April 2008 6-14 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-8
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
GrouD (mrem/vr)(mrem/m Limit
Infant Effective 5.40E-OI 25 2.16E-02
Bone 1.84E+00 25 7.36E-02
Avg.Lung 4.75E-Ol 25 1.90E-02
Bronchi 9.63E-04 no limit given -
Child Effective 2.28E-01 25 9.11E-03
Bone 1.30E+00 25 5.20E-02
Avg.Lung 6.46E-01 25 2.58E-02
Nearest Potential Bronchi 9.63E-04 no limit given -
Resident (BHV-1)-
Teenage Effective 2.70E-Ol 25 1.08E-02
Bone 4.70E+00 25 1.88E-Ol
Avg.Lung 5.09E-Ol 25 2.03E-02
Bronchi 9.63E-04 no limit given -
Adult Effective 1.59E-Ol 25 6.36E-03
Bone 2.04E+00 25 8.17E-02
Avg.Lung 3.42E-01 25 1.37E-02
Bronchi 9.63E-04 no limit given -
Infant Effective 8.03E-02 25 3.21E-03
Bone 2.81E-Ol 25 1.I2E-02
Avg.Lung 8.47E-02 25 3.39E-03
Bronchi 1.38E-04 no limit given -
Child Effective 3.58E-02 25 1.43E-03
Bone 2.07E-Ol 25 8.29E-03--
Avg.Lung 1.06E-Ol 25 4.24E-03
Nearest Historical Bronchi 1.38E-04 no limit given -
Resident (BHV-2)Teenage Effective 4.22E-02 25 1.69E-03
Bone 7.23E-Ol 25 2.89E-02
Avg.Lung 8.21E-02 25 3.29E-03--
Bronchi 1.38E-04 no limit given -
Adult Effective 2.53E-02 25 1.01E-03
Bone 3.23E-Ol 25 1.29E-02
Avg.Lung 5.56E-02 25 2.22E-03
Bronchi 1.38E-04 no limit given -
34489-10 ...FINAL -April 2008 6-15 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-8 (Cont'd)
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
Group (mrem/vr\(mrem/vr)Limit
Infant Effective 3.l5E-Ol 25 1.26E-02
Bone 1.08E+OO 25 4.32E-02
Avg.Lung 2.75E-Ol 25 1.10E-02
Bronchi 5.57E-04 no limit given -
Child Effective 1.33E-Ol 25 5.31E-03
Bone 7.59E-Ol 25 3.04E-02
Avrr.Lnnrr 3.76E-Ol 25 1.50E-02._...
Nearest Actual Resident Bronchi 5.57E-04 no limit given -
Teenage Effective 1.58E-OI 25 6.30E-03
Bone 2.73E+OO 25 1.09E-Ol
Avg.Lunrr 2.95E-OI 25 1.18E-02
Bronchi 5.57E-04 no limit given -
Adult Effective 9.28E-02 25 3.7IE-03
Bone 1.19E+OO 25 4.77E-02
Avg.Lung 1.99E-OI 25 7.94E-03
Bronchi 5.57E-04 no limit given -
Infant Effective 3.35E-02 25 1.34E-03
Bone 1.18E-Ol 25 4.71E-03
Avg.Lung 4.50E-02 25 1.80E-03
Bronchi 4.23E-05 no limit given -
Child Effective 1.29E-02 25 5.l7E-04
Bone 7.72E-02 25 3.09E-03
Avg.Lung 3.80E-02 25 1.52E-03
White Mesa Community Bronchi 4.23E-05 no limit given -
Teenage Effective 1.36E-02 25 5.46E-04
Bone 2.29E-O I 25 9.17E-03
Avg.Lunrr 2.69E-02 25 1.08E-03
Bronchi 4.23E-05 no limit given -
Adult Effective 8.60E-03 25 3.44E-04
Bone 1.09E-Ol 25 4.37E-03-
Avrr.Lung 1.88E-02 25 7.54E-04
Bronchi 4.23E-05 no limit given -
34489-10 ..-FINAL -April 2008 6-16 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE 6.1-8 (Cont'd)
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(COLORADO PLATEAU ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction of
GrouD (mrem!vr)_(mr".,!,{~Limit
Infant Effective 2.2IE-02 25 8.83E-04
Bone 7.69E-02 25 3.07E-03---_._--
Avg.Lung 2.39E-02 25 9.55E-04
Bronchi 3.49E-05 no limit given -
Child Effective 9.22E-03 25 3.69E-04
Bone 5.37E-02 25 2.15E-03
Avg.Lung 2.68E-02 25 l.07E-03
Blanding Bronchi 3.49E-05 no limit given -
Teenage Effective l.06E-02 25 4.23E-04
Bone 1.8IE-OI 25 7.24E-03
Avt!.LUI1rr 2.04E-02 25 8.18E-04
Bronchi 3.49E-05 no limit given -
Adult Effective 6.37E-03 25 2.55E-04
Bone 8.15E-02 25 3.26E-03
Avg.Lnng 1.39E-02 25 5.56E-04
Bronchi 3.49E-05 no limit given -
From Table 6.1-8,the 40 CFR 190 annual dose commitments are at most 18.8%(dosc to the
bone for the teenage at BHV-1)ofthe 40 CFR 190 dose criterion of25 mrem/yr.In addition,the
40 CFR 190 annual effective dose commitments demonstrate compliance with the R313-15-
101(4)(10 CFR 20.1101(d))ALARA goal of 10 mrem/yr to the individual member of the public
likely to receive the highest total effective dose equivalent.The maximum total effective dose
equivalent was 0.540 mrem/yr (infant at BHV-l),or 5.4%of the 10 mrem/yr goal.
In addition,Table 6.1-9 presents a summary of the 40 CFR 190 annual dose commitments from
the meat ingestion pathway for Grazing Locations 1 and 2.As before,in the unlikely event a
receptor were to eat meat from cattle grazing in areas I or 2,the total dose would remain well
below regulatory limits.
34489-10·-FINAL·April 2008 6-17 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.1-9
PHASE 2-40 CFR 190 ANNUAL DOSE COMMITMENTS)FOR MEAT INGESTION
PATHWAY (COLORADO PLATEAU ORE)(mremlyr)
Location Age Group Oman"
Effectivel\Bonel\Avg.Lung'
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Graziug Location I Child I.07E-02 5.35E-02 4.87E-02
Teeuage I.68E-02 2.78E-OI 4.26E-02
Adult I.22E-02 I.50E-OI 3.5IE-02
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 2 Child 6.7IE-04 3.32E-03 2.80E-03
Teenage I.03E-03 I.75E-02 2.46E-03
Adult 7.39E-04 9.20E-03 2.03E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
b)Exclusive ofradon.
The annual doses to the population estimated within 50 miles (80 km)ofthe site are provided in
Table 6.1-10.
TABLE 6.1-10
PHASE 2-ANNUAL POPULATION DOSE COMMITMENTS WITHIN 50 MILES
(80 km)OF THE MILL FOR COLORADO PLATEAU ORE
ANNUAL POPULATION DOSE COMMITMENTS,
Organ PERSON-REM PER YEAR
Mill Operatious
Effective I.50E-OI
Bone 1.15E+OO
Avg.Lung I.56E-O I
Bronchi 8.66E+OO
The population dose arising from processing Colorado Plateau ore during Phase 2 is estimated at
0.15 person-rem.This can be compared to the dose from natural background sources of
radiation ofabout 360 mrem/yr as previously discussed in Phase 1.
The current population ofSan Juan County is about 14,400 people.Assuming everyone living in
San Juan County receives an annual dose of (about)360 mrem/yr,then the total dose due to
natural background is approximately 5184 person-rem.The theoretical incremental dose of
0.15 person-rem is clearly inconsequential by comparison.
34489-10 -FINAL -April 2008 6-18 SENES Consultants Limited
Proposed Development o/New Tailings Ce1l4Bfor White Mesa Uranium Mill
6.2 MILDOS-AREA RESULTS FOR ARIZONA STRIP ORE
The potential annual doses to the people living close to the mill and to the population living
within 50 miles (80 km)as a result of processing Arizona Strip ore was calculated using
MILDOS-AREA.
The MILDOS-AREA calculated total annual dose commitments (including radon)and 40 CFR
190 total annual dose commitments for processing of Arizona Strip ore are provided in
Sections 6.2.1 and 6.2.2,respectively.
6.2.1 R313-15-301 (l)(a)Regulatory Compliance
The MILDOS-AREA calculated total annual dose commitments (including radon)for Phases 1
and 2 are provided in this section.These doses are regulated by R313-15-30I(l)(a)which
requires that the dose to an individual member of the public shall not exceed 100 mrem/yr (radon
included).
Phase 1
Table 6.2-1 presents a summary ofthe individual dose commitments for the residential receptors
for the age group ofinfant,child,teenage and adult for Phase I.
34489-10 -FINAL -Apl'il2008 6-19 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
TABLE 6.2-1
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Age Estimated Applicable Limit FractionLocationOrganDoseGroup(mrem/yr)(mrem/yr)of Limit
infant Effective 3.12E+00 100 3.12E-02
Bone 4.86E+00 --
Avg.Lung I.34E+00 --
Bronchi 2.72E+Ol --
Child Effective 2.32E+00 100 2.32E-02
Bone 3.48E+00 --
Avg.Lung 1.79E+00 --
Nearest Potential Bronchi 2.72E+Ol --
Resident (BHV-l)~_nage Effective 2.43E+00 100 2.43E-02
Bone l.23E+Ol --
Avg.Lung 1.43E+00 --
Bronchi 2.72E+Ol --
Adult Effective 2.14E+00 100 2.14E-02
Bone 5.42E+00 --
Avg.Lung 9.94E-Ol --
Bronchi 2.72E+Ol --
Infant Effective 6.60E-Ol 100 6.60E-03
Bone 7.65E-Ol --
Avg.Lung 2.58E-Ol ---
Bronchi 6.93E+00 --
Child Effective 5.46E-Ol 100 5.46E-03
Bone 5.80E-Ol ----
Avg.Lung 3.17E-Ol --
Nearest Historical Bronchi 6.93E+00 --
Resident (BHV-2)Teenage Effective 5.63E-Ol 100 5.63E-03
Bone I.92E+OO --
Avg.Lung 2.55E-Ol --
Bronchi 6.93E+00 --
Adult Effective 5.19E-Ol 100 5.19E-03
Bone 8.85E-Ol --
Avg.Lung 1.85E-Ol --
Bronchi 6.93E+00 --
34489-10 --FINAL-April 2008 6-20 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.2-1 (Cont'd)
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Age Estimated Applicable Limit FractionLocatiollOrgallDoseGroupImrem/vr)(mrem/yr)ofLimit
Illfallt Effective 1.96E+00 100 1.96E-02
Balle 2.86E+00 --
Aw.LUllg
..__.
7.91E-OI --
Bronchi 1.81E+01 --
Child Effective 1.50E+00 100 1.50E-02
Balle 2.05E+00 --
Avo.LUll"1.06E+00 --
Nearest Actual Bronchi 1.81E+OI --
Residellt Teella~e Effective 1.56E+00 100 1.56E-02
Boue 7.18E+00 --
Avo.Luu"8.50E-01 --
Bronchi 1.8IE+OI ---
Adult Effective 1.40E+00 100 1.40E-02
Balle 3.I8E+00 --
Aw.LUII~5.96E-OI --
Bwuchi 1.81E+01 --
Illfallt Effective 4.68E-OI 100 4.68E-03
Bone 3.5IE-OI --
Aw.Luu~1.56E-OI --
BWllchi 5.72E+00 --
Child Effective 4.16E-OI 100 4.16E-03
Bone 2.53E-01 ----
Avo.LUll"1.46E-01 --
White Mesa Bronchi 5.72E+00 --
Community Teenao-e Effective 4.19E-01 100 4.19E-03-
Balle 6.90E-OI --
Av".LUll"1.16E-OI --
Bronchi 5.72E+00 --
Adult Effective 4.04E-OI 100 4.04E-03
Balle 3.5IE-OI --
Av".Lun"9.18E-02 --
Bronchi 5.72E+00 --
34489-10·--FINAL -April 2008 6-21 SENES Consultants Limited
Proposed Development o/New Tailings Ce1l4B/or White Mesa Uranium M:.cil:..-l _
TABLE 6.2-1 (Cont'd)
PHASE I-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Age Estimated Applicable Limit FractionLocationOrganDoseGroup(mrem/vrl (mrem/yr)of Limit
Infant Effective 2.18E-OI 100 2.I8E-03
Bone 2.20E-0 I ---
Avg.Lung 7.98E-02 ---
Bronchi 2.39E+00 --
~Id Effective l.8SE-OI 100 l.8SE-03
Bone l.64E-OI --
Avg.Lung 9.22E-02 --
Blanding Bronchi 2.39E+00 --
Teenage Effective l.89E-OI 100 l.89E-03
Bone S.16E-OJ -----
Avg.Lung 7.49E-02 --
Bronchi 2.39E+00 --
Adult Effective l.78E-OI JOO l.78E-03
Bone 2.44E-OI --
Avg.Lung S.64E-02 --
Bronchi 2.39E+00 --
From Table 6.2-I,the total annual effective dose commitments are at most 3.I%(effective dose
for infant at BHV-I)of the R313-15-30I(l)(a)limit of 100 mrem/yr (radon included)to an
individual member of the public.Therefore,the predicted annual effective dose commitments
comply with R3 I3-15-I0I(I)(a).
In addition,Table 6.2-2 presents a summary of the annual dose commitments fi·om the meat
ingestion pathway for Grazing location I and 2.As before in the unlikely event that a receptor
consumed beef from one of the grazing locations,the total dose would remain well below
regulatory limits.
34489~IO -FINAL -April 2008 6-22 SENES Consultants Limited
____P_ro""'P'-'o-'-s-'-ecj Development o/New Tailings Cell 4B jor White Mesa Uranium Mill
TABLE 6.2-2
PHASE I-TOTAL ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (ARIZONA STRIP ORE)(mrem/yr)
Location Age Group Orgau"
Effective'Boneft Avg.Lung'
Infant O.OOE+OO O.OOE+OO 0.00£+00
Child 2.75E-02 1.37E-OI 1.25E-OIGrazingLocationITeenage4.33E-02 7.16E-OI 1.09E-OI
Adult 3.13E-02 3.87E-01 9.03E-02
Infant 0.00£+00 0.00£+00 0.00£+00
Grazing Location 2 Child 1.87E-03 9.29E-03 7.93E-03
Teenage 2.90E-03 4.89E-02 6.94E-03
Adult 2.07E-03 2.57E-02 5.73E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
Phase 2
Table 6.2-3 presents a summary of the individual dose commitments for the residential receptors
for the age group ofinfant,child,teenage and adult for Phase 2.
