ML22308A254

Triso-X, LLC, License Application Chapter 1, Revision 2

ML22308A254
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Issue date:	11/04/2022
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TX0-LTR-0011_0 ENCLOSURE 2 ATTACHMENT 2 LICENSE APPLICATION CHAPTER 1 REVISION 2 NON-PROPRIETARY

Revision: 2

© Copyright 2022 by X Energy, LLC Release Date: 04-NOV-2022 Page i TRISO-X Fuel Fabrication Facility Special Nuclear Material License Application Revision

2 Status

Approved Project

Fuel NRC Docket No.

70-7027

Revision: 2

© Copyright 2022 by X Energy, LLC Release Date: 04-NOV-2022 Page ii SPECIAL NUCLEAR MATERIAL LICENSE CHAPTER INDEX CHAPTER TITLE REVISION REVISION DATE 1

General Information 2

11/4/2022 2

Organization and Administration 1

4/5/2022 3

Integrated Safety Analysis 1

4/5/2022 4

Radiation Safety 1

4/5/2022 5

Nuclear Criticality Safety 1

4/5/2022 6

Chemical Process Safety 1

4/5/2022 7

Fire Safety 1

4/5/2022 8

Emergency Management 1

4/5/2022 9

Environmental Safety 1

4/5/2022 10 Decommissioning 1

4/5/2022 11 Management Measures 1

4/5/2022 12 Material Control and Accounting of Special Nuclear Material 1

4/5/2022 13 Protection of Special Nuclear Material 1

4/5/2022 Addendum Sensitive Information 1

4/5/2022

Revision: 2

© Copyright 2022 by X Energy, LLC Release Date: 04-NOV-2022 Page iii RECORD OF REVISION Revision Date Section/Page Description of Change 1

5-Apr-22 ALL Initial issue.

2 4-Nov-22 N/A All changes for this revision are based on RSI responses (ML22286A144).

Section 1.1.1 Added geotechnical discussion of site regarding slope stability, soil liquefaction, differential settlement, bearing capacity, karst features, and site cross sections.

Section 1.1.2 Added design basis values for seismic, wind, precipitation, hydrological, and geological NPH.

Section 1.3 Separated special exemptions and special authorizations. Re-numbered subsections.

Section 1.3.1.1 Added detail for criticality monitoring exemption.

Figures 1-3 thru 1-8 Added new figures for site geological cross sections.

Revision: 2

© Copyright 2022 by X Energy, LLC Release Date: 04-NOV-2022 Page iv ABBREVIATIONS AND ACRONYMS This list contains the abbreviations and acronyms used in this document.

Abbreviation or Acronym Definition ALARA As Low As Reasonably Achievable ALI Annual Limit on Intake AHJ Authority Having Jurisdiction ANS American Nuclear Society ANSI American National Standards Institute ASCE American Society of Civil Engineers BDC Baseline Design Criteria BS/BA Bachelor of Science / Bachelor of Arts CAA Controlled Access Area CAAS Criticality Accident Alarm System CEDE Cumulative Effective Dose Equivalent CFR Code of Federal Regulations CM Configuration Management DAC Derived Air Concentration DFP Decommissioning Funding Plan DOE U.S. Department of Energy DOT U.S. Department of Transportation EPA U.S. Environmental Protection Agency ETSZ East Tennessee Seismic Zone FFF Fuel Fabrication Facility FHA Fire Hazards Analyses FNMCP Fundamental Nuclear Material Control Plan HALEU High Assay Low Enriched Uranium HPGe High Purity Germanium IAEA International Atomic Energy Agency IBC International Building Code ICPMS Inductively Coupled Plasma Mass Spectrometry ICRP International Commission on Radiation Protection Publication ISA Integrated Safety Analysis IROFS Items Relied On For Safety KPA Kinetic Phosphorescence Analyzer LA License Application LEU Low Enriched Uranium MBA Material Balance Area

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© Copyright 2022 by X Energy, LLC Release Date: 04-NOV-2022 Page v Abbreviation or Acronym Definition MC&A Material Control and Accountability MMI Modified Mercalli Intensity MOU Memorandum of Understanding NCRP National Commission on Radiation Protection NCS Nuclear Criticality Safety NFPA National Fire Protection Association NIST National Institute of Standards and Technology NMSS Nuclear Materials Safety and Safeguards NRC U.S. Nuclear Regulatory Commission OCA Owner Controlled Area OJT On-the-Job Training OSHA Occupational Safety and Health Administration PHA Process Hazard Analyses PM Preventive maintenance PSP Physical Security Plan QA Quality Assurance RCA Radiologically Controlled Area REM Roentgen Equivalent Man RPP Radiation Protection Program RSO Radiation Safety Officer RWP Radiation Work Permits SEP Site Emergency Plan SME Subject Matter Expert SNM Special Nuclear Material SRC Safety Review Committee TEDE Total Effective Dose Equivalent TRISO-X FFF TRISO-X Fuel Fabrication Facility U

Uranium U-235 Uranium-235 U-238 Uranium-238 UL Underwriters Laboratory USGS United States Geological Survey

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GENERALINFORMATION TableofContents

SECTION TITLE STARTS ONPAGE 1.1 1.1.1 1.1.1.1 1.1.1.2 1.1.1.3 1.1.1.4 1.1.2 1.1.3 1.1.4 FacilityandProcessInformation SiteDescriptionandLocation Population,NearbyLandUses,andTransportation Meteorology Hydrology Geology FacilityBuildingsandStructures GeneralProcessDescription RawMaterials,Products,ByProductsandWastes 12 1.2 1.2.1 1.2.2 1.2.3 1.2.4 1.2.5 1.2.6 1.2.7 InstitutionalInformation CorporateIdentity U.S.NuclearRegulatoryCommissionLicenseInformation FinancialQualifications Type,Quantity,andFormofLicensedMaterial AuthorizedUsesandActivities SiteSafeguards Terminology/Definitions 111 1.3 1.3.1 1.3.1.1 1.3.1.2 1.3.1.3 1.3.1.4 1.3.1.5 1.3.2 1.3.2.1 1.3.2.2 SpecialExemptionsandSpecialAuthorizations SpecialExemptions CriticalityMonitoring PostingandLabeling ICRP68DACandALIValues ICRP60OrganDoseWeightingFactors CertainUnplannedContaminationEvents SpecialAuthorizations ChangestotheLicenseApplication ReleaseforUnrestrictedUse 116

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GENERALINFORMATION

1.1 FacilityandProcessInformation

TheprimarypurposeoftheTRISOXFuelFabricationFacility(FFF)inOakRidge,Tennessee,isto manufacturecoatedparticlefuelforthenextgenerationofcommercialnuclearreactors.The modulardesignoftheprocesscells/areasanticipatesadditionalmanufacturingcapabilitiesto satisfytheneedsofavarietyoffueldesignsandreactors(e.g.,pebblebedhightemperaturegas cooled, prismatic gascooled, molten saltcooled, accident tolerant fuel, nuclear thermal propulsion,andothers).Nuclearmaterialsenrichedtolessthan20weightpercentU235are utilizedintheproductmanufacturingoperationsauthorizedbythislicense.

