ML16200A086

Boiling Water Reactor License Termination Plan - Chapter 2 - Site Characterization, Rev. 0

ML16200A086
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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Download: ML16200A086 (83)

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LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 2 SITE CHARACTERIZATION

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

2. Site Characterizzation ................................................................................................................. 2-1 2.1. Historical Site S Assessm ment ................................................................................................. 2-2 2.1.1. Objectiives ................................................................................................................... 2-2 2.1.2. Method dology ............................................................................................................... 2-3 2.1.2.1. Preliminary Claassification ..................................................................................... 2-3 2.1.2.2. Doccument Reviiew ................................................................................................. 2-4 2.1.2.3. Licenses, Perm mits and Auth horizations .................................................................. 2-5 2.1.2.4. Perrsonnel Interrviews ............................................................................................. 2-5 2.1.2.5. Prooperty Inspecctions.............................................................................................. 2-5 2.1.3. Operatiional History y..................................................................................................... 2-6

4. Inciden 2.1.4 nts ...................................................................................................................... 2-6 2.1.4.1. Rad diological Sp pills ................................................................................................ 2-7 2.1.4.2. Cheemical Spillss ..................................................................................................... 2-8 2.1.5. Finding gs and Conclusions ........................................................................................... 2-8 2.1.6. Initial Survey S Areaas/Units and Classificatioon ........................................................... 2-9 2.1.6.1. Surrvey Areas ......................................................................................................... 2-9 2.1.6.2. Surrvey Units.......................................................................................................... 2-9 2.1.6.3. Claass 1 Open Land L Areas .................................................................................... 2-10 2.1.6.4. Claass 2 Open Land L Areas .................................................................................... 2-10 2.1.6.5. Claass 3 Open Land L Areas .................................................................................... 2-10 2.1.6.6. Non n-Impacted Open O Land Areas A ....................................................................... 2-11 2.1.6.7. Claass 1 Structurres................................................................................................ 2-11 2.1.6.8. Claass 2 and 3 Structures S ...................................................................................... 2-12 2.2. Characterization Approach ............................................................................................... 2-12 2.2.1. Data Quality Q Objecctives ............................................................................................ 2-14 2.2.2. Survey y Design ........................................................................................................... 2-14 2.2.2.1. Num mber of Stattic Measurem ments and/orr Samples ............................................. 2-15 2.2.2.2. Dettermination of o Static Meeasurement aand Sample L Locations ......................... 2-16 2.2.2.3. Scaan Coverage .................................................................................................... 2-16 2.2.2.4. Typ pes of Measu urements and d Samples ................................................................ 2-16 2.2.3. Instrummentation Selection, Use and Minimuum Detectabble Concenntrations (M MDCs) ........................................................................................... 2-18 2.2.3.1. Callibration........................................................................................................... 2-18 2.2.3.2. Insttrument Usee and Control ............................................................................... 2-19

4. Laboraatory Instrum 2.2.4 ment Method ds and Sensittivities .................................................. 2-19 2.2.5. Quality y Assurance ..................................................................................................... 2-19 2.3. Summary of Characterization Surveey Results ................................................................ 2-20 2.3.1. Backgrround Study..................................................................................................... 2-21 2.3.2. Potentiial Radionucclides of Con ncern......................................................................... 2-22 2.3.3. Non-Im mpacted Opeen Land Areaas ............................................................................. 2-22

4. Impacted Open Lan 2.3.4 nd Areas ...................................................................................... 2-24 2.3.4.1. Claass 1 Open Land L Areas .................................................................................... 2-25 2.3.4.2. Claass 2 Open Land L Areas .................................................................................... 2-26 2-i