TABLE 6.2-3
PHASE 2-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Age Estimated Applicable Limit FractionLocationOrganDoseGroup(mrem/yr)(mrem/yr)of Limit
Infant Effective 3.IOE+00 100 3.IOE-02
Bone 4.81£+00 - -
Avg.Lung I.3IE+OO --
Bronchi 2.70E+OI --
Child Effective 2.30E+00 100 2.30E-02
Bone 3.42E+00 --
Avg.LU1:'jL 1.74£+00 - -
Nearest Potential Bronchi 2.70E+01 --
Resident (BHV-1)Teenage Effective 2.40£+00 100 2.40E-02
Bone 1.21E+01 --
Avg.Lung 1.40E+00 --
_I3ronchi 2.70E+OI -----
Adult Effective 2.12£+00 100 2.12E-02
Bone 5.3IE+00 --
Avg.Lung 9.7IE-OI --
Bronchi 2.70E+01 --
34489-10 "_.FINAL-April 2008 6-23 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 48for White Mesa Uranium Mill-------
TABLE 6.2-3 (Cont'd)
PHASE 2-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Group (mrem/Vl')'(mrem/vr)of Limit
Infant Effective 6.59E-OI 100 6.59E-03-
Bone 7.60E-OI --
Avg.2.56E-0I --Lung ....._-
Bronchi 6.93E+00 ----
Child Effective 5A5E-OI 100 5A5E-03
Bone 5.75E-OI --
Avg.3.14E-OI --Lung
Nearest Historical Bronchi 6.93E+OO --
Resident (BHV-2)Teenage Effective 5.62E-OI 100 5.62E-03
Bone 1.91E+00 --
Avg.2.52E-OI --Lung
Bronchi 6.93E+00 --
Adult Effective 5.18E-OI 100 5.18E-03
Bone 8.76E-OI --
Avg.1.84E-OI --Lung
Bronchi 6.93E+00 --f---
Infant Effective 1.95E+00 100 1.95E-02
Bone 2.83E+00 --
Avg.7.77E-OI --Lung
Bronchi 1.80E+OI --
Child Effective 1.49E+OO 100 1.49E-02
Bone 2.02E+OO --
Avg.1.03E+00 --Lung
Nearest Actual Bronchi 1.80E+OI --
Resident Teenage Effective 1.55E+00 100 1.55E-02
Bone 7.06E+00 --
Avg.8.32E-OI --Lung
Bronchi 1.80E+OI --
Adult Effective 1.39E+00 100 1.39E-02
Bone 3.13E+00 --
Avg.5.84E-0 I --Lung
Bronchi 1.80E+OI --
34489·!0-FINAL -April 2008 6-24 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mil~_
TABLE 6.2-3 (Cont'd)
PHASE 2-COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE
RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Location Age Ol"gan Estimated Dose Applicable Limit Fraction
CI"OnD (ml"em!vl"j (ml"em!vl"j of Limit
Infant Effective 4.69E-Ol 100 4.69E-03-_.__.---
Bone 3.49E-0 I --
Avg.1.55E-Ol --
._..._._--.1.unL_------_._....._----_.---_.._._.--
Bronchi 5.75E+00 --
Child Effective 4.l7E-Ol 100 4.17E-03
Bone 2.52E-Ol --
Avg.1.45E-Ol --Lung
White Mesa Bronchi 5.75E+00 --
Community Teenage Effective 4.20E-Ol 100 4.20E-03
Bone 6.85E-Ol --
Avg.l.l5E-Ol --Lung
Bronchi 5.75E+00 --
Adult Effective 4.05E-Ol 100 4.05E-03
Bone 3.48E-Ol --
Avg.9.l4E-02 --Lung
Bronchi 5.75E+00 --
Infant Effective 2.l9E-Ol 100 2.l9E-03
Bone 2.20E-Ol --
Avg.7.98E-02 --Lung
Bronchi 2.40E+00 --
Child ~!ective 1.86E-Ol 100 1.86E-03-----
Bone 1.64E-Ol --
Avg.9.22E-02 --
-----Lung .1---
Blanding Bronchi 2.40E+00 --
Teenage Effective 1.90E-Ol 100 1.90E-03
Bone 5.l5E-Ol --
Avg.7.49E-02 --Lun"
Bronchi 2.40E+00 --
Adult Effective 1.79E-Ol 100 1.79E-03
Bone 2.44E-Ol -1--------_._.--_._----------Avg.5.65E-02 --Lun"
Bronchi 2.40E+00 --
34489-10 -FINAL-April 2008 6-25 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
From Table 6.2-3,the total annual effective dose commitments are at most 3.1 %(effective dose
for infant at BHV-l)of the R313-15-30I(l)(a)limit of 100 mrem/yr (radon included)to an
individual member of the public.Therefore,the predicted annual effective dose commitments
comply with R313-15-1 Ol(l)(a).
In addition,Table 6.2-4 presents a summary of the annual dose commitments from the meat
ingestion pathway for Grazing location I and 2.As before in the unlikely event that a receptor
consumed beef from one of the grazing locations,the total dose would remain well below
regulatory limits.
TABLE 6.2-4
PHASE 2-TOTAL ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (ARIZONA STRIP ORE)(mremlyr)
Location Age Group Organb
EffectiveR Bonea Avg.Lung'
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 1 Child 2.73E-02 1.36E-OI 1.24E-OI
Teenage 4.29E-02 7.IOE-OI 1.08E-OI
Adult 3.IOE-02 3.83E-OI 8.94E-02
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 2 Child 1.71E-03 8.50E-03 7.18E-03
Teenage 2.65E-03 4.48E-02 6.28E-03
Adult 1.89E-03 2.35E-02 5.18E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
6.2.2 40 CFR 190 Regulatory Compliance
MILDOS-AREA calculated 40 CFR 190 doses (excludes radon).These doses are regulated by
the 40 CFR 190 criterion of 25 mrem/yr to the whole body (excluding the dose due to radon)
(EPA 2002)or to any organ of the body.The 40 CFR 190 doses are also used to demonstrate
compliance with R313-15-101(4)(10 CFR 20.1101(d)).The licensee must demonstrate as an
ALARA goal,that total effective dose equivalent to the individual member ofthe public likely to
receive the highest total effective dose equivalent will not exceed 10 mrem/yr (absent of the
radon dose).
Phase 1
Table 6.2-5 presents a summary ofthe 40 CFR 190 individual dose commitments for residential
receptors for the age group ofinfant,child,teenage and adult for Phase I.
34489-10 ~FINAL -April 2008 6-26 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE 6.2-5
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Gronn (mrem!vr)'(mrem!vr\of Limit
Infant Effective 1.39E+OO 25 5.55E-02
Bone 4.76E+OO 25 1.90E-Ol -
Avg.1.24E+OO 25 4.95E-02Lung
Bronchi 2.48E-03 no limit given -
Child Effective 5.92E-O 1 25 2.37E-02---
Bone 3.37E+OO 25 1.35E-Ol
Avg.1.69E+OO 25 6.74E-02Lung
Nearest Potential Bronchi 2.48E-03 no limit given -
Resident (BHV-I)Teenaae Effective 7.03E-Ol 25 2.8lE-02
Bone l.22E+Ol 25 4.88E-O!
Avg.l.33E+OO 25 5.3lE-02Lung
Bronchi 2.48E-03 no limit given -
Adult Effective 4.l4E-Ol 25 1.66E-02
Bone 5.32E+OO 25 2.!3E-Ol
Avg.8.93E-Ol 25 3.57E-02Lung
Bronchi 2.48E-03 no limit given -..-
Infant Effective 2.06E-Ol 25 8.24E-03
Bone 7.20E-Ol 25 2.88E-02
Avg.2.l8E-O!25 8.73E-03Lung
Bronchi 3.54E-04 no limit given -
Child Effective 9.l9E-02 25 3.68E-03
Bone 5.32E-Ol 25 2.13E-02
Avg.2.73E-Ol 25 1.09E-02Lung
Nearest Historical Bronchi 3.54E-04 no limit given -
Resident (BHV-2)Teenage Effective 1.09E-Ol 25 4.34E-03
Bone 1.86E+OO 25 7.44E-02
Avg.2.llE-Ol 25 8.44E-03Lung
Bronchi 3.54E-04 no limit given -
Adult Effective 6.49E-02 25 2.60E-03
Bone 8.30E-O I 25 3.32E-02
Avg.1.43E-O I 25 5.73E-03LUlla
Bronchi 3.54E-04 no limit given -
34489-10 -FINAL-April 2008 6-27 SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
TABLE 6.2-5 (Cont'd)
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
GrouD (mrem/vr)(mrem/vrl ofLimit
Infant Effective 8.11E-Ol 25 3.24E-02
Boue 2.79E+00 25 LlIE-OI
Avg.7.16E-Ol 25 2.86E-02Lung
Bronchi 1.44E-03 no limit given ._-
Child Effective 3.44E-Ol 25 1.38E-02
Bone 1.97E+00 25 7.88E-02
Avg.9.78E-Ol 25 3.91E-02Lung
Nearest Actual Bronchi 1.44E-03 no limit given -
Resident Teenage Effective 4.09E-Ol 25 I.64E-02
Bone 7.09E+00 25 2.83E-Ol
Avg.7.71E-Ol 25 3.08E-02Lung
Bronchi 1.44E-03 no limit given -
Adult Effective 2.41E-Ol 25 9.64E-03
Bone 3.09E+00 25 1.24E-Ol
Avg.5.17E-Ol 25 2.07E-02Lung
Bronchi 1.44E-03 n~limit given -
Infant Effective 8.58E-02 25 3.43E-03
Bone 3.02E-Ol 25 1.21 E-02
Avg.Ll6E-01 25 4.64E-03Lung
Bronchi 1.08E-04 no limit ~iven ---_.
Child Effective 3.33E-02 25 1.33E-03
Bone 1.99E-0 I 25 7.95E-03
Avg.9.80E-02 25 3.92E-03Lung
White Mesa Bronchi 1.08E-04 no limit given -
Community -
Teenage Effective 3.51E-02 25 1.41 E-03
Bone 5.90E-0 I 25 2.36E-02
Avg.6.92E-02 25 2.77E-03Lung
Bronchi 1.08E-04 no limit given -
Adult Effective 2.21E-02 25 8.85E-04
Bone 2.82E-Ol 25 Ll3E-02
Avg.4.87E-02 25 1.95E-03
--Lung
Bronchi 1.08E-04 no limit given -
34489-10 -FINAL-April 2008 6-28 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE 6.2-5 (Cont'd)
PHASE I-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Gronp (mrem/yr)(mrem/yr)ofLimit
Infant Effective 5.64E-02 25 2.26E-03
Bone 1.96E-O I 25 7.83E-03
Avg.6.08E-02 25 2.43E-03Lung
Bronchi 8.89E-05 no limit given -
Child Effective 2.35E-02 25 9.4!E-04
Bone 1.37E-O!25 5.48E-03
Avg.6.86E-02 25 2.74E-03Lung
Blanding Bronchi 8.89E-05 no limit given -
Teenage Effective 2.70E-02 25 1.08E-03
Bone 4.62E-O!25 1.85E-OZ-
Avg.5.20E-02 25 2.08E-03Lung
Bronchi 8.89E-05 no limit given -
Adult Effective 1.63E-02 25 6.50E-04
Bone 2.08E-O!25 8.32E-03
Avg.3.55E-02 25 1.42E-03Lung
Bronchi 8.89E-05 no limit given -
From Table 6.5-2,the 40 CFR 190 annual dose eommitments are at most 48.8%(dose to the
bone for the teenage at SHV-I)ofthe 40 CFR 190 dose eriterion of25 mrem/yr.In addition,the
40 CFR 190 annual effeetive dose eommitments demonstrate eomplianee with the R313-15-
101(4)(10 CFR 20.1101(d»ALARA goal of 10 mrem/yr to the individual member ofthe publie
likely to reeeive the highest total effeetive dose equivalent.The maximum total effeetive dose
equivalent was 1.39 mrem/yr (infant at SHV-I),or 13.9%ofthe 10 mrem/yr goal.
In addition,Table 6.2-6 presents a summary of the 40 CFR 190 annual dose eommitments from
the meat ingestion pathway for Grazing loeation I and 2.As before in the unlikely event that
someone was to eonsume beef from grazing area I or 2,the total dose would be small and well
below regulatory limits.
34489-I0 -FINAL-April 2008 6-29 SENES Consultants Limited
P!oposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
TABLE 6.2-6
PHASE 1-40 CFR 190 ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (ARIZONA STRIP ORE)(mrem/yr)
Location Age Group Organ
Effective"Bonea Avg.Lnng"
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 1 Child 2.75E-02 1.37E-OI 1.25E-OI
Teenage 4.33E-02 7.16E-OI 1.09E-OI
Adult 3.13E-02 3.87E-OI 9.03E-02
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 2 Child 1.87E-03 9.27E-03 7.90E-03
Teenage 2.88E-03 4.87E-02 6.92E-03
Adult 2.06E-03 2.57E-02 5.7IE-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
b)Exclusive ofradon.
The annual doses to the population estimated within 50 miles (80 km)ofthe site are provided in
Table 6.2-7.
TABLE 6.2-7
PHASE I-ANNUAL POPULATION DOSE COMMITMENTS WITHIN 50 MILES
(80 km)OF THE MILL FOR ARIZONA STRIP ORE
ANNUAL POPULATION DOSE COMMITMENTS,
Organ PERSON-REM PER YEAR
Mill Operations
Effective 3.08E-01
Bone 2,48E+00
Avg.Lung 3.28E-OI
Bronchi 1.64E+01 ._-
The population dose arising from processing Arizona Strip ore during Phase I is estimated at
0.31 person-rem.This can bc compared to the dose from natural background sources of
radiation ofabout 360 mrem/yr as previously discussed.