1.1.1 SiteDescriptionandLocation TheTRISOXsiteislocatedintheHorizonCenterIndustrialParkonpropertyabuttingportionsof RenovareBoulevard,withinthewesternlimitsoftheCityofOakRidgeandinthenortheastern portionofRoaneCounty,Tennessee.Thesiteissituatedinanareadedicatedandzonedfor industrialdevelopment,onanapproximately110acregreenfieldsite.Ofthetotalacreage, approximately 60 acres are designated for manufacturing and administrative buildings, equipmentyards,accessroads,parking,andstormwatermanagement.Thesiteissituatedat approximatelylatitudeN35°5741andlongitudeW84°2213.

ThesitelocationinnortheasternRoaneCountyisintheValleyandRidgephysiographicprovince.

The regional topography near the site is typical of the Valley and Ridge province which is characterized by northeast-southwest trending ridges and intervening valleys. The site and otherdevelopedareasalongStateRoute95(TN95-OakRidgeTurnpike)tothenortheastand southwestarelocatedonrelativelyflatorslightlyundulatingterrainassociatedwiththeEastFork PoplarCreekValley,whilejustnorthwestofthesite,thereisasteepinclinetothetopofBlack OakRidge.Severalotherridgesorientednortheasttosouthwestarepresentwithinthevicinity ofthesite.ThePoplarCreekValleyisthenextvalleynorthandparallelsBlackOakRidge.East ForkRidgeislocatedtothesouthandeastofthesiteandisinterruptedbythevalleyofBear CreekandTN95.PineRidgeislocatedsouthandeastofEastForkRidge.

1.1.1.1 Population,NearbyLandUses,andTransportation Asitelocationmap,includingthepopulationcenterslocatednearthesite,isshowninFigure1 1.TheclosestmajorpopulationcenteristheCityofOakRidgewhichhadapopulationof31,402 asofApril1,2020,pertheUnitedStatesCensusBureauwebsite.Theclosestresidentstothe sitearelocatedinaresidentialdevelopmentoffPoplarCreekRoad,approximately0.6miles northwestofthesiteboundary,separatedfromthesitebyBlackOakRidgeandareasofdense vegetation.TherearealsoresidentialneighborhoodslocatedtotheeastoffTN95,approximately 1.3milesormorefromthesite.TheNorthBoundaryGreenway,alowdensityrecreationaltrail usedforhikingandbiking,bordersthesiteboundarytothenorthwest.

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Theimmediateareasurroundingthesiteconsistsofruralwoodedareaandlightcommercialand industrialusebuildings.Theimmediatelyadjacentonestorywarehouse/officebuildinglocated near the southern corner of the property is the corporate office of Philotechnics Inc., a radiologicalserviceandmixedandradioactivewastebrokerageproviderlicensedbytheStateof Tennessee,doesnotmanage,utilize,orstorechemicals(hazardousmaterials)inquantitiesthat posehazardstotheTRISOXsite.RenovareBoulevard,whichbordersthesitetothesoutheast, isatwolanedividedroadwaythatprovidesaccesstothesiteandtootherparcelswithinthe HorizonCenterIndustrialPark.

Landsadjacenttotheindustrialparkarepredominantlyundevelopedandforested,consistingof largetractsofU.SDepartmentofEnergyOakRidgeReservationlandwhichborderthesitetothe northwestandsurroundtheindustrialparkinotherdirections,withtheexceptionoftheTN95 roadway corridor to the east. The existing land use within one mile of the site consists of primarily industrial development and woodlands. Within a fivemile radius of the site, approximately83percentofthelandisundeveloped(e.g.,forest,pasture,wetland)andthe remainderisdeveloped.Otherlanduseswithin5milesofthesiteincludeheavyindustrial,light industrial/manufacturing,commercial/officespace,agricultural,andresidential.TheMethodist MedicalCenterofOakRidgeisthenearesthospital,locatedapproximately9milesfromthesite.

TheclosestschooltothesiteisLindenElementarySchool,locatedapproximately5milesfrom thesite.

TransportationinfrastructurenearthesiteincludesRenovareBoulevard;TN95;twointerstate highways-Interstate40andInterstate75-severalTennesseestatehighways;andlocalroads.

TheMcGheeTysonAirport,whichservespublicandmilitaryneeds,islocated26milesfromOak Ridgebyroad.

1.1.1.2 Meteorology OakRidgeislocatedinthebroadTennesseeRivervalleybetweentheCumberlandMountains, whichlietothenorthwest,andtheGreatSmokyMountains,tothesoutheast.TheCumberland Mountainsmoderatethelocalclimatebyretardingtheflowofcoldairfromthenorthduring winter.Bothmountainrangesaregenerallyorientedinanortheastsouthwestdirection.The valleybetweenthemiscorrugatedbybrokenridgesapproximately300to500feethighand orientedparalleltothemainvalleyinanapproximatenortheastsouthwestdirection.

The climate of Oak Ridge is classified as humid subtropical. The subtropical designation indicatesthattheregionexperiencesawiderangeofseasonaltemperatures.Suchareasare typifiedbysignificanttemperaturedifferencesbetweensummerandwinter.Thenormalliquid equivalentannualprecipitationintheOakRidgeareais50.91inches,andtheaverageannual snowfall is 5.9 inches. The normal daily minimum temperature in January is 28.9 degrees Fahrenheit(°F)andthenormaldailymaximumtemperatureinJulyis88.4°F.

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Directdeflectionofthewindsbyterrainisadominantmechanismthatdrivesthewindsinthe TennesseeRivervalley.Thismechanismactsapproximately50-60percentofthetime,resulting inwindsthatblowindirectionsgenerallyalongtheapproximatenortheastsouthwestaxisofthe valley.Thedistributionofprevailingmonthlywinddirectionsisbimodal,withwindsfromthe northeast(50-60degrees),orfromthesouthwest(210-220degrees).Themeanannualwind speedis2.8milesperhour.

SeverestormconditionsareinfrequentintheOakRidgearea,duetotheareabeingsouthof mostblizzardconditions,andtoofarinlandtobeaffectedbyhurricaneactivity.Tornadoes generallyoccurmorefrequentlyinthewesternandmiddleportionsofTennessee;however, EasternTennesseeexperiencestornadooutbreaksofvaryingmagnitudesapproximatelyevery threetosixyears.Inafourcountyareaaroundthesitefortheperiod1950to2020,thehighest intensitytornadoeswereratedF3asaresultofstormsonFebruary21,1993.Duetothelow frequency of tornadoes in this region, no specific design criteria relative to tornadoes are requiredbytheInternationalBuildingCode.Lightningriskatthesitehasbeenaddressedthrough lightningprotectionsystemsasspecifiedintheFireHazardsAnalysisasdescribedinChapter7.

1.1.1.3 Hydrology Thesiteiscategorizedasupland;nowaterbodiesorwetlandswereidentifiedwithinthesite.

ThenearestwaterbodytothesiteisEastForkPoplarCreek,theclosestportionsofwhichrunin asouthwestdirectionthroughtheindustrialparkbetweenTN95andRenovareBoulevardatan approximateelevationoflessthan770feet.EastForkPoplarCreekemptiesintoPoplarCreek approximately1.25milessouthwestofthesite,andPoplarCreekemptiesintotheClinchRiver approximately3milessouthwestofthesiteboundary.

FederalEmergencyManagementAgencyFloodInsuranceRateMapNumber47145C0130F,Panel 0130F,RoaneCounty,Tennessee,andIncorporatedAreas,EffectiveDateSeptember28,2007, showsthesitetobeinanareaofminimalfloodhazard(ZoneX).Thenearestsectionofdetailed studyforEastForkPoplarCreekisapproximately1.5milesnortheastofthesite,witha100year basefloodelevationof783feetatthedownstreamendofmapping.TheclosestClinchRiver locationtothesitehasa100yearbasefloodelevationof747feetatthePoplarCreekoutlet.

