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HomeMy WebLinkAboutDRC-2008-002261 - 0901a0688075feaaEnvironmental Report Support of Consfiuction Cell 4b Utatr Prepared by Denison Mines (USA) Corp. t050 tZft Street, Suite 950- Denver, Colorado 80265 White Mesa ium Mill '{*"' %,f Fteceived e'N ;, "'rr)F ;,) ,!*, *o'*ii;'tii,r,i',1, \u,(r . v /\6;'- ,{"/\QazzszEzYZ b April 30,2008 Introduction Denison Mines (USA) Corp. is seeking an amendment to its' Radioactive Materials License, No. UTI900479 in order to obthin UDEQ's approval to construct, operate and (when operations are complete) reclaim a proposed new tailings impoundment at its White Mesa Uranium Mill, Cell 4b. The construction of the Cell 4b is an essential element of future operations at the White Mesa Mill as its construction is necessary in order to continue providing sufficient impoundment surface area for the evaporation ofMill processes water. This Cell also provides additional tailings capacity which is necessary to accommodate the tailing volume associated with routine ore processing operations. While the new cell has not yet been constructed, it was contemplated, described and assessed previously, being a critical component of the initial 1978 NRC- FEIS and attendant licensing of the facility. More specifically, the initial environmental analysis and license application for the facility contanplated six tailing cells; operating cells 1, 2 and 3, as well as 3 additional 80 acre cells, Cells 4, 5 and 6. With the construction of Cell 4a (40 acres), Cell 4b will consume the second 40 acres of the previously authorized 80 acre Cell4. The information required for an amendment to the Mill's Radioactive Materials License is found at R313-24-3. More specifically, the regulations state the following: (l) Each new license application, renewal, or major amendment shallcontain an environmental report describing the proposed action, a statement of its pu{poses, and the environment affected. The environmental report shall present a discussion of the following: (a) An assessment of the radiological and non-radiological impacts to the public health from the activities to be conducted pursuant to the license or amendment; O) An assessment of any impact on waterways and groundwater resulting from the activities conducted pursuant to the license or amendment; (c) Consideration of alternatives, including altemative sites and engineering methods, to the activities to be conducted pursuant to the license or amendment; and (d) Consideration of the long-term impacts including decommissioning, decontamination, and reclamation impacts, associated with activities to be conducted pursuant to the license or amendment. In order to fulfill the requirements above, Denison considered and used the information topics and format cited by NRC in its guidance document NUREG 1359 for its recent License Renewal Application. Because the Renewal Application provided current environmental information and assessments, the scope of this Environmental Report can be limited in some respects, focusing on pathways and assessments directly related to theconskuction of the new tailings cell. Accordingly topical headings suggested byNUREG 1359 have been included in this document; however, where p.*io*ty providei information is sufficient and unaffected by this bmendment request, the prior information is incorporated by reference. Denison's assessment of the pathways to be considered for construction of cell 4b is principally focused on the examination of potential airborne releases from the pond and the groundwater considerations tlpically attendant to the design of a tailing cell. It is important to note that UDEQ has approved the design andconstruction of directly adjacent and nearly completed Cell 4a. The liner design andunderllng ground conditions for cell 4b me identical to those of cell 4a. . Table of Contents lntroduction Table of Contents lndex of Figures.1.0 Site Location and Layout.2.O Climate and Meteorology... 1.1 Regional Climate. 1.2 Onsite Monitoring Program... 3.0 Use of Adjacent Lands and Water. 4.0 Population Distribution and Socioeconomic Profile. 5.0 Topography...... i....... 6.0 Geologic Setting... 6.1 Regional Geology... 6.2 Iocal Geology.6.3 Site-Specific Geologic Setting.. 7.0 Hydrologic Setting 7.1 Perched Zone Hydrogeology. 7.2 Perched Groundwater Flow..7.3 Perched Hydrogeology (Down-gradient of Tailings Cells..7.4 GroundwaterQuality. 8.0 Ecological Resources and Biota. 8.1 Te,rrestial. 8.2 Aquatic and Wetland Biota..... 9.0 Background Radiological and Non-Radiological Characteristics.......... 10.0 Environme,ntal Effects Related Directly to the Construction of Cell 4bl0.l Groundwater Pathway Impact... 10.2 Proposed Additional Groundwater Monitoring.... 10.3 Radiological Impact Related Directly to the Construction of Cell4b 10.4 Radiological Monitoring Assessment... I 1.0 Alternatives..... I1.1 Issuance of Amendme,nt for Cell 4b.... I1.2 No Action Alternative I I .3 Alternatives Considered But Eliminated..... I I.4 Cumulative Effects...... 11.5 Comparison of Predicted Environmental Impacts. 11.6 Updates and Changes to Factors That May Cause Reconsideration of Altematives....... 12.0 Costs and Benefits...... 13.0 Mitigaiton of Impacts... 14.0 Long Term Impacts.... Appendix A Site Hydrogeology Estimation Of Groundwater Travel Times and Recommended Additional Monitoring Wells For Proposed Tailings Cell4BWhite Mesa Uranium Mill Site Near Blanding, Utah Iiii iv 1 I I 4 4 6 8 8 8 9 9 t2 t2 l5 l5 19 23 23 26 26 26 27 27 28 30 30 31 3l 32 33 33 33 34 34 35 TT Appendix B Dose Assessment Pertaining to the Proposed Development of New Tailings Cells For the White Mesa Uranium Mill, SENES Consultants, Hydro Geo Chem, Inc Appendix C Review of Environmental Monitoring Program, SENES Condultants Index of Fisures Fisure Figure I Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 Figure 8 Figure 9 Figure l0 Figure I I Figure 12 Location Map White Mesa Mill White Mesa Mill Land Map White Mesa Wind Rose Population in the Project Vicinity Local Topography Generalized Stratigraphy of Whit Mesa Mill Approximate Elevation Top of Brushy Basin Kriged 4ft Quarter Water Levels Approximate Location of Ruin Spring Depth to Perched Water Stock Watering Pond Locations Reclamation Cover Grading Plan for Cell 4b Page 2 J 5 7 9 l0 l3 t6 t7 l8 20 36 lv 1.0 Site Location and Layout The Mill is regionally located in central San Juan County, Utah, approximately 6 miles (9.5 km) south of the city of Blanding. The Mill can be reached by taking a private road for approximately 0.5 miles west of Utah state Highway l9l. See Figure 1. Within San Juan County, the Mill is located on fee land and mill site claims, covering approximately 5,415 acres , encompassing all orpart of Sections 21,22,27,28,29,32, and 33 of T37S, P.22F,, and Sections 4, 5, 6, 8,9, and 16 of T38S, P.22F,, Salt Lake Base and Meridian. See Figure 2. All operations authorizedby the License are conducted within the confines of the existing site boundary. The milling facility currently occupies approximately 50 acres and the current tailings disposal cells encompass another 250 acres. See Figure 2. The resident currently nearest to the milling facility is located approximately 1.2 miles (1.9 km) north of the Mill site, just north of air sampling station BHV-I. See Figure 2. 2.0 Climate and Meteorolory 2.1 Reeional Climate The climate of southeastern Utah is classified as dry to arid continental. Although varying somewhat with elevation and terrain, the climate in the vicinity of the Mill can be considered as semi-arid with normal annual precipitation of about 13.4 inches. Most precipitation is in the form of rain with snowfall accounting for about 29o/o of the annual total precipitation. There are two separate rainfall seasons in the region, the first in late summer and early autumn (August to October) and the second during the winter months (Decernber to March). The mean annual relative humidity is about 44 percent and is normally highest in January and lowest in July. The average annual Class A pan evaporation rate is 68 inches (National Oceanic and Atmospheric Administration and U.S. Department of Commerce, 1977), with the largest evaporation rate typically occurring in July. This evaporation rate is not appropriate for determining water balance requirements for the tailings management system and must be reduced by the Class A pan coefficient to determine the later evaporation rate. Values of pan coefficients range from 600/o to 8lo/o. Denison assumes for a water balance calculations an average value of TOYo to obtain an annual lake evaporation rate for the Mill area of 47.6 inches. Given the annual average precipitation rate of 13.4 inches, the net evaporation rate is 34.2 inches per year. BItt 'JLITr Erlt*t 3a,L E.t*.* aoI {i,, T,; J J .: a ):: 3) f s Bg a $t fi I T I E! Fr!g ti 24 ! ,s I 'ilo'>'tt I'i ( -f --lo \.. i[Ji ,\ zs t.. .o ! | (*i\. -.\ t --r" fr( \.,1,''j_.1, /:R: _--=a-_-LIl}r -. -l-e;-i-E.q L,.o^ i (' ,'io. Ytil/',u irt I i '\rW;| t1 a'il 21 'v3 -,:e ( l'l,t-') lit: ' 'r\rr..rrlr_f 7- t I.ftt' ',t(12 i .1,F- - - F i i+ -,., - -iF- it ""-" l+Il z@o lo I:\ or"* I i\ 4t i't;''t. - 1 q'r'34. + e :,-'. I {r$;_r 7 /jti{r ii-.a.f ?^ \. .f, ,: l:r z rii l)..fr\ L-'.'taa 'l_ l.)r .n*i It^ \ _l_ I _t 1 J{t" (.,I 1s tJ.t?b,t I 'dr, r):n Property Boundery Roseruetlon Boundary Canyon Rlm Denison Mines (USA) Corp. Figure 2 White Mesa Mill Land Map-aar lrII The weather in the Blanding area is typified by warm summers and cold winters. The mean annual temperature in Blanding is about 50" (F). January is usually the coldest month and July is usually the warmest month. Winds are usually light to moderate in the area during all seasons, although occasional stronger winds may occur in the late winter and spring. The predominant winds are from the north through north-east (approximately 30 percent of the time) and from the south through south-west (about 25 percent of the time). Winds are generally less than 15 mph, with wind speeds faster than 25 mph occurring less than one percent of the time. The National Weather Service Station in Blanding, Utah is located about 6.25 miles north of the Mill. Data from the station is considered representative of the local weather conditions (1978 ER, Section2.7.2). However, as an element of the pre-construction baseline study and ongoing monitoring programs, the Mill operates an onsite meteorological station, described in greater detail below. Further details about weather and climate conditions are provided in the 1978 ER (Section 2.7) and in the FES (Section 2.1). The 1978 ER and FEIS are resource documents, incorporated here by reference. 2.2 On Site Monitorins Proqram On-site meteorological monitoring at the Mill was initiated in early 1977 and continues today. The original purpose of the meteorological monitoring program was to document the regional atmospheric baseline and to provide data to assist in assessing potential air quality and radiological impacts arising from operation of the Mill. After the Mill construction was completed, the monitoring programs were modified to facilitate the assessment of Mill operations. The current meteorological monitoring program includes data collection for wind speed, wind direction, atmospheric stability according to the standard Pasquill scheme (via measurernents of deviations in wind direction, referred to as sigma-theta), and precipitation as either rain or snow. The recorded on-site meteorological conditions are reported to Denison on a serni-annual basis and are described in semi-annual reports prepared for Denison and maintained at the Mill. Figure 3 shows the windrose for the Mill site during the period of January - December 2007, the most recent full year of compiled meteorological data. 3.0 Use of Adjacent Lands and Water Approximately 65.8oh of San Juan County is federally owned land administered by the U.S. Bureau of Land Management, the National Park Service, and the U.S. Forest Service. Primary land uses include livestock grazing, wildlife range, recreation, and exploration for minerals, oil, and gas. Approximately 22oh of the county is Native American land owned either by the Navajo Nation or the Ute Mountain Ute Tribe. The area within 5 miles of the Mill site is predominantly range land owned by Blanding residents. The Mill site, including tailings cells, encompasses approximately 3 00 acres. 4.0 A more detailed discussion of land use at the Mill site, in surrounding areas, and in southeastern Utah, is presented in the FES (Section 2.5). Results of archeological studies conducted at the site and in the surrounding areas as part of the 1978 ER are also documented in the FES (Section 2.s.2.3). Population Distribution and Socioeconomic Profile Demographic information is generally derived from information obtained by the U.S. Census Bureau. These records are updated on a five year frequency for population centers which exceed 65,000 people and on a ten year frequency for lesser populations. As such, the local population update for the area of interest was last recorded in the year 2000, and it is that data base which was utilized to formulate the danographic information provided in the recent license renewal effort and this report. According to the 2000 census, the population density of San Juan County, in which the Mill is located, is 1.8 individuals per square mile. By comparison, the statewide density is greater than27.2 persons per square mile. The town of Blanding, Utah, approximately 6 miles north of the Mill, is the largest population center near the Mill site, with 3,162 persons. Approximately 5 miles southeast of the Mill site is the White Mesa community, where approximately 277 Ute Mountain Ute tribal mernbers reside. See Figure 4. The Navajo Reservation is located approximately 19 miles southeast of the Mill. The nearest community on the Navajo Reservation is Montezuma Creek, a community of approximately 507 individuals in Utah. The nearest resident to the Mill is located approximately 1.5 miles to the north of the Mill, near air monitoring station BHV-I. Table I provides population centers located within 50 miles of the Mill site. Table l-Population Centers Within 50 Miles of the Mill Site Populetion Center 2000 Population Distance From Siteo (miles) Blandine. UT 3.162 6 White Mesa. UT 27',t 4 Bluff. UT 320 l5 Montezuma Creek. UT 507 20 Aneth. UT s98 27 Mexican Hat. UT 88 30 Monticello- UT 1.958 2',1 Eastland/Ucolo. UT 249'32 Dove Creek, CO 698 37 Towaoc. CO 1.097 50 '2ooo census 2 Approproximate distance from Mill site by air 3 Based on l97E population estimate San Juan County, Utah, is the largest and poorest county in Utah. As of Decernber 2006, the unernployment rate in San Juan County was 4.9yo, compared to 2.60/o for Utah as a whole, and 4.5o/o for the nation as a whole. When operating, the Mill is one of the largest private employers in San Juan County, ernploying up to 60-140 full time anployees. As {T ! B B 3t fa !{ti iItI? I I ! !r iI sC/U.Eat2r!--- I}l[,Es PROPERTYBOI'NDARY RESERVANOil BOI'T{DARY CANYOOTIRIM Denison Mines (USA) Corp Figure 4 Population in The Project Vicinity 2000 Ce,nsus such, the Mills employees represent a significant economic base for the city of Blanding and rural residents of San Juan County. In addition, the Company pays local taxes to San Juan County, further supporting the development of the local economic base. The Mill also provides income to local minorities, typically ernploying a high percentage of minority workers rangrng from 45-75olo Native Americans Since its inception in 1980, the Mill has run on a campaign basis, in each case rernaining on standby pending accumulation of sufftcient ore stockpiles to justify a milling campaign. Ctrrently, Mill employees are predominantly residents of San Juan County, or residents of neighboring counties who commute to the Mill on a daily basis. Historically, the Mill has drawn upon such residents of San Juan County and neighboring counties for each milling campaign, rather than relying upon an influx of workers to the area. As a result, Mill campaigns have not given rise to any unusual demands on public services or resulted in any cultural or socioeconomic issues for the surrounding areas- 5.0 Topography The Mill site is located on a gently sloping mesa that, from the air, appears similar to a peninsula, as it is surrounded by steep canyons and washes and is connected to the Abajo Mountains to the north by a narrow neck of land. On the mesa, the topography is relatively flat, sloping at less than one (1) percent to the south and nearly horizontal from east to west. See Figure 5. 6.0 Geologic Seffing 6.1 Regional Geoloey The Mill site lies within a region designated as the Canyon Lands section of the Colorado Plateau physiographic province. Elevations in the region range from approximately 3,000 feet in the boffom of canyons to over 11,000 feet among the peaks of the Henry, Abajo and La Sal Mountains. The average elevation for the area, excluding deeper canyons and isolated mountain peaks, is about 5,000 feet. The sedimentary rocks exposed in southeastern Utah have a total thickness of approximately 6,000 to 7,000 feet. These sedimentary units range in age from Pennsylvanian to Late Cretaceous; older rock units which underlie those of Pennsylvanian age are not exposed in the Mill site area. Structural features in the Mill site area have been divided into three main categories on the basis of origin or mechanism of the stress that created the structure. These categories are: (l) structures related to large-scale regional uplifting or downwarping directly related to movernents in the basement complex (the Monument Uplift and the Blanding Basin); (2) structures due to diapiric deformation of thick sequences of evaporate deposits, salt plugs and salt anticlines (the Paradox Fold and Fault Belt); and (3) structures formed due to magmatic intrusions (the Abajo Mountains). A generalized stratigraphic column for the region is provided as Figure 6. a\$tf!t ttilll2lcrLfffib*rrilrrflffiCidarur,ltalt-'lltE\foirt.aJr',,Ftal.?{-[2natl0fi7t3,{,tldn4,l&ic ,Dt, tt r l, Frcm USGS 7.5 mlnule quad ahest tor Blact Mesa Denison Mines (USA) Corp N t o 1000 2000 3000 SCALE IN FEET -I PROPERTYBOUNDARY Figure 5 Local Topography And Location of Ruin Spring oourfilx Aro EoLIAN SAND - Ho;p;1tt REDorsH nnil VEFY = = = = = = {AtrCUS_SmtS - =s}rAuE. rcHr cRAy. soFT sAilDSrOflE OrxRz. ttc+{t }tl'Lor mom{-POORLY E'RIED. IRON OOilCRE^IIOiIS.rEU iOI'RATED OIXRI1I. I,IGTfI GRAY TO UGHr BROU?{. CROSS-BEDOED. OOitcl,rOxERAItc.Pq)RLY SORIED NIERBEDOTD W1THGMY-GREEN SMI.,E -T- I II st{ tE. cRAy. cRAy-cREEN. AilD ptnpLE.J S|LW t{ PART U{TH SOUE SANDSIONEI IENSES I =lolFI<t =lEl9l sAilDsroiG. AR(osrc. ttLrory ro cREENTsH* | ct^Y. Rt{E TO COARSE GRAfi{ED. T,TIIRBEDDEO-l wmt cRtEiltslt-cR^y To Reoosx-anowngl sH{.E EI 5l sHr..., REDD.H-.RA' srLTy ro sANDy = i ilrtRtrDDm ufiH sAilDSIoflE. ARt(OStc.-l R[DD6H-cRAv. To v€rlor-BRouN. nNi-I TO TiEDUU-GRANED-t- II smosronq c[rARt1z. yur.outsm-ToI REDO|SI| BROnil. FrNE-To oorRsE-I GRATNE) tirIEREEDDtD WIIH REDO|SH- IGRAY sfrat SANDSIIh|E, RED-BROrVil. THtil-BtDDED. wIH RIPPI,"E T^Rrc. ARGITTCEOI,,S UIIH SHATEilEREGDS sAr{DstonE. auFrz fttm To cRAnsH BROtrN-. XAS$IG, CRoSS-BEDD$. F|NE- TO T'EDruT'-GMIIGD sAr{DsloNE. atnRTZ, UOHT tEtfOUlSH- BROIVT{ rc UGHT-GR^Y AilO ${M. TAJSSrI€.cRoss-BootD, FRTAETE. Ftr{E- Io IIEDIIJT-GMIiIED Denison Mines (USA) Corp Figure 6 Generalized Stratigraphy of White Mesa Mill DAKOTA SANDSTONE BURRO CANYON FORMATION BRUSHY BASIN MEMBER WESTWATER CANYON MEMBER RECAPTURE MEMBER SALT WASH MEMBER SUMMER^/ILLE FORMATION ENTRADA SANDSTONE NAVA'O SANDSTONE @at!zY9-F IJ =og. (L(L \\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\\ tlttttttttttt,ttrttttttlttl Scction ncor Wotcr WcllTokcn from f E Est: + Tdr sd ;tI*Ib ia!I T E EttI5 Ia Er--. I3rt 9rljI The Summerville Formation, Entrada Sandstone, and Navajo Sandstone are the deepest units of concern encountered at the site. 6-2 Local Geolosl/ The Mill site is located on thb western edge of the Blanding Basin, sometimes referred to as the Great Sage Plain, lyrng east of the north/south-trending Monument Uplift, south of the Abajo Mountains and adjacent to the northwest-trending Paradox Fold and Fault Belt. The AbajoMountains are the most prominent topographic feature in the region, rising over 4,000 ft above the surface of the plain. The lithology of the immediate area is composed olthousands of feet ofmulti-colored pre-Tertiary age marine and non-marine sedimentary rocks. Erosion on theregionally-uplifted sedimentary strata has produced an array of eroded canyons and mesas. The Mill is more specifically located on White Mesa and rests on alluvial windblown silt and sand which covers sandstones and shales of Jurassic and Cretaceous age. The surface of the mesa is nearly flat, with a surface relief of 98 ft. The maximum relief between White Mesa and the adjacent Cottonwood Canyon is about 750 ft. 6.3 Site-Specific Geolosic Settine The Mill is located within the Blanding Basin of the Colorado Plateau physiographic province. Typical of large portions of the Colorado Plateau province, the rocks underlying thi site arerelatively underformed. The average elevation of the site is approximatety S,OOO ft (1,707 m) above mean sea level (amsl). The site is underlain by unconsolidated alluvium and indurated sedimentary rocks consistingprimarily of sandstone and shale. The indurated rocks are relatively flat lying with dipsgenerally less than 3". The alluvial materials consist mostly of aeolian silts and fine-grainid aeolian sands with a thickness varying from a few feet to as much as 25 to 30 ft (7.6 to 9.1 m)across the site- The alluvium is underlain by the Dakota Sandstone and Burro Canyon Formation, which are sandstones having a total thickness rangrng from approximately IOO to i+Oft (31 to 43 m). Beneath the Burro Canyon Formation lies the Morrison formatiorl consisting,in descending order, of the Brushy Basin Member, the Westwater Canyon Member, the Recapture Member, and the Salt Wash Member. The Brushy Basin and Recapture Members ofthe Morrison Formation, classified as shales, are very fine-grained and Lurr" u very lowpermeability. The Westwater Canyon and Salt Wash Members also have a low average verticalpermeability due to the presence of interbedded shales. See Figure 6 for a generalized stratigraphic column for the region. Beneath the Morrison Formation lies the Summerville Formation, an argillaceous sandstone withinterbedded shales, and the Entrada Sandstone. Beneath the Entrada lies the Navajo Sandstone. The Navajo and Entrada Sandstones constitute the primary aquifer in the area of the site. TheEntrada and Navajo Sandstones are separated from the Burro Canyon Formation by approximately 1,000 to 1,100 ft (305 to 335 m) of materials having a low average verticalpermeability. Groundwater within this system is under ll artesian pressure in the vicinity of the site, and is used only as a secondary source of water at the site. 7.0 HydrogeologicSetting The site is located within a region that has a dry to arid continental climate, with average annual precipitation of approximately 13.4 in. Recharge to aquifers occurs primarily along the mountain fronts (for example, the Henry, Abajo, and La Sal Mountains), and along the flanks of folds such as Comb Ridge Monocline. Although the water quality and productivity of the Navajo/Entrada aquifer are generally good, the depth of the aquifer (approximately 1,200 ft below land surface (bls)) makes access difficult. The Navajo/Entrada aquifer is capable of yielding significant quantities of water to wells (hundreds of gallons per minute (gpm)). Water in wells completed across these units at the site rises approximately 800 ft above the base of the overlfng Summerville Formation. 