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.3.4.3. Claass 3 Open Land L Areas .................................................................................... 2-27 2.3.5. Non-Im mpacted Stru uctures .......................................................................................... 2-29 2.3.6. Impacted Structurees and System ms ............................................................................ 2-30 2.3.6.1. Bassement Strucctures Below w 636 foot Ellevation ............................................... 2-30 2.3.6.2. Turrbine Buildin ng Tunnel..................................................................................... 2-31 2.3.6.3. LA ACBWR Adm ministration Building .................................................................. 2-31 2.3.7. Surfacee and Groundwater ......................................................................................... 2-32 2.3.7.1. Areea Groundwaater Use ....................................................................................... 2-32 2.3.7.2. Gro oundwater Flow .............................................................................................. 2-33 2.3.7.3. Previous Investtigations ....................................................................................... 2-34 2.3.7.4. On--Going Investigations ..................................................................................... 2-35 2.3.7.5. Sum mmary of Grroundwater Analytical A R Results .................................................. 2-35 2.4. Continuing Characterizaation ............................................................................................ 2-36 2.5. References ........................................................................................................................ 2-37 2-ii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF TABLE ES Table 2-1 1 LACBW WR Open Land Survey Units........................................................................ 2-39 Table 2-2 2 LACBW WR Structurral Survey Units U .......................................................................... 2-40 Table 2-3 3 Instrumment Types and a Nominall MDCs .................................................................... 2-42 Table 2-4 4 Off-Sitte Laboratory y Analyticall Methods annd Typical M MDCs ............................... 2-43 Table 2-5 5 2005 Dairyland D Baackground Sttudy for Soills .......................................................... 2-44 Table 2-6 6 Investiggative Levells for Cs-137 7 Based on B Background Studies ............................ 2-45 Table 2-7 7 Initial Suite S of LAC CBWR Site--Specific Ra dionuclides .......................................... 2-46 Table 2-8 8 Non-Im mpacted Opeen Land Surv vey Units - C Characterizaation Surveyy Summary ...................................................................................................... 2-47 Table 2-9 9 Non Im mpacted Coal Pile and So oil Samples - Test Amerrica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-49 Table 2-1 10 Impacted Class 1 Open O Land Survey S Units - Characterrization Survvey Summaary .................................................................................................................. 2-50 Table 2-1 11 Class 1 Concrete, Asphalt, A Sed diment and S Soil Samples - Test Ameerica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-51 Table 2-1 12 Impacted Class 2 Open O Land Survey S Units - Characterrization Surveyy Summary ...................................................................................................... 2-52 Table 2-1 13 Class 2 Asphalt, Seediment and Soil Samplees - Test Am merica Laboraatory Analyssis ................................................................................................. 2-53 Table 2-1 14 Impacted Class 3 Open O Land Survey S Units - Characterrization Surveyy Summary ...................................................................................................... 2-54 Table 2-1 15 Class 3 Asphalt, Seediment and Soil Samplees - Test Am merica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-55 Table 2-1 16 Concreete Core Isotopic Analysis Results................................................................. 2-56 Table 2-1 17 1983 Groundwater G Analysis fro om Temporaary Well-Pooint South off Turbine Buildinng .................................................................................................................... 2-60 Table 2-1 18 2013 Groundwater G Monitoring Results ................................................................... 2-61 Table 2-1 19 2014 Groundwater G Monitoring Results (pC Ci/L) ..................................................... 2-62 LIST OF O FIGURE RES Figure 2--1 LACBW WR Site Maap - Open Laand Survey U Units and Cllassification .................... 2-64 Figure 2--2 LACBW WR Site Maap - Building gs Identificaation ...................................................... 2-65 Figure 2--3 LACBW WR Site Draainage and Sewer S Map ............................................................... 2-66 Figure 2--4 LACBW WR LCE Ex xclusion Areea (Class 1) ............................................................... 2-67 Figure 2--5 Non Im mpacted Opeen Land Sam mpling Locatiions ...................................................... 2-68 Figure 2--6 Class 1 Open Land d Sampling Locations L .................................................................. 2-69 Figure 2--7 Class 2 Open Land d Sampling Locations L .................................................................. 2-70 Figure 2--8 Class 3 Open Land d Sampling Locations L .................................................................. 2-71 Figure 2--9 Concreete Core Sam mpling Locattions ......................................................................... 2-72 Figure 2--10 LACBWR Site - Typical T Geolo ogical Crosss-Section .............................................. 2-75 Figure 2--11 Ground dwater Samp pling Wells - LACBWR R Site .................................................... 2-76 2-iii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF ACRONYM MS AND AB BBREVIAT TIONS AEC Unitedd States Atomic Energy Commissionn ALARA As Loow As Reaso onably Achieevable bgs Beloww Ground Su urface CRD Control Rod Drive DCGL Derived Concentrration Guideline Levels DQO Data Quality Q Objeective EPA Unitedd States Env vironmental Protection P A Agency FCP Forced Circulation n Pump FESW Fuel Element E Storrage Well FRS Final Radiation Su urvey FSS Final Status Surveey G-1 Genoaa 1 Coal/Oil Station G-3 Genoaa 3 Fossil Sttation HSA Historrical Site Assessment HTD Hard-to-Detect IR Incideent Reports ISFSI Independent Spen nt Fuel Storaage Installatioon LACBW WR La Crrosse Boiling g Water Reacctor LER Licensee Event Reports LSA Low Specific S Activity LSE LACB BWR Site En nclosure LTP License Terminatiion Plan MARLA AP Multi--Agency Rad diological Laboratory L A Analytical Prootocols Mannual MARSA AME Multi--Agency Rad diation Surv vey and Asseessment of MMaterials andd Equipmentt Manu ual MARSSIIM Multi--Agency Rad diation Surv vey and Site Investigation Manual MDC Minimmal Detectab ble Concentrrations MDCR Minimmum Detectaable Count RateR MWe Megaw watt Electricc NIST Nationnal Institute of Standardds and Technnology 2-iv

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 NRC Unitedd States Nucclear Regulaatory Commiission ORC Operaational Revieew Committee PSDAR Shutdown Decommissioning Activitties Report Post-S QA Qualitty Assurancee QAPP Qualitty Assurancee Project Plaan QC Qualitty Control RCA Radio ologically Coontrolled Areea REMP oactive Effluent Monitoring Reports Radio ROC Radio onuclides of Concern RPV Reactor Pressure Vessel V

SRC Safety y Review Co ommittee STS Source Term Surv vey TSD Technnical Supporrt Document WDNR Wiscoonsin Departtment of Nattural Resourrces WGTV Wastee Gas Tank Vault V

WTB Wastee Treatment Building ZNPS Zion Nuclear N Pow wer Station 2-v

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Page Intenttionally Left ft Blank 2-vi

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0

2. Site S Chara acterization n In accorrdance with h the requirements off 10 CFR 500.82 (a)(9)(iii)(A) and tthe guidancce of Regulato ory Guide 1..179, Standa ard Format and Conteents for License Terminnation Planns for Nuclear Power Reeactors (1),, this chap pter providees a descrription of the radioloogical characterrization perfo formed at thee La Crosse Boiling B Watter Reactor ((LACBWR) site.

The purp pose of site characterizaation is to ennsure that thhe Final Raddiation Survey (FRS) w will be conducteed in all areeas where co ontamination n existed, reemains, or hhas the poteential to exiist or remain. The term F Final Radiattion Survey is from 100 CFR 50.82(9)(ii)(D) annd is used inn this License Termination T n Plan (LTP)) in order to acknowledgge the distinnction betweeen the two types of complliance survey ys that will be b performed d at LACBW WR. These surveys are; 1) a Final S Status Survey (FSS) for op pen land areeas and buried piping b ased on guiidance proviided in NUR REG-1575, Mu ulti-Agency Radiation Survey S and Site S Investiggation Manual (MARSS SIM) (2) andd 2) a Source Term T Surveey (STS) fo or below grround structtures to be backfilled prior to liccense terminatiion. See LTP P Chapter 5 for a descripption of the FRS.

