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Boiling Water Reactor License Termination Plan - Chapter 6 - Compliance with the Radiological Criteria for License Termination, Rev. 0
	ML16200A093
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/27/2016
From:	; LaCrosseSolutions
To:	; Office of Nuclear Material Safety and Safeguards
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LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 6 COMPLIANCE WITH THE RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 TABLE OF O CONTE ENTS

6. Com mpliance withh the Radiollogical Criterria for Licennse Terminattion .................................... 6-1 6.1. Site Releasee Criteria ........................................................................................................... 6-1 6.2. General Sitee Description n .................................................................................................... 6-1 6.2.1. Site Geeology................................................................................................................ 6-1 6.2.2. Site Hy ydrogeology y ...................................................................................................... 6-2 6.2.3. Area Land Use ............................................................................................................ 6-2 6.2.44. Area Groundwater G Use ............................................................................................... 6-3 6.3. Basements, Structures and a Piping to o Remain aft fter License T Terminationn (End State)) .. 6-3 6.4. Future Land d Use Scenarrio and Averrage Membeer of the Crittical Group ......................... 6-6 6.5. Dose Model Overview ....................................................................................................... 6-7 6.5.1. Backfillled Basements.................................................................................................. 6-7 6.5.1.1. BFM M Insitu Sceenario ............................................................................................. 6-7 6.5.1.2. BFM M Excavatio on Scenario ....................

. ............................................................... 6-8 6.5.2. Soil .............................................................................................................................. 6-9 6.5.3. Buried Piping .............................................................................................................. 6-9 6.5.44. Existin ng Groundwaater ............................................................................................... 6-10 6.5.5. Remain ning Above Ground Builldings....................................................................... 6-10 6.5.6. Dose Summation S for fo Complian nce ............................................................................ 6-10 6.5.7. Alternaate Scenarioss ................................................................................................... 6-10 6.6. Mixture Fraactions for In nitial Suite Radionuclide R es .......................................................... 6-11 6.6.1. Potentiial Radionucclides of Con ncern and Iniitial Suite ............................................. 6-11 6.6.2. Mixture Fractions for f Initial Su uite Radionuuclides .................................................. 6-12 6.7. Soil Dose Assessment A and a DCGL .................................................................................... 6-13 6.7.1. Soil So ource Term ...................................................................................................... 6-13 6.7.2. Soil Ex xposure Path hways and Crritical Groupp ........................................................... 6-14 6.8. Soil DCGL Computatio on Model - RESRAD R v77.0 ........................................................ 6-14 6.8.1. Parameeter Selection n Process ..................................................................................... 6-14 6.8.2. RESRA AD Parameteer Selection for Uncertaiinty Analysiis ...................................... 6-15 6.8.3. Soil DC CGL Uncertainty Analyssis Results................................................................ 6-17 6.9. Soil Determ ministic Anallysis and Soiil DCGLs ................................................................. 6-18 6.10. Basementt Fill Concep ptual Model ................................................................................ 6-19 6.100.1. Sou urce Term ........................................................................................................ 6-20 6.10.1.1. Reeactor Buildiing ............................................................................................... 6-20 6.10.1.2. Waste W Treatment Building g ............................................................................... 6-20 6.10.1.3. Waste W Gas Tan nk Vault....................................................................................... 6-21 6.10.1.4. Reemaining Strructures ........................................................................................ 6-21 6-i

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 6.100.2. BFM M Exposuree Pathways .................................................................................... 6-22 6.11. BFM Insiitu Scenario..................................................................................................... 6-22 6.111.1. BFM M Insitu Gro oundwater ScenarioS .................................................................... 6-22 6.11.1.1. BF FM Insitugw Computation Model ................................................................... 6-24 6.11.1.2. BF FM Insitugw RESRAD Uncertainty U A Analysis for Initial Suitee .................... 6-24 6.11.1.3. BF FM Insitugw RESRAD Deterministic D c Analysis annd DSR Ressults .............. 6-26 6.11.1.4. BF FM Insitugw Dose Factorrs .............................................................................. 6-26 6.111.2. BFM M Insitu Driilling Spoils Scenario annd DF Calcuulation ............................... 6-33 6.12. BFM Exccavation Sceenario ............................................................................................ 6-33 6.13. Insignificcant Dose Co ontributors and a Radionuuclides of Cooncern ............................... 6-35 6.133.1. Rad dionuclides of o Concern and a Adjustedd Soil DCGL Ls and BFM M DFs ............ 6-36 6.14. Concentraations in Exccavated Fill Material .................................................................. 6-39 6.15. Alternate Land Use Scenario S Dosse .............................................................................. 6-39 6.16. BFM Elev vated Area Consideratio C ons ............................................................................ 6-41 6.17. Soil Areaa Factors .......................................................................................................... 6-42 6.18. Buried Piiping Dose Assessment A and a DCGL ............................................................... 6-43 6.188.1. Sou urce Term an nd Radionucclide Mixturee ........................................................... 6-43 6.188.2. Exp posure Scenaario and Crittical Group .............................................................. 6-43 6.188.3. Burried Piping Dose D Assessment ........................................................................ 6-44 6.188.4. Burried Pipe DC CGLs Initial Suite ....................................................................... 6-44 6.188.5. Burried Pipe Raadionuclides of Concern and Adjusteed DCGLs ........................ 6-45 6.19. Existing Groundwate G er Dose.......................................................................................... 6-47 6.20. Demonstrrating Comp pliance with Dose Criteriion ....................................................... 6-48 6.21. Referencees .................................................................................................................... 6-49 6-ii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF TABLE ES Table 6-1 1 Basemeents and Bellow Ground Structures too Remain inn LACBWR End Sttate Ground surface elev vation is 6399 feet AMSL L ......................................... 6-4 Table 6-2 2 Buried Piping to reemain in LAC CBWR End State ..................................................... 6-5 Table 6-3 3 Initial Suite S of Poteential Radion nuclides andd Mixture Frractions ............................ 6-12 Table 6-4 4 Determministic Valu ues selected for f Sensitivee Kd parameeters used inn to calculatte Soil DCGL Ls ............................................................................ 6-17 Table 6-5 5 Determministic param meter valuess selected forr non-sensitiive Kd parrameters for soil DCGL calculation c ............................................................... 6-18 Table 6-6 6 Soil DC CGL Uncertainty Resultt and Determ ministic Valuues selected for Non n-Nuclide Specific Param meter Distriibutions ................................................ 6-18 Table 6-7 7 LACBW WR Soil DC CGLs for Inittial Suite Raadionuclidess ....................................... 6-19 Table 6-8 8 Determministic Geom metry RESR RAD Parameeters used in the Uncerttainty Analy ysis for the five f BFM Inssitugw Configgurations.......................... 6-25 Table 6-9 9 Resultss of RESRAD D Uncertain nty Analysis for BFM Insitugw and Selecteed Determiniistic Parameeters .......................................................................... 6-27 Table 6-1 10 BFM In nsitugw Rx Building B abov ve 619: Unccertainty Anaalysis Resultts for Disstribution Co oefficients (K Kd) ........................................................................... 6-28 Table 6-1 11 BFM In nsitugw Rx Building B beloow 619 Unceertainty Anaalysis Resultts for Disstribution Co oefficients (K Kd) ........................................................................... 6-28 Table 6-1 12 BFM In nsitugw WTB B Uncertaintty Analysis R Results for Distrib bution Coeffi ficients (Kd)....................

. ............................................................. 6-29 Table 6-1 13 BFM In nsitugw WGT TV Uncertaiinty Analysiss Results forr Distrib bution Coeffi ficients (Kd)....................

. ............................................................. 6-29 Table 6-1 14 BFM In nsitugw Rem maining Strucctures Uncert rtainty Analyysis Results for Disstribution Co oefficients (K Kd) ........................................................................... 6-30 Table 6-1 15 BFM In nsitugw DSR Rs for Reacto or Building, W WTB, WGT TV, and Remain ning Structu ures ............................................................................................... 6-31 Table 6-1 16 BFM In nsitugw Dosee Factors ....................................................................................... 6-32 Table 6-1 17 BFM In nsitu Drilling Spoils Dosse Factors ................................................................ 6-34 Table 6-1 18 BFM Excavation E Dose D Factors ................................................................................ 6-35 Table 6-1 19 Soil DC CGLs for RO OC Adjusted d for Insignifficant Contrributor Dose Fraction F ........................................................................................................... 6-37 Table 6-2 20 Reactorr Building BFM B DFs forr ROC Adjuusted for Insiignificant Contribbutor Dose Fraction F ........................................................................................ 6-38 Table 6-2 21 WTB BFMB DFs for ROC Adju usted for Insiignificant Contribbutor Dose Fraction F ........................................................................................ 6-38 Table 6-2 22 WGTV V BFM DFs for f ROC Ad djusted for Innsignificant Contribbutor Dose Fraction F ........................................................................................ 6-38 6-iii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 6-2 23 Remain ning Structurres BFM DF Fs for ROC A Adjusted forr Insigniificant Contrributor Dosee Fraction.................................................................. 6-38 Table 6-2 24 ROC an nd Insignificcant Radionu uclide Mixtu ture Fractionns ...................................... 6-39 Table 6-2 25 Surfacee Soil Area Factors F ......................................................................................... 6-43 Table 6-2 26 RESRA AD Source Term T Parameeters for Burried Piping DCGL Calcculations ....... 6-45 Table 6-2 27 Buried Piping DCG GLs ............................................................................................... 6-46 Table 6-2 28 Buried Pipe DCGL Ls for ROCs Adjusted foor Insignificant Radionnuclide Fracttions ............................................................................................. 6-47 Table 6-2 29 Summeed Buried Piipe DCGLs for f ROCs addjusted for Insigniificant Radio onuclide Fraactions....................................................................... 6-47 Table 6-3 30 Ground dwater Expo osure Factorss................................................................................ 6-48 LIST OF O FIGURE RES Figure 6--1 Site Reegional Locaation .............................................................................................. 6-50 Figure 6--2 Site Ovverview............................................................................................................ 6-51 Figure 6--3 LACBW WR Building gs ................................................................................................. 6-52 Figure 6--4 LACBW WR End Staate ................................................................................................. 6-53 Figure 6--5 LACBW WR End Staate - Backfillled Structurees .......................................................... 6-54 Figure 6--6 LACBW WR End Staate - Backfilled Reactor Building Baasement Elevatiion View ......................................................................................................... 6-55 Figure 6--7 RESRA AD Parameteer Selection Flow Chart.............................................................. 6-56 ATTA ACHMENT TS 6-1 RES SRAD Inputt Parameters for LACBW WR Soil DCG GL Uncertaiinty Analysis................... 6-57 6-2 RES SRAD Inputt Parameters for LACBW WR BRM Unncertainty A Analysis ........................... 6-79 6-3 Dose Contribution Percentag ge for Initiall Suite Radioonuclides annd Determinaation of Agggregate Dosee Percentage from Insign nificant Dosee Contributoors ..................................66-103 6-iv

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF ACRONYM MS AND AB BBREVIAT TIONS AF Areaa Factor ALARA As Low L As Reaasonable Ach hievable AMCG Aveerage Membeer of the Critical Group AMSL Aboove Mean Seea Level ANL Argonne Nation nal Laboratorry BFM Baseement Fill Model M

BFM Inssitugw BFMM Insitu Gro oundwater BFM Inssituds BFMM Insitu Drillling Spoils bgs Beloow Ground Surface S

DCGL Deriived Concen ntration Guiddeline Levell DF Dosse Factor DPC Dairryland Poweer Cooperativ ve FRS Finaal Radiation Survey G-3 Gennoa-3 GW Groundwater HSA Histtorical Site Assessment A

HTD Hard d-to-Detect ISFSI Indeependent Speent Fuel Storrage Installaation LACBW WR La Crosse C Boilinng Water Reeactor LSE LACCBWR Site Enclosure LTP Liceense Termination Plan MARSA AME Mullti-Agency Radiation R Su urvey and Asssessment off Materials aand Equipmeent Mannual MARSSIIM Mullti-Agency Radiation R Su urvey and Sitte Investigation Manual MDA Minnimum Detecctable Activiity MDC Minnimal Detectable Concen ntration NRC Nucclear Regulattory Commission PRCC Parttial Rank Co orrelation Co oefficient RESRAD D RESSidual RADiioactive matterials ROC Raddionuclides ofo Concern TEDE Totaal Effective Dose D Equivaalent USACE U.S. Army Corp ps of Engineeers WGTV Wasste Gas Tank k Vault WTB Wasste Treatmen nt Building 6-v

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Page Intenttionally Left ft Blank 6-vi

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0

6. Complianc C ce with thee Radiolog gical Criteeria for Liccense Termination 6.1. Site Release Criteria The site release r criterria for the La Crosse Booiling Water Reactor (LA ACBWR) aree the radioloogical f unrestricted release specified in criteria for n Title 10, S Section 20.14402, of the Code of Feederal Regulatio ons (10 CFR R 20.1402):

Dose Criterion: TheT residual radioactivity y that is disttinguishable from backgrround radiattion resultts in a Total Effective Dose Equivaleent (TEDE) to an averagge member oof the criticaal groupp that does not n exceed 25 5 mrem/yr, including i thaat from grouundwater souurces of drinnking waterr; and As Lo ow As Reaso onably Achiievable (ALA ARA) Criterrion: The ressidual radioaactivity has bbeen reducced to levels that are ALARA.

Chapter 4 describes the method ds and resullts for demoonstrating coompliance w with the AL LARA Criterionn. This Chaapter describ bes the metthods for deemonstratingg compliancce with the Dose Criterionn.

6.2. General G Site Description n This secttion providees a general description of the geoloogy and hyddrogeology at the LACB BWR site. Lannd and grou undwater use in the vicinity of sitte are also described. A detailedd site descriptio on of site geology and a hydroggeology is provided inn Haley & Aldrich, Inc.,

Hydrogeological Invvestigation Report, R La Crosse Boiiling Water Reactor, D Dairyland P Power Cooperative, Genoa Wisconsin (1).

The LAC CBWR faciliity is located d 17 miles so outh of the C City of La C Crosse and a mile south oof the Village of o Genoa (po opulation ab bout 800) (seee Figure 6- 1). The neaarest commuunity (three m miles to the noorthwest) is Reno, R Minnesota, an unnincorporatedd hamlet of about 300 ppeople locateed on the west shore of th he Mississippi River. Th he nearest ccommunity iin Iowa is N New Albin (pop.

522), five miles soutthwest of thee plant. Vicctory, Wisconnsin, five m miles south of the plant oon the east shorre, is an unin ncorporated hamlet of about a 80 peoople. The LA ACBWR liceensed site arrea is shown in n Figure 6-2 2, with a more m detailed view of tthe facilitiess inside thee LACBWR R Site Enclosurre (LSE) fencce shown in Figure 6-3.

6.2.1. Site Geology y LACBW WR is located d on the east bank of the Mississippii River in thee Wisconsinn Driftless seection of the Central C Lowland Physio ographic Pro ovince. The local geoloogy of the site is geneerally described d as approximately 15 feeet of hydrau ulic fill overrlying 100 too 130 feet of glacial outtwash and fluviial deposits.. These unconsolidated deposits aree underlain by flat lyinng sandstonee and shales off the Dresh hbach Group p and by deense Precam mbrian crysttalline rockss encountered at approxim mately 650 feeet below thee ground surrface (bgs).

6-1

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The prim mary soil typees encounterred at the sitee are:

0 to 20 2 feet bgs. Hydraulic H Fiill - Fill sand ds are encouuntered from m approximattely 0 to 20 ffeet bgs and a described d as light broown to brow wn, fine to mmedium sandss with occasiional fine grravel, 20 to 30 feet bgs.. Brown to grey, g fine to medium m finee sands undeerlie the fill, with an average thickn ness of 7 to 28 feet, 30 to 100 feet bgs. Brown, fin ne to medium m sands thatt also have zzones of coarrse sand andd fine graveel below the finer sands, 100 to 115 feet bgs. Brown fiine to mediu um sand and fine to mediium gravels,,

115 to 135 feet bgs. Brown fiine to mediu um sand withh trace silt, ooccasional zoones of gravvel.

6.2.2. Site Hydrogeeology Regionallly, groundw water flows from f the bluff towards thhe Mississipppi River. Clloser to the river, it is likelly that the grroundwater flow f directio on turns doownstream aas groundwaater dischargges to the surfaace water. Groundwater G r elevation data from eeight onsitee wells agreees with reggional groundw water flow an nd also show ws seasonal variation v on uupward and downward ggradients thaat are influenceed by the river stage.

6.2.3. Area A Land Use U

The LAC CBWR faciliity is located d in the far western w portiion of Vernoon County onn the east baank of the Misssissippi Riveer. Althoug gh the site area a is 163.5 acres, it iis relativelyy isolated ass it is bounded by the Mississippi River to the west, w a rail line to thee east, U.S. Army Corpps of Engineerrs (USACE) property to the north, an nd a wildlifee and fish reffuge to the south.

The 163.5 acre site iss comprised of the follow wing:

the 1.5 acre LAC CBWR facilitty, the Genoa-3 G (G-3

3) coal-fired, 379 MWe electric e powwer station thhat was comppleted in 19669 and is owned and d operated by y Dairyland Power Coopperative (DP PC). The G-3 station is locateed to the souuth, adjacentt to LACBW WR, an areea south of G-3 G where th he LACBWR R Independeent Spent Fuuel Storage Innstallation (ISFS SI) is located d,

an appproximately y 36 acre areea surroundin ng the ISFSII containing the closed ccoal ash landdfill from past operatiions, the laand north of the LACBW WR plant was the site of the former G Genoa-1 (G--1) coal (andd later oil) fueled fu powerr plant (remo oved in 1989 9) which now w includes thhe site switchhyard and baarge wash hing area (an approximately 900 m2 coal c ash landdfill is also ppresent),

a parccel of land too the east off Highway 35 5, across froom LACBWR R.

The areaa of the Misssissippi Riveer adjacent to t the site iss used for reecreational ppurposes (booating and fresh h water fishiing) and com mmercial barrge and shipp traffic (e.g.. barges of ccoal are delivvered to the G-3 station loccated south of o the LACB BWR plant). There is a ppublic boat llanding on thhe 6-2

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 site, locaated approxim mately 4,000 0 feet south of o the plant. There is a pportion (Poool 9) of the U Upper Mississip ppi River Naational Wildllife & Fish Refuge R just ssouth of the site which hhas limited aaccess for huntin ng, fishing and a recreatio onal activitiees. Further soouth are pubblic land areas and the G Genoa National Fish Hatcheery.

Lock and d Dam No. 8, 8 located on n the Mississsippi River aat mile 679.22, is approxiimately 0.6 m miles north of the site. Th he dam is a 110 feet wid de, 600 feet long lock aand dam struucture ownedd and operated by the USA ACE. This faacility also alllows publicc access to aan observatioon platform, open from daw wn to dusk during the months of April A througgh Novembeer. The Staate of Wisconsin maintains a highwaay wayside off State Highway H 355 approxim mately 1/2 miile north of the LACBW WR site, acrosss from Lock k and Dam No.N 8.

The closest town is Genoa, G locatted approxim mately 1 mille to the norrtheast of thhe site. Therre are no resideences within 2,000 feet of o any LACB BWR structuure.

6.2.4. Area A Ground dwater Use There aree two water supply wellls on the sitee (Deep Welll 3 and Deeep Well 4) thhat were insttalled in 1963 to t 129 feet and 116 feeet bgs, respeectively. Botth wells are located upggradient from m the LSE and are still in useu as potablle water for LACBWR.

L S Separate grooundwater wwells supply w water to the G-3 plant. Reg gionally, therre are five doomestic wellls south of thhe LACBWR site and eaast of Highway y 35.

6.3. Basements, B Structures S and a Piping to t Remain aafter Licensse Terminattion (End Sttate)

The conffiguration of the remain ning backfillled basemennts, buried piping, openn land areass and buildingss at the time of license teermination iss designatedd as the Endd State.

All but twot LACBW WR building gs will be demolished tto at least thhree feet bellow grade w which correspon nds to an ellevation of 636 6 foot Av verage Meann Sea Level (AMSL). T The two buildings that will remain intaact are the LACBWR L Administratio A on Building and LACBWR Crib H House.

The below ground po ortions of thee buildings to t be demoliished and baackfilled are listed in Tabble 6-1 and sho own in Figurres 6-4 and 6-5.

6 Figure 6-6 providees a cross-secction of the Reactor Buiilding basementt below 636 foot elevatiion which is the only ba sement withh a portion bbelow the average water tab ble elevation n. Note that there are alsso three veryy small sum mps with flooors that exteend to one foot below the av verage waterr table elevaation.

As seen in Figure 6--2, there are numerous buildings b asssociated witth the G-3 coal plant thaat are outside ofo the LSE but b within th he LACBWR R licensed bboundary. H However, theese buildings and adjacent open land areasa were not used to su upport LAC CBWR operaations. The majority off open land areaas and build dings outsidde of the LS SE fence aree designatedd as non-imppacted. See LTP Chapters 2 and 5 forr additional discussion d an nd justificattion of the noon-impactedd classificatiion of areas outtside of the LSE.

L The strucctures to be backfilled willw be com mprised of cooncrete onlyy and includde full and ppartial basementts, isolated sumps s and remaining po ortions of fooundations. All systems and components will be removed.

r The T backfillled structurees are generrally referreed to as eithher basemennts or structures in this LTP P Chapter. For the Reaactor Buildinng, only the concrete exterior to the steel liner willl remain; all interior concrete and thee steel liner will be remooved. All reemaining 6-3

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 6-1 Basemments and Below B Ground Structurres to Remaain in LACB BWR End S State Ground surface elevation e is 639 feet AM MSL Materiial Flloor and Waall Flloor Elevatioon Basemeent/Structuree remain ning Suurface Area (m2) (ffeet AMSL)

Reactorr Building Conncrete 511.544 612 Waste Treatment T Buuilding Conncrete 101.900 630 Waste Gas G Tank Va ault Conncrete 460.044 621 Remain ning Structurres Piping and Ventilation V

Conncrete 177.077 629 Tunnels Reactor/Geneerator Plant Conncrete 359.599 629 Chimney Slaab Conncrete 117.866 635 Turbine Summp Conncrete 5.64 618 Turbine Pit Conncrete 7.09 618 concrete will be deccontaminated as necesssary to meett the 10 CF FR 20.1402 unrestrictedd use criteria.

For the purpose of dose assesssment, the basementsb oother than thhe Reactor Building, W Waste Treatmen nt Building (WTB),

( andd Waste Gas Tank Vaultt (WGTV) arre grouped iinto one cateegory designateed as the R Remaining Structures.

S This T createss four separaate areas to consider in dose assessmeent and Finaal Radiation n Survey (F FRS) design; Reactor B Building, WTB, WGTV V and Remainin ng Structurees. There aree several reassons for thiss organizatioon. The Reacctor Buildinng has a unique configuratio on, includinng a portion below the aaverage wateer table elevvation and a very low poteential for con ntaining signnificant residual radioacctivity after all interior concrete annd the steel lineer is removed d. This leadss to unique dose d assessm ment assumpptions and FR RS classificaation.

In addition, the FRS S design can n effectivelyy accommoddate a surveyy unit consisting of onlly the Reactor Building.

B The T WTB haas the highesst contaminaation potentiial of all Endd State strucctures and need ds to be ad ddressed sep parately to ensure thatt the sourcee term in tthe WTB iss not inappropriately averraged with the t other sttructures. Thhe small sizze of the W WTB structuure to remain iss not particu ularly condu ucive to an efficient e FRS S design and implemenntation but ddue to the relatiively higher contamination potentiaal this loss oof efficiencyy is considerred justified. The WGTV was w evaluateed separately y because the floor is at a lower elevvation than tthe WTB annd the Remainin ng Structures, which req quires differeent modelingg parameterss.

As seen in Table 6--1, the Remaaining Strucctures consisst of a grouup of structuures that all have relativelyy low contam mination pottential. Two of the structtures, the Tuurbine Sumpp and Turbinne Pit, are very small in sizze. Treating each of thee basementss in the Reemaining Strructure cateegory separatelly does not provide p a meeaningful disstinction in ddose modelinng due to theeir generallyy 6-4

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 similar elevations e annd contamin nation poten ntial. Treatinng the Rem maining Struuctures separrately would reesult in unneecessary com mplexity in FRS F design, implementaation and documentationn. See LTP Chaapter 5 for diiscussion of the FRS pro ocess.

The End d State will also includ de a limited d number oof buried pipes, with tthe majorityy not associateed with contaaminated op perational systems. The eexception is the remainiing portion oof the Circulatinng Water Discharge D pip w used as for liquid eeffluent disccharge as weell as pe which was circulatin ng water disscharge. Forr the purposse of this L License Term mination Plaan (LTP), bburied piping is defined as that contained in soil. Typical T comm mercial powwer plants alsso contain ppiping that peneetrates walls and is embeedded in con ncrete. The ddesign of the LACBWR R plant incluudes a tunnel too contain alll systems pip ping that raan between bbuildings whhich eliminaated the neeed for penetrations. There is no embedd ded piping prresent. The bburied pipinng to remain in the LACB BWR End Statee is listed in Table 6-2.

Tablee 6-2 Buuried Piping g to remain in LACBW WR End Statte Deescription of Piping P Quantity 1044 of 4Schedd. 40 PVC 57 of 2 P PVC Adminisstration Build ding Sanitary System inclu uding drain 22500 gal septiic tank piping, leach l field latterals, and tan nks 7750 gal dosinng tank 944 gal distribution tank 708 perforated 4 PVC 144 4 PV VC High Preessure Servicce Water from m LACBWR Crib C House 50 of 6 to G-3 222 of 88 511 of 33 Well waater piping forr Well #3 95 of 2 9388 of 48 conccrete pipe Storm Water W Piping 3 steel grates aat grade 100 of 10 PVC 5225 of 60 steeel pipe Remainiing portion off Circulating Water Dischaarge Pipe The poteential for significant surfface or subsu urface soil ccontaminatioon at LACBW WR is low bbased on the finndings of thee EnergySollutions Techn nical Supporrt Documentt (TSD) RS--TD-3131966-003, La Crossse Boiling Water Reacctor Historiccal Site Asssessment (H HSA) (2) annd the resullts of extensivee characterizzation perfo ormed in 20 014 (see LT TP Chapter 22). There aare indicationns of subsurfacce soil con ntamination under the Turbine Buuilding baseed on posittive groundw water monitorin ng results down gradien nt of suspectted broken ddrain lines. However, ggeoprobe sam mples collectedd under the Turbine T Buiilding in thee vicinity off the suspectt drain liness did not ideentify plant-derrived radionu uclides abov ve backgrou und. Full chaaracterizatioon of the subbsurface soill will be performed after the Turbinee Building foundation is removedd and the unnderlying sooil is exposed.

6-5

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Low con ncentrations ofo groundwaater contamin nation have been identiffied adjacentt to the susppected broken floor f drains under the Turbine T Buillding. Grouundwater sam mpling in 1983 from a well located down d gradient of the Turbine Bu uilding idenntified contaamination aat relativelyy low concentraations. In late 2012, fivee additional monitoring well pairs w were installeed to supporrt site characterrization and d license terrmination. Results R indiccated lower groundwateer contaminnation levels thaan found in 1983, predo ominantly H-3. See LTP P Chapter 2, section 2.3..7 for a sum mmary of ground dwater samp pling results..

6.4. Future F Landd Use Scenarrio and Aveerage Memb ber of the CCritical Grou up The Reeasonably Fo oreseeable Scenario, S iss defined inn NUREG-11757, Volum me 2, Revisiion 1 Consolid dated Decom mmissioning Guidance - Characterrization, Suurvey, and D Determinatioon of Radiolog gical Criteria a (NUREG-1757), (3), TableT 5.1 ass a land use scenario thaat is likely wwithin the next 100 years. The T Reasonab bly Foreseeaable Scenarioo for LACBWR is indusstrial use.

DPC firsst acquired laand at the siite in 1941to o build its fiirst coal-fireed generationn station, G--1. In 1949 an additional 18.6 acres weere acquired d for G-1 coaal ash dispoosal. An addiitional 80.8 acres were acq quired in 19662. Finally, ana additionaal 26.8 acres was filled bby dredging in 1962-63. The total areaa owned or controlled c by y DPC was th hen, and conntinues to bee, 163.5 acrees.

The G-1 plant begaan operation n in 1941 anda was deccommissioneed and dism mantled in 1989.

LACBW WR constructiion began in n 1963, was completed iin1967, and was permannently shut ddown in 1987. DPCs thiird plant on nsite, G-3, began b comm mercial operaation in 19669 and conttinues operation n as a major generation resource to the DPC sysstem. The G G-3 plant hass been updatted to meet current environ nmental standards and iss currently p erforming a major turbiine overhaull. The projectedd remaining operation liffe of G-3 is projected p to be 20-25 yeears.

Residential use of thee site over th he next 100 years appeaars unlikely. The site is rrelatively isoolated as it is bounded by thet Mississip ppi River to the west, a rail line to tthe east, US SACE properrty to the northh, and a wildlife and fish refuge to th he south. Theere are severral small com mmunities neearby that would be more suitable s to ad dditional ressidential devvelopment thhan the DPC C site. In adddition, the preseence of overr 36 acres off closed coall ash landfillls further suupports the aassumption of no foreseeab ble future residential dev velopment. Based B on surrrounding laand use, the cconversion oof the property to recreation nal use at some point in the distant fu future is morre likely thann residential use.

In summ mary, the DP PC site has been b in conttinuous induustrial use foor 74 years and DPC haas no plans to change the landl use in the t future. The T site conttains a transsmission stattion and valuuable infrastruccture to suppport the sitess future use for f power suupply after G G-3 is decommmissioned iin 20-25 years. Adjacent land, and a part p of the DPCD site is ccurrently used for recreeational purpposes.

Finally, there t are largge tracts of land l nearby that would bbe preferablle, and moree cost-effectiive to develop for residentiial use withiin at least th he next 100 year time pperiod than tthe conversion of the DPC site from in ndustrial use. Residential land use iss therefore categorized aas less likelly but plausiblee in accord dance with NUREG-17 757, Table 5.1 definitiions. Baseed on the aabove discussioon of future land use, the Averagee Member oof the Critical Group ((AMCG) foor the LACBW WR dose assessment is thee Industrial Worker.

W 6-6

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 6.5. Dose D Model Overview Dose mo odeling is peerformed to demonstratee that residuual radioactivvity remaining at the tim me of license termination will w not result in a dosse to the AM MCG (indusstrial workeer) exceedinng the 25 mrem m/yr criterion

n. This sectio on provides a general ovverview of thhe LACBWR site conceeptual model an nd computatiional method ds for dose assessment.

a There aree four poten ntial sources of residual radioactivityy in the Endd State that were categoorized as followws for the purpose p of dose d modeliing; backfillled basemennts, soil, buuried piping, and groundw water. The in ntact LACB BWR Admin nistration Buuilding will also remainn intact but has a very low w potential of o containin ng significan nt levels of residual raddioactivity, if any. Thee vast majority of residual radioactivitty to remain n at the timme of licensee terminatioon will be inn the concrete of backfilleed basementts. There is no indicatioon that signnificant soil contaminatiion is currentlyy present at the t LACBW WR site or will be presentt in the End State. Withh the exceptiion of the remaiining portion n of the Circculating Watter Dischargee Pipe, the liimited burieed piping thaat will remain was w not assocciated with contaminated c d systems annd is expecteed to containn minimal, iff any, contamin nation. The potential fo or significannt groundwaater contamiination is allso very low w but groundw water exposurre factors were w calculatted. The dosse from eachh of the fouur sources w will be summed as applicablle to demonsstrate compliiance with thhe 25 mrem//yr dose criteerion.

An overv view of the dose assessm ment method ds for the foour sources is provided below. Dettailed descriptioons and resuults are proviided in sectio ons 6.7 to 6..17.

6.5.1. Backfilled B Ba asements The dosee model for backfilled basements b to o remain beloow 636 foott elevation ((see Table 6-1) is designateed as the Bassement Fill Model M (BFMM). The BFM M calculatess the dose to the AMCG from residual radioactivity r y remaining in i the basem ments.

The baseement End State S will bee comprised of backfilleed concrete sstructures thhat are physiically altered to o a conditionn that would d not realistiically allow the remaininng structures to be occuupied.

The BFM M conceptuaal model inclludes two so ource term ggeometries; 11) the Insituu geometry w where the concrrete remainss in the as-left configu uration at thhe time of license terminnation and 22) the Excavation geometry y where som me or all of thhe concrete iis excavated and broughtt to the surfaace.

The resu ults of the BFM B dose assessmentss are expresssed as Dosse Factors ((DF) in uniits of mrem/yr per mCi tottal activity for f each of the three basements annd the Remaaining Strucctures group. It cannot be ruled r out thaat a portion of o the backfi filled structurres could bee excavated and a portion remain r in thhe ground. Therefore, the final doose for dem monstrating compliancee will conservaatively includde the sum ofo the BFM Insitu I and BF FM Excavattion dose.