The floor in the TRISOX FFF is located at an elevation of approximately 811 feet, and the elevationofRenovareBoulevardneartheprimaryentrancetothesiteisapproximately776feet.

Therefore,thefacilityfloorelevationrangesfrom28to64feetabovethemapped100yearbase floodelevationsofthenearestwaterbodiesasdescribedabove,andthefloorelevationismore than35feetaboveRenovareBoulevard.RenovareBoulevardissituatedatahigherelevation thanthelowerlyingunmappedportionsofEastForkPoplarCreekclosesttothesite.

Fourgroundwaterobservationwellswereinstalledonthesiteinfallof2021withtotaldepths andscreenedintervalsbasedonobservedfirstwateridentifiedintheuppermostbedrockduring drilling.Nowaterwasidentifiedintheshallowunconsolidatedsurficialsedimentsabovethe

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bedrock.Totalwelldepthsrangefromapproximately39feetto75feetbelowgroundsurface.

Theunderlyingbedrockinwhichtheobservationwellsarecompletedisprimarilycomprisedof dolomiteandisthefirsttypeofbedrockencounteredatallsites.

Depth to groundwater measurements taken at the four observation wells vary from approximately 10 to 57 feet below the top of the well casing. Groundwater elevation measurementsandmodelingindicatethatgroundwatergenerallyflowsinasouthwestdirection towardEastForkPoplarCreek.Therearenoknownhousehold,public,orindustrialusersof groundwaterdowngradientofthesite.

1.1.1.4 Geology TheTRISOXsiteislocatedwithintheValleyandRidgeProvince,along,narrowbelttrending northeasttosouthwestthatisborderedonthewestbytheAppalachianPlateauandontheeast bytheBlueRidgeProvince.TheprovinceisexpansiveandextendsfromVermonttoAlabama.

Thisphysiographicprovinceconsistsofaseriesofnortheast/southwesttrendingsynclinesand anticlinescomposedofEarlyPaleozoicsedimentaryrocks.DrainagepatternsintheValleyand Ridge Province generally follow the northeastsouthwest trend of topography. However, segments of major rivers cut across the regional topographic alignment following deeply entrenched,ancientstreamcourses.TheseincludethePowell,Clinch,Holston,andFrenchBroad riversthatjointoformtheTennesseeRiverafterflowingmanymilesinnortheast/southwest trendingvalleys.

The Rome Formation and the Conasauga, Knox, and Chickamauga Groups and associated formationscomprisethemajorityoftheunderlyingbedrockoftheValleyandRidgeProvince.

ThesiteisunderlainbylimestonesdolomitesoftheKnoxGroupandlimestoneswithinterbedded shale, argillaceous limestone, mudstone, and wackestone associated with the Chickamauga Group.

SiteTopography TheterrainwithintheHorizonCenterSite(HCS)boundariesistypicaloftheOakRidgeregionand generallycontainsmildrollinghillswithridgesandvalleys.Theexistingsitesurfaceelevations varyfromapproximatelyElevation780feettoElevation825feetinmostpartsoftheHCS,except atthenorthcornerwheretheexistingsurfaceelevationrisestoapproximately850feet.More detailedtopographydescriptionsareincludedinSection3.3oftheEnvironmentalReport(ER).

The site development for the project will include extensive site grading with cut and fill.

Engineeredfillwillbeusedforplacementandcompaction.Thefinalsitegradewillberelatively levelacrossthesitewithmostboundariesmatchingtheexistingsurroundingtopography.The onlysignificantslopeforthesiteisonthenorthsideofthefacility,separatedfromtheprimary facilitystructuresandequipmentbyaperimeteraccessroad.Thisslopewillbedesignedwitha gradeofapproximately3:1(Horizontal:Vertical)afterexcavation.Thedesignwillbeverifiedby aslopestabilitycalculationanddesignedusingstandardgeotechnicalengineeringpractice.The

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toeofthenorthslopeisexpectedtobeatleast150feetto200feetfromtheedgeoftheprocess building(PB).

SiteGeotechnicalInvestigations SitespecificgeotechnicalinvestigationspresentedintheEnvironmentalReport,Section3.3.3.2, indicatetheoverallsubsurfaceprofileconsistsofclaysoilsunderlainbyweatheredlimestone anddolomitetomorecompetentbedrockatgreaterdepths.Theclayoverburdenisclassifiedas CHorCLperUSCS(unifiedsoilclassificationsystem)andisconsideredtohavenegligiblepotential ofliquefaction.Theinsitumediumstifftoverystifforhardclaysarenotsusceptibletostrength degradationduringseismicevents.

Based on the drilling logs from the construction of groundwater monitoring wells (GW1 to GW6),theoverburdensoilthicknessvariesfrom7feetto50feet.Thesoilthicknessof50feet wasencounteredatGW1withthesurfaceelevationat841.55feet,whichwaslocatedonthe hillatthenorthcornerofthepropertyboundary.However,thegroundwatermonitoringwells arelocatedawayfromthemainfacilitiesnearthepropertyboundaries.Detailedinformation about groundwater monitoring wells can be found in Section 3.4.1.2 of the Environmental Report.

BasedonthesoilboringlogswithinthefootprintoftheHCS,theoverburdenconsistsofresidual claysoilsencounteredatdepthsrangingfrom3.6feetto31.5feetbelowtheexistingground surfaceatboringlocations.Thesoiloverburdenbecomesdeeperatlocationsclosertothenorth andnorthwestboundariesonthehillside.

PotentialforDifferentialSettlement Aftersitegradingcutandfilltoestablishthefinalgrade,theoverburdensoilthicknessbelowthe finalgradeisexpectedtovarygenerallyfromlessthan5feettoapproximately25feetwithinthe footprintoftheprocessbuilding(PB).ThemajorityofthePBarea,alowlyingareainthemiddle ofthesite,willreceivefill.Potentialsettlementinthisareawillbemitigatedwiththefollowing measures.

TheentirePBisdesignedtorestonalargematfoundationtoreducethepotentialfordifferential settlement.Furthermore,ageotechnicalgroundimprovementapproachusinganintermediate foundationsystemisdesignedtofurtherminimizethepotentialfordifferentialsettlementfrom theunderlyingclaysoils.Thisintermediatefoundationtypeiscalledarigidinclusion(RI)system, whichprimarilyconsistsofcementgroutcolumnsbeinginstalleddowntothetopofbedrock acrosstheentirePBareainagridpattern.TheRIelementsaresimilartoapilefoundation, without steel reinforcement. Typically, between the foundation mat and the top of the RI elementsthereisalayerofcompactedgranularsoilcalledtheloadtransferplatform(LTP).The LTP,RIelements,andtheinsitusoilsactasacompositematrixsystemwithoverallimproved engineeringpropertiestomitigatedifferentialsettlements.Thelargematfoundationsupported

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bytheRImatrixsystemwillminimizethepotentiallongtermdifferentialsettlementofthePB andensurethesafeoperationoftheproposedfacility.