The site characterization incorp porates the results r of innvestigationns and surveeys conducted to quantify the extent anda nature of o contamination at LA ACBWR. Inn addition, thhe results oof site characterrization survveys and anaalyses have been b and conntinue to bee used to identify areas oof the site that will require remediation n, as well ass to plan rem mediation m methodologiees, develop w waste classificaation and vollumes, and estimate e costts.

The chaaracterization n survey wasw designed d and execcuted using the guidannce provideed in NUREG--1575 (MA ARSSIM) and NURE EG-1757, Volume 2, Revision 11, Consoliddated Decommissioning Guidance G - Characteriza C ation, Surveey, and Determination of Radioloogical Criteria, Final Reporrt, (3). In ad ddition, surv veys were deesigned and executed inn accordancee with PG-EO-3 313196-SV-P PL-001, Ch haracterizatioon Survey P Plan for the La Crossse Boiling W Water Reactor (4), and GP P-EO-31319 96-QA-PL-00 01, Quality Assurance Project Plaan LACBWR R Site Characteerization Pro oject (QAPP P) (5) which describes ppolicy, organnization, funnctional activvities, the Data Quality Objjective (DQO O) process, and a measurees necessary to achieve qquality data. The informatiion obtained d from the characterizzation provi des guidancce for decoontaminationn and remediation planning g. Materials which weree shown to bbe contaminaated with raddioactive maaterial at concen ntrations greeater than th he unrestricteed release crriteria have been and wiill continue to be removed and properlly packaged for shipmen nt and dispossal.

The deco ommissionin ng approach for LACBW WR requires the demolittion, removaal and dispossal as waste off all LACB BWR buildiings, structu ures and coomponents (with the eexception of the LACBW WR Administtration build ding and Criib House) too a depth off at least 3 ffeet below ggrade.

None off the buildin ngs and stru uctures assoociated withh the Genoaa 3 Fossil S Station (G-33) are radiologiically impaccted such th hat they requ uire remedi al actions; therefore, nno remediatiion is planned and a these strructures, inccluding the G-3 G Crib Houuse, will rem main intact aand functional for G-3 pow wer operation ns. The pub blic roads annd railways that traversse the site aas well as seeveral minor strructures willl also remainn.

The majo or sub-gradee structures that t will be backfilled aand remain aat license terrmination arre the basementts of the Reeactor Buildiing, Waste Treatment T B Building (W WTB), Waste Gas Tank V Vault 2-1

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 (WGTV)) and the reemainder off the basemeent structurees located bbelow the 6336 foot elevvation (3 feet below grade)). These remaining stru uctures inclu lude the Pipping and Veentilation Tuunnel, Reactor/GGenerator Plant, P the onne foot thick k portion off the Chimnney Foundattion, the Tuurbine sump and d the Turbine pit.

In the Reactor R Building, all in nternal struuctural surfaaces, system ms and com mponents wiill be removed. All intern nal concrete will be rem moved to exxpose the steeel liner, whhich will alsso be removed, leaving on nly the remaaining structtural concreete outside tthe liner below the 6366 foot elevation n (i.e., concrrete bowl below 636 foot elevatioon, concretee pile cap annd piles.) IIn the WTB, th he only portion of the strructure that will remain is the 630 aand 635 foott floor, sumpp and concrete footers belo ow the 636 fo oot elevationn. In the WG GTV and thee other remaaining basem ments, the remaining structu ure will conssist of the flloors and fouundation waalls as well aas concrete ppiling cap and piles p below the t 636 foot elevation. The T structurral surfaces tthat will remmain at LACB BWR followingg the terminaation of the license l are constructed c oof steel reinfforced concrrete which w will be covered byb at least 3 feet of soil and physicaally altered tto a conditioon which woould not allow w the remaininng backfilled d structures too be plausiblly occupied..

LTP Chaapter 1, secction 1.3.1 describes d the site licennse boundaryy. The fennced area oof the Independ dent Spent Fuel F Storage Installation (ISFSI) Faccility as locaated in Lot 7 of the sitee (and shown inn Figure 2-1)) is excluded d from the sccope of the LLTP.

2.1. Historical H Site Assessmeent In accorrdance with h the guidaance provid ded in MAR RSSIM, secction 3.0, a Historical Site Assessment (HSA) (6) was performed p and a documeented in Auugust of 19999. Histoorical informatiion, includin ng any 10 CFR C 50.75(g g) files, empployee interrviews, radiological inccident reports, pre-operatio onal survey data, spill reports, speecial surveyys (e.g., sitee aerial surrveys, marine fauna f and sediment s su urveys), operational surrvey recordss, and Annnual Radioloogical Environm mental Repo orts to the Nuclear Reegulatory C Commission (NRC) werre reviewedd and compiled d for this inv vestigation.

2.1.1. Objectives O

The HSA A was a detailed d inveestigation to o collect exxisting infoormation (frrom the staart of LACBW WR activities related to radioactive r materials m or other contaaminants) foor the site annd its surrounddings. The HSA focuseed on historrical events and routinne operationaal processess that resulted in contamin nation of plaant systems,, buildings, surface andd subsurfacee soils withiin the Radiologgically Contrrolled Area (RCA).

( It allso addresse d support strructures, opeen land areaas and subsurfacce soils outside of the RCAR but withhin the owneer controlledd area. The current RCA A and the 1.5 acre a fenced LACBWR Site Enclossure (LSE) area sharee the same boundary. The informatiion compiled by the HS SA was used d to establissh initial surrvey units. This inform mation may alsoo be used as input into th he developm ment of remeediation planns and the deesign of the FRS.

The scop pe of the HSA included potentiial contaminnation from m radioactivve materialss and hazardouus materials.