6.5.1.1. BFM Insitu Scenaario The BFM M Insitu geom metry includ des two expo osure scenariios; 1) exposure to well water contaaining residual radioactivityy as a resultt of leaching g from the bbackfilled concrete surffaces into thhe fill material and 2) expo osure to drillling spoils that are broought to the surface durring the assuumed installatio on of an onssite water su upply well. The T well waater scenario is designateed as BFM IInsitu Groundw water (BFM Insitugw). The T drilling spoils scenaario is designnated as BFM M Insitu Drrilling Spoils (BBFM Insituds).

6-7

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The concceptual mod del for the BFM B Insitugww scenario aassumes thatt the residuaal radioactiviity in floors annd walls is released to adjacent a fill through leacching into w water that coomes into coontact with the concrete surfaces s afteer backfill. The scenarrio assumes that 100% % of the ressidual radioactivvity is releaased instantly into the fillfi which is then treatedd as contam minated soil. The release occurs o immeediately afterr license terrmination takking no creddit for radiooactive decayy. A water sup pply well is assumed to be installed d adjacent too the down ggradient edgge of the buiilding and floww to the well is conservattively modelled assumingg that structuures are not present. Beccause a clean cover c of at least l 3 feet is i present ov ver potentiallly contaminnated surfacces the dose from direct exxposure and soil ingestio on/inhalation n is negligibble or zero. The BFM IInsitugw exposure pathway to the industrial worker AMCG is drinking d wateer from the oonsite well.

The BFM M Insituds sceenario assummes that the drilling d spoiils from the iinstallation oof the onsitee well are broug ght to the suurface. The well installaation is assuumed to occcur immediaately after liccense terminatiion, before any a leaching from concreete occurs annd taking noo credit for raadioactive ddecay.

The resiidual radioaactivity in the t floor co oncrete thatt is contactted by the borehole dduring installatio on is assumed to be inaadvertently mixed m with tthe fill mateerial above tthe floor surrface, brought tot the groun nd surface, and a spread over a 15 cm m thick layerr. The BFM Insituds exposure pathwayss are the sam me as those th hat apply to contaminateed surface sooil.

The BFM M Insitugw dose d assessmment is impleemented usinng the RESidual RADioactive materials (RESRA AD) v7.0 model.

m The BFM Insitu uds dose as sessment iss implemennted using E Excel spreadsheet calculatiions coupled d with RESR RAD modeliing. The ressults of the BFM Insitu dose assessmeents are exprressed as DF Fs in units ofo mrem/yr per mCi tottal activity inventory in each basementt (and the Reemaining Structures) (seee Table 6-1 ). The invenntory of residdual radioacctivity at the tim me of licensee termination n, as determiined by the F FRS, will bee multiplied by the BFM M DFs for each Radionuclid de of Concerrn (ROC), an nd summed as necessaryy, to demonsstrate complliance with the 25 mrem/yr dose criterio on.

6.5.1.2. BFM Excavation Scenario The BFM M Excavatio on scenario assumes a thaat some or aall of the bacckfilled struucture concreete is excavated and spread on the ground surface at som me time aftter license termination. For conservaatism, the exccavation is assumed a to occur o immeddiately after license term mination takinng no credit forr radioactivee decay. The residual raadioactivity remaining inn the backfilled basements is assumed to inadverteently mix with w the masss of structuural concretee removed dduring excavvation which is consistent with w the guiidance in NU UREG-17577, Appendix J, for addreessing subsuurface contamin nation. Thee calculation n is perform med using E Excel spreaadsheet and results in BFM Excavation DFs that are expresseed in the sam me units as tthe DFs for tthe BFM Inssitu scenarioo, i.e.,

mrem/yr per total mCi. The fun ndamental driver d of the BFM Excavvation DF ccalculation iss that the averaage concentrration in the excavated concrete c is liimited such tthat the surfface soils DCCGLs are not exxceeded.

BFM Ex xcavation DF Fs were calcculated sepaarately for thhe Reactor B Building, WWTB, WGTV V, and Remain ning Structurres consisten nt with the BFM B Insitu D DF calculatiions.

6-8

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 6.5.2. Soil Derived Concentratio C on Guidelinee Levels (DC CGLs), in unnits of pCi/gg, were develloped for ressidual radioactivvity in surfaace soils thaat corresponnd to the 25 mrem/yr doose criterionn. RESRAD D was used to perform p the calculation.

c For consservatism, and a to optimmize remed diation efficciency, surfaface soil is defined ass that contained d in a 1 m deepth from th he surface. A standard suurface soil contaminatioon thickness of 15 cm woulld result in lower dose (i.e., higherr DCGL). H However, in the unlikelly event thaat soil contamin nation is ideentified at LACBWR L with w a thicknness greater than 15 cm m additional dose modeling g may be required if thee conceptuaal model assuumed a 15 cm contamiination thickkness.

Using a 1 m thick kness reducces the pottential for delays or unnecessaryy remediatioon if contamin nation with a thicknesss somewhat greater thaan 15 cm iss encountereed. There iss low potential for subsurfaface contamin nation to remmain in the End State w with a geomeetry comprissed of a clean sooil layer oveer a contaminnated soil lay yer at depth..

In the unlikely u evennt that geommetries are encounteredd during coontinuing chharacterizatioon or during FSS F that arre not boun nded by thee assumed 1 m soil contaminatioon thicknesss, the discovereed geometriees will be ad ddressed by additional m modeling. T The U.S. Nuuclear Regullatory Commisssion (NRC) will w be notiffied if additio onal modelinng is requireed.

Standardd methods fo or RESRAD parameter selection s andd uncertaintyy analysis arre used consistent with guiddance in NU UREG-1757. The AMCG G for soil is thhe Industriall Worker.

6.5.3. Buried B Pipin ng With thee exception of o the portioon of the Ciirculating W Water Dischaarge Pipe, noone of the bburied piping to o remain at a LACBWR R was asso ociated withh contaminaated system ms and therrefore contamin nation poten ntial is miniimal (see Table T 6-2). A buried ppiping dose assessmentt was conducteed to develop p DCGLs forr pipe.

The concceptual model for the bu uried piping dose assessm ment is simiilar to the B BFM and inccludes two scen narios: Insituu and Excav vation. In th he Insitu sccenario the rresidual raddioactivity onn the internal surfaces s of the t pipe is assumed a to instantaneou i usly release aand mix witth a thin 2.554 cm layer of soil s in an areea equal to th he internal surface s area of the pipe. For the Exccavation scennario, the soil mixing m layerr is 15 cm due d to the ex xtensive groound surfacee disturbancee associatedd with the pipe excavation.

e The Insitu sccenario assu umes that thee released radioactivity iis a below grround 2.54 cm layer of soil with no crredit taken for fo the preseence of the ppipe to reducce environm mental transportt and migratiion. This is a conservativ ve assumptioon, particulaarly for the C Circulating WWater Discharg ge Pipe which will be filled with a flowable fill materiaal. The Exccavation sceenario assumes that the pip pe is excavatted followed d by instant release of aall radioactivvity into a 15 cm layer of soil s on the ground g surface with no cover.

c The Inndustrial Woorker is expoosed to the IInsitu and Excaavated soil via the sam me pathwayss applicable to the BFM M and soil dose assesssment scenarioss. RESRAD modeling iss used in con njunction witth Excel sprreadsheet to calculate DC CGLs in units of o dpm/100 cm c 2.

6-9

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 6.5.4. Existing E Grooundwater Groundw water monito oring has beeen and willl continue tto be conduucted until sometime bbefore license teermination. The T final mo onitoring datte will depennd on the evvaluation of sampling reesults.

Low leveels of H-3 an nd Sr-90 hav ve been iden ntified in sammples collectted since 2012 after fivee new well pairrs were instaalled at the siite. Groundw water exposuure factors inn units of mmrem/yr per ppCi/L groundwwater concentration are provided p to perform doose assessmeent for existting groundw water contamin nation presennt at license termination,, if any.

6.5.5. Remaining R Above A Grou und Building gs The LA ACBWR Ad dministrativee Building, LACBWR R Crib Houuse and T Turbine Buiilding Switchyaard Fire Service Water System willl remain inttact. The buildings aree not expectted to contain residual r rad dioactivity. They T will be b free releeased in acccordance wiith the guiddance in NURE EG-1575, Su upplement 1, Multi-Agency Radiatioon Survey aand Assessm ment of Mateerials and Equiipment Manu ual (MARSA AME) (4) .

6.5.6. Dose D Summa ation for Co ompliance The vario ous source terms t and coonceptual models m discuussed above are not neceessarily muttually exclusivee. For exam mple, althoug gh a low pro obability, a given basem ment could bbe subject tto the BFM Inssitu drilling spoils scenaario and subssequently exxcavated. Annother exam mple could bee that the activ vity released to groundw water in the BFM Insituugw scenario for one bassement com mbines with the groundwateer activity released r fro om another basement thhat is downn gradient bbefore encounteering the well. Thereforee, the BFM Insitugw dosse will be suummed acrooss all basem ments.

The dose from soil, buried piping, and groundwateer could alsso be view wed as occuurring simultaneeously with the BFM do ose scenario os. Thereforee, the final ssite-wide doose assessmeent to demonstrrate compliaance with th he 25 mrem//yr dose critterion will innclude the ssummation oof the following g using the mean m values from FRS:

maxim mum BFM Insitu I ds dose e,

maxim mum BFM Excavation E dose, d

sum ofo the BFM Insitugw dose from all baasements com mbined, maxim mum soil do ose, maxim mum buried d piping dosee, maxim mum existin ng groundwaater dose.

6.5.7. Alternate A Scenarios As discu ussed in seection 6.4, the industrrial use sceenario was selected aas a reasonnably foreseeabble scenario o based on past p and projjected use oof the LACB BWR site. Tw wo alternatee land use scenaarios were co onsidered in ncluding recrreational usee, and resideential use witth a water suupply well and onsite gardeen.

A qualitaative evaluaation of a recreational laand use scennario concluuded that thhe dose wouuld be lower thaan that calcuulated for thee industrial use u scenario because occcupancy timee would be less 6-10

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 than thatt assigned to o an industrial worker. In addition, if a water ssupply well were installled in the recreational land use scenario the recreattional userss intake rate from the w well would bee less than assuumed for the industrial worker.

w The resid dent garden ner land usee was consid dered to bee a less likkely but plaausible landd use scenario as defined in i NUREG-1757, Table 5-1. RESRA AD was useed, in conjunnction with E Excel spreadsheet, to calcu ulate the dosse from the Resident R Gaardener alterrnate scenariio. NUREG--1757 states thaat if the peak k dose fromm a less likelyy put plausibble scenarioo is significcant then grreater assurancee that the scenario is unllikely would d be necessarry. The alterrnate scenariio is addresssed in section 6.15.

6 6.6. Mixture M Fractions for In nitial Suite Radionuclid des A comprrehensive iinitial suite of 21 radionuclides w were identifiied that couuld potentially be present at a the LACB BWR site. As A discussed below, the iinitial suite includes maany radionucclides that havee not been positively identified in n LACBWR R 10 CFR Part 61 annalysis or dduring characterrization but could theoreetically be present, p albeit at very loow mixture ffractions, rellative the primaary radionucclide which is i Cs-137.

The initiaal suite mixtture fractionss were used in the RESR RAD uncertaainty analysees for Soil D DCGL and BFM M DF dose asssessments. The initial suite s mixturee fractions w were used in conjunctionn with the soil DCGLs D andd BFM DFs to identify the insignifficant dose ccontributors and final list of ROC thaat will be considered c during d the FRS F and finnal dose suummation foor compliancce as described d in section 6.5.6.

6 6.6.1. Potential P Radionuclidess of Concern n and Initiall Suite EnergySo olutions TS SD RS-TD--313196-001 1, Radionucclides of C Concern D During LAC CBWR Decommissioning (5 5) establisheed an initiaal suite of ppotential RO OC. Two inndustry guiddance documen nts were rev viewed inclluding NUR REG/CR-34774, Long-Liived Activattion Produccts in Reactor Materials, M (66), and NUR REG/CR-428 89, Residuall Radionuclidde Concentrration Withinn and Around Commercia al Nuclearr Power Plants; O Origin, Disstribution, Inventory, and Decommissioning Asssessment (7 7). The revieew also incluuded an evaaluation of a LACBWR spent fuel inveentory assesssment condu ucted in 1988 8 that was ddecay correccted to Januaary 2015. Seeveral 10 CFR Part P 61 wastte stream anaalyses were also a revieweed.

The list of o activation n product raadionuclides for consideeration in thee initial suitte was develloped after elim minating nob ble gases, raddionuclides with w half-livves less than two years, aand radionucclides with theo oretical neuttron activatiion productss with abunddances less than 0.01 peercent relatiive to Co-60 an nd Ni-63 (th he prominen nt activationn products iddentified in LACBWR 10 CFR Paart 61 samples). The revieew of Referrence 6, wh hich include s both activvation and fission prodducts, coupled with review w of the LAC CBWR fuel inventory aand 10 CFR Part 61 anaalyses resultted in several additional a raadionuclidess being inclu uded in thee list of thoose that could be potenntially present during d the deecommission ning of LACBWR.

Finally, the results of o concrete core samples collectedd from the W WTB, Reacttor Buildingg and Piping an nd Ventilatio on Tunnels were review wed. No radiionuclides w were positiveely identifiedd that were not already acco ounted for by b the assessm ments descriibed above.

6-11

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The resulting list of potentially p present p radio onuclides is called the IInitial Suite and is provvided in Table 6-3. The process for dettermining th he mixture frractions is deescribed beloow.

6.6.2. Mixture M Fractions for In nitial Suite Radionuclid des As descrribed in Reference 5, the t mixture fractions ffor the Initiial Suite raddionuclides were developeed from conccrete core daata collected d during chaaracterizationn from the R Reactor Buillding, WTB, an nd Piping/Veentilation Tu unnels. The vast majoritty of the acttivity was loocated in thee first 1.27 cm slices from the cores which w were th herefore useed to determ mine the radiionuclide miixture fractions. The use off cores with h higher con ncentrations was requireed to ensure that the miixture fractions assigned too low abund dance radion nuclides werre not overlyy influencedd by the repported Minimum m Detectablle Concentrration (MDC) values which weree in many cases the only concentraation data avvailable. Thhe mixture frractions assiggned to the IInitial Suite radionuclidees are provided d in Table 6-3 3.

Table T 6-3 Initial Su uite of Poten ntial Radion nuclides and Mix xture Fracttions Mixtture Nuclide Fracttions H-3 0.000071 C-14 0.000065 Fe-55 0.002294 Ni-59 0.010038 Co-60 0.012221 Ni-63 0.080048 Sr-90 0.009907 Nb-94 0.000008 Tc-99 0.000015 Cs-137 0.877736 Eu-152 0.000093 Eu-154 0.000080 Eu-155 0.000045 Pu-238 0.000014 Pu-239/240 0.000013 Pu-241 0.003306 Am-241 0.000037 Am-243 0.000004 Cm-243/244 0.000005 Total 1.000 The mixtture was bassed on a com mpilation of 12 1 cores from m all buildinngs to determ mine one miixture fraction for all build dings. The application a of o the combbined data too determine the mixturee was justified in Referencce 5 by a reeview of Css-137/Sr-90 ratios whicch were relaatively consistent across coores from thee different arreas. The pottential effectt of uncertaiinty in the m mixture fractiions 6-12

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 on the finnal complian nce dose callculations iss minimized by the fact that the vasst majority oof the mixture isi comprised d of Cs-137 which is a beta-gammaa emitter. T There is no ddose impact from uncertainnty in the miixture fractio ons for Cs-137, or any oother beta-gaamma emitting radionuclides, because the FRS for f structurees and soill will be pperformed uusing gamm ma spectrosccopy.

Complian nce with the 25 mrem/y yr dose critterion will bbe demonstrrated using actual measured concentraations for gamma-beta g emitters. Note N that thhe dose conntribution frrom beta-gaamma emitters that were designated as insignificant contribbutors is allready accouunted for inn the insignificcant contribuutor dose caalculation an nd the correesponding addjustments tto the BFM DFs, soil DCG GLs and Burried Pipe DCGLs. The additional ddose from anny beta-gam mma radionuuclide that is po ositively idenntified during FRS will be b directly ccalculated annd included iin the complliance demonstrration.

The prim mary source of o potential dose impactt from mixtuure uncertainnty is limiteed to the Harrd-to-Detect (HHTD) mixtu ure fractions because theere will be nno analysis oof HTD radiionuclides dduring FRS. Ho owever, the method useed to calculaate the insiggnificant coontributor doose percentaage is conservaative and provides suffiicient margiin to accounnt for uncerrtainty in thhe HTD miixture fraction. See section 6.13 for the assessment of insignificcant contribuutor dose perrcentage.

There were w only a few posiitive soil sample s resuults identifiied during characterizaation, predomin nantly Cs-137, and the concentraations were insufficiennt to providde a meaniingful evaluatioon of the relaative mixturee fractions for fo the HTD radionuclidees which weere all reportted as less than the MDC. When W the Cs-137 concentrations aree low the rellative mixturre fractions oof the HTD rad dionuclides that t are not positively identified i arre artificiallyy increased due to usinng the MDC vaalue which couldc be ordders of magn nitude higheer than the aactual concenntrations preesent.

Therefore, the radion nuclide mixtu ure fractionss determinedd from the cooncrete corees were appliied to soil and used u to deterrmine the so oil ROC. Ho owever, as ddescribed in section 6.133 the insignifficant contributtor dose percentage assiigned to soill is demonsttrated to be conservativve and to proovide sufficientt margin to account a for mixture m unceertainty.

6.7. Soil Dose Assessment an nd DCGL Site-speccific DCGLss were develloped for ressidual radioaactivity in surface soil tthat represennt the 10 CFR 20.1402 2 dosse criterion of 25 mrem//yr. A DCG GL was calculated for each initial suite radionuclide in orderr to provide an input to the determiination of innsignificant ccontributors dose percentag ge and the fiinal list of ROC.

The surfface soil co onceptual model m assum mes that thee soil contaamination iss contained in a uniformly y contaminaated 1 m lay yer of soil from the grround surfacce downwardd. There arre no expectatiions that at the time off license terrmination reesidual radiooactivity wiill remain w with a geometry y consisting of a clean surface layeer of soil ovver a contam minated subssurface soil layer with conccentrations exceeding e th he surface so oil DCGL.

6.7.1. Soil Source TermT There is limited poteential for sig gnificant surrface or sub surface soil contaminatiion at LACB BWR based on n the resultts of soil characterizat c ion perform med in 20144. There arre indicationns of subsurfacce soil con ntamination under the Turbine Buuilding baseed on posittive groundw water monitorin ng results doown gradientt of suspecteed broken drrain lines. Hoowever, geoprobe samplles 6-13

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 collectedd under the Turbine T Buiilding in thee vicinity off the suspectt drain liness did not ideentify plant-derrived radion nuclides abo ove backgrround. Subssurface soill will be eevaluated dduring continuinng characteriization after the Turbinee Building fooundation iss removed annd the underrlying soil expoosed.

Soil charracterization n results are provided in LTP Chapteer 2 and sum mmarized heere. A total of 22 biased suurface soil saamples and 79 7 subsurfacce soil samplles (at varyinng depths to six meters) were collectedd inside the LSE L fence. Thirteen T t surface ssoil sample aanalyses resuults indicated Cs-of the 137 abov ve the MDC C with a maaximum of 1.07 pCi/g. Two of thee surface sooil sample reesults indicatedd Co-60 abov ve the MDC C with a max ximum of 0.287 pCi/g. F Fifteen of thhe subsurfacee soil samples indicated Css-137 abovee MDC with a maximum m of 0.161 ppCi/g with nno subsurfacee Co-60 results greater thaan MDC. Thee Cs-137 ressults are all iin the range of natural baackground.

6.7.2. Soil Exposurre Pathwayss and Criticcal Group The AMCG at the LACBWR L site is the In ndustrial Woorker. The fo following exxposure pathhways apply:

Direcct exposure tot external raadiation Inhallation of airb borne radioacctivity Ingesstion of soil Ingesstion of wateer from onsitte well The agricultural and d gardening pathways are a not appliicable to inddustrial landd use. The m meat, milk, graain and vegettable ingestion pathwayss are therefoore not includded.

6.8. Soil DCGL Computatio C on Model - RESRAD R v77.0 The RES SRAD modell was used to o calculate DCGLs D for ssurface soil. The RESRA AD output reeports for the modeling discussed below aree providedd electroniccally in coonjunction with EnergySo olutions TSD RS-TD-3 313196-004, LACBWR Soil DCGL L and Conccrete BFM Dose Factors (8).

(

6.8.1. Parameter P Selection S Proocess RESRAD D parameterss are classifi fied as behavvioral, metabbolic or physical. Somee parameterss may belong to o more than n one catego ory. Physiccal parameteers are deterrmined by thhe geometryy and location of the source term and the t geological characteriistics of the site (i.e., source-specific and site-specific) including the geoh hydrologic, geochemical g l, and meteoorologic chaaracteristics. The characterristics of atm mospheric an nd biospherric transport up to, but not includinng, uptake bby, or exposuree to, the dosee receptor aree also consid dered physiccal input paraameters.

Behaviorral parameteers define thee receptors behavior coonsidering thhe conceptuaal model sellected for the site. For thee same grou up of recepto ors, a param meter value ccould changge if the sceenario changed (e.g., param meters for industrial useu could bee different from resideential use). For LACBW WR, the behaavioral param meters are baased on an iindustrial usse scenario aand are the same for both the t BFM and d soil dose assessments.

a 6-14

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Metaboliic parameterrs define cerrtain physiollogical charaacteristics off the potentiial receptor. One set of meetabolic paraameters appliies to both th he BFM andd soil dose asssessments.

Physical,, behavioral and metabollic parameteers are treateed as determiinistic param meters in thee final dose mod deling to callculate soil DCGLs D (andd BFM DFs)). The deterrministic moodule of the code uses singgle values fo or input parameters and d generates a single vallue for dose. The param meter selection n process is described d bellow.

Argonne National Laboratory L (ANL)

( rankked physicall parameterss by priorityy as 1, 2, or 3.

Priority 1 parameterss have the highest h potential impactt on dose annd Priority 3 the least. This ranking is i documentted in Attach hment B to the t ANL repport, NURE EG/CR-6697,, Developmeent of Probabillistic RESRA AD 6.0 and RESRAD-BU R UILD 3.0 Com mputer Codees, (NUREG G/CR-6697) (9).

Priority 3 physical parameters p were w assigneed either a ssite-specific value or thhe median vvalues from the parameter distributions d defined in NUREG/CR N R-6697. Prioority 1 and 2 parameters were either assigned site-specific detterministic values, v evaluuated by unncertainty annalysis using the parameteer distributioons defined ini NUREG/C CR-6697, orr evaluated bby uncertainnty analysis uusing site-specific parametter distributiions. The Partial P Rank Correlationn Coefficiennt (PRCC) vvalues from thee RESRAD uncertainty analysis were used to evaluate thhe relative ssensitivity oof the Priority 1 and 2 parrameters. A PRCC vaalue less thhan -0.25 w was considerred sensitivee and negativelly correlated T 25th perccentile of thee parameter distributionn was assignned to d to dose. The negativelly correlated d parameterss. A PRCC C value greaater than +0..25 was connsidered sensitive and posittively correlated to dosee. The 75th percentile p off the parameeter distributtion was assiigned to positiv vely correlatted parameteers. Priority 1 and 2 paraameters withh a PRCC abbsolute valuee less than 0.255 were assign ned the median value off the parametter distributiion.

Consisten nt with thee guidance in NUREG G-1757, secction I.6.4.2,, metabolic and behavvioral parameteers were assiigned the meean values from fr NUREG G/CR-5512 Vol. 3, Resiidual Radioaactive Contamin nation Fro om Decom mmissioning Parameterr Analysis (NUREG//CR-5512) (10)

Table 6.887.

Figure 6--7 provides a flow ch hart of the parameter selection prrocess. The set of sellected determinnistic parameeters and parrameter distrributions is uused in a RE ESRAD Unccertainty Anaalysis to determ mine the final deterministtic parameteer set used too calculate sooil DCGLs.

6.8.2. RESRAD R Paarameter Seelection for Uncertainty U y Analysis The unceertainty anallysis includeed all of thee initial suitee radionuclides from Taable 6-3 thaat had rounded mixture fraactions of 0.1% 0 or greeater. The cconcentrations assignedd to the sellected radionuclides, and en ntered into RESRAD R forr the uncertaainty analysis, were valuues equal to their respectiv ve mixture factions.

f Thiis approach is consistennt with the guidance inn NUREG-1757,Section I.7.5 I and enssures that thee sensitivitiees of the signnificant radioonuclides arre fully accouunted for. The threshold of o 0.1% forr including radionuclidees was prim marily applieed to facilittate a practical implementaation of the RESRAD R unncertainty annalysis moduule but is also fully consistent with the objective off identifying sensitive paarameters fo r significantt radionucliddes. The rationale for selecttion of deterrministic parameters thro ough the unccertainty anaalysis is discuussed below w.

Attachmeent 6-1 prov vides a tablee with the deeterministic values and parameter ddistributions used for the un ncertainty an nalysis. The references or o justificatioons for the pparameter sellections are listed 6-15

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 in Attach hment 6-1. The T basis fo or the behav vioral and mmetabolic parrameters (NU UREG/CR-55512) and the generic g paraameter distriibutions (NUUREG/CR-66697) are strraightforwarrd and consistent with the process flo ow chart in n Figure 6-7. The basiis for the ssite-specific parameterss and parameteer distributioons are discuussed in moree detail below w.

The conttaminated arrea was assu umed to be th he full 75000 m2 area insside the LSE E fence. Thee site-specific soil s type is sand.

s The deepth of soil contaminatio c on was conseervatively asssumed to bee 1 m to ensuree efficient remediation (iif necessary)) and FRS iff contaminatiion is foundd at depths grreater than the typical defaault value of o 0.15 m. TheT followinng site-speciific determinnistic param meters from Refference 1 weere applied:

Contaaminated Zo one Hydrauliic Conductiv vity, Soil Density, D

Soil Porosity, P

Soil Effective E Porosity, Saturrated Zone Hydraulic H Grradient.

A site-sppecific deterrministic vallue was also o selected fofor the Satuurated Zonee Field Capaacity parameteer based on a calculatio on performeed for a sannd soil type in ZionSollutions Techhnical Support Document 14-006, Co onestoga Ro overs & Asssociates (C CRA) Reporrt, Evaluatioon of Hydrolog gical Parameters in Supp port of Dosee Modeling ffor the Zion R Restoration Project (11)).

The Inhaalation Rate parameter for fo the industtrial worker AMCG waas derived froom NUREG G/CR-5512, Taable 5.1.1 wh hich providees an annual inhalation rrate of 8400//y for a residdential user.. This equates tot 23 m3/d. The inhalaation rate the industrial worker wass then calcuulated as follows:

Inhalation Rate (m3/y yr) = 23 m3/dd ÷ 24h/d

2000 2 h/y = 11917 m3/yr.

A similarr process waas followed to determin ne the Drinkking Water Inntake Rate pparameter foor the industrial worker. NU UREG/CR-5 5512, Table 6.87, providdes a water intake rate oof 478 L/yr for a residentiaal user which correspond ds to 1.31 L//d. This ratee was conservvatively appplied as the inntake rate for a worker as follows:

f 1.31 1 L/d

250 work w days/yyr = 327 L/yrr.

The RES SRAD param meters Indoo or and Outdo oor Time Frractions weree derived froom NUREG G/CR-6697 Attt. C, Table 7.6-1, whicch recommends a mediaan indoor w work day off 8.76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months s/day.

Assumin ng 5 days a week and 50 weeks per p year, thiis equates too 2190 houurs per year.. The majority of industriaal work is expected e to be indoors. Consistent with Table 2-3 of the ANL report Ussers Manua al for RESRA AD Version 6 (12) , 75% % of work tiime is assum med to be inddoors and 25% outdoors. The corresponding RESRA AD Indooor Fractionn parameteer =

(2190*.7 75)/(24*365)) = .1875 5. The Ou utdoor Tim me Fractionn is thenn calculatedd as (2190*.2 25)/(24*365)) = 0.0625.

Site-speccific parametter distributiions were deeveloped forr the Well P Pump Intakee Depth and Well Pumping g Rate Param water supply wells suppoorting meters. Theree are two exiisting onsitee industrial w LACBW WR. The welll depths are 116 feet an nd 129 feet bbelow the gground surfacce (bgs) (1). The 129 foot depth is 109 9 feet (33.1 m) m below th he average wwater table ellevation whiich is 20 feett bgs.

The 33.1 m depth is assumed a to be b maximum m well depthh. The minim mum well deppth is assum med to be repressented by a nominal n 20 foot f screen depth d (6.08 mm) starting att the averagee water tablee 6-16

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 elevation

n. The modee of the reccommended triangular ddistribution is assumed to be mid--point between 6.08 m and 33.1 m whicch is 19.6 m. Note that thhe site-speciific distributtion is reasonnably similar tot the NUR REG/CR-6697 distributtion values of 6, 10, and 30 foor the trianngular distributiion.

NUREG//CR-6697 does not prov vide a recommmended v alue for weell pumping rate due to high variabilitty. For an inddustrial use scenario, thee pump rate depends on industry. Too ensure thatt well pumping g rate is inccluded in the t uncertaiinty analysi s a nominaal uniform distributionn was developeed. NUREG G-6697, Tablle 3.10-1 app plies a sanitaary and potaable water ussage rate forr four persons ofo 328.7 m3/yr./ This vallue is assum med to be thee minimum industrial w well pumpingg rate assuming g four workers. A nomiinal maximu um rate is aassumed bassed on supplly to 20 woorkers which eqquates to1643.5 m3/yr. These T minimmum and maxximum valuees are not inntended to prredict actual waater use at ana unknown future indusstrial facilityy on the site after license terminatioon but de a range that can be useed to determ to provid mine if the doose is sensitivve to well puumping rate.

The remaaining param meters in Atttachment 6--1 not discuussed above were selected in accorddance with the process p flow w chart in Fig gure 6-7.

6.8.3. Soil DCGL Uncertainty U y Analysis Results R

The full RESRAD Uncertainty U Report R for Sooil DCGL paarameters iss provided ellectronicallyy with Referencce 8. The unccertainty anaalysis resultss are provideed in Tables 6-4 to 6-6.

The unceertainty anallysis results for the Kd parameters indicated thhat only threee Kd param meters were sennsitive which h are listed, along with the selectedd deterministtic parameteers, in Tablee 6-4.

The senssitive param meter for Cs--137 was asssigned the 75th percenttile value frrom the sannd Kd distributiions in Shep ppard and Th hibault, Defaault Soil/Soliid /Liquid Paartition Coefefficients, Kds, for Four Majajor Soil Typ pes: A Comp pendium, (13) which are listed in Reeference 8. E Europium waas not providedd in Referencce 13 and was w thereforee assigned thhe 75th percentile value from the deefault NUREG//CR-6697 distribution.

d All non-seensitive Kdd parameterss were assigned the m mean determinnistic values for sand fro om Reference 13 as lissted in NUR REG-6697, T Table 3.9-2 (see Table 6-5). The unccertainty anaalysis resultss and the seelected deterrministic vallues for all other parameteers evaluated d are listed inn Table 6-6.

Table 6-4 4 Determ ministic Vallues selected d for Sensitive Kd paraameters used inn to calcula ate Soil DCG GLs Kd in Contaminated Kd in Unssaturated Kd in Saturrated Radionuclidee Zone Zone Zone Cs-137 75th 1460 NS NS NS NS 1

Eu-152 NS NS 75th 7302 NS NS Eu-154 75th 7302 NS NS NS NS Note N 1: NS indiccates non-sensitive parameter 6-17

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 6-5 5 Determ ministic parrameter valu ues selected d for non-sensitive Kd pa arameters foor soil DCG GL calculatioon Radionuclide K (cm3/g)

Kd Radiionuclide Kd (cmm3/g) 1 1 H-3 0.06 Euu-154 825 C-14 5 Euu-1551 825 Fe-55 220 Np Np-237 5 Ni-59 400 Puu-238 550 Ni-63 400 Puu-239 550 Co-60 60 Puu-240 550 Sr-90 15 Puu-241 550 Nb-94 160 Am m-241 19000 Tc-99 0.1 Am m-241 19000 Cs-1377 280 Cm m-243 40000 Eu-1521 825 Cm m-244 40000 Note N 1: Sand Kd ds not listed in NUREG-6607 7 Table 3.9-2 ffor this radionuuclide. The meaan value from NUREG-6697, N Table T 3.9-1 waas used.