SubsurfaceBearingCapacity Thesubsurfacemediumstifftoverystiffclaysoilsdiscoveredbythesitespecificgeotechnical investigationsexhibitadequatebearingcapacityforthePBwithstandardfactorofsafetyagainst general soil failure based on the preliminary analysis. The primary design concern was the potentialfordifferentialsettlementproducedbytheunderlyingclaysoils.Asdiscussedabove, thelargematfoundationsupportedbytheRImatrixsystemwillminimizethepotentialforlong termdifferentialsettlementofthePBandensurethesafeoperationoftheproposedfacility.

WiththeuseoftheRImatrixsystem,theoverallfoundationbearingcapacitywillbeimprovedas well. Detailed information about geology and soils can be found in Section 3.3 of the EnvironmentalReport.

PotentialforKarstFeatures AccordingtotheUnitedStatesGeologicalSurvey(USGS),theregioncontainingthesitemay containcarbonaterocksthatcanbecomekarstified.Thesefoldedandfaultedcarbonaterocks arePaleozoicinageandaresubjecttodissolutionthatmayproducearangeoffeaturesthat includesolution,collapse,covercollapsesinkholesandcaves.Karstfeaturespreviouslyreported onlandsadjacenttothesitehaveincludedspringsandsinkholesofvarioussizes.Basedonthe topography of the site, several shallow draws and depressions exist which may reveal karst featuresbeneaththesurface.Karstfeaturesarecausedbydissolutionofcarbonaterocksand deepweatheringalongprevailingfracturesandstrikeorientedbedding,creatingconduitsand voids (open and/or clayfilled). Voids within the dolomite and limestone bedrock were encountered on the site during the geotechnical drilling program to support facility design.

Bedrockwasencounteredduringdrillingataminimumdepthof3.6feetandamaximumdepth of50.0feet.

Inearly2022,asubsurfaceinvestigationwasperformedtosupportthefacilitydesign,which involved 22 geotechnical soil borings and a surface geophysical investigation. There were 6 boringslocatedwithinthePBfootprintwithtotalboringdepthsrangingfrom30feetto100feet belowgroundsurface(b.g.s.)androckcoretotallengthsrangingfrom22feetto100feet.Voids wereencounteredduringrockcoringinmostboringswithinthePBfootprintwiththevertical dimensionsfromasthinas0.2feettoapproximately2.6feet.The2.6feetopeningwasat82feet deepb.g.s.atonecornerofthePB,whilethemajorityofvoidswerefilledwithstiffclayand encounteredwithintheupper25feetb.g.s.

The surface geophysical investigation performed shear wave seismic refraction tomography (SWSRT)andelectricalresistivitytomography(ERT)tomapthesubsurfacebedrockconditions, includingpossiblemajorvoid(emptyorsoilfilled)anomaliesthatmaybeassociatedwithkarst features.Thetomographysurveylineswereover700feetlongeachandspacedat50feetto

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covertheentirePBarea.Thegeophysicalfindingsindicatedthesamegeneralsubsurfaceprofiles asdiscoveredbysoilborings,whichcontainedshallowresidualstiffoverburdenunderlainby weatheredbedrockwithhigherweatheringatupperrockformationandveryhardcompetent rockatgreaterdepths.ThegeophysicalreportalsoidentifiedsomeanomalieswheretheERT resultsshowedhighresistivityatdeepzonescomparedtothesurroundingrockdata,although theshearwavevelocityatthosedeepzonesdidnotshowabnormalresults.

FurthersoilboringinvestigationswereperformedinJune2022tofocusontheanomalylocations identifiedinthegeophysicalworkandincluded6boringsinthePBfootprint.Rockcoringof60 feet to 80 feet were performed to reach those anomaly zones as identified by geophysical investigationand20feetto30feetbeyond(deeper)theanomalylocations.Theseadditionalrock coringsamplesdidnotfindanysignificantvoidsatthoseanomalies.Detailedinformationabout geologyandsoilscanbefoundinSection3.3,andkarstisdiscussedin3.3.2,oftheEnvironmental Report.

SubsurfaceEngineeringCharacteristics ThesoillayeroverbedrockgenerallyconsistsofmediumstifftoverystiffCHandCLclayatdepths rangingfrom3.6feetto18feetbelowtheexistinggroundsurfacewithinthePBfootprint.Ata boringlocationtothesouthofthePB,theclaywasencounteredtoadepthof27feetb.g.s.Based onthe12geotechnicalboringsperformedinthePB/ABarea,thelimestoneanddolomitebedrock exhibithigherweatheringatshallowerdepth(generallyupper10feetto20feet)andbecame morecompetentatgreaterdepths.Therockcorerecoveryrangesfromapproximately24%to 100%whileRockQualityDesignation(RQD)rangesfrom0to100%.ThelowerrecoveryandRQD weremostlywithintheupperrocklayers.Theunconfinedcompressivestrengthvaluesofintact rockcoresrangefrom4,500psito19,500psi,whichindicateshardtoveryhardstrength.

Thecrosssectionsofsubsurfacesoil/rockprofilesareprovidedinFigures13through18.

Seismicity TheEastTennesseeSeismicZone(ETSZ)isthesecondmostactivezoneintheeasternUnited Statesintermsofsmallmagnitude(M<5)seismicity,secondinfrequencytotheNewMadrid seismiczone.ActivityintheETSZhasremainedhighforseveraldecadeswithonlyafewevents havingmagnitudesaslargeasM4.6.Generally,earthquakesintheETSZproduceminororno damage: the largest observed earthquakes have produced only minor damage to buildings, typicallychimneycollapse,cracksinplaster,andbrokenwindows,consistentwithintensityVIon theModifiedMercalliIntensity(MMI)scale.

1.1.2 FacilityBuildingsandStructures AsiteplanshowingthelocationandarrangementofbuildingsisincludedasFigure12.Security fencingalongornearthepropertyboundariesdefinestheOwnerControlledArea.Thesite includes4buildingsfornuclearmanufacturing,administrativeoffices,rawmaterialpreparation, andsecurity.

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Thebuildingcodeofrecordforthebuildingsonthesiteisthe2018EditionoftheInternational BuildingCode.Thetypeofconstructionisclassifiedasnoncombustible.Allhandling,processing, andstorageoflicensedmaterialoccursinthenuclearmanufacturingbuilding,whichissizedfor twoprocesslines,eachincludingsimilarprocessstepsasoutlinedinSection1.1.3.

SeismicLoad:Thedesignofthestructuresandfacilitiescomplieswithseismicloadingsbasedon the2018EditionoftheInternationalBuildingCodeandAmericanSocietyofCivilEngineers(ASCE) 716, Minimum Design Loads and Associated Criteria for Buildings and Other Structures, as appropriateforthegeographiclocationofthesite.

TheASCE7designbasisearthquakeissetat2/3ofthesiteclassadjustedMaximumConsidered Earthquake(MCER)accelerationsinaccordancewithSection11.4.5ofASCE716:

SDS(Design,5%damped,spectralresponseacceleration,shortperiods)=2/3*SMS=0.432 SD1(Design,5%damped,spectralresponseacceleration,1speriods)=2/3*SM1=0.122

TheSeismicDesignCategory(SDC)isdeterminedinaccordancewithSection11.6ofASCE716 asafunctionofthestructuresRiskCategoryandthemagnitudeofthedesignspectralresponse accelerationparametersstatedabove.TheSDCfortheTRISOXFFFProcessBuildingisC.The equivalentlateralforce(ELF)seismicanalysisprocedureisusedaspermittedbySection12.6of ASCE716.TheELFproceduredetailedinSection12.8ofASCE716takesintoconsiderationthe dynamicpropertiesofthestructurealongwiththeseismicImportanceFactor(1.25forRisk CategoryIII)structurestodeterminetheseismicresponsecoefficient(Cs)andultimatelythe seismicforcesonthestructure.