The objectives of thee HSA were to:

Id dentify potential, likely, or known sources of radioactive and chemical contamiinants based on exissting or deriv ved informattion, 2-2

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Distinguish D portions p of th he site that may m need furrther action from those that pose litttle or no threat to human health h, Provide an asssessment off the likelihood of contam minant migraation, Provide inforrmation usefu ful to subsequ uent continuuing characteerization surrveys, Provide an in nitial classificcation of areeas and strucctures as nonn-impacted oor impacted, Provide a graaded initial classification n for impacteed soils and sstructures inn accordancee with MARSSIM M guidance, g andd Delineate D inittial survey unit u boundariies and areass based uponn the initial cclassificationn.

2.1.2. Methodology M y The objeective of the HSA record ds search and d interview process wass to identify those events that may havee significanttly impacted d the hazardo ous materiall or radiologgical status oof LACBWR R site land areaas and structtures. Thesee included sy ystem, struccture, or areaa contaminaation from syystem failures resulting r in airborne releases, liquid d spills or reeleases, or tthe loss of ccontrol over solid material. Dependin ng upon paast site opeerations andd processes,, the potenntial for ressidual contamin nation variess by area. In n order to faccilitate effecctive charactterization, annd to guide ffuture decontam mination actiivities and FRS planning g, land areass and structuures are classsified based upon their poteential for con ntamination..

Each incident identiffied that possed a realistiic potential tto impact thhe characteriization of the site was furth her investigaated. This in nvestigationn focused onn the scope oof contaminaant samplingg and analysis, any remed dial actions taken to mitigate m the ssituation, annd any postt-remedial aaction sampling g, survey, an nd analysis in i an attemp pt to identify fy the as leeft condition of the inccident location. Historical records r prov vided the sou urce of a vastt majority off the documeents inspecteed.

Relevantt informatio on that beccomes availlable duringg any addiitional charracterizationn and remediation phases of o the licensee termination n plan will bbe evaluated..

Also inclluded in the research asssociated with h the developpment of thee HSA were::

Relevant R exceerpts from written w reportts and corresspondences, Personnel intterviews, inccluding the use u of questtionnaires, oof current, foormer and reetired plant personn nel to confirrm documen nted incidentts and identtify undocum mented inciddents, Site inspectio on, utilizing g historic site drawingss, photograpphs, prints, and diagram ms to id dentify, locatte, confirm, and documeent areas of cconcern.

Information from thiis research was w used in the HSA deevelopment, including thhe compilation of data, evaaluation of results, r docuumentation of o findings, and the ideentification of initial Suurvey Units.

2.1.2.1. Prelimminary Classsification The HSA A investigaation was designed d to o obtain suufficient info formation too provide iinitial classificaation of the site land areeas and strucctures as imppacted or noon-impacted. Impacted areas have a potential p for contaminatiion (based on o historicall data) or coontain know wn contaminnation 2-3

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 (based ono past or preliminary p radiologicall surveillancce). Non-im mpacted areeas are idenntified through knowledge k of o site history y or previouus survey infformation annd are those aareas where there is no reaasonable possibility for residual raadioactive coontaminationn. Areas w were classifieed as impacted d from a raadiological perspective.

p Potential chemical hhazards inciddents on ow wner-controlled areas weree also docum mented.

If a land area or struccture was claassified as im mpacted, theen a determiination of thee initial imppacted area classsification (ee.g. Class 1, Class 2 or Class C 3) in aaccordance wwith MARS SSIM, sectioon 2.2 was made based upon n the inform mation obtain ned.

Initial cllassification of LACBW WR areas was w based oon historicaal informatioon and avaiilable historicall radiologicaal survey datta. Classify ying a surveyy area has a minimum oof two stages: (1) initial claassification and a (2) finall classificatiion. Initial cclassificationn of most arreas is perfoormed at the tim me of identifiication of thee survey area using the iinformation available whhen the HSA A was prepared. Final classsification iss performed and verifiedd as a DQO O during chaaracterizationn and FRS desiign. The ch haracterizatio on data was used to vallidate or upddate, as neceessary, the iinitial classificaations indicaated in the HSA H as descrribed in this Chapter. RRadiological survey data from continuin ng characteriization surveeys, operatio onal surveyss in support of decommiissioning, rooutine surveillan nce, and an ny other ap pplicable surrvey data m may cause an increasee in survey area classificaations (for ex xample, from m Class 3 to o Class 2 andd from Classs 2 to Classs 1) until thee time of comm mencement off the FRS.

2.1.2.2. Docum ment Review w Records maintained to satisfy the t requirem ments of 10 CFR Part 500.75(g)(1) pprovided a m major source off documentaation for thee HSA recorrds review pprocess. Durring the connduct of the HSA for LACB BWR, many y record typees were evalluated. A suummary of tthe types of records reviiewed include:

Operational O Review R Commmittee (ORC C) Meeting M Minutes, Safety Review w Committeee (SRC) Meeeting Minuttes, Licensee L Eveent Reports (LER) Summ maries, Site Initiated Incident Rep ports (IR),

Operator O Log gs including Reactor Opeerator and H Health Physiccs entries, Annual A Envirronmental Monitoring M Reports, R

Environmenta E al investigattions performmed by indeppendent entitties, Regulatory R acctions conceerning the sitte, Documentatio D on from interviews cond ducted with rretired/separrated site perrsonnel, Health H Physiccs surveys an nd sampling g results assoociated with identified evvents, Site inspectioon and surveiillance type documents aassociated w with identifieed events, Radiological R and environ nmental survey documennts, 2-4

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Quality Q Contrrol (QC) /Qu uality Assuraance (QA) fi finding type ddocuments.

2.1.2.3. Licenses, Permits and Authorizations LACBW WR was operaated in accorrdance with several Fedderal and Staate of Wiscoonsin licensees and permits. The NRC Operating License L for LACBWR aand supportting Techniccal Specificaations allowed Dairyland D Power Coopeerative (Dairryland) to usse any quanttity of radioaactive materrial at the site, to support operations o du uring its opeerating lifetiime, and to implement ddecommissiooning activitiess.