Table T 6-6 Soil DCGL Uncertain nty Result aand Determ ministic Valu ues selected for Non-N Nuclide Speccific Param meter Distrib butions Uncertaintty Parameter Selected d Deterministiic Value Result Contaminated d zone erosion rate median 0.0015 Contaminated d zone b param meter median 0.97 Evapotranspiration coefficieent median 0.62 1

Wind Speed median 6.8 Runoff coeffiicient 75th 0.45 Saturated zonne b parameter median 0.97 Well pump in ntake depth median 19.6 b Parameter of o Unsaturated zone median 0.97 Mass loadingg for inhalation n median 2.35E-055 Indoor dust fiiltration factor median 0.55 External gam mma shielding factor f 75th 0.4 Well Pumpin ng Rate median 986.1 Depth of Soill Mixing Layerr 25th 0.15 6.9. Soil Determiinistic Analy ysis and Soiil DCGLs The soil DCGLs weere calculated using the parameter sset providedd in Attachm ment 6-1 witth the parameteer distributio ons replaced by the deterrministic valuues listed inn Tables 6-4, 6-5 and 6-66. The Contamin nated Zone FieldF Capacity was also changed froom 0.2 to 0.066 to be coonsistent witth the unsaturatted and saturrated zone. The T full RES SRAD Summ mary Reportt for Soil DC CGLs is provvided electronically with Reference R 8. The T Soil DC CGLs for thee Initial Suitee are listed inn Table 6-7.

6-18

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 6.10. Basement B Fill Conceptu ual Model The BFM M is used to calculate do ose to the ind dustrial workker AMCG ffrom residuaal radioactivvity in the backffilled basem ments to remain after liceense terminaation. A genneral descripption of the BFM conceptu ual model waas provided in section 6.5.1. 6 This seection describes the connceptual moddel in more dettail including g assumed physical p connfiguration, ggeohydrologgy, source-teerm and exposure pathwayss. The computational mo odel is described in sectiions 6.11 andd 6.12.

The BFM M conceptuaal model assu umes that alll structures are removedd to a depth of three feeet bgs (639 foott), i.e., to an elevation off 636 foot, anda then backkfilled. Thee average waater table deppth is 20 feet bgs b at 619 fo oot elevation n (1) which defines d the bbeginning off the saturated zone. Thhe site groundw water is in direct d commmunication with w the Mi ssissippi rivver resultingg in river ddriven seasonal groundwateer fluctuation n. Based on n direct obseervation of w water ingresss into the P Piping and Venttilation Tunn nels, the seaasonal fluctu uation can reesult in wateer rising up to 10 feet aabove the averaage water taable level, i.e.,i 6 foot eleevation. An onsite wateer supply w to the 629 well is assumed to be installled in the saaturated zon ne below thee 619 foot avverage wateer table elevaation.

The seasonal water fluctuations f result in flu ushing of waater into andd out of the unsaturated zone above 61 19 foot and contacting backfilled b sttructure surffaces. Note that the Reactor Buildiing is somewhaat of an exceeption in thaat a portion of o building iss below 6199 foot and is assumed to be in in the satturated zone (see Figure 6-6).

Table 6-7 7 LACB BWR Soil D DCGLs for IInitial Suite Radionuclid R des Radionuclidee Soil DCGL (pCi/gg)

H-3 5.352E+06 C-14 6.768E+06 Fe-55 1.019E+07 Ni-59 2.599E+07 Co-60 1.281E+01 Ni-63 9.495E+06 Sr-90 6.577E+03 Nb-94 2.018E+01 Tc-99 2.008E+03 Cs-137 5.811E+01 Eu-152 2.844E+01 Eu-154 2.635E+01 Eu-155 1.122E+03 Pu-238 1.693E+03 Pu-239 1.523E+03 Pu-240 1.525E+03 Pu-241 3.691E+04 Am-241 1.105E+03 Am-243 1.872E+02 Cm-243 2.892E+02 Cm-244 2.720E+03 The BFM M includes tw wo scenarios; Insitu and d Excavationn. The BFM Insitu scenaario includes two exposuree pathways; ingestion of o drinking water from an onsite w well and diirect exposuure to drilling spoils s that arre assumed to t be brough ht to the surrface during the installattion of the oonsite 6-19

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 well. Thee BFM Excaavation scen nario assumees large scalle industrial excavation of some or all of the backffilled concreete and spreaading the con ncrete over a 1 m layer oon the grounnd surface.

6.10.1. Source Term m The sourrce term fo or the BFM is the totaal inventory of residuall radioactivity remaininng in Basemen nt End Staate at the time of license term mination. LT TP Chapterr 2 providess the characterrization dataa for the bassements thatt will remainn. The dimeensions and surface areaas are providedd in Referencce 8. The exp pected sourcce term confiigurations annd activity leevels projectted to remain in n each basem ment are sum mmarized bellow.

6.10.1.1. Reactor Building The Reacctor Building g is a right circular c cylin nder with a hhemisphericcal dome andd semi-ellipssoidal bottom. ItI has an ov verall internal height off 144 feet annd an insidee diameter oof 60 feet, aand it extends 262 feet 6 incches below gradeg level. The steel shhell thicknesss is 1.16 incch, except foor the upper heemispherical dome, whicch is 0.60 in nch thick. T The lowest ffloor elevatioon is at 6122 foot elevationn.

The totall wall/floor surface areaa in the porttion of the bbuilding to bbe backfilledd, i.e., below w 636 foot elev vation, is 512 2 m2. The su urface area below the 6619 foot aveerage water ttable elevatiion is 363 m2. Remediation plans calll for all bellow grade cconcrete inteerior to the steel liner to be removed exposing th he steel linerr. Subsequen nt to interior concrete rem moval, the rremaining poortion of the steeel liner willl be removed d. The remaaining structuural concrette outside thee liner and bbelow the 636 foot f elevatio on will remaain. The rem maining conccrete bowl sits on an external suupport structure comprised of a concrette pile cap and a piles. Thhe pile cap and piles weere isolated from reactor operations by y the interiorr concrete, th he steel linerr and the extterior concreete bowl. There is no eviden nce of contaamination leaakage beyon nd the steel lliner or the concrete bow wl exterior tto the liner. Thherefore the pile p cap and d piles are coonsidered to bbe non-impaacted areas.

Six 1.27 cm thick corre slices werre collected from the surrface downw ward and shippped to an ooffsite laboratorry for analyssis. The corees were colleected from bbiased locatiions as indiccated by elevvated survey measuremen m nts and reprresent the areas expeccted to conntain the hhighest levels of contamin nation. As sh hown in Tab ble 6-3, Cs--137 is the ppredominatee radionuclidde at 88% oof the radionuclide mixturee. The Cs-137 results fro om the six coores ranged ffrom 66 pCii/g to 7,500 ppCi/g with an average a of 1,,903 pCi/g.

There is no indicatio on that contaamination is present in thhe concrete tto remain affter the steell liner is remov ved therefore no cores were colleccted from thhe concrete outside thee steel linerr. In addition, general clleanup of loose l contammination onn the steel liner (conccrete dust) after demolitio on and remo oval of the in nternal conccrete is expeected for opeerational raddiation proteection purposes before the steels liner iss removed. This T reducess the alreadyy low potentiial for transffer of activity in i contaminaated dust fro om the steell liner to thee underlyingg concrete duduring removval of the liner. Therefore, minimal m souurce term is expected e in tthe Reactor Building Ennd State.

6.10.1.2. Wastee Treatment Building The WTB B contained facilities an nd equipmen nt for decontaamination annd the collecction, processsing, storage, and a disposall of low leveel solid radio oactive wastte. The sizee of the WTB B floor to reemain 6-20

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 below 63 36 foot elevaation is small at 36.9 m2 with a totaal wall and ffloor surfacee area of 1022 m2.

The WTB B basement floor is at ellevation 630 0 feet. A smaall sump is ppresent withh a floor elevvation of 626 feeet.

Concretee cores were collected att biased locaations as indiicated by eleevated surveey measurem ments.

The Cs-1 137 concentrrations in thee first core slices (0 - 1.227 cm) of thhe three cores analyzed bby the offsite laaboratory ran nged from 12 240 pCi/g to o 25,400 pCii/g with an aaverage of 122,003 pCi/g. The Cs-137 concentration c ns in the tw wo core slicces from 1.227cm - 2.544 cm were m much lower with values th hat were approximately 1% of those found in thhe 0 - 1.27 cm m slices. Thhe majority oof the source teerm is expectted to be on the floor as opposed to w walls.

Decontam mination will w be reqquired to meet m the uunrestricted use criteria. The iinitial decontam mination threeshold is the open air demolition d ccriteria of 2 mR/hr per EnergySoluutions Technicaal Support Document D RSS-TD-31319 96-005, La C Crosse Openn Air Demollition Limits (14).

This equ uates to approximately 10,000 pCi/g Cs-137 assuuming that ccontaminatioon is presennt in a 1.27 cm thick uniforrm layer. Although the biased charaacterization samples likkely identifieed the approxim mate maximu um concentrrations, the full f areal exttent and conncentrations of contaminnation remainin ng after rem mediation to o the open air demoliition criteriaa will not be known until remediation is complleted.

6.10.1.3. Wastee Gas Tank Vault V

The WG GTV is a 29 foot by 31 foot f undergrround concreete structuree with 14 feeet high walls and 2 feet thiick floors, walls, w and ceiiling located d 3 feet bgs jjust outside of the WTB B. The gas ddecay system routed r mainn condenseer gases th hrough varioous componnents for ddrying, filteering, recombin ning, monito oring and ho oldup for deecay in the WGTV. Thhe vault flooor is at 621 foot elevation n. A small su ump is presen nt that exten nds to 618 fooot elevationn.

Concretee cores were not collected from the WGTV W due tto access resstrictions andd low expecttation of signifficant contam mination. Ho owever, 10 CFR Part 661 samples collected frrom liquid in the WGTV and a WTB su umps can be used to prov vide a very rrough estimaate of potentiial contaminnation levels in the WGTV.. The most recent samples from the sumps indiccate Cs-137 concentratioons of 0.547 µC Ci/L and 0.00215 µCi/L for the WTB and WGT TV, respectiively. By sim mple ratio oof the concentraations in thee sump liquid, the contaamination levvels in the W WGTV could be in the rrange of 4% off the contam mination leveels in the WT TB. Additioonal surveyss and/or coree samples w will be collected d from the WGTV W as a part p of contiinuing charaacterization aafter all tankks and equippment is removed to provid de a better esstimate of co ontaminationn levels to ssupport remeediation plannning and FRS classificatio on.

6.10.1.4. Remaaining Structu ures The Rem maining Strructures category inclu udes the Pipping and V Ventilation Tunnel, Reeactor Plant/Gen nerator Plan nt area, a one foot thick remnant off the four fooot thick Chiimney founddation slab, a smmall sump inn the Turbinee Building an nd a small pit in the Turrbine Buildinng.

Three concrete core samples werre collected from the Pipping and Venntilation Tunnnel. The Css-137 concentraations in thee three coress ranged from m 10 pCi/g tto 20 pCi/g with an average of 15 ppCi/g.

The activ vity was idenntified in thee core slice from 0-1.277 cm. Minim mal activity nnear or below w the MDC waas found in th he slice from m 1.27-2.54 cm.c 6-21

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Cores weere not collected in thee Reactor Pllant/Ventilattion Plant aarea or the T Turbine Buiilding sump and d pit due to the t low expeectation of siignificant coontaminationn being preseent and theirr very small areas. Additio onal concrette cores an nd/or dose rrate surveyss will be pperformed dduring continuin ng characteriization in theese areas to support FRS S classificatiion and plannning.

The remn nant of the Chimney fo oundation sllab has a veery low poteential of beiing contaminnated because it i is the lowest one foot portion of a solid four ffoot slab. Thhe top surfacce of the exiisting four foott thick foun ndation slab is expected d to containn minimal ccontaminatioon levels and the potential for contamiination to miigrate three feet f into the solid concreete slab is veery low.

6.10.2. BFM B Exposu ure Pathway ys The BFM M includes two t exposurre scenarios, Insitu and Excavation.. As discusssed in sectioon 6.4 the reasonably foresseeable futu ure land use at the LACBWR site iss industrial aand the AMC CG is thereforee the industriial worker.

The folloowing exposu ure pathway ys are applicaable to the B BFM scenariios:

Direcct exposure tot external raadiation in as left Endd State geometry (negligiible),

Inhallation of airb borne radioacctivity in ass left End S State geomettry (negligible),

Ingesstion of conccrete or fill material m in as left Endd State geom metry (negligiible),

Ingesstion of wateer from onsitte well, Direcct exposure, inhalation dose d and ingeestion dose ffrom contam minated drilliing spoils brougght to the surrface during g installation of the onsitee well into thhe fill materrial, and Direcct exposure, inhalation dose d and ingeestion dose ffrom concrette that is broought to the surface by excavaation.

The agricultural and d gardening pathways are a not appliicable to inddustrial landd use. The m meat, milk, graain and vegettable ingestion pathwayss are therefoore not includded.

6.11. BFMB Insitu Scenario S

6.11.1. BFM B Insitu Groundwat G ter Scenario o The BFM M Insitu gro oundwater (BFM( Insitu ugw) concepptual model is based onn a conservvative screening g approach. One hundred d percent off the inventoory in the bacckfilled baseement concrrete is assumed to release an nd instantly mix with th he fill materiial. RESRAD D is then useed to perform m the dose modeling assum ming that th he source teerm is in thee fill and thhat the strucctures providde no resistance to water flow, i.e., are not present.

The fill volume v into o which the released acttivity mixess is proportiional to the distance thaat the activity moves m from m the concreete surface into i the fill. A portion of the Reacctor Basemeent is below the average waterw table ellevation of 619 6 foot. Miixing is assuumed to occuur over the eentire fill volum me in the Reeactor Basem ment below 619 6 foot beccause the filll is assumedd to be in coontact with watter continuou usly for the full year. With W the exxception of tthree small ssumps with floor elevationns at 618 foo ot, the remaaining End State S basemeent floors arre above 6119 foot elevaation.

The surfaface areas beelow 619 foo ot in the threee sumps arre insignificaant (less thann 1% of thee total 6-22

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 backfilled basement surface areaa) and are in ncluded witth the basem ments above 619 foot foor the purpose of o fill mixingg assumption ns.

The mixiing distancee into the filll after leach hing from flooor and walll surfaces aabove 619 fooot is more unccertain than leaching intto the Reacttor Building fill volumee below 619 foot. Abovee 619 foot, con ntact with water w is the result of peeriodic flushhing from sseasonal waater level risse, or rainwaterr infiltrationn, as opposeed to contin nual contact with waterr in the satuurated zone.. To address this t uncertainty in a man nner consistent with thee screening aapproach useed to develoop the BFM co onceptual model, m a siimple sensittivity analyysis was coonducted too determinee the dependen nce of dosee on the miixing distance. The m mixing volum me sensitiviity calculation is provided d in Referencce 8.

The fill mixing m distances evaluatted ranged from fr 2.54 cmm to full mixxing throughhout the entirre fill volume. For the Reaactor Buildin ng above 61 19 foot an asssumption oof full mixinng resulted iin the highest dose.

d For th he remaining g basementss the nominnal minimum m mixing ddepth of 2.544 cm resulted in the high T Reactor Building aabove 619 ffoot differedd from the other hest dose. The basementts because the t source term is entirrely on the w walls of a rright circulaar cylinder w which caused th he RESRAD D Length Parrallel to Flow parameterr to be correelated to thee mixing disstance from the walls. This reduced the modeled weell water conncentrations..

Based on n the resultss of the sensitivity anallysis, full m mixing with tthe fill was assumed foor the Reactor Building, B ab bove and beelow 619 foo ot, and a 2.554 cm mixinng distance into the filll was assumed for all otherr basements//structures.

The RES SRAD non-d dispersion grroundwater model is ussed in the B BFM Insitugww assessmennt. An importan nt parameterr is the vertiical flow raate of water through thee unsaturateed zone whiich is typically determined d by the infiiltration ratee as defined by the preccipitation, evvapotranspirration and runo off coefficien nt parameterrs. A differeent approachh to defininng the verticcal flow ratee was required for LACBWR due to o the site groundwater g r being hyddraulically cconnected too the Mississip ppi River anda the resu ulting seasoonal water level fluctuuation into and out of the unsaturatted zone.

The vertiical water flo ow rate is co onservatively modeled iin RESRAD D by assuminng that the annnual rate is deefined by thee distance th hat water reccedes from thhe seasonal high elevatiion of 629 fooot to the 619 foot f average water table elevation (10 ft or 3.05 m m). This seaasonal 3.05 m water elevvation change iss used to conservatively y bound the net flow of water to thee saturated zzone in RESRAD by forcin ng the infilttration rate tot be 3.05 m/y.

m See Eqquation 1 annd correspoonding discuussion below for a descriptio on of the meethod used to o assign a 3.05 m/yr infiiltration rate in RESRAD D.

The use of 3.05 m//yr is conseervative because the seeasonal wateer level flucctuation inccludes periods ofo increase and a decreasee, as well as a horizontaal componennt, that are nnot accountedd for.

Full reso olution of thet actual water w flow pattern durring the seaasonal flucttuations intoo the unsaturatted zone wou uld require detailed d grouundwater traansport and ddispersion m modeling which is not justiffied given the bounding/screening ap pproach usedd to develop the BFM coonceptual moodel.

As listedd in Table 6-1, there are portions of eight structuures that willl be backfillled and remaain at license teermination. Due to diffe ferences in configuration c n and contam mination pootential, the BFM was run separately for f the Reacctor Buildin ng, WTB, W WGTV, and the Remaiining Structtures group.

6-23

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 6.11.1.1. BFM Insitugw Com mputation Model M

RESRAD D was used to t develop DoseD to Sourrce Ratios (D DSRs), withh units of mrrem/yr per ppCi/g, for each radionuclidee in the initial suite. Thee DSRs weree used in conjunction w with calculateed fill concentraations to dettermine BFM M Insitugw DFs. The fill concentratioons were calculated assuuming that a un nit source terrm of 1 pCi total invento ory was pressent in the bbasement conncrete at thee time of licensse terminatioon which was w instantly y released annd mixed w with a volum me of fill thhat is dependen nt on the mixing distancce as discusssed above. T The fill conccentration thhen has units that can be deescribed as pCi/g p p total pCii in concretee. BFM Insittugw DFs, in units of mreem/yr in fill per per mCi total t activity y in concretee, were then calculated bby convertingg pCi to mCi and multipplying the DSR by the pCi//g per mCi value. v Excell spreadsheeet calculationns were usedd to calculatte the BFM Inssitugw DFs ass detailed in Reference 8. 8 6.11.1.2. BFM Insitugw RES SRAD Unceertainty Anallysis for Inittial Suite An unceertainty anallysis was peerformed to select deteerministic R RESRAD paarameters foor the calculatio on of DSRs for the BFM B Insitugw g model. T The processs for determ mining the input parameteers for the BF FM Insitugw RESRAD uncertainty u aanalysis was the same ass that used foor the soil DCGGL uncertain nty analysis (see

( process flowchart inn Figure 6-7)).

The paraameter set deeveloped to perform the soil DCGL L uncertaintyy analysis is applicable tto the BFM Inssitugw analyssis with chan nges to acco ount for the geometries of the backkfilled structtures.

The affeected RESRA AD geometrry parameteers are Coveer Depth, A Area of Conntaminated Z Zone, Thicknesss of Contam minated Zonee, Length Paarallel to Aquuifer Flow, U Unsaturatedd Zone Thickkness, and Fracttion of Contaminated Zo one below th he Water Tabble.

The uncertainty anaalysis was performed p for f five struucture confiigurations; R Reactor Buiilding above 619 foot elev vation, Reaactor Buildin ng below 6619 foot eleevation, WT TB, WTGV,, and Remainin ng Structures resulting in n five separaate uncertainnty analyses. The param meters used foor the five BFMM Insitugw uncertainty u analyses a are listed in AAttachment 66-2. The parrameters listed as Variablee in Attach hment 6-2 werew assigneed the valuess shown in Table 6-8 ffor the respeective structures.

The selecction of the Precipitation P n, Evapotran nspiration Raate, and Runnoff Coefficient parameteers in the BFMM Insitugw RE ESRAD mod del requires additional a exxplanation. AAs discussedd above, the BFM Insitugw conceptual model m assummes that thee onsite grouundwater iss in communnication witth the Mississipppi river andd fluctuates seasonally into the unsaaturated zonne. River stagge measurem ments indicate fluctuations f that are up to five feet higher than the averagee site water ttable elevation of 619 foott. However, the river stage s n preciselyy represent site water table levelss. For does not example,, it is known n that water level season nally rises too an elevatioon sufficienttly high for wwater to be obsserved in thee Piping and d Ventilation n Tunnels wiith a floor at 629 foot elevation whiich is 10 feet (3 3.05 m) abov ve the averag ge water table elevation..

The seassonal water table rise must m be acccounted for in the concceptual moddel for the BFM Insitugw dose assesssment but does not precisely p fit the RESR RAD grounddwater moddeling approachh. The season nal water risse was addreessed by assuuming that tthe boundaryy of the satuurated and unsaaturated zonee is the averaage water tab ble elevationn of 619 fooot. The seasoonal 3.05 m w water rise abovve the 619 fooot results in n water perio odically enteering backfiilled structurres that are iin the unsaturatted zone.

6-24

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 6-8 Deterrministic Geeometry RE ESRAD Paraameters useed in the Un ncertainty Analy ysis for the five f BFM In nsitugw Configurations Parameter Rx R Building Rx Buildinng WTB B WGTV Remainingg Above A 619 Below 6199 Structuress Cover Depth (m) 0.91 6.10 2.72 5.46 2.4 Areaa of Contaminaated Zone 262.68 182.41 101.900 460.04 667.26 (m2)

Thicckness of Contaaminated 5.18 0.75 0.02544 0.0254 0.0254 zonee (m)

Leng gth Parallel to Aquifer A

18.29 15.24 6.10 9.75 38.10 Floww (m)

Unsaaturated Zone 1E-10 0 3.35 0.61 3.67 Thicckness (m)

Fraction of contam minated 0 1 0 0 0 zonee below the watter table The effecct of the 3.0 05 m seasonaal flushing heighth is acccounted for iin the BFM Insitugw sceenario by conseervatively asssuming thatt the distancce that the w water recedess after the sseasonal (3.005 m) rise repreesents a constant infiltraation rate of 3.05 m/yr. T This is conseervative relaative to the aactual precipitattion driven infiltration i rate r at the LA ACBWR sitte which is 00.25 m/yr (ass calculated from precipitattion, evapotranspiration n and runoff coefficiennt in the S Soil DCGL parameter set).

Maximizzing the infi filtration ratee maximizes the well water conceentrations foor all signifficant radionuclides when the t non-dispeersion groun ndwater moddel is selecteed in RESRA AD.

To forcee RESRAD to use a 3.0 05 m/yr infiiltration ratee, the precippitation paraameter is used to representt the infiltrattion rate dirrectly by asssigning 3.05 m/yr to thee precipitatioon parameteer and setting thhe Evapotran nspiration Raate and Runo off Coefficieent parameteers to zero. F From Equatiion 6-1 in Refference 12, it i is seen thaat this will result r in an iinfiltration rrate equal to the precipittation parameteer.

Equation n 6-1 1 1 Where:

W I = In nfiltration Raate (m/yr)

E = Ev vapotranspirration Coeffi ficient (dimensionless)

R = Runoff R Coeffficient (dimeensionless)

P = Prrecipitation Rate R (m/yr)

The distrribution evalluated in thee sensitivity analysis wass a uniform distribution with a miniimum value of 0.25 m/yr (the ( actual precipitation p driven infilltration rate at the site) and a maxiimum value of 3.05 m/yr seelected to rep present the seasonal s watter table flucctuation.

Consisten nt with NUR REG-1757 guidance, g thee uncertaintyy analysis w was perform med assumingg that the initiaal suite radion nuclides are present at th heir mixturee fractions ass listed in Taable 6-3. Onlly the radionuclides that were w greaterr than 0.1% % of the mixxture were included inn the uncerttainty analysis. This limitaation was necessary to result in prractical RES SRAD run times. How wever, 6-25

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 including g all radionu uclides with greater than n 0.1% of thhe mixture fraction proovides confiddence that all seensitive paraameters will be identifiedd.

The RES SRAD Uncerrtainty Reports are proviided electronnically with Reference 8. Tables 6-99 to 6-14 proviide summarries of the uncertainty y analysis rresults withh the selectted determinnistic parameteers. Table 6-9 9 provides thhe results for the non-raddionuclide sspecific parameters. Tablles 6-10 to 6-14 provide th he radionucliide specific KdK results foor each of thhe basementss evaluated.

The paraameter distrib butions for th he site-speciific soil typee of sand fromm Referencee 14 were ussed to generate the median,, 25th and 75 5th percentile determinisstic values. N Reference 14 does Note that R th h

not contain values for Europiu um; the 25 percentile from the N NUREG-66997 Kd param meter distributiion was used d.

The majjority of th he uncertain nty analysis results thaat were sennsitive indiccated a neggative correlatioon between Kd and do ose (i.e., 300 of the 344 sensitive parameters were negattively correlated). The parameters with w positive correlatioons were onnly slightly above the 0.25 threshold d and each occurred in only one of o the three uncertainty runs. The ppredominannce of negative correlation with Kd waas expected since s the priimary dose ppathway in tthe BFM Inssitugw scenario is through th he ingestion of well water and lowerr Kd values result in a ggreater percenntage of radioaactivity in thee water phasse at equilibrrium. Thereffore, the deteerministic KKd values sellected for the non-sensitive n e radionucliides that weere includedd in the unccertainty annalysis weree also conservaatively assign ned the 25th percentile values v from R Reference 14. The 75thh percentiles were assigned as indicated d by the PRC CC results ini order to fofollow the paarameter sellection proceess in Figure 6-7 but this will have a very minorr, if any, efffect on dosee since the parameters were shown to o be only slig ghtly sensitiv ve.

The Kd values v selectted for the very v low abu undance (<0 .1%) initial suite radionnuclides that were not incluuded in the uncertainty u analysis weere also assiggned the 255th percentilee values for sand listed in Reference R 14. Using thee 25th percen ntiles for all initial suite radionuclidees is conservvative and prov vides consisteency in deteermining the insignificannt dose contrributors and the dose fraaction attributabble to the remmoved radionuclides.

6.11.1.3. BFM Insitugw RES SRAD Deterrministic Annalysis and D DSR Resultss As discussed above, the BFM Insitugw RESR RAD dose asssessments w were perform med separatelly for the Reacctor Buildin ng (above and below 619 elevaation), WTB B, WGTV and Remaaining Structurees. The param meters proviided in Attacchment 6-2 w were appliedd to all five analyses witth the determin nistic values in Tables 6-8 replacing the t variablee parameterrs and the vaalues in Tablles 6-9 to 6-144 replacing th he parameterr distribution ns. The Conntaminated Z Zone Field CCapacity wass also changed from 0.2 to 0.066 to be consistent c with w the unsaaturated and saturated zoone.

The RES SRAD Uncerrtainty Repo orts are prov vided electroonically withh Reference 8. The resuulting DSRs aree provided in n Table 6-155.

6.11.1.4. BFM Insitugw Dosse Factors The BFM M Insitugw DFs were calcculated by ExcelE spreadssheet in Refference 8. Thhe resulting BFM Insitugw DFs D are listeed in Table 6-16.

6 Note thhat the DFs for the Reacctor Buildingg Above 6199 foot and Belo ow 619 foott were summ med in Refeerence 8 to determine tthe Reactor Building DFs in Table6-16.

6-26

La Croosse Boiling Waater Reactor Licensse Termination Plan P Revisiion 0 Table 6--9 Results of o RESRAD Un ncertainty Ana alysis for BFM InsituI gw and S Selected Determ ministic Parameeters Reactor Reaactor Remaaining Paraameter Building Buillding WTB WGTV Strucctures Above 619 9 Beloww 619 Percentile Va alue Percentilee Value Percentile Value Percentile Vallue Percentile Value th th th th Cover Erosion Rate R 75 0.0 0029 75 0.0029 75 0.0029 median 0.00015 75 0.0029 Contaminated zone z erosion rate median 0.0 0015 75th 0.0029 mediian 0.0015 median 0.00015 median 0.0015 Contaminated zone z b parameter median 0.9 97 median 0.97 mediian 0.97 median 0.977 median 0.97 Wind Speed (N Note 3) 25th 3.3 3 median 6.8 75th 10.2 median 6.8 75th 10.2 Precipitation Note 4 3.0 05 Note 4 3.05 Note 1 3.05 Note 1 3.055 Note 1 3.05 Saturated zone b parameter median 0.9 97 median 0.97 mediian 0.97 25th 0.844 median 0.97 Well pump intaake depth Note 2 6.0 08 Note 2 6.08 Note 2 6.08 Note 2 6.088 Note 2 6.08 th Well Pumping RateR median 9866.1 median 986.1 mediian 986.1 median 9866.1 75 1311.2 Unsaturated zon ne b parameter median 0.9 97 median 0.97 mediian 0.97 median 0.977 median 0.97 Mass loading fo or inhalation median 2.3 35E-5 median 2.35E- mediian 2.35E-5 median 2.355E-5 median 2.35E-5 5

Indoor dust filtrration factor median 0.5 55 25th 0.35 mediian 0.55 median 0.555 median 0.55 External gammaa shielding factor median 0.2 27 median 0.27 mediian 0.27 median 0.277 median 0.27 Depth of Soil Mixing M Layer median 0.2 23 median 0.23 mediian 0.23 median 0.233 median 0.23 Note 1: Positive correlation with doose. Maximum site--specific value based on seasonal watter rise value (3.05 m) used for conserrvatism and linkage to conceptual modeel.

Note 2: Negativee correlation with dose.

d Minimum sitee-specific value useed for conservatismm Note 3: Site-speccific wind speed daata used (US Army Corps of Engineerrs, Mississippi Riveer Lock and Damn 4, Alma WI, Web address http://ww ww.mvp-wc.usace.army.m mil/projects/Lock4.shtml)

Note 4: The preccipitation parameterr was not sensitive for the Reactor Buuilding Above and Below B 619 foot. Thhe 3.05 m/yr rate w was applied for connsistency with the other basements.

.

6-27

La Crosse Boiling B Wateer Reactor License Terrmination Plaan Revision 0 Table 6-10 BFM B Insitugw g Rx Buildiing above 61 19: Uncertaainty Analyssis Results fo or Distributtion Coefficients (Kd)

Rad dionuclide Kd K in Contamminated Zone Kd in Unsaaturated Zonee Kd in Satu urated Zone H-33 25th 0.05 NS 0.05 NS 0.05 C-114 NS 1.8 25th 1.8 NS 1.8 Fe--55 NS 38 NS 38 NS 38 Ni--59 NS 147 NS 147 NS 147 Co--60 NS 9 NS 9 NS 9 Ni--63 NS 147 NS 147 NS 147 Sr-990 25th 5 NS 5 25th 5 Cs--137 25th 50 NS 50 25th 50 Eu--152 NS 95 NS 95 NS 95 Eu--154 75th 7302 NS 95 NS 95 Pu--241 NS 173 NS 173 NS 173 Table 6-11 BFM B Insitugw g Rx Buildiing below 61 19 Uncertaiinty Analysiis Results fo or Distributtion Coefficients (Kd)

Raddionuclide Kd K in Contamiinated Zone Kd in Unsatuurated Zone Kd in Satu urated Zone H-33 NS 0.05 NA NA NS 0.05 C-14 NS 1.8 NA NA NS 1.8 Fe-555 NS 38 NA NA NS 38 Ni-559 NS 147 NA NA NS 147 Co-60 NS 9 NA NA NS 9 Ni-663 NS 147 NA NA NS 147 Sr-9 90 25th 5 NA NA 25th 5 Cs-137 25th 50 NA NA 25th 50 Eu-152 NS 95 NA NA NS 95 Eu-154 NS 95 NA NA NS 95 Pu-2241 NS 173 NA NA NS 173 6-28

La Crosse Boiling B Wateer Reactor License Terrmination Plaan Revision 0 Table T 6-12 BFM Insitugw WTB Uncertaainty Analyysis Results ffor Distriibution Coeefficients (K Kd)

Raddionuclide Kd K in Contamiinated Zone Kd in Unsatturated Zone Kd in Saturrated Zone H-3 NS 0.05 NS 0.05 NS 0.05 C-144 NS 1.8 NS 1.8 NS 1.8 Fe-5 55 NS 38 NS 38 NS 38 Ni-5 59 NS 147 NS 147 25th 147 Co-660 NS 9 NS 9 NS 9 Ni-6 63 NS 147 NS 147 NS 147 Sr-90 25th 5 25th 5 25th 5 Cs-1 137 NS 50 25th 50 25th 50 Eu-1152 NS 95 NS 95 NS 95 Eu-1154 NS 95 NS 95 NS 95 Pu-2 241 NS 173 NS 173 NS 173 Table T 6-13 BFM Insitugw WGTV Uncerrtainty Anaalysis Resultts for Distriibution Coeefficients (K Kd)

Raddionuclide Kd K in Contam minated Zone Kd in Unsatturated Zone Kd in Satu urated Zone H-3 3 NS 0.05 75th 0.09 NS 0.05 C-1 14 NS 1.8 NS 1.8 NS 1.8 Fe-55 NS 38 75th 1279 NS 38 th Ni-59 NS 147 75 1110 NS 147 th Co--60 NS 9 NS 9 25 9 th Ni-63 25th 147 NS 147 75 1110 Sr-9 90 25th 5 25th 5 25th 5 Cs-137 NS 50 25th 50 25th 50 Eu--152 NS 95 NS 95 NS 95 th Eu--154 25 95 NS 95 NS 95 Pu-241 NS 173 NS 173 NS 173 6-29

La Crosse Boiling B Wateer Reactor License Terrmination Plaan Revision 0 Tabble 6-14 BFM B Insitugw g Remainin ng Structurees Uncertain nty Analysis Results fo or Distributtion Coefficients (Kd)

Radiionuclide Kd in Contam minated Zone Kd in Unsaaturated Zonee Kd in Satu urated Zone H-3 NS 0.05 NS 0.05 NS 0.05 C-144 NS 1.8 NS 1.8 NS 1.8 Fe-555 NS 38 75th , 25th 38 NS 38 (Note 1)

Ni-599 NS 147 NS 147 NS 147 Co-60 NS 9 NS 9 25th 9 Ni-633 NS 147 NS 147 NS 147 Sr-90 0 NS 5 25th 5 25th 5 Cs-1337 NS 50 25th 50 25th 50 Eu-152 NS 95 NS 95 NS 95 Eu-154 NS 95 NS 95 NS 95 th Pu-2441 NS 173 NS 173 25 173 Note 1: Inconssistent uncertaiinty results witth PRCC valuees only slightlyy above 0.25 crriteria. 25th perrcentile value was used.