WindLoad:Thebasic(general)windspeedof112MPHisbasedupona1,700yrreturnperiod forRiskCategoryIIIstructuresperASCE716CommentarySectionC26.5.1.Fortornadowind loads,thedesignwindpressuresforanEF1(110MPH)tornadoutilizingthemethoddetailedin ASCE 716 Commentary Section 26.14.4 exceed those for the general wind speeds.

Conservatively, the higher pressures determined for tornado winds are utilized in the load combinationsintendedforgeneralwindloads.

SnowLoad:Thegroundsnowloadof10psfisdictatedbyASCE716andusedinconjunction withequationsinCh.7ofASCE716todeterminetheloadsonthestructure.PerASCE716 CommentarySectionC7.2,thegroundsnowloadmapsweredevelopedbytheCorpofEngineers, ColdRegionResearchandEngineeringLaboratory(CRREL)toestimatesnowloadswitha2%

annualprobabilityofbeingexceeded(50yrMeanRecurrenceIntervalorMRI).Furtherdetailis providedintheaforementionedcommentarysection.NotealsothattheSnowImportanceFactor foraRiskCategoryIIIstructureis1.10whichincreasestheflatroomsnowloadby10%fromwhat wouldbecalculatedforacommonRiskCategoryIIstructure.

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RainLoad:Rainloadsareassumedtobeboundedbysnoworliveloads,pendingthefinalized designoftheroofdrainagesystem.Thisassumptionwillbeevaluatedoncetheroofdrainage detailsarefinalizedandiftheassumptionturnsouttobeinvalid,rainloadswillbeexplicitly considered.Chapter8.3ofASCE716requiresthateachportionofaroofshallbedesignedto sustaintheloadofallrainwaterthatwillaccumulateonitiftheprimarydrainagesystemforthat portionisblockedplustheuniformloadcausebythewaterthatrisesabovetheinletofthe secondarydrainagesystematitsdesignflow.

IceLoad:TheProcessBuildingdoesnotmeetthedefinitionofanicesensitivestructureas giveninSection10.2ofASCE716whichiswhyatmosphericicingloadsandwindoniceloads arenotexplicitlyevaluatedasaloadcase.

Hydrologicaland/orGeologicalLoad:Therearenoadditionalhydrologicalloadsthatapplyto thestructuredesignotherthansnow,ice,andrain.Therearenofloodingloadsonthestructure andthefoundationsareabovethegroundwatertable.

1.1.3 GeneralProcessDescription TRISOX FFF manufacturing operations consist of receiving high assay low enriched uranium (HALEU)intheformofuraniumoxidepowderenrichedtolessthan20weightpercentU235; convertingtheoxideintoauranylnitratesolution,intogelspheres,andthenintofuelkernels; and processing the fuel kernels through coating, overcoating, fuel form pressing, and carbonization.Coatedparticlesand/orfinalfuelformsareremovedfromtheprocessatthe appropriatepointandloadedintolicensedshippingcontainersforshipmenttootherlicensed facilities.Theseoperationsaresupportedbyshippingandreceiving,laboratory,qualitycontrol, research and development, uranium and chemical recovery, and waste disposal processes.

DetailedfacilityandprocessdescriptionsareprovidedintheTRISOXFuelFabricationFacility IntegratedSafetyAnalysisSummary.

1.1.4 RawMaterials,Products,ByProductsandWastes

1. ThefeedmaterialfortheTRISOXFFFisuraniumoxidepowder.Themanufacturing, recovery,support,andwastepackagingactivitiesaresupportedbyanumberofnon radiologicalchemicalmaterialsstoredinbulkquantities,aslistedintheNRCrequired EmergencyPlanandISASummary.

2. Finished products containing licensed material include coated particles and final fuel formsinvariousshapesandconfigurations.

3. There are no byproducts as defined by 10 Code of Federal Regulations (CFR) 30.4 extractedorconvertedafterextractionfromtheTRISOXFFFforuseinacommercial, medical,orresearchactivity.

4. Uraniumisrecoveredfromnonconformingproductmaterials,processsolutions,and scrapmaterialsbyprocessingitintoaformthatissuitableforuseasfeedstockinthe manufacturingprocess.

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5. Process solutions contaminated with uranium that cannot be recovered/recycled are identified as liquid wastes. Liquid wastes are collected and sampled to determine appropriatehandling/treatmentsteps.TreatmenttypicallyinvolvesadjustmentofpH, filtering,ionexchange,and/orprecipitation.Precipitatesaredewatered,andthesolids are packaged for offsite disposal. If needed, liquid wastes that have been handled/treatedcanbesampledanddischargedthroughaninlinemonitortoshipping packages or conveyances for offsite disposal. Used oils may also be sampled and containerizedforshipmenttoalicenseddisposalfacility.

6. Airborneeffluentsaredischargedtotheatmosphereviaanumberofprocessstacks.

HEPA filtration and dry scrubber systems are used as needed to remove radioactive particulatesandchemicalsfromairborneeffluentstoassurecompliancewith10CFR20 andapplicableStateofTennesseeregulationspriortodischargetotheatmosphere.

7. SanitarywastesaredischargedthroughpipingwhichgoestotheCityofOakRidgepublicly ownedtreatmentworks.Theinputsforthesanitarysewersystemfromthesiteinclude bathroomsandshowers.

8. Solid waste materials include, but are not limited to, damaged and/or obsolete equipment,usedventilationfiltersandpersonalprotectiveequipment,processingand wastetreatmentresidues,andmiscellaneouscombustiblewastes.Materialscouldbe radiologically contaminated, noncontaminated, hazardous, or mixed (hazardous and radioactive). Solid waste materials are processed, recycled, and/or containerized for shipmenttoalicenseddisposalfacility.

1.2 InstitutionalInformation

1.2.1 CorporateIdentity ThisapplicationisfiledbyTRISOX,LLC,aDelawarelimitedliabilitycompany,headquarteredat 801ThompsonAvenue,Rockville,Maryland.TRISOX,LLCisawhollyownedsubsidiaryofX Energy,LLC,aMarylandlimitedliabilitycompany.TRISOX,LLCisaprivatelyheldcompanyand is not owned or controlled by a foreign corporation or government. The principal place of businessandlocationofthelicensedfacilityisasfollows:

TRISOXFuelFabricationFacility (specificstreetaddresstobeassignedbyU.S.PostOffice/CityofOakRidge)

OakRidge,Tennessee37830

1.2.2 U.S.NuclearRegulatoryCommissionLicenseInformation

1. DocketNumber:707027

2. LicenseNumber:TBD

3. PeriodofLicense:40years

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1.2.3 FinancialQualifications AsummaryoffinancialqualificationsthatdemonstratesthefinancialcapabilityofTRISOX,LLC toconstructandoperatetheTRISOXFFFhasbeensubmittedseparatelyforNRCreview.The financialarrangementstoassurethatdecommissioningfundswillbeavailablearesetforthin Chapter10.

1.2.4 Type,Quantity,andFormofLicensedMaterial The following types, maximum quantities, and forms of special nuclear materials (SNM) are authorizedunder10CFR70,30and40.