The CUtTent population of San Juan County is about 14,400 people.Assuming everyone living in
San Juan County receives an annual dose of (about)360 mrem/yr,then the total dose due to
natural background is approximately 5184 person-rem.The theoretical incremental dose of
0.31 person-rem is clearly inconsequential by comparison.
34489~IO -FINAL -April 2008 6-30 SENES Consultants Limited
Proposed Development o/New Tailings Ce1l4B/or White Mesa Uranium Mill
Phase 2
Table 6.2-8 presents a summary of the 40 CFR 190 individual dose commitments for residential
receptors for the age group of infant,child,teenage and adult for Phase 2.
TABLE 6.2-8
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Allplieable Limit Fraction
Gronp (mrem!vr)(mrem!vr)ofLimit
Infant Effective l.38E+OO 25 5.50E-02
Bone 4.7IE+OO 25 1.88E-OI•.
Avg.l.2IE+OO 25 4.84E-02Lunrr
Bronchi 2.45E-03 no limit given ..-
Child Effective 5.81 E-O I 25 2.32E-02
Bone 3.3IE+OO 25 l.32E-OI
Avg.I.64E+OO 25 6.58E-02Lung
Nearest Potential Bronchi 2.45E-03 no limit given -
Resident (BHV-I)Teenage Effective 6.89E-Ol 25 2.76E-02
Bone 1.20E+Ol 25 4.79E-OI
Avg.1.29E+OO 25 5.18E-02Lung
Brouchi 2.45E-03 no limit given -
Adult Effective 4.05E-OI 25 1.62E-02
Bone 5.21E+OO 25 2.08E-OI_.-
Avg.8.7IE-Ol 25 3.48E-02Lung
Bronchi 2.45E-03 no limit given --
34489-10 -FINAL -April 2008 6-31 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium M!."'ll _
TABLE 6.2-8 (Cont'd)
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fl'action
Grouo (mrem/vr)(mrem/vr)of Limit
Infant Effective 2.05E-Ol 25 8.20E-03
Bone 7.16E-OI 25 2.86E-02.•.
Avg.2.16E-OI 25 8.64E-03Lung
Bronchi 3.53E-04 no limit given -
Child Effective 9.11 E-02 25 3.64E-03
Bone 5.27E-0I 25 2.11E-02
Avg.2.70E-Ol 25 1.08E-02Lung
Nearest Historical Bronchi 3.53E-04 no limit give:l -
Resident (BHV-2)Teenage Effective 1.07E-OI 25 4.30E-03
Bone 1.84E+00 25 7.38E-02
Avg.2.09E-OI 25 8.35E-03Lung
Bronchi 3.53E-04 no limit given -
Adult Effective 6.42E-02 25 2.57E-03
Bone 8.22E-OI 25 3.29E-02
Avg.1.42E-OI 25 5.66E-03Lu'!.8
Bronchi 3.53E-04 no limit given -
Infant Effective 8.04E-OI 25 3.22E-02
Bone 2.76E+00 25 1.10E-Ol
Avg.7.02E-Ol 25 2.81E-02Lung
Bronchi 1.42E-03 not limited -_.
Child Effective 3.39E-OI 25 1.35E-02
Bone 1.94E+00 25 7.74E-02
Avg.9.57E-Ol 25 3.83E-02Lung
Nearest Actual Bronchi 1.42E-03 not limited -
Resident Teenage Effective 4.02E-OI 25 1.61E-02
Bone 6.97E+00 25 2.79E-OI
Avg.7.54E-OI 25 3.02E-02Lung
Bronchi 1.42E-03 not limited -
Adult Effective 2.36E-Ol 25 9.46E-03
Bone 3.03E+00 25 1.21E-Ol
Avg.5.06E-OI 25 2.02E-02Lung
Bronchi 1.42E-03 not limited -
34489-10 -FINAL -April 2008 6-32 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE 6.2-8 (Cont'd)
PHASE 2-COMPARISON OF 40 CFR 190 ANNUAL DOSE COMMITMENTS WITH
APPLICABLE RADIATION PROTECTION STANDARDS
(ARIZONA STRIP ORE)
Location Age Organ Estimated Dose Applicable Limit Fraction
Group (mrem/vr)(mrem/vr)ofLimit
Infant Effective 8.53E-02 25 3.4IE-03-
Bone 3.00E-OI 25 I.20E-02
Avg.I.l5E-Ol 25 4.59E-03Lung
Bronchi I.08E-04 not limited -
Child Effective 3.30E-02 25 I.32E-03.-
Bone I.97E-Ol 25 7.87E-03
Avg.9.68E-02 25 3.87E-03Lung
White Mesa Bronchi I.08E-04 not limited -
Community Teenage Effective 3.48E-02 25 I.39E-03
Bone 5.85E-OI 25 2.34E-02
Avg.6.83E-02 25 2.73E-03Lung
Bronchi I.08E-04 not limited -
Adult Effective 2.19E-02 25 8.75E-04
Bone 2.79E-OI 25 I.I2E-02
Avg.4.8lE-02 25 I.92E-03Lung
Bronchi I.08E-04 not limited -
Infant Effective 5.64E-02 25 2.26E-03
Bone I.96E-Ol 25 7.82E-03
Avg.6.07E-02 25 2.43E-03Lung_.
Bronchi 8.88E-05 not limited -
Child Effective 2.35E-02 25 9.40E-04..-
Bone I.37E-Ol 25 5.47E-03
Avg.6.84E-02 25 2.74E-03Lung
Blanding Bronchi 8.88E-05 not limited -
Teenage Effective 2.70E-02 25 I.08E-03
Bone 4.6lE-Ol 25 I.85E-02
Avg.5.l9E-02 25 2.08E-03Lung
Bronchi 8.88E-05 not limited -
Adult Effective I.62E-02 25 6.49E-04
Bone 2.08E-Ol 25 8.3 IE-O:i-
Avg.3.55E-02 25 I.42E-03Lung
Bronchi 8.88E-05 not limited -
34489-10·-FINAL -Apri12008 6-33 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa UranzC'-·u:.:.:m:.:.:M:.:.:C'-ilC'-I _
From Table 6.2-8,the 40 CFR 190 annual dose commitments are at most 48%(dose to the bone
for the teenage at BHV-I)of the 40 CFR 190 dose criterion of 25 mrem/yr.In addition,the
40 CFR 190 annual effective dose commitments demonstrate compliance with the R313-15-
101(4)(10 CFR 20.1101 (d))ALARA goal of 10 mrem/yr to the individual member of the public
likely to receive the highest total effective dose equivalent.The maximum total effective dose
equivalent was 1.38 mrem/yr (infant at BHV-I),or 13.8%ofthe 10 mrem/yr goal.
In addition,Table 6.2-9 presents a summary of the 40 CFR 190 annual dose commitments from
the meat ingestion pathway for Grazing location I and 2.As before in the unlikely event that
someone was to consume beef from grazing area I or 2,the total dose would be small and well
below regulatory limits.
TABLE 6.2-9
PHASE 2-40 CFR 190 ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION
PATHWAY (ARIZONA STRIP ORE)(mremlyr)
Location Age Group Organ
Effective'Ronca AVI'.Lnnl!'
Infant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location I Child 2.73E-02 l.36E-OJ l.24E-OI
Teenage 4.29E-02 7.10E-OJ l.08E-OI
Adult 3.10E-02 3.83E-OI 8.94E-02
Jnfant O.OOE+OO O.OOE+OO O.OOE+OO
Grazing Location 2 Child l.71E-03 8A8E-03 7.J4E-03
Teenage 2.63E-03 4A6E-02 6.25E-03
Adult l.88E-03 2.35E-02 5.17E-03
Note:
a)Assumes cattle will graze at the particular Grazing location for 2 months ofthe year.
b)Exclusive ofradon.
The annual doses to the population estimated within 50 miles (80 km)of the site are provided in
Table 6.2-10.
TABLE 6.2-10
PHASE 2-ANNUAL POPULATION DOSE COMMITMENTS WITHIN 50 MILES
(80 km)OF THE MILL FOR ARIZONA STRIP ORE
ANNUAL POPULATION DOSE COMMITMENTS,
Organ PERSON-REM PERYEAR
-Mill Operations
Effective 3.15E-OI
Bone 2.55E+OO
Avg.Lung 3.34E-OI
Bronchi l.65E+OI
34489-10 -FINAL-April 2008 6-34 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
The population dose arising from processing Arizona Strip ore during Phase 2 is estimated at
0.32 person-rem.This can be compared to the dose from natural background sources of
radiation in the Colorado Plateau of about 360 mrem/yr as previously discussed.
The current population ofSan Juan County is about 14,400 people.Assuming everyone living in
San Juan County receives an annual dose of (about)360 mrem/yr,then the total dose due to
natural background is approximately 5184 person-rem.The theoretical incremental dose of
0.32 person-rem is clearly inconsequential by comparison.
34489·10 -FINAL·April 2008 6-35 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
7.0 KEY OBSERVATIONS
As described in Section 1.0,milling of conventional ore is scheduled for the Spring of 2008
when the milling of currently available alternate feed materials is completed (OUSA 2007a).
The objective of this dose assessment was to extend the previous report (SENES 2007)to
incorporate the dose from the proposed development of new tailings cell 4B,in support of a
license amendment application for the construction and operation ofthat cell.
The NRC-approved MILOOS-AREA was used to estimate the dose commitments received by
individuals and the general population within a 50 mile (80 km)radius of the site for the
processing of Colorado Plateau or Arizona Strip ore separately.In each scenario,the doses
arising from the emissions of dust and radon from the mill area and ore pads were assumed to be
the same as in the previous 2007 report since the scenarios both involve the processing of
Colorado Plateau and Arizona Strip ores.Therefore,MILOOS-AREA runs from the previous
repOlt were revised to exclude the tailings cells.The doses from the tailings cells were estimated
in separate MILOOS-AREA runs and added to the dose from the mill area and ore pads.Table
7-1 provides a summary of the source telms included in Phases I and 2.
TABLE 7-1
SOURCE TERMS INCLUDED IN PHASES 1 AND 2
Source Term Phase 1 Phase 2
Mill area included included
Ore Pads included included
Tailings Cell 2 with Interim Soil Cover included included
Tailings Cell 3 active interim soil cover
Tailings Ce1l4A active active
Tailings Ce1l4B excluded active
The wind erosion and radon release rates from the tailings cells (active and with interim soil
cover)were modelled by using a maximal worst case approach.
Each active tailings cell was modelled to have an active exposed (non-solution)tailings solids
area of 10 acres (Le.,the maximum uncovered tailings solids area at any time allowed under
NESHAPs Regulation 40 CFR 61.252(b),Subpart W)since it is not possible to predict the
distribution of uncovered tailings between the active cells at any given time.As a result,the
release rate of wind-eroded tailings dust was estimated at 10 acres at all times for each active
cell.The total annual radon release rate was estimated by assuming a radon release rate of 20
pCi/m2s (i.e.,maximum radon-222 emissions to ambient air from an existing uranium mill pile)
over the entire area ofeach cell consistent with NESHAPs.
The tailings cells (2 and 3)with interim soil cover were assumed to be the entire areas of each
cell;however,only radon is released at a rate of 10 pCi/m2s after the application of the soil
cover.
34489~IO -FINAL-April 2008 7-1 SENES Consultants Limited
Proposed Development o/New Tailings Ce1l4B/or White Mesa Uranium Mill
The calculated total annual effective dose commitments (including radon)calculated using
MILDOS-AREA were compared to the Utah Administrative Code R313-15-301(1)(a)
requirement that the dose to individual members of the public shall not exceed 100 mrem/yr
(radon included).For processing of Colorado Plateau ore,the maximum total annual effective
dose commitments was calculated to be a maximum of 1.4 mrem/yr for an infant at the nearest
potential resident,BHV-I (Tables 6.1-1 and 6.1-3)(i.e.,effective dose)and is about 1.4%ofthe
R313-15-30I(l)(a)limit of 100 mrem/yr (radon included)to an individual member of the public
for Phases I and 2.For processing of Arizona Strip ore,the total annual effective dose
commitments were calculated to be a maximum of 3.1 mrem/yr for an infant at the nearest
potential resident,BHV-I (Tables 6.2-1 and 6.2-3)(i.e.,effective dose)and is about 3.1%ofthe
100 mrem/yr limit (radon included)to an individual member of the public for Phases I and 2.
Overall,using conservative assumptions,the predicted annual effective dose commitments for
Phases I and 2 comply with R313-15.
In addition,our MILDOS-AREA calculated 40 CFR 190 annual dose commitments (excluding
radon)were compared to the 40 CFR 190 criterion,which is 25 mrem/yr to the whole body
(excluding the dose due to radon)and 25 mrem/yr to any other organ to any member of the
public (EPA 2002).The 40 CFR 190 doses were also used to demonstrate compliance with the
ALARA goal set out in R313-15-101(4)(10 CFR 20.1101(d))(i.e.,the ALARA goal is to
demonstrate that total effective dose equivalent to the individual member of the public likely to
receive the highest total effective dose equivalent will not exceed 10 mrem/yr (absent of the
radon dose)).For processing of Colorado Plateau ore,the 40 CFR 190 annual dose
commitments were calculated to be a maximum of 4.8 mrem/yr for a teenager at the nearest
potential resident,BI-IV-I (Tables 6.1-5 and 6.1-8)(i.e.,dose to the bone)and is about 19%of
the 40 CFR 190 dose criterion of 25 mrem/yr,for Phases I and 2.Further,the 40 CFR 190
annual effective dose commitments demonstrate compliance with the R313-15-101(4)(10 CFR
20.IIOI(d))ALARA goal of 10 mrem/yr to the individual member of the public likely to receive
the highest total effective dose equivalent (the maximum total effective dose equivalent (radon
excluded)during Phases I and 2 was 0.545 mrem/yr for an infant at BHV-I).For Arizona Strip
ore,the 40 CFR 190 annual dose commitments were at most 12 mrem/yr for a teenage at the
nearest potential resident,BHV-I (Tables 6.2-5 and 6.2-8)(i.e.,dose to the bone)and is about
49%of the 40 CFR 190 dose criterion of 25 mrem/yr for Phases I and 2.Further,the 40 CFR
190 annual effective dose commitments demonstrate compliance with the R313-15-101(4)(10
CFR 20.1101(d))goal of 10 mrem/yr to the individual member of the public likely to receive the
highest total effective dose equivalent (the maximum total effective dose equivalent (radon
excluded)during Phases I and 2 was 1.39 mrem/yr for an infant at BHV-I).Overall,using
conservative assumptions,ore processing in Phases I and 2 comply with the requirements of 40
CFR 190 and the ALARA goal set out in R313 -15-101(4).