6-30

La Croosse Boiling Waater Reactor Licensse Termination Plan P

Revisiion 0 Table 6-15 BFM B Insitugw DSRs D for Reacttor Building, WTB, W WGTV, aand Remainingg Structures R

Remaining WTB B WG GTV Rx Building Rx Buildin ng S Structure Excavation n Dose Excavaation Dose Above 619' Below 619 9' Excaavation Dose Radionuclide Factoor Faactor (mrem/yr per (mrem/yr per Factor (mrem/yrr per (mremm/yr per pCi/g) pCi/g) (mrem/yr per pCi/gg) pC Ci/g) pCi/g)

H-3 3.51E-03 7.13E-04 7.16E-06 1.233E-05 44.62E-05 C-14 1.94E-02 2.26E-02 1.99E-04 2.933E-04 11.26E-03 Fe-55 6.14E-05 5.65E-04 7.61E-13 0.000E+00 11.53E-13 Ni-59 2.65E-05 5.75E-05 2.11E-06 2.155E-06 22.18E-06 Co-60 4.15E-02 1.10E-01 2.95E-04 2.411E-03 44.05E-04 Ni-63 6.01E-05 1.58E-04 9.26E-07 5.266E-07 77.82E-07 Sr-90 5.26E-01 1.13E+00 1.30E-02 2.200E-02 33.47E-02 Nb-94 8.77E-02 6.42E-03 2.32E-04 2.400E-04 22.43E-04 Tc-99 8.22E-02 1.64E-02 1.10E-04 2.499E-04 77.82E-04 Cs-137 1.48E-02 3.97E-02 1.84E-04 9.588E-04 11.53E-04 Eu-152 5.12E-04 2.67E-03 1.61E-08 1.688E-05 77.17E-09 Eu-154 7.30E-06 3.88E-03 1.62E-10 9.199E-06 44.50E-11 Eu-155 4.35E-05 6.03E-04 4.51E-16 1.722E-07 44.49E-17 Pu-238 2.65E-01 7.42E-01 2.33E-03 1.644E-02 11.85E-03 Pu-239 3.79E-01 8.24E-01 3.00E-02 3.088E-02 33.09E-02 Pu-240 3.78E-01 8.24E-01 2.93E-02 3.066E-02 33.00E-02 Pu-241 6.33E-03 1.59E-02 1.32E-04 3.588E-04 22.02E-04 Am-241 1.86E-01 4.46E-01 6.34E-03 1.355E-02 55.83E-03 Am-243 2.22E-01 4.44E-01 1.55E-02 1.644E-02 11.57E-02 Cm-243 5.35E-03 1.14E-01 9.04E-06 1.377E-05 77.79E-05 Cm-244 3.02E-03 9.08E-02 2.91E-05 4.366E-05 33.13E-05 6-31

La Crosse Boiling B Wateer Reactor License Terrmination Plaan Revision 0 Tablee 6-16 BFFM Insitugw Dose Factoors WTB Remaining Rx Building WGTV V BFM M Insitugw DF Sttructures BFM Insitugw g DF BFM Insitu ugw DF Raadionuclide Do ose Factor BFM M Insitugw DF (mrem/yr per p (mrem/yr per (mrrem/yr per (mrrem/yr per mCi) mCi) mCi) mCi)

H-33 4.44E-03 3 1.57E-03 1 6.00E-004 11.55E-03 C-114 1.02E-01 1 4.36E-02 4 1.43E-002 44.21E-02 Fe--55 2.37E-03 3 1.67E-10 1 0.00E+000 55.12E-12 Ni--59 2.50E-04 4 4.63E-04 4 1.04E-004 77.29E-05 Co--60 4.74E-01 1 6.48E-02 6 1.17E-001 11.36E-02 Ni--63 6.80E-04 4 2.03E-04 2 2.56E-005 22.62E-05 Sr-990 4.91E+000 2.85E+00 1.07E+000 11.16E+00 Nb--94 6.36E-02 2 5.10E-02 5 1.17E-002 88.14E-03 Tc--99 1.03E-01 1 2.42E-02 2 1.21E-002 22.62E-02 Cs--137 1.71E-01 1 4.05E-02 4 4.66E-002 55.14E-03 Eu--152 1.13E-02 2 3.54E-06 3 8.18E-004 22.40E-07 Eu--154 1.61E-02 2 3.55E-08 3 4.47E-004 11.51E-09 Eu--155 2.52E-03 3 9.91E-14 9 8.37E-006 11.51E-15 Pu--238 3.20E+000 5.10E-01 5 7.97E-001 66.21E-02 Pu--239 3.59E+000 6.59E+00 1.50E+000 11.04E+00 Pu--240 3.58E+000 6.44E+00 1.49E+000 11.00E+00 Pu--241 6.88E-02 2 2.90E-02 2 1.74E-002 66.78E-03 Amm-241 1.93E+000 1.39E+00 6.57E-001 11.95E-01 Amm-243 1.94E+000 3.40E+00 7.98E-001 55.27E-01 Cmm-243 4.74E-01 1 1.98E-03 1 6.67E-004 22.61E-03 Cmm-244 3.79E-01 1 6.40E-03 6 2.12E-003 11.05E-03 6-32

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 6.11.2. BFM B Insitu Drilling D Spooils Scenario and DF C Calculation The BFM M Insitu Driilling Spoilss (BFM Insiituds) scenarrio addresses one of thee BFM exposure pathwayss listed in seection 1. Th he dose from m residual raadioactivity iin the concreete is assum med to be broug ght to the surrface during the installattion of a welll that randoomly hits bacckfilled strucctural concrete.. The drillerr is assumeed to be unaaware that tthe backfilled structuree is present.. The residual radioactivity y in the conncrete surfacces is broughht to the surrface with thhe drilling sspoils which in ncludes the fill f material above the sttructure flooor. The sourcce term for the BFM Innsituds scenario is the resid dual radioacttivity remain ning in conncrete at the time of liccense terminnation assuming g no decay or release to t the fill. The T BFM Innsituds DFs are calculatted with uniits of mrem/yr per total mC Ci.

There aree a number of o ways that installers haandle and disspose of drillling spoils, including thhe use of slurry pits, tanks, and dumping g the drillingg spoils on tthe existing ssurface soilss. The use oof pits would lik kely involve additional dilution d by refilling r the ppit with the material exccavated durinng its constructtion. As a conservative c e assumption n, no dilutioon of the spooil material is assumed after being bro ought to the surface.

The welll is assumed to be drilled d into the baasement fill ddown to thee concrete flooor where reefusal is met an nd drilling stopped.

s Th he extent of drilling intoo concrete iss assumed too be sufficieent to capture 100 1 percent of the remaaining resid dual radioacttivity in the concrete suurface withiin the borehole area. The volume of spoil s material brought tto the surfacce is calculaated based oon the borehole diameter an nd depth of drilling d whicch is conservvatively assuumed to be the minimum m fill depth of 3 feet in ord der to minimmize the mix xing volume for all basem ments. The concrete annd fill are unifoormly mixed and spread over o a circullar area on thhe ground suurface to a ddepth of 0.155 m.

The dosee from the ciircular area at a the surfacce was calcuulated by RE ESRAD using the surface soil DCGLs and a AFs. The T AFs werre calculated d using the ddeterministicc parameterss applied foor soil DCGLs and the spo oils spread area which h was determ mined to bbe 0.457 m2. The RESRAD Summary y Reports are provided electronically e y with Referrence 8.

The AFss and BFM Insituds DF Fs were calcculated by E Excel spreaddsheet in Reeference 8 uusing RESRAD D results. Thhe BFM Insittuds DFs are listed in Tabble 6-17.

6.12. BFMB Excava ation Scenarrio The BFM M Excavation n scenario asssumes that some or all oof the backffilled structuures are excavvated and the concrete c spreead on the suurface immeediately afterr license terrmination takking no creddit for decay. The T calculattion of allow wable total mCi is drriven by thee baseline llimitation inn the conceptu ual model that the averaage radionucclide concenttrations in thhe concrete after inadveertent mixing during d excavvation will not exceed the surface soil DCGL Ls. The asseessment proovides BFM Exccavation DF Fs in units off mrem/yr peer total mCi.

Due to differences d in n configuratiion and conttamination ppotential, thee BFM Excaavation DFs were calculated separately y for the Reaactor Buildin ng, WTB, W WGTV, and Remaining Structures iin the same manner as was done for thee BFM Insitu u assessmentts.

The BFM M Excavatio on DFs are calculated c byy Excel spreeadsheet in Reference 88. The resultts are listed in Table T 6-18.

6-33

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table T 6-17 BFM Insiitu Drilling Spoils Dosee Factors B

BFM BFM Insiituds In nsituds Radionuclide R Reactoor BFFM Insituds BFM Inssituds Rem maining Buildin ng WTB WGTV V Strructures (mrem/yrr per (mrrem/yr per (mrem/yrr per (m mrem/yr mCi) mCi) mCi)) per mCi)

H-3 7.15E-0 09 7.03E-08 7 3.64E-008 8.002E-09 C-14 1.26E-0 08 1.24E-07 1 6.42E-008 1.441E-08 Fe-55 2.43E-0 09 2.39E-08 2 1.24E-008 2.773E-09 Ni-59 1.38E-0 09 1.36E-08 1 7.01E-009 1.555E-09 Co-60 1.16E-0 01 1.14E+00 1 5.91E-001 1.330E-01 Ni-63 3.50E-0 09 3.45E-08 3 1.78E-008 3.993E-09 Sr-90 2.05E-0 04 2.02E-03 2 1.04E-003 2.330E-04 Nb-94 7.94E-0 02 7.81E-01 7 4.04E-001 8.991E-02 Tc-99 3.10E-0 07 3.05E-06 3 1.58E-006 3.448E-07 Cs-137 2.83E-0 02 2.78E-01 2 1.44E-001 3.117E-02 Eu-152 5.46E-0 02 5.38E-01 5 2.78E-001 6.113E-02 Eu-154 5.81E-0 02 5.72E-01 5 2.96E-001 6.552E-02 Eu-155 2.01E-0 03 1.97E-02 1 1.02E-002 2.225E-03 Pu-238 1.08E-0 04 1.06E-03 1 5.47E-004 1.221E-04 Pu-239 1.19E-0 04 1.17E-03 1 6.04E-004 1.333E-04 Pu-240 1.18E-0 04 1.16E-03 1 6.00E-004 1.332E-04 Pu-241 1.65E-0 05 1.62E-04 1 8.39E-005 1.885E-05 Am-241 6.94E-0 04 6.83E-03 6 3.53E-003 7.779E-04 Am-243 9.57E-0 03 9.41E-02 9 4.87E-002 1.007E-02 Cm-243 5.88E-0 03 5.78E-02 5 2.99E-002 6.660E-03 Cm-244 6.77E-0 05 6.66E-04 6 3.44E-004 7.660E-05 6-34

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 6-18 6 BFMM Excavatioon Dose Factors Remmaining WTB W

Rx Building WGTV Struucture Excaavation Excavation Dose D Excavation D Dose Excaavation Raddionuclide Dosee Factor Factor (mremm/yr F Factor (mremm/yr Dose Factor (mremm/yr per per mCi) per mCi) (mrem m/yr per mCi) m m

mCi)

H-3 3.69E-06 4.8 88E-05 1.63E-05 8.188E-06 C-14 2.92E-06 3.8 86E-05 1.29E-05 6.477E-06 Fe-55 1.94E-06 2.5 56E-05 8.56E-06 4.300E-06 Ni-59 7.60E-07 1.0 01E-05 3.36E-06 1.699E-06 Co-60 1.54E+00 2.04E+01 6.81E+00 3.422E+00 Ni-63 2.08E-06 2.7 75E-05 9.19E-06 4.61E-06 Sr-90 3.00E-03 3.9 97E-02 1.33E-02 6.666E-03 Nb-94 9.79E-01 1.29E+01 4.32E+00 2.177E+00 Tc-99 9.84E-03 1.3 30E-01 4.35E-02 2.188E-02 Cs-137 3.40E-01 4.50E+00 1.50E+00 7.544E-01 Eu-152 E 6.94E-01 9.19E+00 3.07E+00 1.544E+00 Eu-154 E 7.50E-01 9.92E+00 3.31E+00 1.666E+00 Eu-155 E 1.76E-02 2.3 33E-01 7.78E-02 3.900E-02 Pu-238 1.17E-02 1.5 54E-01 5.15E-02 2.599E-02 Pu-239 1.30E-02 1.7 72E-01 5.73E-02 2.888E-02 Pu-240 1.30E-02 1.7 71E-01 5.72E-02 2.877E-02 Pu-241 5.35E-04 7.0 08E-03 2.36E-03 1.199E-03 Am-241 A 1.79E-02 2.3 36E-01 7.90E-02 3.966E-02 Am-243 A 1.06E-01 1.40E+00 4.66E-01 2.344E-01 Cm-243 C 6.83E-02 9.0 03E-01 3.02E-01 1.51E-01 Cm-244 C 7.26E-03 9.6 61E-02 3.21E-02 1.61E-02 6.13. Innsignificantt Dose Contributors and Radionucclides of Con ncern NUREG--1757, sectio on 3.3 statess that radionuuclides conttributing no greater thann 10% of thee dose criterion (i.e., 2.5 mrrem/yr) are considered c to o be insignnificant contrributors. TThe 10% critterion applies to t the sum of o the dose contributions from thee aggregate of radionucclides considdered insignificcant. This seection providdes the assessment of dosse contributiions from thhe initial suitte and identifiess the radionuuclides that can c be design nated as insiignificant doose contributtors.

The radio onuclides reemaining aftter the remo oval of insiggnificant conntributors weere designatted as the ROC. The ROC list is determ mined for co oncrete usingg the BFM D DFs and for ssoil using thhe soil DCGLs. The dose from f the rem moved insign nificant conttributors waas accountedd for by adjuusting the soil DCGLs D and d BFM DFs for the ROC. The inssignificant contributors will be exclluded from furrther detailed evaluation ns during FRSF and dem monstration of compliaance with thhe 25 mrem/yr dose criteriaa.

6-35

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Note that Sr-90 was included in n the ROC list for soil aalthough thee dose contrribution was very low. Assuming the raadionuclide mixture in Table T 6-3, thhe Sr-90 dosse fraction wwas 0.009% oof the 25 mrem m/yr criterionn. When the actual a soil ch haracterizatiion data for the initial suuite radionucclides was used d to calculatee dose perceentages, the Sr-90 dose w was determiined to be 2.06E-02 mreem/yr or 0.053% percent of the 25 mrem/yr m critterion. Sr-900 was incluuded as a soil ROC foor the qualitativ ve reason th hat it was positively p dentified in some concrete samplees not becauuse it id representted a significcant dose fraaction.

6.13.1. Radionuclide R es of Concern and Adju usted Soil D DCGLs and BFM DFs The soil DCGLs an nd BFM DFs were ussed in Refeerence 5 to calculate tthe relative dose contributtions from th he initial suitte radionucliides, identifyy the insigniificant contriibutors, selecct the final ROC Cs and adjusst the ROCs for the dosee percentagee attributablee to the remooved insignifficant contributtor radionucllides.

The dosee percentagees for the iniitial suite radionuclides were calcullated for soiil and for eaach of the threee BFM scenaarios; BFM Insitugw, BF FM Insituds, and BFM E Excavation. The final list of insignificcant contribu utors remov ved was the same for sooil and the B BFM scenarrios but the dose percentag ges attributaable to the in nsignificant contributors c were differrent for eachh. Attachmennt 6-3 contains a copies of Tables 20 and 22 from Reference 5 which provvide the dose percentagees for the initiaal suite and d the dose percentages attributablee to the agggregate of the insignifficant contributtors that werre removed. Two metho ods were ussed for the ccalculation aand the resuults of both are provided in Attachment 6-3. The firrst method ap applied the raadionuclide mixture fracctions in Table 6-3 and the second applied the actuaal concentrattions of charracterizationn results.

The Table 6-3 mixtu ure was bassed on conccrete cores bbut was alsoo applied too soil. Resullts of surface and a subsurfacce soil charaacterization in i the impaccted area surrrounding LA ACBWR inddicate that theree is minimall residual radioactivity in i soil. Bas ed on the chharacterization survey reesults to date, LACBWR does not an nticipate thee presence oof significannt soil contaamination inn any remaininng subsurfacce soil thatt has not yet been ccharacterizedd. Due too the very low concentraations of radionuclidess identified in LACBW WR soil, tthe direct ddeterminatioon of radionuclide mixturee fractions fo or initial suitte radionucliides in soil is not techniccally feasible due to the MDC M biasing g issues disscussed abo ove. Basedd on a geneeralized assuumption thaat the contamin nated water that caused concrete co ontaminationn would be similar to thhe source of soil contamin nation, the ROC R and raddionuclide mixture m derivved for the cooncrete was considered to be reasonably representaative of soilss for FRS planning and iimplementattion.

From Atttachment 6-3 3, it is seen that s and conccrete scenariios, Cs-137, Co-60 and S t for all soil Sr-90 contributte greater than 97.28% of o the total dose.

d Thereefore, the finnal ROCs foor LACBWR R soil and baseement concrrete are Css-137, Co-60 and Sr-9 0. The rremaining rradionuclides are designateed as insigniificant contriibutors and are a eliminateed from furthher detailed evaluation.

The data from high activity a coress that were used u to calcuulate the radiionuclide miixture in Tabble 6-3 is the most m represeentative dataa available. The T most acccurate radionnuclide mixxture fractionns are calculated when the HTD H radionuclides are positively p deetected. If thhe HTD radiionuclides arre not positivelyy detected, then t the mixtture percentages assigneed to the HT TD radionucllides are baseed on the MDC C values whiich is conserrvative. How wever, the acccuracy of thhe mixture ffractions assiigned to HTD D radionucliides using MDC valu ues will deecrease as the total sample acttivity, predomin nately Cs-13 37, decreasess.

6-36

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 The poteential effect of mixture variability v on o dose is coonservativelly accountedd for by appplying the most limiting inssignificant coontributor do ose percentaage from all of the scenaarios evaluatted to the adjusstment of soil DCGLs an nd BFM Do ose Factors ((i.e. 2.179%% as seen in Attachment 6-3).

The dosee percentage ranged from m 0.403% to 2.179%.

The 2.179% value reepresents thee hypotheticaal dose contrribution of thhe insignificcant radionucclides (0.68 mrrem/yr) at th he dose lim mit of 25 mrrem/yr, assuuming that tthe mixture fractions oof the insignificcant contribu utors remainn constant ass activity inccreases. Hoowever, it is unlikely thaat the HTD rad dionuclide cooncentrationns will increaase linearly w with dose upp to 25 mrem m/yr. Basedd on a review of the charactterization daata over a rannge of total aactivity in thhe samples, iit is clear thaat the concentraations of inssignificant contributor c radionuclides r s are below MDC overr a wide rannge of total sam mple activity up to and exceeding a totalt activityy representinng 25 mrem//yr. For exam mple, the maxim mum 2.179% % value wass calculated forf the WTB B Groundwatter scenario.. When the aactual mean acttivity of the selected corre samples iss used the doose calculateed for the W WTB Groundw water scenario is 0.787 mrrem/yr with a correspon nding dose ppercentage aattributed to the insignifficant contributtors of only 0.086% (0.0 021 mrem/yrr) (see Attacchment 6-3).. The realistic expectatiion is that the insignifican nt radionucllides would d remain att their MDC values aas concentraations approach h values corrresponding to 25 mrem/y yr and that thhe insignificcant contribuutor dose fraaction would acctually be clooser to 0.0866% than the 2.179% vallue calculateed using the mixture in T Table 6-3.

As anoth her example,, the concrette core samp ples taken dduring charaacterization tthat represennt the worst casse dose consequences are a from the WTB basem ment. The average totaal activity foor the core sammples taken in the WT TB is 1.2E+ +04 pCi/g. Assuming that the avverage activiity is homogen neously distrributed over the entire suurface of thee WTB basem ment (101.9 m2) to a deppth of 1/2 inch, the t worst caase dose con nsequence wasw 155 mreem/yr for thee WTB Excavation scennario.

(see Attaachment 6-3)). This resullt obviously indicates thhat remediatiion is necesssary but the point is that ev ven in this worst w case scenario, s thee dose basedd on actual ccore concenntrations from m the WTB ressults in an in nsignificant contributor c dose d percenttage of 1.5877% which iss below the w worst case valuue of 2.179%%.

As a co onservative measure, th he most lim miting insignnificant dosse contributoor percentagge of 2.179% (calculated for the Gro oundwater sccenario for the WTB) was used to adjust thee soil DCGLs and a BFM Dose D Factors to account for the insiggnificant conntributor dosse (Referencce 5).

See Tables 6-19 to 6-23 for the adjusted a soil DCGLs andd BFM Dosee Factors. A separate anaalysis of insignificant contrributor dose percent was performed ffor Buried P Pipe. See secction 6-18.

Table 6-19 Soil S DCGLss for ROC A Adjusted forr Insignificaant Contributor C r Dose Fracttion Adjusted S Soil DCGLs ROC (pC Ci/g)

Co-60 1.25EE+01 Sr-90 6.40EE+03 Cs-137 5.65EE+01 6-37

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Tablee 6-20 Reeactor Build ding BFM D DFs for ROC C Adjusted for Inssignificant Contributor C r Dose Fracction Reactor Build ding Adjusted d BFM DFs (mreem/yr per mC Ci)

ROC Insitu I GW Insittu Drilling Spooils Excavation Co-60 4.87E-01 1.19E-01 1.58E+00 Sr-90 5.05E+00 2.11E-04 3.08E-03 Cs-137 C 1.76E-01 2.91E-02 3.50E-01 Tablee 6-21 WT TB BFM DF Fs for ROC C Adjusted ffor Insignifiicant Co ontributor Dose D Fractioon WTB A Adjusted BFM M DFs (mreem/yr per mC Ci)

ROC In nsitu GW Insituu Drilling Spooils Excavation Co-60 6.66E-02 6 1.17E+00 2.10E+01 Sr-90 2.93E+00 2 2.08E-03 4.08E-02 Cs-137 C 4.16E-02 4 2.86E-01 4.63E+00 Tablee 6-22 WG GTV BFM DFs for RO OC Adjusted d for Insign nificant Co ontributor Dose D Fractioon WGTV A Adjusted BFM M DFs (mreem/yr per mC Ci)

ROC In nsitu GW Insituu Drilling Spooils Excavation Co-60 1.20E-01 1 6.08E-01 7.00E+00 Sr-90 1.10E+00 1 1.07E-03 1.37E-02 Cs-137 C 4.79E-02 4 1.48E-01 1.54E+00 Tablee 6-23 Reemaining Structures BF FM DFs forr ROC Adju usted for Inssignificant Contributor C r Dose Fracction Reemaining Stru uctures Adjustted BFM DFs (mreem/yr per mC Ci)

ROC In nsitu GW Insituu Drilling Spooils Excavation Co-60 1.40E-02 1 1.34E-01 3.52E+00 Sr-90 1.19E+00 1 2.36E-04 6.85E-03 Cs-137 C 5.28E-03 5 3.26E-02 7.75E-01 The mixture fraction n for the RO OC and the mixture fraaction for thhe aggregatee of insignifficant contributtors is listed in Table 6-2 24. Note thaat the majoriity of the 0.11013 mixturre fraction foor the insignificcant contribuutors is attribbutable to Ni-63 N (with a fraction off 0.08) whicch has a veryy low dose imppact and was therefore in ncluded in thhe group of innsignificant contributorss.

6-38

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table T 6-24 ROC an nd Insignificcant Radion nuclide Mixturee Fractions ROC Mixture F Fractions Co-60 0.0 122 Sr-90 0.00091 Cs-137 0.87774 Insignificant I

0.10013 Contributors C

Total 1.000 6.14. Concentratio C ons in Excav vated Fill Material M

A check calculation n was perforrmed in Reference 8 too determinee the maxim mum hypothetical concentraations of RO OC in fill material m after excavation. The calcullation assum med that 1000% of the residuual radioactiivity in the concrete c wass instantly reeleased to the fill and unniformly mixxed in the fill du uring basemment concretee excavation n. Therefore,, the source term would be in the filll and not in thee concrete. The calculaation was baased on BFM M DFs that w were the sum mmation of BFM Insitugw + BFM Insittuds + BFM Excavation.. The summaation DF wiill be appliedd during FR RS for complian nce (see LTP P Chapter 5)). For all RO OC and all baasements, thhe hypotheticcal maximum m fill concentraations were less than thee surface soill DCGLs.

6.15. Alternate A Laand Use Scenario Dose As discu ussed in secttion 6.4, tw wo alternate less likely but plausibble land use scenarios were considereed, Resident Gardener with onsitee well and R Recreationall Use with onsite welll. In accordan nce with NU UREG-1757, these less likely l but pllausible scennarios were not analyzeed for complian nce, but werre used to risk-inform r the decision of Industtrial Use as the reasonnably foreseeab ble land usee. NUREG-1757 states that t if the p eak dose froom a less likkely put plauusible scenario is significaant then greeater assuran nce that the s cenario is unnlikely woulld be necessaary.

A quantiitative evalu uation of thee dose from the Recreattional Use sscenario wass not requireed. A simple qu ualitative ev valuation con ncluded thatt the dose thhan the Recreeational Usee scenario w will be less thann the dose from the Indu ustrial Use scenario s becaause the occcupancy timme and well w water intake ratte would be less.

A dose assessment a of o the Resid dent Gardeneer scenario ((with onsite well for drinking water and irrigation n) was perforrmed. The Resident R Garrdener pathw ways includeed direct dose, inhalationn, soil ingestionn and fruit annd vegetablees from an onsite o gardenn. It was connsidered higghly unlikelyy that livestockk would be raaised on the site so the meatm and miilk pathwayss were inactiive. The alteernate scenario dose assessm ment was peerformed forr backfilled cconcrete andd soil sourcee terms. The dose assessmeents included d the ROC att their respecctive mixtur e fractions aas listed in T Table 6-24.

The Resiident Gardeener soil dosse was calcu ulated with the RESRA AD determinnistic param meters used for the Industriial Use soil dose assessment with tthe parameteer changes llisted below. The contamin nated zone thickness t waas changed to more cloosely represent actual ssite conditions as opposed to the 1 m depth d assumeed in the scrreening apprroach used inn the Industrrial scenarioo. The root deptth parameteer was added since the plant pathw way is activve in the Reesident Garddener 6-39

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 scenario. The remain ning parameeter changess are metaboolic and behhavioral (froom NUREG G/CR-5512). The T parameteers changes are: a Contaminated C d Zone Thick kness - 0.15m m, nhalation Raate - 8400 m3/yr, In Fraction of Time Spent In ndoors - 0.64 49, Fraction of Time Spent Outdoors O - 0.124, Fruit, Vegetab ble and Graiin Consumpttion - 112 kgg/yr, Leafy L Vegetaable Consum mption - 21.4, Drinking D Watter Intake - 478 4 L/yr, Depth D of Rooots - 1.22 m.

The assessment of th he soil dose from the Reesident Gardener alternatte scenario w was perform med in two wayss. First, the maximum m so oil concentraations identi fied during ccharacterizaation were ussed to provide thet most acccurate estimaate of dose from f soil in the Residennt Gardener sscenario. Seccond, the altern nate scenarioo dose was calculated assuming a thee ROC conccentrations w were theoretiically equal to o the maxiimum allow wable soil concentratiions in thee Industriall Scenario (i.e.,

concentraations that result r in 25 mrem/yr). The T doses w were calculaated assuminng that a ressident could nott plausibly occupy o the LACBWR L siite until afterr the G-3 plaant ceased ooperation andd was decommiissioned whiich was consservatively assumed a to bbe 30 years after licensee terminationn (see section 6.4).

6 The dosse calculation ns are docum mented in Reeference 8.

The soil dose from the Resident Gardener alternate scennario using tthe maximum m concentraations identifiedd during chaaracterization n as the sou urce term waas 0.66 mreem/yr. Whenn the source term was the hypotheticaal maximum m soil conccentrations tthat could rremain giveen the Induustrial Scenario DCGLs, the dose was 31.4 mrem/y yr. A dose aassessment w was also perrformed usinng the hypothetical maximu um radionucclide concen ntrations in fill materiaal. The fill iis assumed to be excavated and spreaad on the grround surfacce during thhe excavatioon of structuure concretee (see section 6.14).

6 The reesulting dosee from the Resident R Garddener was 266.9 mrem/yrr.

The dosee from back kfilled conccrete was allso calculateed for the R Resident Gaardener Alteernate Scenario assuming the BFM Insitu I geommetry descriibed in secction 6.11.1. The RESRAD determin nistic parameeters used for f the BFM M Insitugw doose assessm ment were m modified as listed above to represent th he Resident Gardener G scenario. The WTB was uused for the assessment since it is projeected to conttain the majoority of residdual radioacttivity at licennse terminattion.

The resu ulting Resideent Gardenerr dose from backfilled cconcrete in the insitu geeometry (i.ee., the as-left coondition at the t time of license term mination) waas 0.94 mrem m/yr. Note tthat the Ressident Gardenerr dose from m the BFM M Insitu scenario is low w because the BFM D DFs appliedd for complian nce during FRSF will bee the summaation of the BFM Insittugw + BFM M Insituds + BFM Excavation (see LTP P Chapter 5) which is do ominated by the Excavaation Scenariio. This resuults in low dosee from the BFMB Insitu scenario.

s Foor example, tthe dose froom the BFM M Insitu geom metry for the WTB in th he Industriaal Use scen nario, assum ming no deecay, is 1.777 mrem/yr.. For comparisson, when th he 30 year deecay period is i included thhe dose is 0..84 mrem/yrr.

6-40

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 The final consideration is the dose d from thhe Resident Gardener allternative sccenario giveen the BFM Ex xcavation Sccenario. Beccause the BFM Excavaation concepptual model is based onn the limitationn that the ex xcavated con ncrete would d not exceedd the surfacee soil DCGL Ls, the maxiimum alternate scenario do ose from exccavated conccrete would be essentially the same as calculateed for soil. Howwever, the doose from con ncrete would d be less sincce plants cannnot be growwn in concrette.

In concluusion, the do ose from thee Recreation nal Use and Resident Gaardener alterrnate scenarios is not signifficant and th herefore greaater assurancce that these scenarios w will not occurr is unnecesssary.

6.16. BFM B Elevateed Area Con nsiderations The BFM M is a mixing g model thatt uses the tottal inventoryy as the sourcce term and is independeent of the conccentration an nd distributiion of the residual r raddioactivity. The standaard approachh for calculatin ng Area Factors (AFs) in n conjunctio on with conccentration-baased DCGLss to determinne the acceptability of elevaated areas off activity doees not apply..

Although h AFs are no ot applicablee to the BFM M, the maxim mum concenntrations thatt could remaain in the Basem ments are limited by the implementtation of thee open air deemolition lim mits describbed in Referencce 14. The Basements will be rem mediated to the open aiir demolitioon limits priior to demolitioon of structuures above 63 36 foot elevaation. The oopen air dem molition limitts are:

Less L than 2 mR/hr m beta-g gamma total surface conttamination oon contact wiith structuraal cooncrete.

L than 1,000 dpm/100cm2 beta-gaamma loose ssurface conttamination.