7.1 Perched Zone Hydroeeoloey Perched groundwater beneath the site occurs primarily within the Burro Canyon Formation. Perched groundwater at the site has a generally low quality due to high total dissolved solids (TDS) in the range of 1,200 to 5,000 milligrams per liter (mdL), and is used primarily for stock watering and irrigation in the areas upgradient (north) of the site, The saturated thickness of the perched water zone generally increases to the north of the site, increasing the yield of the perched zone to wells installed north of the site. Perched water is supported within the Burro Canyon Formation by the underlying, fine-grained Brushy Basin Member. Figure 7 is a contour map showing the approximate elevation of the contact of the Burro Canyon Formation with the Brushy Basin Manber, which essentially forms the base of the perched water zone at the site. Contact elevations are based on monitoring well drilling and geophysical logs and surveyed land surface elevations. As indicated, the contact generally dips to the south/southwest beneath the site. The permeability of the Dakota Sandstone and Burro Canyon Formation at the site is generally low. No significant joints or fractures within the Dakota Sandstone or Burro Canyon Formation have been documented in any wells or borings installed across the site (Ifuight Pi6sold, 1998). Any fractures observed in cores collected from site borings are typically cemented, showing no open space. Based on samples collected during installation of wells MW-16 and MW-17 (the locations of the various monitoring wells are indicated on Figure 7), located immediately downgradient of the tailings cells at the site, porosities of the Dakota Sandstone range from 13.4Yo to 260/o, averaging 20Yo, and water saturations range from 3.7o/o to 27.2Yo, averaging l3.5yo- The average volumetric water content is approximately 3Yo. The permeability of the Dakota Sandstone based on packer tests in borings installed at the site ranges from 2.718-06 centimeters per second (cm/s) to 9.128-04 cmls, with a geometric average of 3.89E-05 cm/s. t2 The average porosity of the Burro Canyon Formation is similar to that of the Dakota Sandstone. Based on samples collected from the Burro Canyon Formation at MW-16, located immediately downgradient of the tailings cells at the site, porosity ranges from 2o/o to 29.lYo, averaging l8.3oh, and water saturations of unsaturated materials range from 0.6% to 77.2Yo, averaging 23.4yo. Titan, 1994, reported that the hydraulic conductivity of the ilurro Canyon Formation ranges from l.9E-07 to 1.6E-03 cm/s, with a geometric mean of l.lE-05 cm,/s, based on the results of 12 pump/recovery tests performed in monitoring wells and 30 packer tests performed in borings prior to that time. Hydraulic testing of wells Mw-I, Mw-3, Mw-5, Mw-17, Mw-18, Mw-19, Mw-20, and MW- 22 duing the week of July 8, 2002, yielded average perched zone permeabilities ranging from approximately 4.0E-07 cm/s to 5.0E-04 cm./s, similar to the range reported by previous investigators at the site (HGC, 2002). Downgradient (south to southwest) of the tailings cells, average perched zone permeabilities based on tests at MW-3, MW-5, MW-17, MW-20, and MW-22 ranged from approximately 4-08-07 to 4.0E-05 cmls. Permeability estimates were based on pump/recovery and slug tests analyzed using several different methodologies. A number of temporary monitoring wells have been installed at the site to investigate elevated concentrations of chloroform initially discovered at well MW-4 in 1999. Some of the conglomeratic zones encountered within the perched zone during installation of these wells are believed to be partly continuous or at least associated with a relatively continuous zone of higher permeability (IUSA and HGC, 2001). The higher permeability zone defined by these wells is generally located east to northeast of the tailings cells at the site, and is hydraulically cross- gradient to upgradient of the tailings cells with respect to perched groundwater flow. Relatively high permeabilities measured at MW-11, located on the southeastern margin of the downgradient edge of tailings Cell 3, and at MW-14, located on the downgradient edge of tailings Cell 4, of 1.4E-03 cm/s and 7.58-04 cm/s, respectively (UMETCO,1993), may indicate that this zone extends beneath the southeastern margin of the cells. This zone of higher permeability within the perched water zone does not appear to exist downgradient (south-southwest) of the tailings cells, however. At depths beneath the perched water table, the zone is not evident in lithologiclogs of the southernmost temporary wells TW4-4 and TW4-6 (located east (cross-gradient) of Cell 3), nor is it evident in wells Mw-3, Mw-5, Mw-12, Mw-15, Mw-16, Mw-17, Mw-20, Mw-21,or MW-22, located south to southwest (downgradient) of the tailings cells, based on the lithologic logs or hydraulic testing of the wells. Because of the generally low permeability of the perched zone beneath the site, well yields are typically low (less than 0.5 gpm), although yields of about 2 Wm may be possible in wells intercepting the higher permeability zones on the east side of the site. Sufficient productivity can, in general, only be obtained in areas where the saturated thickness is greater, which is the primary reason that the perched zone has been used on a limited basis as a water supply to the north (upgradient) of the site. t4 7.2 Perched Groundwater Flow Perched groundwater flow at the site is generally to the south/southwest. Figure 8 displays the local perched groundwater elevation contours at the Mill. As indicated, the perched groundwater gradient changes from generally southwesterly in the western portion of the site to generally southerly in the eastern portion of the site. Perched water discharges in springs and seeps along Westwater Creek Canyon and Cottonwood Canyon to the west-southwest of the site, and along Corral Canyon to the east of the site, where the Burro Canyon Formation outcrops- Perched water flowing beneath the tailings cells eventually discharges in springs and seeps located in Westwater Canyon, to the south-southwest of the cells. The primary discharge point for perched water flowing beneath the tailings cells is believed to be Ruin Spring, located approximately 10,000 ft south-southwest of the Mill site, as shown in Figure 9. 7.3 Perched Zone Hydroeeoloev (Beneath and Down-gradient Of the Tailings Cells) As of the 4th Quarter,2006, perched water has been encountered at depths of approximately 50 to 115 ft bls in the vicinity of the tailings cells at the site (Figure l0). Beneath tailings Cell 3, depths to water ranged from approximately 72 ft below top of casing (btoc) east of the cell (at MW-31), to approximately 115 ft btoc at the southwest margin of the cell (at MW-23). Assuming an average depth of the base of tailings Cell 3 of 25 ft below grade, this corresponds to perched water depths of approximately 47 to 90 ft below the base of the cell, or an average depth of approximately 70 feet beneath the base of the cell. The saturated thickness of the perched zone as of the 4th Quarter, 2006 ranged from approximately 94 ft in the northeast portion of the site to less than 5 ft in the southwest portion of the site. Beneath tailings Cell 3, the saturated thickness varies from approximately 49 ft in the easternmost corner of the cell to approximately 6 ft in the westernmost corner of the cell. South- southwest of the tailings cells, the saturated thickness ranges from less than I ft at MW-21 to approximately 25 ft at MW-I7. The average saturated thickness south-southwest of the tailings cells, based on measurements at MW-3, MW-5, MW-12, MW-14, MW-l5, MW-17, and MW- 20, is approximately 14 ft. The average saturated thickness based on measurernents at MW-5, MW-I5, MW-3, and MW-20, which lay close to a line between the center of tailings Cell 3 and Ruin Spring, is approximately 12 ft. By projecting conditions at these wells, the average saturated thickness is estimated to be approximately 10 to 15 ft between MW-20 and Ruin Spring. l5 #( B <{,E \ \\ il fi l/ Slao_ _ rr{a ./{5a50 .//.//////,//z//,//////ilorES: Locetbm md clovettom-lor Tff.il3, Tru.za,and ru&2t m epprcrlmer!Weior htrl lor fWa{ b fom lho OrfiU ourrri. ZOr . n[-., \'-'tl;' \ rl \\\. x,,c N t'\ Gror A \'\\\ 'l' \.r | '\--, S_*+ 0 3000 SCATE IN FEET EXPLANA lo}I MW-A p€rched moniioflng rxell shoHing| 5491 elevalion inlbetanrsl ^ -_-^ tompora?y porchcd mnitoiing rrellv ss Ehowingl olovslion ln feot iltslAEZ-1 perchedplezometcrshowinga 5891 olorrdionin f.et anrCinry€l p€rch€d monltoring wott instalted Aprit,l' 55a5 sirowingotGvation inHrnst a ---- hmporary pcrched monihhg wdl insb{€dv ccrz Aptl, 2005 slrowing atevalion in h.t snst // 03 --7/:.? t,\ ll ll\\\\ *'* ffffi',ffiH'T#Xl##iiffif 1l ;l 1l ll I ll ez 1l 1l tl 1l 1l gl gt 1l 1l Figure 8 Ifuiged 4h Quarter,2OOT Watet Lwels Z:\|trtnrllal{\2007 Ll6E i6ndloolo!il\Es,a!.ffit 1lfl.t-agrirlor3.r{,d{tfu@3.74,W24ad r.3,tlt?n,& tD7, ll r l, From USGS 7.5 minulo quad sheet for BEck llcca Denison Mines (USA) Corp N I Figure 9 White Mesa Mill Approximate [ocation Ruin Spring o lm 20@ 3000 SCAIE IN FEET - PROPERTYBOUNDARY e\rilFrrufrttclailffitnffi rtEr. ntr6tGrtr.a7h ilrt17-Z ef&ildlr}r}l:' ri(&t0t ct, ttrl? P-len o mr-rs &2 \s e P.2 17 fr t/ P.3c8c iltY.tca (DRt1 32 n!tr6. O Llw4u v 2N-6t.]6 s2o 670 \6g 74o o DRy o84 ,s CNtx =, |fii-a a m EXPLANATK)N a tvlW,-1i 97 o84 e 5;' PERCTIED T'O}IITORIi{G WEIL STIOVYIT{O I'EPTHTOWATER IN FEET BTOG TEMPORARY PERCHED T,|oi{ITORI'{G WEIL SFIOWING DEPTH TO WATER IN FEET BTOC PIE:ZOIIETER STIOYING T'EPTH TO WATER lN FEET BTOC N IW , VYILDLIFE FOITID i{oTE: DATA FOR PIEZOTGTERS ARE FROiIAI'GI'SI 2M2 ilmscAt E ria FEEY Denison Mines (USA) Corp. Figure l0 White Mesa Mill Depth to Perched Water Septerrber,2fi)2 Perched zone hydraulic gradients currently range from a maximum of approximately 0.04 feet per foot (fl/ft) immediately northeast of tailings Cell 3 to less than 0.01 ff/ft downgradient of Cell 3, between Cell 3 and MW-20. The average hydraulic gradient between the downgradient edge of tailings Cell 3 and Ruin Spring was approximated by HGC to be approximately 0.012 fl/ft. HGC also estimated a hypothetical worst case average perched zone hydraulic gradient, assuming the perched water elevation to be coincident with the base of tailings Cell 3, to be approximately 0.019 fl/ft. See Section 3.2 of Appendix A. HGC also estimated the average permeability of the perched zone downgradient of tailings Cell 3, based on pump/recovery test and slug test data obtained from perched zone wells located along the downgradient edge of and south of Cell 3, to be between 2.398-05 cm/s and 4.3E-05 cm/s. See Section 3.3 of Appendix A to the February 28, 2007 Environmental Report incorporated here by reference. 7.4 GroundwaterOuality 7.4.1 Entrada/Navajo Aquifer The Entrada and Navajo Sandstones are prolific aquifers beneath and in the vicinity of the site, Water wells at the site are screened in both of these units, and therefore, for the purposes of this discussion, they will be treated as a single aquifer. Water in the Entrada./Navajo Aquifer is under artesian pressure, rising 800 to 900 ft above the top of the Entrada's contact with the overlying Summervillle Formation; static water levels are 390 to 500 ft below ground surface. Within the region, this aquifer is capable of yielding domestic quality water at rates of 150 to 225 grm, and for that reason, it serves as a secondary source of water for the Mill. Additionally, two domestic water supply wells drawing from the Entrada,rNavajo Aquifer are located 4.5 miles southeast of the Mill site on the Ute Mountain Ute Reservation. Although the water quality and productivity of the Navajo/Entrada aquifer are generally good, the depth of the aquifer (>1,000 ft bls) makes access diffrcult. Table 2 is a tabulation of groundwater quality of the Navajo Sandstone aquifer as reported in the FES and subsequent sampling. The total dissolved solids (TDS) range from 244 to 1,110 mg/liter in three samples taken over a period from January 27, 1977, to May 4, 1977. High iron (0.057 mg/liter) concentrations are found in the Navajo Sandstone. Because the Navajo Sandstone aquifer is isolated from the perched groundwater zone by approximately 1,000 to 1,100 ft of materials having a low average vertical permeability, sampling of the Navajo Sandstone is not required under the Mill's previous NRC Point of Compliance monitoring program or under the state's GWDP. However, samples were taken at two other deep aquifer wells (#2 and #5) on site (See Figure ll for the locations of these wells), on June 1,1999 and June 8, 1999, respectively, and the results are included in Table 2. t9 Z:\ffif,t'Eitt2ilrLka*krrCHlcrl5i\Enruricllckton.fifrdt r!3.r'7dilF,,a',T-r,grnaf,,,rrtl,tlts4'&fttoi.rcr. urtT PROPERTY BOUNDARY ,F cttu,3. a mfl-lt P-t&'n 28 o uw-tegt \D m-t6a prvt 32 ltrw'ts ' a mtaa $il-n a 70 EXPLANATION O lvfw-11 97 o84 e !;' w PERCHED T'C{ITORING YYELL STIOWTT{G DEPTH TO WATER IN FEET BTOC TEMPORAMT PERCHED T,ION]TORIIIIG WELL SHC'WING DEPTH TO WATER IN FEET BTOC PIEZOTT,ETER SHOW|I{G I'EPTH TO WATER IN FEET BTOC WILDLIFE FOM) N INOTE: DATA FOR PIEZOMETERS ARE FROMAT'GIJST, ZNz 30@ SCATE IN FEE? Denison Mines (USA) Corp. Figure I I White Mesa Mill Stock Watering Pond Locations Table 2 Water Quality of Groundwater in the Mill Vicinity Parameter FES, Test Well (G2R) ot27t77 -3t23fi811 Well #2 6t0t9gr Well #5 6toSDgr Field Specifi c Conductivity (umhos/cm)310 to 400 Field pH 6.9 to 7 .6 Temperature (oC)ll to 22 Estimated Flow m/hr (eDm)109(20) pH 7.9 to 8.16 Determination. mey'liter TDS (@I8trC)216tolll0 Redox Potential 2ll1o220 Alkalinitv (as CaCOS")180 to 224 Hardness, total (as CaCOr)177 to2O8 Bicarbonate 226 214 Carbonate (as COr)0.0 <l_0 <1.0 Aluminum 0.003 0.058 Aluminum, dissolved <0. I Ammonia (as N)0.0 ro 0.16 <0.05 <0.05 Antimonv <0.001 <0.001 Arsenic- total .007 to 0.014 0.018 <0.001 Barium. total 0.0 to 0.15 0.1l9 0.005 Bervllium <0.001 <0.001 Boron. total <0.1 to 0.1 I Cadmium. total <0.005 to 0.0 <0.001 0.018 Calcium 50.6 39.8 Calcium, dissolved 5l to l12 Chloride 0.0 to 50 <1.0 2.3 Sodium 7.3 9.8 Sodium, dissolved 5.3 to 23 Silver <0.001 <0.001 Silver. dissolved <0.002 to 0.0 Sulfate 28.8 23.6 Sulfate. dissolved (as SOo)17 to 83 Vanadium 0.003 0.003 Vanadium. dissolved <.002 to 0.16 Manganese 0.01l 0.032 Mansanese. dissolved 0.03 to 0.020 Chromium, total 0.02 to 0.0 0.005 0.005 Cooper- total 0.005 to 0.0 0.002 0.086 Fluoride 0. l8 0.18 Fluoride, dissolved 0.1to 0.22 Iron. total 0.35 to 2- l 0.43 0.20 Iron- dissolved 0.30 to 2.3 t Zero ualues (0.0) are below detection lirnits 21 Parameter FES, Test Well (G2R) ot27t77 -3t23fl8t1 Well #2 6tLuggl Welt #5 6t089gl Lead, total 0.02 - 0.0 <0.001 0.018 Masnesium 20.4 21.3 Masnesium. dissolved l5 to 2l Mercury, total <.00002 ro 0.0 <0.001 <0.001 Molvbdenum 0.001 <0.001 Molybdenum. dissolved 0.004 to 0.010 Nickel <0.001 0.004 Nitrate + Nitrate as N <0. l0 <0.10 Nitrate (as N)<.05 to 0-12 Phosphorus. total (as P)<0.01 to 0.03 Potassium 3.1 3.3 Potassium. dissolved 2.4 to 3.2 Selenium <0.001 <0.001 Selenium, dissolved <.005 to 0.0 Silica. dissolved (as SiOr)5.8 to 12 Shontium. total (as U)0.5 to 0.67 Thallium <0.001 <0.001 Uranium. total (as U)<.002 to 0.16 0.0007 o.0042 Uranium, dissolved (as U)<.002 to 0.031 Zinc 0.010 0.126 Zinc, dissolved 0.007 to 0.39 Total Orsanic Carbon l.l to 16 Chemical Oxvsen Demand <l to 66 Oil and Grease I Total Suspended Solids 6 to 1940 <1.0 10.4 Turbidiw 5.56 19. I Determination (pCi/liter) Gross Alpha <1.0 Gross Aloha f orecision 1.6+1.3 to 10.2+2.6 Gross Beta <2.0 Gross Beta * precision 8+8 to 73+19 Radium 226 + orecision 0.3+0.2 Radium 228 <1.0 Ra126 * precision 0.1+-3 to 0.6+0.4 Th-230 + orecision 0.1+0.4 to0.7+2.7 Pb-2 l0 * precision 0.0+4.0 to l.GF2.0 Po-210 * precision 0.Gf0.3 to 0.0+0.8 Source: Adapted from FES Table 2.25 with additional Mill sampling data 7.4.2 Perched Groundwater Zone Perched groundwater in the Dakota/Burro Canyon Formation is used on a limited basis to the north (upgradient) of the site because it is more easily accessible. The quality of the Burro Canyon perched water beneath and downgradient from the site is poor and extremely variable. The concentrations of total dissolved solids (TDS) measured in water sampled from upgradient and downgradient wells range between approximately 1,200 and 5,000 mg/|. Sulfate concentrations measured in three upgradient wells varied between 670 and 1,740 mgll (Titan, 1994). The perched groundwater therefore is used primarily for stock watering and irrigation. 22 The saturated thickness of the perched water zone generally increases to the north of the site. See the Background Groundwater Quality Report: Existing Wells For Denison Mines (USA) Corp.'s White Mesa Mill Site, San Juan County, Utah dated December 2006 prepared by Intera, Inc., Appendix B. At the time of renewal of the Mill license by the NRC in March, 1997 and up until issuance of the Mill's Groundwater Discharge Permit (*GWDP') in March 2005, the Mill implemented a groundwater detection monitoring program to ensure compliance to 10 CFR Part 40, Appendix A, in accordance with the provisions of Mill License condition I1.3A. The detection monitoring program was in accordance with the report entitled, "Points of Compliance, White Mesa Uranium Mill," submitted by letter to the NRC dated October 5,1994. Under that program, the Mill sampled monitoring wells Mw-5, Mw-l1, Mw-12, Mw-14, Mw-15 and MW-l7, on a quarterly basis. Samples were analyzed for chloride, potassium, nickel and uranium, and the results of such sampling were included in the Mill's Semi-Annual Effluent Monitoring Reports that were filed with the NRC up until August 2004 and with the DRC subsequent thereto. Prior to 1997, commencingin 1979, the Mill monitored up to 20 constituents in up to 13 wells. That program was changed to the Points of Compliance Program in 1997 because: . The Mill and tailings system had produced no impacts to the perched zone or deep aquifer; and . The most dependable indicators of water quality and potential cell failure were considered to be chloride, nickel, potassium and natural uranium. 8.0 Ecological Resources and Biota 8.1 Terrestrial a) Flora The natural vegetation presently occurring within a 25-mile (40-km) radius of the Mill site is very similar to that of the region, being characteized by pinyon-juniper woodland intergrading with big sagebrush (Arternisia tridentata) communities. The pinyon-juniper community is dominated by Utah juniper (Juniperus osteosperma) with occurrences of pinyon pine (Pinus edulis) as a codominant or subdominant tree species. The understory of this communitS which is usually quite open, is composed of grasses, forbs, and shrubs that are also found in the big sagebrush communities. Common associates include galleta grass (Hilaria jamesii), green ephedra (Ephedra viridis), and broom snakewood (Gutierrezia sarothrae). The big sagebrush communities occur in deep, well-drained soils on flat terrain, whereas the pinyon-juniper woodland is usually found on shallow rocky soil of exposed canyon ridges and slopes. See Section 2.9 of the 1978 ER. Based on the work completed by Dames & Moore in the 1978 ER, no designated or proposed endangered plant species occur on or near the project site (1978 ER, Section2.8.2.l). Of the 65 proposed endangered species in Utah at that time, six have documented distributions in San Juan 23 County. A careful review of the habitat requirements and known distributions of these species by Dames & Moore in the 1978 ER indicated that, because of the disturbed environment, these species would probably not occur on the project site. The Navajo Sedge has been added to the list as a threatened species since the Dames & Moore study. In completing the 2002 EA, NRC staff contacted wildlife biologists from the BLM and the Utah Wildlife Service to gather local information on the occurrences of additional species surrounding the Mill. In the 2002 EA, NRC staff concluded that the Navajo Sedge has not been observed in the area surrounding Blanding, and is typically found in areas of moisture (2002 EA at 4). b) Fauna Wildlife data were collected by Dames & Moore through four seasons at several locations on theMill site, prior to construction of the Mill. The presence of a species was based on direct observations, trappings and signs such as the occurrence of scat, tracks, or burrows. A total of 174 vertebrate species potentially occur within the vicinity of the Mill (1978 ER, Appendix D), 78 of which were confirmed (1978 ER, Section2.8.2.2). Although seven species of amphibians are thought to occur in the area, the scarcity of surface water limits the use of the site by amphibians. Eleven species of lizards and five snakes potentially occur in the area (1978 ER, Section2.8.2.2). Fifty-six species of birds were observed in the vicinity of the Mill site (1978 ER, Section 2.8.2.2). The food habits of eagles vary depending on the season and the region in which they live. Fish, carrion and waterfowl such as mallard, are consumed by eagles when available to thern. The FES indicates that mallards are both common and permanent in the vicinity of the Mill (FES, Table 2.28). Raptors are prominent in the westem United States. Five species were observed in the vicinity of the site. Although no nests of these species were located at the time of the FES, all (except the golden eagle, Aquila chrysaetos) have suitable nesting habitat in the vicinity of the site. The nest of a prairie falcon (Falco mexicanus) was found about 314 mile (1.2 km) east of the site. Although no sightings were made of this species, members tend to return to the same nests for several years if undisturbed (1978 ER, Section2.8.2.2). Of several mammals that occupy the site, mule deer (Odocoileus hemionus) is the largest species. The deer inhabit the project vicinity and adjacent canyons during winter to feed on the sagebrush and have been observed migrating through the site to Murphy Point (1975 ER, Section 2.8.2.2). Winter deer use of the project vicinity, as measured by browse utilization, is among the heaviest in southeastern Utah at 25 days of use per acre in the pinyon-juniper-sagebrush habitats in the vicinity of the project site. In addition, this area is heavily used as a migration route by deer traveling to Murphy Point to winter. Daily movement during winter periods by deer inhabiting the area has also been observed between Westwater Creek and Murphy Point. The present size of the local deer herd is not known. 24 Other mammals present at the site include the coyote (Canis latrans), red fox (Vulpes vulpes), gray fox (Urocyon cineroargenteus), striped skunk (Mephitis mephitis), badger (taxidea taxus), longtail weasel (Mustela frenata), and bobcat (Lynx rufus). Nine species of rodents were trapped or observed on the site, the deer mouse (Peromyscus maniculatus) having the greatest distribution and abundance. Although desert cottontails (Sylvilagus auduboni) were uncommon in 1977, black-tailed jackrabbits (Lepus californicus) were seen during all seasons. In the 2002 EA, NRC staff noted that, in the vicinity of the site, the U.S. Fish and Wildlife Service had provided the list set out in Table 3.12-1, of the endangered, threatened, and candidate species that may occur in the area around the site. Table 3 Endangered, Threatened and Candidate Species in the Mill Area The2002 EA also noted that, in addition, the species listed on Table 3.12-2 may occur within the Mill area that are managed under Conservation Agreements/Strategies Table 4 Species Managed Under Conservation Agreements/Strategies at the Mill Area For the 2002 EA, NRC staff contacted wildlife biologists from the BLM and the Utah Wildlife Service to gather local information on the occurrences of these additional species surrounding the Mill. NRC staff made the following conclusions (2002 EA p. 4): While the ranges of the bald eagle, peregrine falcon, and willow flycatcher encompass the project area, their likelihood of utilizing the site is extremely low. The black-footed ferret has not been seen in Utah since 1952, and is not expected to occur any longer in the area. The Common Name Scientific Name Status Navaio Sedse Carex specuicola Threatened Bonytail Chub Gila elegans Endangered Colorado Pikeminnow Prvchocheilus lucius Endangered Humoback Chub Gila cvoha Endangered Razorback Sucker Xyrauchen texanus Endaneered Bald Eaele Haliaeetus leucoceohalus Threatened California Condor GvmnoevDs cal i fornianus Endangered Gunnison Sase Grouse Centrocercus minimus Candidate Mexican Spotted Owl Strix occidentalis lucida Threatened Southwestern Willow Flycatcher Empidonax traillii extimus Endansered Western Yellow-billed Cuckoo Cocclrzus americanus occidentalis Candidate Black-footed Ferret Mustela nisripes Endansered Source: 20028A Common Name Scientific Name Colorado River Cutthroat Trout Oncorhynchus clarki oleuriticus Gunnison Sage Grouse Centrocercus minimus Source:2002F,A 25 Califomia Condor has only rarely been spotted in the area of Moab, Utah, (70 miles north) and around Lake Powell (approximately 50 miles south). The Mexican Spotted Owl is only found in the mountains in Utah, and is not expected to be on the Mesa. The Southwestern Willow Flycatcher, Western Yellow-billed Cuckoo, and Gunnison Sage Grouse are also not expected to be found in the immediate area around the Mill site. 8.2 Aquatic and Wetlands Biota Aquatic habitat at the Mill site ranges temporally from exhemely limited to nonexistent due to the aridity, topography and soil characteristics of the region and consequent dearth of perennial surface water. Two small stockwatering ponds are located on the Mill site a few hundied yards from the ore pad area (See Figure 11). One additional small *wildlife pond'', east of Celi 44, was completed in 1994 to serve as a diversionary feature for migrating waterfowl. Althoughmore properly considered features of the terrestrial environment, these ponds essentiafy represent the total aquatic habitat on the Mill site. These ponds probably harbor algae, insects, other invertebrate forms, and amphibians. They also provide a water source for smajl mammals and birds. Similar epherneral catch and seepage basins are typical and numerous to the northeast of the Mill site and south of Blanding. Aquatic habitat in the Mill vicinity is similarly limited. The three adjacent streams (Corral Creek, Westwater Creek, and an unnamed arm of Cottonwood Wash) are only intermittently active, carrying water primarily in the spring during increased rainfall and snowmelt runofi in the autumn, and briefly during localized but intense electrical storms. lntermittent water flow most tlpically occurs in April, August, and October in those streams. Again, due to the temporary nature of these steams, their contribution to the aquatic habitat of the region is probably limited to providing a water source for wildlife and a temporary habitat for insect and amphibian species. In the 2002F,A, NRC staff concluded that (p. 4) no populations of fish are present on the project site, nor are any known to exist in the immediate area of the site. Four species of fish aesignated as endangered or threatened (the Bonytail Chub, Colorado Pikeminnow, Humpback Chub and Razorback Sucker) occur in the San Juan River 18 miles south of the site, which Dames &Moore noted in the 1978 ER (Section 2.8.2) is the closest habitat suitable for these species. NRCstaff further concluded that there are no discharges of mill effluents to surface waters, and therefore, no impacts are expected for the San Juan River due to operations of the Mill. 9.0 Background Radiological and Non-Radiological Characteristics Background Radiological and Non-Radiological Effects have been evaluated, updated andreported extensively in Denison's February 28, 2OO7 License Renewal Application and accompanying Environmental Report, incorporated here by reference. 10.0 Environmental Effects Related Directly to the Construction of Cell 4b The environmental effects of Cell 4b construction consist of those related to the release of airborne particulate (dusting), radon release from the operating cell, and the impact, if any, on 26 groundwater beneath the pond. In order to evaluate these environmental considerations two separate evaluations were completed, Site Hydrogeologt Estimation Of Groundwater Travel Times and Recommended Additional Monitoring Wells For Proposed Tailings Cell 4BWhite Mesa Uranium Mill Site Near Blanding, Utah, Hydro Geo Chem, Inc., 2008 and Dose Assessment Pertaining to the Proposed Development of New Tailings Cells For the White Mesa Uranium Mill, SENES Consultants, Ltd, 2008. These evaluations are provided as Appendix A and Appendix B, respectively, and are discussed in summary in the pertinent subsections below. 