1. [

]SRIkilogramsofU235containedinuraniumenrichedtolessthan20%,inany chemical/physicalform.Contaminantsmayinclude107gramsoftransuranicmaterials pergramofuranium,and600Becquerelsoffissionproductspergramofuranium.

2. 350 grams of U235 in any chemical/physical form and at any enrichment for use in measurement and detection instruments, check sources, and instrument response standards.

3. 350 grams of U235 in any chemical/physical form and at any enrichment for use in researchanddevelopmentstudies.

4. 25 millicuries of plutonium as counting and calibration standards and/or for use in researchanddevelopmentstudies.

5. 300 millicuries of Cs137 as sealed radioactive sources for use in measurement and detectioninstruments,checksources,instrumentresponsestandards,andcountingand calibrationstandards.

6. 2millicuriesofanylicensedmaterialbetweenatomicnumbers3and83assealedand unsealedradioactivesourcesforuseinmeasurementanddetectioninstruments,check sources,instrumentresponsestandards,andcountingandcalibrationstandards.

7. 1microcurieofanylicensedmaterialbetweenatomicnumbers84and95assealedand unsealedradioactivesourcesforuseinmeasurementanddetectioninstruments,check sources,instrumentresponsestandards,andcountingandcalibrationstandards.

1.2.5 AuthorizedUsesandActivities ThislicenseauthorizestheuseofSNMforoperationsinvolvingenricheduraniumpursuantto10 CFRPart70aslistedinthissection.Thisalsoincludesthesupportactivitiesrelatedtothe manufactureofSNMcontainingproducts.

1. ManufacturingOperations

a. FuelManufacturing-Conversionofuraniumoxidestouranylnitratesolutions, andfabricationofcoatedparticlesandfinalfuelformscontaininguranium.

b. UraniumRecovery-recycling/recoveryofSNMfromprocessscrapmaterials.

2. LaboratoryOperations

a. Chemical,instrumental,andphysicalanalysesandtestingonmaterialconsisting ofand/orcontainingSNM.

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b. Preparationofanyrequiredsamplesorstandards.

3. Research and Development Operations - Process, product, and other research and development activities using natural, source, and SNM compounds and mixtures in benchtop,laboratoryscale,and/orfullscaleprototypeequipmentenvironmentsrelated to:

a. Enricheduraniumfueldesigns.

b. Manufacturingandprocessingtechnologyandequipment.

c. Recycling/recovery.

4. WasteOperations

a. Volumereduction,treatment,packaging,andstorageofliquidandsolidwastes contaminatedwithorcontainingnonrecoverableuranium.

b. Treatment,packaging,andstorageofhazardousormixedwaste.

c. Shipmentofwastestolicensedfacilitiesfordisposal.

5. SupportOperations

a. Receipt,handling,andstorageofrawmaterials.

b. Storageoflicensedmaterialcompoundsandmixturesinareaswithcontainers arrangedspecificallyformaintenanceofradiologicalandnuclearsafety.

c. Storage of finished fuel products and the preparation of these products for transportationoffsite.

d. Decontaminationofequipmentandmaterials.

e. Maintenance,repair,calibration,and/ortestingofSNMprocessingequipment, instruments,auxiliarysystems,contaminatedequipment,andfacilities.

1.2.6 SiteSafeguards PhysicalsecurityattheTRISOXFFFisdescribedintheNRCapprovedTRISOXFuelFabrication Facility Physical Security Plan, and nuclear material control and accountability (MC&A) is describedintheNRCapprovedTRISOXFuelFabricationFacilityFundamentalNuclearMaterial ControlPlan.Bothplansaremaintainedcurrentinaccordancewithapplicableregulationsas outlinedinChapters12and13.Theseplansdetailthemeasuresemployedatthefacilitytodetect potential loss of, and mitigate the opportunity for theft of, SNM of Moderate Strategic Significance, in accordance with the applicable requirements of 10 CFR 73 and 10 CFR 74.

SafeguardsInformationiscontrolledasdescribedintheTRISOXFacilitySafeguardsInformation Plan.

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1.2.7 Terminology/Definitions Definitionsfortermsspecifictoaparticularsafetyfunctionmaybegiveninthecorresponding chapteronthatfunction.Thefollowingdefinitionsapplytotermsusedinthislicense:

Term Definition U235Enrichments Low enriched uranium, which is also known as high assay low enricheduranium(HALEU),isdefinedasanycompoundofuraniumin whichtheenrichmentintheisotopeofuranium235islessthan20 percentbyweight.

NuclearSafety Nuclearcriticalitysafety Will,Shall Arequirement.

Should Arecommendation.

May Permission(optional),neitherarequirementnorarecommendation.

Are Anexistingpracticeforwhichthereisarequirementtocontinue.

Frequencies Whenaudit,measurement,surveillance,and/orotherfrequenciesare specifiedinlicensedocumentsandapprovedprocedures,thefollowing timespansapply:

Monthly-anintervalnottoexceed40days Quarterly-anintervalnottoexceed4months SemiAnnually-anintervalnottoexceed7months Annually-anintervalnottoexceed15months Biennially-anintervalnottoexceed30months Triennially-anintervalnottoexceed45months Fortimespansnotcoveredabove,anextensionof0.25times theintervalwillapply.

CriticalityControlor CriticalitySafety Control Theadministrativeandtechnicalrequirementsestablishedtominimize theprobabilityofachievinginadvertentcriticalityintheenvironment analyzed.

WorkAreaAir Samplers Stationaryairsamplersdemonstratedtoberepresentativeofworkers breathingair.Ifstationaryairsamplershavenotbeendemonstrated toberepresentative,theresultsoflapelairsamplerswillconstitute workareaairsamplers.

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Term Definition Equivalent Experience For the purpose of meeting educational requirements described throughoutthelicense,two(2)yearsexperienceisconsideredtobe equivalenttoone(1)yearofpostsecondaryeducation.Forexample, eight(8)yearsofapplicableexperiencewillsatisfytherequirementfor aB.S.degree(4yearsofpostsecondaryeducation).

OwnerControlled Area Asiteareaboundedbyafencedesignedtoprovidephysicalsecurity, andwhichencompassestheControlledAccessArea.Theareacontains radioactivematerialprocessing,storage,andlaboratoryareas,aswell assupportfunctions.

RestrictedArea A site area in which individuals may be exposed to radiation or radioactive material at levels or concentrations in excess of that allowedforthegeneralpublic(seedefinitionin10CFR20.1003).This couldincludeanylocationonthesitewheretheTRISOXFFFislocated, depending upon activities conducted and the exposure potential as evaluatedbythesafetyfunction.

Radiologically ControlledArea Asiteareawhereuncontainedradioactivematerialispresent,suchthat contamination levels are likely to be encountered in excess of acceptablelevelsforunrestricteduse.Thistypeofarea,designatedfor contaminationcontrolpurposes,requiresvariouslevelsofprotective clothingandotherpersonnelprotectiveactions.Itcouldincludeany location within the Restricted Area, either on a permanent or temporarybasis.Thistermisanalogoustothe10CFR20.1003defined termcontrolledareaanarea,outsideofarestrictedarea,butinside thesiteboundary,accesstowhichcanbelimitedbythelicenseefor anyreason.

UncontrolledArea Asiteareawhereradioactivematerialsmaybehandledintheformof sealedsources,inpackagesorclosedcontainers,insmallamounts(air samples, bioassay samples, etc.), or not at all. This type of area is designatedforcontaminationcontrolpurposesandisnotlikelytohave contaminationatlevelsinexcessofthoseacceptableforunrestricted use.