Several government g and regulato ory agencies have providded oversighht at LACBW WR during ssiting, licensingg, constructioon, operation ns, and decom mmissioningg. These ageencies includde:

United U Statess Atomic Eneergy Commiission (AEC C),

United U Statess Nuclear Reegulatory Co ommission (N NRC),

United U Statess Environmen ntal Protectiion Agency ((EPA),

Wisconsin W Deepartment off Natural Reesources (WD DNR),

Local/County L y Governmen nts.

From Au ugust 28, 197 73 to the preesent, the faccility has beeen operated uunder NRC License DPR R-45.

This periiod includess power opeerations to 1987, 1 permaanent shutdoown for deccommissioninng in 1987, and d ISFSI consstruction and d spent fuel off-load whiich was com mpleted in 20012.

2.1.2.4. Person nnel Intervieews Interviewws with curreent or previo ous employeees were perrformed to ccollect first-hhand inform mation about thee site and to verify or clarify inform mation gatherred from thee records thaat were revieewed.

The personnel interv views includ ded a combin nation of quuestionnairess completed by a majoriity of the particcipants as well w as indiviidual and gro oup interview ws with sevveral of the pparticipants. Key personneel were chossen due to th heir knowled dge of and aassociation with the sysstems and soource terms being investigated for the assessment.. A numberr of the perssonnel intervviewed possessed site knowwledge and experience e th hat ranged frrom the site cconstructionn period to shhutdown.

Between 2010 and 2011, apprroximately 40 4 recollectiions of inteerest were llogged from m the individuaals contacteed as part of the HS SA questionnnaire progrram. This consisted of a standardiized personn nel survey which w was completed c vvoluntarily bby retired/sepparated stafff and site persoonnel who worked w at the LACBWR R during its ooperational years. Withh few excepttions, the persoonnel observ vations docum mented on th he questionnnaire were ccorroboratedd either by loogged memories of other questionnaire q e completerss, current onn-site workiing staff thaat had LACB BWR operation nal period exxperience, orr by documentation discoovered durinng the recordds search.

2.1.2.5. Property Inspectio ons Several on-site prop perty inspecctions were made overr the coursee of the HS SA developm ment.

Several site s events off interest weere identified d which weree subsequenttly documennted in the H HSA.

2-5

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.1.3. Operational O History LACBW WR was a 50 5 Megawattt Electric (MWe)( Boilling Water Reactor thhat is owneed by Dairyland. This sing gle unit, also o known as Genoa G Statioon #2, is loccated on the east shore oof the Mississip ppi River so outh of the Village off Genoa, Veernon Counnty, Wisconssin. The site is borderedd on the no orth by the Mississippii River andd a narrow strip of laand betweenn the Mississip ppi River annd Highway 35. The licensed site c omprises a ttotal of 163.5 acres, witth the LSE com mprising app proximately 1.5 acres of the licensedd site. The LSE boundaary is fencedd and served ass the RCA boundary b duuring operattions. Mateerial leavingg the LSE w was surveyedd and confirmeed to be suittable for unrrestricted use before release. The ssite is accessed by an aaccess road on the t south sid de of the plannt. Other pro ominent feattures on the site include::

th he land north h of the LAACBWR plan nt, includingg the site sw witchyard annd the site oof the foormer Genoaa Station #1 (G-1) coal (and( later oill) fueled powwer plant (removed in 19989),

an n operationaal 350 MWe fossil generrating stationn (G-3) locaated south annd approxim mately 175 feet fromm the LSE, th he fenced ISF FSI facility that t is locateed directly soouth of G-3,, and a small parcel of land to thet east of Highway H 35, across from m LACBWR that is part oof the liicensed site.

The plan nt was one of a series of demonsttration plantts funded inn part by A AEC. The A Allis-Chalmerss Company was the oriiginal licenssee; the AEC C later soldd the plant tto Dairylandd and providedd them with a provisionall operating license.

LACBW WR achieved d initial critiicality on Juuly 11, 19677, and was operated foor approxim mately 19 years until it wass permanenttly shut dow wn by Dairyyland on Appril 30, 1987. Final reeactor defuelingg was complleted on Junee 11, 1987. The Dairylaand authorityy to operate LACBWR uunder Operating License DPR-45, D purrsuant to 100 CFR 50, w was terminat ated by Liceense Amenddment No. 56, dated d Augusst 4, 1987; anda a possesss but not-opperate statuss was granteed by NRC. The 333 irrad diated fuel asssemblies, which w were in i Fuel Elem ment Storagee Well (FES SW), were pplaced into five (5) dry caskks and transfeferred to the sites ISFSI by Septembber 2012.

Limited dismantleme d ent of shutdo own and unu used systemss and waste disposal operations has been ongoing at LACBW WR since 199 94. Waste stored s in thee FESW andd other Classs B/C wastee was shipped for disposall in June 20 007. The Reactor R Pressure Vessel (RPV) witth head instaalled, internals intact, and 292 control ro ods in place was filled w with concrette, removed from the Reeactor Building, and shippeed for dispo osal in Junee 2007. Othher systems and compoonents have been removed, including the t spent fueel storage raccks, Gaseouus Waste Dissposal System m (except foor the undergroound gas sto orage tanks)); Condensaate system and Feedwaater system m (except foor the Condensate Storage Tank and condenser); Turbine annd Generatoor; and Com mponent Coooling Water Sy ystem pumps, heat exchangers, pipin ng and compponents thatt were locateed in the Tuurbine Building.

2.1.4. In ncidents Based on n the revieww of existing plant reco ords (e.g. annnual and ssemi-annual reports, liceensee notificatiions, occurreence reportss, and questiionnaires), iincidents wiith radiologiical or hazarrdous 2-6

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 material implication ns occurred between th he commenccement of pplant operatiion in 19677 and placing the t reactor in n a SAFSTO OR condition in 1987. All of thesee incidents ttook place w within the LSE and, while contributing c to the radiollogical contaamination annd potential contaminatiion of the structtures and soils directly related r to thee operation oof the reactoor, were conntained withiin the LSE, which is alread dy known to be impacteed.