10.1 Groundwater Pathway Impact The evaluation provided by Hydro Geo Chem tnc. finds that travel time for any water exiting the pond to the perched water zone and then to the point(s) of perched zone discharge is very long, far exceeding the time period of milling operations and closure of the tailings cells when little free liquid is available for infiltration through the cell liner systern. More specifically, HGC found that the time for fluids that could be released from the cells to reach the points of seepage and spring formation at ruin spring and Cottonwood seep are on the order of several thousand years. However, this analysis is very conservative in that travel time through the pond liner was not considered, and because the liner systern is robust state-of-the art construction, travel time through the liner is a significant protective factor. [n fact, this aspect has been evaluated extensively by MWH Americas, Inc. in their report Infiltration and Contaminant Transport Modeling Report, White Mesa Mill Site, Blanding (Jtah, November, 2007, incorporated here by reference. The infiltration modeling effort revealed that the construction design for Cells 4a and 4b will meet the "Closed Cell Performance Requirernents" of the Groundwater Discharge Permit at Part 1.D.6. More specifically, MWH concluded that the approved reclamation plan for the cells will meet the following regulatory requirements for a period of not less than 200 years: a) Minimize infiltration of precipitation or other surface water into the tailings, including but not limited to the radon barrier;b) Prevent the accumulation of leachate head within the tailings waste layer that could rise above or over-top the maximum FML liner elevation internal to any disposal cell, i.e. create a "bathtub" effect; and,c) Ensure that groundwater quality at the compliance monitoring wells does not exceed Ground Water Quality Standards or Ground Water Compliance Limits specified in Part 1.C.1 and Table 2 of the Permit. 10.2 ProposedAdditional GroundwaterMgnitorine In order to monitor the performance of Cell 4b, and consistent with EPA Guidance, it was concluded by Hydro Geo Chem Inc. that an additional well or wells will be needed to monitor the Cell's performance at the downgradient edge of the cell. This in addition to the many wells already incorporated into the Groundwater Discharge Permit for the facility. Accordingly, two additional wells are proposed, one at the southwest corner of proposed Cell 4b and one between the southwest corner well and existing well MW-15 (See Figure l0 of Appendix B. These 27 installations will conservatively maintain the approximate existing spacing as defined by the proximity of MW-14 to MW-15 along the downgradient edge of existing Cell4a. 10.3 Radioloeical Impact In February 2007, a dose assessment was prepared for DUSA by SENES Consultants, Ltd. in support of the license renewal application for the mill. 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% U:Os and l.5Yo VzOs) or Arizona Strip (0.637Yo) ores are processed at the mill. In order to evaluate the radiological impact of Cell 4b's operation the prior dose assessment analyses was extended from the previous report of February 2007 to incorporate the dose from the proposed development of new tailings cells anticipated in the future. The results of this extended assessment are provided as Attachment B to this report (Proposed Development of New Tailings cells For The White Mesa (Jranium Mill, SENES, 2008), and reveal that the addition of Cell 4b to the facility will not impact the ability of the facility to comply with regulatory requirements The U.S. 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 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 from the previous report were revised to exclude the tailings cells. The doses from the tailings cells were estimated in separate MILDOS-AREA runs and added to the dose from the mill area and ore pads. Table 4 provides a summary of the source terms included in Phases I and 2 of the development of new tailings cells including Cells 4a and 4b. TABLE 4 SOURCE TERMS INCLUDED IN PHASE 1 AND 2 Source Term Phase I Phase 2 Mill area included included Ore Pads included included Tai ings Cell 2 with Interim Soil Cover included included Tai ings Cell3 active interim soil cover Tai ings Cell4A active active Ta ings Cell48 excluded active 28 The wind erosion and radon release rates from the tailings cells (active and with interim soil cover) were modeled by using a maximal worst case approach. Each active tailings cell was modeled to have an active area of l0 acres (i.e., the maximum expected to be uncovered at any time since it is not possible to predict the diskibution of uncovered tailings between the active cells at any given time. The release rate of wind-eroded tailings dust was estimated for 10 acres. 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 of each cell consistent with NESHAPs. Emissions from 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 R3l3-15- 301(1)(a) requirement that the dose to individual mernbers of the public shall not exceed 100 mrem/yr (radon included). For proposed development of new tailings cells 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, BHV-I (Tables 6.1-1 and 6.1-3) (i.e., effective dose) and is aboutl.4Yo of the R3l3-15-301(1)(a) limit of 100 mrem/yr (radon included) to an individual mernber of the public for Phases I and 2. For proposed development of new tailings cell for the processing of Arizona Strip ore, the total annual effective dose commitrnents were calculated to be a maximum of 3.1 mrem/yr for an infant at the nearest potential resident, BHV-I (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, the predicted annual effective dose commitments for proposed development of new tailings cells during anticipated ore processing operations 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 mernber of the public (U.S. EPA 2002). The 40 CFR 190 doses were also used to dernonstrate compliance with R313-15-101(4) (10 CFR 20.1101(d)) (i.e., the licensee must dernonstrate that total effective dose equivalent to the individual member of the public likely to receive the highest total effective dose equivalent will not exceed l0 mrem/yr (absent of the radon dose). For proposed development of new tailings cells for the processing of Colorado Plateau ore, the 40 CFR 190 annual dose commitrnents were 29 calculated to be a maximum of 4.8 mrem/yr for a teenage at the nearest potential resident, BHV-I (i.e., dose to the bone) and is about lgYo 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 R3l3-15-l0l(4) (l0CFR 20.1101(d)) limit of 10 mrem/yr to the individual member of the public likely to receive the highest total eflective dose equivalent. For Arizona Strip ore, the 40 CFR 190 annual dose commitments were at most 12 mren/yr for a teenage at the nearest potential resident, BHV-I (i.e., dose to the bone) and is well within the 40 CFR 190 dose criterion of 25 mrem/yr for Phases I and 2. Further, the annual effective dose commitments dernonstrate compliance with R3l3-15-101(4) (10 CFR 20.1I01(d)) limit of 10 mrern/yr to the individual member of the public likely to receive the highest total effective dose equivalent. 10.4 Prooosed Radioloeical Monitorine to Accommodate Cell4b Operations As an elernent of evaluating potential off-site doses related to the construction and operation of Cell 4b, Denison commissioned a review of its environmental monitoring programs in order to determine what, if any, additional monitoring would be needed to accommodate the operation of Cell 4b. The review was conducted by SENES Consultants, Ltd who concluded that the current environmental monitoring regime was sufficient and that added monitoring was not warranted due to the operation of Cell 4b. The results of the SENES review are attached here as Appendix C to this report. 11.0 Alternatives The action under consideration is the construction of an already contemplated tailings Cell (Cell 4b) in order accomodate continued operation of the Mill. The alternatives available to the Executive Secretary are to: a) Amend the License to include the construction of Cell 4b with its existing terms and conditions; b) Amend the License to include the construction of Cell 4b with such additional conditions as are considered necessary or appropriate to protect public health, safety and the environment; or c) Deny the addition of Cell 4b construction into the License. As demonstrated in this ER, the environmental impacts associated with construction and operation of Cell 4b do not warrant either limiting the Mill's future operations or denying the Cell 4b construction approval request. As there are no significant public health, safety or environmental impacts associated with the construction of Cell 4b, Denison 30 asselts that alternatives with equal or greater impacts need not be evaluated, and altemative a) is the appropriate alternative for selection. l1.l Issuance of Amendment for Cell 4a The Mill is one of only two operating uranium mills in the Unites States and the only uranium mill on the western slope of the Rocky Mountains. As a result, the Mill is the only currently available opportunity for production of uranium from conventionally mined ore in San Juan County and in the four corners area of the United States. The Mill therefore provides a benefit to the regional community and to the uranium industry as a whole in the United States. The construction of Cell 4b would allow the Mill to continue to provide these benefits for many more years and as contemplated in the original licensing effort. As was dernonstrated in Section 3 of the ER accompanying the 20O7 License Renewal Application, the Mill's equipment, facilities and procedures are adequate to minimize impacts to public health, safety and the environment. More importantly, UDEQ has already approved the construction of Cell 4a which is identical to Cell 4b with regard to its robust and state-of-the-art protective design features. Also, the Mill has operated since its inception in compliance with all applicable regulatory standards and ALARA goals and is capable of continuing to operate in compliance with such standards and goals. In addition to the License, the Mill has been issued a Groundwater Discharge Permit, which provides additional protection for public health and the environment, including a rigorous groundwater monitoring program to monitor and assess the performance of tailings cells associated with the facility. The Mill has demonstrated that it is capable of continuing to operate in a manner that satisfies all regulatory standards and ALARA goals under the existing terms and conditions of the License and GWDP, this amendment application has assessed and proposed additional monitoring necessary to accommodate newly constructed Cell 4b. Based upon these factors and considerations Denison asserts that there is no need to add any additional conditions to the License in order to protect public health, safety or the environment as a result of Cell 4b construction. 11.2 No Action Alternative A "no action" alternative would result in the amendment request being denied and the immediately available processing opportunities for mined uranium ore being lost in the short term, severely impacting independent uranium miners in the area and lessening the United States' capability to respond to the need for uranium for nuclear power generation. Denying the request for construction of Cell 4b severely constrain the utilization of the Mill in the near term and eliminate its ability to operate over the longer term during a time when commodity prices for uranium are favorable, and the dernand for uranium milling capacity is unprecedented. Permitting the Mill to continue processing 3l conventionally mined ore for the recovery of uranium and the construction of Cell 4b will provide the opportunity for regular employment in an economically depressed area of the United States. A large percentage of the workers at the Mill are Native American, and this employment opportunity has significant direct impact in the local Native American community. In addition to the direct hiring of employees at the Mill, local miners and other western United States mining companies require access to hn operating uranium mill. The inability of these mining entities to gain access to local milling services will prevent the mining industry from responding to the current uranium supply shortage. Thus, secondary local economies will not enjoy the benefit of renewed mining income, and national dernand for uranium will continue to be reliant primarily on foreign supplies of uranium for nuclear fuel. In order to respond to the current uranium market, conventional mining companies will be forced to license and construct new uranium milling facilities to engage in conventional ore processing, directly in opposition to the objective of non-proliferation of new uranium mill tailings disposal facilities ernbodied by 10 CFR Part 40 Appendix A, Criterion 2. As has been demonstrated by the forgoing assessments, the impacts associated with the construction and operation of Cell 4b are well within the realm of impacts anticipated in the FES, the 1985 EA and the 1997 EA, and UDEQ's approval of Cell 4b construction will satisff applicable criteria inR313-22-33 and P.3l3-24. As a result, Denison asserts that the Executive Secretary should have no basis for denying the proposed action. I1.3 Altematives Considered But Eliminated a) Consideration of Alternative Sites The Mill is already sited and in existence and has been operating for over 25 years. It is not feasible to consider moving the Mill to an alternative site or to construct additional tailing cells at a different location. Even if that were possible, it has been demonstrated in Section 3 of the February, 2007 ER accompanying the License Renewal Application that the Mill is sited in a good hydrogeologic setting and is otherwise well sited for its operations, including tailings cells contemplated at the time of the Mill's original licensure. This is evident from the fact that the Mill has operated since its inception in compliance with applicable regulatory standards and ALARA goals. If the construction of Cell 4b is not approved as an element of continued milling operations, there can be no assurance that, as an alternative, an equally well-suited site for milling and tailings cell contruction, that complies with the applicable siting requiremants of l0 CFR Part 40 Appendix A, can be identified and obtained. Even if a suitable alternative site were to be identified and obtained, licensing and construction of a new mill and tailings cells could not be accomplished in a time frame that would ensure production could commence in a period of suitable market conditions. Furthermore, as the existing Mill tailings would have to be decommissioned in place, creation of a new mill site would result in unnecessary proliferation of mill tailings disposal facilities in contravention of l0 CFR Part 40 Appendix A, Criterion 2. 32 b) Consideration of Alternative Engineering Methods As will be demonstrated in Section 3, the existing Mill facilities, equipment, procedures and training of personnel have resulted in ttre Mill operating since inception in compliance with all applicable regulatory standards and ALARA goals- Current modeling demonstrates that the Mill is capable of continuing to operate urider the existing terms and conditions of the License in a manner that will continue to comply with such standards and goals. Furthermore, the Mill's GWDP institutes additional protections and engineering controls, including the requirement that any new construction of tailings cells must meet current best available technology standards. Therefore, there is no need to consider alternative engineering methods. The existing equipment and facilities, together with the existing terms and conditions of the License and the GWDP are sufficient to ensure that all applicable requirements will continue to be satisfied. ll.4 Cumulative Effects There Ne no past, present, or reasonably foreseeable future actions which could result in cumulative impacts that have not been conternplated and previously approved under the existing Mill License and the design of Cell4b. As stated throughout this License Amendment request, the Cell 4b construction will result in no activity with potential, significant, incremental impacts to public health, safety or the environment over and above the actions contemplated in the FES, the 1985 EA and the 1997 EA. The activities contemplated with regard to ore processing and disposal of tailings remain unchanged from those previously authorized under the License. I1.5 Comparison of the Predicted Environmental Impacts There have been no observed significant impacts which were not previously quantified and addressed to public health, safety or the environment resulting from the proposed construction of Cell 4b. As there will be no significant changes in Mill operations if the License is amended to accommodate construction of Cell 4b, possible impacts to public health, safety or the environment will not exceed those predicted in the original License application and periodic renewals. 11.6 Updates & Changes to Factors That May Cause Reconsideration of Alternatives As discussed in Section 12 below, Costs and Benefits, there have been no changes to factors that may cause reconsideration of alternatives. There have been no significant changes in the costs associated with operation of the Mill (including its impoundments), and the benefits associated with continued operation and construction of already contemplated tailing cells have become more evident over time as the number of uranium mills has dwindled and the demand for uranium milling service capacity from local miners and the industry as a whole has increased in recent years. Furthermore, no new 33 alternatives to the services provided by identified since the last License renewal in 12.0 Cost and Benefits the Mill and its impoundments have been 1997. Appendix A to NUREG 1569 requires that the applicant for a license renewal describe any updates and changes to the economic costs and benefits for the facility since the last application. There have been no significant changes to the costs associated with the Mill since the last License renewal in 1997. While there will a change to the currently disturbed area as a result of the Cell 4b construction, this additional Cell was conternplated, described and assessed, as a critical component of the initial 1978 NRC-FEIS and attendant licensing of the facility. As indicated in Section 3 of February,2007 ER accompanylng the renewal application, the Mill has operated in accordance with applicable regulatory standards and ALARA goals since its inception, and updated MILDOS AREA modeling indicates that the Mill is capable of continuing to operate well within those standards and goals. There have been no significant demographic changes that have impacted the ability of the Mill to operate in a manner that will result in no significant impacts to public health, safety or the environment. It is expected that continued Mill operations will continue to draw primarily upon the existing work force in the area with little impact on social services. The Mill is one of only two operating uranium mills in the United States and is one of the largest private employers in San Juan County. The benefits of the Mill will continue to be the provision of well-paying jobs to workers in San Juan County and the support of the tax base in that County. Moreover, as the only operating uranium mill on the westem slope of the Rocky Mountains, the Mill is relied upon by the large number of independent uranium miners in San Juan County and the Colorado Plateau as the only feasible uranium mill for their uranium ores. With the recent gap between the supply and demand for uranium and the increases in the price of uranium, the need for continued licensing of the Mill is crucial for such miners and for the uranium industry in the United States as a whole. In sum, the costs associated with the operation of the Mill have not changed significantly, but the benefits have become more evident over time as the number of uranium mills has dwindled and the demand for uranium milling services from local miners and the industry as a whole has increased. 13.0 Mitigation of Impacts NUREG 1569 requires that the ER provide the "results of ef[ectiveness of any mitigation proposed and implemented in the original license". In the case of the White Mesa Mill, there have not been any mitigations proposed or implemented under the License. 34 14.0 Long Term Impacts The long term impacts, including decommissioning, decontamination, and reclamation impacts associated with activities conducted pursuant to the License have been considered in detail in the FES, the Mill's Reclamation Plan, and the 2000 EA prepared by the NRC in connection with the Reclamation Plan. The Mill's Reclamation Plan and financial surety zurangements, as well as the provisions in the Mill's GWDP that relate to final reclamation of the site are described in detail in Section 8 of the February, 2007 License Renewal Application, and are incorporated here by reference. The construction of Cell 4b will not result in any changes to operations at the Mill that would impact decommissioning, decontamination or reclamation aspect associated with Mill activities, or the previous analyses of such aspects. The grading contours and other reclamation features related to closure of Cell4b at site closure are shown in Figure 20. All design features for Cell 4b are included in the Cell4b Design Report prepared by Geosyntec Consultants which was transmitted to UDEQ in January of 2008. 35 SITE ITYDROGEOLOGY ESTIMATION OF GROUI\DWATER TRAVEL TIMES AND RECOMMEiYDED ADDITIONAL MONITORING WELLS FOR PROPOSED TAILINGS CELL 48 WIIITE MESA URANIUM MILL SITE NEAR BLAI\DING, UTAH Prepared f'or: DENTSON MrNES (USA) CORP Independenc e Plaza, Suite 950 1050 lTth Street Denver, Colorado 80265 (303) 628-7798 Prepared by: ITYDRO GEO CHEM,INC. 51 West WeEnore, Suite l0l Tucson, Arizona 85705-1 678 (s20)293-1s00 January 8,2008 2. l. Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H17 I 8000\cell4b\hydrcel14b.doc January 8,2008 TABLE OF CONTENTS INTRODUCTION ............... I SITE HYDROGEOLOGY............. .........32.1 Geologic Setting....... ...................32.2 Hydrogeologic Setting ................42.3 Perched Zone Hydrogeology .........................5 2.3.1 Lithologic and Hydraulic Properties............... .........................6 2.3.1.1 Dakota .-.-.-......-7 2.3.1.2 Burro Canyon .............-.......7 2.3.2 Perched GroundwaterFlow ...............9 PERCHED ZONE HYDROGEOLOGY BENEATH AND DOWNGRADIENT OF THE TAILINGS CELLS ................. 1I3.1 Saturated Thickness .................. I I3.2 Perched WaterFlow.......... -....-..123.3 Permeability .-......... 13 EVALUATION OF POTENTIAL FLOW PATHS AND TRAVEL TIMES FOR TTYPOTHETICAL SEEPAGE ORIGINATING FROM CELL #3...-..................... I54.I Estimated Travel Time from the Base of Cell #3 and Proposed Cell48 to the Perched Zone ......... ......... 154.2 Estimated Travel Times from Tailings Cell #3 and Proposed Cell48 to Ruin Spring....... .................... 164.3 Estimated Total Travel Time from the Base of Tailings Cell #3 and Proposed Cell 48 to Ruin Spring........ .....................17 RECOMMENDED ADDITIONAL PERCHED ZONE MONITORING WELLS DOWNGRADIENT OF PROPOSED CELL 48 ............. ..........21 REFERENCES............. .....23 LIMITATTONS STATEMENT.......... _._..____..____......2s TABLES Peel Hydraulic Test Results Results of July 2002 and June 2005 Hydraulic Tests J. 4. 5. 6. 7. TABLE OF CONTENTS (Continued) FIGURES I Site PIan and Perched Well Locations2 Kriged Brushy Basin Contact Elevations3 Perched Water Levels, August 19904 Perched Water Levels, August 19945 Perched Water Levels, September 20026 Ikiged 3'd Quarter, 2007 Water Levels7 Portion of USGS Black Mesa 7.5' Sheet Showing Approximate Location of Tailing Cells in Relation to Nearby Canyons and Ruin Spring8 Depth to Water, 3dQuarter 20079 Approximate Saturation Thickness, 3rd Quarter 200710 Site Plan showing Existing and Proposed Perched well Locations Sile Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8Oo0\cell4b\hydrcell4b.doc January 8,20O8 1. INTRODUCTION This report provides a brief description of the hydrogeology of the White Mesa Uranium Mill site (the 'Mill" or the "site"), located south of Blanding, Utah, and focuses on the occrurence and flow of groundwater within the relatively shallow perched groundwater zone at the site. Based on available existing hydrogeologic information from the site, estimates of hydraulic gradients and intergranular rates of groundwater movement (interstitial or pore velocities) are provided. These estimates are used to calculate average travel times for a hypothetical conservative solute (assuming no dispersion) from existing tailings cell #3 and proposed cell 48 at the site to a downgradient discharge point. Recommendations for additional perched zone monitoring wells downgradient of proposed cell48 are also provided. Figure I is a site plan showing the locations of perched monitoring wells and proposed cell48. Tailings cell #3 has been in service for many years and a large quantity of groundwater monitoring and hydraulic test data exists for perched monitoring wells completed around the perimeter of the cell. Data from the vicinity of the cell are used in conjunction with data downgradient of the cell to calculate perched zone hydraulic properties and groundwater gradients between cell #3 and the discharge point. Cell 48 is proposed to be installed at the downgradient edge of cell #3. The data from the immediate vicinity and downgradient of cell #3 used to compute rates of movernent and travel times for a hypothetical conservative solute will likewise be used to calculate travel times for the hypothetical solute from proposed cell 48 to the discharge point. Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4bthydrcell4b.doc January 8,2008 2. SITE ITYDROGEOLOGY Titan, 1994 provides a detailed description of site hydrogeology based on information available at that time. A brief summary of site hydrogeology that is based primarily on Titan, 1994, but includes the results of more recent site investigations, is provided below. 2.1 Geologic Setting The White Mesa Uranium Mill site is located within the Blanding Basin of the Colorado Plateau physiographic province. Typical of large portions of the Colorado Plateau province, the rocks underlying the site are relatively undefonned. The average elevation of the site is approximately 5,600 feet above mean sea level (amsl). The site is underlain by unconsolidated alluvium and indurated sedimentary rocks consisting primarily of sandstone and shale. The indurated rocks are relatively flat lying with dips generally less than 3". The alluvial materials consist mostly of aeolian silts and hne-grained aeolian sands with a thickness varying from a few feet to as much as 25 to 30 feet across the site. The alluvium is underlain by the Dakota Sandstone and Burro Canyon Formation, which are sandstones having a total thickness ranging from approximately 100 to 140 feet. Beneath the Burro Canyon Formation lies the Morrison Formation, consisting, in descending order, of the Brushy Basin Member, the Westwater Canyon Member, the Recapture Member, and the Salt Wash Member. The Brushy Basin and Recapture Members of the Morrison Formation, classified as shales, are very fine-grained and have a very low perrneability- The Brushy Basin Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hy&cell4b.doc January 8,2008 Member is primarily composed of bentonitic mudstones, siltstones, and claystones. The Westwater Canyon and Salt Wash Mernbers also have a low average vertical permeability due to the presence of interbedded shales. Beneath the Morrison Formation lie the Summerville Formation, an argillaceous sandstone with interbedded shales, and the Entrada Sandstone. Beneath the Entrada lies the Navajo Sandstone. The Navajo and Entrada Sandstones constitute the primary aquifer in the area of the site. The Entrada and Navajo Sandstones are separated from the Burro Canyon Formation by approximately 1,000 to 1,100 feet of materials having a low average vertical permeability. Groundwater within this system is under artesian pressure in the vicinity of the site, is of generally good quality, and is used as a secondary source of water at the site. 2.2 HydrogeologicSetting The site is located within a region that has a dry to arid continental climate, with average annual precipitation of less than ll.8 inches, and average annual evapotranspiration of approximately 61.5 inches. Recharge to aquifers occurs primarily along the mountain fronts (for example, the Henry, Abajo, and La Sal Mountains), and along the flanks of folds such as Comb Ridge Monocline. Although the water quality and productivity of the NavajolEnhada aquifer are generally good, the depth of the aquifer (approximately 1,200 feet below land surface [bls]) makes access difficult. The Navajo/Entrada aquifer is capable of yielding significant quantities of water to Site Hydrogeology CW Travel Times Proposed Wells Cell 48 H 17 I 8000\cell4b\hydrcell4b.doc January 8,2008 wells (hundreds of gallons per minute [gpm]). Water in wells completed across these units at the site rises approximately 800 feet above the base of the overlying Summerville Forrration. Perched groundwater in the Dakota Sandstone and Burro Canyon Formation is used on a limited basis to the north (upgradient) of the site because it is more easily accessible. Water quality of the Dakota Sandstone and Burro Canyon Formation is generally poor due to high total dissolved solids (TDS) and is used primarily for stock watering and irrigation. The saturated thickness of the perched water zone generally increases to the north of the site, increasing the yield of the perched zone to wells installed north of the site. 2.3 Perched Zone Ilydrogeology Perched groundwater beneath the site occurs primarily within the Burro Canyon Formation. Perched groundwater at the site has a generally low quality due to high total dissolved solids (TDS) in the range of approximately 1,200 to 5,000 milligrams per liter (mdL), and is used primarily for stock watering and irrigation in the areas upgradient (north) of the site. Perched water is supported within the Burro Canyon Formation by the underlying, fine-grained Brushy Basin Member. Figure 2 is a contour map showing the approximate elevation of the contact of the Burro Canyon Formation with the Brushy Basin Member, which essentially forms the base of the perched water zone at the site. Contact elevations are based on perched monitoring well drilling and geophysical logs and surveyed land surface elevations. As indicated, the contact generally dips to the south./southwest beneath the site. Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 Groundwater within the perched zone generally flows south to southwest beneath the site. Beneath the tailings cells, perched water flow is generally southwest to south-southwest. 2.3.1 Litholoeic and Hvdraulic Properties Although the Dakota Sandstone and Burro Canyon Formations are often described as a single unit due to their similarity, previous investigators at the site have distinguished between them. The Dakota Sandstone is a relatively-hard to hard, generally fine-to-medium grained sandstone cemented by kaolinite clays. The Dakota Sandstone locally contains discontinuous interbeds of siltstone, shale, and conglomeratic materials. Porosity is primarily intergranular. The underlying Burro Canyon Formation hosts most of the perched groundwater at the site. The Burro Canyon Formation is similar to the Dakota Sandstone but is generally more poorly sorted, contains more conglomeratic materials, and becomes argillaceous near its contact with the underlying Brushy Basin Member. The permeability of the Dakota Sandstone and Burro Canyon Formation at the site is generally low. No significant joints or fractures within the Dakota Sandstone or Burro Canyon Formation have been documented in any wells or borings installed across the site (Knight Pi6sold, 1998). Any fractures observed in cores collected from site borings are typically cemented, showing no open space. Site Hydrogeologr GW Travel Times Propord Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc Ianuary 8,2008 6 2.3.1.1 Dakota Based on samples collected during installation of wells MW-l6 (no longer in service) and MW-17, located immediately downgradient of the tailings cells at the site, porosities of the Dakota Sandstone range from 13.4 to 26percent, averaging 20 percent, and water saturations range from 3.7 to 27.2 percent, averaging 13.5 percent- The average volumetric water content is approximately 3 percent. The permeability of the Dakota Sandstone based on packer tests in borings installed at the site ranges from 2.71 x 10-6 centimeters per second (cm/s) to g.l2x lpa cm/s, with a geomekic average of 3.89 x l0-5 cm/s. 2.3.1.2 Burro Canyon The average porosity of the Burro Canyon Formation is similar to that of the Dakota Sandstone. Based on samples collected from the Burro Canyon Formation at MW-16, located immediately downgradient of the tailings cells at the site (and no longer in service), porosity ranges from 2 to 29.1 percent, averaging 18.3 percent, and water saturations of unsaturated materials range from 0.6 to 77.2 percent, averaging 23.4 percent. Titan, 1994, reported that the hydraulic conductivity of the Burro Canyon Formation ftrnges from 1.9 x 10-7 to 1.6 x l0 -3 crn/s, with a geometric mean of l.l x l0-5 cm/s, based on the results of l2pumping/recovery tests performed in monitoring wells and 30 packer tests performed in borings prior to that time. Hydraulic testing of wells Mw-01, MW-03, Mw-05, Mw-I7, Mw-lg, Mw-I9, Mw- 20, and MW-22 during the week of July 8, 2A02, and newly installed wells MW-23,1\/N,l-25, Mw-27, Mw-28, Mw-29, Mw-30, Mw-31, Mw-32, Tw4-20,Tw+zl, and TW4-22 during Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H17 I 8000\cell4b\hydrcell4b.doc January 8,2008 7 June, 2005, yielded average perched zone permeabilities ranging from approximately 2 x lO'7 cm/s to 5 x 104 crn/s, similar to the range reported by previous investigators at the site (Hydro Geo Chem, Inc [HGCf, 2002; HGC, 2005). Downgradient (south to southwest) of the tailings cells, average perched zone permeabilities based on tests at MW-3, Mw-5, Mw-17, Mw-20, MW'22, and MW-25 ranged from approximately 4 x l0-7 to I x lOa cm/s Permeability estimates from these tests were based on pumping/recovery and slug tests analyzed using several different methodologies. A number of temporary (TW4-series) perched zone monitoring wells have been installed at the site to investigate elevated concentrations of chloroform initially discovered at well MW-4 in 1999. Some of the conglomeratic zones encountered within the perched zone during installation of these wells are believed to be partly continuous or at least associated with a relatively continuous zone of higher permeability (International Uranium IUSA] Corporation UUSAJ and HGC, 2001). The higher permeability zone defined by these wells is generally located east to northeast of the tailings cells at the site, and is hydraulically cross-gradient to upgradient of the tailings cells with respect to perched groundwater flow. Relatively high permeabilities measured at MW-11, located on the southeastern margin of the downgradient edge of tailings cell #3, and at MW-14, located on the downgradient edge of tailings cell #4, of 1.4 x 10-3 cm/s and 7.5 x tA-a cm/s, respectively (UMETCO , lgg3), may indicate that this zone extends beneath the southeastem margin of the cells. This zone of higher pemreability within the perched water zone does not appear to exist downgradient (south-southwest) of the tailings cells, however. At depths beneath the perched water table, the zone is not evident in lithologic logs of the southemmost temporary wells TW4-4 and TW4-6 (located east [cross-gmdient] of cell #3), Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 nor is it evident in wells MW-3, MW-5, MW-12, MW-15, MW-16, MW-17, MW-20, MW-21, or MW-22, located south to southwest (downgradient) of the tailings cells, based on the lithologic logs or hydraulic testing of the wells- Because of the generally low permeability of the perched zone beneath the site, well yields are typically low (less than 0.5 gpm), although sustainable yields of as much as about 4 gpm may be possible in wells intercepting larger saturated thicknesses and higher permeability zones in the northeast portion of the site. Sufficient productivity can, in general, only be obtained in areas where the saturated thickness is greater, which is the primary reason that the perched zone has been used on a limited basis as a water supply to the north (upgradient) of the site. 2.3.2 Perched Groundwater Flow Perched groundwater flow at the site has historically been to the south/southwest. Figures 3 through 6 are perched groundwater elevation contour maps for the years 1990, 1994, 2002, and 200'1, respectively. The 1990, 1994, and 2002 maps were hand contoured because of sparse data. As groundwater elevations indicate, the perched groundwater gradient changes from generally southwesterly in the westem portion of the site, to generally southerly in the eastern portion of the site. The most significant changes between the 2002 ar,d 2007 water levels result from pumping of wells MW-4, TW4-19, TW4-20, and MW-26. These wells are pumped to reduce chloroform mass in the perched zone east and northeast of the tailings cells. Site Hydrogeolog5r GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\lrydrcell4b.doc January 8,2008 In general, perched groundwater elevations have not changed significantly at most of the site monitoring wells since installation, except in the vicinity of the wildlife ponds and the pumping wells. For example, relatively large increases in water levels occurred between 1994 and 2002 at MW-4 and MW-19, located in the east and northeast portions of the site, as shown by comparing Figures 4 and 5. These water level increases in the northeastern and eastern portions of the site are likely the result of seepage from wildlife ponds located near the piezometers shown in Figure 5, which were installed in 2001 for the purpose of investigating these changes. The increase in water levels in the northeastem portion of the site has resulted in a local steepening of groundwater gradients over portions of the site. Conversely, pumping of wells MW-4,TW4-l9,TW4-20, and lvIW-26 has depressed the perched water table locally and reduced average hydraulic gradients to the south and southwest of these wells. Perched water discharges in springs and seeps along Westwater Creek Canyon and Cottonwood Canyon to the west-southwest of the site, and along Corral Canyon to the east of the site, where the Burro Canyon Forrnation outcrops. The discharge point located most directly downgradient of the tailings cells is Ruin Spring. This feature is located approximately 10,000 feet south-southwest of tailings cell #3 and is depicted on the USGS 7.S-minute quad sheet for Black Mesa (Figure 7). Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 10 3. PERCHED ZONE IIYDROGEOLOGY BENEATH AND DOWNGRADIENT OF TIIE TAILINGS CELLS Perched water as of the 3rd Quarter, 2007 was encountered at depths of approximately 57 to I 15 feet bls in the vicinity of the tailings cells at the site (Figure 8). Beneath tailings cell #3, depths to water ranged from approximately 77 feet below top of casing (btoc) in the eastern portion of the cell (at MW-25), to approximately 114 feet btoc at the southwest margin of the cell (at MW-23). Assuming an average depth of the base of tailings cell #3 of 25 feet below grade, this corresponds to perched water depths of approximately 52 to 89 feet below the base of the cell, or an average depth of approximately 70 feet beneath the base of the cell. A similar assumption can be made for proposed cell 48. 3.I SaturatedThickness The saturated thickness of the perched zone as of the 3rd Quarter, 2007 ranges from approximately 93 feet in the northeast portion of the site to less than 5 feet in the southwest portion of the site (Figure 9). Beneath tailings cell #3, the saturated thickness varies from approximately 49 feet in the eastemmost corner of the cell to approximately 7 feet in the western portion of the cell. South-southwest of the tailings cells, the saturated thickness ranges from less than I foot at MW-21 to approximately 26 feet at MW-17. The average saturated thickness south-southwest of the tailings cells, based on measurements at MW-3, MW-5, MW-12, MW-14, MW-15, MW17, and MW-20, is approximately 14 feet. The average saturated thickness based on measurements at MW-5, MW-15, MW-3, and MW-20, which lay close to a line between the center of tailings cell #3 and Ruin Spring, is approximately 12 feet. By projecting conditions at Site Hy&ogeology GW Travel Times Proposed Wells Cell 48 H17 I 8000\cell4b\hydrcell4b.doc January 8,2008 I I these wells, the average saturated thickness is estimated to be approximately 10 to 15 feet between MW-20 and Ruin Spring. 3.2 Perched Water Flow Perched groundwater flow beneath the tailings cells has historically been southwest, with the gradient steepening in recent years (since about 1994) and becoming more westerly as perched water levels in the northeastern portion of the site have risen. Perched water flowing beneath the tailings cells eventually discharges in springs and seeps located in Westwater Canyon, to the south-southwest of the cells. The primary discharge point for perched water flowing beneath the tailings cells is believed to be Ruin Spring, located approximately 10,000 feet south-southwest of the cells. Perched zone hydraulic gradients currently range from a maximum of approximately 0.05 feet per foot (fl/ft) east of tailings cell #2 to approximately 0.01 fl/ft downgradient of cell #3, between cell #3 and MW-20. The average hydraulic gradient between the downgradient edge of tailings cell #3 and Ruin Spring can be approximated assuming the following: The elevation of Ruin Spring, based on the USGS topographic map for Black Mesa, is approximately 5,390 feet amsl. The distance between the downgradient edge of tailings cell #3 and Ruin Spring is approximately I 0,000 feet. The average groundwater elevation at the downgradient edge of tailings cell #3 is approximately 5,510 feet amsl. Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 12 l) 2) 3) Using these assumptions, the average perched zone hydraulic gradient between tailings cell #3 and Ruin Spring is approximately: 55 l0 - 5390 =O.Olzft I fi10,000 A hypothetical worst case average perched zone hydraulic gradient can also be estimated assuming the perched water elevation to be coincident with the base of tailings cell #3. The elevation of the base of tailings cell #3, which is also the approximate pre-existing land surface elevation near the center of the cell, is approximately 5,580 feet amsl. Under these conditions, for an unconfined perched zone, the maximum possible average perched zone hydraulic gradient between tailings cell #3 and Ruin Spring would be approximately: s580 - s390 =0.019ft I ft10,000 Although the downgradient edge of proposed cell 48 is closer to Ruin Spring (approximately 9,000 feet from Ruin Spring rather than about 10,000 feet), the above hydraulic gradient calculations can also be applied to cell48. 3.3 Permeability The average permeability of the perched zone downgradient of tailings cell #3 can be approximated based on the pumping/recovery test and slug test data obtained from perched zone wells located along the downgradient edge of and south of cell #3. Peel conducted hydraulic tests at perched zone wells MW-I1, MW-I2, MW-14, and MW-15 n 1992 (LIMETCO, 1993). Site Hy&ogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcel14b.doc January 8,2008 I 3 Results of these tests are provided in Table l. HGC conducted slug tests at perched zone wells MW-3, MW-5, MW-17, MW-20, and MW-22 in July 2002 (HGC,2002), and MW-25 in June, 2005 (HGC,200s). The HGC slug test results were analyzed using various solution methods including KGS (Hydea 1994), and Bouwer-Rice (Bouwer and Rice, 1976). Each method yielded slightly different results as shown in Table 2, which is based on Table 1 of HGC, 2002, and Table 1 of HGC, 2005. A range of average permeabilities for the portion of the site south of the tailings cells can be obtained by taking the geometric mean of the Peel test results and the results obtained by the various solution methods used to analyze the HGC data. Averaging the Peel test results for wells MW-ll, MW-12, MW-14, and MW-15 with the HGC KGS results for wells MW-3, MW-5, MW-17, MW-20, MW-22, and MW-25 yields a geometric average of 2.3 x l0-5 crn/s, and similarly averaging the Peel test results with the HGC Bouwer-Rice results yields a geomehic average of 4.3 x l0-s cm/s, as shown in Table 2. The "early timd'results at MW-5 using the Bouwer-Rice solution (from Table I of HGC, 2002) were used in the computations to yield a conservatively high estimate of permeability. Sile Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January8,2008 14 4. EVALUATION OF POTENTIAL FLOW PATHS AI{D TRAVEL TIMES FOR ITYPOTITETICAL SEEPAGE ORIGINATING FROM CELL #3 Although more than 25 years of groundwater monitoring at the site has shown no impact to perched water from the tailings cells, an evaluation of hypothetical transport of a conservative solute in seepage from existing cell #3 and proposed cell 48 is presented assuming a flow path from the base of the existing and proposed cells to the perched water, and thence to Ruin Spring. Average travel times for a conservative constituent moving from the base of tailings cell #3 and proposed cell 48 to the perched water, and then moving with the perched water to Ruin Spring, are computed assuming no dispersion. The porosities and water saturations used in the calculations were based on measurements reported in Titan, 1994,for samples collected from the Dakota Sandstone during drilling of MW- 16 and Mw-17, and from the Burro canyon Formation during drilling of MW-16. 4.1 Estimated Travel Time from the Base of Cell #3 and Proposed CeIl 48 to the perched Zone Knight-Pi6sold estimated a maximum volumetric seepage rate for tailings cell #3 based on cell construction and liner characteristics, of approximately 80 cubic feet per day (fVday) or 0.42 gpm over the entire cell (Knight-Pi6sold, 1998). Most of this seepage was estimated to be via diffusion through the liner. This rate was estimated to decrease over time as the cell desaturates once the final cover is emplaced. Assuming a cell fooprint of 3.38 x 106 ft2, this rate is equivalentto 2.37 x l0-5 fttday or 0.0086 feet per year (fVyr). Site Hy&ogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4bVrydrcell4b.doc January 8,2008 15 The average rate of downward movement of a conservative solute dissolved in the seepage, assuming l) no dispersion, 2) an average water saturation of 0.20, 3) an average porosity of 0.18, and assuming that this rate of seepage would not significantly raise the average saturation of the underlying materials, can be approximated as: o.oo86ft I yr = 0.24 ft / vr(.20x.18) The average time to travel 70 feet to the perched water zone would then be approximately 290 years. This is a conservative estimate because the average water saturations would be likely to increase, thereby reducing the downward rate of travel, and increasing the travel time. Assuming a similar travel time from the base of proposed cell 48 to the perched water would be even more conservative because the improved liner system to be used for that cell would result in less seepage than from cell #3. However, for purposes of calculation, potential seepage rates and downward rates of movement for a hypothetical conservative solute will be assumed to be the same for cell 48 as those calculated for cell #3. 4.2 Estimated Travel Times from Tailings Cell #3 and Proposed Cell48 to Ruin Spring Under current conditions, the average hydraulic gradient between the downgradient edge of tailings cell #3 to Ruin Spring is estimated to be 0.012, as discussed in Section 3.2. Assuming the following: Site Hydrogeology CW Travel Times Proposed Wells Cell 48 H :\7 I 8000\cell4bVrydrcell4b.doc January 8,2008 I 6 Average porosity Average hydraulic gradient Flow path length Average penneability ftmge :0.18 : A.Ol2 : 10,000 feet :2.3 x 1o-5 to 4.3 x 10-5 cm/s (0.064 ftlday to 0.120 fl/day) the average rate of intergranular movement of perched groundwater (interstitial or pore velocity) can be approximated to range from 0.0043 ftlday to 0.0080 ftJday (or 1.6 fl/yr to 2.9 ftlyr). The estimated average travel time for a conservative solute, assuming no dispersion, from tailings cell #3 to Ruin Spring would then be approximately 6,250 to 3,450 years over this range of perrreabilities. Under conditions of the maximum possible average perched groundwater gradient of 0.019 ftlft, as estimated in Section 3.2, and assuming the same permeabilities, porosity, and path length as above, the estimated average travel times would range from approximately 4,055 to 2,160 years. For proposed cell 48, which is about 9,000 feet from Ruin SprinB, the estimated travel times would be approximately 5,625 to 3,100 years using the gradient of 0.012, and approximately 3,650 to 1,950 years using the gradient of 0.019. 4.3 Estimated Total Travel Time from the Base of Tailings Cell #3 and Proposed CeIl4B to Ruin Spring The total average travel time for a conservative solute from the base of tailings cell #3 or proposed cell48 to Ruin Spring under current conditions would be the sum of l) the travel time from the base of either cell to the perched water table, and 2) the time to travel within the Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 17 perched zone to Ruin Spring. Based on the estimates provided in Sections 4-l and 4.2, the total average travel time of a conservative solute (assuming no dispersion) over the range of average permeability estimates would be between 6,540 and 3,740 years for cell #3, andbetween 5,915 and 3,390 years for proposed cell 48, assuming an average hydraulic gradient of 0.012 ft/ft. As discussed in Section 4. 1, because the rate of movement of a conservative solute from the base of cell 48 would likely be slower than for cell #3 because seepage rates would lower, the total travel time would likely be higher than estimated above. Conditions may hypothetically develop under which travel times may be reduced, such as an increase in average perched zone groundwater gradients between tailings cell #3 or cell 48 and Ruin Spring (as discussed in Section 3.2) or as a result of reduced vadose zone travel times due to development of a relatively large leak in either cell. Under hypothetical conditions in which a relatively large leak were to develop, potentially reducing vadose zone travel times to only a few years, the vadose zone travel time could be ignored, and the total average travel time (assuming no dispersion) would range from approximately 6,250 to 3,450 years for cell #3, and between 5,625 and 3,100 years for proposed cell 48, assuming an average hydraulic gradient of 0.012 fl/ft. Under hypothetical conditions in which the average perched zone hydraulic gradient between either cell and Ruin Spring reached 0.019 fl/ft, which also implies a negligible vadose zone travel time, the total average travel time (assuming no dispersion) over the estimated range in permeability would be between approximately 4,055 and2,160 years for cell#3, and between 3,650 and 1,950 years for cell 48. Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 18 Es ''na1ss based on hypothetical assumptions of a relatively large leak in tailings cell #3 or an average hydraulic gradient as high as 0.019 fl/ft betrveen either cell and Ruin Spring are considered very conservative because they assume conditions that are unlikely ever to develop. Furthermore the improved construction and leak detection system proposed for cell 48 would make this hypothetical scenario even less likely for cell4B than for cell #3. Site Hydrogeolory GW Travel Times Proposed Welts Cell 48 H:\7 I 8000\cell4b\lrydrcell4b.doc January 8,2008 19 Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 800O\cell4bVrydrcell4b.doc January &,2008 20 5. RECOMMENDED ADDITIONAL PERCIMD ZONE MONITORJNG WELLS DOWNGRADIENT OF PROPOSED CELL 48 The current perched grotrndwater monitoring well network for the tailings cells includes wells that are upgradient, crossgradient, and downgradient of the cells as shown in Figure 10. Most of the wells are located along the margins of the cells and many that are between the cells function as both upgradient wells for the cell located immediately downgradient of the wells and as downgradient wells for the cell located immediately upgradient of the wells. For example, well MW-30 functions as a downgradient well for cell #2 and as an upgradient well for cell #3. Wells MW-5, MW-12, and MW-23 that currently function as downgradient wells for cell #3 would also serve as upgradient wells for proposed cell 48. The current arrangement of tailings cell perched monitoring wells is conservative with respect to U.S. Environmental Protection Agency (US EPA) Draft Technical Guidance (US EPA, 1992) which generally recommends downgradient wells only along the downgradient margin of the facility which in this case would be the entire complex of tailings cells. Once proposed cell 48 is installed, an additional well or wells would be needed at the downgradient edge of the cell to be consistent with EPA Draft Guidance (US EPA, 1992). As shown in Figure 10, two additional wells are proposed, one at the southwest corner of proposed cell 48 and one between the southwest comer well and existing well MW-I5. These installations would conservatively maintain the approximate existing spacing as defined by the proximity of MW-14 to MW-15 along the downgradient edge of existing cell 4A. Existing wells MW-3, MW-20, and MW-21 would continue to firnction as distal downgradient wells for the entire cell Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000kell4b$ydrcell4b.doc January 8,2008 21 complex. Once installed, sampling frequencies for the new wells will be based on testing of the wells for perched zone hydraulic prcperties in the same fashion as for the existing wells. Site Hydrogeolory GW Travel Times Proposed Wells Cell 48 H:V I 8000\ccll,lb\lrydrcell4b.docJanuary8,2008 22 6. REFERENCES Bouwer, H. and R.C. Rice. 1976. Aslug test method for detennining hydraulic conductivity of unconfined aquifers with completely or partially penetrating wells. Water Resources Research, Vo. 12:3. Pp.423-428. Hyder, 2., l.J. Butler, C.D. McElwee, and W. Liu. 1994. Slug tests in partially penetrating wells. WaterResources Research. Vol. 30:11. Pp. 2945-2957. Hydro Geo Chem. 2001. Update to report "Investigation of Elevated Chloroform Concentrations in Perched Groundwater at the White Mesa Uranium Mill Near Blanding, Utah". Hydro Geo Chem. 2002. Hydraulic Testing at the White Mesa Uranium Mill Near Blanding, Utah During July, 2002- Submitted to Intemational Uranium (USA) Corporation, Denver, Colorado. Hydro Geo Chem. 2005. Perched Monitoring Well Installation and Testing at the White Mesa Uranium Mill, April Through June, 2005. Submitted to International Uranium (USA) Corporation, Denver, Colorado. KnighrPi6sold. 1998. Evaluation of Potential for Tailings Cell Discharge - White Mesa Mill. Attachment 5, Groundwater Information Report, White Mesa Uranium Mill, Blanding, Utah. Submitted to UDEQ. TITAN. 1994. Hydrogeological Evaluation of White Mesa Uranium Mill. Submitted to Energy Fuels Nuclear. UMETCO. 1993. Groundwater Study. White Mesa Facilities. Blanding, Utah. Prepared by UMETCO Minerals Corporation and Peel Environmental Services. US EPA. 1992. EPA RCRA Ground-Water Monitoring: Draft Technical Guidance, November 1992. Site Hydrogeology GW Travel Times hoposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcel14b.doc January 8,2008 23 Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000\cell4b\hydrcell4b.doc January 8,2008 24 The opinions and recommendations presented in this report are based upon the scope of services and information obtained through the perforrnance of the services, as agreed upon by HGC and ttre party for whom this report was originally prepared. Results of any investigations, tests, or findings presented in this report apply solely to conditions existing at the time HGC's investigative work was performed and are inherently based on and limited to the available data and the extent of the investigation activities. No representation, warranty, or guarantee, express or implied, is intended or given. HGC makes no representation as to the accuracy or completeness of any information provided by other parties not under contract to HGC to the extent that HGC relied upon that information. This report is expressly for the sole and exclusive use of the party for whom this report was originally prepared and for the particular purpose that it was intended. Reuse of this report, or any portion thereof, for other than its intended purpose, or if modified, or if used by third parties, shall be at the sole risk of the user. Site Hydrogeology CW Travel Times Proposed Wells Cell 48 H:\7 I 8O00\cell4b\ttydrcell4b.doc January 8,2008 25 Site Hydrogeology GW Travel Times Proposed Wells Cell 48 H:\7 I 8000kell4b\hydrcell4b.doc January 8,2008 26 TABLE 1 Pee! Hydraulic Test Resutts 1 Nofes.' ' From UMETCO,lgg3 Well llydreufic eondrrctMty (cm/s) vtw-11 1.4 x 10" \rw-l2 2.2 x 1O' vrw-14 7.5 x 10' vtw-15 1.9 x 10- H1718000\cell4b\Tables.xls: Table 1 11812008 TABLE 2 Results of July 2002 andJune 2005 Hydraulic Tests 2 Geometric Average of above tesf resulfs with Peet3 tesf results for MW-l1, MW-12, MW-14, and MW'15. 2.3x10s I +.3x10-s Nofes.'2 From HGC,2002; HGC,20053 From UMETCO,1993 Well Permeability in centimeteni per second KGS Bouwer-Rice vtw-3 4.0 x 10-7 1.5 x 10-5 \rw-5 3.5 x 10€2-4 x1O'5 MW.17 2.6 x 106 2.7 x 1O-5 vrw-20 9.3 x 10€ vw-22 1.0 x 10€7.9 x 106 MW-25 1.1 x 104 7.4 x 10-5 H:\718000\cel14b\Tables.xls: Table 2 FIGURES li \\ t/l\ //\\ //---:Z;' . ,ilr-r, ll $ t1 $ \\\. rw.rc N \tra ',t\ 'x\\\ l\o I-T T38S s------ - 0 3000 SCALE IN FEET EXEIAMlIIqtr tv.n ,)a//,//,//,//,//,//,//,////// tcmpreryFr.hGdmnnqingsl { *ilorrccono 422-ta FrcM F@mcrm!'!t eddmnitoTimftllt ina"tuoepnt,zo&16l\ tryr*yrdEdmnibriruY wcll iNt.lLd AEil,2(Ps 5t" nd t.mporry pcrdi.d mnitding €tt6 innsllcdM.y,2OOT(lodbB.pporimdc) , fl" lt l1 -till 1l 1l rl 1l 1l 1l rl lr ila23 OItY+a! ?tlz4 .p:: a-flEZ{ SITE PLAN AND PERCHED WELL LOCATIONS WHITE MESA SITE HYDRO GEO CHEM, INC. E(/JQ/-E( -9, \,F/(a\g)' t Mw.2o Frd.d @ibriq FI Btwim a g9 clrvffi 'n fd eYsl (!st lryrryFrch.dmnibdr€Ell- sw4detunHadPIEZ.I mddoimmrtrtuma 5552 d*tr;in f.d Id MW.3l pcrch.d mnibring sfl in$llcd ?se 3Mngd*ftnhLd{rd ..,. 1"3?1'lSXllfElT:91P,:l \\ il /t tr.o2G02 i,(06521 lf \l ll\\ // //// gA,.''n",, \#H,, //^ilI @ *oro G5r2 aJ )L --_-6W- 5€o- xw.olG.X +&ro rla MW-z, ti 1l \\ \\\ ,'# 5a{0 -.- N I + - 0 3000 SGALE IN FEET E[8I3UAI|O! //,// ,r'/// HYDRO G80 CHEM, INC. KRIGED BRUSHY BASIN CONTACT ELEVATIONS WHITE MESA SITE ! ):')uty( ,l\. .\r '5,t , i: I ) T38S A .ri"-=ttt"-J' FXP1 AN ION a II-J PERCIIEO I(,{lTORtr'lC I€LL5,71 !*IO;IiG XAIEi T"EI'EL IiI FEET ATSL u notlfE PoD sso_ ___ t rER LE\rEL CqrrcuR uNE. DASI{EO n{€RE UXCERTA'I N t SCALE N lEtt $trxtI \ olFi-,sro--- tr 28 ^.I o r-F@g/ i \. 5i.'( ))(r\ PROPERIY Bq,ltDARY I\\ i "-zt' ) i=ir55705r0 iii q 1j$5---- srao \--------____5a7o It\\\\t\ aDt5 ai 1- .or3=rrr===J=========.===--------/rr-./- S.jO F *aalaa FXPI ANATION . TU-J 31?1 U PERCHED IoiIITORING UELL S}IOING WAIER LE\tr1 IN FEEI AUSL nLt}-tFE Poiro s5@ --- WAIER LEVEL CONTOUR LtitE. DAS}IED *IERE UNCERTAIN N t SCALI n fEEl 7aEJL !.I' PERCHED WATER LEIELS AUGUST 1994 i^''. 'i<Fany/ .i\. Pf,CEFIY a)l,r{oARY Art=-trr==-J - 3.150FAa9' FXPI ANATION a ru-ll 551 { o 552't a r;r, 55so- --- PERCHED TO{IIORINC TELL S}IOUNG 'AIER T.EIEL IN FEEI AUSL IEilPORARY PERCHEO T'O{ITORI'{G TELL STIOUING UAIER LfvEL IN FEEI ATSI. PIEZOT'EIER SHONNG UAIER LE!,[L IN FEEI AT.SL UAIER LET'EL COIITOI.IR UNE, DAS8EO THERE UNCERTAII{ N IU UI'J)UFE PilD NOIE: w IER LEVELS FOR PIEZOUEIE8S ARE FRO' ruG|JST, 2OO2 sc[E n FEtt n k- ,i'uo.i- 4'..\o$.! \\----_-ss!o alra5rl alcrl\ 28 .-';:ffi\- /' ,t tE!',, i//'fft, -sltQ =5,160=5540 I I re).lt"6 l,r'l IAa ltkEL,',' PERCHED WATER LEIELS SEPTEMBER 2OO2 HEZ.3a50t \\ \\ ilil m.02G5o3 II Ii l1\\ )(//ltt 1//)/, ). j ,fi Itil ll ^ji rl 1l 32 f,s,03G171 'u,['' tl tl $ \\\ N tto A I + trw.20G4ar \ 1\ 1\\\-=*: {\=_-.r, - 0 3000 SCALE IN FEET N-22 -/.'fu//////,//////,//,//SXEIAIAIIOT .a F dEd mnito.irE Eil Bhoringg6t ald&ninked //// I{OTES: Location. and olevation3 ior TW4-23, fW+24. and TWI-25 a]o^ tdporry pcdd mnturiE m[lr 55$ sl@i4 cLvdion m fd emllPig-l fchcd dcemtcr showirua 5591 Glrydton in fd 6lMw-31 porchcd mnilo.ing rcll indefl.d April. + 5$7 slEwing dddbn in k ffil Location. and olevation3 ior TW4-Z3,TW+24, atl{Jlw+z5 aro approrlmale; Water lsvsl tor tW-26 ffW&15) i3 from ths lecord ouartet, AXrT . t€@rry pr<trcd mnilonre Ell indelldI s71 Asil, 2G tum.bvdbn in i.d dEl e - - t€mrryrelEdmnitoriremllide{da. ${ Mry, 2mz stp*m ilrcrido obvdbn HYDRO GEO CHEM, INC. KRIGEO 3rd QUARTER, 2007 WATER LEVELS W}IITE IIIESA SITE Cffi*: f,w.02aii0 ll ll ll\\ tt////- 32 rl lr tl tl-f-. ,$ro, ll \1 tl $ $\ N t\.t ,|1\ I+ xw.03l1 T38S 'b'3 1\ 1\\--\=:=:-:__ - 0 3000 SCALE IN FEET //m-22 ,;-a ////./ EXEIAIAIIOX //.//,// NOTES: Locationc olTW+23,TW$24 and TW+25 ar. approrimde; ,w.I parchcd milodng sllahoring Otc d.Plhinf6d - lryrary pcrd.d runibrlng ellI t1 3honhe dopth in f..l Hea3urem.nt tor llw-26 13 f?om lhe 3econd quanet, 2007PlEzn Fr.*lcd pi@mtor shorirea 65 dcpth in fd Mw-31 Frchcd mnitonrE mll l6Ellcd AEil, { rc lhowingd€plh in hll r ta@rryF.ch.dffidmsllinddld {> 57 Apit. 2006 shodlg d6pth ln id !t ." l.nporey Fdd mtudng EI inst6k6 -- Mry, 2m7 rhowiE dcpth h fd DEPTHS TO WATER 3rd QUARTER,2007 WHITE i'ESA SITE ,Sb,I TXR*OryF dilinn. rnc.EE E(/J()) /?{("-E '-- )Fr;q,\u, )-.r/ Ii/ -1 -JL(t 1t I//lill I1 11 11 -ltll 1l 1l 1l 1l 1i ll sz 1l xw{2a[i4-- \(UACll \ li ll\\ // lt/t /-' tw-03G . ,1r.,, lr tl tl $ $ T38S 1\ N \rt + + l{w.20O2 1\\rrl.//r\'\------ :t- ---- - 0 3000 SCALE IN FEET //t*.77 -:3//.//,// ////////EXEIAIAIIO! pcrch.d rcnnofig h[ slwitrg _//// NOTES: LocatloB and value3 ,or TW&23,fw+24, arn,,fw+25 are approximate;a 79 3tud.d thid(rus (bot)l.ltmrffi Grchcd mntudm mllO rr "mrc iiua"orhid(@('td)Value ror MW-26 Ir ba3ed on lhe 3ocond quarlot,2007 water lsvelPtEz-l pcr.hcd pkemder sMnga 05 dud.d thk*ms(t6t)Mw-31 p.rdlcd mnloring Ell idalhd Apdl, 2005 + 79 3fwirB s.td.d tticftrs (hGl) ^ tryrery gdEd mnhoiiE Ell idellcd I5' Apr0, 2ooo .hoxirB dudd thiclr^B (h. * -- tclmmN mrdr.d lrMilodm mI iBLlbd8 oe uai. zm'z aho.ins w*cithidn@ (fd APPROXIMATE SATURATED THICKNESS 3rd QUARTER,2007 WHITE iIESA SITE HYDROcEo CHEM, INC. ll \i 11\\ // tt////- T38S \I 11 $ \\ - 0 3000 SCALE IN FEET ETETE,IAIIOtr //N-D -:a//,//.//,//,//.////,//,//,//a pGrch.d lMnonng Ell t+llo r.trtporry p€.rficd mhibkrg sr f wirorlfe oono pcrchcd pigamclor * n* lanrpor*y pordcd mnilodng Ell)r('n{dkdMey,2007(lodoB.pgorims) O rcpscd lmFry pdcfiGd mnito.ing rcll ii te*rlsir?i r (PROPOSED) r[i-s lnneos5gl11\ wr ! {'bndoned)lr rrrlenoectolDts- - m HYDRO GEO CHEM, INC. SITE PLAN SHOWNG EXISTING AND PROPOSED PERCHED WELL LOCATIONS W}IITE MESA SITE DOSE ASSESSMENT IN SUPPORT OF THE LICENSE RENEWAL APPLICATION & ENVIRONMENTAL REPORT FOR THE WHITE MESA URANIUM MILL Prepared for: Denison Mines (USA) Corp. (DUSA) Prepared by: SENES Consultants Limited 121 Granton Drive, Unit12 Richmond Hill, Ontario L4B 3N4 February 2007 Printed on Recycled Paper Containing Post-Consumer Fibre Q Dose Assessment in Support of the License Renewal Application and Environmental Report for the Wite Mesa Uranium Mill EXECUTIVE SUMMARY 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 (9.5 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 (2,191ha). The mill is licensed by the State of Utah Division of Radiation Control (DRC) to process uranium ore and selected alternate feed materials. 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 Aizona Strip and processing of ores from those properties can be anticipated in the future. Milling of conventional ore is scheduled for early 2008 when the milling of currently available alternate feed material is completed (DUSA 2007). This dose assessment was prepared in support of the license renewal application for the mill. An element of the license renewal application is to complete a dose estimate to members of the public based on the operations at the mill. During the recovery of uranium from conventionally mined ore at the mill, small amounts of uranium and other radioactive contaminants can be released to the atmosphere from various processes and activities. The radioactivity can be dispersed by wind into the surrounding environment and subsequently, via deposition to soil, plants and animals. In this assessment, 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 ore or Arizona Strip ore. The expected ore grade from the Colorado Plateau ore is an average of 0.25% U3Os and l.5Yo YzOs NRC 1980) while the Arizona Strip ore is assumed to contain 0.637% U:Os (DUSA (2007a)). The proposed ore process rate for the Colorado Plateau ore and Arizona Strip ore is approximately 730,000 tons per year (tpy) (an average of 2000 tons per day). Assuming that the average uranium recovery is at the historical recovery yield of 94Yo,approximately 1,715 tons (3,431,000 lbs) of U3Os per year would be recovered from Colorado Plateau ore at the proposed ore process rate. Similarly, approximately 4,371 tons (8,742,188 lbs) of U3Os per year would be recovered from Arizona Strip ore at the proposed ore process rate. The proposed operating schedule at the mill is assumed tobe Z4hr/day for 365 days per year. The MILDOS-AREA calculated total annual effective dose commitments (including radon) were compared to the Utah Administrative Code R3l3-15-301(l)(a) requirements that the dose to individual members of the public shall not exceed 100 mrem/yr (radon included). Overall, the 34489 - February 2007 ES-I SENES Consultants Limited Dose Assessment in Support of the License Renewal Application and Environmental Report for the White Mesa Uranium Mill total annual effective dose commitments are at most 1.20 mrem/yr (effective dose for infant at BHV-I) of the R3l3-15-301(1)(a) limit of 100 mrem/yr (radon included) to an individual member of the public for the processing of Colorado Plateau ore. The total annual effective dose commitments are at most 2.94 mremlyr (effective dose for infant at BHV-I) of the R3l3-15- 301(1)(a) limit of 100 mrem/yr (radon included) to an individual member of the public for the processing of Arizona Strip ore. Therefore, the predicted annual effective dose commitments for anticipated ore processing operations comply with R313-15. In addition, the MILDOS-AREA-calculated 40 CFR190 annual dose commitment (excluding radon) was compared to the 40 CFR190 Criterion of 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 40CFR 190 doses were also used to demonstrate compliance with R313-15-101(4) (i.e., the licensee must 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 (absent of the radon dose)). Overall, from Table 6.3, the 40 CFRI90 annual dose commitments are at most 4.62 mrem/yr (dose to the bone for the teen at BHV-I) of the 40 CFRI9O dose criterion of 25 mrem/yr for Colorado Plateau ore. In addition, the 40 CFR190 annual effective dose commitments demonstrate compliance with the R3l3-15-l0l(4) limit of 10 mrem/yr to the individual member of the public likely to receive the highest total effective dose equivalent. From Table 6.8, the 40 CFR190 annual dose commitments are at most 11.7 mrem/yr (dose to the bone for the teen at BHV-I) of the 40 CFRI9O dose criterion of 25 mremlyr for Arizona strip ore. In addition, the 40 CFRI9O annual effective dose commitments demonstrate compliance with the R313-15-101(4) limit of 10 mrem/yr to the individual member of the public likely to receive the highest total effective dose equivalent. For Colorado Plateau ores, the maximum effective dose is 0.535 mrem/yr and for Arizona Strip Ore it is 1.37 mrem/yr, in both cases for an infant at BHV-I. Therefore, the predicted 40 CFR annual effective dose commitments for anticipated ore processing operations comply with R313-15-101(4). 34489 - February 2007 ES-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill 34489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill LIST OF TABLES PagS: No. 4.1 Characteristics of Tailings at White Mesa......... ........4-7 4.2 Radioactive Particulate and Radon Emission Rates (Colorado Plateau Ore).......... ........4-9 4.3 Radioactive Particulate and Radon Emission Rates (Arizona Strip Ore)........................4-9 6.1 Comparison of Annual Dose Commitments with Applicable Radiation Protection Standards (Colorado Plateau Ore).......... ........-...........6-2 6.2 Total Annual Dose Commitments (mrem) for Meat lngestion Pathway (Colorado Plateau Ore).......... ..................6-5 6.3 Comparison of 40 CFR190 Annual Dose Commitments with Applicable Radiation Protection Standards (Colorado Plateau Ore) .......... ...6-6 6.4 40 CFR190 Annual Dose Commitments (mrem) for Meat Ingestion Pathway (Colorado Plateau Ore).......... ..................6-9 6.5 Annual Population Dose Commitments within 50 miles (80 km) of the Mill for Colorado Plateau Ore........... ..............6-9 6.6 Comparison of Annual Dose Commitments with Applicable Radiation Protection Standards (Arizona Strip Ore) ................6-10 6.7 Total Annual Dose Commitments (mrem) for Meat lngestion Pathway (Arizona Strip Ore) ..............6-13 6.8 Comparison of 40 CFR190 Annual Dose Commitments with Applicable Radiation Protection Standards (Arizona Strip Ore) .................6-14 6.9 40 CFR190 Annual Dose Commitments (mrem) for Meat Ingestion Pathway (Arizona Strip Ore) ..............6-17 6.10 Annual Population Dose Commitments within 50 miles (80 km) of the Mill for Arizona Strip Ore ...........6-17 LIST OF F'IGURES Paee No. 4.1 Source Locations.. ..................4-2 5.1 Receptor Locations with Respect to the Vanadium Stack......... ....................5-2 34489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill ACRONYMS & ABBREVIATIONS ALC Allowable Concentration ANL Argonne National Laboratory ALARA As Low As Reasonably Achievable Avg. Average ASCII American Standard Code for Information lnterchange Bi-210 Bismuth 210 Bi-214 Bismuth 214 CCD Counter Current Decantation CFR Code of Federal Regulations Ci Curie DCF Dose Conversion Factor DRC State of Utah Division of Radiation Control DUSA Denison Mines (USA) Corp. EPA Environmental Protection Agency Ew Process Emission Factor F Radon Release FES Final Environmental Statement Fs Annual frequency of occurrence of wind group S ft Feet ft3 Cubic feet grams g ore Grams of ore GPS Global Positioning System GUI Graphical User Interface ha hectares hr hours ICRP International Commission on Radiological Protection ID Induced Draft lbs Pounds km Kilometres kts Knots NESHAPS National Emission Standards for Hazardous Air Pollutants NRC Nuclear Regulatory Commission NUREG Regulatory Guide m Meters m' Square metres rffem Millirem 34489 - February 2007 AC-1 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill MPC Pb-210 Pb-zt4 pci Po-210 Po-218 Pla-226 Rn-222 Rs s S SENES TGLM Th-230 tpy U:Os Unat u-234 u-235 u-238 VzOs yd3 yr Maximum Permissible Concentration Lead2l0 Lead2I4 picoCurie Polonium 210 Polonium 218 Radium 226 Radon222 Resuspension rate for wind group S Seconds Emission Rate Specialists in Energy, Nuclear and Environmental Science Task group on Lung Dynamics Lung Model Thorium 230 tons per year Triuranium octaoxide ("Yellowcake") Natural Uranium Uranium 234 Uranium 235 Uranium 238 Vanadium Oxide Cubic yards Years 34489 - February 2007 AC.2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill 1.0 l.t INTRODUCTION BlcrcRouNo 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 (9.5 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 (2,19I ha). The mill was built in 1979 and licensed by the U.S. Nuclear Regulatory Commission (NRC) to process uranium ore and selected altemate 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 authority over the mill was assumed by the State of Utah 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 further processed for recovery of vanadium before recycling (NUREG 1979). 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 altemate feeds for the recovery of uranium. The residual tailings from these processes are stored in the tailings ponds 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 processing of those ores can be anticipated in the future. Milling of conventional ore is scheduled for early 2008, when the milling of currently available alternate feed material is completed (DUSA 2007). This dose assessment was prepared in support of the license renewal application for the mill. An element of the license renewal application is to complete a dose estimate to members of the public based on the operations at the mill. The goal is to determine potential doses to both nearby individuals and to populations in the vicinity of the mill from ore processing operations at the mill. 34489 - February 2007 l-1 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Mesa Uranium Mill 1.2 Os"rrcrrvB The objectives of this assessment are to estimate the potential annual doses to the people living close to the mill and to the population living within 50 miles (80 km), from any releases to the atmosphere of natural uranium (i.e., uranium-238 decay chain and associated radioactive constituents) during the routine ore processing operations. The mill is licensed for the annual recovery of 4,380 tons of uranium (as UlOs) The amount of ore needed to provide that quantity of uranium depends on the grade(s) of the ores processed, with larger quantities of low grade ores and smaller quantities of higher grade ores required to achieve the same production. The mill uses an acid leach-solvent extraction process for uranium recovery with a nominal recovery of approximately 94Yo, with remainder of the uranium being discharged to tailings. The ore supply expected for the mill is typically from mining activities on the Colorado Plateau and Arizona Strip districts. The expected ore grade from the Colorado Plateau district is an average of 0.25o/o U:Os and l.5YoYzOs NRC 1980) while the Arizona Strip ore is assumedto contain 0.637% U:Os and no vanadium (DUSA (2007a)). In this assessment, the doses to individual members of the public are estimated separately for the processing of Colorado Plateau and Arizona Strip ores. The proposed ore process rate for the Colorado Plateau ore and Arizona Strip ore is approximately 730,000 tons per year (tpy) (an average of 2000 tons per day). Assuming that the average uranium recovery is at the historical recovery yield of 94Yo, approximately 1,715 tons (3,431,000 lbs) of U3Os per year would be recovered from Colorado Plateau ore at the proposed ore process rate. Similarly, approximately 4,371 tons (8,742,188lbs) of U3O3 per year would be recovered from Arizona Strip ore at the proposed ore process rate. The activity concentration of the U-238 in the ore is calculated as follows: ActivityConcentration=(OreGrade (gUrOr/gore))(%U-238lgUrO*)(SpecificActivityof U-238) (1) where, Ore Grade (g U3Os/ g ore) : 0.0025 for Colorado Plateau Ore and 0.00637 for Arizona Strip Ore %U-238lgof U:Os:0.848 Specific Activity of U-238:3.30 x 105 pCi/gtJ-2381gorc a a t-234489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill Using equation 1, the activity concentration of U-238 for Colorado Plateau ore is 700 pCi tJ-2381g ore. Similarly, the activity concentration of U-238 for Arizona Strip ore is 1783 pCi U-Z3&lgore. In all cases, the ores are assumed to be in secular equilibrium. It should be noted that the current licensed production capacity is 4,380 tons of UrOs (8,760,000 lbs of UsOr) per year. Therefore, the processing of Colorado Plateau ore is approximately at 40Yo of the current licensed U3Os production capacity while the processing of Arizona Strip ore is just below the current licensed yellowcake production capacity. The proposed operating schedule at the mill is assumed to be 24 hr/day for 365 days per year. 1.3 AppRoacH The MILDOS computer code calculates the dose commitments received by individuals and the general population within a 50 mile (80 km) radius of an operating uranium recovery facility. The MILDOS code is an NRC-approved code designed as a tool to provide input on regulatory and compliance evaluations for various uranium recovery operations. As part of this assessment, the EnecoTech analysis (EnecoTech 1991a and l99lb) was reviewed to examine the input parameters and emissions calculations used to perform the previous MILDOS modeling for the mill in 1991. The intent of the review was to ensure that issues addressed in 1991 were addressed in the current assessment where relevant. It should be noted that the MILDOS code developed in 1981 has gone through a number of changes over the years and served as the basis for the development of the MILDOS-AREA code. The approach used for this assessment is to evaluate the exposure pathways considered in the EnecoTech analysis with the updated MILDOS-AREA code. All sources considered in the EnecoTech analysis (EnecoTech 1991a) are considered in this assessment and updated as appropriate to current conditions. As discussed later, emissions from the vanadium stacks are also considered in this analysis. A description of the sources used in this assessment is provided in Section 4.0. The source emissions calculations for airborne radioactive releases at the mill include those related to dust generation during ore handling, area source dusting from ore pad stockpiles and the tailings ponds. The source emissions calculations generally follow the guidance of NRC's Regulatory Guide 3.59 (NRC 1987) and NUREG-0706 (NRC 1980). Details of emissions estimates are provided in Appendix A. 34489 - February 2007 l-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill Many of the receptors used in the EnecoTech analysis were also used in this assessment. A description of the receptors used in this assessment is provided in Section 5.0. Locations for the sources and receptors used in this assessment were updated with Global Positioning System (GPS) coordinates provided by DUSA (DUSA 2007b). The physical parameters pertaining to particle size (and distribution) are consistent with the EnecoTech analysis. These parameters are the default values within the MILDOS-AREA code (ANL 1998) as well as in NUREG-0556 (NRC 1979). The dose to receptors near the mill was estimated using MILDOS-AREA for the processing of Colorado Plateau ore and, separately, for the processing of Arizona Strip ore. The proposed ore process rate for the Colorado Plateau ore is approximately 730,000 tpy which would recover approximately 2,573 tons (3,431,000 lbs) of U3Os per year (assuming that the average uranium recovery is 94%). The proposed ore process rate for Arizona Strip ore is approximately 730,000 tpy, which would recover approximately 4,371tons (8,742,188 lbs) of U3O3 per year (assuming that the average uranium recovery is 94%). In addition to doses to individual receptors, the dose received by the general population within an 50 mile (80 km) radius of the mill is predicted. CoNrnNrs On THrs Rsponr The remainder of this report is arranged into seven sections. Section 2.0, Regulatory Compliance, provides a description of the regulatory framework pertaining 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 of the public and how MILDOS-AREA was used. Section 3.0 also describes how the MILDOS-AREA software has evolved, highlighting some of the key differences between the updated version, MILDOS AREA (NRC 1998), and the original version of MILDOS. Section 4.0, Source Terms, describes the source terms 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 ore and Arizona Strip ore based on the ore grade, ore process rate and uranium recovery yield. 