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Term Definition ConditionsAdverse toSafety AsusedinSections2.2,2.5.1,and11.6,eventsthatcouldhavethe potential to impact the safety of licensed activities, including equipmentfailures,malfunctions,ordeficiencies;procedureproblems, errors, or omissions; improper installations; nonconformances with regulatoryrequirementsorcommitments;qualityrelatedissues;ora significant condition, such that if uncorrected, could have a serious effectonsafety.

1.3 SpecialExemptionsandSpecialAuthorizations

1.3.1 SpecialExemptions

1.3.1.1CriticalityMonitoring 10CFR70.24(a)requiresalicenseeauthorizedtopossessSNMinstatedamountstomaintainin eachareainwhichsuchlicensedSNMishandled,usedorstoredtoemployaCAASmeetingthe statedrequirements.

Notwithstandingtherequirementsof10CFR70.24(a),thelicenseeisgrantedanexemptionfrom criticalitymonitoringrequirementsforSNMstoredinauthorizedshippingcontainerscomplying withtherequirementsoftheCodeofFederalRegulations,Title10,Part71,andwhicharein isolatedarraysoronatransportvehicleandwhicharenomorereactivethanthatapprovedfor transport.

Therequirementsin10CFR71.55,GeneralRequirementsforFissileMaterialPackages,and10 CFR 71.59, Standards for Arrays of Fissile Material Packages, ensure that arrays will remain subcriticalundernormalconditionsandunderaccidentconditions.Theexemptiondoesnot affectthelevelofprotectionforeitherthehealthandsafetyofworkersandthepublicorforthe environment;nordoesitendangerlifeorpropertyorthecommondefenseandsecurity.

Under the provisions of 10 CFR 70.17, Specific Exemptions, the Commission may, upon application, grant exemptions from the requirements of 10 CFR 70 when the exemption is authorizedbylaw,willnotendangerlifeorpropertyorthecommondefenseandsecurityand areotherwiseintheinterestofthepublic.

The exemption is authorized by law because the Atomic Energy Act of 1954, as amended, containsnoprovisionsprohibitingalicenseefrombeingexemptedfromCAASmonitoringina givenareainwhichthereisnegligibleriskofcriticality.Grantingsuchanexemptionwillnot endangerlife,property,orthecommondefenseandsecurity.

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Grantingthisexemptionto10CFR70.24(a)isinthepublicinterestbecausehavingcriticality accidentalarmsinanareainwhichthereisanegligibleriskofcriticalitymaycauseunnecessary evacuationsandanemergencyresponsebasedonapotentialspuriousalarm.Spuriousalarms couldalsocauseunnecessaryrisktoindividualsduringanevacuationandprovideconfusing informationaboutthesafetyofthefacilitytothepublic.

1.3.1.2PostingandLabeling 10CFR20.1904(a)requiresalicenseetoensurethateachcontaineroflicensedmaterialbearsa durable, clearly visible label bearing the radiation symbol and the words: CAUTION, RADIOACTIVEMATERIALorDANGER,RADIOACTIVEMATERIAL.Thelabelmustalsoprovide sufficient information (such as the radionuclide(s) present, an estimate of the quantity of radioactivity,thedateforwhichtheactivityisestimated,radiationlevels,kindsofmaterials,and massenrichment)topermitindividualshandlingorusingthecontainers,orworkinginthevicinity ofthecontainers,totakeprecautionstoavoidorminimizeexposure.

Notwithstandingtherequirementsof10CFR20.1904(a),thelicenseeisgrantedanexemption fromaffixingalabeltoeachcontaineroflicensedmaterialwhenentrancesintoeachbuildingin whichradioactivematerialsarestored,used,orhandledarepostedwithasignstating"EVERY CONTAINERORVESSELWITHINTHISAREAMAYCONTAINRADIOACTIVEMATERIALS".

Theexemptionisauthorizedbylawbecausethereisnostatutoryprohibitionontheproposed postingofasinglesignindicatingthateverycontainerinthepostedareahasthepotentialfor internalcontamination.Toreduceunnecessaryregulatoryburden,theNRCissuedafinalrulein 2007 that, in part, modified 10 CFR 20.1905, Exemptions to Labeling Requirements, thereby exemptingcertaincontainersholdinglicensedmaterialfromthelabelingrequirementsof10CFR 20.1904ifcertainconditionsaremet.Althoughthe2007rulemakingonlyappliedtofacilities licensedunder10CFR50and10CFR52,Licenses,Certifications,andApprovalsforNuclearPower Plants,therationaleunderlyingtherulesupportstheexemptionrequest.ExemptingTRISOX fromthisrequirementreduceslicenseeadministrativeandinformationcollectionburdensbut servethesamehealthandsafetyfunctionsasthecurrentlabelingrequirements.Therefore,the exemptiondoesnotaffectthelevelofprotectionforeitherthehealthandsafetyofworkersand thepublicorfortheenvironment;nordoesitendangerlifeorpropertyorthecommondefense andsecurity.

1.3.1.3ICRP68DACandALIValues Derivedairconcentration(DAC)andtheannuallimitonintake(ALI)valuesbasedonthedose coefficientspublishedintheInternationalCommissiononRadiationProtectionPublication68 (ICRP68)maybeusedinlieuoftheDACandALIvaluesinAppendixBof10CFR20inaccordance withapprovedprocedures.SeeChapter4foradditionaldetails.

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TheICRP68guidancewaspromulgatedafterthe10CFR20,AppendixBcriteriawereestablished, and provides an updated and revised internal dosimetry model. Use of the ICRP68 models providemoreaccuratedoseestimatesthanthemodelsusedin10CFR20andallowsTRISOXto implement an appropriate level of internal exposure protection. In a Staff Requirements MemorandumdatedApril21,1999(SECY99077),theCommissionapprovedthestaffgranting exemptionsbasedontheprecedentsetbythedecisiontoauthorizetheuseofmodelsinICRP Publication68.

ThisexemptionisinaccordancewiththeAsLowAsisReasonablyAchievable(ALARA)principle, internationalstandardsonradiationprotection,anddoesnotconflictwithestablishedNRCdose limits.Nonewaccidentprecursorsarecreatedbythisexemptiontoallowmodificationtothe valuesusedtoassessinternaldose.Thereisnosignificantincreaseintherisktoworkersor membersofthepublicasaresultofthisexemption.Theactivitiesthatareauthorizedbythis exemptionareincompliancewithlawandwillnotendangerlifeorpropertyorthecommon defenseandsecurity.

1.3.1.4ICRP60OrganDoseWeightingFactors Tissue weighting factors listed in the International Commission on Radiation Protection Publication 60 (ICRP60) may be used in lieu of the organ dose weighting factors in 10 CFR 20.1003 for effective dose assessments listed in ICRP68 methodologies, in accordance with approvedprocedures.

TheICRP60guidancewaspromulgatedinthesameyearthat10CFR20organdoseweighting factorswereestablished.UseoftheICRP60modelsprovidemoreaccuratedoseestimatesthan themodelsusedin10CFR20andallowsTRISOXtoimplementanappropriatelevelofinternal exposureprotection.InaStaffRequirementsMemorandumdatedApril21,1999(SECY99077),

the Commission approved the staff granting exemptions based on the precedentset by the decisiontoauthorizetheuseofmodelsinICRPPublication68.