Less These limmits define the t acceptab ble operation nal levels off fixed (as mmeasured by contact exposure rate) andd removablee contaminattion that can n remain prrior to openn air demolittion. The llimits ensure thhat the dose to the publlic from airb borne contam mination gennerated duriing demolitiion is acceptable. The op pen air demo olition limitts are operaational levells and are nnot a part oof the complian nce calculatioons for 10 CFR C 20.1402 2.

To comp ply with the open air deemolition lim mits, radiologgical surveyys will be peerformed priior to demolitioon. These surveys s willl use conven ntional gammma instrumeents in typiccal scanningg and measurem ment modes.. Scanning coverage c forr pre-remediiation surveyys on structuures prior to open air demo olition could u to 100% of the acccessible surfface area depending onn the d include up contamin nation potenttial. The pree-remediatio on surveys peerformed to prepare buillding surfacees for open airr demolition n will provide confideence that coontaminationn above thee limits wiill be identified d and remediated.

The dosee from a hyp pothetical maaximum con ncentration thhat could rem main after reemediation tto the open air demolition limits was evaluated e ussing the drillling spoils sscenario. Thhe purpose oof the assessmeent was to fu urther risk-iinform the acceptability a y of a worst--case conditiion in the coontext of potenttial dose. Th he Worst-Caase Drilling g Spoils asseessment is cconsidered a less likelyy but

( defined in NUREG--1757, Tablle 5.1). Connsistent withh NUREG 1757, plausiblee scenario (as Table 5.11, the scenarrio is not an nalyzed for compliance c wwith the 10 CFR 20.14002 dose criteerion, but is used to help p risk inforrm and justify the deecision that the hypothhetical maxiimum concentraation that co ould remain in elevated d areas after remediationn to the 2 m mR/hr demoolition limit are acceptable, assuming all activity iss accounted for and inclluded in the final complliance demonstrration using the BFM DF Fs.

6-41

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 The Worrst-Case Driilling Spoils scenario asssumes that the water suupply well iis drilled dirrectly into a spot of resid dual radioacctivity in basement b flooor concrete that conttains the hiighest hypothetical Cs-137 concentratiion. The drilling I assum umed to occuur immediattely after liccense terminatiion taking no o credit for decay.

d The entire invenntory within the drill diam meter is assuumed to be exccavated and brought to the surface while mixinng with overrburden fill and soil. Thhis is very unliikely for two o reasons. First, F the scenario assum mes that a wwater supplyy well is insttalled immediattely after liccense termination. Secon nd, the probaability of an assumed eigght inch borehole hitting an n area contaiining the maaximum hypo othetical conntamination level duringg drilling is low.

From Reeference 8, assuming an n arbitrary circular c areaa with a 366 inch diameeter and uniiform contamin nation througgh the first half h inch of concrete, thee Cs-137 cooncentration that would rresult in 2 mR//hr at contacct is approximately 10,000 pCi/g Css-137. The levels of loose contaminnation have esseentially no effect e on thee dose rate because b the aactivity assoociated with a very thin layer of loose dust is trrivial. For example, e a loose contam mination levvel of 10,0000 dpm/1000 cm2 2

correspon nds to appro oximately 45 5 pCi/cm co ompared to 229,000 pCi/ccm2 total invventory in a 1 cm2 area conntaining unifform radioacctivity throu ugh a half iinch layer aat a concenttration of 100,000 pCi/g.

Also fromm Referencee 8, the Cs-137 concentrration that w would result iin 25 mrem//yr in the Drrilling Spoils sccenario, assuuming one-h half inch con ntamination depth, was approximately 80,000 ppCi/g Cs-137. Therefore, the dose from this less likelly but plauusible scennario wouldd be approximmately 10,000/80,000*25 5 = 3.1 mrem m/yr and is not significaant. Furtherr reduction oof the hypothetical maximu um area of residual rad dioactivity, bbeyond that required foor remediatioon to meet thee 2 mR/hr open air demolitiond limit, is n ot justified on a riskk-informed bbasis.

Demonsttrating comp pliance with h the dose criterion c usinng the total inventory aand BFM D DFs is sufficientt to accountt for the acctivity, and assess a the ddose, in the areas with the hypothetical maximum m concentrattions.

6.17. Soil Area Fa actors The RES SRAD modeeling for so oil assumes that the enntire area w within the LSE, 7500 m2, is contamin nated. Isolatted areas off contaminatiion that are smaller thann 7500 m2 w will have a llower dose for a given con ncentration. The ratio off the dose frrom the full source term m area to the dose from a smmaller area is defined as the Area Faactor (AF).

Referencce 8 calculattes AFs for each e ROC using u RESRA AD with thee determinisstic parameteer set used to calculate c soiil DCGLs. TheT Area of o Contaminnated Zone parameter was varied from 1.0 m2 too 100 m2. Th he need to apply a AFs to o contaminatted areas greeater than 1000 m2 is unliikely.

The AFss were calcu ulated by div viding the pC Ci/g per 25 mrem/yr vaalue from RE ESRAD for each smaller area a by the so oil DCGLs in i Table 6-7.

The full RESRAD R Suummary Rep ports are proovided electrronically witth Referencee 8. The resuulting AFs are provided p in Table T 6-25.

6-42

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Tablee 6-25 Su urface Soil A Area Factorrs Area FFactors Radionuuclide 2 2 1m 2m 5 m2 10m2 100m2 Cs-137 9.44 5.56 3 .07 2.04 1.19 Co-60 9.11 5.42 3 .01 2.00 1.18 Sr-90 11.22 6.66 3 .69 2.45 1.41 6.18. Buried B Pipinng Dose Asseessment and d DCGL Buried piping is defined as below w ground pip pe located ooutside of strructures and basements. This section describes d thee buried pipe dose assesssment methhods and proovides the rresulting DC CGLs.

The calcu ulations are performed byb RESRAD D and Excel sspreadsheet aas detailed inn Reference 8.

6.18.1. Source Term m and Radio onuclide Mixture With the exception of o a portion ofo the Circu ulating Waterr System Pippe, none of the buried ppiping to remain n at LACBW WR was asso ociated withh contaminatted systems and therefoore contaminnation potential is minimal. See Table 6-2 6 for list of o buried pippe to remainn. The High Pressure Seervice Water froom LACBW WR Crib Hou use to G-3 annd Well wateer piping forr Well #3 aree consideredd non-impacted d because th hey only con ntacted cleann river wateer or grounddwater withh no potentiaal for contamin nation and will w continu ue operation n after licennse terminattion. No DC CGLs or FS SS is required for non-imp pacted areas.

DCGLs for buried pipe were calculated for the innitial suite radionuclidees. To datee, no characterrization has been perfo ormed in buried b pipinng due to th the very loww contaminnation potential. The radio onuclide mix xture is asssumed to bee the same as listed inn Table 6-33. As discussedd in LTP Ch hapter 5, if continuing c characterizatiion is perforrmed for buried pipe annd the results in ndicate that the t buried piping p dose could c exceedd 50% of thhe 25 mrem/yyr dose criteerion, then sammples will be analyzed for HTD radio onuclides andd additional assessmentss performed.

6.18.2. Exposure E Scenario and Critical Grroup Consisten nt with the guidance in NUREG-1757, Appeendix J regaarding assesssment of bburied material, two exposu ure scenarioss were considered; 1) innadvertent inntrusion whhich results iin the buried piipe being ex xcavated and d spread acrross the surfface (Excavvation scenarrio), and 2) dose from buried pipe rem maining in sittu (Insitu sceenario).

NUREG--1757, Appeendix J statees that it sho ould be apprropriate to uuse the arithhmetic averaage of the radionuclide conccentration in n the analysis, including any interspeersing cleann soil. The bburied piping att LACBWR is a minimu um of 1 m below b grade.. The LACB BWR buriedd pipe excavvation conceptu ual model is more conserrvative than the NUREG G-1757, Apppendix J connceptual moddel in that no mixing m is asssumed to occcur with thee soil in the 1 m cover oor the intersppersing cleann soil between pipes during g excavationn.

The concceptual mod dels for the buried b pipe Insitu I and EExcavation sscenarios aree similar to those developeed for the BF FM. In the Insitu I scenarrio the residuual radioacttivity on the internal surrfaces of the pippe is assumeed to instanttaneously rellease and miix with a thiin 2.54 cm layer of soil in an 6-43

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 area equaal to the intternal surfacce area of th he pipe. Thee Insitu scennario model assumes thaat the released radioactivity y as a beloow ground 2.54 2 cm layyer of soil w with no creddit taken foor the presence of the pipee to reduce environmen ntal transporrt and migraation. This iis a conservvative assumption, particularly for the Circulating g Water Disccharge Pipe which willl be filled w with a flowable fill materiall. The assum mption of a thin t soil mixxing layer foor buried maaterial was shhown to be con nservative on n the sensitiivity analysiis for the BF FM (see secttion 6.11.1). The Excavvation scenario model assum mes that the released rad dioactivity iss mixed withh a 15 cm laayer of soil oon the ground surface after excavation. A 15 cm mixing m layer is assumed due to the extensive grround surface disturbance d caused c by th he large scalee excavationn required too remove pippe. The Induustrial Worker is i exposed to a Excavateed soil via thhe same pathhways appliccable to the BFM o the Insitu and and soil models.

m 6.18.3. Buried B Pipinng Dose Asseessment RESRAD D modeling was perforrmed to callculate DSR Rs which arre the basis for determ mining 2

DCGLs for f the intern nal surfaces of the pipes after converrting units too dpm/100 cm m.

The burieed piping was separated d into two caategories. Thhe first categgory includeed the summ mation and grou uping of all impacted i burried pipe oth her than the Circulating Water Disccharge Pipingg and is designnated as the Group.

Thhe second caategory cons isted of the Circulating Water Dischharge Pipe only y. The separation of the Circulating Water pipe w was necessaary because tthe geometryy was significan ntly differen nt from the other o pipe annd the pipes are located iin distinctly different paarts of the site.

The Insitu dose calcculation forr the buried piping Grroup (whicch as statedd above does not include the t Circulating Water Discharge D pip pe) was perfformed by R RESRAD moodeling usinng the input parrameters app plied to the BFM B Insitu Groundwater G r scenario w with adjustmeents to the soource term geo ometry (see Table T 6-26). The depth of the buriedd piping varries but is inn all cases grreater than one meter below w the ground d surface in order to be below the ffreeze zone. The elevation of the thin layer (2.54 cm) sourcee term was nominally aassumed to be the sam me as the deeepest basementt floor, i.e..,, the WGTV V at 621 foott elevation. Using a low wer elevatioon maximizees the insitu dose, which is driven by th he groundwaater pathwayy, by minimizzing the disttance to the w water table. Th he assumed RESRAD paarameters A Area of Conntaminated Z Zone and L Length Paralllel to Flow were calculateed assuming g that the all of the pipe in the groupp was locateed in one cirrcular area equaal in size to the t summed internal surface area off all Group piipes.

The insittu dose for the Circulatting Water Discharge D P Pipe was alsso calculatedd using the BFM Insitu Grroundwater parameters p with w the elev vation of thee thin contam minated layeer being set aat the elevation n of the botttom of the pipe (630 foot). f The ccontaminatedd area was set equal to the internal surface s area of the pipe.. See Table 6-26 for thee source term m parameterrs. The dose from the Excaavation scenaarios (and correspondin c ng DCGLs) ffor both thee Buried Pippe Group annd the Circulatin ng Water Discharge D Pipe P were calculated ussing the RE ESRAD parrameters useed to calculate surface soill DCGLs witth source terrm adjustmennts as listed in Table 6-226.

6.18.4. Buried B Pipe DCGLs Initial Suite The RES SRAD Summ mary Report file names for f the RESR RAD Buried Piping runss are listed inn Referencce 8. The fulll RESRAD SummaryS Reeports are stoored electronnically. Thee detailed inpputs 6-44

La Crossse Boiling WaterW Reactorr License Termination T Plan Revision n0 Table 6--26 RESR RAD Sourcce Term Parrameters forr Buried Pip ping DCGL L Calculatioons Parameter Buried Pipe Buried PPipe Circuulating Ciirculating Group Group p Waater Water Dischharge D Discharge Piipe Pipe Insitu Excavatiion Innsitu Exxcavation Cover C Depth (mm) 5.465 0 2.74 0 Area A of Contam minated 1349.71 1349.7 1 7666.14 766.14 Zone Z (m2)

Thickness T of 0.0254 0.15 0.00254 0.15 Contaminated C zone z (m)

Length L Parallel to 41.45 41.45 1600.02 160.02 Aquifer A Flow (m m)

Unsaturated U Zone 0.61 6.07066 3.33 6.0706 Thickness T (m) to the DC CGL calculaation, includ ding RESRA AD source teerm parameeter calculatiions, a list oof the resulting RESRAD DSRs D generrated by mo odeling and all unit connversions are provided in an Excel sprreadsheet ass described in i Referencee 8. The burried pipe DC CGLs for thhe initial suitte are provided d in Table 6-2 27.

6.18.5. Buried B Pipe Radionuclid des of Conccern and Ad djusted DCG GLs The Buriied Pipe DC CGLs in Tab ble 6-27 werre used in R Reference 5 tto calculate the relative dose contributtions from th he initial suitte radionucliides, identifyy the insigniificant contriibutors, selecct the final ROCs and adju ust the ROC Cs for the do ose fraction aattributable to the remooved insignifficant contributtors. The do ose percenttages for th he initial suuite were caalculated ussing the miixture fractions from Table 6-3.

The dosee percentagees for the in nitial suite raadionuclidess were calcuulated for eaach of the bburied pipe scen narios; Insitu u and Excavaation. The fiinal list of innsignificant ccontributors was the sam me for all buriedd pipe scenarrios and the same as identified for sooil and basements. The R ROCs are C Co-60, Sr-90 and d Cs-137.

The dosee percentagess for the insiignificant co ontributors w were differennt for each off the four buuried pipe DCG GL categoriees. Thereforee, adjustmen nts to the Buuried Pipe DC CGLs to acccount for the insignificcant radionu uclide fractioons were calcculated separrately for eaach of the fouur. Attachmeent 6-3 contaains a copy of o Table 24 from f Referen nce 5 whichh provides the dose perceentages for thhe initial suiite and the dose d percentaages attributable to the aaggregate of the insignifi ficant contributtors that werre removed.

6-45

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tab ble 6-27 Buried B Pipiing DCGLs Buried Pipe Circulatingg Buried Pipe Group Circullating Water Group Water Dischaarge Disccharge Pipe Pipe Raddionuclide Excavation Exxcavation Insitu Insitu (dpm/1100 cm2) (dpmm/100 cm2)

(dpm/100

( cm2) (dpm/100 cm m 2)

H-3 4.69E+08 4.65 5E+09 1.56E+08 6.23E+09 C-14 1.82E+07 2.43E+10 1.53E+07 2.45E+10 Fe-55 0.00E+00 5.95 5E+10 0.00E+00 7.77E+10 Ni-59 1.12E+10 1.52 2E+11 0.00E+00 1.98E+11 Co-60 9.12E+06 8.43E+04 4.92E+07 8.58E+04 Ni-63 4.67E+10 5.55 5E+10 1.98E+11 7.24E+10 Sr-90 5.84E+05 3.99 9E+07 6.94E+05 4.23E+07 Nb-94 1.01E+08 1.27 7E+05 1.01E+08 1.29E+05 Tc-99 2.33E+07 8.79 9E+07 7.26E+06 1.19E+08 Cs-137 C 2.57E+07 3.60 0E+05 1.31E+08 3.66E+05 Eu-152 E 1.46E+09 1.82 2E+05 1.45E+12 1.86E+05 Eu-154 E 2.68E+09 1.70 0E+05 1.40E+14 1.73E+05 Eu-155 E 1.43E+11 6.62 2E+06 4.72E+19 6.71E+06 Pu-238 P 1.50E+06 9.90 0E+06 1.04E+07 1.29E+07 Pu-239 P 7.85E+05 8.91E+06 7.88E+05 1.16E+07 Pu-240 P 7.93E+05 8.92 2E+06 8.11E+05 1.16E+07 Pu-241 P 5.14E+07 3.04 4E+08 1.11E+08 3.68E+08 Am-241 A 1.82E+06 6.52 2E+06 3.84E+06 7.93E+06 Am-243 A 1.49E+06 1.11E+06 1.52E+06 1.16E+06 Cm-243 C 7.57E+08 1.71E+06 6.63E+08 1.79E+06 Cm-244 C 3.03E+08 1.59 9E+07 3.01E+08 2.07E+06 The dosee fraction of o the aggreegate of the insignificannt contributtors ranges from 0.413% to 1.961%. Table 6-28 provides p thee final Buried d Pipe DCGL Ls for the R ROC adjustedd for the rem moved insignificcant dose perrcentage.

The finall DCGLs to be used du uring FSS acccount for thhe fact that tthe dose froom the Insituu and Excavation scenarioss must be su ummed in thee conceptuall model for buried pipe dose assessm ment, i.e., the insitu and ex xcavation sceenarios may y occur in paarallel. The ssummed Burried Pipe DC CGLs are proviided in Tablee 6-29.

6-46

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tabble 6-28 Buried Pip pe DCGLs ffor ROCs A Adjusted forr Insignificaant Radionu uclide Fracttions Buried B Pipe Buriied Pipe Circulatting Circulating Group Group G Water Disccharge W Water Discharrge Pipee Pipe Radionnuclide Insitu Excavation Insituu Excavation dpm/100 cm2)

(d (dpm//100 cm2) (dpm/1000 cm2) dpm/100 cm2)

(d Co--60 9.01E+06 8.39E+04 4.882E+07 8.55E+04 Sr--90 5.77E+05 3.98E+07 6.880E+05 4.22E+07 Cs-137 2.54E+07 3.59E+05 1.228E+08 3.65E+05 Table 6-29 6 Summmed Burieed Pipe DCG GLs for RO OCs adjusted d for Insignifican nt Radionucclide Fractions Circulatting Buriied Pipe Water Disccharge Group G

Radionuclide Pipee (dpm/100 cm2)

(dpm/1000 cm2)

Co-60 8.31E+04 8.53E++04 Sr-90 5.69E+05 6.70E++05 Cs-137 3.54E+05 3.64E++05 6.19. Existing E Gro oundwater DoseD There is low potenttial for signiificant groundwater conntamination to be preseent althoughh low concentraations have been identiified in grou undwater addjacent to suuspected brooken floor ddrains under thee Turbine Bu uilding. Sam mpling in 19 983 from a w well located ddown gradieent of the Tuurbine Building indicated po ositive grounndwater contamination aat relatively low concenttrations.

In late 20012, five addditional mon nitoring welll pairs were installed to support sitee characterizzation and licennse terminatiion. Results indicated lower groundw water contam mination levvels than fouund in 1983, prredominantly y H-3. See LTP Chaptter 2 for a summary oof characteriization and HSA results. Groundwater G r Exposure Factors weere calculateed to determ mine the dose from exiisting groundw water contamiination that maym be present at the tim me of licensee terminationn.

Groundw water Exposu ure Factors for existing g GW contaamination w were calculatted for the three ROCs id dentified in Table 6-24 plus H-3. Because thhe industriaal scenario ddoes not include irrigation n the only exxposure pathw way from grroundwater iis potable waater from ann onsite well. The GW Exp posure Facto ors were th herefore calcculated in R Reference 8 directly using the Feederal Guidancee Report 11 1 Ingestion Dose Conv version Facttors and thee assumed iindustrial w worker AMCG drinking d watter intake ratte of 327 L/yyr. See Tablee 6-30.

6-47

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Tablle 6-30 Groundwate G r Exposure Factors Grooundwater E Exposure Facctors Raadionuclide (mrem/yr per pCi/L)

Co-60 8.800E-03 Cs-137 1.644E-02 Sr-90 4.644E-02 H-3 2.099E-05 6.20. Demonstrati D ing Complia ance with Dose Criterioon As discussed in sectiion 6.5.5, thhe final demoonstration off compliancee with the ddose criterionn will be made through the summation of dose from m exposure scenarios thhat are not mmutually excllusive and couldd potentiallyy occur in paarallel.

After commpliance is demonstrateed independ dently througgh the FRS of each struucture, openn land area and buried pipin ng, the meann concentrations or invenntory values from the FR RS will be ussed to calculate dose and su ummed as sh hown in Equation 6-2.

Equation 6-2 where:

Complian nce Dose = Dose to IIndustrial W Worker AMCG (mrem/yr))

Max BFM M Insitu (ds) = maximum m BFM Insittuds dose fromm basements (mrem/yr)

Max BFM M Excavation n = maximum m BFM Exccavation dosee from basements (mrem/yr)

Summatio on BFM Insiitu (gw) and Burieed Pipe Insitu u = summatioon of BFM IInsitugw dosee from all basementss (mrem/yr) and Buried Pipe Insitu ddose (mrem/yr)) from all pippe Max Open n Land = maximum m dose fromm open land ssurvey units (mrem/yr))

Max Buriied Piping Ex xcavation = maximum m dose from buried pipinng Excavatioon (mrem/yr))

Max Exissting Ground dwater = maximum m dose from existing grooundwater The dosee for basements is calculaated directly y from meann STS resultss. The dose ffor open landd and buried piiping is calcu ulated by divviding the mean m FSS conncentrations by the DCG GLs and multiplyiing the ratio by 25 mrem m/yr. Note th hat the BFM Insitugw dosse from the bbasement 6-48

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 assigned the Maximu um BFM Excavation dosse in Equatioon 6-2 will nnot be includded in the B BFM Insitugw Summation S term in Equuation 6-2. The T two scennarios are muutually excluusive; the contamin nation can eiither be retaiined in the co oncrete and excavated oor released too the fill and contributte to dose fro om well wateer, not both. The Buriedd Pipe Insitu dose is incluuded in groundwwater summattion becausee it is based onlyo on the ggroundwaterr pathway.

6.21. References R

1. Haley H & Aldrrich Inc., Hyydrogeologiccal Investigaation Report,, La Crosse B Boiling Watter Reactor, R Dairryland Power Cooperativ ve, Genoa WWisconsin, Fiile No. 387005-008, January 2015.

2. EnergySoluti E ons Techniccal Support Document D RRS-TD-3131996-003, La C Crosse Boilinng Water W Reactoor Historical Site Assessm ment (HSA)).

3. U.S.

U Nuclear Regulatory Commission n, NUREG-11757, Volum me 2, Revisioon 1, Consolidated C Decommisssioning Guid dance - Charracterization, Survey, annd Determinaation of Radiologiccal Criteria, Final F Reportt - Septembeer 2006.

4. U.S.

U Nuclear Regulatory Commission n NUREG-11575, Suppleement 1, Muulti-Agency Radiation R Surrvey and Assessment of Materials annd Equipmennt Manual (M MARSAME E) -

December D 20006.

5. EnergySoluti E ons Techniccal Support Document D RRS-TD-3131996-001, Raddionuclides oof Concern C Duriing LACBW WR Decomm missioning.

6. Pacific North hwest Laboraatory, NURE EG/CR-34744, Long-Liveed Activationn Products inn Reactor R Mateerials, Pacificc Northwest Laboratory - 1984.

7. Pacific North hwest Laboraatory, NURE EG/CR-42899, Residual R Radionuclidee Concentrattion Within W and Around A Comm mercial Nucclear Power P Plants; Origiin, Distribution, Inventoory, an nd Decomm missioning Asssessment - 1985.

8. EnergySoluti E ons Techniccal Support Document D RRS-TD-3131996-004, LAC CBWR Soil DCGL D and Concrete BFM M Dose Facttors.

9. Argonne A Natiional Laboraatory, NURE EG/CR-66977, Developm ment of Probaabilistic RESRAD R 6.0 0 and RESRA AD-BUILD 3.0 Computter Codes - D December 2000.

10. Sandia Nation nal Laboratoory, NUREG G/CR-5512, V Volume 3, RResidual Raddioactive Contaminatio C on From Deccommissioniing Parameteer Analysis - October 19999.

11. ZionSolution Z s Technical Support Doccument 14-0006, Conestooga Rovers & Associatess (C

CRA) Reporrt, Evaluation n of Hydroloogical Parammeters in Suppport of Dosse Modeling for th he Zion Resttoration Project.

12. Argonne A Natiional Laboraatory, Userss Manual forr RESRAD V Version 6, A ANL/EAD-4,, July 2001.

13. Sheppard and d Thibault, Default D Soil/S Solid /Liquidd Partition CCoefficients,, Kds, for Foour Major M Soil Tyypes: A Com mpendium, Health H Physi cs, Vol. 59 NNo 4, October 1990.

14. EnergySoluti E ons Techniccal Support Document D RRS-TD-3131996-005, La C Crosse Openn Air Demolition D Limits.

L 6-49

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 6-1 Site S Regionaal Location 6-50

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 6-2 2 Site Ovverview 6-51

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 6-3 LACBWR Buildings 6-52

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 6-4 LACBWR En nd State 6-53

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 6-5 5 LACBWR R End State - Backfilled Strucctures 6-54

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 6-6 6 LACB BWR End State S - Back kfilled Reacctor Building Basementt Elevation V View 6-55

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 6-7 RESRAD Parameter P Selection Fllow Chart Seleect model paarameter Classifyy as Behavioral, Metabo olic, or Physical Behavioral pa arameter Metabolic parameter Physicaal parameter Assign defau ult value Assign default value from NUREG G/CR 5512 from NUR REG/CR 5512 S Site data Vol. 3 Vol.

V 3 avvailable?

Yes Input paraameter Inputt parameter value value No Inpuut parameter value Classify as Priiority 1, 2 or 3 Prio ority 1 or 2 P Priority 3 Assign distribution from Assignn Median value NUREG G/CR-6697, Att C from RRESRAD v7.0 Complete sensitivity analysiis using RESRAD v7.0 Inpuut parameter value Classify parameter as Sensitive or Non-sensitivve Sensitive,, lPRCCl > 0.25 Non-sennsitive, lPRCCl < 00.25 Assign 75% perccentile value if Assiign 25% percentilee value if A

Assign 50% value TEDE is positivvely correlated TEDDE is negatively co orrelated distribution with the paarameter with the parameeter Input parameeter Input parameteer Input parameter value value value 6-56

La Crosse Boiling B Wateer Reactor License Terrmination Plaan Revision 0 ATTACHMENT 6-1 RESRAD R In nput Parammeters for LA ACBWR Sooil DCGL Uncertainty Analysis 6-57

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Soil Concentrations Basic rad diation dose limit (mre em/y) 3D 25 10 CFR R 20.1402 NR N R NR NR Initial prin ncipal radionuclide (pCi/g) P 2D 1 Unit Value NR N R NR NR Distribu ution coefficients (contaminated, unsatturated, and saturated 3 d zones) (cm /g)

Mean KdK Value for sand Ac-227 (d daughter of Cm-243 anda NUREG G/CR-6697, Table P 1D 450 6.72 3.2 2 NA NA 825 Pu-239) 3.9-2, Sheppard S and Thibault Am-241 (also daughter of Cm-245 S Not Included in Uncertainty < 0.1% of radionuclide P 1 NA N A NA NA NA and Pu-2 241) Analyssis mixture S Not Included in Uncertainty < 0.1% of radionuclide Am-243 P 1 NA N A NA NA NA Analyssis mixture C-14 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 2.4 3.2 2 NA NA 11 Not Included in Uncertainty < 0.1% of radionuclide Cm-243 P 1S NA N A NA NA NA Analyssis mixture Not Included in Uncertainty < 0.1% of radionuclide Cm-244 P 1S NA N A NA NA NA Analyssis mixture Co-60 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 5.46 2.5 3 NA NA 235 Cs-137 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.1 2.3 3 NA NA 446 Eu-152 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.72 3.2 2 NA NA 825 Eu-154 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.72 3.2 2 NA NA 825 Not Included in Uncertainty < 0.1% of radionuclide Eu-155 P 1S NA N A NA NA NA Analyssis mixture Fe-155 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 5.34 2.6 7 NA NA 209 Median Value NUREG G/CR-6697, Att. C Gd-152 (daughter for Eu-152) P 1D 825 6.72 3.2 2 NA NA 825 (No sannd value listed in Table 3.9-2)

H-3 P 1S Lognormmal-N NUREG G/CR-6697 Att. C -2.81 0.5 5 NA NA 0.06 Not Included in Uncertainty < 0.1% of radionuclide Nb-94 P 1S NA N A NA NA NA Analyssis mixture RESRA ADv.7.0 Default Nd-144 (d daughter for Eu-152) P 1D 158 Nd not listed l in NA N A NA NA NA NUREG G/CR-6697 Ni-59 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.05 1.4 6 NA NA 424 Ni-63 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.05 1.4 6 NA NA 424 6-58

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Np-237 (also daughter for Am-241, Not Included in Uncertainty < 0.1% of radionuclide P 1S NA N A NA NA NA Cm-245, and Pu-241) Analys sis mixture Pa-231 (d daughter for Cm-243 and Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA Pu-239) Analys sis radionuclide mixture Not Included in Uncertainty parent < 0.1% of Pb-210 (d daughter for Pu-238) P 1D NA N A NA NA NA Analys sis radionuclide mixture Not Included in Uncertainty parent < 0.1% of Po-210 (d daughter Pu-238) P 1D NA N A NA NA NA Analys sis radionuclide mixture Not Included in Uncertainty < 0.1% of radionuclide Pu-238 P 1S NA N A NA NA NA Analys sis mixture Not Included in Uncertainty < 0.1% of radionuclide Pu-239 (a also daughter for Cm-243) P 1S NA N A NA NA NA Analys sis mixture Not Included in Uncertainty < 0.1% of radionuclide Pu-240 (a also daughter for Cm-244) P 1S NA N A NA NA NA Analys sis mixture Pu-241 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.86 1.8 9 NA NA 953 Not Included in Uncertainty parent < 0.1% of Ra-226 (d daughter Pu-238) P 1D NA N A NA NA NA Analys sis radionuclide mixture Ra-228 (d daughter Cm-244 and d Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 240) Analys sis radionuclide mixture Mean KdK Value for sand NUREG G/CR-6697, Table Sm-148 ((daughter Eu-152) P 1D 245 6.72 3.2 2 NA NA 825 3.9-2, Sheppard S and Thibault Sr-90 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 3.45 2.1 2 NA NA 32 Not Included in Uncertainty < 0.1% of radionuclide Tc-99 P 1S NA N A NA NA NA Analys sis mixture Th-228 (d daughter Cm-244 and d Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 240) Analys sis radionuclide mixture Mean KdK Value for sand Th-229 (d daughter Am-241, Cmm-245, NUREG G/CR-6697, Table P 1D 32000 8.68 3.6 2 NA NA 5884 Np-237, a and Pu-241) 3.9-2, Sheppard S and Thibault Th-230 (d daughter Cm-246 and d Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 238) Analys sis radionuclide mixture Th-232 (d daughter Cm-244 and d Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 240) Analys sis radionuclide mixture Mean KdK Value for sand U-233 (da aughter Am-241, Cm-245, NUREG G/CR-6697, Table P 1D 35 4.84 3.1 3 NA NA 126 Np-237, a and Pu-241) 3.9-2, Sheppard S and Thibault C 6-59

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Not Included in Uncertainty parent < 0.1% of U-234 (da aughter Pu-238) P 1D NA N A NA NA NA Analys sis radionuclide mixture U-235 (da aughter Cm-243 and Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 239) Analys sis radionuclide mixture U-236 (da aughter Cm-244 and Pu- Not Included in Uncertainty parent < 0.1% of P 1D NA N A NA NA NA 240) Analys sis radionuclide mixture Initial con ncentration of radionu uclides No existing groundwater P 3D 0 NR N R NR NR present in n groundwater (pCi/l) contamination Calcula ation Times Start of dose calculation Time sincce placement of mate erial (y) P 3D 0 immedia ately after license NR N R NR NR termination 0, 1, 3, 10, 30,, 100, 300, Time for calculations (y) P 3D RESRA AD Default NR N R NR NR 1000 0 Contam minated Zone 2 Size of LACBWR Licensed Area of ccontaminated zone (m m)P 2D 7500 0 NR N R NR NR Site Excclusion (LSE) area Surfacee Soil contamination Thicknesss of contaminated zo one (m) P 2D 1 thicknesss not expected to NR N R NR NR exceed 1 m.