34489-10-FINAL-April 2008 7-2 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
8.0 REFERENCES
Argonne National Laboratory (ANL)1998a.MILDOS-AREA,Version 2.2013,Developed at the
Environmental Assessment Division
Argonne National Laboratory (ANL)1998b.
Environmental Assessment Division
MILDOS-AREA User's Guide (Draft),
Code of Federal Regulations (CFR)Title 10 Part 20 Standardsfor Protection Against Radiation.
May.
Dames &Moore 1978.Environmental Report:White Mesa Uranium Project San Juan County,
Utah for Energy Fuels Nuclear,Inc.January.
Denison Mines (USA)Corp.(DUSA)2007a.Press Release:Denison Announces Operations
Update.January 30.
Denison Mines (USA)Corp.(DUSA)2007b.2006 ALARA Report.May 10.
EnecoTech Environmental Consultants 1991a.MILDOS Modeling Results (Letter),Prepared for
Umetco Minerals.October 31.
EnecoTech Environmental Consultants 1991b.MILDOS Modeling Correction (Letter),Prepared
for Umetco Minerals.November 27.
United States Environmental Protection Agency (EPA)1989.Code of Federal (CFR)
Regulations Title 40 Part 61 National Emission Standards for Hazardous Air Pollutants
(NESHAPs),Subpart W.December.
United States Environmental Protection Agency (EPA)2002.Code of Federal (CFR)
Regulations Title 40 Part 190 Environmental Radiation Protection for Nuclear Power
Operations.FeblUary.
Google 2005.Google Earth Pro 3.0.0762,November.
Intemational Commission on Radiological Protection ([eRP)1959.Report ofICRP Committee
lIon Permissible Dosefor Internal Radiation,Health Physics 3:1-380,1960.
International Commission on Radiological Protection (ICRP)1966.Deposition and retention
models for internal dosimetly of the human respiratory tract.Health Physics 12;
173-207.
34489H10 -FINAL~April 2008 8-1 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
International Commission on Radiological Protection (ICRP)1971.Recommendations of the
International Commission on Radiological Protection.ICRP Publication lOA.Pergamon
Press,New York.
Intemational Commission on Radiological Protection (ICRP)1972.The Metabolism of
Compounds ofPlutonium and Other Actinides.ICRP Publication 19,Pergamon Press.
International Commission on Radiological Protection (ICRP)1979.Limits for Intakes of
Radionuclides by Workers (adoptedfrom July 1978).ICRP Publication 30.
Landau,S.2007.Email:RE:34489-Preliminary Mildos Results and Emissions Calculations.
Received Feb.13/07.
National Council on Radiation Protection and Measurements (NCRP)1987.Report No.94.
Exposure of Population in the United States and Canada from Natural Background
Radiation
United States Nuclear Regulatory Commission (NRC)1979.Final Environmental Statement
Related to the Energy Fuels Nuclear,Inc,NUREG-0556.Docket No.40-8681.May.
United States Nuclear Regulatory Commission (NRC)1980.Final Generic Environmental
Impact Statement on Uranium Milling Project M-25,NUREG-0706 Vol.3.September.
United States Nuclear Regulatory Commission (NRC)1987.Methods for Estimating
Radioactive and Toxic Airborne Source Termsfor Uranium Milling Operations,March.
SENES Consultants Limited (SENES)2007.Dose Assessment in Support of the License
Renewal Application &Environmental Report for the White Mesa Mill.Prepared for
Denison Mincs (USA)Corp.February.
Strenge,D.L.and Bander,TJ.1981.MILDOS-A Computer Program for
Environmental Radiation Doses from Uranium Recovery
NUREGICR-2011.Prepared for U.S.Nuclear Regulatory Commission.
Turk,D.2007a.Email to A.Ho:RE:Receptor GPs.Received February 14-15.
Calculating
Operations,
Turk,D.2007b. Email to D.Chambers:FW:Additional Weather Information.Received Feb 7.
Yu,C.1992.Calculation of Radiation Dose from Uranium Recovery Operations for Large
Area-Sources.Argonne National Laboratory.
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APPENDIX A
HISTORY OF MILDOS
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APPENDIX A HISTORY OF MILDOS
The MILDOS computer code was developed from the versIon IV for Argonne National
Laboratory's (ANL's)Uranium Dispersion and Dosimetry (UDAD)computer program 198I.
The MILDOS program was based on the models and assumptions from NRC Draft Regulatory
Guide RH802-4 (Calculational Models for Estimating Radiation Doses to Man from Airbome
Radioactive Material Resulting from Uranium Milling Operation)and portions of the UDAD
document (Strenge and Bender 1981).
In 1989,ANL developed the MILDOS-AREA code by modifying the MILDOS code developed
in 1981.The MILDOS-AREA code was designed for use on IBM or IBM compatible
computers;the changes made were intended to enhance capabilities for calculating dose from
large area-sources and updated dosimetry calculations.The major revision from the original
MILDOS code is the treatment of atmospheric dispersion from area sources;MILDOS-AREA
substituted a finite-element approach for the virtual-point source method (the algorithm used in
the original MILDOS code)when specified by the user.The new approach subsequently led to a
reduction in the number of sources from 20 to lOin MILDOS-AREA due to the fact that a large
area can be considered as a single source rather than two or more point sources.
The intemal dosimetry calculations were also updated in MILDOS-AREA.In the original
version of MILDOS,the dose to exposed individual is calculated for comparison with
requirements of both 40 CFR 190 and 10 CFR 20 (R313-15).The calculations of ingestion
DCFs were based on ICRP Publication 2 and lOA's ingestion models (ICRP 1966).The
inhalation DCFs are calculated by the ANL computer program UDAD in accordance with Task
Group on Lung Dynamics Lung Model (TGLM)of the International Commission on
Radiological Protection (ICRP 1966,ICRP 1972).ICRP Publication 19 (ICRP 1972)gives dose
commitments to adult members of the public at age 20 that are assumed to live another 50 years.
DCFs are provided as a function of patticle size and organ for the radionuclides U-238,U-234,
Th-230,Ra-226,Pb-210,Po-210 and Bi-210.The inhalation dose factors incorporated into
MILDOS-AREA are calculated using the dosimetric model from ICRP Publication 30 (ICRP
1979)(Yu 1992);the inhalation dose factors are provided for the age groups of infant,child,
teenager and adult.However,these factors are fixed internally in the code,and are not patt of
the input options.The annual average air concentrations were computed to the maximum
pelmissible concentrations (MPCs)in 10 CFR 20.The MPCs m
10 CFR 20 (incorporated by reference in R313-15)were revised in 1994 to incorporate the
updated dosimetry to the I CRP 1978 recommendations.
In 1997,the MILDOS-AREA code was updated to meet the requirements of the revised
10 CFR 20.The dose limit to the general public also changed;which led to a revised calculation
34489-10--FINAL -April 2008 A-I SENES Consultants Limited
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of the allowable concentrations (ALCs)for unrestricted areas,with MPC replaced with the term
"effluent concentrations".
In 1998,ANL again updated the MILDOS-AREA code in an attempt to improve the "user
friendliness"of the software.In the past,the user must develop an input file in an American
Standard Code for Information Interchange (ASCII)file containing values that are required by
the code.The code executes this file to produce the output.The latest version of
MILDOS-AREA,has a graphical user interface (OUI)which provides an interface for the user to
input each parameter needed for the calculations in the Windows operating system.The OUI
allows the results of the MILDOS-AREA calculations to be viewed.The 1998 update was the
last time ANL made changes to the MILDOS-AREA code.The most up-to-date version of
MILDOS-AREA was used in this assessment.
MILDOS-AREA calculates the impacts based on annual average air concentrations of nuclides
considered.The human pathways considered in MILDOS-AREA for individual and population
impacts are:inhalation,extemal exposure from ground concentrations,extemal exposure from
cloud immersion,ingestion ofvegetables,ingestion ofmeat and ingestion ofmilk.
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APPENDIXB
EMISSION CALCULATIONS
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APPENDIXB EMISSION CALCULATIONS
Supplemental Infonnation which describes the model and assumptions used to calculate the
source emissions for the sources described in Section 4.0 are provided below.
B.l CALCULATION OF ANNUAL DUST Loss
The calculation of the annual dust loss from the ore pads and the tailings cells was required to
calculate an emission factor.This dusting rate for the tailings impoundments is calculated
according to the emission factor (Ew)equation from NRC Regulatory Guide 3.59 (NRC 1987).
The equation offor the dusting rate is calculated as follows:
where,
E =3.156x107 x "R F
w 0.5 7 s s
(B.I)
Ew=annual dust loss per unit area in glm2yr;
Fs=annual average frequency of occurrence of wind speed group S (dimensionless)obtained
from the joint relative frequency disttibution for the mill (provided by DUSA (Turk 2007b));
Rs=resuspension rate for the tailings pond at the average wind speed for wind group S,for
particles :s 20 11m in diameter in glm2s;
3.156 x 107=number of seconds per year;and,
0.5=fraction ofthe total dust lost constituted by particle :s 20 11m in diameter.
TABLE B.l
PARAMETER VALUES FOR CALCULATION OF ANNUAL DUSTING RATE FOR
EXPOSED TAILINGS
Average Wind
Frequency
Wind Speed (kts)Resuspension of Rs xFsSpeedRate(Rs)Occurrence,
III/m's)"IFs)b
oto 3 I.5 0 0.165 O.OOE+OO
4 to 6 5.5 0 0.427 O.OOE+OO
7 to 10 10.0 3.92E-07 0.276 1.08E-07
II to 16 15.5 9.68E-06 0.106 I.03E-06
17t021 21.5 5.71E-05 0.021 1.20E-06
21+28.0 2.08E-04 0,005 1.04E-06f----,
Is 3.37E-06
Notes:
a)Resuspension rate ofa function ofwind speed is computed by the MILDOS code.
b)Wind speed frequency obtained from joint frequency distribution data provided by DUSA (Turk 2007b).
34489~IO-FINAL ~April 2008 B-1 SENES Consultants Limited
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Using equation 8.1 and the parameters in Table B-1,the annual dust loss from the tailings cells
is approximately 213 glm2yr.As mentioned in Section 4.2.1,the annual dust lost for ore pads is
10%of that of the tailings cells since the paliiculates on the ore pad are coarse material (1 to 6
inch)because the ore has not yet been ground;therefore the annual dust loss from the ore pad is
21.29 glm\T.
B.2 EMISSION CALCULATIONS
The equations and assumptions used to calculate the radioactive particulate (U-238)and its
daughters thorium (Th-230),radium (Ra-226)and lead (Pb-210))and radon emission rates from
the grizzly,grinding,ore pads,vanadium stack (exclusively for processing Colorado Plateau
ore),yellowcake stacks (nOlih and south yellowcake stacks)and the tailings cells were taken
from NRC Regulatory Guide 3.59 (NRC 1987),NUREG-0706 (NRC 1980)and the EnecoTech
analysis (EnecoTech 1991a and 1991b).
8.2.1 Wet Grinding
Radioactive Particulate Emissiofl Rates
Colorado Plateau Arizona Strip
Ore Ore
Process Rate (tpy)730,000 730,000
Coulamiuant Concentration (pCi/g U-238)700 1783
Process Emission Factor (lbs/ton)'0.16 0.16
Activity Enrichment Ratio 2.5 2.5
Control Factor (%)"99.90 99.90
Notes:
a)For moisture <8%(NRC 1987).
b)Particulate emission control from the wet grinding operations was assumed to be 99.9%(EnecoTech 1991a and
1999b)
The U-238 Emission Rate (S)is calculated as follows:
S=(Process Rate (tons/yr))*(Process
(453.6 gllb)*(Contaminant Concentration
(I-Control Factor)*(l0-12 CilpCi)
Emission Factor (lbs/ton))*
(pCi/g))*(Activity Enrichment Ratio)*
(8.2-1 )
Using equation 8.2-1,the U-238 Emission Rate from wet grinding operations of Colorado
Plateau ore is approximately 9.27E-05 Ci/yr.U-238 decay daughters (Th-230,Ra-226 and
Pb-21 0)are assumed to be in secular equilibrium;therefore the decay daughters are also emitted
at a rate of9.27E-05 Ci/yr.Similarly,the U-238 Emission Rate from the wet grinding operations
34489-10 -FINAL·April 2008 B-2 SENES Consultants Limited
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of Arizona Strip ore is approximately 2.36E-04 Cilyr and the decay daughters (Th-230,Ra-226
and Pb-2l 0)are also emitted at a rate of 2.36E-04 Ci/yr.
Radon Emission Rates
Colorado Arizona
l)lateau ore Strip ore
Process Rate (tpy)730,000 730,000
Contaminant Concentration 700 1783(pCi/g Ra-226)
Activity Factor(%)'20 20
Note:
a)It was assumed that only 20%ofthe radon is available for release or emanation from the mineral grains in
which it is produced (i.e.the emanating fraction or power is 0.20)(NRC 1980).
Radon Release (F):
F=(Process Rate (tons/yr»*(2000 Ibs/ton)*(453.6 gllb)*
(Contaminant Concentration pCi/g Ra-226)*(l 0-12 Ci/pCi)*(Activity Factor)(8.2-2)
Using equation 8.2-2,the radon release from the wet grinding operations of Colorado Plateau
ore is approximately 92.7 Ci/yr.Similarly,the radon release from the wet grinding operations of
Arizona Strip ore is approximately 236 Ci/yr.
8.2.2 Ore Dump to Grizzly
Radioactive Particulate Emission Rates
-Colorado Plateau Arizona Strip
Ore Ore
Process Rate (tpy)730,000 730,000
Contaminant Concentration (pCi/g U-238)700 1783
Process Emission Factor (Ibs/ton)'0.16 0.16
Activity Enrichment Ratio 2.5 2.5
Control Factor (%)99.90 99.90
Notes:
a)For moisture <8%(NRC 1987).
b)Grizzly Dump is enclosed on three sides.Trucks dump inside enclosure under negative pressure.The 1D fans
are ducted through a baghouse.Ore moisture content is 10 %(EnecoTech 1991a and 1999b).