Special emphasis was w placed on o obtaining and revieewing the aannual Radiioactive Efffluent Monitoriing Reports (REMP), focusing fo on gaseous annd liquid relleases since 1967, incluuding reports covering c thee periods of o SAFSTOR R and decoommissioninng activitiess after the plant shutdown n in 1987. Available saampling resu ults associatted with soiil and grounndwater withhin or around th he plant sitee were also reviewed. The T objectivve was the iidentificationn of those eevents posing a significant probability p of o impacting g the radioloogical status or hazardouus material sstatus of LACB BWR site land areas and structu ures. Thesse included system, sttructure, or area contamin nation from system s failurres resultingg in airborne releases, liqquid spills orr releases.

2.1.4.1. Radioological Spillls The histtorical revieew indicated d that betweeen 1967 aand 1987, thhere were sseveral inciidents involving g system leaakages, radio ological spillls, and/or raddioactive liqquid effluent releases witth the potential to affect the classificatiion of LACB BWR structuures or soilss. The inciddents are listted in chronological order as a follows; The T stainless steel liner in the FESW W had a hisstory of leakkage to the R Reactor Buiilding flloor. Incidennts involving g leakage off the FESW w were noted ffrom 1967 too 2012.

In ncidents involving leakaage from thee resin regenneration wasste system tto the Circullating Water W Dischaarge line werre noted from m 1967 to 19973.

In n 1970, pottentially con ntaminated Control Rodd Drive (C CRD) oil waas used for dust suuppression on o the licenseed site roadss.

In n Septemb ber, 1977, removablee alpha ccontaminatioon was ddetected dduring decontaminattion of a Fo orced Circulation Pump (FCP) duriing maintenance involvving a stteam cleaninng tank in thee Reactor Bu uilding 701 ffoot elevatioon. (ORC, 009/27/77)

On O Novembeer 5, 1980, partial blockaage of drain lines under Turbine Buuilding resultted in th he potential for leakage of drain waater into the soil under thhe Turbine B Building. (DDPC-80-84 Inciden nt Report, OR RC-80-71, ORC-80-75, O ORC-80-877, ORC-80-997)

On O Novembeer 24, 1980, residual rad dioactive conntaminationn was detected in soils uunder th he Turbine Building.

B (D DPC-80-93 Incident I Repport, ORC-880-71, ORC--80-75, ORC C 87, ORC-80-9 97, LER 80--12)

On O Decemb ber 6, 1980, the Turb bine Buildding Waste Water T Tank overflowed appproximately y 1/2 gallon of waste water w to the Turbine Buuilding floorr. (DPC-800-102 In ncident Repo ort, ORC-80 0-71, ORC-80-75, ORC- 80-87, ORC C-80-97)

On O Decemberr 15, 1980, the t Turbine Building Waaste Water T Tank overfloowed waste w water in nto the Turbiine Building g Basement Tunnel.

T (DPPC-80-106 Inncident Repoort) 2-7

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 In ncidents invo olving leakaage of potenttially contam minated liquiid from the T Turbine Buiilding waste w water tanks t throug gh the normaal effluent reelease pathw way to the CCirculating WWater Discharge D lin ne were noted d from 1980 0 to 1986.

On O January 30, 1981, the Turbine Building Waste W Water Tank overflowedd and unnspecified volume v of waater into the laundry room m. (DPC-811-10 Incidennt Report)

On O May 31, 1982, a lid seal failed on o a spent rresin liner w which resulteed in the sppill of coontaminated d water and spent resin onto the flooor of the S Spent Resin Liner Room m and in nto the basemment. (DPC-82-51 Incid dent Report)

On O July 02, 1982, 1 approxximately 1,2 200 gallons oof condensatte water wass released frrom a siight flow seeal rupture to the Turbin ne Buildingg floor, and approximateely 20 galloons of coontaminated d water flowwed into the soils outsidde the Turbiine Buildingg door and T Truck Bay B door. In n addition, approximatel a ly 25 gallonss of contam minated liquidd was dischaarged to o an unrestricted area. (D DPC-82-58 Incident I Repport, LER 822-016)

On O July 16, 1983, a leak k in the Seaal Water Inj njection Systtem leak at 1A FCP caaused appproximately y 15,000 galllons of reacctor coolant to be dischaarged to the Reactor Buiilding basement floo or. (LER 83 3-07) 2.1.4.2. Chemmical Spills Between 1967 and 20 014, the HSA A documentted several inncidents invvolving the uunplanned sppill or release ofo chemicalss and/or poteentially hazaardous liquidds to the ennvironment. These inciidents ranged frrom spills off acids and caustics c usedd in the plannts various systems to tthe spill of ddiesel and fuel oil from sy ystems and storage tank ks. A majoority of the incidents occcurred insidde of impacted d buildings. These spillss were contrrolled and reemediated inn accordancee with the sttation policies and proced dures for id dentificationn, control aand remediaation of hazzardous maaterial releases.

2.1.5. Findings F andd Conclusions LACBW WR was desig gned with mu ultiple bound daries to conntrol and conntain the raddioactive conntents within itss many systeems, compon nents, and sttructures. M Many of thesee systems annd structures have been imp pacted due tot routine op perations annd maintenannce activitiees during thee operationaal and post opeerational history of the plant. Daiiryland LAC C-TR-138, IInitial Site Characterizzation Survey fo or SAFSTOR R (7) identifiied historicaal failed fuel incidents att LACBWR and the poteential for fissio on products tot enter and impact i reacttor and support systems.

Structurees classified as impactted by the operation oof the facilitty include R Reactor Buillding, Turbine Building, WTB, W Low Specific S Acttivity (LSA)) Building, WGTV, andd the Ventillation Stack. In n addition too the structurres, the soilss surroundingg these builddings have aalso been deemed to be direectly impacteed by the op peration of thhis facility. T This area is defined by tthe LSE fencce.