1.4 34489 -February 2007 t-4 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill Section 5.0, Receptors, describes the receptors used in the MILDOS-AREA runs. 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 summa.ry of the dose estimates from the MILDOS-AREA runs. Section 8.0, References, provides a list of reference material used to prepare this report. Appendix A: Emissions Calculations describe the basis of the emission estimates for each source. 34489 - February 2007 l-5 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill 2.0 REGULATORY COMPLIANCE The 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 of the public that are as low as reasonably achievable (ALARA). 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 in a year, exclusive of the dose contribution from natural background (including radon) and medical sources. Under 10 CFR20.1301 (NRC l99l), the NRC has adopted the provisions of the U.S. Environmental Protection Agency (EPA) environmental radiation standards in 40 CFRI9O (EPA 2002). This subpart requires that the licensee provide reasonable assurance that the radiation attributed the mill operations does not exceed the annual dose of 25 millirem (mrem) to the whole body, 75 millirem to the thyroid and25 millirem to any other organ of any member of the public (radon and it daughters excepted). In addition, 10 CFR20.1301 (d) (R313-15-l0l(4)) sets a constraint limit 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 - February 2007 2-l SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill 3.0 3.1 RADIATION DOSE ASSESSMENT ENrcorrcH ASSESSMENT As mentioned in Section 1.3, all of the sources considered by EnecoTech are addressed in this analysis. In addition, the vanadium stack which is an additional point source, is considered in this assessment. The emission calculations from the mill point sources (grinder, loading ore to the gizzly, yellowcake stack and vanadium stack) and area sources such as the ore pads and the tailings ponds were revised based on the new operating parameters and meteorological data provided by DUSA. Some of the receptors used in the EnecoTech analysis are used in this assessment. In addition, there are new receptor locations added to this assessment. Locations for the sources and receptors used in this assessment were updated using the GPS coordinates provided by DUSA (DUSA 2007b). A description of the sources and receptors used in this assessment is provided in Sections 4.0 and 5.0, respectively. It should be noted that the MILDOS code used in the EnecoTech analysis is outdated. The MILDOS code has been updated to MILDOS-AREA; the most up-to-date MILDOS-AREA code version 2.20P is used in this assessment. A discussion on the development of the MILDOS code is provided in Section 3.2. GnNnnal lxponnnarroN ABour Mrr-nos-Anra The MILDOS computer code was developed from the version IV for Argonne National Laboratory's (ANL's) Uranium Dispersion and Dosimetry (UDAD) computer program 1981. The MILDOS program was based on the models and assumptions from the U.S. NRC's 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 MILDOS-AREA code by modifying the MILDOS code developed in 1981. The MILDOS-AREA code was designed or used 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 10 in MILDOS-AREA due to the fact that a large area can be considered as a single source rather than two or more point sources. 3.2 34489 - February 2007 3-1 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill The internal 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 CFR190 and 10 CFR Part 20 (R313-15). The calculations of ingestion DCFs were based on ICRP Publication 2 and 10A's ingestion models (ICRP 1966). The inhalation DCFs are calculated by the ANL computer program UDAD (Momeni 1979) in accordance with Task group on Lung Dynamics lung model (TGLM) of the lnternational 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 particle 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 1991); 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 part of the input options. The annual average air concentrations were computed to the maximum permissible concentrations (MPCs) in 10 CFR Part 20. The MPCs in l0 CFR20 (incorporated by reference in R3l3-15) were revised in 1994 to incorporate the updated dosimetry to the ICRP 1978 recommendations. ln 1997, the MILDOS-AREA code was updated to meet the requirements of the revised l0 CFR Part 20. The dose limit to the general public also changed; which led to a revised calculation 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 (ASCID 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 (GUD which provides an interface for the user to input each parameter needed for the calculations in the Windows operating system. The GUI 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 is 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, external exposure from ground concentrations, external exposure from cloud immersion, ingestion of vegetables, ingestion of meat and ingestion of milk. 34489 - February 2007 3-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill 3.3 TUB Usn Or Mrloos-AREA Ix Turs AssnssurN:r The 1991 EnecoTech analysis conducted by EnecoTech Environmental Consultants (under contract from Umetco Minerals) evaluated the potential radiological doses arising from the production of 8,760,000 lbs of U3Os per year at the mill from processing conventionally mined ores. As mentioned, the original MILDOS code is no longer applicable. In this assessment, the most up-to-date MILDOS-AREA code version 2.20P (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, in separate cases, at the proposed ore process rates for each ore. As mentioned, the proposed ore process rate for the Colorado Plateau ore is approximately 730,000 tpy would recover approximately 1,715 tons (3,431,000 lbs) of U3Os per year (assuming that the average uranium recovery is 94%). The proposed ore process rate for Arizona Strip ore is approximately 730,000 tpy would recover approximately 4,371 tons (8,7 42,188 lbs) of yellowcake per year (assuming that the average uranium recovery is 94%). MILDOS-AREA was used to design a conceptual model of the mill. MILDOS-AREA requires the location of sources and receptors to be defined by the user; the locations are calculated relative to the reference point at the mill on a Cartesian grid system. The reference point used for the MILDOS-AREA code used in this assessment was the vanadium stack. The GPS coordinates were ploffed using Google Earth Pro (Google 2005). The easting, northing and elevation of each source and receptor relative to the vanadium stack were measured in Google Earth Pro. The measured coordinates are entered directly for point sources. For area (quadrilateral) sources (i.e., ore pads and tailings ponds), the user must enter the boundaries and elevation of the area source which are calculated based on the easting and northing of the source. The sources are defined to represent each significant radionuclide release point at the mill; radionuclide releases for particulates and radon are defined by the user for point sources. MILDOS-AREA calculates the release rates from area sources based on the radionuclide concentrations, source area and meteorological data. MILDOS-AREA only considers airborne releases of radioactive materials; releases to surface water and groundwater are not addressed. The U-238 decay chain is assumed to be the only significant source of radiation from uranium milling operations (the contribution from the U-235 chain is less than 5o/o of that from the U-238 chain). The particulate 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. TheseRn-222 daughters include Po-218, Pb-214, Bi-214, Pb-210 and Po-210. The model accounts for the releases and in-growth of other radionuclides using the assumption of secular equilibrium within the U-238 decay chain. 34489 - February 2007 3-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Mesa Uranium Mill The transport of model 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 particulates, 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 of meat and vegetables. 3-434489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Mesa Uranium Mill 4.0 SOURCE TERMS The radionuclides of concern for license renewal modeling consideration include; U-238 and its daughters Th-230, Ra-226, Pb-210 andRn-222 which are 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 gizzly), point sources (grinder, yellowcake stacks and vanadium stack) and area source dusting from ore pad stockpiles and the tailings ponds. The large area sources such as the tailings area are divided into smaller sources (four tailings ponds) to allow for the size and irregular shape ofthese areas. As mentioned in Section 3.3, the source locations used in the EnecoTech analysis were revised using the GPS coordinates provided by DUSA (DUSA 2007b). The coordinates for all the sources except for the grinder were calculated first by plotting the GPS coordinates provided by DUSA (DUSA 2007b) in Google Earth Pro and then using the measuring tool in Google Earth Pro to measure the easting, northing and elevation of each source relative to a reference point at the mill (i.e., the vanadium stack). The source locations (plotted in Google Earth) are shown in Figure 4.1. 4-l34489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill FIGURE 4.1 SOURCE LOCATIONS Source Legend: 11 Vanadium Stack12 Ore Pad13 Grizzly 14 Tailings Pond'l 15 Tailings Pond 216 Tailings Pond 3 17 Tailings Pond 418 North Yellowcake Stack 19 South Yellowcake Stack20 Grinder 34489 - February 2007 4-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill The dose to members of the public is estimated for the processing of Colorado Plateau ore or Arizona Strip ore in separate cases. 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. It should be noted that 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 l.5o/o VzOs). A description of the approach used to calculate the emissions from the point and area sources are described in Section 4.1 and 4.2,respectively. Detailed source emissions calculations are provided in Appendix A. 4.1 PorNr SouncBs Mill point sources used in the EnecoTech analysis were also used in this assessment. These sources include the grinder, loading ore to the gizzly and yellowcake 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 onsite crushing of the ore, only a wet grinding operation. The ore dust emissions are controlled because the material is wet during the grinding operations. The particulate emission control from the grinding operation is assumed to be 99.9%o. U-238 and its decay daughters are all emitted at a rate of 9.27E-05 Cilyr (assuming secular equilibrium) for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCilg. Similarly, U-238 and its decay daughters are all emitted at a rate of 2.368-04 Cilyr (assuming secular equilibrium) for Arizona Strip ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 1783 pCilg. The emission rates for Rn-222 released during wet grinding is calculated assuming that only 20% of the radon is available for release or emanation from the mineral grains in which it is produced (NUREG 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 Cilyr and 236 Cilyr for Colorado Plateau ore and Arizona Strip ore, respectively. 4.1.2 Grizzly The emissions from trucks dumping ore onto the gizzly is highly controlled; 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 l0%o. The exhaust from the induced draft (ID) fans used on the grizzly is ducted through a baghouse. The combined particulate dust 34489 - February 2007 4-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill control on this operation is assumed tobe99.9o/o. U-238 and its decaydaughters are all emitted at a rate of 9.27E-05 Cilyr (assuming secular equilibrium) for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCilg. Similarly, U-238 and its decay daughters are all emitted at a rate of 2.368-04 Cilyr (assuming secular equilibrium) for Arizona Strip ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 1783 pCi/g. 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 lbs/hr U:Os when the process rate was 1300 lbs/hr. This yields an emission rate of 0.092 lbs/hr of yellowcake per ton of feed (EnecoTech l99la 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), and are based on the proposed ore process rate of Colorado Plateau ore and Arizona Strip Ore. Therefore, U-238 is all emitted at a rate of 1.01E-02 Cilyr for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCilg. Similarly, U-238 is emitted at a rate of 2.368-04 Cilyr for Arizona Strip ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 1783 pCilg. Based on field measurements, the decay daughters of U-238 (Th-230, Ra-226 and Pb-210) are processed along with yellowcake at 0.22o/o,0.13% and 0.78oh, respectively (EnecoTech 1991a and l99lb). Therefore, the decay daughters Th-230, Ra-226 and Pb-210 are emitted at a rate of 2.228-05 Cilyr,1.31E-05 Cilyr and 7.88E-05 Cilyr, respectively for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 730,000 tpy (divided equally between the north and south yellowcake dryers) and an ore specific activity of 700 pCilg. Similarly, the decay daughters Th-230, Ra-226 and Pb-210 are emitted at a rate of 5.67E-05 Cilyr, 3.35E-05 Cilyr and2JlE-04 Ct/yr, respectively for Arizona Strip ore. This calculation assumes the proposed ore process rate of 730,000 tpy (divided equally between the north and south yellowcake dryers) and an ore specific activity of 1783 pCilg. Since the ore processing steps reject nearly all the radium to the tailings, very little radon is released during the production of yellow cake. No significant radon releases occur during yellowcake drying and packaging, since only about 0.lo/o of the original Ra-226 in the ore is found in yellowcake. Therefore, the amount of Rn-222 emitted from the yellowcake stack is assumed to be negligible. 4-434489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill 4.1.4 Vanadium Stack The vanadium stack source term was only used in the MILDOS-AREA model 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 recycled to the counter-current decantation step or further processed for recovery of vanadium before recycling. The product from the vanadium recovery contains less than 0.005% U:Os (NUREG 1980). Therefore, the emission rate for the vanadium stack was calculated to be 0.005o/o of the total emission rate from the yellowcake stacks (north and south yellowcake stack). U-238 is emitted at a rate of 1.01E-06 Ci/yr for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCilg. By adopting the EnecoTech analysis (EnecoTech l99la and 199lb) measurements for the decay daughters of U-238 (Th-230, Ra-226 and Pb-210) processed along with yellowcake of 0.22oh, 0.13% and0.78o/o, respectively, the emissions from the remaining radionuclides are assumed to be negligible and in any event are likely discharged to the tailings ponds. 4.2 Anna Souncrs Mill area sources used in the EnecoTech analysis were also used in this assessment. These sources include the ore pads and the tailings ponds. The area of the ore pad was reduced in this assessment to match anticipated future requirements as discussed below. In addition, the number of tailings ponds was reduced from 5 (used in the EnecoTech analysis) to 4 in this assessment. A description of the 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 of emissions namely unloading ore from trucks to the ore pad and wind emissions. Approximately 300,000 tons of ore is 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 1DUSA, 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 is used in the calculations. U-238 and its decay daughters are all emitted at a rate of 1.58E-02 Cilyr for each isotope for Colorado Plateau ore. This calculation 34489 - Februarv 2007 4-5 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCi/g. Similarly, U-238 and its decay daughters are all emitted at a rate of 4.028-02 Cilyr (assuming secular equilibrium) for Arizona Strip ore. This calculation assumes the proposed ore process rate of 730,000 tpy and an ore specific activity of 1783 pCilg. Wind erosion from the ore pad is assumed to have a 50o/o control factor due to the active watering program in place. 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 gl^'yr; this was calculated using the method from NRC's Regulatory Guide 3.59 (NRC 1987) on the basis of the meteorological data (provided by DUSA (DUSA 2007c) presented in Appendix A; the annual dust loss from the ore pads is 10% that of the tailings piles since the particulates in the ore pads are coarse material (1 to 6 inch) because the ore has not yet been ground. U-238 and its decay daughters are all assumed to be emitted at a rate of 3.178-04 Ci/yr for each isotope for Colorado Plateau ore. This calculation assumes the proposed ore process rate of 300,000 tpy and an ore specific activity of 700 pCi/g. Similarly, U-238 and its decay daughters are all emitted at a rate of 8.07E-04 Cilyr (assuming secular equilibrium) for Arizona Strip ore. This calculation assumes the proposed ore process rate of 300,000 tpy and an ore specific activity of 1783 pCilg. Therefore, the total emission rate of U-238 and its daughter from truck dumping and wind erosion is l.6lE-02 Cilyr and 4.108-02 Cilyr for Colorado Plateau ore 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 Ct/yr and 956 Cilyr for Colorado Plateau ore and Arizona Strip ore, respectively. 4.2.2 Tailings ponds The current, or anticipated, status of the various tailings ponds at the mill are summarized in Table 4.1. In brief, Tailings Cell 1 is used as an evaporation pond and will always have a water cover (tailings solution); hence, no dust or radon emissions are expected from Tailings Cell 1. Tailings Cell 2 is almost entirely covered with an interim soil cover. Data from the 2005 NESHAP's report indicates an average radon flux of 6.6 pCilr*s from covered areas and an average radon flux of 55.8 pCi/m2s from remaining exposed beaches 34489 - February 2007 4-6 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill Tailings Cell Water Cover (acres) Interim Soil Cover (acres) Beach (acres) I 55 2 66.1 0.7 J 35 37 7 4A 36 4 TABLE 4.1 CHARACTERISTICS OF TAILINGS AT WHITE MESA Wind erosion of tailings from Cell 2 will be limited to the small area remaining to be covered. Tailings Cell 3 has a mixture of water cover (tailings solution), an interim soil cover and exposed tailings beach. As for cell l, it is assumed that no tailings dust or radon will be released from the water covered parts of Cell 3. Wind eroded tailings dust would arise from uncovered tailings beach. Radon release rates are based on the 2005 NESHAP's report which indicates a radon flux about 7.1 pCi/m2s from covered areas and24.2pCilm2s from exposed tailings beach. In the case of Cell 4, for present purposes, it is assumed that the cell is fully developed with approximately 36 acres of water cover (tailings solution) and 4 acres of exposed tailings. As mentioned in Section 4.0, large area sources such as the tailings area are divided into smaller sources (four tailings ponds) to allow for the size and irregular shape ofthese areas. Therefore, the tailings areas were divided into four area sources in the MILDOS-AREA run. Tailings ponds I , 2, 3, and 4 represent cell 1 , cell 2, cell 3 and cell 4,A., respectively. Using the onsite wind data generated over the last 3 years (provided by DUSA (DUSA 2007c)), the annual dust loss from the tailings ponds is estimated to be approximately 213 g/m2yr; this was calculated using the method from NRC's Regulatory Guide 3.59 (NRC 1987). It is assumed that the average uranium recovery rate is 94%o. ln addition, a process emission control factor of 70oh was assumed, based on 1) the active watering (tailings solutions spraying) program on exposed areas of tailings beaches in active areas; 2) solutions cover other tailings areas; and 3) crusting agents from the sprayed solutions act to minimize the erosion of the tailings beaches by wind. With these assumptions and the particulate emission factor, U-238 is emitted at a rate of 2.09E-04 Cilyr and the decay daughters Th-230, Ra-226 and Pb-210 are emiffed at a rate of 3.48E-03 Cilyr from Cell2 and 3 while U-238 is emitted at a rate of 1.09E-04 Cilyr and the decay daughters Th-230, Ra-226 and Pb-2 l0 are emitted at a rate of 1 .8 I E-03 Cilyr from Cell 44' for Colorado Plateau ore. These calculations assume the proposed ore process rate of 730,000 tpy and an ore specific activity of 700 pCilg. Similarly, for Arizona Strip ore, U-238 is emitted at a rate of 5.328-04 Cilyr and the decay daughters Th-230, Ra-226 and Pb-210 are emitted at a rate 34489 - February 2007 4-7 SENES Consultants Limited 4.3 Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill of 8.87E-03 Cilyr from Cell2 and 3 while U-238 is emitted at a rate of 2.768-04 Cilyr and the decay daughters Th-230,Ra-226 and Pb-210 are emitted at arate of 4.61E-03 Cilyr from Cell 44' for Arizona Strip ore. These calculations assume the proposed ore process rate of 730,000 tpy and an ore specific activity of 1783 pCi/g. The tailings consist of a mixture of sands and slimes, which are the sources of radon. The National Emission Standards for Hazardous Air Pollutants (NESHAPS) (Regulation 40 CFR60, Subpart W) standard limits theRn-222 emission rate to 20 pCi/m2s from uranium mills and their associated tailings impoundments. [n order to demonstrate compliance with NESHAP's, the mill carries out a NESHAP's evaluation on an annual basis. As indicated previously, data from the 2005 NESHAP's report (IUC, 2005) was used in this assessment. In this analysis, a total annual radon releases rate of approximately 130 Ci/yr was estimated for the tailings source. MnrBoRor,oGrcAL Dara Meteorological conditions influence re-suspension and dispersion of radionuclides from point sources and area sources. The mill has an onsite weathering monitoring station that records the wind speed, wind direction and stability class. This data is used to formulate a joint frequency distribution which is a required input for MILDOS-AREA. The joint frequency distribution used in this assessment was provided by DUSA (DUSA 2007c) using the most recent three years (2004 to 2006) of recorded data. 4.4 PopularroN DATA The population data was obtained from the year 2000 U.S. census and were used to complete demographic and population dose projections. Census data is only available in 10 year intervals and local demographics have experienced little change since the 2000 census. 4.5 URaNruu Mrr,r, Souncp Erratsslox RarBs 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 4.2. 4-834489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill TABLE 4.2 RADIOACTIVE PARTICULATE AND RADON EMISSION RATES (coLoRADO PLATEAU ORE) a) No signihcant release during this process. b) Source is exclusive to the processing ofColorado Plateau 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, rcspectively for Arizona Strip ore are provided in Table 4.3. TABLE 4.3 RADIOACTIVE PARTICULATE AND RADON EMISSION RATES (ARTZONA STRrP ORE) Process Grinding Ore Dump to Grizzly 0re Pads North YC Stack South YC Stack Tailings Cell2 and 3 Tailings Cell4A Vanadium Stackb Emission Rate (Cilyr) u-238 9.27E-05 9.278-05 t.6tE-02 1.0lE-02 l.0lE-02 2.09E-04 1.09E-04 l.0lE-06 Th-230 9.27E-O5 9.278-05 1.61E-02 2.228-O5 2.22E-05 3.48E-03 l.8lE-03 222E-09 Ra-226 9.278-05 9.27E-05 t.6tE-02 t.3lE-05 t.3l E-05 3.48E-03 t.8l8,03 l.3l E-059 Pb-2 l0 9.27E-05 9.278-05 t.6tE-02 7.888-05 7.88E-05 3.48E-03 l.8lE-03 7.88E-09 Rn-222 9.278+01 Note a 3.758+02 Note a Note a 117.71 12.36 Note a Notes: Process Grinding Ore Dump to Grizzly Ore Pads North YC Stack South YC Stack Tailings Cell 2 and 3 Tailings Cell4A Emission Rate (Cilyr) u-238 2.36E-04 2.368-04 4 oE-02 2.588-02 2.58E-02 5.32E-04 2.768-04 Th-230 2.368-04 2.36E-04 4.0E-02 5.67E-05 5.67E-05 8.87E-03 4.61E-03 Ra-226 2.368-04 2.368-04 4 0E-02 3.35E-05 3.35E-05 8.87E-03 4.61E-03 Pb-2 I 0 2.36E-04 2.368-04 4 0E-02 2.01E-04 2.01E-04 8.87E-03 4.61E-03 Rn-222 2.368+02 9.568+02 Note a Note a tt7 .7 |t2.36 Note: a) No significant release during this process. 