34489-10-FINAL -April 2008 8-3 SENES Consultants Limited
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The U-238 Emission Rate (S)is calculated as follows:
S=(Process
(Contaminant
(10-12 Ci/pCi)
Rate (tons/yr))*(Process Emission Factor
Concentration (pCi/g))*(Activity Enrichment
(lbs/ton))*(453.6 gllb)*
Ratio)*(l-Control Factor)*
(8.2-3)
Using equation 8.2-3,the U-238 Emission Rate due to the trucks dumping Colorado Plateau ore
on the grizzly is approximately 9.27E-05 Ci/yr.U-238 decay daughters (Th-230,Ra-226 and
Pb-210)are assumed to be in secular equilibrium;therefore the decay daughters are also emitted
at a rate of 9.27E-05 Ci/yr.Similarly,the U-238 Emission Rate due to the trucks dumping
Arizona Strip ore on the grizzly is approximately 2.36E-04 Ci/yr and the decay daughters
(Th-230,Ra-226 and Pb-210)are also emitted at a rate of2.36E-04 Ci/yr.
Radon Emission Rates
No radon is released from the trucks dumping ore onto the grizzly.
B.2.3 Yellowcake Stacks
As mentioned in Section 4.1.3,the mill has two yellowcake dryers (north and south yellowcake
stack dryers);therefore the total emissions were assumed to be divided equally between the two
stacks (i.e.,north and south yellowcake stacks).
Radioactive Particulate Emission Rates
Colorado Plateau Arizoua Strip
Ore Ore --Process Rate (tpy U3OS)1716 4371
Coutaminant Conceutration (Ci/g ofU-238)3.33E-07 3.33E-07
Process Emission Factor (g U-238/g U3OS)0.848 0.848
Emission Rate (Ibs/ton)'0.092 0.092
Note:
a)Based stack tests that showed an emission rate of0.06 lbs/hr U308 per 1300 lbs/hr process rate which translates
to 0.092 lb/ton including controls (EuecoTech 1991a and 1999b).
The U-238 Emission Rate (S)for one yellowcake stack is calculated as follows:
S=[(Process Rate (tons/yr U30s))*(Emission Rate (lbs/ton))*(Process Emission
(453.6 gllb)*(Contaminant Concentration (Ci/g))]/2
Factor)*
(8.2-4)
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Based on field measurements,the decay daughters Th-230,Ra-226 and Pb-210 are processed
along with yellowcake at 0.22%,0.13%and 0.78%,respectively.
Using equation B.2-4,the U-238 Emission Rate from each yellowcake stack (north and south
yellowcake stacks)is approximately 1.01E-02 Cilyr for the processing of Colorado Plateau ore.
The emission rate for the decay daughters Th-230,Ra-226 and Pb-210 is 2.22E-05,
1.31 E-05 and 7.88E-05 Ci/yr,respectively from each yellowcake stack (nolth and south
yellowcake stacks).Similarly,the U-238 Emission Rate from each yellowcake stack (north and
south yellowcake stacks)is approximately 2.58E-02 Ci/yr for the processing of Arizona Strip
ore.The emission rate for the decay daughters Th-230,Ra-226 and Pb-210 is 5.67E-05,
3.35E-05 and 2.0IE-04 Ci/yr,respectively from each yellowcake stack (north and south
yellowcake stacks).
Radon Emission Rates
There is no significant radon releases during this process.
B.2.4 Vanadium Stack
Radioactive Particulate Emission Rates
As mentioned in Section 4.1.4,the vanadium source was only used in the MILDOS-AREA
model for Colorado Plateau ore.The product from the vanadium recovery contains less than
0.005%U308 (NRC 1980).Therefore,the emission rates ofU-238 and its decay daughters from
the vanadium stack were assumed to be 0.005%of the total emission rate from the yellowcake
stacks (north and south yellowcake stacks).
Emission Rate (S)(Ci/yr)
Radioactive Particnlate Total from
Yellowcake Vanadium Stacka
Stacks
D-238 2.02E-02 1.01E-06
Th-230 4.45E-05 2.22E-09
Ra-226 2.63E-05 1.31E-09
Pb-2l0 1.58E-04 7.88E-09
Note:
a)Total from yellowcake stacks (north and sonth yellowcake stacks)*0.005%.
Radon Emission Rates
There are no significant radon releases during this process.
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B.2.5 Ore Pads
The ore pad storage operation has two different sources of emissions -namely unloading from
the truck to the ore pad and wind emissions.For the wind emissions calculated,it was assumed
that approximately 300,000 tons of ore are temporarily stockpiled with a height of 30 ft (9.1 m).
and bulk density of ore of 120 Ibs/ftJ (1.47 tons/yd\Using these assumptions,the area of the
ore pad is approximately 17,000 m2
Radioactive Particulate Emission Rates
Source Description:TlUck Unloading
Colorado Plateau Arizoua Strip
Ore Ore-Process Rate (tpy)730,000 730,000
Contaminant Concentration (pCi/g U-238)700 1783
Process Emission Factor (ibs/yd3)'0.04 0.04
Activity Emission Ratio 2.5 2.5
Control Factor None None
Bulk Density ofOre (tons/yd3)1.47 1.47
Note:
a)Process emission factor for Truck end dump (NRC 1987).
The U-238 Emission Rate (S)is calculated as follows:
S=(Process Rate (tons/yr»*(l
(Process Emission Factor (lbs/ydJ»*(453.6 g/Ib)*(Contaminant
(Activity Enrichment Ratio)*(l 0-12 CilpCi)
ydJ/1.47
Concentration
tons)*
(pCi/g»*
(B.2-5)
Using equation B.2-5,the U-238 Emission Rate from ttuck unloading Colorado Plateau ore is
approximately 1.58E-02 Ci/yr.U-238 decay daughters (Th-230,Ra-226 and Pb-21 0)were
assumed to be in secular equilibrium;therefore the decay daughters are also emitted at a rate of
1.58E-02 Ci/yr.Similarly,the U-238 Emission Rate from tlUck unloading of Arizona Strip ore is
approximately 4.02E-02 Ci/yr and the decay daughters (Th-230,Ra-226 and Pb-210)are also
emitted at a rate of4.02E-02 Ci/yr.
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Source Description:Wind Erosion
Colorado Plateau Arizoua Strip
Ore Ore
Area (m')'17000 17000 --
Contaminant Concentration (pCi/g U-238)700 1783
Process Emission Factor,Ew (g/m'yr)b 21.29 21.29
Activity Enrichment Ratio 2.5 2.5
Control Factor (%)'50 50
Notes:
a)Calculated assuming a stockpile of 300,000 tons of ore with a height of 30 ft.and bulk ore density of
1.47 tons/yd3•
b)The process emission factor for the ore pad was derived in Section B.I.
c)The control factor of 50%is based on the assumption that an active watering program will be in place during
operations (EnecoTech 1991a and 1999b).
The U-238 Emission Rate (S)is calculated as follows:
S=(Process Emission Factor (glm2yr))*(Area (m2))*(Contaminant Concentration
(Activity Enrichment Ratio)*(l-Control Factor)*(l 0-12 CilpCi)
(pCi/g))*
(8.2-6)
Using equation 8.2-6,the U-238 Emission Rate from trucks unloading Colorado Plateau ore is
approximately 3.I7E-04 Ci/yr.U-238 decay daughters (Th-230,Ra-226 and Pb-210)were
assumed to be in secular equilibrium;therefore the decay daughters are also emitted at a rate of
3.17E-04 Ci/yr.Similarly,the U-238 Emission Rate from truck unloading of Arizona Strip ore is
approximately 8.07E-04 Ci/yr and the decay daughters (Th-230,Ra-226 and Pb-210)are also
emitted at a rate of 8.07E-04 Ci/yr.
The total radioactive paliiculate emission rates from the ore pad are obtained by adding the
results of truck unloading and wind erosion and are as follows:
Emission Rate (S)(Ci/yr)
Radioactive Partieulate Colorado Plateau Arizona Strip
Ore Ore
U-238 1.61E-02 4.IOE-02
Th-230 1.61E-02 4.IOE-02
Ra-226 1.61E-02 4.IOE-02
Pb-210 1.61 E-02 4.IOE-02
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Radon Emission Rates
Colorado Arizona
Plateau ore Strip ore
Area (m2)17000 17000
Contaminant Concentration 700 1783(PCi/g Ra-226)
Specific Radon Flux Factor
(pCi Rn-222/m2s)/(pCi/g Ra-1 1
226)
Radon Release (F):
F=(Specific Radon Flux Factor (pCi Rn-222/m2s)/(pCi/g Ra-226))*(Contaminant Concentration
(pCi/g Ra-226))*(Area (m2))*(3.156xl07 s/yr)*(l0-12 CilpCi)(8.2-7)
Using equation 8.2-7,the radon release from storage of Colorado Plateau ore is approximately
375 Ci/yr.Similarly,the radon release from storage of Arizona Strip ore is approximately
956 Ci/yr.
8.2-6 Tailings Cells
Factors used to Calculate Radioactive Particulate Emission Rates
Colorado Plateau Ore Arizona Stri(l.9re
Active Active
Cell 3 Cell4AJ4B Cell 3 Ccll4AJ4B
Area (acres)10 10 10 10
Contamiuant Concentration (pCi/g D-42 42 107 107238)'
Contaminant Concentration ofall other 700 700 1783 1783isotopes(pCi/g)
Process Emission Factor,Ew(glm2yr)b 213 213 213 213
Activity Enrichment Ratio 2.5 2.5 2.5 2.5
Control Factor (%)'70 70 70 70
!:'lotes:
a)Assumes 94%recovery.
b)The process emission factor for the tailings cells was derived in Section B.1.
c)The control factor of 70%is based on the assumption that active watering programs as well as crusting agents
are used to minimize the erosion ofthe tailings by wind (EnecoTech 1991a and 1991b).
34489-10·-FINAL·April 2008 B-8 SENES Consultants Limited
Proposed Development o/New Tailings Ce1l4B/or White Mesa Uranium Mill
The Emission Rate (S)for U-238 and its decay daughters were calculated as follows:
S=(Process Emission
(Contaminant Concentration
(10-12 Ci/pCi)
Factor (g/m2yr»*(Area
(pCi/g»*(Activity Enrichment
(acres»*(4047 m2/acre)*
Ratio)*(l-Control Factor)*
(8.2-8)
Using equation 8.2-8,the U-238 Emission Rate from the active tailings cells 3,4A and 48 fi'om
the processing of Colorado Plateau ore is approximately 2.71 E-04 Ci/yr.The decay daughters
(Th-230,Ra-226 and Pb-21 0)are emitted at a rate of4.52E-03 Ci/yr.
Similarly,the U-238 Emission Rate from the active tailings cells 3,4A and 48 fi'om the
processing ofArizona Strip ore is approximately 6.9IE-04 Ci/yr.The decay daughters (Th-230,
Ra-226 and Pb-21 0)are emitted at a rate of 1.15E-02 Ci/yr.
There is no dust released from tailings cells 2 and 3 with interim covers.
Factors Used to Calculate Radon Emission Rates
Colorado Plateaul Arizona Strip Ore
Interim Soil Cover Active
Cell 2 Cell 3 Cell 3 Ce1l4A14B
Area (acres)66.8 70 70 40
Contaminant Concentration 10 10 20 20(pCi/m2s)
Radon Release (F):
F=(Contaminant Concentration (pCi/m2s)*(Area (acres»*(4047
(10.12 Ci/pCi)
m2/acre)*(3.l56xI07 s/yr)*
(8.2-9)
Using equation 8.2-9,the radon release from the active tailings cells 3,4A and 48 are
approximately 179 and 102 Ci/yr,respectively.The radon release for tailings cells 2 and 3 with
interim cover are approximately 85.3 and 89.4 Ci/yr,respectively.
34489~I 0·-FINAL-April 2008 8-9 SENES Consultants Limited
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APPENDIXC
MILDOS-AREA RESULTS
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APPENDIXC MILDOS-AREA RESULTS
This Appendix provides the dose estimates for MILDOS-AREA runs for the mill area (including
the ore pads)and each tailings cell for the processing of Colorado Plateau or Arizona Strip ore.
The total annual dose commitments and 40 CFR 190 annual dose commitments for Phases I and
2 are provided in Sections C.I and C.2 for Colorado Plateau ore and Arizona Strip ore,
respectively.