An area surrounding s the LSE has also been designated d aas impacted. This area iincludes anccillary support buildings b su uch as the LACBWR L Crib House, L LACBWR A Administratiion Buildingg and various warehouses w and a storage buildings.

b 2-8

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 In additiion to the area a within the LSE an nd the open land areas surrounding the LACB BWR support buildings, the t open lan nd immediaately surroun unding the L LSE fence is designateed as impacted d to provide a buffer zon ne between thet LSE andd the G-3 lannd and facillities south oof the LSE whiich is consid dered non-im mpacted. Th he licensed ssite comprisees a total off 163.5 acress with the LSE areas comprrising approx ximately 1.5 acres of thee owner conttrolled area.

2.1.6. In nitial Surveey Areas/Un nits and Classsification As part of o the HSA process, p the impacted i ACBWR struuctures and oopen land arreas were divvided LA into preliiminary surv vey areas an nd assigned area classifiications baseed on the opperational hiistory and existting survey data.

d 2.1.6.1. Survey Areas The entirre 163.5 acrres licensed site was div vided into suurvey areas.. Survey arreas are typiically larger phhysical sectioons of the sitte that may contain one or more surrvey units deepending onn their classificaation. Surv vey area sizee was deterrmined baseed upon the specific arrea and the most efficient and practiccal size need ded to boun nd the lateraal and vertiical extent oof contaminnation identifiedd in the areaa. Survey arreas that hav ve no reasonnable potential for residuual contaminnation were classsified as non-impacted d. These arreas have noo radiologicaal impact froom site operaations and are iddentified in the HSA. Survey S areas with reasonnable potentiial for residuual contaminnation were classsified as im mpacted. Figure F 2-1 provides p an iillustration oof the LACB BWR site annd the current classificationns by area.

2.1.6.2. Survey Units The surv vey areas werre further divided into su urvey units. A survey uunit is a porttion of a struucture or open land l area thaat is surveyeed and evalu uated as a sinngle entity ffollowing FR RS. Survey units were deliineated to ph hysical areass with similaar operationaal history or similar poteential for ressidual radioactiv vity to the extent e practical. To the extent pracctical, surveyy units weree establishedd with relatively y compact sh hapes and highly irregulaar shapes weere avoided uunless the unnusual shapee was appropriaate for the siite operation nal history orr the site top ography.

The surv vey units esttablished by the HSA were w used as initial surveey units for characterizaation.

Prior to characterizaation, survey y unit sizes for f Class 1 oopen land suurvey units were adjustted in accordan nce with the guidance g pro ovided in MARSSIM, seection 4.6 foor the suggessted physicall area sizes for survey unitss for FSS.

The deco ommissionin ng approach that will bee implementted at LACB BWR calls for the com mplete segmentaation, remov val and dispo osal of all immpacted sysstems and abbove-grade structures. With the excep ption of structure basem ment floors an nd walls thatt reside 3 feeet below graade, no portiion of any struccture will reemain at sitte closure and a consequuently, be suubjected to FRS. How wever, survey units u have beeen establish hed for strucctures to faccilitate otherr characterizzation objectives.

These ob bjectives incclude provid ding survey data d for rem mediation plaanning, estim mating the w waste volume contained c onnsite, and dissposition opttions for the waste.

In additioon, the surveey units estab blished for structures s thaat are 3 feet below gradee are intendeed for the purpo ose of charaacterization planning p andd do not corrrespond to the survey uunits that w will be 2-9

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 used for the FRS of remaining g below grad de structurees (designateed as STS aand discussed in section 5.5.2 of Chap pter 5).

Tables 2--1 and 2-2 provide p a deetailed list of o the surveyy units for bboth the opeen land areas and impacted d structures respectively y. Figure 2-2 2 provides a detailed innventory of the buildingg and site strucctures. A sum mmary of th he survey uniit classificatiions are pressented as folllows.

2.1.6.3. Class 1 Open Lan nd Areas The follo owing open land l areas haave been claassified as im mpacted Classs 1:

Reacttor Building g, WTB, WG GTV, Ventilaation Stack G Grounds (L1010101),

Turbiine Buildin ng, Turbine Office Bu uilding, 1B Diesel G Generator Buuilding Groounds (L1010102),

LSA Building, Maintenance M Eat Shack Grounds G (L10010103),

North h LSE Area (L1010104).

The basiss for this claassification iss due to a series of docummented inciddents of the contaminatiion of soil by radioactive r material m in these t areas during facillity operationns. These iincidents include spills of radioactive liquids and d resins, radiioactive sysstem leakagee, and storagge of radioaactive packagess and contain ners.

Based on n an assessmment of historrical inciden nts and eventts, it was annticipated thaat the surface and subsurfacce soils in th hese areas could c possiblly contain reesidual radiooactive mateerial in exceess of the unresstricted use criteria.

c Classs 1 open lannd survey unnits are showwn on Figuree 2-1.

2.1.6.4. Class 2 Open Lan nd Areas The follo owing open land l areas were w classifieed as impacteed Class 2:

LACB BWR Adm ministration Building, LACBWR R Crib Hoouse, Wareehouse Groounds (L2011101),

G-3 Crib C House, LACBWR Circ. Water Discharge L Line, Area SSouth of LSE E Fence Groounds (L2011102).

Based up pon a review w of the histtorical inform mation and operational radiation annd contaminnation surveys performed p n these areaas as documeented in the HSA, theree was a poteential for ressidual in radioactiv ve contamin nation to exceed the unreestricted releease criteria.

Class 2 open o land surrvey units arre shown on Figure 2-1.

2.1.6.5. Class 3 Open Lan nd Areas The follo owing open land l areas were w classifieed as Class 3 :

North h End of Liccensed Site (L L3012101),

Transsmission Sw witchyard Areea (L301210 02),

Plantt Access, ISF FSI Haul Road Grounds (L3012109)).