Diamete er of 7500 m2 Length pa arallel to aquifer flow (m) P 2D 98 NR N R NR NR contaminated zone Does the e initial contamination Contamminated zone at NA NA NA No NA N A NA NA penetrate e the water table? surface Contamin nated fraction below water w Contamminated zone at P 3D 0 NR N R NR NR table surface Cover a and Contaminated d Zone Hydrologic cal Data Cover de epth (m) P 2D 0 No cove er NR N R NR NR Density o of cover material P 2D NA No cove er NR N R NR NR Cover ero osion rate P,B 2D NA No cove er NR N R NR NR Density o of contaminated zone e 3 P 1D 1.76 6 Site spe ecific NR N R NR NR (g/cm )

Contamin nated zone erosion ra ate NUREG G/CR-6697 Att. C m/y) P,B 2S Continuous Lo ogarithmic 5E-08 0.00 0 07 0.005 0.2 0.0015 Table 3.8-1 e

Contamin nated zone total poros sity P 2D 0.31 Site spe ecific NR N R NR NR 6-60

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median RES SRAD default. No distribu ution or median value Contamin nated zone field capaacity P 3D 0.2 NR N R NR NR provideed in NURE/CR-6697 Att. C e

Contamin nated zone hydraulic Site specific P 2D 34822 NR N R NR NR conductivvity (m/y) 313 feeet/day = 34822 m/y Site sppecific soil type sand Contamin nated zone b parameter P 2S Lognorm mal-N NURE EG/CR-6697 Att. C -.0253 0.21 6N A NA 0.97 Table 3.5-1 3 Median Humidity in air (g/m ) P 3D 7.2 1.98 0.33 4 0.001 0.999 7.2 NURE EG/CR-6697 Att. C NURE EG/CR-6697 Att. C Evapotra anspiration coefficient P 2S Uniforrm 0.5 0.7 5 NR NR 0.625 Figure 4.3-1 NURE EG/CR-6697 Att. C Average annual wind speed (m m/s) P 2S Bounded Logn normal - N 1.445 0.24 1 19 1.4 13 4.2 Figure 4.5-1 NURE EG/CR-6697 Att. C Precipitattion (m/y) P 2D 0.78 8 L Crosse, WI La NR N R NR NR Table 4.1-2 Irrigation (m/y) B 3D NA Inddustrial Scenario NR N R NR NR Irrigation mode B 3D NA Inddustrial Scenario NR N R NR NR NURE EG/CR-6697 Att. C Runoff co oefficient P 2S Uniforrm 0.1 0.8 8 NR NR 0.45 Figure 4.2-1 Watershe ed area for nearby strream 2 P 3D 1.00E+ +06 R ESRAD Default NR N R NR NR or pond ((m )

Accuracyy for water/soil

- 3D 1.00E--03 R ESRAD Default NR N R NR NR computattions Saturate ed Zone Hydrolog gical Data 3 e Density o of saturated zone (g/ccm ) P 2D 1.76 6 Site-specific NR N R NR NR e

Saturated d zone total porosity P 1D 0.31 Site-specific NR N R NR NR e

Saturated d zone effective poros sity P 1D 0.28 8 Site-specific NR N R NR NR Calcula ated values for sand Saturated d zone field capacity P 3D 0.0666 f NR N R NR NR soil type e

Sitte-specific value Saturated d zone hydraulic P 1D 34822 NR N R NR NR conductivvity (m/y) 313 feeet/day = 34822 m/y e

Saturated d zone hydraulic grad dient P 2D 0.00445 Site-specific NR N R NR NR 6-61

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Site speecific soil type sand 0.97 Saturatedd zone b parameter P 2S Lognormmal-N NUREG G/CR-6697 Att. C -.0253 0.21 6N A NA Table 3.5-1 Assume ed zero due to Water tabble drop rate (m/y) P 3D 0 hydraulic connectivity with NR N R NR NR Mississippi river.

Site-speecific distribution Existingg industrial water supply wells w onsite at depth of 116 and 129 below ground surface (the 129 depth equals 33.1 m below the wateer table). 33.1 m assume ed to be maximum well deppth.

Minimum m well depth assume ed to be represented Well pummp intake depth (m beelow P 2S Trianguular by a nominal 20 screen 6.08 19. 6 33.1 NR 19.6 water tab ble) depth (66.08 m) starting at the wateer table.

Mode is s assumed to be mid--

point beetween 6.08 m and 33.1 m which is 19.6 m.

Note thaat the site-specific distributtion is reasonably similar to t the NUREG-6697 distributtion values of 6, 10, and 30 for the triangular distributtion.

Model: Nondispersion (ND) orr Mass- Applicable to flowing P 3D ND NR N R NR NR Balance (MB) groundw water 6-62

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median NUREG G/CR-6697, Att. C provides no recommended value du ue to high variability.

Industrial Scenario pump rate deppends on industry.

NUREG G-6697, Table 3.10-1 3

Well pum mping rate (m /y) P 2S Uniforrm applies a sanitary and 328.7 1643 .5 NR NR 986.1 potable water usage rate for 3

four perrsons of 328.7 m /yr.

This vallue is assumed to be the minimum industrial rate.

Maximu um industrial rate assume ed to supply 20 workers s which equates 3

to1643.5 m /yr.

Unsaturrated Zone Hydrological Data e

Number oof unsaturated zone strata s P 3D 1 Site-speecific NR N R NR NR e

Unsat. zo one thickness (m) P 1D 5.1 m Site Speecific NR N R NR NR 3 1.76 6 e Unsat. zo one soil density (g/cm m)P 2D Site-speecific NR N R NR NR e

Unsat. zo one total porosity P 2D 0.31 Site-sp e ecific NR N R NR NR e

Unsat. zo one effective porosity P 2D 0.28 8 Site-sp ecific e NR N R NR NR 0.0666 Calcul a ated values for sand Unsat. zo one field capacity P 3D f NR N R NR NR soil type e

e Unsat. zo one hydraulic conducttivity Site-speecific P 2D 34822 NR N R NR NR (m/y)

Site speecific soil type sand Unsat. zo one soil-specific b P 2S Lognormmal-N NUREG G/CR-6697 Att. C -.0253 0.21 6N A NA 0.97 parameteer Table 3.5-1 Occupancy O

6-63

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median NUREG G/CR-5512, Vol. 3 Table 5.1.1 mean value is 8400/y which w equates to 23 3 3 Inhalation n rate (m /y) M,B 3D 19177 m /d NR N R NR NR 3

Industrial Scenario m /yr 3

=23 m /d/ ÷ 24h/d

2000 h/y))

See See Seee See NUREG- NUREG-3 NURE EG- N NUREG-Mass loaading for inhalation (g//m ) P,B 2S Continuouss Linear NURE G G/CR-6697, Att. C 6697 6697 2.35E-05 6697 Taable 6697 Table Table Table 4.6-1 4.6-1 4.6-1 4.6-1 RESRA AD Users Manual Exposure e duration B 3D 30 parame eter value not used in NR N R NR NR dose caalculation NUREG G/CR-6697, Att. C Indoor duust filtration factor P,B 2S Uniforrm 0.15 0.9 5 NR NR 0.55 Figure 7.1-1 7

NUREG G/CR-6697, Att. C Shieldingg factor, external gamma P 2S Bounded Log gnormal-N -1.3 0.5 9 0.044 1 0.2725 Table 7.10-1 NUREG G-6697 Att. C, Table 7.6-1 re ecommends a median indoor work day as 8.76 hoours/day. Assuming 5 days a week w and 50 weeks per years this equates to 2190 ho ours per year.

Majorityy of industrial work is expecteed to be indoors.

Fraction oof time spent indoors B 3D 0.18775 NR N R NR NR Consisttent with Table 2-3 of the Use ers Manual for g

RESRA AD Version 6 75%

of work time is indoors and 25% ou utdoors.

The corrresponding RESRA AD indoor Fraction parame eter =

(2190*.7 75)/(24*365) = .1875 6-64

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median As explained in the basis forr the Indooor Fraction parame eter, the indoor time Fraction oof time spent outdoorrs (on fraction was set at 75% and B 3D 0.06225 NR N R NR NR site) outdoorr time fraction at 25%.

(2190*.225)/(24*365) =

0.0625 Circularr contaminated zone Shape fa actor flag, external gam mma P 3D Circular assume ed for modeling NR N R NR NR purpose es Ingestio on, Dietary Fruits, no on-leafy vegetables, grain g

M,B 2D NA Industrial Scenario NR N R NR NR consump ption (kg/y)

Leafy veg getable consumption (kg/y) M,B 3D NA Industrial Scenario NR N R NR NR Milk conssumption (L/y) M,B 2D NA Industrial Scenario NR N R NR NR M,B Meat and d poultry consumption n (kg/y) 3D NA Industrial Scenario NR N R NR NR M,B Fish conssumption (kg/y) 3D NA Industrial Scenario NR N R NR NR M,B Other sea afood consumption (k kg/y) 3D NA Industrial Scenario NR N R NR NR M,B NUREG G/CR-5512, Vol. 3 Soil ingesstion rate (g/y) 2D 18.3 3 NR N R NR NR Table 6.87 NUREG G/CR-5512, Vol. 3 Table 6.87 Industrial Scenario water supply assumed a to be from an onsitte well.

M,B Drinking water intake (L/y) 2D 327 478 L/y from NUREG/CR- NR N R NR NR 5512 co orresponds to 1.31 L/d whicch is considered a conserv vative value for 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months woork day.

1.31 L/dd

250 work days =

327 L/y 6-65

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Contamin nation fraction of drinkking All wate er assumed B,P 3D 1 NR N R NR NR water contaminated Contamin nation fraction of hous sehold B,P 3 1 All wate er from well water (if u used)

Contamin nation fraction of livesstock B,P 3D NA Industrial Scenario NR N R NR NR water Contamin nation fraction of irriga ation B,P 3D NA Industrial Scenario NR N R NR NR water Contamin nation fraction of aqua atic B,P 2D NA Industrial Scenario NR N R NR NR food Contamin nation fraction of plannt food B,P 3D NA Industrial Scenario NR N R NR NR Contamin nation fraction of mea at B,P 3D NA Industrial Scenario NR N R NR NR Contamin nation fraction of milk B,P 3D NA Industrial Scenario NR N R NR NR Ingestio on, Non-Dietary Livestockk fodder intake for me eat M 3D NA Industrial Scenario NR N R NR NR (kg/day)

Livestockk fodder intake for milk M 3D NA Industrial Scenario NR N R NR NR (kg/day)

Livestockk water intake for mea at M 3D NA Industrial Scenario NR N R NR NR (L/day)

Livestockk water intake for milk k M 3D NA Industrial Scenario NR N R NR NR (L/day)

Livestockk soil intake (kg/day) M 3D NA Industrial Scenario NR N R NR NR Mass loa ading for foliar deposittion 3 P 3D NA Industrial Scenario NR N R NR NR (g/m )

NUREG G/CR-6697, Att. C Depth of soil mixing layer (m) P 2S Trianguular 0 0.1 5 0.6 NR 0.15 Figure 3.12-1 3

Depth of roots (m) P 1D NA Industrial Scenario NR N R NR NR Drinking water fraction from grround B,P 3D 1 Industrial Scenario NR N R NR NR water Househo old water fraction from m B,P 3 1 Industrial Scenario NR N R NR NR ground w water (if used)

Livestockk water fraction from ground g

B,P 3D NA Industrial Scenario NR N R NR NR water Irrigation fraction from ground water B,P 3D NA Industrial Scenario NR N R NR NR Wet weig ght crop yield for Non--Leafy 2 P 2D NA Industrial Scenario NR N R NR NR (kg/m )

6-66

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Wet weig ght crop yield for Leaffy 2 P 3D NA Industrial Scenario NR N R NR NR (kg/m )

Wet weig ght crop yield for Foddder 2 P 3D NA Industrial Scenario NR N R NR NR (kg/m )

Growing Season for Non-Leaffy (y) P 3D NA Industrial Scenario NR N R NR NR Growing Season for Leafy (y)

( P 3D NA Industrial Scenario NR N R NR NR Growing Season for Fodder (y) P 3D NA Industrial Scenario NR N R NR NR Transloca ation Factor for Non-LLeafy P 3D NA Industrial Scenario NR N R NR NR Transloca ation Factor for Leafy yP 3D NA Industrial Scenario NR N R NR NR Transloca ation Factor for Fodde er P 3D NA Industrial Scenario NR N R NR NR Weatheriing Removal Constan nt for P 2D NA Industrial Scenario NR N R NR NR Vegetatioon (1/y)

Wet Foliaar Interception Fractio on for P 3D NA Industrial Scenario NR N R NR NR Non-Leaffy Wet Foliaar Interception Fractio on for P 2D NA Industrial Scenario NR N R NR NR Leafy Wet Foliaar Interception Fractio on for P 3D NA Industrial Scenario NR N R NR NR Fodder Dry Foliaar Interception Fraction for P 3D NA Industrial Scenario NR N R NR NR Non-Leaffy Dry Foliaar Interception Fraction for P 3D NA Industrial Scenario NR N R NR NR Leafy Dry Foliaar Interception Fraction for P 3D NA Industrial Scenario NR N R NR NR Fodder Storage e times of contaminated foodstuffs (days):

Fruits, no on-leafy vegetables, and a

B 3D NA Industrial Scenario NR N R NR NR grain Leafy veg getables B 3D NA Industrial Scenario NR N R NR NR Milk B 3D NA Industrial Scenario NR N R NR NR Meat and d poultry B 3D NA Industrial Scenario NR N R NR NR Fish B 3D NA Industrial Scenario NR N R NR NR Crustace ea and mollusks B 3D NA Industrial Scenario NR N R NR NR Well wate er B 3D NA Industrial Scenario NR N R NR NR Surface w water B 3D NA Industrial Scenario NR N R NR NR Livestockk fodder B 3D NA Industrial Scenario NR N R NR NR 6-67

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Special Radionuclides (C C-14) 3 C-12 con ncentration in water (g g/cm ) P 3D NA Industrial Scenario NR N R NR NR C-12 con ncentration in contamiinated P 3D NA Industrial Scenario NR N R NR NR soil (g/g)

Fraction o of vegetation carbon from P 3D NA Industrial Scenario NR N R NR NR soil Fraction o of vegetation carbon from P 3D NA Industrial Scenario NR N R NR NR air C-14 eva asion layer thickness in i soil P 2D NA Industrial Scenario NR N R NR NR (m)

C-14 eva asion flux rate from so oil P 3D NA Industrial Scenario NR N R NR NR (1/sec)

C-12 eva asion flux rate from so oil P 3D NA Industrial Scenario NR N R NR NR (1/sec)

Fraction o of grain in beef cattle feed B 3D NA Industrial Scenario NR N R NR NR Fraction o of grain in milk cow feeed B 3D NA Industrial Scenario NR N R NR NR Dose Co onversion Factors s (Inhalation mrem/p pCi)

Ac-227 M 3D 6.70E++00 FGR 11 NR N R NR NR Am-241 M 3D 4.44E--01 FGR 11 NR N R NR NR Am-243 M 3D 4.40E--01 FGR 11 NR N R NR NR C-14 M 3D 2.09E--06 FGR 11 NR N R NR NR Cm-243 M 3D 3.07E--01 FGR 11 NR N R NR NR Cm-244 M 3D 2.48E--01 FGR 11 NR N R NR NR Cm-245 M 3D 4.55E--01 FGR 11 NR N R NR NR Cm-246 M 3D 4.51E--01 FGR 11 NR N R NR NR Co-60 M 3D 2.19E--04 FGR 11 NR N R NR NR Cs-134 M 3D 4.62E--05 FGR 11 NR N R NR NR Cs-137 M 3 D 3.19E--05 FGR11 NR N R NR NR Eu-152 M 3D 2.21E--04 FGR 11 NR N R NR NR Eu-154 M 3D 2.86E--04 FGR 11 NR N R NR NR Gd-152 M 3D 2.43E--01 FGR 11 NR N R NR NR H-3 M 3D 6.40E--08 FGR 11 NR N R NR NR 6-68

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCEERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median I-129 M 3D 1.74E--04 FGR 11 NR N R NR NR Nb-94 M 3D 4.14E--04 FGR 11 NR N R NR NR e

Nd-144 M 3D 7.04E--02 ICRP6 0 NR N R NR NR Ni-59 M 3D 2.70E--06 FGR 11 NR N R NR NR Ni-63 M 3D 6.29E--06 FGR 11 NR N R NR NR Np-237 M 3D 5.40E--01 FGR 11 NR N R NR NR Pa-231 M 3D 1.28E++00 FGR 11 NR N R NR NR Pb-210 M 3D 1.36E--02 FGR 11 NR N R NR NR Po-210 M 3D 9.40E--03 FGR 11 NR N R NR NR Pu-238 M 3D 3.92E--01 FGR 11 NR N R NR NR Pu-239 M 3D 4.29E--01 FGR 11 NR N R NR NR Pu-240 M 3D 4.29E--01 FGR 11 NR N R NR NR Pu-241 M 3D 8.25E--03 FGR 11 NR N R NR NR Pu-242 M 3D 4.11E--01 FGR 11 NR N R NR NR Ra-226 M 3D 8.58E--03 FGR 11 NR N R NR NR Ra-228 M 3D 4.77E--03 FGR 11 NR N R NR NR e

Sm-148 M 3D 7.34E--02 ICRP6 0 NR N R NR NR Sr-90 M 3D 1.30E--03 FGR 11 NR N R NR NR Tc-99 M 3D 8.32E--06 FGR 11 NR N R NR NR Th-228 M 3D 3.42E--01 FGR 11 NR N R NR NR Th-229 M 3D 2.15E++00 FGR 11 NR N R NR NR Th-230 M 3D 3.26E--01 FGR 11 NR N R NR NR Th232 M 3D 1.64e+

+00 FGR 11 NR N R NR NR U-233 M 3D 1.35E--01 FGR 11 NR N R NR NR U-234 M 3D 1.32E--01 FGR 11 NR N R NR NR U-235 M 3D 1.23E--01 FGR 11 NR N R NR NR U-236 M 3D 1.25E--01 FGR 11 NR N R NR NR U-238 M 3D 1.18E--01 FGR 11 NR N R NR NR Dose Co onversion Factors s (Ingestion mrem/p pCi)

Ac-227 M 3D 1.41E--02 FGR 11 NR N R NR NR 6-69

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCEERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Am-241 M 3D 3.64E--03 FGR 11 NR N R NR NR Am-243 M 3D 3.62E--03 FGR 11 NR N R NR NR C-14 M 3D 2.09E--06 FGR 11 NR N R NR NR Cm-243 M 3D 2.51E--03 FGR 11 NR N R NR NR Cm-244 M 3D 2.02E--03 FGR 11 NR N R NR NR Cm-245 M 3D 3.74E--03 FGR 11 NR N R NR NR Cm-246 M 3D 3.70E--03 FGR 11 NR N R NR NR Co-60 M 3D 2.69E--05 FGR 11 NR N R NR NR Cs-134 M 3D 7.33E--05 FGR 11 NR N R NR NR Cs-137 M 3D 5.00E--05 FGR 11 NR N R NR NR Eu-152 M 3D 6.48E--06 FGR 11 NR N R NR NR Eu-154 M 3D 9.55E--06 FGR 11 NR N R NR NR Gd-152 M 3D 1.61E--04 FGR 11 NR N R NR NR H-3 M 3D 6.40E--08 FGR 11 NR N R NR NR I-129 M 3D 2.76E--04 FGR 11 NR N R NR NR Nb-94 M 3D 7.14E--06 FGR 11 NR N R NR NR e

Nd-144 M 3D 1.51E--04 ICRP6 0 NR N R NR NR Ni-59 M 3D 2.10E--07 FGR 11 NR N R NR NR Ni-63 M 3D 5.77E--07 FGR 11 NR N R NR NR Np-237 M 3D 4.44E--03 FGR 11 NR N R NR NR Pa-231 M 3D 1.06E--02 FGR 11 NR N R NR NR Pb-210 M 3D 5.37E--03 FGR 11 NR N R NR NR Po-210 M 3D 1.90E--03 FGR 11 NR N R NR NR Pu-238 M 3D 3.20E--03 FGR 11 NR N R NR NR Pu-239 M 3D 3.54E--03 FGR 11 NR N R NR NR Pu-240 M 3D 3.54E--03 FGR 11 NR N R NR NR Pu-241 M 3D 6.84E--05 FGR 11 NR N R NR NR Pu-242 M 3D 3.36E--03 FGR 11 NR N R NR NR Ra-226 M 3D 1.32E--03 FGR 11 NR N R NR NR Ra-228 M 3D 1.44E--03 FGR 11 NR N R NR NR 6-70

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median e

Sm-148 M 3D 1.58E--04 ICRP6 0 NR N R NR NR Sr-90 M 3D 1.42E--04 FGR 11 NR N R NR NR Tc-99 M 3D 1.46E--06 FGR 11 NR N R NR NR Th-228 M 3D 3.96E--04 FGR 11 NR N R NR NR Th-229 M 3D 3.53E--03 FGR 11 NR N R NR NR Th-230 M 3D 5.48E--04 FGR 11 NR N R NR NR Th-232 M 3D 2.73E--03 FGR 11 NR N R NR NR U-233 M 3D 2.89E--04 FGR 11 NR N R NR NR U-234 M 3D 2.83E--04 FGR 11 NR N R NR NR U-235 M 3D 2.66E--04 FGR 11 NR N R NR NR U-236 M 3D 2.69E--04 FGR 11 NR N R NR NR U-238 M 3D 2.55E--04 FGR 11 NR N R NR NR Plant Trransfer Factors (pCi/g plant)/(pCi/g so oil)

Ac-227 P 1D NA Industrial Scenario NR N R NR NR Am-241 P 1D NA Industrial Scenario NR N R NR NR Am-243 P 1D NA Industrial Scenario NR N R NR NR C-14 P 1D NA Industrial Scenario NR N R NR NR Cm-243 P 1D NA Industrial Scenario NR N R NR NR Cm-244 P 1D NA Industrial Scenario NR N R NR NR Co-60 P 1D NA Industrial Scenario NR N R NR NR Cs-134 P 1D NA Industrial Scenario NR N R NR NR Cs-137 P 1D NA Industrial Scenario NR N R NR NR Eu-152 P 1D NA Industrial Scenario NR N R NR NR Eu-154 P 1D NA Industrial Scenario NR N R NR NR Fe-55 P 1D NA Industrial Scenario NR N R NR NR Gd-152 P 1D NA Industrial Scenario NR N R NR NR H-3 P 1D NA Industrial Scenario NR N R NR NR Nb-94 P 1D NA Industrial Scenario NR N R NR NR Nd-144 P 1D NA Industrial Scenario NR N R NR NR Ni-59 P 1D NA Industrial Scenario NR N R NR NR 6-71

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Ni-63 P 1D NA Industrial Scenario NR N R NR NR Np-237 P 1D NA Industrial Scenario NR N R NR NR Pa-231 P 1D NA Industrial Scenario NR N R NR NR Pb-210 P 1D NA Industrial Scenario NR N R NR NR Pm-147 P 1D NA Industrial Scenario NR N R NR NR Po-210 P 1D NA Industrial Scenario NR N R NR NR Pu-238 P 1D NA Industrial Scenario NR N R NR NR Pu-239 P 1D NA Industrial Scenario NR N R NR NR Pu-240 P 1D NA Industrial Scenario NR N R NR NR Pu-241 P 1D NA Industrial Scenario NR N R NR NR Ra-226 P 1D NA Industrial Scenario NR N R NR NR Ra-228 P 1D NA Industrial Scenario NR N R NR NR Sb-125 P 1D NA Industrial Scenario NR N R NR NR Sm-148 P 1D NA Industrial Scenario NR N R NR NR Sr-90 P 1D NA Industrial Scenario NR N R NR NR Tc-99 P 1D NA Industrial Scenario NR N R NR NR Th-228 P 1D NA Industrial Scenario NR N R NR NR Th-229 P 1D NA Industrial Scenario NR N R NR NR Th-230 P 1D NA Industrial Scenario NR N R NR NR Th-232 P 1D NA Industrial Scenario NR N R NR NR U-233 P 1D NA Industrial Scenario NR N R NR NR U-234 P 1D NA Industrial Scenario NR N R NR NR U-235 P 1D NA Industrial Scenario NR N R NR NR U-236 P 1D NA Industrial Scenario NR N R NR NR Meat Trransfer Factors (pCCi/kg)/(pCi/d)

Ac-227 P 2D NA Industrial Scenario NR N R NR NR Ag-108mm P 2D NA Industrial Scenario NR N R NR NR Am-241 P 2D NA Industrial Scenario NR N R NR NR Am-243 P 2D NA Industrial Scenario NR N R NR NR C-14 P 2D NA Industrial Scenario NR N R NR NR 6-72

La Crosse Boiling Watter Reactor Licensee Termination PlanP Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Cm-243 P 2D NA Industrial Scenario NR N R NR NR Cm-244 P 2D NA Industrial Scenario NR N R NR NR Co-60 P 2D NA Industrial Scenario NR N R NR NR Cs-134 P 2D NA Industrial Scenario NR N R NR NR Cs-137 P 2D NA Industrial Scenario NR N R NR NR Eu-152 P 2D NA Industrial Scenario NR N R NR NR Eu-154 P 2D NA Industrial Scenario NR N R NR NR Fe-55 P 2D NA Industrial Scenario NR N R NR NR Gd-152 P 2D NA Industrial Scenario NR N R NR NR H-3 P 2D NA Industrial Scenario NR N R NR NR Nb-94 P 2D NA Industrial Scenario NR N R NR NR Nd-144 P 2D NA Industrial Scenario NR N R NR NR Ni-59 P 2D NA Industrial Scenario NR N R NR NR Ni-63 P 2D NA Industrial Scenario NR N R NR NR Np-237 P 2D NA Industrial Scenario NR N R NR NR Pa-231 P 2D NA Industrial Scenario NR N R NR NR Pb-210 P 2D NA Industrial Scenario NR N R NR NR Po-210 P 2D NA Industrial Scenario NR N R NR NR Pu-238 P 2D NA Industrial Scenario NR N R NR NR Pu-239 P 2D NA Industrial Scenario NR N R NR NR Pu-240 P 2D NA Industrial Scenario NR N R NR NR Pu-241 P 2D NA Industrial Scenario NR N R NR NR Ra-226 P 2D NA Industrial Scenario NR N R NR NR Ra-228 P 2D NA Industrial Scenario NR N R NR NR Sb-125 P 2D NA Industrial Scenario NR N R NR NR Sm-148 P 1D NA Industrial Scenario NR N R NR NR Sr-90 P 2D NA Industrial Scenario NR N R NR NR Tc-99 P 2D NA Industrial Scenario NR N R NR NR Th-228 P 2D NA Industrial Scenario NR N R NR NR Th-229 P 2D NA Industrial Scenario NR N R NR NR 6-73

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Th-230 P 2D NA Industrial Scenario NR N R NR NR Th-232 P 2D NA Industrial Scenario NR N R NR NR U-233 P 2D NA Industrial Scenario NR N R NR NR U-234 P 2D NA Industrial Scenario NR N R NR NR U-235 P 2D NA Industrial Scenario NR N R NR NR U-236 P 2D NA Industrial Scenario NR N R NR NR Milk Tra ansfer Factors (pC Ci/L)/(pCi/d)

Ac-227 P 2D NA Industrial Scenario NR N R NR NR Am-241 P 2D NA Industrial Scenario NR N R NR NR Am-243 P 2D NA Industrial Scenario NR N R NR NR C-14 P 2D NA Industrial Scenario NR N R NR NR Cm-243 P 2D NA Industrial Scenario NR N R NR NR Cm-244 P 2D NA Industrial Scenario NR N R NR NR Co-60 P 2D NA Industrial Scenario NR N R NR NR Cs-134 P 2D NA Industrial Scenario NR N R NR NR Cs-137 P 2D NA Industrial Scenario NR N R NR NR Eu-152 P 2D NA Industrial Scenario NR N R NR NR Eu-154 P 2D NA Industrial Scenario NR N R NR NR Fe-55 P 2D NA Industrial Scenario NR N R NR NR Gd-152 P 2D NA Industrial Scenario NR N R NR NR H-3 P 2D NA Industrial Scenario NR N R NR NR Nb-94 P 2D NA Industrial Scenario NR N R NR NR Nd-144 P 2D NA Industrial Scenario NR N R NR NR Ni-59 P 2D NA Industrial Scenario NR N R NR NR Ni-63 P 2D NA Industrial Scenario NR N R NR NR Np-237 P 2D NA Industrial Scenario NR N R NR NR Pa-231 P 2D NA Industrial Scenario NR N R NR NR Pb-210 P 2D NA Industrial Scenario NR N R NR NR Po-210 P 2D NA Industrial Scenario NR N R NR NR Pu-238 P 2D NA Industrial Scenario NR N R NR NR 6-74

La Crosse Boiling Watter Reactor Licensee Termination PlanP Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Pu-239 P 2D NA Industrial Scenario NR N R NR NR Pu-240 P 2D NA Industrial Scenario NR N R NR NR Pu-241 P 2D NA Industrial Scenario NR N R NR NR Ra-226 P 2D NA Industrial Scenario NR N R NR NR Ra-228 P 2D NA Industrial Scenario NR N R NR NR Sm-148 P 2D NA Industrial Scenario NR N R NR NR Sr-90 P 2D NA Industrial Scenario NR N R NR NR Tc-99 P 2D NA Industrial Scenario NR N R NR NR Th-228 P 2D NA Industrial Scenario NR N R NR NR Th-229 P 2D NA Industrial Scenario NR N R NR NR Th-230 P 2D NA Industrial Scenario NR N R NR NR Th-232 P 2D NA Industrial Scenario NR N R NR NR U-233 P 2D NA Industrial Scenario NR N R NR NR U-234 P 2D NA Industrial Scenario NR N R NR NR U-235 P 2D NA Industrial Scenario NR N R NR NR U-236 P 2D NA Industrial Scenario NR N R NR NR Bioaccuumulation Factors s for Fish ((pCi/kg)//(pCi/L))

Ac-227 P 2D NA Industrial Scenario NR N R NR NR Am-241 P 2D NA Industrial Scenario NR N R NR NR Am-243 P 2D NA Industrial Scenario NR N R NR NR C-14 P 2D NA Industrial Scenario NR N R NR NR Cm-243 P 2D NA Industrial Scenario NR N R NR NR Cm-244 P 2D NA Industrial Scenario NR N R NR NR Cm-245 P 2D NA Industrial Scenario NR N R NR NR Cm-246 P 2D NA Industrial Scenario NR N R NR NR Co-60 P 2D NA Industrial Scenario NR N R NR NR Cs-137 P 2D NA Industrial Scenario NR N R NR NR Eu-152 P 2D NA Industrial Scenario NR N R NR NR Eu-154 P 2D NA Industrial Scenario NR N R NR NR Gd-152 P 2D NA Industrial Scenario NR N R NR NR 6-75

La Crosse Boiling Watter Reactor Licensee Termination PlanP Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median H-3 P 2D NA Industrial Scenario NR N R NR NR I-129 P 2D NA Industrial Scenario NR N R NR NR Nb-94 P 2D NA Industrial Scenario NR N R NR NR Ni-59 P 2D NA Industrial Scenario NR N R NR NR Ni-63 P 2D NA Industrial Scenario NR N R NR NR Np-237 P 2D NA Industrial Scenario NR N R NR NR Pa-231 P 2D NA Industrial Scenario NR N R NR NR Po-210 P 2D NA Industrial Scenario NR N R NR NR Pb-210 P 2D NA Industrial Scenario NR N R NR NR Pu-238 P 2D NA Industrial Scenario NR N R NR NR Pu-239 P 2D NA Industrial Scenario NR N R NR NR Pu-240 P 2D NA Industrial Scenario NR N R NR NR Pu-241 P 2D NA Industrial Scenario NR N R NR NR Pu-242 P 2D NA Industrial Scenario NR N R NR NR Ra-226 P 2D NA Industrial Scenario NR N R NR NR Ra-228 P 2D NA Industrial Scenario NR N R NR NR Sr-90 P 2D NA Industrial Scenario NR N R NR NR Th-228 P 2D NA Industrial Scenario NR N R NR NR Th-229 P 2D NA Industrial Scenario NR N R NR NR Th-230 P 2D NA Industrial Scenario NR N R NR NR Th-232 P 2D NA Industrial Scenario NR N R NR NR U-233 P 2D NA Industrial Scenario NR N R NR NR U-234 P 2D NA Industrial Scenario NR N R NR NR U-235 P 2D NA Industrial Scenario NR N R NR NR U-236 P 2D NA Industrial Scenario NR N R NR NR U-238 P 2D NA Industrial Scenario NR N R NR NR Bioaccuumulation Factors s for Crustacea/ Mollusks M ((pCi/kg)/(p pCi/L))

Ac-227 P 3D NA Industrial Scenario NR N R NR NR Am-241 P 3D NA Industrial Scenario NR N R NR NR 6-76