C.I MILDOS-AREA RESULTS FOR COLORADO PLATEAU ORE
The MILDOS-AREA calculated total annual dose commitments (including radon)and 40 CFR
190 annual dose commitments for the mill area (including the ore pads)and each tailings cell for
processing ofColorado Plateau ore are provided in Sections C.!.!and C.I.2,respectively.
c.1.1 R313-15-301 (l)(a)Regulatol'y Compliance
TABLE C.l-l
ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Gronp (including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Ce1l4A Ce1l4B
Effective l.i IE+OO 6.03E-02 5.84E-02 l.30E-OI 6.88E-02 5.55E-02
Infant Bone 1.81E+OO 2.57E-03 2.70E-03 6.09E-02 4.94E-02 3.74E-02
Avg.Lung 4.66E-Ol 2.45E-03 2.55E-03 3.46E-02 2.77E-02 2.14E-02
Bronchi 9.22E+OO 9.67E-OI 9.34E-Ol 1.87E+OO 9.14E-OI 7.44E-Ol
Effective 7.96E-OI 6.03E-02 5.84E-02 1.29E-OI 6.77E-02 5.46E-02
Child Bone 1.24E+OO 2.65E-03 2.79E-03 7.48E-02 6.06E-02 4.54E-02
Nearest Avg.Lung 6.20E-OI 2.56E-03 2.69E-03 4.86E-02 3.88E-02 2.92E-02
Potential Bronchi 9.22E+OO 9.67E-OI 9.34E-OI 1.87E+OO 9.14E-Ol 7.44E-OI
Resident Effective 8.34E-Ol 6.04E-02 5.85E-02 l.32E-OI 7.05E-02 5.66E-02
(BHV-I)Bone 4.40E+OO 3.28E-03 3.53E-03 2.42E-OI 1.98E-OI 1.46E-OlTeenage~g.Lung 4.94E-OI 2.54E-03 2.66E-03 3.99E-02 3.I5E-02 2.38E-02
Bronchi 9.22E+OO 9.67E-OI 9.34E-OI 1.87E+OO 9.14E-OI 7.44E-OI
Effective 7.30E-O I 6.03E-02 5.84E-02 1.27E-OI 6.59E-02 5.32E-02
Adult Bone 1.9 1E+OO 2.85E-03 3.03E-03 1.20E-Ol 9.80E-02 7.29E-02
Avg.Lung 3.43E-O I 2.50E-03 2.6IE-03 2.88E-02 2.25E-02 l.70E-02
Bronchi 9.22E+OO 9.67E-O I 9.34E-OI 1.87E+OO 9.14E-Ol 7.44E-OI
34489~10 .,.FINAL -April 2008 C-I SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
TABLE C.l-l (Cont'd)
ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B
Effective 2.18E-Ol 2.14E-02 2.09E-02 4.54E-02 2.53E-02 2.42E-02
Infant Bone 2.69E-Ol l.84E-03 l.90E-03 l.88E-02 1.55E-02 1.53E-02---
Avg.Lung 8.29E-02 1.61E-03 l.65E-03 I.l7E-02 9.36E-03 9.18E-03
Bronchi 2.20E+OO 3.31E-Ol 3.22E-OI 6.43E-OI 3.39E-O1 3.23E-O1
Effective l.75E-Ol 2.14E-02 2.08E-02 4.48E-02 2.49E-02 2.37E-02
Child Bonc l.91E-OI l.97E-03 2.04E-03 2.20E-02 1.82E-02 1.80E-02
Nearest Avg.L~l.OlE-Ol l.82E-03 l.87E-03 l.48E-02 I.l9E-02 I.l7E-02
Historical Bronchi 2.20E+OO 3.31E-OI 3.22E-OI 6.43E-OI 3.39E-O1 3.23E-OI
Residcnt Effective l.80E-Ol 2.14E-02 2.09E-02 4.57E-02 2.57E-02 2.44E-02
(BHV-2)Bone 6.40E-Ol 3.10E-03 3.28E-03 6.48E-02 5.52E-02 5.52E-02TeenageAvg.Lung 8.09E-02 l.78E-03 1.83E-03 l.23E-02 9.7IE-03 9.60E-03
Bronchi 2.20E+OO 3.31E-Ol 3.22E-OI 6.43E-OI 3.39E-Ol 3.23E-O1
Effective l.65E-Ol 2.14E-02 2.08E-02 4.43E-02 2.44E-02 2.33E-02
Adult Bone 2.89E-OI 2.34E-03 2.45E-03 3.38E-02 2.84E-02 2.82E-02
Avg.Lung 5.86E-02 l.70E-03 l.74E-03 9.44E-03 7.2IE-03 7.10E-03
Bronchi 2.20E+OO 3.3lE-OI 3.22E-OI 6.43E-OI 3.39E-Ol 3.23E-OI
Effective 6.83E-Ol 4.54E-02 4.33E-02 9.67E-02 5.23E-02 4.57E-02
Infant Bone l.05E+OO 2.46E-03 2.54E-03 4.45E-02 3.6IE-02 3.10E-02
Avg.Lung 2.68E-Ol 2.30E-03 2.36E-03 2.59E-02 2.07E-02 l.79E-02
Bronchi 5.98E+OO 7.20E-OI 6.84E-O1 l.38E+OO 6.95E-Ol 6.09E-Ol
Effective 5.03E-Ol 4.54E-02 4.33E-02 9.57E-02 5.14E-02 4.49E-02
Child Bone 7.12E-Ol 2.55E-03 2.65E-03 5.38E-02 4.37E-02 3.74E-02
Avg.Lung 3.56E-Ol 2.44E-03 2.53E-03 3.52E-02 2.8IE-02 2.41E-02
Nearest Bronchi 5.98E+OO 7.20E-Ol 6.84E-OI l.38E+OO 6.95E-Ol 6.09E-O1ActualEffective5.24E-Ol 4.54E-02 4.34E-02 9.81 E-02 5.34E-02 4.66E-02Resident------
Teenage Bone 2.52E+OO 3.36E-03 3.58E-03 l.70E-OI l.40E-Ol I.l9E-Ol
Avg.Lung 2.85E-Ol 2.41E-03 2.50E-03 2.90E-02 2.29E-02 l.96E-02
Bronchi 5.98E+OO 7.20E-Ol 6.84E-OI l.38E+OO 6.95E-Ol 6.09E-OI
Effective 4.65E-Ol 4.54E-02 4.33E-02 9.4IE-02 5.0IE-02 4.38E-02
Adult Bone I.lOE+OO 2.8IE-03 2.95E-03 8.54E-02 6.99E-02 5.96E-02
Avo.Lung 2.00E-Ol 2.36E-03 2.43E-03 2.13E-02 l.65E-02 l.41E-02
Bronchi 5.98E+OO 7.20E-OI 6.84E-OI l.38E+OO 6.95E-Ol 6.09E-OI
34489-10-FINAL -April 2008 C-2 SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
TABLE C.l-l (Cont'd)
ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mremlyr)
Location Age Organ Mill Area Interim Soil Covel'Active
Group (including Tailings Tailings Tailings Tailings Tailiugs
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B--~(lE-OIEffective 2.23E-02 2.48E-02 5.17E-02 3.15E-02 2.82E-02
Iufant Bone 1.16E-OJ 2.8IE-03 3.05E-03 1.44E-02 1.22E-02 l.08E-02
Avg.Lung 4.60E-02 2.26E-03 2.47E-03 l.04E-02 8.6IE-03 7.61E-03
Bronchi 1.65E+OO 3.36E-OI 3.74E-OI 7.48E-Ol 4.43E-Ol 3.97E-OI
Effective 1.21E-Ol 2.23E-02 2.48E-02 5.11E-02 3.09E-02 2.77E-02-----_._--------
Child Bone 7.67E-02 3.14E-03 3.38E-03 1.51 E-02 1.27E-02 1.12E-02
Avg.Lung 4.24E-02 2.76E-03 2.99E-03 l.09E-02 8.64E-03 7.69E-03-
White Mesa Bronchi 1.65E+OO 3.36E-OI 3.74E-OI 7.48E-OI 4.43E-Ol 3.97E-Ol
Community Effective 1.21E-OI 2.24E-02 2.49E-02 5.13E-02 3.10E-02 2.79E-02
Teenage Bone 2.15E-OI 5.93E-03 6.28E-03 3.51E-02 3.09E-02 2.72E-02
Avg.Lung 3.35E-02 2.67E-03 2.90E-03 9.33E-03 7.10E-03 6.34E-03
Bronchi 1.65E+OO 3.36E-Ol 3.74E-OI 7.48E-OI 4.43E-OI 3.97E-Ol
Effective 1.17E-OI 2.23E-02 2.48E-02 5.07E-02 3.05E-02 2.73E-02
Adult Bone l.06E-OI 4.04E-03 4.33E-03 2.08E-02 1.78E-02 1.57E-02
Avg.Lung 2.66E-02 2.47E-03 2.69E-03 7.88E-03 5.77E-03 5.18E-03
Bronchi 1.65E+OO 3.36E-OI 3.74E-Ol 7.48E-OI 4.43E-OI 3.97E-Ol
Effective 6.98E-02 8.36E-03 8.50E-03 1.82E-02 l.05E-02 l.04E-02
Infant Bone 7.53E-02 1.17E-03 1.22E-03 7.12E-03 5.86E-03 5.93E-03
Avg.Lnng 2.45E-02 8.95E-04 9.22E-04 4.57E-03 3.64E-03 3.67E-03
Bronchi 7.34E-OI l.25E-OI 1.27E-Ol 2.53E-O I 1.40E-OI l.38E-OI
Effective 5.72E-02 8.34E-03 8.49E-03 1.79E-02 1.03E-02 l.02E-02
Child Bone 5.16E-02 l.34E-03 l.39E-03 8.18E-03 6.75E-03 6.83E-O~_
.!':."_g~!:lll1g_2.78E-02 U5E-03 1.19E-03 5.69E-03 4.5IE-03 4.55E-03--.
Blanding Bronchi 7.34E-Ol 1.25E-OI 1.27E-OI 2.53E-Ol 1.40E-O I l.38E-OJ
Effective 5.84E-02 8.37E-03 8.52E-03 1.82E-02 l.06E-02 l.04E-02
Teenage Bone 1.65E-OI 2.74E-03 2.88E-03 2.28E-02 1.96E-02 1.99E-02
Avg.Lung 2.26E-02 U OE-03 1.14E-03 4.84E-03 3.74E-03 3.76E-03
Bronchi 7.34E-OI 1.25E-Ol l.27E-OI 2.53E-OI 1.40E-O I l.38E-OJ
Effective 5.46E-02 8.33E-03 8.47E-03 1.77E-02 l.OIE-02 9.99E-03
Adult Bone 7.58E-02 1.79E-03 1.87E-03 1.23E-02 l.03E-02 l.05E-02
Avg.Lnng 1.70E-02 9.99E-04 l.03E-03 3.84E-03 2.86E-03 2.87E-03
Bronchi 7.34E-OI 1.25E-Ol 1.27E-OJ 2.53E-OI 1.40E-Ol l.38E-OJ
34489-10 -FINAL-April 2008 C-3 SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4Bfor White Mesa Uranium Mill
C.2.2 40 CFR 190 Regulatory Compliance
TABLE C.I-2
40 CFR 190 ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (including Tailings Tailings Tailings Tailings Tailiugs
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B
Effective 5,22E-O I O,OOE+OO O,OOE+OO l.24E-02 l.03E-02 7,72E-03
Iufaut Bone l.76E+OO O,OOE+OO O,OOE+OO 5,43E-02 4,54E-02 3,39E-02-
Avg,Luug 4,33E-O I O,OOE+OO O,OOE+OO 2,83E-02 2.38E-02 l.80E-02
Bronchi 9,30E-04 O,OOE+OO O,OOE+OO 2,34E-05 l.93E-05 1,4IE-05
Effective 2,12E-O I O,OOE+OO O,OOE+OO l.lIE-02 9,23E-03 6,83E-03
Child Boue l.20E+OO O,OOE+OO O,OOE+OO 6,80E-02 5,65E-02 4,18E-02
Nearest Avg,Lung 5,85E-O I O,OOE+OO O,OOE+OO 4,19E-02 3,48E-02 2.57E-02
Potential Bronchi 9.30E-04 O,OOE+OO O,OOE+OO 2,34E-05 l.93E-05 1,4IE-05
Resident Effective 2,49E-OI O,OOE+OO O,OOE+OO l.46E-02 l.20E-02 8,86E-03
(BHV-I)Bone 4,37E+OO O,OOE+OO O,OOE+OO 2,34E-OI l.93E-OI l.4IE-OITeenageAvg,Lung 4,6IE-OI O,OOE+OO O,OOE+OO 3,33E-02 2,75E-02 2,03E-02
Bronchi 9.30E-04 O,OOE+OO O,OOE+OO 2,34E-05 l.93E-05 l.4IE-05
Effective l.46E-O I O,OOE+OO O,OOE+OO 8,99E-03 7,44E-03 5,49E-03
Adult Bone l.88E+OO O,OOE+OO O,OOE+OO 1.13E-OI 9,35E-02 6,90E-02
Avg,Lung 3,lOE-O I O,OOE+OO O,OOE+OO 2,24E-02 l.85E-02 l.36E-02
Bronchi 9.30E-04 O,OOE+OO O,OOE+OO 2,34E-05 l.93E-05 l.4IE-05
Effective 7,43E-02 O,OOE+OO O,OOE+OO 3.36E-03 2,99E-03 2,98E-03
Infant Bone 2,54E-OI O,OOE+OO O,OOE+OO l.47E-02 l.31E-02 l.30E-02
Avg,Lung 7,02E-02 O,OOE+OO O,OOE+OO 8,IOE-03 7,28E-03 7,22E-03
Bronchi l.28E-04 O,OOE+OO O,OOE+OO 5,68E-06 5,02E-06 5,04E-06
Effective 3,07E-02 O,OOE+OO O,OOE+OO 2,86E-03 2,53E-03 2,53E-03
Child Bone l.76E-OI O,OOE+OO O,OOE+OO l.76E-02 l.56E-02 l.56E-02
Nearest Avg,Lung 8,70E-02 O,OOE+OO O,OOE+OO l.07E-02 9,54E-03 9,53E-03
Historical Bronchi l.28E-04 O,OOE+OO O,OOE+OO 5,68E-06 5,02E-06 5,04E-06
Resident Effective 3,58E-02 O,OOE+OO O,OOE+OO 3,63E-03 3,22E-03 3,23E-03
(BHV-2)Bone 6,2IE-OI O,OOE+OO O,OOE+OO 5,79E-02 5,12E-02 5,14E-02TeenageAvg,Lung 6,73E-02 O,OOE+OO O,OOE+OO 8.37E-03 7,42E-03 7,43E-03
Bronchi l.28E-04 O,OOE+OO O,OOE+OO 5,68E-06 5,02E-06 5,04E-06
Effective 2,12E-02 O,OOE+OO O,OOE+OO 2,27E-03 2,OIE-03 2,02E-03
Adult Bone 2,72E-OI O,OOE+OO O,OOE+OO 2,85E-02 2,53E-02 2,53E-02
Avg,Lung 4.55E-02 O,OOE+OO O,OOE+OO 5,66E-03 5,OIE-03 5,02E-03
Bronchi l.28E-04 O,OOE+OO O,OOE+OO 5,68E-06 5,02E-06 5,04E-06
34489-10 --FINAL-April 2008 C-4 SENES Consultants Limited
Proposed Development ofNew Tailings Ce1l4B for White Mesa Uranium Mill
TABLE C.1-2 (Coot'd)
40 CFR 190 ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Gronp (including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B
Effective 3.0IE-OI O.OOE+OO O.OOE+OO 8.77E-03 7.42E-03 6.32E-03
Infant Bone 1.02E+OO O.OOE+OO O.OOE+OO 3.85E-02 3.25E-02 2.77E-02
Avg.Lung 2.43E-OI O.OOE+OO O.OOE+OO 2.04E-02 1.74E-02 1.48E-02
Bronchi 5.32E-04 O.OOE+OO O.OOE+OO 1.61E-05 l.35E-05 1.14E-05
Effective 1.21E-OI O.OOE+OO O.OOE+OO 7.79E-03 6.54E-03 5.55E-03
Child Bone 6.85E-OI O.OOE+OO O.OOE+OO 4.77E-02 4.0IE-02 3.4IE-02-~Y.£.Lung 3.30E-OI O.OOE+OO O.OOE+OO 2.93E-02 2.46E-02 2.09E-02
Nearest 5.32E-04 O.OOE+OO O.OOE+OO l.35E-05ActualBronchi1.61E-05 1.14E-05
Resident Effective 1.42E-OI O.OOE+OO O.OOE+OO 1.01E-02 8.46E-03 7.16E-03
Teenage Bone 2.48E+OO O.OOE+OO O.OOE+OO 1.62E-OI l.35E-OI 1.14E-OI
Avg.Lung 2.59E-O I O.OOE+OO O.OOE+OO 2.32E-02 1.94E-02 I.64E-02
Bronchi 5.32E-04 O.OOE+OO O.OOE+OO 1.61E-05 l.35E-05 1.14E-05
Effective 8.31 E-02 O.OOE+OO O.OOE+OO 6.27E-03 5.26E-03 4.45E-03
Adult Bone 1.07E+OO O.OOE+OO O.OOE+OO 7.88E-02 6.60E-02 5.60E-02
Avg.Lung 1.74E-OI O.OOE+OO O.OOE+OO 1.56E-02 l.3IE-02 l.lIE-02-
Bronchi 5.32E-04 O.OOE+OO O.OOE+OO 1.61E-05 l.35E-05 1.14E-05
Effective 2.98E-02 O.OOE+OO O.OOE+OO 1.90E-03 1.98E-03 I.72E-03
Infant Bone 1.02E-OI O.OOE+OO O.OOE+OO 8.2IE-03 8.59E-03 7.4IE-03
Avg.Lung 3.45E-02 O.OOE+OO O.OOE+OO 5.38E-03 5.6IE-03 4.85E-03
Bronchi 3.85E-05 O.OOE+OO O.OOE+OO 1.94E-06 2.05E-06 l.76E-06
Effective 1.04E-02 O.OOE+OO O.OOE+OO l.29E-03 l.36E-03 1.17E-03
Child Bone 6.IIE-02 O.OOE+OO O.OOE+OO 8.25E-03 8.66E-03 7.45E-03
Avg.Lung 2.86E-02 O.OOE+OO O.OOE+OO 4.82E-03 5.07E-03 ~:~~~White Mesa Bronchi 3.85E-05 O.OOE+OO O.OOE+OO 1.94E-06 2.05E-06
Community Effective 1.08E-02 O.OOE+OO O.OOE+OO 1.46E-03 1.53E-03 l.32E-03
Teenage Bone 1.85E-OI O.OOE+OO O.OOE+OO 2.24E-02 2.36E-02 2.03E-02
Avg.Lun[2.0IE-02 O.OOE+OO O.OOE+OO 3.45E-03 3.63E-03 3.12E-03
Bronchi 3.85E-05 O.OOE+OO O.OOE+OO 1.94E-06 2.05E-06 1.76E-06
Effective 6.70E-03 O.OOE+OO O.OOE+OO 9.7 IE-04 1.02E-03 8.78E-04
Adult Bone 8.57E-02 O.OOE+OO O.OOE+OO 1.21E-02 I.27E-02 1.09E-02
Avg.Lung 1.41 E-02 O.OOE+OO O.OOE+OO 2.42E-03 2.54E-03 2.18E-03
Bronchi 3.85E-05 O.OOE+OO O.OOE+OO 1.94E-06 2.05E-06 l.76E-06
34489-10 -FINAL-April 2008 c-s SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE C.I-2 (Cont'd)
40 CFR 190 ANNUAL DOSE COMMITMENTS
(COLORADO PLATEAU ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (including Tailings Tailings Tailings Tailings Tailiugs
ore pads)Ccll2 Cell 3 Cell 3 Cell4A Cell4B
Effective 2.00E-02 O.OOE+OO O.OOE+OO 1.05E-03 1.01E-03 1.03E-03
Infaut Bone 6.79E-02 O.OOE+OO O.OOE+OO 4.59E-03 4042E-03 4.52E-03-_.__..