Theunderlyingpurposeof10CFRPart20istoensurethatoccupationalworkersandmembers ofthepublicareprotectedfromradiation;thattheirdoses,asaresultoflicensedactivities,are withinprescribedlimits;andthattheirdosesareALARA.

ThisexemptionisinaccordancewiththeALARAprinciple,internationalstandardsonradiation protection,anddoesnotconflictwithestablishedNRCdoselimits.Nonewaccidentprecursors arecreatedbythisexemptiontoallowmodificationtothevaluesusedtoassessinternaldose.

Thereisnosignificantincreaseintherisktoworkersormembersofthepublicasaresultofthis exemption.Theactivitiesthatareauthorizedbythisexemptionareincompliancewithlawand willnotendangerlifeorpropertyorthecommondefenseandsecurity.

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1.3.1.5CertainUnplannedContaminationEvents Notwithstandingtherequirementsof10CFR70.50(b)(1),thelicenseeisgrantedanexemption fromtherequirementtoreportunplannedcontaminationeventswhenthefollowingconditions aremet:

1. Theeventoccursinarestrictedareainabuildingwhichismaintainedinaccessibleto thepublicbymultipleaccesscontrols.

2. Theareawascontrolledforcontaminationbeforetheeventoccurred,thereleaseof radioactivematerialisundercontrol,andnocontaminationhasspreadoutsidethearea.

3. Radiationsafetypersonneltrainedincontaminationcontrolarereadilyavailable.

4. Equipmentandfacilitiesthatmaybeneededforcontaminationcontrolarereadily available.

5. Theotherwisereportableunplannedcontaminationeventisdocumentedinthe licenseesCorrectiveActionProgram.

Chapter4describestheradiationprotectionprogrammeasuresthatkeepworkerexposures ALARAthrough:(a)approvedradiationprotectionproceduresandradiationworkpermits;(b) theuseofventilationsystems,containmentsystems,andrespiratorstocontrolexposureto airborneradioactivematerial;(c)theuseofprotectiveclothingtopreventthespreadofsurface contamination;(d)theuseofsurveysandmonitoringprogramstodocumentcontamination levels and exposures to workers; and (e) identification of items relied on for safety and managementmeasurestomaintainthoseitemsavailableandreliable.

Inaddition,(f)accesstothesiteisrestrictedtoindividualsthathavecompletedsitespecific nuclearsafetytrainingrequirementsorindividualsthatareformallyescorted;(g)duringnormal operations,trainedandqualifiedradiationprotectionstaffingisprovidedandreadilyavailableto supportandrespondtoradiologicalconditions,andthestaffistrainedincontaminationcontrol proceduresandtechniquesrequiredforrespondingtoacontaminationeventwhenneeded;(h) appropriateradiationsurveysareperformedbyqualifiedpersonnelduringorafteranunplanned contaminationeventasnecessarytoassessradiologicalconditionsandprovidetheappropriate response,surveyresultsarecomparedtospecifiedactionguides,appropriateactionsaretaken when contamination levels in excess of action levels are found and the affected area is decontaminatedinasafeandtimelymanner,andsurveyrecordsforcontaminationeventsare documentedpursuantto10CFR20.2103andareavailableforreview.

Based on the limited scope of the exemption, and the access and contamination controls, training,radiationsurveysandotherALARAmeasuresdescribedintheapplication,grantingthe exemptionasstatedabovedoesnotendangerlifeorproperty.Theexemptiondoesnotalter reportingrequirementsforunplannedcontaminationeventsthroughotherNRCrequirements suchas10CFR20.2202,Notificationofincidents,and10CFR20.2203,Reportsofexposures, radiationlevelsandconcentrationsofradioactivematerialexceedingtheconstraintsorlimits.In addition,theexemptiondoesnotinvolveinformationoractivitiesthatcouldimpactthecommon defenseandsecurity.

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Granting this exemption request is otherwise in the public interest because it promotes regulatoryefficiency.Theexemptionrelievesthelicenseefromareportingrequirementfor unplannedcontaminationeventsthatdonotpresentarisktopublichealthandsafetygiventhe sitespecificconditionsandprogramsdescribedabove.Specifically,theexemptionrelievesthe licenseefromgeneratingreportsofcontaminationeventsincontrolledareaswheretherelease ofradioactivematerialisundercontrolandnocontaminationhasspreadoutsidethecontrolled area.Grantingtheexemptionallowsthelicenseetofocustheresourcesrequiredtofulfillthe reportingrequirementonotheractivities.Inaddition,itrelievestheNRCstafffromreceiving andprocessingreportswhichdonotpresentarisktopublichealthandsafety.

Therefore,theexemptiondoesnotaffectthelevelofprotectionforeitherthehealthandsafety ofworkersandthepublicorfortheenvironment;nordoesitendangerlifeorpropertyorthe commondefenseandsecurity.

1.3.2 SpecialAuthorizations

1.3.2.1ChangestotheLicenseApplication ChangesmaybemadetotheLicenseApplicationand/ortosupportingdocumentsreferencedin thelicensewithoutpriorNRCapprovalprovidedthatthefollowingconditionsaremet:

1. Thechangedoesnotdecreasethelevelofeffectivenessofthedesignbasisasdescribed intheLicenseApplication.

2. Thechangedoesnotresultinadeparturefromthemethodsofevaluationdescribedin theLicenseApplicationusedinestablishingthedesignbasis.

3. Thechangedoesnotresultinadegradationofsafety.

4. Thechangedoesnotaffectcompliancewithapplicableregulatoryrequirements.

5. Thechangedoesnotconflictwithanexistinglicensecondition.

6. Within30daysaftertheendofthecalendaryearinwhichthechangeisimplemented, thelicenseeshallsubmittherevisedchaptersoftheLicenseApplicationtotheDirector, NMSS,usinganappropriatemethodlistedin10CFR70.5(a),andacopytotheappropriate NRCRegionalOffice.

Thisauthorizationisconsistentwiththeprocessformakingchangesunder10CFR70.72,Facility ChangesandChangeProcess,andisfurthersupportedbySectionC5,OtherChanges,inNRC RegulatoryGuide3.74,GuidanceforFuelCycleFacilityChangeProcesses,January2012.

1.3.2.2ReleaseforUnrestrictedUse LimitsdevelopedbytheNRCasspecifiedinGuidelinesforDecontaminationofFacilitiesand EquipmentPriortoReleaseforUnrestrictedUseorTerminationofLicensesforByproduct,Source, orSpecialNuclearMaterial,U.S.NuclearRegulatoryCommission,April1993,maybeusedfor decontaminationandsurveyofsurfacesorpremisesandequipmentpriortoabandonmentor releaseforunrestricteduse.

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TheseguidelinesareincludedasaregulatoryacceptancecriterioninNUREG1520,Standard ReviewPlanfortheReviewofaLicenseApplicationforaFuelCycleFacility,asanacceptable methodofdemonstratingcompliancewiththeradiationsurveyandmonitoringrequirementsin 10CFRPart20.SeeChapter4foradditionaldetails.

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Figure11:SiteLocation

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Figure12:SitePlan

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Figure13:PlanViewofGeologicCrossSections

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Figure14:GeologicCrossSection1

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Figure15:GeologicCrossSection2

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Figure16:GeologicCrossSection3

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Figure17:GeologicCrossSection4

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Figure18:GeologicCrossSection5