4-934489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill 5.0 RECEPTORS The receptors used in this assessment were provided by DUSA. The receptors used in this assessment are as follows: o Nearest Historical Resident (BHV-2); o Nearest Actual Resident o Nearest Potential Resident (BHV-I); o White Mesa Ute Community; o Blanding, Utah. ln addition, two grazing locations I and2 are considered as a possible source of meat. As mentioned in Section 1.3, the receptor locations were determined using a GPS receiver and were provided by DUSA (DUSA 2007b). The GPS coordinates were used for all the receptors except for Grazing location I and2 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. 34489 - February 2007 5-l SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill FIGURE 5.1 RECEPTOR LOCATIONS WITH RESPECT TO THE VANADIUM STACK 34489 - Februarv 2007 5-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Applicotion & Environmental Report for Wite Mesa Uranium Mill At the time of the 1979 Final Environmental Statement (FES) 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 'opotential" resident is approximately 1.2 miles (1.9 km) north of the Mill, near the location of air monitoring station BHV-1. The nearest actual resident is located approximately 1.6 miles (2.5 km) north of the mill. Nearby population groups 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 l) 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 l99la and 1991b). Although considered unlikely, in one worst case scenario, it is possible that the meat animal grazed at Grazing location I and 2 would be eaten by the residents near the mill. We have not included a scenario whereby it is assumed that gtazing at Grazing locations I and 2 supports dairy cattle, because the prospect of supporting dairy cattle in those locations is not credible, given the arid climate and the much larger feed requirements of dairy cattle as opposed to beef cattle. We have also been advised by DUSA that no dairy catlle graze in Grazing locations I and2. It should be noted, however, that in all of the MILDOS AREA model runs in this report, we did assume, conservatively, that individuals at each receptor location are assumed to drink all of their milk from cows and eat all of their beef from cattle that graze at the receptor location (but not at Grazing locations I or 2). This is also thought to be a very conservative assumption. 34489 - February 2007 5-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill 6.0 RADIATION DOSE ESTIMATES This section describes the MILDOS-AREA results of the mill's potential radiological impacts to the population in the vicinity of the Mill. This analysis is 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 have been included in the MILDOS-AREA model. MILDOS-AREA calculates the total annual effective dose commitment (including radon). The calculated total annual effective dose commitments are compared to the 10 CFR20 (R313-15) requirements that the dose to individual members of the public shall not exceed 100 mrem/yr (radon included). In addition, MILDOS-AREA calculates 40 CFRI9O doses (excludes radon). The 40 CFRI90 Criterion 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 40CFR 190 doses are also used to demonstrate compliance with 10 CFR20.ll0l(d) (R313-15-l0l(4)). Under 10 CFR 20.llOl(d) (R313-15-101(4) the licensee must demonstrate that the total effective dose equivalent to the individual member of the public likely to receive the highest total effective dose equivalent will not exceed l0 mrem/yr (absent of the radon dose). In this assessment, a worst case scenario in which there is a possibility that individuals near the mill ingest meat from cattle grown at Grazing Location I or 2 is considered. It is assumed that the cattle will graze at Grazing location I or 2 for 2 months of the year (due to the arid nature of the region and the lack of forage). Therefore, the meat ingestion dose to individuals near the mill who might consume beef grazed at Grazing Location I or 2 is assumed to be one-sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations. MILDOS-AREA was run separately for Colorado Plateau ore and Arizona Strip ore. Total annual dose commitments and 40 CFRI9O annual dose commitments were estimated for locations in which individual members of the public might reside (BHV-I (nearest potential resident), BHV-2, Nearest Actual Resident, White Mesa Ute Community and Blanding, Utah) are provided in Sections 6.1 and 6.2 for Colorado Plateau ore and Arizona Strip ore, respectively. In addition, total annual dose commitments and 40 CFR190 annual dose commitments from the meat ingestion pathway that is estimated for Grazing location I and 2 are provided in Sections 6.1and6.2. 34489 - February 2007 6-l SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill 6.1 MILDOS-Anr.q. Rrsulrs Fon Cor,oRADo Pla,roau Onr 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 is calculated using MILDOS-AREA. As mentioned in Section 1.2, the proposed ore process rate for the Colorado Plateau ore is approximately 730,000 tpy. Assuming that the average uranium recovery is at the historical recovery yield of 94o/o, the ore processing operations is expected to yield 1715 tons (3,431,000 lbs) of U:O8 per year. The MILDOS-AREA-calculated total annual dose commitments (including radon) and 40 CFR190 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(lXa) Regulatory Compliance The MILDOS-AREA calculated total annual dose commitments (including radon) are provided in this section. These doses are regulated by R3l3-15-301(l)(a) which requires the dose to an individual member of the public shall not exceed 100 mrem/yr (radon included). Table 6.1 presents a summary of the individual dose commitments for the residential receptors for the age group of infant, child, teenage and adult. TABLE 6.1 COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE RADIATION PROTECTTON STANDARDS (COLORADO PLATEAU ORE) Location Age Grorrn Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Nearest Potential Resident (BHV-1) Infant Effective 1.20E+00 100 t.20E-02 Bone 1.86E+00 Avs. Lung 5.01E-01 Bronchi 1.05E+01 child Effective 8.93E-01 100 8.93E-03 Bone 1.31E+00 Avg. Lung 6.68E-01 Bronchi 1.058+0t Teenage Effective 9.34E-01 100 9.348-03 Bone 4.65E+00 Avs. Luns 5.34E-01 Bronchi 1.05E+01 Adult Effective 8.25E-01 100 8.25E-03 Bone 2.04E+00 Avs. Lung 3.728-01 Bronchi 1.05E+01 6-234489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill TABLE 6.1 (Cont'd) COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE RADIATION PROTECTTON STANDARDS (COLORADO PLATEAU ORE) Location Age Grorrn Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Nearest Historical Resident (BHV-2) Infant Effective 2.548-01 100 2.548-03 Bone 2.898-01 Ave. Luns 9.56E-02 Bronchi 2.698+00 child Effective 2.10E-01 100 2.10E-03 Bone 2.16E-01 Ave. Lune 1.17E-0t Bronchi 2.69E+00 Teenage Effective 2.t6E-O1 100 2.168-03 Bone 7. 1 8E-0 t Ave. Lune 9.428-02 Bronchi 2.69E+00 Adult Effective 2.00E-01 100 2.008-03 Bone 3.288-01 Avs. Lune 6.85E-02 Bronchi 2.698+00 Nearest Actual Resident lnfant Effective 7.s9E-01 100 7.59E-03 Bone 1.098+00 Avg. Lung 2.958-0t Bronchi 7.01E+00 child Effective s.77F-01 100 5.778-03 Bone 7.7 tE-ot Avg. Lung 3.93E-01 Bronchi 7.01E+00 Teenage Effective 6.01E-01 100 6.01E-03 Bone 2.70E+00 Avs. Luns 3. I 6E-0 I Bronchi 7.01E+00 Adult Effective 5.388-01 r00 5.388-03 Bone l.l9E+00 Avs. Luns 2.21E-01 Bronchi 7.01E+00 34489 - Februarv 2007 6-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill TABLE 6.1 (Cont'd) COMPARISON OF ANNUAL DOSE COMMITMENTS TO APPLICABLE RADIATION PROTECTION STANDARDS (COLORADO PLATEAU ORE) Location Age Group Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit White Mesa Community Infant Effective 1.77F-01 r00 t.77E-03 Bone 1.29E-01 Avs. Luns 5.5sE-02 Bronchi 2.16E+00 child Effective 1.56E-01 r00 t.s6E-03 Bone 9.088-02 Avs. Lune 5.2t8-02 Bronchi 2.16E+00 Teenage Effective 1.57E-0 t 100 1.57E-03 Bone 2.48E-01 Ave. Luns 4.t5E-02 Bronchi 2.16E+00 Adult Effective 1.52E-01 100 t.s2E-03 Bone 1.25E-01 Avs. Luns 3.31E-02 Bronchi 2.16E+00 Blanding Infant Effective 8.37E-02 100 8.37E-04 Bone 8.26E-02 Ave. Lune 2.918-02 Bronchi 9.21E-01 child Effective 7.098-02 100 7.098-04 Bone 6.00E-02 Avs. Lune 3.358-02 Bronchi 9.218-01 Teenase Effective 7.238-02 100 7.23E-04 Bone 1.898-01 Ave. Lune 2.73E-02 Bronchi 9.2tF-01 Adult Effective 6.81E-02 100 6.81E-04 Bone 8.89E-02 Ave. Lung 2.O6E-02 Bronchi 9.21E-01 From Table 6.1, the total annual effective dose commitments are at most 0.0120 (effective dose for infant at BHV-I) of the R3l3-15-301(lXa) limit of 100 mrem/yr (radon included) to an individual member of the public. Therefore, the predicted annual effective dose commitments comply with R3 13-1 5-30 1. 6-434489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Mesa Uranium Mill In the worst case scenario in which there is a possibility that individuals near the mill ingest meat from cattle grown at Grazing Location I or 2. It is 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 beef grazed at Grazing Location 1 or 2 is assumed to be one-sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations. Table 6.2 presents a summary of the annual dose commitments from the meat ingestion pathway for Grazing location I and2. Even in the very unlikely event that a resident were to consume meat from one of the grazing locations, the total dose would remain well below regulatory limits. TABLE 6.2 TOTAL ANNUAL DOSE COMMITMENTS (mrem) FOR MEAT INGESTION PATHWAY (COLORADO PLATEAU ORE) Location Age Group Organb Effectiye'Bone"Avg. Lung' Gruzins. Location I Infant 0.0081{0 0.00E+00 0.00E+00 child 1.088-02 5.35E-02 4.878-02 Teenaqe 1.68E-02 2.788-01 4.27E-02 Adult 1.228-02 l.slE-01 3.52E-02 Grazins. Location 2 Infant 0.00E+00 0.00E+00 0.00E+00 chitd 5.828-04 2.88E-03 2.38E-03 Teenase 8.9sE-04 t.52E-02 2.08E-03 Adult 6.358-04 7.93E-03 1.728-03 Note: a) Assumes cattle will graze at the particular Grazing location for 2 months of the year. b) Exclusive ofradon. 6.1.2 40 CFR190 Regulatory Compliance MILDOS-AREA calculated 40 CFR190 doses (excludes radon). These doses are regulated by the 40 CFR190 criterion, which is 25 millirem (mrem) to the whole body (excluding the dose due to radon) (EPA 2002) or to any organ of the body. The 40CFR 190 doses are also used to demonstrate compliance with R3l3-15-l0l(4) (10 CFR20.1101(d). The licensee must 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 l0 mrem/yr (absent of the radon dose). Table 6.3 presents a summary of the 40 CFR190 individual dose commitments for the residential receptors for the age group of infant, child, teenage and adult. 34489 - February 2007 6-5 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill TABLE 6.3 COMPARISON OF 40 CFR19O ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (coLoRADO PLATEAU ORE) Location Age Groun Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Nearest Potential Resident (BHV-l) Infant Effective 5.358-01 25 2.t48-02 Bone L82E+00 25 7.298-02 Avs. Luns 4.63E-01 25 1.85E-02 Bronchi 9.55E-04 not limited child Effective 2.238-01 25 8.94E-03 Bone t.278+00 25 5. I 0E-02 Avs. Lune 6.308-01 25 2.s2F-02 Bronchi 9.55E-04 not limited Teenage Effective 2.65E-01 25 1.068-02 Bone 4.628+00 25 1.85E-01 Avs. Luns 4.96E-01 25 1.98E-02 Bronchi 9.558-04 not limited Adult Effective 1.568-01 25 6.248-03 Bone 2.00E+00 25 7.99E-02 Ave. Luns 3.33E-01 25 1.33E-02 Bronchi 9.55E-04 not limited Nearest Historical Resident (BHV-2) Infant Effective 7.84E-02 25 3.14E-03 Bone 2.72E-01 25 1.09E-02 Avs. Lune 8.018-02 25 3.21E-03 Bronchi 1.358-04 not limited child Effective 3.42E-02 25 1.37E-03 Bone 1.988-01 25 7.918-03 Avs. Luns 1.00E-01 25 4.018-03 Bronchi 1.35E-04 not limited Teenage Effective 4.03E-02 25 l.6l E-03 Bone 6.92E-0t 25 2.77E-02 Avs. Luns 7.768-02 25 3. l0E-03 Bronchi 1.358-04 not limited Adult Effective 2.408-02 25 9.618-04 Bone 3.07E-01 25 t.23E-02 Avp. Lune 5.258-02 25 2.10E-03 Bronchi 1.358-04 not limited 6-634489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill TABLE 6.3 (Cont'd) COMPARISON OF 40 CFR19O ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (coLoRADO PLATEAU ORE) Location Age Grouo Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Infant Effective 3. I I E-01 25 1.258-02 Bone 1.06E+00 25 4.258-02 Ave. Luns 2.678-0r 25 1.078-02 Bronchi 5.50E-04 not limited child Effective 1.30E-01 25 5.188-03 Bone 7.40E-01 25 2.968-02 Avs. Luns 3.63E-01 25 1.458-02 Bronchi 5.508-04 not limited Teenape Effective 1.53E-01 25 6. l4E-03 Bone 2.66E+00 25 t.07E-01 Avs. Luns 2.868-01 25 t.t4E-02 Bronchi 5.508-04 not limited Adult Effective 9.018-02 25 3.60E-03 Bone 1.16E+00 25 4.648-02 Avs. Lung 1.93E-01 25 7.70F-03 Bronchi 5.50E-04 not limited Infant Effective 3. I 8E-02 25 t.278-03 Bone l.l lE-01 25 4.438-03 Avs. Luns 4.048-02 25 1.628-03 Bronchi 4.06E-05 not limited child Effective I . l8E-02 25 4.738-04 Bone 7.018-02 25 2.808-03 Ave. Luns 3.398-02 25 r.35E-03 Bronchi 4.068-0s not limited Teenage Effective t.24E-02 25 4.95E-04 Bone 2. I 0E-0 t 25 8.388-03 Ave. Lune 2.398-02 25 9.568-04 Bronchi 4.06E-0s not limited Adult Effective 7.758-03 25 3.10E-04 Bone 9.888-02 25 3.958-03 Avs. Luns 1.68E-02 25 6.718-04 Bronchi 4.068-05 not limited 34489 - February 2007 6-7 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill TABLE 6.3 (Cont'd) COMPARISON OF 40 CFRl9O ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (coLoRADO PLATEAU ORE) Location Age Gronn Organ Estimated Dose (mrem/vr'l Applicable Limit (mrem/vr) Fraction of Limit Blanding Infant Effective 2.138-02 25 8.51E-04 Bone 7.34E-02 25 2.948-03 Avg. Luns 2.188-02 25 8.738-04 Bronchi 3.36E-05 not limited child Effective 8.58E-03 25 3.438-04 Bone 4.978-02 25 1.998-03 Avs. Lung 2.448-02 25 9.788-04 Bronchi 3.368-05 not limited Teenage Effective 9.778-03 25 3.91E-04 Bone 1.698-01 25 6.75E-03 Avg. Luns 1.86E-02 25 7.43E-04 Bronchi 3.36E-05 not limited Adult Effective 5.87E-03 25 2.358-04 Bone 7.51E-02 25 3.00E-03 Avs. Luns 1.26E-02 25 5.06E-04 Bronchi 3.36E-05 not limited From Table 6.3, the 40 CFR190 annual dose commitments are at most 0.185 (dose to the bone for the teen at BHV-I) of the 40 CFRI9O dose criterion of 25 mremlyr. In addition, the 40CFRI9O annual effective dose commitments demonstrate compliance with the R313-15- 101(4) (10 CFR20.1101(d) limit 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 0.535 mrem/yr (infant at BHV-l), or 0.0214 of the 10 mrem/yr limit. In the worst case scenario in which there is a possibility that individuals near the mill ingest meat from caffle grown at Grazing Locations I or 2, it is 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 beef grazed at Grazing Location I or 2 is assumed to be one-sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations. Table 6.4 presents a summary of the 40 CFRI9O 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 - Februarv 2007 6-8 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill TABLE 6.4 40 CFR190 ANNUAL DOSE COMMITMENTS (mrem) FOR MEAT INGESTION PATHWAY (COLORADO PLATEAU ORE) Location Age Group Organo Effective"Bone"Avs. Luns" Grazing Location I Infant 0.008+00 0.008+00 0.008+00 child 1.08E-02 5.358-02 4.87E-O2 Teenase 1.68E-02 2.78E-01 4.278-02 Adult 1.22E-02 L5IE-01 3.52E-02 Grazing Location 2 Infant 0.008+00 0.00E+00 0.00E+00 child 5.80E-04 2.878-03 2.378-03 Teenase 8.92E-04 t.s2E-02 2.078-03 Adult 6.33E-04 7.908-03 1.728-03 Note: a) Assumes cattle will graze at the particular Grazing location for 2 months of the year. b) Exclusive ofradon. The annual doses to the population estimated within 50 miles (80 km) of the site are provided in Table 6.5. TABLE 6.5 ANNUAL POPULATION DOSE COMMITMENTS WITHIN 50 MILES (80 km) OF THE MILL FOR COLORADO PLATEAU ORE Organ ANNUAL POPULATION DOSE COMMITMENTS, PERSON-REM PER YEAR Mill Ooerations Effective Bone Avg. Lung Bronchi l.l5E-01 9.18E-01 1.22F-01 6.28E+00 The population dose arising from the processing of Colorado Plateau ore is estimated at 0.15 person-rem. This can be compared to the dose from natural background sources of In the United States, nominal average levels of natural background radiation are as follows (National Council on Radiation Protection and Measurements (NCRP), 1987): Cosmic and Cosmogenic Terrestrial Inhaled (Radon) Ingested Total (Average) 28 mrem/yr 28 mrem/yr 200 mrem/yr 40 mrem /yr 296 mremlyr (96 mrem/yr excluding radon) 34489 - February 2007 6-9 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for 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 T4mremlyr came from terrestrial radiation. (Dames & Moore, 1978). At the Hanksville site, the corresponding average dose equivalent was about 122 mrem/yr (68 mrem/yr from cosmic radiation and 54 mrem/yr from terrestrial radiation). (Dames & Moore, 1978). lngested 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 of the dose from radon-222, to about 161 mrem/yr; which is higher than both the US averages of 96 mrem/yr. If the nominal U.S. dose from radon of about 200 mrem per year is added, then the total dose from natural background in the area of the mill is 360 mrem/y (or more assuming the dose from radon would increase along with that from terrestrial source). The current 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/y, 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. 6.2 MILDOS-ARna Rpsulrs FoRARTzoNA SrRrp 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 of Arizona Strip ore is calculated using MILDOS-AREA. As mentioned in Section 1.2, the proposed ore process rate for Arizona Strip ore is approximately 730,000 tpy. Assuming that the average uranium recovery is at the historical recovery yield of 94Yo, the ore processing operations is expected to yield 4,371 tons (8,742,188lbs) of yellowcake per year. The MILDOS-AREA calculated total annual dose commitments (including radon) and 40 CFR190 annual dose commitments for processing of Arizona Strip ore are provided in Sections 6.2.1 and 6.2.2, respectively. 34489 - February 2007 6-10 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill 6.2.1 Ri13-15-301 (lXa) Regulatory Compliance The MILDOS-AREA calculated total annual dose commitments (including radon) are provided in this section. These doses are regulated by R3l3-15-301(1Xa) which requires the dose to an individual member of the public shall not exceed 100 mrem/yr (radon included). Table 6.6 presents a summary of the individual dose commitments for the residential receptors for the age group of infant, child, teenage and adult. TABLE 6.6 COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Groun Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Nearest Potential Resident (BHV-l) lnfant Effective 2.94E+00 100 2.94E-02 Bone 4.748+00 Avg. I-uns 1.27E+00 Bronchi 2.49E+01 chitd Effective 2. l5E+00 100 2.t5E-02 Bone 3.35E+00 Avg. Luns 1.698+00 Bronchi 2.498+01 Teenase Effective 2.25E$0 100 2.258-02 Bone l.l8E+01 Avg. Lung 1.35E+00 Bronchi 2.498+01 Adult Effective 1.97E+00 100 1.97E-02 Bone 5. I 9E+00 Avg. Lune 9.408-01 Bronchi 2.49E+01 34489 - February 2007 6-1 1 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill TABLE 6.6 (Cont'd) COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Groun Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit Nearest Historical Resident (BHV-2) Infant Effective 6.008-01 100 6.00E-03 Bone 7.35E-01 Avg. Luns 2.40E-01 Bronchi 6.098+00 child Effective 4.87E-01 100 4.87E-03 Bone 5.458-01 Avg. Luns 2.948-Ot Bronchi 6.098+00 Teenase Effective s.038-01 100 5.03E-03 Bone 1.82E+00 Avg. Lung 2.36E-01 Bronchi 6.09E+00 Adult Effective 4.60E-01 100 4.60E-03 Bone 8.29E-0t Avg. Lung 1.70E-01 Bronchi 6.09E+00 Nearest Actual Resident Infant Effective 1.838+00 r00 L838-02 Bone 2.788+00 Avg. [-uns 7.478-01 Bronchi 1.63E+01 chitd Effective 1.37E+00 t00 1378-02 Bone 1.96E+00 Avg. Luns 9.968-01 Bronchi 1.63E+01 Teenase Effective 1.43E+00 100 t.43E-02 Bone 6.888+00 Avg. Lunp 7.99E-01 Bronchi 1.638+01 Adult Effective 1.278+00 100 1.278-02 Bone 3.03E+00 Avg. Lrrns 5.598-01 Bronchi 1.638+01 34489 - February 2007 6-12 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill TABLE 6.6 (Cont'd) COMPARISON OF ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Grouo Organ Estimated Dose (mrem/vr) Applicable Limit (mrem/vr) Fraction of Limit White Mesa Community lnfant Effective 3.96E-0r 100 3.96E-03 Bone 3.238-01 Avg. Luns 1.36E-01 Bronchi 4.728+00 child Effective 3.458-0t 100 3.45E-03 Bone 2.248-01 Avg. Lung t.268-01 Bronchi 4.728+00 Teenase Effective 3.47E-01 r00 3.47E-03 Bone 6.188-01 Avg. Lung 9.94E-02 Bronchi 4.728+00 Adult Effective 3.34E-01 t00 3.348-03 Bone 3.10E-01 Avg. Luns 7.868-02 Bronchi 4.72E+00 Blanding Infant Effective 1.94E-01 100 1.94E-03 Bone 2.08E-01 Avg. Lung 7.20E-02 Bronchi 2.06E+00 child Effective t.628-01 100 t.628-03 Bone 1.50E-01 Avg. Luns 8.278-02 Bronchi 2.06E+00 Teenage Effective 1.65E-01 100 1.65E-03 Bone 4.74F-01 Avg. [.uns 6.68E-02 Bronchi 2.06E+00 Adult Effective 1.548-01 100 1.548-03 Bone 2.22F,01 Avg. Luns 5.028-02 Bronchi 2.06E+00 34489 - February 2007 6-t3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Mesa Uranium Mill From Table 6.6, the total annual effective dose commitments are at most 0.0294 (effective dose for infant at BHV-I) of the R313-15-301(1)(a) of 100 mrem/yr (radon included) to an individual member of the public. Therefore, the predicted annual effective dose commitments comply with R3 l3-l s-101(l)(a). In the worst case scenario in which there is a possibility that individuals near the mill ingest meat from cattle grown at Grazing Location I or 2. It is 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 beef grazed at Grazing Location I or 2 is assumed to be one-sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations. Table 6.7 presents a summary of the annual dose commitments from the meat ingestion pathway for Grazing location I and2. As before, even 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 6.7 TOTAL ANNUAL DOSE COMMITMENTS FOR MEAT INGESTION PATHWAY (ARTZONA STRrP ORE) Location Age Group organb Effective"Bone"Avs. Lunsu Grazing Location 1 lnfant 0.008+00 0.008+00 0.008+00 child 2.738-02 1.37E-01 t.248-01 Teenage 4.28E-02 7.10E-01 L09E-01 Adult 3. I 0E-02 3.83E-01 8.97E-02 Infant 0.00E+00 0.00E+00 0.00E+00 child 1.48E-03 7.35E-03 6.05E-03.rts Teenase 2.28E-03 3.88E-02 5.30E-03 Adult t.62E-03 2.028-02 4.388-03 Note: a) Assumes cattle will graze at the particular Grazing location for 2 months of the year. b) Exclusive ofradon 6.2.2 40 CFR190 Regulatory Compliance MILDOS-AREA calculated 40 CFR190 doses (excludes radon). These doses are regulated by 40 CFR190 Criterion is 25 millirem (mrem) to the whole body (excluding the dose due to radon) (EPA 2002). The 40CFR 190 doses are also used to demonstrate compliance with R313-15-101(4) (10 CFR20.ll01(d)). The licensee must 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). 34489 - February 2007 6-t4 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill Table 6.8 presents a summary of the 40 CFRI9O individual dose commitments for residential receptors for the age group of infant, child, teenage and adult. TABLE 6.8 COMPARISON OF 40 CFR19O ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Group Organ Estimated Dose (mrern/vr) Applicable Limit (mrem/yr) Fraction of Limit Nearest Potential Resident (BHV-l) lnfant Effective 1.378+00 25 5.478-02 Bone 4.65E+00 25 1.86E-01 Avg. Luns l. l8E+00 25 4.72E-02 Bronchi 2.438-03 not limited child Effective 5.70E-0r 25 2,288-02 Bone 3.248+00 25 L298-01 Avg. Lune 1.60E+00 25 6.418-02 Bronchi 2.43F.03 not limited Teenase Effective 6.75E-01 25 2.708-02 Bone 1.1 7E+0 I 25 4.708-01 Avg. Luns 1.26E+00 25 5.058-02 Bronchi 2.438-03 not limited Adult Effective 3.968-01 25 1.588-02 Bone 5.108+00 25 2.048-01 Avg. Luns 8.488-01 25 3.398-02 Bronchi 2.43E-03 not limited Nearest Historical Resident (BHV-2) Infant Effective 2.008-01 25 8.008-03 Bone 6.968-01 25 2.798-02 Avg. Luns 2.04E-0r 25 8.188-03 Bronchi 3.458-04 not limited child Effective 8.728-02 25 3.498-03 Bone 5.03E-01 25 2.018-02 Avg. Luns 2.558-01 25 1.02E-02 Bronchi 3.458-04 not limited Teenase Effective 1.03E-01 25 4.108-03 Bone 1.768+00 25 7.03F-02 Avg. Lunp 1.988-01 25 7.9r8-03 Bronchi 3.45E-04 not limited Adult Effective 6.1 lE-02 25 2.4s8-03 Bone 7.838-01 25 3.13E-02 Avg. Luns 1.34E-01 25 5.358-03 Bronchi 3.45E-04 not limited 34489 - February 2007 6-1s SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill TABLE 6.8 (Cont'd) COMPARISON OF 40 CFR19O ANNUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Group Organ Estimated Dose (mrem/vr) Applicable Limit (mrem./vr) Fraction of Limit Nearest Actual Resident lnfant Effective 7.938-01 25 3.178-02 Bone 2.71F.+00 25 1.09E-01 Avg. Luns 6.77E-01 25 2.718-02 Bronchi 1.40E-03 not limited child Effective 3.30E-0t 25 t.32E-02 Bone 1.898+00 25 7.548-02 Avg. Lune 9.25E-01 25 3.70E-02 Bronchi 1.40E-03 not limited Teenase Effective 3.91E-01 25 t56E-02 Bone 6.80E+00 25 2.728-01 Avg. Lung 7.288-0t 25 2.9t8-02 Bronchi 1.40E-03 not limited Adult Effective 2.298-01 25 9. I 7E-03 Bone 2.968+00 25 I . I 8E-01 Avg. Luns 4.908-01 25 1.96E-02 Bronchi 1.40E-03 not limited White Mesa Community Infant Effective 8.128-02 25 3.25E-03 Bone 2.828-01 25 Lt3E-02 Avg. Lung t.03E-01 25 4.12E-03 Bronchi 1.038-04 not limited child Effective 3.01E-02 25 1.208-03 Bone 1.79E-01 25 7.15E-03 Avg. Luns 8.628-02 25 3.458-03 Bronchi 1.038-04 not limited Teenage Effective 3.16E-02 25 1.268-03 Bone 5.358-01 25 2.148-02 Avg. [,uns 6.088-02 25 2.43E-03 Bronchi 1.03E-04 not limited Adult Effective r.97E-02 25 7.908-04 Bone 2.53E-01 25 l.0lE-02 Avg. Luns 4.278-02 25 L7lE-03 Bronchi 1.03E-04 not limited 34489 - February 2007 6-16 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill TABLE 6.8 (Cont'd) COMPARISON OF 40 CFR19O AI\NUAL DOSE COMMITMENTS WITH APPLICABLE RADIATION PROTECTION STANDARDS (ARIZONA STRIP ORE) Location Age Groun Organ Estimated Dose (mrem/vr) Applicable Limit (mremiyr) Fraction of Limit Blanding Infant Effective 5.44E-02 25 2.1 8E-03 Bone 1.87E-01 25 7.48E-03 Avg. Luns 5.s7E-02 25 2.238-03 Bronchi 8.578-05 not Iimited child Effective 2.198-02 25 8.768-04 Bone 1.278-01 25 5.06E-03 Avg. Luns 6.24E-02 25 2.498-03 Bronchi 8.57E-05 not limited Teenase Effective 2.49E-02 25 9.958-04 Bone 4.30E-01 25 t.72E-02 Avg. Luns 4.728-02 25 1.89E-03 Bronchi 8.578-05 not limited Adult Effective 1.49E-02 25 s.988-04 Bone 1.92E-01 25 7.668-03 Avg. Luns 3.22E-02 25 1.29E-03 Bronchi 8.578-05 not limited From Table 6.8, the 40 CFRI90 annual dose commitments are at most 0.47 (dose to the bone for the teen at BHV-l) of the 40 CFRI9O dose criterion of 25 mrem/yr. In addition, the 40 CFRI9O annual effective dose commitments demonstrate compliance with R3l3-15-101(4) (10 CFR20.1l0l(d)) limit of 10 mrem/yr to the individual member of the public likely to receive the highest total effective dose equivalent. In the worst case scenario in which there is a possibility that individuals near the mill ingest meat from cattle grown at Grazing Location I or 2. It is 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 beef grazed at Grazing Location I or 2 is assumed to be one-sixth of the MILDOS-AREA calculated meat ingestion dose from these grazing locations. Table 6.9 presents a summary of the 40 CFRI9O annual dose commitments from the meat ingestion pathway for Grazing location I and 2. Again, even in the unlikely event that someone were to consume beef from grazing area I or 2, the total dose would be small and well below regulatory limits. 