Avg.Lung 1.88E-02 O.OOE+OO O.OOE+OO 2.63E-03 2.54E-03 2.58E-03
Bronchi 3.l7E-05 O.OOE+OO O.OOE+OO 1.63E-06 1.56E-06 1.61E-06
Effective 7.55E-03 O.OOE+OO O.OOE+OO 8.57E-04 8.23E-04 8044E-04
Child Bone 4.34E-02 O.OOE+OO O.OOE+OO 5.31E-03 5.09E-03 5.23E-03
Avg.Lung 2.06E-02 O.OOE+OO O.OOE+OO 3.22E-03 3.09E-03 3.17E-03
Blanding Bronchi 3.l7E-05 O.OOE+OO O.OOE+OO 1.63E-06 1.56E-06 1.61E-06
Effective 8049E-03 O.OOE+OO O.OOE+OO 1.07E-03 1.03E-03 1.05E-03
Teenage Bone 1.48E-Ol O.OOE+OO O.OOE+OO 1.69E-02 1.62E-02 1.67E-02
Avg.Lung 1.56E-02 O.OOE+OO O.OOE+OO 2047E-03 2.38E-03 2044E-03
Bronchi 3.l7E-05 O.OOE+OO O.OOE+OO 1.63E-06 1.56E-06 1.61 E-06
Effective 5.05E-03 O.OOE+OO O.OOE+OO 6.77E-04 6049E-04 6.67E-04
Adult Bone 6.50E-02 O.OOE+OO O.OOE+OO 8047E-03 8.13E-03 8.35E-03
Avg.Lung 1.06E-02 O.OOE+OO O.OOE+OO 1.68E-03 1.62E-03 1.66E-03
Bronchi 3.l7E-05 O.OOE+OO O.OOE+OO 1.63E-06 1.56E-06 1.61 E-06
34489-10 -FINAL -April 2008 C-6 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4B for White Mesa Uranium Mill
C.2 MILDOS-AREA RESULTS FOR ARIZONA STRIP ORE
The MILDOS-AREA calculated total annual dose commitments (including radon)and 40 CFR
190 annual dose commitments for the mill area (including the are pads)and each tailings cell for
processing ofArizona Strip are are provided in Sections C.2.]and C.2.2,respectively.
C.2.I R313-IS-30I (I)(a)Regulatory Compliance
TABLE C.2-I
ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
Estimated Dose (ml'em/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (iucluding Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B
Effective 2.82E+OO 6.03E-02 5.84E-02 1.52E-OI 8.64E-02 6.86E-02
Infant Bone 4.59E+OO 2.57E-03 2.70E-03 1.47E-OI 1.21E-OI 9.IIE-02
Avg.Lung 1.19E+OO 2.45E-03 2.55E-03 8.04E-02 6.62E-02 5.04E-02
Bronchi 2.35E+OI 9.67E-OI 9.34E-OI 1.87E+OO 9.15E-OI 7.45E-OI
Effective 2.03E+OO 6.03E-02 5.84E-02 1.48E-OI 8.36E-02 6.63E-02
Child Bone 3.15E+OO 2.65E-03 2.79E-03 1.82E-O I 1.50E-OI 1.11 E-OI
Nearest Avg.Lung 1.57E+OO 2.56E-03 2.69E-03 1.16E-OI 9.42E-02 7.02E-02
Potential Bronchi 2.35E+OI 9.67E-OI 9.34E-OI 1.87E+OO 9.15E-OI 7.45E-OI
Resident Effective 2.12E+OO 6.04E-02 5.85E-02 1.57E-OI 9.07E-02 7.15E-02
(BHV-I)Bone 1.12E+OI 3.28E-03 3.53E-03 6.05E-OI 4.97E-OI 3.67E-OITeenageAvg.Lung 1.26E+OO 2.54E-03 2.66E-03 9.34E-02 7.57E-02 5.63E-02
Bronchi 2.35E+OI 9.67E-OI 9.34E-OI 1.87E+OO 9.15E-OI 7.45E-OI
Effective 1.86E+OO 6.03E-02 5.84E-02 1.43E-OI 7.90E-02 6.29E-02
Adult Bone 4.88E+OO 2.85E-03 3.03E-03 2.97E-OI 2.44E-OI 1.8IE-OI
Avg.Lnng 8.74E-OI 2.50E-03 2.6IE-03 6.54E-02 5.27E-02 3.94E-02--
Bronchi 2.35E+OI 9.67E-OI 9.34E-OI 1.87E+OO 9.15E-OI 7.45E-OI
34489-10-FINAL -April 2008 C-7 SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE C.2-1 (Cont'd)
ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (including Tailings Tailings Tailings Tailings Tailings
ore pads)CeU 2 CeU3 CeU3 CeU4A CeU4B
Effective 5.57E-OI 2.14E-02 2.09E-02 5.10E-02 3.04E-02 2.93E-02._--
Infant Bone 6.85E-OI l.84E-03 l.90E-03 4.19E-02 3.62E-02 3.59E-02-
Avg.Lung 2.11E-OI l.6IE-03 l.65E-03 2.47E-02 2.IOE-02 2.07E-02
Bronchi 5.6IE+OO 3.3IE-OI 3.22E-OI 6.44E-OI 3.39E-O I 3.23E-OI
Effective 4.45E-OI 2.14E-02 2.08E-02 4.98E-02 2.92E-02 2.8IE-02
Child Bone 4.85E-OI l.97E-03 2.04E-03 4.96E-02 4.28E-02 4.25E-02
Nearest Avg.Lung 2.56E-OI l.82E-03 l.87E-03 3.18E-02 2.7IE-02 2.69E-02
Historical Bronchi 5.6IE+OO 3.3IE-OI 3.22E-OI 6.44E-OI 3.39E-OI 3.23E-OI
Resident Effective 4.59E-O I 2.14E-02 2.09E-02 5.18E-02 3.10E-02 2.99E-02
(BHV-2)Bone l.63E+OO 3.10E-03 3.28E-03 l.54E-OI l.35E-OI l.35E-O ITeenageAVQ.Lung 2.05E-OI l.78E-03 l.83E-03 2.58E-02 2.16E-02 2.15E-02
Bronchi 5.6IE+OO 3.3IE-OI 3.22E-OI 6.44E-OI 3.39E-OI 3.23E-O I
Effective 4.2IE-OI 2.14E-02 2.08E-02 4.83E-02 2.79E-02 2.68E-02
Adult Boue 7.36E-OI 2.34E-03 2.45E-03 7.84E-02 6.79E-02 6.78E-02
AVQ.Lun£...l.49E-OI l.70E-03 l.74E-03 l.87E-02 l.54E-02 l.53E-02
Bronchi 5.6IE+OO 3.3IE-OI 3.22E-OI 6.44E-OI 3.39E-OI 3.23E-OI
Effective l.74E+OO 4.54E-02 4.33E-02 l.l2E-O I 6.49E-02 5.64E-02
Infant Bone 2.67E+OO 2.46E-03 2.54E-03 l.05E-OI 8.77E-02 7.48E-02
Avg.Lung 6.82E-OI 2.30E-03 2.36E-03 5.88E-02 4.87E-02 4.18E-02
Bronchi l.53E+OI 7.20E-OI 6.84E-O I l.38E+OO 6.96E-OI 6.IOE-OI
Effective l.28E+OO 4.54E-02 4.33E-02 l.09E-OI 6.26E-02 5.44E-02
Child Bone l.8IE+OO 2.55E-03 2.65E-03 l.29E-OI l.07E-OI 9.09E-02
Avg.Lung 9.05E-OI 2.44E-03 2.53E-03 8.18E-02 6.73E-02 5.73E-02
Nearest Bronchi l.53E+OI 7.20E-OI 6.84E-OI l.38E+OO 6.96E-OI 6.10E-OIActual.