La Crosse Boiling Watter Reactor Licensee Termination PlanP Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Am-243 P 3D NA Industrial Scenario NR N R NR NR C-14 P 3D NA Industrial Scenario NR N R NR NR Cm-243 P 3D NA Industrial Scenario NR N R NR NR Cm-244 P 3D NA Industrial Scenario NR N R NR NR Cm-245 P 3D NA Industrial Scenario NR N R NR NR Cm-246 P 3D NA Industrial Scenario NR N R NR NR Co-60 P 3D NA Industrial Scenario NR N R NR NR Cs-137 P 3D NA Industrial Scenario NR N R NR NR Eu-152 P 3D NA Industrial Scenario NR N R NR NR Eu-154 P 3D NA Industrial Scenario NR N R NR NR Gd-152 P 3D NA Industrial Scenario NR N R NR NR H-3 P 3D NA Industrial Scenario NR N R NR NR I-129 P 3D NA Industrial Scenario NR N R NR NR Nb-94 P 3D NA Industrial Scenario NR N R NR NR Ni-59 P 3D NA Industrial Scenario NR N R NR NR Ni-63 P 3D NA Industrial Scenario NR N R NR NR Np-237 P 3D NA Industrial Scenario NR N R NR NR Pa-231 P 3D NA Industrial Scenario NR N R NR NR Pb-210 P 3D NA Industrial Scenario NR N R NR NR Po-210 P SD NA Industrial Scenario NR N R NR NR Pu-238 P 3D NA Industrial Scenario NR N R NR NR Pu-239 P 3D NA Industrial Scenario NR N R NR NR Pu-240 P 3D NA Industrial Scenario NR N R NR NR Pu-241 P 3D NA Industrial Scenario NR N R NR NR Pu-242 P 3D NA Industrial Scenario NR N R NR NR Ra-226 P 3D NA Industrial Scenario NR N R NR NR Ra-228 P 3D NA Industrial Scenario NR N R NR NR Sr-90 P 3D NA Industrial Scenario NR N R NR NR Th-228 P 3D NA Industrial Scenario NR N R NR NR 6-77

La Crosse Boiling Watter Reactor Licensee Termination Plan P Revisioon 0 SOIL DCG GL: RESRAD PARAMETERS FOR UNCE ERTAINTY ANALYSIIS Parameter (unit) a b c d Type Priority Treatme ent Value/Distrribution Basis Distribution's Statistical Parameters 1 2 3 4 Mean/

Median Th-229 P 3D NA Industrial Scenario NR N R NR NR Th-230 P 3D NA Industrial Scenario NR N R NR NR Th-232 P 3D NA Industrial Scenario NR N R NR NR U-233 P 3D NA Industrial Scenario NR N R NR NR U-234 P 3D NA Industrial Scenario NR N R NR NR U-235 P 3D NA Industrial Scenario NR N R NR NR U-236 P 3D NA Industrial Scenario NR N R NR NR U-238 P 3D NA Industrial Scenario NR N R NR NR Graphic cs Parameters Number o of points 32 RESRA AD Default NR N R NR NR Spacing log RESRA AD Default NR N R NR NR Time inte egration parameters s Maximum m number of points for dose 17 RESRA AD Default NR N R NR NR Notes:

a P = physical, B = behavioral, M = metabolic; (see NUR REG/CR-6697, Attachm ment B, Table 4.)

b 1 = high--priority parameter, 2 = medium-priority parammeter, 3 = low-priority parameter p (see NUREGG/CR-6697, Attachment B, Table 4.1) c D = deterrministic, S = stochasticc d Distributtions Statistical Parameters:

Lognormal-n: 1= mean, 2 = stand dard deviation Bounded loognormal-n: 1= mean, 2 = standard deviation, 3 = minimum, 4 = maximum Truncated lognormal-n: 1= mean,, 2 = standard deviation, 3 = lower quantile, 4 = upper quantile Bounded nnormal: 1 = mean, 2 = sttandard deviation, 3 = minimum, m 4 = maximum m Beta: 1 = m minimum, 2 = maximum m, 3 = P-value, 4 = Q-value Triangularr: 1 = minimum, 2 = mo ode, 3 = maximum Uniform: 1 = minimum, 2 = maxiimum e Sm-148 an ND--144 not listed in RESRA AD FGR 11 DCF file e Referencce: Haley and Aldrich, Inc.,

I "Hydrogeological Investigation I Report La L Crosse Boiling Waterr Reactor, Dairyland Po ower Cooperative, Genooa, WI January 2015 f ZionSoluutions Technical Supporrt Document 14-003, Conestoga Rovers & Asssociates (CRA) Report, Zion Hydrogeologic In nvestigation Report g Argonnee National Laboratory, Users Manual for RESSRAD Version 6, ANL L/EAD 4, July 2001 6-78

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 ATTACHMENT 6-2 RESRAD D Input Parrameters forr LACBWR R BFM Unceertainty An nalysis 6-79

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License Termination Plan R

Revision 0 BFM INSITTUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatmeent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Soil Concentrations Basic radiation dose limit (mre em/y) 3D 25 10 CFR R 20.1402 NR N R NR NR Initial priincipal radionuclide (p pCi/g) P 2D 1 Unit Vaalue NR N R NR NR Distribu ution coefficients (contaminated, unsaaturated, and saturate 3

ed zones) (cm /g)

Mean KdK Value for sand Ac-227 ((daughter of Cm-243 and NUREG G/CR-6697, Table P 1D 4500 6.72 3.2 22 NA NA 825 Pu-239) 3.9-2, Sheppard S and Thibault Am-241 (also daughter of Cm m-245 Not Incluuded in < 0.1%

% of radionuclide P 1S NA N A NA NA NA and Pu-2 241) Uncertainty y Analysis mixturee Not Incluuded in < 0.1%

% of radionuclide Am-243 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee C-14 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 2.4 3.2 22 NA NA 11 Not Incluuded in < 0.1%

% of radionuclide Cm-243 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Not Included inn Uncertainty < 0.1%

% of radionuclide Cm-244 P 1S NA N A NA NA NA Analy ysis mixturee Co-60 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 5.46 2. 5 53 NA NA 235 Cs-137 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 6.1 2.3 33 NA NA 446 Eu-152 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 6.72 3.2 22 NA NA 825 Eu-154 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 6.72 3.2 22 NA NA 825 Not Incluuded in < 0.1%

% of radionuclide Eu-155 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Fe-55 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 5.34 2.6 67 NA NA 209 Median n Value NUREG G/CR-6697, Att. C Gd-152 (daughter for Eu-152) P 1D 8255 6.72 3.2 22 NA NA 825 (No sannd value listed in Table 3.9-2) 3 H-3 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C -2.81 0. 5 NA NA 0.06 Not Incluuded in < 0.1%

% of radionuclide Nb-94 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee RESRA ADv.7.0 Default Nd-144 ((daughter for Eu-152)) P 1D 1588 Nd not listed in NA N A NA NA NA NUREG G/CR-6697 Ni-59 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 6.05 1.4 46 NA NA 424 Ni-63 P 1S Lognorm mal-N NUREG G/CR-6697 Att. C 6.05 1.4 46 NA NA 424 6-80

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License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Np-237 (also daughter for Amm-241, Not Inclu uded in < 0.1%

% of radionuclide P 1S NA N A NA NA NA Cm-245,, and Pu-241) Uncertainty y Analysis mixturee Pa-231 ((daughter for Cm-2433 and Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA Pu-239) Uncertainty y Analysis radionuuclide mixture Not Inclu uded in parent < 0.1% of Pb-210 ((daughter for Pu-238)) P 1D NA N A NA NA NA Uncertainty y Analysis radionuuclide mixture Not Inclu uded in parent < 0.1% of Po-210 ((daughter Pu-238) P 1D NA N A NA NA NA Uncertainty y Analysis radionuuclide mixture Not Inclu uded in < 0.1%

% of radionuclide Pu-238 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Not Inclu uded in < 0.1%

% of radionuclide Pu-239 ((also daughter for Cm m-243) P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Not Inclu uded in < 0.1%

% of radionuclide Pu-240 ((also daughter for Cm m-244) P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Pu-241 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 6.86 1. 8 89 NA NA 953 Not Inclu uded in parent < 0.1% of Ra-226 ((daughter Pu-238) P 1D NA N A NA NA NA Uncertainty y Analysis radionuuclide mixture Ra-228 ((daughter Cm-244 an nd Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 240) Uncertainty y Analysis radionuuclide mixture Mean KdK Value for sand NUREG G/CR-6697, Table Sm-148 (daughter Eu-152) P 1D 2455 6.72 3.2 22 NA NA 825 3.9-2, Sheppard S and Thibault Sr-90 P 1S Lognormmal-N NUREG G/CR-6697 Att. C 3.45 2.1 2 NA NA 32 Not Inclu uded in < 0.1%

% of radionuclide Tc-99 P 1S NA N A NA NA NA Uncertainty y Analysis mixturee Th-228 ((daughter Cm-244 and Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 240) Uncertainty y Analysis radionuuclide mixture Mean KdK Value for sand Th-229 ((daughter Am-241, Cm m-245, NUREG G/CR-6697, Table P 1D 3200 8.68 3.6 62 NA NA 5884 Np-237, and Pu-241) 3.9-2, Sheppard S and Thibault Th-230 ((daughter Cm-246 and Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 238) Uncertainty y Analysis radionuuclide mixture Th-232 ((daughter Cm-244 and Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 240) Uncertainty y Analysis radionuuclide mixture Mean KdK Value for sand U-233 (d daughter Am-241, Cm m-245, NUREG G/CR-6697, Table P 1D 35 4.84 3.1 3 NA NA 126 Np-237, and Pu-241) 3.9-2, Sheppard S and Thibault C 6-81

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License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Not Inclu uded in parent < 0.1% of U-234 (d daughter Pu-238) P 1D NA N A NA NA NA Uncertainty y Analysis radionuuclide mixture U-235 (d daughter Cm-243 and d Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 239) Uncertainty y Analysis radionuuclide mixture U-236 (d daughter Cm-244 and d Pu- Not Inclu uded in parent < 0.1% of P 1D NA N A NA NA NA 240) Uncertainty y Analysis radionuuclide mixture Initial co oncentration of radionu uclides No exissting groundwater P 3D 0 NR N R NR NR present in groundwater (pCi/l) contammination Calcula ation Times Start off dose calculation Time sin nce placement of mate erial (y) P 3D 0 immediately after license NR N R NR NR terminaation 0, 1, 3, 10, 30 0, 100, 300, Time forr calculations (y) P 3D RESRA AD Default NR N R NR NR 1000 Contam minated Zone Sourcee term and physical geometries vary for the five 2 structures evaluated for Area of ccontaminated zone (m m)P 2D Variable NR N R NR NR BFM Innsitugw Uncertainty Analyses (see Table 6-8 in text)

Sourcee term and physical geometries vary for the five structures evaluated for Thicknesss of contaminated zo one (m) P 2D Variable NR N R NR NR BFM Innsitugw Uncertainty Analyses (see Table 6-8 in text)

Sourcee term and physical geometries vary for the five structures evaluated for Length p parallel to aquifer flow w (m) P 2D Variable NR N R NR NR BFM Innsitugw Uncertainty Analyses (see Table 6-8 in text)

Contamiinated fraction below water table Sourcee term and physical geometries vary for the five structures evaluated for P 3D Variable NR N R NR NR BFM Innsitugw Uncertainty Analyses (see Table 6-8 in text) 6-82

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License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Cover a and Contaminated d Zone Hydrologic cal Data Source e term and physical geometries vary for the five structures evaluated for Cover deepth (m) P 2D Variable NR N R NR NR BFM In nsitugw Uncertainty Analyses (see Table 6-8 in text) e Density oof cover material P 2D 1.766 Site-s p pecific NR N R NR NR NUREG G/CR-6697 Att. C Cover errosion rate P,B 2S Continuous Logarithmic L 5E-08 0.00 07 0.005 0.2 0.0015 Table 3.8-1 3

Density oof contaminated zone e e 3 P 1D 1.766 Site-s p pecific NR N R NR NR (g/cm )

Contamiinated zone erosion ra ate NUREG G/CR-6697 Att. C P,B 2S Continuous Logarithmic L 5E-08 0.00 07 0.005 0.2 0.0015 m/y) Table 3.8-1 3

e Contamiinated zone total poro osity P 2D 0.31 Site-s p pecific NR N R NR NR 0.43 RESRA AD default. No distribu ution or median valuee Contamiinated zone field capa acity P 3D 0.2 2 NR N R NR NR provideed in NURE/CR-66977 Att. C e

Site-sppecific Contamiinated zone hydraulic c P 2D 348222 NR N R NR NR conductiivity (m/y) 313 fee et/day = 34822 m/y Site sppecific soil type sand 0.97 Contamiinated zone b parame eter P 2S Lognormmal-N NUREG G/CR-6697 Att. C -.0253 0.2 1 16 N A NA Table 3.5-1 3

3 Median n Humidityy in air (g/m ) P 3D 7.2 2 1.98 0.3 3 34 0.001 0.999 7.2 NUREG G/CR-6697 Att. C Site-s specific value to force the Prrecipitation parameterr Evappotranspiration coeffic cient P 2S 0 to eq qual to the infiltration NR N R NR NR NR rate e (see text section 6.11.1.2)

NUR REG/CR-6697 Att. C Averagge annual wind speed d (m/s) P 2S Bounded Log gnormal - N 1.445 0.24 19 1.4 13 4.2 Figure 4.5-1 6-83

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median For the e BFM analysis the Evapottranspiration coefficiient and Runoff coefficiient were set to zero to forcee the Precipitation parame eter to equal the infiltratiion rate.

This wa as necessary to incorpo orate the effect of season nal ground water elevatio on rise associated with the e Mississippi river stage.

Precipitaation (m/y) P 2S Unifo orm 0.25 3.0 05 NR NR Minimu um value of 0.25 is traditional infiltration rate based on Evapottranspiration coefficiient, Runoff coefficiient and site precipittation rate parame eters listed in the parame eter set for Soil DCGL.

The ma aximum value of 3.055 is the seasonal s high ground dwater elevation at thee site as driven by river stage..

Irrigation n (m/y) B 3D NAA Indust r Scenario rial NR N R NR NR Irrigation n mode B 3D NAA Indust r Scenario rial NR N R NR NR Site-sp pecific value to force the Pre ecipitation parameter Runoff ccoefficient P 2D 0 NR N R NR NR NR to equa al to the infiltration rate. Se ee section 6.11.1.2.

Watersh hed area for nearby sttream 2 P 3D 1.00E+06 RESR A Default AD NR N R NR NR or pond (m )

Accuracyy for water/soil

- 3D 1.00EE-03 RESR A Default AD NR N R NR NR computa ations 6-84

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Saturatted Zone Hydrolog gical Data 3 e Density o of saturated zone (g/ccm ) P 2D 1.766 Site-s p pecific NR N R NR NR e

Saturate ed zone total porosity P 1D 0.31 Site-s p pecific NR N R NR NR e

Saturate ed zone effective poroosity P 1D 0.288 Site-s p pecific NR N R NR NR Calcula ated values for sand Saturate ed zone field capacity P 3D 0.06 66 f NR N R NR NR soil typ pe e

Site-sppecific Saturate ed zone hydraulic P 1D 348222 NR N R NR NR conductiivity (m/y) 313 feeet/day = 34822 m/y e

Saturate ed zone hydraulic grad dient P 2D 0.004 45 S ite-sppecific value NR N R NR NR Site sppecific soil type sand Saturate ed zone b parameter P 2S Lognormmal-N NUREG G/CR-6697 Att. C -.0253 0.2 1 16 N A NA 0.97 Table 3.5-1 3

Assumed zero due to Water ta able drop rate (m/y) P 3D 0 hydraulic connectivity with NR N R NR NR Mississ sippi river.

6-85

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Site-sppecific distribution Existingg industrial water supply wells onsite at depth of 116 and 129 below ground d surface (the 129 depth equals e 33.1 m below the watter table). 33.1 m assume ed to be maximum well deepth.

Minimu um well depth assume ed to be represented Well pummp intake depth (m be elow P 2S Triangular by nom minal 20 screen depthh 6.08 19.6 33.1 NR 10 water tab ble)

(6.08 m) m from top of water table.

Mode is mid-point between 6.08m and 33.1 m which is 19.6 m.

Note thhat the site-specific distribu ution is reasonably similar to the NUREG-6697 ution values of 6, 10, distribu and 30 for the triangular ution.

distribu Model: NNondispersion (ND) or Mass- P 3D ND D Applic a able to moving NR N R NR NR Balance (MB) ground dwater 6-86

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median NUREG G/CR-6697, Att. C providees no recommended value due d to high variability..

Industrrial Scenario pump rate deepends on industry.

3 Genera al water usage rate Well pummping rate (m /y) P 2S Unifoorm 328.7 164 3 3.5 NR NR 986.1 for fourr persons is 328.7 3

m /yr (NNUREG-6697, Table 3.10-1)) which is assumed too be minimum industrial rate.

Maximu um industrial rate assume ed to supply 20 workers which equals 3

1643.5 m /yr.

Unsatu urated Zone Hydro ological Data Number of unsaturated zone strata P 3D 1 Site-sppecific NR N R NR NR Unsat. zzone thickness (m) P 1D Variable Struct u specific ure NR N R NR NR 3 e Unsat. zzone soil density (g/cm m)P 2D 1.766 Site sp pecific NR N R NR NR e

Unsat. zzone total porosity P 2D 0.31 Site sp pecific NR N R NR NR e

Unsat. zzone effective porosity yP 2D 0.288 Site sp pecific NR N R NR NR Calcula ated values for sand Unsat. zzone field capacity P 3D 0.0666 f NR N R NR NR soil typ pe Unsat. zzone hydraulic conduc ctivity e P 2D 348222 S ite-sp pecific value NR N R NR NR (m/y)

Site sppecific soil type sand Unsat. zzone soil-specific b 0.97 P 2S Lognormmal-N NUREG G/CR-6697 Att. C -.0253 0.2 1 16 N A NA parametter Table 3.5-1 3

Occupa ancy NUREG G/CR-5512, Vol. 3 Table 5.1.1 5 mean value is 8400/y which equates to 23 3 3 Inhalatio on rate (m /y) M,B 3D 1917 m /d NR N R NR NR 3

Industrrial Scenario m /yr 3

=23 m /d ÷ 24h/d

2000 h/yy) 6-87

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median See See Seee See NUREG- NUREG-3 NURE EG- N NUREG-Mass loaading for inhalation (g g/m ) P,B 2S Continuous Linear NURE G G/CR-6697, Att. C 6697 6697 5 2.35E-05 6697 TTable 66 697 Table Table Table 4.6--1 4.6-1 4.6-1 4.6-1 RESRA AD Users Manual Exposurre duration B 3D 30 parame eter value not used inn NR NRR NR NR dose ca alculation NUREG G/CR-6697, Att. C Indoor dust filtration factor P,B 2S Unifo orm 0.15 0. 9 95 NR NR 0.55 Figure 7.1-1 NUREG G/CR-6697, Att. C Shielding g factor, external gammma P 2S Bounded Log gnormal-N Table 7.10-1 7 -1.3 0. 5 59 0.044 1 0.2725 NUREG G-6697 Att. C, Table 7.6-1 reecommends a median n indoor work day as 8.76 hoours/day. Assuming 5 days a week and 50 weeks per yeaars this equates to 2190 hours0.0253 days 0.608 hours 0.00362 weeks 8.33295e-4 months per year.

Majority of industrial work iss expecte ed to be indoors.

Fraction of time spent indoorssB 3D 0.18775 NR N R NR NR Consis stent with Table 2-3 off the Ussers Manual for g

RESRA AD Version 6 75%

of workk time is indoors and 25% ou utdoors.

The co orresponding RESRA AD indoor Fraction parame eter =

(2190*.75)/(24*365) = .18755 As explained in the basis forr the Indoor Fraction parame eter, the indoor time Fraction of time spent outdoo ors (on fraction n was set at 75% andd B 3D 0.06225 NR N R NR NR site) outdoo or time fraction at 25%.

(2190*.25)/(24*365) =

0.0625 Circulaar contaminated zone Shape faactor flag, external ga amma P 3D Circu ular assume ed for modeling NR N R NR NR purposes 6-88

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Ingestion, Dietary Fruits, no on-leafy vegetables, grain g

M,B 2D NAA Indust r Scenario rial NR N R NR NR consump ption (kg/y)

Leafy veegetable consumption n (kg/y) M,B 3D NAA Industrrial Scenario NR N R NR NR Milk consumption (L/y) M,B 2D NAA Industrrial Scenario NR N R NR NR M,B Meat and d poultry consumption (kg/y) 3D NAA Industrrial Scenario NR N R NR NR M,B Fish connsumption (kg/y) 3D NAA Industrrial Scenario NR N R NR NR M,B Other seeafood consumption (kg/y) 3D NAA Industrrial Scenario NR N R NR NR M,B NUREG G/CR-5512, Vol. 3 Soil inge estion rate (g/y) 2D 18.33 NR N R NR NR Table 6.87 6

NUREG G/CR-5512, Vol. 3 Table 6.87 6

Industrrial Scenario water supply assumed to be from an onsite well.

M,B Drinking water intake (L/y) 2D 3277 478 L/yy from NUREG/CR- NR N R NR NR 5512 corresponds to 1.31 L/d whiich is considered a conserv rvative value for 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months work day.

1.31 L//d

250 work days =

327 L/yy Contamiination fraction of drinnking All wateer assumed B,P 3D 1 NR N R NR NR water contamminated Contamiination fraction of hou usehold B,P 3 1 All wateer from well water (if used)

Contamiination fraction of livestock B,P 3D NAA Industrrial Scenario NR N R NR NR water Contamiination fraction of irrig gation B,P 3D NAA Industrrial Scenario NR N R NR NR water Contamiination fraction of aqu uatic B,P 2D NAA Industrrial Scenario NR N R NR NR food Contamiination fraction of plannt food B,P 3D NAA Industrrial Scenario NR N R NR NR Contamiination fraction of mea at B,P 3D NAA Industrrial Scenario NR N R NR NR 6-89

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Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Contamiination fraction of milk k B,P 3D NAA Industrrial Scenario NR N R NR NR Ingestion, Non-Dietary Livestocck fodder intake for me eat M 3D NAA Indust r Scenario rial NR N R NR NR (kg/day)

Livestocck fodder intake for miilk M 3D NAA Indust r Scenario rial NR N R NR NR (kg/day)

Livestocck water intake for me eat M 3D NAA Indust r Scenario rial NR N R NR NR (L/day)

Livestocck water intake for milk M 3D NAA Indust r Scenario rial NR N R NR NR (L/day)

Livestocck soil intake (kg/day) M 3D NAA Indust r Scenario rial NR N R NR NR Mass loa ading for foliar deposiition 3 P 3D NAA Indust r Scenario rial NR N R NR NR (g/m )

NUREG G/CR-6697, Att. C Depth off soil mixing layer (m)) P 2D Triangular 0 0.1 5 0.6 NR 0.15 Figure 3.12-1 Depth off roots (m) P 1D NAA Indust r Scenario rial NR N R NR NR Drinking water fraction from ground g

B,P 3D 1 Industrrial Scenario NR N R NR NR water Househo old water fraction from m

B,P 3 1 Industrrial Scenario NR N R NR NR ground w water (if used)

Livestocck water fraction from ground B,P 3D NAA Indust r Scenario rial NR N R NR NR water Irrigationn fraction from ground d water B,P 3D NAA Indust r Scenario rial NR N R NR NR Wet weig ght crop yield for Nonn-Leafy 2 P 2D NAA Indust r Scenario rial NR N R NR NR (kg/m )

Wet weig ght crop yield for Leafy 2 P 3D NAA Indust r Scenario rial NR N R NR NR (kg/m )

Wet weig ght crop yield for Fodder 2 P 3D NAA Indust r Scenario rial NR N R NR NR (kg/m )

Growing g Season for Non-Lea afy (y) P 3D NAA Indust r Scenario rial NR N R NR NR Growing g Season for Leafy (y) P 3D NAA Indust r Scenario rial NR N R NR NR Growing g Season for Fodder (y) P 3D NAA Indust r Scenario rial NR N R NR NR Transloccation Factor for Non--Leafy P 3D NAA Indust r Scenario rial NR N R NR NR Transloccation Factor for Leafy yP 3D NAA Indust r Scenario rial NR N R NR NR Transloccation Factor for Fodd der P 3D NAA Indust r Scenario rial NR N R NR NR Weatherring Removal Constan nt for P 2D NAA Indust r Scenario rial NR N R NR NR Vegetation (1/y) 6-90

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Wet Foliar Interception Fractio on for P 3D NAA Indust r Scenario rial NR N R NR NR Non-Lea afy Wet Foliar Interception Fractio on for P 2D NAA Indust r Scenario rial NR N R NR NR Leafy Wet Foliar Interception Fractio on for P 3D NAA Indust r Scenario rial NR N R NR NR Fodder Dry Foliaar Interception Fractioon for P 3D NAA Indust r Scenario rial NR N R NR NR Non-Lea afy Dry Foliaar Interception Fractioon for P 3D NAA Indust r Scenario rial NR N R NR NR Leafy Dry Foliaar Interception Fractioon for P 3D NAA Indust r Scenario rial NR N R NR NR Fodder Storage e times of contam minated foodstuffss (days):

Fruits, noon-leafy vegetables, and a

B 3D NAA Indust r Scenario rial NR N R NR NR grain Leafy ve egetables B 3D NAA Indust r Scenario rial NR N R NR NR Milk B 3D NAA Indust r Scenario rial NR N R NR NR Meat and d poultry B 3D NAA Indust r Scenario rial NR N R NR NR Fish B 3D NAA Indust r Scenario rial NR N R NR NR Crustace ea and mollusks B 3D NAA Indust r Scenario rial NR N R NR NR Well watter B 3D NAA Indust r Scenario rial NR N R NR NR Surface water B 3D NAA Indust r Scenario rial NR N R NR NR Livestocck fodder B 3D NAA Indust r Scenario rial NR N R NR NR Special Radionuclides (C C-14) 3 C-12 con ncentration in water (g g/cm ) P 3D NAA Indust r Scenario rial NR N R NR NR C-12 con ncentration in contamminated P 3D NAA Indust r Scenario rial NR N R NR NR soil (g/g))

Fraction of vegetation carbon from P 3D NAA Indust r Scenario rial NR N R NR NR soil Fraction of vegetation carbon from P 3D NAA Indust r Scenario rial NR N R NR NR air C-14 eva asion layer thickness in soil P 2D NAA Indust r Scenario rial NR N R NR NR (m)

C-14 eva asion flux rate from so oil P 3D NAA Indust r Scenario rial NR N R NR NR (1/sec)

C-12 eva asion flux rate from so oil P 3D NAA Indust r Scenario rial NR N R NR NR (1/sec) 6-91

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNCCERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Fraction of grain in beef cattle e feed B 3D NAA Indust r Scenario rial NR N R NR NR Fraction of grain in milk cow feed f B 3D NAA Indust r Scenario rial NR N R NR NR Dose C Conversion Factorrs (Inhalation mrem//pCi)

Ac-227 M 3D 6.70E+00 FGR 11 1 NR N R NR NR Am-241 M 3D 4.44E E-01 FGR 11 1 NR N R NR NR Am-243 M 3D 4.40E E-01 FGR 11 1 NR N R NR NR C-14 M 3D 2.09E E-06 FGR 11 1 NR N R NR NR Cm-243 M 3D 3.07E E-01 FGR 11 1 NR N R NR NR Cm-244 M 3D 2.48E E-01 FGR 11 1 NR N R NR NR Cm-245 M 3D 4.55E E-01 FGR 11 1 NR N R NR NR Cm-246 M 3D 4.51E E-01 FGR 11 1 NR N R NR NR Co-60 M 3D 2.19E E-04 FGR 11 1 NR N R NR NR Cs-134 M 3D 4.62E E-05 FGR 11 1 NR N R NR NR Cs-137 M 3 D 3.19E E-05 FGR11 1 NR N R NR NR Eu-152 M 3D 2.21E E-04 FGR 11 1 NR N R NR NR Eu-154 M 3D 2.86E E-04 FGR 11 1 NR N R NR NR Eu-155 M 3D 4.14E E-05 FGR 11 1 NR N R NR NR Gd-152 M 3D 2.43E E-01 FGR 11 1 NR N R NR NR H-3 M 3D 6.40E E-08 FGR 11 1 NR N R NR NR I-129 M 3D 1.74E E-04 FGR 11 1 NR N R NR NR Nb-94 M 3D 4.14E E-04 FGR 11 1 NR N R NR NR e

Nd-144 M 3D 7.04E E-02 ICRP6 0 NR N R NR NR Ni-59 M 3D 2.70E E-06 FGR 11 1 NR N R NR NR Ni-63 M 3D 6.29E E-06 FGR 11 1 NR N R NR NR Np-237 M 3D 5.40E E-01 FGR 11 1 NR N R NR NR Pa-231 M 3D 1.28E+00 FGR 11 1 NR N R NR NR Pb-210 M 3D 1.36E E-02 FGR 11 1 NR N R NR NR Po-210 M 3D 9.40E E-03 FGR 11 1 NR N R NR NR Pu-238 M 3D 3.92E E-01 FGR 11 1 NR N R NR NR 6-92

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Pu-239 M 3D 4.29E E-01 FGR 11 1 NR N R NR NR Pu-240 M 3D 4.29E E-01 FGR 11 1 NR N R NR NR Pu-241 M 3D 8.25E E-03 FGR 11 1 NR N R NR NR Pu-242 M 3D 4.11E E-01 FGR 11 1 NR N R NR NR Ra-226 M 3D 8.58E E-03 FGR 11 1 NR N R NR NR Ra-228 M 3D 4.77E E-03 FGR 11 1 NR N R NR NR e

Sm-148 M 3D 7.34E E-02 ICRP6 0 NR N R NR NR Sr-90 M 3D 1.30E E-03 FGR 11 1 NR N R NR NR Tc-99 M 3D 8.32E E-06 FGR 11 1 NR N R NR NR Th-228 M 3D 3.42E E-01 FGR 11 1 NR N R NR NR Th-229 M 3D 2.15E+00 FGR 11 1 NR N R NR NR Th-230 M 3D 3.26E E-01 FGR 11 1 NR N R NR NR Th232 M 3D 1.64e+ +00 FGR 11 1 NR N R NR NR U-233 M 3D 1.35E E-01 FGR 11 1 NR N R NR NR U-234 M 3D 1.32E E-01 FGR 11 1 NR N R NR NR U-235 M 3D 1.23E E-01 FGR 11 1 NR N R NR NR U-236 M 3D 1.25E E-01 FGR 11 1 NR N R NR NR U-238 M 3D 1.18E E-01 FGR 11 1 NR N R NR NR Dose CConversion Factorrs (Ingestion mrem/p pCi)

Ac-227 M 3D 1.41E E-02 FGR 11 1 NR N R NR NR Am-241 M 3D 3.64E E-03 FGR 11 1 NR N R NR NR Am-243 M 3D 3.62E E-03 FGR 11 1 NR N R NR NR C-14 M 3D 2.09E E-06 FGR 11 1 NR N R NR NR Cm-243 M 3D 2.51E E-03 FGR 11 1 NR N R NR NR Cm-244 M 3D 2.02E E-03 FGR 11 1 NR N R NR NR Cm-245 M 3D 3.74E E-03 FGR 11 1 NR N R NR NR Cm-246 M 3D 3.70E E-03 FGR 11 1 NR N R NR NR Co-60 M 3D 2.69E E-05 FGR 11 1 NR N R NR NR Cs-134 M 3D 7.33E E-05 FGR 11 1 NR N R NR NR Cs-137 M 3D 5.00E E-05 FGR 11 1 NR N R NR NR 6-93

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Eu-152 M 3D 6.48E E-06 FGR 11 1 NR N R NR NR Eu-154 M 3D 9.55E E-06 FGR 11 1 NR N R NR NR Eu-155 M 3D 1.53E E-06 FGR 11 1 NR N R NR NR Gd-152 M 3D 1.61E E-04 FGR 11 1 NR N R NR NR H-3 M 3D 6.40E E-08 FGR 11 1 NR N R NR NR I-129 M 3D 2.76E E-04 FGR 11 1 NR N R NR NR Nb-94 M 3D 7.14E E-06 FGR 11 1 NR N R NR NR e

Nd-144 M 3D 1.51E E-04 ICRP6 0 NR N R NR NR Ni-59 M 3D 2.10E E-07 FGR 11 1 NR N R NR NR Ni-63 M 3D 5.77E E-07 FGR 11 1 NR N R NR NR Np-237 M 3D 4.44E E-03 FGR 11 1 NR N R NR NR Pa-231 M 3D 1.06E E-02 FGR 11 1 NR N R NR NR Pb-210 M 3D 5.37E E-03 FGR 11 1 NR N R NR NR Po-210 M 3D 1.90E E-03 FGR 11 1 NR N R NR NR Pu-238 M 3D 3.20E E-03 FGR 11 1 NR N R NR NR Pu-239 M 3D 3.54E E-03 FGR 11 1 NR N R NR NR Pu-240 M 3D 3.54E E-03 FGR 11 1 NR N R NR NR Pu-241 M 3D 6.84E E-05 FGR 11 1 NR N R NR NR Pu-242 M 3D 3.36E E-03 FGR 11 1 NR N R NR NR Ra-226 M 3D 1.32E E-03 FGR 11 1 NR N R NR NR Ra-228 M 3D 1.44E E-03 FGR 11 1 NR N R NR NR e