34489 - Februarv 2007 6-t7 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill TABLE 6.9 40 CFR190 ANNUAL DOSE COMMITMENTS (mrem) FOR MEAT INGESTION PATHWAY (ARTZONA STRrP ORE) Location Age Group Organ Effective"Bone"Avs. Luns" Grazinglocation I Infant 0.00E+00 0.00E+00 0.00E+00 child 2.73E-02 1.378-01 t.24E-01 Teenage 4.28E-02 7.10E-01 1.09E-0r Adult 3. l0E-02 3.83E-01 8.978-02 Grazing Location 2 Infanl 0.00E+00 0.00E+00 0.00E+00 child 1.488-03 7.32E-03 6.03E-03 Teenase 2.278-03 3.878-02 5.288-03 Adult t.6lE-03 2.O2F-02 4.358-03 Note: a) Assumes cattle will graze at the particular Grazing location for 2 months of the year. b) Exclusive ofradon. The annual doses to the population estimated within 50 miles (80 km) of the site are provided in Table 6.10. TABLE 6.10 ANNUAL POPULATION DOSE COMMITMENTS WITHIN 50 MILES (80 km) OF THE MILL FOR ARIZONA STRIP ORE Organ ANNUAL POPULATION DOSE COMMITMENTS, PERSON.REM PER YEAR Mill Ooerations Effective Bone Avg. Lung Bronchi 2.7tE-01 2.21E+00 2.88E-01 1.418+01 The population dose arising from the processing of Colorado Plateau ore is estimated at 0.345 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. In the United States, nominal average levels of natural background radiation are as follows (National Council on Radiation Protection and Measurements (NCRP), 1987): The current 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/y, then the total dose due to natural background is approximately 5184 person-rem. The theoretical incremental dose of 0.345 person-rem is clearly inconsequential by comparison. 34489 - February 2007 6-l 8 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill 7.0 KEY OBSERVATIONS As mentioned in Section 1.0, milling of conventional ore is scheduled for early 2008 when the milling of currently available altemate feed materials completed (DUSA 2007). This dose assessment was prepared in support of the license renewal application for the White Mesa Uranium mill. The goal was to determine the potential doses to populations in the vanity of the mill. In this assessment, MILDOS-AREA was used to estimate the dose commitments received by individuals and the general population within a 50 mile (80 km) radius for the processing of Colorado Plateau ore or Arizona Strip ore. The expected ore grade from the Colorado Plateau ore is an average of 0.25o/o U:Os and l.5o/o YzOs NRC 1980) while the Arizona Strip ore is assumed to contain 0.637% U3O8 (DUSA 2007a). The proposed ore process rate for the Colorado Plateau ore and Arizona Strip ore is approximately 730,000 tons per year (tpy) (2000 tons per day). Assuming that the average uranium recovery is at the historical recovery yield of 94o/o, approximately 1,715 tons (3,431,000 lbs) of U3Os per year would be recovered from Colorado Plateau ore at the proposed ore process rate. Similarly, approximately 4,371 tons (8,742,188 lbs) of UlOs per year would be recovered from Aizona Strip ore at the proposed ore process rate. The proposed operating schedule at the mill is assumed to be 24 hr/day for 365 days per year. The MILDOS-AREA calculated total annual effective dose commitments (including radon) were compared to the R3l3-15-301(1)(a) (10 CFR20) requirements that the dose to individual members of the public shall not exceed 100 mrem/yr (radon included). Overall, the total annual effective dose commitments are at most 0.0120 (effective dose for infant at BHV-I) of the R313-15-301(lXa) (10 CFR20) limit of 100 mrem/yr (radon included) to an individual member of the public for the processing of Colorado Plateau ore. The total annual effective dose commitments are at most 0.0294 (effective dose for infant at BHV-1) of the R313-15-301(l)(a) (10 CFR20) limit of 100 mrem/yr (radon included) to an individual member of the public for the processing of Arizona Strip ore. Therefore, the predicted annual effective dose commitments for anticipated ore processing operations comply with R313-15-301(1)(a) (10 CFR20). ln addition, the MILDOS-AREA-calculated 40 CFRI9O annual dose commitment (excluding radon) were compared to the 40 CFR190 Criterion, which is 25 mremlyr 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 40CFR 190 doses were also used to demonstrate compliance with R313-15-101(4) (10 CFR20.1l0l(d)) (i.e., the licensee must demonstrate that total effective dose equivalent to the individual member of the public likely to receive the highest total effective dose 34489 - February 2007 7-l SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill equivalent will not exceed l0 mrem/yr (absent of the radon dose). Overall, from Table 6.3, the 40 CFRI9O annual dose commitments are at most 0.185 (dose to the bone for the teen at BHV-I) of the 40 CFRI9O dose criterion of 25 mremlyr for Colorado Plateau ore. tn addition, the 40 CFRI90 annual effective dose commitments demonstrate compliance with the R3l3-15-101(4) (10 CFR20.l10l(d) limit of l0 mrem/yr to the individual member of the public likely to receive the highest total effective dose equivalent. From Table 6.8, the 40 CFRI9O annual dose commitments are at most 0.47 (dose to the bone for the teen at BHV-I) of the 40 CFR190 dose criterion of 25 mrem/yr. In addition, the 40 CFRI9O annual effective dose commitments demonstrate compliance with R313-15-101(4) (10 CFR20.1101(d)) limit of l0 mrem/yr to the individual member of the public likely to receive the highest total effective dose equivalent. Therefore, the predicted 40 CFR annual effective dose commitments for anticipated ore processing operations comply with R313 -15 (10 CFR20). 34489 - February 2007 7-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill 8.0 REFERENCES Argonne National Laboratory (ANL) 1998a. MILDOS-AREA, Version 2.208, 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 Standards for Protection Against Radiation. May. Dames & Moore 1978. Environmental Report: Wite Mesa Uranium Project San Juan County, Utahfor Energy Fuels Nuclear, Inc. Jantary. Denison Mines (USA) Corp. (DUSA) 2007. Press Release: Denison Announces Operations Update. January 30. EnecoTech Environmental Consultants 1991a. MILDOS Modeling Results (Letter), Prepared for Umetco Minerals. October 31. EnecoTech Environmental Consultants 199lb. MILDOS Modeling Coruection (Letter), Prepared for Umetco Minerals. November 27. Environmental Protection Agency (EPA) 1989, Code of Federal (CFR) Regulations Title 40 Part National Emission Standards for Hazardous Air Pollutants (NESHAPS), Subpart W. December. Environmental Protection Agency (EPA) 2002. Code of Federal (CFR) Regulations Title 40 Part 190 Environmental Radiation Protectionfor Nuclear Power Operations. February. Google 2005. Google Earth Pro 3.0.0762, November. International Commission on Radiological Protection (ICRP). 1959. Report of ICRP Committee II on Permissible Dosefor Internal Radiation, Health Physics 3:l-380, 1960. International Commission on Radiological Protection (ICRP). 1966. Deposition and retention models for internal dosimetry of the human respiratory tract. Health Physics 12; 173- 207. 34489 - February 2007 8-1 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for White Meso Uranium Mill International Commission on Radiological Protection (ICRP). 1971. Recommendations of the International Commission on Radiological Protectioz. ICRP Publication l0A. Pergamon Press, New York. International Commission on Radiological Protection (ICRP). 1972. The Metabolism of Compounds of Plutonium 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. ruC 2005. NESHAP's Evaluation of White Mesa Mill. Landau, S. (DUSA) 2007a. Email: RE: 34489- Preliminary Mildos Results and Emissions Calculations. Received Feb. 13/07. Nuclear Regulatory Commission (NRC) 1987. Report No. 94. Exposure of Population in the United States and Canadafrom Natural Background Radiation Nuclear Regulatory Commission (NRC) 1979. Final Environmental Statement Related to the Energlt Fuels Nuclear, ftc, NUREG-0556. Docket No. 40-8681. May. Nuclear Regulatory Commission (NRC) 1980. Final Generic Environmental Impact Statement on Uranium Milling Project M-25, NUREG-0706 Vol. 3. September. Nuclear Regulatory Commission (NRC) 1987. Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations, March. Strenge, D.L. and Bander, T.J. 1981. MILDOS- A Computer Program for Calculating Environmental Radiation Doses from Uranium Recovery Operations, NUREG/ CR- 201 l. Prepared for US Nuclear Regulatory Commission. Turk, D. (DUSA) 2007b. Email: RE: Receptor GPS. Received February 14-15. Turk, D. (DUSA) 2007c. Email: 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. 34489 - February 2007 8-2 SENES Consultants Limited Dose A,ssessment in Support af the License Renewal Application & Emtironmental Reportfor White Mesa Uranium Mill APPENDIX A EMIS$ONS CALCULATIONS 3,{489 -February 2007 SENES eonsultants Limitd Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uronium Mill A.O EMISSIONSCALCULATIONS Supplemental Information which describes the model and assumptions used to calculate the sonrce emissions for the sources described in Section 4.0 are provided below. A.1 Calculation of Annual Dust Loss The calculation of the annual dust loss from the ore pads and the tailings ponds was required to calculate an emission factor. This dusting rate for the tailings impoundments is calculated according to the emission factor (E*) equation from NRC's Regulatory Guide 3.59 (NRC 1987). The equation of for the dusting rate is calculated as follows: 3.156x10?*0.5s where, E*: annual dust loss per unit area in d^?rr; Fs: aflnual average frequency of occurrence of wind speed group S (dimensionless) obtained from the joint relative frequency distribution for the mill (provided by DUSA (DUSA 2007c); Rs: resuspension rate for the tailings pond at the average wind speed for wind group S, for particles < 20 pm in diameter in glmzs; 3.156x107: number ofseconds per year; and, 0.5: fraction of the total dust lost constituted by particle < 20 pm in diameter. TABLE A.1 PARAMETER VALUES FOR CALCULATION OF ANNUAL DUSTING RATE FOR EXPOSED TAILINGS a) Resuspension rate of a function of wind speed is computed by the MILDOS code. b) Wind speed frequency obtained from joint frequency distribution data provided by DUSA (DUSA 2007c). A-1 Wind Speed (kts)Average Wind Speed Resuspension Rate (Rs) (g/m's)" Frequency of Occurrence, (Fs)b RsxFg 0to3 1.5 0 0.165 0.00E+00 4to6 5.5 0 0.427 0.00E+00 7tol0 10.0 3.92E-07 0.276 1.08E-07 ll to 16 15.5 9.68E-06 0.106 L03E-06 17 to 2l 21.5 5.71E-05 0.021 1.20E-06 2l+28.0 2.088-04 0.005 1.04E-06 Is 3.37E.06 Notes: 34489 - February 2007 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for Wite Mesa Uranium Mill Using equation A.1 and the parameters in Table A-1, the annual dust loss from the tailings ponds is approximately 213 gl^'yr. As mentioned in Section 4.2.1, the annual dust lost for ore pads is l0o/o of that of the tailings ponds since the particulates 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 il^'yr. L.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 (north and south yellowcake stacks) and the tailings ponds were taken from NRC's Regulatory Guide 3.59 OfRC 1987), NUREG-0706 OrRC 1980) and the EnecoTech analysis (EnecoTech l99la and 1991b). A.2.1 Wet Grinding Radiouctive Partic ulate Emission Rates Colorado Plateau Ore Arizona Strip Ore Process Rate (tpy)730,000 730,000 Contaminant Concentration (pCi/g U-238)700 1783 Process Emission Factor (lbs/ton)u 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 is assumed tobe99.9o/o (EnecoTech l99la and leeeb) The U-238 Emission Rate (S) is calculated as follows: S: (Process Rate (tons/yr))*(Process Emission Factor (lbs/ton))*(453.6 g/lb)*(Contaminant Concentration (pCi/g))*(Activity Enrichment Ratio)*(l-Control Factor)*(10-'' CilpCil (A.2-1) Using equation A.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- 210) are assumed to be in secular equilibrium; therefore the decay daughters are also emitted at a rate of 9.278-05 Cilyr. Similarly, the U-238 Emission Rate from the wet grinding operations of 34489 - February 2007 A-2 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill Arizona Strip ore is approximately 2.368-04 Cilyr and the decay daughters (Th-230, Ra-226 and Pb-210) are also emitted at arate of 2.368-04 Cilyr. Radon Emission Rates Colorado Plateau ore Arizona Strip ore Process Rate (tpy)730,000 730,000 Contaminant Concentratron (pCr/gRa-226) 700 r 783 Activity Factor(%o)"20 20 Note: a) It is assumed that only 20oh of the 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) (NUREG 0706 1980). Radon Release (F): F: (Process Rate (tons/yr))*(2000 lbs/ton)*(453.6 g/ton)*(Contaminant Concentration pCi/g Ra- 226)*Oo't2 CilpCi)*(Activity Factor) ( -2-2) Using equation A.2-2, the radon release from the wet grinding operations of Colorado Plateau ore is approximately 92.7 Cilyr. Similarly, the radon release from the wet grinding operations of Aizona Strip ore is approximately 236 Cilyr. A.2.2 Ore Dump to Grizzly Radioactive Partic ulate E mission Rates Colorado Plateau Ore Arizona Strip Ore Process Rate (tpy)730,000 730,000 Contaminant Concentration (pCi/g U-238)700 I 783 Process Emission Factor (lbs/ton)"0.l6 0.16 Activity Enrichment Ratio 2.s 2.5 Control Factor (%)99.90 99.90 Notes: a) For moisture <8% (NRC 1987). b) Gizzly Dump is enclosed on three sides. Trucks dump inside enclosure under negative pressure. The ID fans are ducted through a baghouse. Ore moisture content is l0 %. 34489 - February 2007 A-3 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Report for ll'hite Mesa Uranium Mill The U-238 Emission Rate (S) is calculated as follows: S: (Process Rate (tons/yr))*(Process Emission Factor (lbs/ton))*(453.6 g/lb)*(Contaminant Concentration (pCi/g))*(Activity Enrichment Ratio)*(l-Control Factor)*(10'" Cilpctl (A.2-3) Using equation A.2-3, the U-238 Emission Rate due to the trucks dumping Colorado Plateau ore on the gizzly is approximately 9.278-05 Cilyr. 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 Ctlyr. Similarly, the U-238 Emission Rate due to the trucks dumping Arizona Strip ore on the gizzly is approximately 2.368-04 Crlyr and the decay daughters (Th-230, Ra-226 and Pb-210) are also emitted at a rate of 2.368-04 Crlyr. Radon Emission Rates No radon is released from the trucks dumping ore onto the grizzly. A.2.3 YellowcakeStacks As mentioned in Section 4.1.3, the mill has two stack dryers); therefore the total emissions were stacks (i.e., north and south yellowcake stacks). Radioactive Partic ulate E mission Rates yellowcake dryers (north and south yellowcake assumed to be divided equally between the two Colorado Plateau Ore Arizona Strip Ore Process Rate (tpy U3Os)t7t6 4371 Contaminant Concentration (Cilg of U-238)3.338-07 3.338-07 Process Emission Factor (g U-238/g U3Os)0.848 0.848 Emission Rate/ Control Factor (lbs/ton)u 0.092 0.092 Note: a) Based stack tests that showed an emission rate of 0.06 lbsnu UrOe per 1300 lbs/hr process rate which translates to 0.092 lb/ton including controls. The U-238 Emission Rate (S) for one yellowcake stack is calculated as follows: S: [(Process Rate (tons/yr U:Os))*(Emission Rate (lbs/ton))*(Process Emission Factor)* (453.6gllb)*(ContaminantConcentration(Crlg))llz ( .2-4\ 34489 - February 2007 A-4 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill Based on field measurements, the decay daughters Th-230, Ra-226 and Pb-210 are processed along with yellowcake at 0.22oh,0.13% and0.78oh, respectively. Using equation A.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 Tlt-230, Ra-226 and Pb-210 is 2.228-05 Cilyr, 1.31E-05 Cilyr and 7.88E-05 Cilyr, respectively from each yellowcake stack (north and south yellowcake stacks). Similarly, the U-238 Emission Rate from each yellowcake stack (north and south yellowcake stacks) is approximately 2.58E-02 Cilyr 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 Crlyr, 3.358-05 Cilyr and 2.018-04 Cilyr, respectively from each yellowcake stack (north and south yellowcake stacks). Radon Emission Rates There is no significant radon releases during this process. A.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% UrOs (NUREG 1980). Therefore, the emission rates of U-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). Radioactive Particulate Emission Rate (S) (CUvr) Total from Yellowcake Stacks Vanadium Stack" u-238 2.028-02 1.52E-06 Th-230 4.458-05 3.348-09 Ra-226 2.638-05 1.97E-09 Pb-210 1.58E-04 t.l8E-08 Note: a) Total from yellowcake stacks (north and south yellowcake stacks)*0.005% Radon Emission Rates There are no significant radon releases during this process 34489 - February 2007 A-5 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill A.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. and bulk density of ore of 120 lbs/ft3 (1.47 tons/yd3;. Usirrg these assumptions, the area of the ore pad is approximately I 7,000 m2. Radioactive Particulate Emission Rates Source Description: Truck Unloading Colorado Plateau Ore Arizona Strip Ore Process Rate (tpy)730,000 730,000 Contaminant Concentration (pCi/g U-238)700 1783 Process Emission Factor (lbs/yd')"0.04 0.04 Activity Emission Ratio 2.5 2.5 Control Factor None None Bulk Density of Ore (tons/yd')1.47 1.47 Note: a) Process emission factor for Truck end dump (NUREG 1987). The U-238 Emission Rate (S) is calculated as follows: S: (Process Rate (tons/yr))*(t yd3lt.+l tons)*(Process Emission Factor (lbs/yd3))*(453.6 g/lb)*(Contaminant Concentration (pCi/g))x(Activity Enrichment Ratio)*(10-" Cilpcil (A.2-5) Using equation A.2-5, the U-238 Emission Rate from truck unloading Colorado Plateau ore is approximately 1.58E-02 Crlyr. 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 1.58E-02 Cilyr. Similarly, the U-238 Emission Rate from truck unloading of Arizona Strip ore is approximately 4.02E-02 Cilyr and the decay daughters (Th-230, Ra-226 and Pb-210) are also emitted at arate of 4.02E-04 Cilyr. 34489 - February 2007 A-6 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill Colorado Plateau Ore Arizona Strip Ore Area (m')'17000 17000 Contaminant Concentration (pCi/g U-238)700 1783 Process Emission Factor,Ey (g/m'yr)"21.29 21.29 Activity Enrichment Ratio 2.5 ')< Control Factor (%o)'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 A. 1. c) The control factor of 50% is based on the assumption that an active watering progam will be in place during operations. The U-238 Emission Rate (S) is calculated as follows: S: (Process Emission Factor (d*2y.))*(Area (m2))*(Contaminant Concentration (pci/g)) *(Activity Enrichment Ratio)*(l-Control Factor)*(10-'' Ci/pcil (A.2-6) Using equation A.2-6, the U-238 Emission Rate from trucks unloading Colorado Plateau ore is approximately 3.1,78-04 Cilyr. 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 3.178-04 Cilyr. Similarly, the U-238 Emission Rate from truck unloading of Arizona Strip ore is approximately 8.07E-04 Cilyr Cilyr and the decay daughters (Th-230, Ra-226 and Pb-210) are also emitted atarute of 8.07E-04 Cilyr. The total radioactive particulate emission rates from the ore pad are obtained by adding the results of truck unloading and wind erosion and are as follows: Radioactive Particulate Emission Rate (S) (Ci/yr) Colorado Plateau Ore Arizona Strip Ore u-238 l.6l E-02 4.toE.-o2 Th-230 l.6tE-02 4.10F-02 Ra-226 t.6tE-02 4.t0E-02 Pb-2 l0 t.6tE-02 4.10E-02 34489 - February 2007 A-7 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor White Mesa Uranium Mill Radon Emission Rates Colorado Plateau ore Arizona Strip ore Area (m')17000 17000 Contaminant Concentration (pCr/gRa-226) 700 1783 Specific Radon Flux Factor (pCi Rn-222 lm2s)/(pCi/g Ra- 226) I I Radon Release (F): F: (Specific Radon Flux Factor (pCi Rn-2221m2s)/(pCi/g Ra-226))*(Contaminant Concentration (pCi/gRa-226))*(Area(m2)*(3.156x107s/yr)*(10-r2Ci/pci) (A-2-7) Using equation A.2-7, the radon release from storage of Colorado Plateau ore is approximately 375 Clyr. Similarly, the radon release from storage of Arizona Strip ore is approximately956 Cilyr. L.2-6 Tailings Ponds Radioactive Particulate E missio n Rates Colorado Plateau Ore Arizona Strip Ore Cell 2 and 3 Cell4A Cell2 and 3 Cell4A Area (acres)7.7 4 7.7 4 Contaminant Concentration (pCi/g U- 238r 42 42 107 107 Contaminant Concentration of all other isotopes (pCi/g) 700 700 I 783 I 783 Process Emission Factor, Ee,, (g/m'yr)"2t3 213 213 213 Activity Enrichment Ratio 2.5 2.5 2.5 2.5 Control Factor (%)"70 70 70 70 Notes: a) Assumes 94o/o rccovery. b) The process emission factor for the tailings ponds was derived in Section A. L c) The control factor of70%o is based on the assumption that an active watering program as well as crusting agents are used to minimize the erosion of the tailings by wind. The Emission Rate (S) for U-238 and its decay daughters are calculated as follows: 34489 - February 2007 A-8 SENES Consultants Limited Dose Assessment in Support of the License Renewal Application & Environmental Reportfor Wite Mesa Uranium Mill S: (Process Emission Factor (g/m2yr))x(Area (acres))*(4047 m2lacre)*(Contaminant Concentration (pCi/g)) *(Activity Enrichment Ratio)*(l-Control Factor)*(10-'' Ci/pci; (A.2-8) Using equation A.2-8, the U-238 Emission Rate from Tailings Cell2 and 3 from the processing of Colorado Plateau ore is approximately 2.098-04 Crlyr. The decay daughters (Th-230, Ra-226 and Pb-210) are emittedata rate of 3.48E-03 Cr/yr. The U-238 Emission Rate from Tailings Cell 44 from the processing of Colorado Plateau ore is approximately 1.09E-04 Cilyr. The decay daughters (Th-230, Ra-226 and Pb-210) are emitted at a rate of 1.81E-03 Crlyr. Similarly, the U-238 Emission Rate from the Tailings Cell 2 and 3 from the processing of Arizona Strip ore is approximately 5.328-04 Cr/yr. The decay daughters (Th-230, Ra-226 and Pb-2 1 0) are emitted at a rute of 8.87E-03 Cily . The U-23 8 Emission Rate from Tailings Cell 4A. from the processing of Arizona Strip ore is approximately 2.76E-04 Cilyr. The decay daughters (Th-230, Ra-226 and Pb-210) are emitted at a rate of 4.61E-03 Crlyr. Radon Emission Rates Colorado Plateau Ore Arizona Strip Ore Cell 2 and 3 Cell4A Cell 2 and 3 Cell4A Area (acres)I12.8 4 I12.8 4 Contaminant Concentration (pCi/m's)8. l7 24.2 8. 17 24.2 Radon Release (F): F: (Contaminant Concentration (pCi/m2s)*(Area (acres))*(4047 m2lacre)*(3.156x107 s/yr)*(10- '2 ci/pci; (A-2-9) Using equation A.2-9, the radon release from Tailings Cell 2 and 3 (combined) and Tailings Cell 4,A. is approximately 117.71 Cilyr and 12.36 Cilyr, respectively from the ore processing operations at the mill. 34489 - February 2007 A-9 SENES Consultants Limited 8/2008) Loren Morton - RE: Denison: Cell 48 Environmental Report - Problems with Figures Page 1 From: "Steve Landau" <slandau@denisonmines.com> To: "'Loren Morton"'<LMORTON@utah.gov>CC: "'David Frydenlund"'<dfrydenlund@denisonmines.com>, "'Dane Finerfrock"'...Date: 5114108 2:26 PMSubject: RE: Denison: Cell 48 Environmental Report - Problems with FiguresAttachments: FIGURE 4.1.pdf; Figure 12.pdf Loren, Please find attached the figures you have requested. Steven D. Landau Manager, Environmental Affairs Denison Mines (USA) Corp. 1050 17th Street, Suite 950 Denver, CO 80265 (303) 389-4132 (303) 389-4125 Fax ---Original Message--- From : Loren Morton [mailto:LMORTON@utah. gov] Sent: Tuesday, May 13, 2008 9:48 AM To: Steve Landau Cc: David Frydenlund; Dane Finerfrock; John Hultquist Subject: Denison: Cell 48 Environmental Report - Problems with Figures Steve, We got the extra copies of the 4l3il08 Cell 48 Environmental Report yesterday. After looking over the PDF files you sent, we found a couple of problems, that need to be fixed, as follows: 1 . Missing Figure 12 - there was no electronic copy provided for Figure 12 of the Environmental Report. 2. Unreadable Figure in Appendix B - on page 4-2 of the 4/08 Senes Consultants Ltd report there is a Figure 4.1, Site Locations - that is unreadable in the PDF format. Please provide the missing figure, and correct the unreadable one. lf it will help, you can email the revised files to me. Thanks, Loren 512812008) Loren Morton - Denison: Cell 48 Environmental Report - Problems with Figures in Electronic 1 From: Loren ModonTo: Steve LandauCC: Dane Finerfrock; David Frydenlund; John HultquistDate: Sll3lOB 9:48 AMSubject Denison: Cell 48 Environmental Report - Problems with Figures in Electronic Version Steve, We got the extra copies of the 4/30/08 Cell 48 Environmental Report yesterday. After looking over the PDF files you sent, we found a couple of problems, that need to be fixed, as follows: 1. Missing Figure 12 - there was no electronic copy provided for Figure 12 of the Environmental Report. 2. Unreadable Figure in Appendix B - on page 4-2 of the 4/08 Senes Consultants Ltd report there is a Figure 4,1, Site Locations - that is unreadable in the PDF format. Please provide the missing flgure, and correct the unreadable one. If it will help, you can email the revised files to me. Thanks, Loren