Resident Effective l.34E+OO 4.54E-02 4.34E-02 l.l5E-OI 6.77E-02 5.86E-02
Teenage Bone 6.40E+OO 3.36E-03 3.58E-03 4.2IE-OI 3.50E-O I 2.97E-OI
AVQ.Lung 7.27E-OI 2.4IE-03 2.50E-03 6.62E-02 5.40E-02 4.60E-02
Bronchi l.53E+OI 7.20E-OI 6.84E-OI l.38E+OO 6.96E-OI 6.10E-OI
Effective l.l9E+OO 4.54E-02 4.33E-02 l.05E-OI 5.94E-02 5.17E-02
Adult Bone 2.80E+OO 2.8IE-03 2.95E-03 2.08E-OI l.73E-OI l.47E-OI
AVQ.Lung 5.09E-OI 2.36E-03 2.43E-03 4.67E-02 3.78E-02 3.23E-02
Bronchi l.53E+OI 7.20E-OI 6.84E-OI l.38E+OO 6.96E-OI 6.lOE-OI
34489~IO -FINAL·April 2008 C-8 SENES Consultants Limited
Proposed Development ofNew Tailings Cell4Bfor White Mesa Uranium Mill
TABLE C.2-1 (Cont'd)
ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group (including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Cell4A Cell4B
Effective 3.56E-OI 2.23E-02 2048E-02 5047E-02 3047E-02 3.IOE-02-
Infant Bone 2.95E-OJ 2.8IE-03 3.05E-03 2.73E-02 2.57E-02 2.24E-02
Avg.Lung l.l7E-OJ 2.26E-03 2047E-03 1.89E-02 I.74E-02 1.53E-02
Bronchi 4.20E+OO 3.36E-OI 3.74E-OI 7o48E-OI 4o43E-OI 3.97E-O I
Effective 3.07E-OI 2.23E-02 2048E-02 5.32E-02 3.32E-02 2.96E-02----
Child Bone 1.96E-OI 3.14E-03 3.38E-03 2.80E-02 2.63E-02 2.29E-02
Avg.Lung 1.08E-OI 2.76E-03 2.99E-03 1.85E-02 1.66E-02 1.46E-02
White Mesa Bronchi 4.20E+OO 3.36E-OJ 3.74E-OJ 7o48E-O\4o43E-OI 3.97E-OI
Community Effective 3.09E-OJ 2.24E-02 2049E-02 5.37E-02 3.36E-02 3.00E-02
Teenage Bone 5o46E-OI 5.93E-03 6.28E-03 6.98E-02 6.76E-02 5.87E-02
Avg.Lung 8.54E-02 2.67E-03 2.90E-03 1.48E-02 1.29E-02 l.l3E-02
Bronchi 4.20E+OO 3.36E-OI 3.74E-OI 7o48E-OI 4o43E-O\3.97E-OI
Effective 2.97E-OI 2.23E-02 2048E-02 5.23E-02 3.22E-02 2.88E-02
Adult Bone 2.70E-OI 4.04E-03 4.33E-03 3.96E-02 3.76E-02 3.27E-02
Avg.Lung 6.77E-02 2047E-03 2.69E-03 l.l8E-02 9.87E-03 8.70E-03
Bronchi 4.20E+OO 3.36E-O\3.74E-O\7o48E-O I 4o43E-OI 3.97E-OI
Effective 1.78E-OI 8.36E-03 8.50E-03 1.99E-02 1.22E-02 1.21 E-02
Infant Bone 1.92E-O I l.l7E-03 1.22E-03 1.43E-02 1.28E-02 1.30E-02
Avg.Lung 6.25E-02 8.95E-04 9.22E-04 8.79E-03 7.70E-03 7.80E-03
Bronchi 1.87E+OO 1.25E-OI 1.27E-OI 2.53E-OI 1.40E-O\1.38E-O\
Effective 1.46E-OI 8.34E-03 8049E-03 1.94E-02 l.l7E-02 l.l6E-02-
Child Bone 1.3\E-OI 1.34E-03 1.39E-03 1.65E-02 1.48E-02 1.51E-02
Avg.Lung 7.09E-02 l.l5E-03 l.l9E-03 I.08E-02 9.42E-03 9.59E-03
Blanding Bronchi 1.87E+OO 1.25E-O\1.27E-O I 2.53E-OI 1.40E-OI 1.38E-OI
Effective 1.49E-OI 8.37E-03 8.52E-03 2.00E-02 1.23E-02 1.22E-02
Teenage Bone 4.19E-O\2.74E-03 2.88E-03 4.92E-02 4049E-02 4.60E-02
Avg.Lung 5.74E-02 l.lOE-03 l.l4E-03 8.8\E-03 7.54E-03 7.67E-03
Bronchi 1.87E+OO 1.25E-OI l.27E-OI 2.53E-OI 1.40E-OI 1.38E-OJ
Effective 1.40E-OI 8.33E-03 8047E-03 1.89E-02 l.l3E-02 l.l2E-02
Adult Bone 1.93E-OI I.79E-03 1.87E-03 2.56E-02 2.3\E-02 2.35E-02
Avg.Lung 4.34E-02 9.99E-04 I.03E-03 6.58E-03 5048E-03 5.56E-03
Bronchi 1.87E+OO 1.25E-OI 1.27E-O\2.53E-OI 1.40E-OI 1.38E-OI
34489-10 -FINAL-April 2008 C-9 SENES Consultants Limited
Proposed Development ofNew Tailings Ce!'4Bfor White Mesa Uranium Mill
C.2.2 40 CFR 190 Regulatory Compliance
TABLE C.2-2
40 CFR 190 ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Group -(including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Ce1l4A Ce1l4B
Effective l.33E+OO O.OOE+OO O.OOE+OO 3.15E-02 2.63E-02 1.97E-02
Infant Bone 4.5IE+OO O.OOE+OO O.OOE+OO l.38E-OI 1.16E-OI 8.63E-02
Avg.Lnng 1.10E+OO O.OOE+OO O.OOE+OO 7.22E-02 6.07E-02 4.59E-02
Bronchi 2.37E-03 O.OOE+OO O.OOE+OO 5.96E-05 4.90E-05 3.59E-05
Effective 5.40E-OI O.OOE+OO O.OOE+OO 2.84E-02 2.35E-02 1.74E-02
Child Bone 3.06E+OO O.OOE+OO O.OOE+OO 1.73E-OI 1.44E-OI l.07E-OI
Nearest Ayg.Lung 1.49E+OO O.OOE+OO O.OOE+OO l.07E-OI 8.86E-02 6.55E-02
Potential Bronchi 2.37E-03 O.OOE+OO O.OOE+OO 5.96E-05 4.90E-05 3.59E-05
Resident Effective 6.36E-OI O.OOE+OO O.OOE+OO 3.71E-02 3.07E-02 2.26E-02
(BHV-I)Bone 1.1IE+OI O.OOE+OO O.OOE+OO 5.95E-OI 4.9IE-OI 3.6IE-OITeenageAvg.Lung 1.17E+OO O.OOE+OO O.OOE+OO 8.48E-02 7.0IE-02 5.16E-02
Bronchi 2.37E-03 O.OOE+OO O.OOE+OO 5.96E-05 4.90E-05 3.59E-05
Effective 3.72E-OI O.OOE+OO O.OOE+OO 2.29E-02 1.89E-02 1.40E-02
Adult Bone 4.80E+OO O.OOE+OO O.OOE+OO 2.88E-O I 2.38E-OI 1.76E-OI
Avg.Lung 7.89E-OI O.OOE+OO O.OOE+OO 5.70E-02 4.72E-02 3.48E-02
Bronchi 2.37E-03 O.OOE+OO O.OOE+OO 5.96E-05 4.90E-05 3.59E-05
Effective 1.90E-OI O.OOE+OO O.OOE+OO 8.54E-03 7.63E-03 7.59E-03
Infant Bone 6.49E-OI O.OOE+OO O.OOE+OO 3.74E-02 3.34E-02 3.33E-02
Avg.Lung 1.79E-OI O.OOE+OO O.OOE+OO 2.07E-02 1.86E-02 1.84E-02
Bronchi 3.27E-04 O.OOE+OO O.OOE+OO 1.45E-05 l.28E-05 l.28E-05-
Effective 7.82E-02 O.OOE+OO O.OOE+OO 7.27E-03 6.46E-03 6.46E-03
Child Bone 4.48E-OI O.OOE+OO O.OOE+OO 4.48E-02 3.98E-02 3.98E-02
Nearest Ave.Lung 2.2IE-OI O.OOE+OO O.OOE+OO 2.73E-02 2.42E-02 2.43E-02
Historical Bronchi 3.27E-04 O.OOE+OO O.OOE+OO 1.45E-05 l.28E-05 l.28E-05
Resident Effective 9.llE-02 O.OOE+OO O.OOE+OO 9.26E-03 8.2IE-03 8.22E-03
(BHV-2)-
Bone 1.58E+OO O.OOE+OO O.OOE+OO 1.47E-OI 1.30E-OI I.3IE-OITeenageAvg.Lung 1.7IE-OI O.OOE+OO O.OOE+OO 2.13E-02 1.89E-02 1.90E-02
Bronchi 3.27E-04 O.OOE+OO O.OOE+OO 1.45E-05 l.28E-05 l.28E-05
Effective 5.39E-02 O.OOE+OO O.OOE+OO 5.80E-03 5.15E-03 5.14E-03
Adult Bone 6.93E-OI O.OOE+OO O.OOE+OO 7.27E-02 6.45E-02 6.45E-02
Avg.Lung 1.16E-OI O.OOE+OO O.OOE+OO 1.44E-02 1.28E-02 1.28E-02
Bronchi 3.27E-04 O.OOE+OO O.OOE+OO 1.45E-05 l.28E-05 l.28E-05
34489-10 --FINAL -Apri12008 C-IO SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4B for White Mesa Uranium Mill
TABLE C.2-2 (Cont'd)
40 CFR 190 ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
_.
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Gronp (including Tailings Tailings Tailings Tailings Tailings
ore pads)Cell 2 Cell 3 Cell 3 Ce1l4A Ce1l4B
Effective 7.69E-Ol O.OOE+OO O.OOE+OO 2.23E-02 L89E-02 L6IE-02
Jnfant Bone 2.60E+OO O.OOE+OO O.OOE+OO 9.79E-02 8.29E-02 7.06E-02-
Avg.Lung 6.l9E-Ol O.OOE+OO O.OOE+OO 5.J9E-02 4A3E-02 3.79E-02
Bronchi L36E-03 O.OOE+OO O.OOE+OO 4.IIE-05 3.43E-05 2.90E-05
Effective 3.08E-Ol O.OOE+OO O.OOHOO L98E-02 L67E-02 L4IE-02
Child Bone L75E+OO O.OOHOO O.OOE+OO L2JE-Ol L02E-OJ 8.66E-02
Avg.Lung 8AlE-OJ O.OOHOO O.OOE+OO 7.47E-02 6.27E-02 5.32E-02NearestBronchiL36E-03 O.OOE+OO O.OOE+OO 4.IIE-05 3.43E-05 2.90E-05Actual
Resident Effective 3.62E-Ol O.OOE+OO O.OOE+OO 2.57E-02 2.16E-02 L83E-02
Teenage Bone 6.33E+OO O.OOE+OO O.OOE+OO 4.l3E-Ol 3.44E-Ol 2.91E-Ol
Avg.Lung 6.63E-Ol O.OOE+OO O.OOE+OO 5.90E-02 4.94E-02 4.19E-02
Bronchi L36E-03 O.OOHOO O.OOE+OO 4.11E-05 3.43E-05 2.90E-05
Effective 2.l2E-Ol O.OOE+OO O.OOE+OO L60E-02 L34E-02 LI3E-02
Adult Bone 2.72E+OO O.OOE+OO O.OOHOO 2.0IE-Ol L68E-Ol L42E-Ol
Avg.Lung 4A4E-Ol O.OOE+OO O.OOE+OO 3.97E-02 3.32E-02 2.82E-02
Bronchi L36E-03 O.OOE+OO O.OOE+OO 4.IIE-05 3.43E-05 2.90E-05
Effective 7.59E-02 O.OOE+OO O.OOE+OO 4.83E-03 5.06E-03 4.36E-03.-
Infant Bone 2.59E-Ol O.OOE+OO O.OOE+OO 2.09E-02 2.l9E-02 L89E-02
Avg.Lung 8.79E-02 O.OOE+OO O.OOE+OO L37E-02 L44E-02 L24E-02
Bronchi 9.8IE-05 O.OOE+OO O.OOE+OO 4.94E-06 5.23E-06 4A8E-06
Effective 2.66E-02 O.OOE+OO O.OOE+OO 3.29E-03 3.45E-03 2.96E-03
Child Bone L56E-Ol O.OOE+OO O.OOE+OO 2.10E-02 2.2IE-02 L90E-02
Avg.Lung 7.28E-02 O.OOE+OO O.OOE+OO L23E-02 L29E-02 LIlE-02
White Mesa Bronchi 9.81 E-05 O.OOE+OO O.OOE+OO 4.94E-06 5.23E-06 4A8E-06
Community Efective 2.75E-02 O.OOE+OO O.OOE+OO 3.7IE-03 3.9IE-03 3.36E-03
Teenage Bone 4.73E-Ol O.OOE+OO O.OOE+OO 5.70E-02 6.00E-02 5.l6E-02
Avg.Lung 5.IIE-02 O.OOE+OO O.OOHOO 8.78E-03 9.24E-03 7.95E-03
Bronchi 9.8IE-05 O.OOE+OO O.OOE+OO 4.94E-06 5.23E-06 4A8E-06
Effective L70E-02 O.OOE+OO O.OOE+OO 2A7E-03 2.60E-03 2.24E-03
Adult Bone 2.l9E-Ol O.OOE+OO O.OOE+OO 3.07E-02 3.23E-02 2.79E-02
Avg.Lung 3.60E-02 O.OOE+OO O.OOE+OO 6.l5E-03 6A7E-03 5.56E-03
Bronchi 9.8IE-05 O.OOHOO O.OOE+OO 4.94E-06 5.23E-06 4A8E-06
34489-10 --FINAL -April 2008 C-ll SENES Consultants Limited
Proposed Development ofNew Tailings Cell 4Bfor White Mesa Uranium Mill
TABLE C.2-2 (Cont'd)
40 CFR 190 ANNUAL DOSE COMMITMENTS
(ARIZONA STRIP ORE)
Estimated Dose (mrem/yr)
Location Age Organ Mill Area Interim Soil Cover Active
Gronp (inclnding Tailings Tailings Tailings Tailings Tailings
o,'e pads)Cell 2 Cell 3 Cell 3 Ce1l4A Ce1l4B-_.
Effective 5.12E-02 O.OOE+OO O.OOHOO 2,68E-03 2.57E-03 2.63E-03
Infant Bone 1.73E-OI O.OOE+OO O.OOE+OO 1.17E-02 1.12E-02 1.15E-02---
Avg.Lung 4.77E-02 O.OOE+OO O.OOHOO 6.7IE-03 6.45E-03 6.58E-03
Bronchi 8.07E-05 O.OOE+OO O.OOE+OO 4.16E-06 3.99E-06 4.11E-06
Effective 1.93E-02 O.OOE+OO O.OOE+OO 2.19E-03 2.10E-03 2.15E-03
Child Bone l.lOE-OI O.OOE+OO O.OOHOO 1.35E-02 1.30E-02 1.33E-02
Avg.Lnng 5.25E-02 O.OOE+OO O.OOE+OO 8.2lE-03 7.87E-03 8.07E-03
Blanding Bronchi 8.07E-05 O.OOE+OO O.OOE+OO 4.16E-06 3.99E-06 4.IIE-06
Effective 2.17E-02 O.OOE+OO O.OOE+OO 2.73E-03 2.6IE-03 2.69E-03
Teenage Bone 3.77E-Ol O.OOE+OO O.OOE+OO 4.32E-02 4.14E-02 4.25E-02
Avg,Lung 3.97E-02 O.OOE+OO O.OOHOO 6.3IE-03 6.04E-03 6.2IE-03
Bronchi 8.07E-05 O.OOE+OO O.OOE+OO 4.16E-06 3.99E-06 4.1IE-06
Effective 1.29E-02 O.OOE+OO O.OOE+OO 1.72E-03 1.66E-03 1.70E-03
Adult Bone 1.66E-O1 O.OOHOO O.OOE+OO 2.16E-02 2.07E-02 2.13E-02
Avg.Lung 2.7IE-02 O.OOHOO O.OOE+OO 4.29E-03 4.IIE-03 4.23E-03
Bronchi 8.07E-05 O.OOE+OO O.OOE+OO 4.16E-06 3.99E-06 4.IIE-06
34489-10 ..FINAL-April 2008 C-12 SENES Consultants Limited