Sm-148 M 3D 1.58E E-04 ICRP6 0 NR N R NR NR Sr-90 M 3D 1.42E E-04 FGR 11 1 NR N R NR NR Tc-99 M 3D 1.46E E-06 FGR 11 1 NR N R NR NR Th-228 M 3D 3.96E E-04 FGR 11 1 NR N R NR NR Th-229 M 3D 3.53E E-03 FGR 11 1 NR N R NR NR Th-230 M 3D 5.48E E-04 FGR 11 1 NR N R NR NR Th-232 M 3D 2.73E E-03 FGR 11 1 NR N R NR NR U-233 M 3D 2.89E E-04 FGR 11 1 NR N R NR NR U-234 M 3D 2.83E E-04 FGR 11 1 NR N R NR NR 6-94

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Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median U-235 M 3D 2.66E E-04 FGR 11 1 NR N R NR NR U-236 M 3D 2.69E E-04 FGR 11 1 NR N R NR NR U-238 M 3D 2.55E E-04 FGR 11 1 NR N R NR NR Plant T Transfer Factors (ppCi/g plant)/(pCi/g so oil)

Ac-227 P 1D NAA Indust r Scenario rial NR N R NR NR Am-241 P 1D NAA Indust r Scenario rial NR N R NR NR Am-243 P 1D NAA Indust r Scenario rial NR N R NR NR C-14 P 1D NAA Indust r Scenario rial NR N R NR NR Cm-243 P 1D NAA Indust r Scenario rial NR N R NR NR Cm-244 P 1D NAA Indust r Scenario rial NR N R NR NR Co-60 P 1D NAA Indust r Scenario rial NR N R NR NR Cs-134 P 1D NAA Indust r Scenario rial NR N R NR NR Cs-137 P 1D NAA Indust r Scenario rial NR N R NR NR Eu-152 P 1D NAA Indust r Scenario rial NR N R NR NR Eu-154 P 1D NAA Indust r Scenario rial NR N R NR NR Fe-55 P 1D NAA Indust r Scenario rial NR N R NR NR Gd-152 P 1D NAA Indust r Scenario rial NR N R NR NR H-3 P 1D NAA Indust r Scenario rial NR N R NR NR Nb-94 P 1D NAA Indust r Scenario rial NR N R NR NR Nd-144 P 1D NAA Indust r Scenario rial NR N R NR NR Ni-59 P 1D NAA Indust r Scenario rial NR N R NR NR Ni-63 P 1D NAA Indust r Scenario rial NR N R NR NR Np-237 P 1D NAA Indust r Scenario rial NR N R NR NR Pa-231 P 1D NAA Indust r Scenario rial NR N R NR NR Pb-210 P 1D NAA Indust r Scenario rial NR N R NR NR Pm-147 P 1D NAA Indust r Scenario rial NR N R NR NR Po-210 P 1D NAA Indust r Scenario rial NR N R NR NR Pu-238 P 1D NAA Indust r Scenario rial NR N R NR NR Pu-239 P 1D NAA Indust r Scenario rial NR N R NR NR Pu-240 P 1D NAA Indust r Scenario rial NR N R NR NR 6-95

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License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Pu-241 P 1D NAA Indust r Scenario rial NR N R NR NR Ra-226 P 1D NAA Indust r Scenario rial NR N R NR NR Ra-228 P 1D NAA Indust r Scenario rial NR N R NR NR Sb-125 P 1D NAA Indust r Scenario rial NR N R NR NR Sm-148 P 1D NAA Indust r Scenario rial NR N R NR NR Sr-90 P 1D NAA Indust r Scenario rial NR N R NR NR Tc-99 P 1D NAA Indust r Scenario rial NR N R NR NR Th-228 P 1D NAA Indust r Scenario rial NR N R NR NR Th-229 P 1D NAA Indust r Scenario rial NR N R NR NR Th-230 P 1D NAA Indust r Scenario rial NR N R NR NR Th-232 P 1D NAA Indust r Scenario rial NR N R NR NR U-233 P 1D NAA Indust r Scenario rial NR N R NR NR U-234 P 1D NAA Indust r Scenario rial NR N R NR NR U-235 P 1D NAA Indust r Scenario rial NR N R NR NR U-236 P 1D NAA Indust r Scenario rial NR N R NR NR Meat Trransfer Factors (p pCi/kg)/(pCi/d)

Ac-227 P 2D NAA Indust r Scenario rial NR N R NR NR Ag-108mm P 2D NAA Indust r Scenario rial NR N R NR NR Am-241 P 2D NAA Indust r Scenario rial NR N R NR NR Am-243 P 2D NAA Indust r Scenario rial NR N R NR NR C-14 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-243 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-244 P 2D NAA Indust r Scenario rial NR N R NR NR Co-60 P 2D NAA Indust r Scenario rial NR N R NR NR Cs-134 P 2D NAA Indust r Scenario rial NR N R NR NR Cs-137 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-152 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-154 P 2D NAA Indust r Scenario rial NR N R NR NR Fe-55 P 2D NAA Indust r Scenario rial NR N R NR NR Gd-152 P 2D NAA Indust r Scenario rial NR N R NR NR 6-96

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median H-3 P 2D NAA Indust r Scenario rial NR N R NR NR Nb-94 P 2D NAA Indust r Scenario rial NR N R NR NR Nd-144 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-59 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-63 P 2D NAA Indust r Scenario rial NR N R NR NR Np-237 P 2D NAA Indust r Scenario rial NR N R NR NR Pa-231 P 2D NAA Indust r Scenario rial NR N R NR NR Pb-210 P 2D NAA Indust r Scenario rial NR N R NR NR Po-210 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-238 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-239 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-240 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-241 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-226 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-228 P 2D NAA Indust r Scenario rial NR N R NR NR Sb-125 P 2D NAA Indust r Scenario rial NR N R NR NR Sm-148 P 1D NAA Indust r Scenario rial NR N R NR NR Sr-90 P 2D NAA Indust r Scenario rial NR N R NR NR Tc-99 P 2D NAA Indust r Scenario rial NR N R NR NR Th-228 P 2D NAA Indust r Scenario rial NR N R NR NR Th-229 P 2D NAA Indust r Scenario rial NR N R NR NR Th-230 P 2D NAA Indust r Scenario rial NR N R NR NR Th-232 P 2D NAA Indust r Scenario rial NR N R NR NR U-233 P 2D NAA Indust r Scenario rial NR N R NR NR U-234 P 2D NAA Indust r Scenario rial NR N R NR NR U-235 P 2D NAA Indust r Scenario rial NR N R NR NR U-236 P 2D NAA Indust r Scenario rial NR N R NR NR Milk Trransfer Factors (pCCi/L)/(pCi/d)

Ac-227 P 2D NAA Indust r Scenario rial NR N R NR NR Am-241 P 2D NAA Indust r Scenario rial NR N R NR NR Am-243 P 2D NAA Indust r Scenario rial NR N R NR NR 6-97

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median C-14 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-243 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-244 P 2D NAA Indust r Scenario rial NR N R NR NR Co-60 P 2D NAA Indust r Scenario rial NR N R NR NR Cs-134 P 2D NAA Indust r Scenario rial NR N R NR NR Cs-137 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-152 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-154 P 2D NAA Indust r Scenario rial NR N R NR NR Fe-55 P 2D NAA Indust r Scenario rial NR N R NR NR Gd-152 P 2D NAA Indust r Scenario rial NR N R NR NR H-3 P 2D NAA Indust r Scenario rial NR N R NR NR Nb-94 P 2D NAA Indust r Scenario rial NR N R NR NR Nd-144 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-59 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-63 P 2D NAA Indust r Scenario rial NR N R NR NR Np-237 P 2D NAA Indust r Scenario rial NR N R NR NR Pa-231 P 2D NAA Indust r Scenario rial NR N R NR NR Pb-210 P 2D NAA Indust r Scenario rial NR N R NR NR Po-210 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-238 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-239 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-240 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-241 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-226 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-228 P 2D NAA Indust r Scenario rial NR N R NR NR Sm-148 P 2D NAA Indust r Scenario rial NR N R NR NR Sr-90 P 2D NAA Indust r Scenario rial NR N R NR NR Tc-99 P 2D NAA Indust r Scenario rial NR N R NR NR Th-228 P 2D NAA Indust r Scenario rial NR N R NR NR Th-229 P 2D NAA Indust r Scenario rial NR N R NR NR 6-98

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Th-230 P 2D NAA Indust r Scenario rial NR N R NR NR Th-232 P 2D NAA Indust r Scenario rial NR N R NR NR U-233 P 2D NAA Indust r Scenario rial NR N R NR NR U-234 P 2D NAA Indust r Scenario rial NR N R NR NR U-235 P 2D NAA Indust r Scenario rial NR N R NR NR U-236 P 2D NAA Indust r Scenario rial NR N R NR NR Bioacccumulation Factors s for Fish ((pCi/kg)/(pCi/L))

Ac-227 P 2D NAA Indust r Scenario rial NR N R NR NR Am-241 P 2D NAA Indust r Scenario rial NR N R NR NR Am-243 P 2D NAA Indust r Scenario rial NR N R NR NR C-14 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-243 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-244 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-245 P 2D NAA Indust r Scenario rial NR N R NR NR Cm-246 P 2D NAA Indust r Scenario rial NR N R NR NR Co-60 P 2D NAA Indust r Scenario rial NR N R NR NR Cs-137 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-152 P 2D NAA Indust r Scenario rial NR N R NR NR Eu-154 P 2D NAA Indust r Scenario rial NR N R NR NR Gd-152 P 2D NAA Indust r Scenario rial NR N R NR NR H-3 P 2D NAA Indust r Scenario rial NR N R NR NR I-129 P 2D NAA Indust r Scenario rial NR N R NR NR Nb-94 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-59 P 2D NAA Indust r Scenario rial NR N R NR NR Ni-63 P 2D NAA Indust r Scenario rial NR N R NR NR Np-237 P 2D NAA Indust r Scenario rial NR N R NR NR Pa-231 P 2D NAA Indust r Scenario rial NR N R NR NR Po-210 P 2D NAA Indust r Scenario rial NR N R NR NR Pb-210 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-238 P 2D NAA Indust r Scenario rial NR N R NR NR 6-99

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PARRAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Pu-239 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-240 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-241 P 2D NAA Indust r Scenario rial NR N R NR NR Pu-242 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-226 P 2D NAA Indust r Scenario rial NR N R NR NR Ra-228 P 2D NAA Indust r Scenario rial NR N R NR NR Sr-90 P 2D NAA Indust r Scenario rial NR N R NR NR Th-228 P 2D NAA Indust r Scenario rial NR N R NR NR Th-229 P 2D NAA Indust r Scenario rial NR N R NR NR Th-230 P 2D NAA Indust r Scenario rial NR N R NR NR Th-232 P 2D NAA Indust r Scenario rial NR N R NR NR U-233 P 2D NAA Indust r Scenario rial NR N R NR NR U-234 P 2D NAA Indust r Scenario rial NR N R NR NR U-235 P 2D NAA Indust r Scenario rial NR N R NR NR U-236 P 2D NAA Indust r Scenario rial NR N R NR NR U-238 P 2D NAA Indust r Scenario rial NR N R NR NR Bioacccumulation Factors s for Crustacea/ Mollusks M ((pCi/kg)/(pCi/L))

Ac-227 P 3D NAA Industrrial Scenario NR N R NR NR Am-241 P 3D NAA Industrrial Scenario NR N R NR NR Am-243 P 3D NAA Industrrial Scenario NR N R NR NR C-14 P 3D NAA Industrrial Scenario NR N R NR NR Cm-243 P 3D NAA Industrrial Scenario NR N R NR NR Cm-244 P 3D NAA Industrrial Scenario NR N R NR NR Cm-245 P 3D NAA Industrrial Scenario NR N R NR NR Cm-246 P 3D NAA Industrrial Scenario NR N R NR NR Co-60 P 3D NAA Industrrial Scenario NR N R NR NR Cs-137 P 3D NAA Industrrial Scenario NR N R NR NR Eu-152 P 3D NAA Industrrial Scenario NR N R NR NR Eu-154 P 3D NAA Industrrial Scenario NR N R NR NR Gd-152 P 3D NAA Industrrial Scenario NR N R NR NR 6-100

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median H-3 P 3D NAA Industrrial Scenario NR N R NR NR I-129 P 3D NAA Industrrial Scenario NR N R NR NR Nb-94 P 3D NAA Industrrial Scenario NR N R NR NR Ni-59 P 3D NAA Industrrial Scenario NR N R NR NR Ni-63 P 3D NAA Industrrial Scenario NR N R NR NR Np-237 P 3D NAA Industrrial Scenario NR N R NR NR Pa-231 P 3D NAA Industrrial Scenario NR N R NR NR Pb-210 P 3D NAA Industrrial Scenario NR N R NR NR Po-210 P SD NAA Industrrial Scenario NR N R NR NR Pu-238 P 3D NAA Industrrial Scenario NR N R NR NR Pu-239 P 3D NAA Industrrial Scenario NR N R NR NR Pu-240 P 3D NAA Industrrial Scenario NR N R NR NR Pu-241 P 3D NAA Industrrial Scenario NR N R NR NR Pu-242 P 3D NAA Industrrial Scenario NR N R NR NR Ra-226 P 3D NAA Industrrial Scenario NR N R NR NR Ra-228 P 3D NAA Industrrial Scenario NR N R NR NR Sr-90 P 3D NAA Industrrial Scenario NR N R NR NR Th-228 P 3D NAA Industrrial Scenario NR N R NR NR Th-229 P 3D NAA Industrrial Scenario NR N R NR NR Th-230 P 3D NAA Industrrial Scenario NR N R NR NR Th-232 P 3D NAA Industrrial Scenario NR N R NR NR U-233 P 3D NAA Industrrial Scenario NR N R NR NR U-234 P 3D NAA Industrrial Scenario NR N R NR NR U-235 P 3D NAA Industrrial Scenario NR N R NR NR U-236 P 3D NAA Industrrial Scenario NR N R NR NR U-238 P 3D NAA Industrrial Scenario NR N R NR NR Graphics Parameters Number of points 32 RESR A Default AD NR N R NR NR Spacing log g RESR A Default AD NR N R NR NR Time inttegration parameters 6-101

La Croosse Boiling Waater Reactor L

License Termination Plan R

Revision 0 BFM INSIT TUgw: RESRAD PAR RAMETERS FOR UNC CERTAINTY ANALY YSIS a b c d Parameter (unit) Type Priority Treatme ent Value/Disttribution Basis Distribution's s Statistical Parametters 1 2 3 4 Mean/

Median Maximum m number of points fo or dose 17 RESR A Default AD NR N R NR NR N

Notes:

a P = physical, B = behaavioral, M = metabolic; (see NUREG/CR-6697 7, Attachment B, Table 4.)

b 1 = high-priority parammeter, 2 = medium-prio ority parameter, 3 = low w-priority parameter (seee NUREG/CR-6697, Atttachment B, Table 4.1))

c D = deterministic, S = stochastic d Distributions Statisticaal Parameters:

L Lognormal-n: 1= mean, 2 = standard deviation B

Bounded lognormal-n: 1= 1 mean, 2 = standard deviation, d 3 = minimum m, 4 = maximum T

Truncated lognormal-n: 1= mean, 2 = standard deviation, 3 = lower qu uantile, 4 = upper quanttile B

Bounded normal: 1 = mean, m 2 = standard deviaation, 3 = minimum, 4 = maximum B

Beta: 1 = minimum, 2 = maximum, 3 = P-valuee, 4 = Q-value T

Triangular: 1 = minimum m, 2 = mode, 3 = maxim mum U

Uniform: 1 = minimum,, 2 = maximum e Sm-14 48 an ND-144 not listed d in RESRAD FGR 11 DCF D file e

Reference:

Haley and Aldrich, Inc., "Hydrogeeological Investigation Report La Crosse Boilling Water Reactor, Dairyland Power Cooperaative, Genoa, WI Januaary 2015 f ZionSolutions Techniccal Support Document 14-003, Conestoga Rov vers & Associates (CRA A) Report, Zion Hydrog geologic Investigation R Report g Argonne National Lab boratory, Users Manu ual for RESRAD Version 6, ANL/EAD 4, July y 2001 6-102

La Crossse Boiling Water W Reactorr License Termination T Plant Revision n0 ATTACHMENT 6-3 Dosee Contributtion Percenttage for Inittial Suite Raadionuclidees and Deterrmination of Aggreg gate Dose Percentage P from f Insigniificant Dosee Contributors 6-103

La Crosse Boiling Wateer Reactor License Termination Pllant Revisionn 0 Table 200 from Referen nce 5 ( TSD RS--TD-313196-00 01) - Dose Contribution per R ROC per Scenarrio Sooil DCGLs Rx Bldg Grouundwater Rx Bldg Drilling Spooils Rx Bldg Excavation WTB Grouundwater WTB Drilling Spooils WTB W Excavation mrem/yr Dose Fraction mrem/yr Dose Fraction mrem/yr m Dose Fraction F mrem/y yr Dose Fractionn mrem/yr Dose Fraction mrem/yr Dosee Fraction mrem m/yr Dose Fractioon H-3 3.30E-09 0.000% 3.14E-06 0.002% 5.05E-12 5 0.0000% 2.61E-0 09 0.000% 1.11E-06 0.002% 4.96E-11 0..000% 3.45E-08 0.000%

C-14 2.41E-09 0.000% 6.66E-05 0.033% 8.23E-12 8 0.0000% 1.91E-0 09 0.000% 2.85E-05 0.045% 8.10E-11 0..000% 2.52E-08 0.000%

Fe-55 7.21E-09 0.000% 6.96E-06 0.003% 7.14E-12 7 0.0000% 5.70E-0 09 0.000% 4.91E-13 0.000% 7.02E-11 0..000% 7.52E-08 0.000%

Ni-59 9.98E-09 0.000% 2.59E-06 0.001% 1.43E-11 1 0.0000% 7.89E-0 09 0.000% 4.80E-06 0.008% 1.41E-10 0..000% 1.05E-07 0.000%

Co-60 2.38E-02 5.911% 5.79E-03 2.858% 1.42E-03 1 5.3774% 1.88E-0 02 5.903% 7.91E-04 1.238% 1.39E-02 5.376% 2.49E-01 5.908%

Ni-63 2.12E-07 0.000% 5.47E-05 0.027% 2.82E-10 2 0.0000% 1.67E-0 07 0.000% 1.63E-05 0.026% 2.78E-09 0..000% 2.21E-06 0.000%

Sr-90 3.45E-05 0.009% 4.45E-02 21.993% 1.86E-06 1 0.0007% 2.72E-0 05 0.009% 2.58E-02 40.445% 1.83E-05 0.007% 3.60E-04 0.009%

Nb-94 1.02E-04 0.025% 5.26E-06 0.003% 6.57E-06 6 0.0225% 8.10E-0 05 0.025% 4.22E-06 0.007% 6.46E-05 0..025% 1.07E-03 0.025%

Tc-99 1.86E-06 0.000% 1.54E-05 0.008% 4.64E-11 4 0.0000% 1.47E-0 06 0.000% 3.62E-06 0.006% 4.57E-10 0..000% 1.95E-05 0.000%

Cs-137 3.77E-01 93.653% 1.50E-01 74.095% 2.48E-02 2 94.2217% 2.98E-0 01 93.661% 3.55E-02 55.598% 2.44E-01 94.213% 3.95E+

+00 93.657%

Eu-152 8.21E-04 0.204% 1.06E-05 0.005% 5.10E-05 5 0.1994% 6.48E-0 04 0.204% 3.31E-09 0.000% 5.03E-04 0..194% 8.59E-03 0.204%

Eu-154 7.61E-04 0.189% 1.29E-05 0.006% 4.66E-05 4 0.1777% 6.02E-0 04 0.189% 2.85E-11 0.000% 4.59E-04 0..177% 7.96E-03 0.189%

Eu-155 1.01E-05 0.003% 1.14E-06 0.001% 9.11E-07 9 0.0003% 7.97E-0 06 0.003% 4.49E-17 0.000% 8.92E-06 0..003% 1.06E-04 0.003%

Pu-238 2.14E-06 0.001% 4.63E-04 0.229% 1.56E-08 1 0.0000% 1.69E-0 06 0.001% 7.38E-05 0.115% 1.53E-07 0..000% 2.23E-05 0.001%

Pu-239/240* 2.18E-06 0.001% 4.77E-04 0.235% 1.58E-08 1 0.0000% 1.73E-0 06 0.001% 8.75E-04 1.369% 1.55E-07 0..000% 2.28E-05 0.001%

Pu-241 2.07E-06 0.001% 2.10E-04 0.104% 5.05E-08 5 0.0000% 1.64E-0 06 0.001% 8.87E-05 0.139% 4.95E-07 0..000% 2.17E-05 0.001%

Am-241 8.29E-06 0.002% 7.07E-04 0.349% 2.54E-07 2 0.0001% 6.56E-0 06 0.002% 5.09E-04 0.797% 2.50E-06 0..001% 8.65E-05 0.002%

Am-243 5.21E-06 0.001% 7.58E-05 0.037% 3.74E-07 3 0.0001% 4.14E-0 06 0.001% 1.33E-04 0.208% 3.67E-06 0..001% 5.47E-05 0.001%

Cm-243/2444* 4.11E-06 0.001% 2.26E-05 0.011% 2.80E-07 2 0.0001% 3.25E-0 06 0.001% 9.42E-08 0.000% 2.75E-06 0..001% 4.30E-05 0.001%

Insignificannt contributor dose d

0.427% 1.054% 0.4003% 0.427% 2.179% 0..404% 0.427%

percentage based b

on mixture Insignificannt contributor dose d

2.60E-02 1.25E+01 1.63E+00 1 01 1.97E+0 7.87E-01 3.19E+00 +01 5.19E+

percentage based b

on actual daata Insignificannt contributor dose d

0.0004% 0.528% 0.0226% 0.336% 0.086% 0..051% 0.886%

based on acttual data (mrem//yr) 6-104

La Crosse Boiling Wateer Reactor License Termination Pllant Revisionn 0 Table 20 from Reference 5 (TSD RS-TD-313196-001) (ccont.) - Dose Contribution peer ROC per Sceenario Remainiing Basements Remaining Basements Drilling WGTV Groundwater G WGTV Drilling Spoils S WGTV Excavation Remaaining Basements Excavvation Grooundwater Spoils mrem/yr Dose Fraction mrem/yr Do ose Fraction mreem/yr Dose Fracction mrem/yr Dose Fraction mrem/yr Dose D Fraction mrrem/yr Dose Fraaction H-3 4.24E-07 0.001% 2.57E-11 0.000% 1.155E-08 0.000%

% 1.09E-06 0.007% 5.66E-12 0.000% 5.778E-09 0.000 0%

C-14 9.34E-06 0.018% 4.19E-11 0.000% 8.422E-09 0.000%

% 2.75E-05 0.177% 9.21E-12 0.000% 4.223E-09 0.000 0%

Fe-55 0.00E+00 0.000% 3.64E-11 0.000% 2.511E-08 0.000%

% 1.50E-14 0.000% 8.02E-12 0.000% 1.226E-08 0.000 0%

Ni-59 1.08E-06 0.002% 7.27E-11 0.000% 3.499E-08 0.000%

% 7.57E-07 0.005% 1.61E-11 0.000% 1.775E-08 0.000 0%

Co-60 1.43E-03 2.712% 7.21E-03 5.380% 8.311E-02 5.916%% 1.66E-04 1.072% 1.59E-03 5.376% 4.118E-02 5.911 1%

Ni-63 2.06E-06 0.004% 1.43E-09 0.000% 7.400E-07 0.000%

% 2.11E-06 0.014% 3.16E-10 0.000% 3.771E-07 0.000 0%

Sr-90 9.70E-03 18.424% 9.43E-06 0.007% 1.211E-04 0.009%% 1.05E-02 67.909% 2.09E-06 0.007% 6.004E-05 0.009 9%

Nb-94 9.68E-07 0.002% 3.34E-05 0.025% 3.577E-04 0.025%

% 6.73E-07 0.004% 7.37E-06 0.025% 1.779E-04 0.025 5%

Tc-99 1.81E-06 0.003% 2.36E-10 0.000% 6.511E-06 0.000%

% 3.92E-06 0.025% 5.21E-11 0.000% 3.226E-06 0.000 0%

Cs-137 4.09E-02 77.619% 1.26E-01 94.210%

9 1.32E+00 93.648%

% 4.51E-03 29.109% 2.78E-02 94.213% 6.662E-01 93.6544%

Eu-152 7.64E-07 0.001% 2.60E-04 0.194% 2.877E-03 0.204%

% 2.24E-10 0.000% 5.73E-05 0.194% 1.444E-03 0.204 4%

Eu-154 3.59E-07 0.001% 2.38E-04 0.177% 2.666E-03 0.189%

% 1.21E-12 0.000% 5.23E-05 0.177% 1.333E-03 0.189 9%

Eu-155 3.79E-09 0.000% 4.62E-06 0.003% 3.522E-05 0.003%

% 6.84E-19 0.000% 1.02E-06 0.003% 1.777E-05 0.003 3%

Pu-238 1.15E-04 0.219% 7.92E-08 0.000% 7.455E-06 0.001%

% 8.99E-06 0.058% 1.75E-08 0.000% 3.775E-06 0.001 1%

Pu-239/240* 1.99E-04 0.378% 8.02E-08 0.000% 7.611E-06 0.001%

% 1.38E-04 0.891% 1.77E-08 0.000% 3.882E-06 0.001 1%

Pu-241 5.32E-05 0.101% 2.57E-07 0.000% 7.222E-06 0.001%

% 2.07E-05 0.134% 5.66E-08 0.000% 3.664E-06 0.001 1%

Am-241 2.41E-04 0.457% 1.29E-06 0.001% 2.899E-05 0.002%

% 7.14E-05 0.461% 2.85E-07 0.001% 1.445E-05 0.002 2%

Am-243 3.12E-05 0.059% 1.90E-06 0.001% 1.822E-05 0.001%

% 2.06E-05 0.133% 4.18E-07 0.001% 9.114E-06 0.001 1%

Cm-243/244* 3.17E-08 0.000% 1.42E-06 0.001% 1.444E-05 0.001%

% 1.24E-07 0.001% 3.14E-07 0.001% 7.119E-06 0.001 1%

Insignificant contributor dosee 1.246% 0.403% 0.428%

% 1.910% 0.403% 0.427 7%

percentage baseed on mixture Insignificant contributor dosee 2.93E+00 77.45E+00 7.81E+01 1.25E+00 2.38E+00 E+01 5.69E based on actuall data (mrem/yr)

Insignificant contributor dosee 0.146% 0.120% 1.336%

% 0.095% 0.038% 0.972 2%

percentage baseed on actual data 6-105

La Crossse Boiling Water W Reactorr License Termination T Plant Revisionn0 Table 222 from Referrence 5 (TS SD RS-TD-3 313196-001) - Insignificcant Contrib butor Dose Percent Using the Highest H Actiivity Cores WTB W Groundwwater WTB Drillling Spoils WTB B Excavation Dose Dose Dosse mrrem/yr mrem/yr mrem/yyr Fraction F Fraction Fraction H-3 1.59E-07 0.000% 7.14E-12 0.000% 4.95E-09 0.0000%

C-144 21E-05 2.2 0.035% 6.28E-11 0.000% 1.96E-08 0.0000%

Fe-55 5 92E-13 1.9 0.000% 2.74E-11 0.000% 2.94E-08 0.0000%

Ni-59 9 28E-06 6.2 0.010% 1.85E-10 0.000% 1.37E-07 0.0000%

Co-60 7.26E-04 1.147% 1.28E-02 5.002% 2.29E-001 5.4999%

Ni-63 3 83E-05 1.8 0.029% 3.11E-09 0.000% 2.48E-06 0.0000%

Sr-90 0 59E-02 2.5 40.855%

4 1.83E-05 0.007% 3.60E-004 0.0099%

Nb-94 2.30E-06 0.004% 3.51E-05 0.014% 5.81E-04 0.0144%

Tc-99 9 28E-06 1.2 0.002% 1.61E-10 0.000% 6.85E-06 0.0000%

Cs-1337 52E-02 3.5 55.694%

5 2.42E-01 94.749% 3.92E+000 94.2366%

Eu-1552 2.19E-09 0.000% 3.32E-04 0.130% 5.67E-03 0.1377%

Eu-1554 47E-11 1.4 0.000% 2.37E-04 0.093% 4.12E-03 0.0999%

Eu-1555 93E-17 2.9 0.000% 5.83E-06 0.002% 6.90E-05 0.0022%

Pu-2338 98E-05 5.9 0.095% 1.24E-07 0.000% 1.81E-05 0.0000%

Pu-239//240 29E-04 7.2 1.152% 1.29E-07 0.000% 1.90E-05 0.0000%

Pu-2441 5.33E-05 0.084% 2.98E-07 0.000% 1.30E-05 0.0000%

Am-24 41 87E-04 4.8 0.769% 2.39E-06 0.001% 8.27E-05 0.0022%

Am-24 43 84E-05 7.8 0.124% 2.17E-06 0.001% 3.23E-05 0.0011%

Cm-243/244 40E-08 5.4 0.000% 1.58E-06 0.001% 2.46E-05 0.0011%

2.304% 0.242% 0.2566%

Dose Based B on Inssignificant Dose D Based on Insignificantt Dose Basedd on Insignifficant Conceentrations Coontributor Concentrations C Contributorr Concentrattions Contribbutor

% Based on % Based onn % Baseed on (mrrem/yr) Dose (mrem/yr) Dose (mrem/yyr) Dosse 2.36E+00 0.218% 9.52E+00 0.092% 1.55E+002 1.5877%

6-106

L La Crosse Boilin ng Water Reactor L

License Termination Plant R

Revision 0 Table 24 2 from Refereence 5 ( TSD RS S-TD-313196-0 001) Buried Pip ping Dose Contrribution per R ROC per Scenarrio Buried Pipe Group p Excavation Buried Pipe Gro oup InSitu Circ Water Pipe EExcavation Circ Water Pippe InSitu mrem/yr Dose D Fraction mrem/yr Dose D Fraction mrem/yr D Dose Fraction mrem/yr D Dose Fraction H-3 1.52E-13 0.000006% 1.51E-12 0.002918% 1.13E-13 0.000004% 4.53E-12 0.022182%

C-14 2.68E-14 0.000001% 3.59E-11 0.069510% 2.67E-14 0.000001% 4.28E-11 0.209552%

Fe-55 4.93E-14 0.000002% 0.00E+00 0.000000% 3.78E-14 0.000001% 0.00E+00 0.000000%

Ni-59 6.83E-14 0.000003% 9.23E-13 0.001788% 5.24E-14 0.000002% 0.00E+00 0.000000%

Co-60 1.45E-07 5.588696% 1.34E-09 2.592108% 1.42E-07 5.580068% 2.48E-10 1.215574%

Ni-63 1.45E-12 0.000056% 1.72E-12 0.003333% 1.11E-12 0.000044% 4.07E-13 0.001991%

Sr-90 2.27E-10 0.008762% 1.55E-08 30.046145% 2.14E-10 0.008401% 1.31E-08 664.004473%

Nb-94 6.52E-10 0.025163% 8.23E-13 0.001593% 6.41E-10 0.025160% 8.18E-13 0.004008%

Tc-99 1.70E-12 0.000066% 6.43E-12 0.012456% 1.26E-12 0.000049% 2.06E-11 0.101008%

Cs-137 2.44E-06 93.988458% 3.42E-08 66.198432% 2.40E-06 993.998448% 6.70E-09 332.818795%

Eu-152 5.12E-09 0.197504% 6.39E-13 0.001238% 5.03E-09 0.197405% 6.45E-16 0.000003%

Eu-154 4.73E-09 0.182523% 3.00E-13 0.000581% 4.65E-09 0.182371% 5.72E-18 0.000000%

Eu-155 6.84E-11 0.002638% 3.17E-15 0.000006% 6.75E-11 0.002648% 9.61E-24 0.000000%

Pu-238 1.46E-11 0.000564% 9.65E-11 0.186737% 1.12E-11 0.000440% 1.39E-11 0.067971%

Pu-239/240 1.49E-11 0.000575% 1.69E-10 0.327211% 1.14E-11 0.000449% 1.69E-10 0.825476%

Pu-241 1.01E-11 0.000388% 5.95E-11 0.115147% 8.31E-12 0.000326% 2.77E-11 0.135521%

Am-241 5.62E-11 0.002168% 2.01E-10 0.389710% 4.62E-11 0.001813% 9.53E-11 0.466862%

Am-243 3.52E-11 0.001357% 2.62E-11 0.050785% 3.38E-11 0.001324% 2.57E-11 0.125811%

Cm-243/244 2.78E-11 0.001071% 1.57E-13 0.000304% 2.66E-11 0.001043% 1.58E-13 0.000774%

Insignificant Radionuclide 0.414% 1.163% 0.413% 1.961%

Dose Percent 6-107

ML16200A093: Difference between revisions

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