2-10

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Historicaal informatio on contained d in the HSA A indicated thhat the preseence of residdual radioacctivity in concen ntrations in excess e of thee unrestricted d release cri teria was noot expected.

Class 3 open o land surrvey units arre shown on Figure 2-1.

2.1.6.6. Non-IImpacted Op pen Land Areeas Based on n a review of the operatiing history of o the facilityy and historrical incidentts as documented in the HS SA, the balaance of the 163.5 acre liicensed site has no reassonable poteential for ressidual contamin nation and haas been desig gnated as noon-impacted..

G-3 Coal C Plant Grounds G (L40 012103)

Coal Pile Ground ds (L4012105)

Capp ped Ash Impoundment Grounds G (L40012106)

Grou unds East of Highway H 355 (L4012107)

Hwy 35/Railroad d Right of Way W Grounds (L4012108))

The non--impacted op pen land surv vey units aree shown on F Figure 2-1.

2.1.6.7. Class 1 Structuress The follo owing is a liist of the major m buildinngs that weree initially cllassified as impacted Cllass 1 structures. The com mplete list off all impactted structuraal survey unnits is providded in Tablee 2-2.

These strructures con ntain the nucclear reactorr, primary reeactor system ms, reactor support systems, radioactivve waste sy ystems, and nuclear n fuell handling aand storage ssystems. During operattions, radioactivve material was routineely handled,, transferredd, and storedd within theese buildings. A majority of the curren nt radioactiv ve material innventory at L LACBWR rresides in theese structurees:

Reacttor Building g (B1010001)

Wastte Treatmentt Building (B B1010002)

Ventiilation Stack k (B1010003 3)

Wastte Gas Tank Vault (B101 10004)

Turbiine Building g (B1010005 5)

Dieseel Generatorr Building (B B1010006)

LSA Building (B B1010007)

Main ntenance Eat Shack (B10 010008)

Througho out facility operations, o th hese structurres were subbjected to spiills of radioaactive liquidds, the spread of loose surfface contamination, and d airborne raadioactive m material. Sttructural surrfaces were rou utinely postted as conttaminated areas.a The decommissioning appproach for these structures involves the compleete segmenttation, remooval, and ddisposal of all systemss and structural material ass waste. Wiith the excep ption of struuctural floors and walls that reside 3 feet below grrade, no porrtion of these structures will remaain at site cllosure and aare thereforre not subjectedd to FRS. Th he Class 1 sttructural surv vey units aree depicted inn Figure 2-1.

2-11

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 2.1.6.8. Class 2 and 3 Stru uctures The folloowing is a liist of some of the majorr buildings tthat were innitially classiified as imppacted Class 2 oro 3 structurres. All aree located wiithin the liceensed site bbut outside oof the LSE. The completee list of all im mpacted stru uctural survey units is proovided in Taable 2-2.

LACB BWR Crib House H (B201 10101)

G-3 Crib C House (B2010102)

(

LACB BWR Administration Bu uilding (B20 010103)

LACB BWR Wareh house #1 (B2 2010104)

LACB BWR Wareh house #2 (B2 2010105)

LACB BWR Wareh house #3 (B2 2010106)

Backk-up Control Center (B30 012101)

Transsmission Sub b-Station Sw witch House (B3012102))

G-1 Crib C House (B3012103)

(

Bargee Washing Break B Room (B3012104))

These strructures did not routinely y house radiioactive systtems or mateerials duringg operations. The structures associated d with LAC CBWR listed d above are outside of the LSE buut were useed by LACBW WR workers and therefore considereed Class 2 or 3. The G-1 Crib H House and B Barge Washing g Break Room m were not associated a with w LACBW WR operationns but are coonsidered Cllass 3 structures because th hey reside in i a Class 3 land area. With the exception oof the LACB BWR Administtration build ding, the G-3 3 Crib Housse and the T Transmissionn Sub-Statioon Switch H House, the decom mmissioning g approach calls c for the complete seegmentation,, removal, annd disposal of all LACBW WR Class 2 orr 3 systems and structurral material aas waste or salvage. Noo portion of these structures will remain n at site clossure and therrefore will not be subjected to FRS.

The LAC CBWR Adm ministration building, b thee G-3 Crib HHouse and thhe Transmisssion Sub-Sttation Switch House H will not n be subjected to FR RS. Insteadd, these struuctures will be surveyed for unrestrictted release using a grraded survey y approach using the guidance of NUREG-1575, Supplem ment 1, Multii-Agency Ra adiation Surrvey and Asssessment of Materialss and Equippment Manual (MARSAME) (8). Thee Class 2 an nd Class 3 sstructural suurvey units for buildinggs are depicted in Figure 2--1.

Based on n a review of the operatiing history of o the facilityy and historrical incidentts as documented in the HSA, H coup pled with the t results of charactterization suurveys (as summarizeed in section 2.3.5),

2 the bu uildings asssociated with h the G-3 sstation have no reasonaable potentiaal for residual contaminatio on and havee been desig gnated as noon-impacted.. The G-3 sstation, incluuding the G-3 Crib C House, will remain intact and fu unctional forr G-3 powerr operations.

2.2. Characteriza C ation Appro oach From Occtober 2014 through Aug gust 2015, site s characteerization of L LACBWR w was performmed in accordan nce with th he Characteerization Su urvey Plan. The Chharacterizatioon Survey Plan 2-12

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 incorporaated the preevious histo orical operaational and radiologicall informatioon collectedd and documen nted in the su urvey areas from the HS SA and prevvious site characterizatioon efforts. It was developeed to providee guidance and a direction n to the perssonnel respoonsible for im mplementingg and executing g characterizzation survey y activities. The Plan w worked in conjunction w with implemeenting procedurres and survey unit speccific survey instructionss (sample pllans) that w were developped to safely annd effectively y acquire thee requisite ch haracterizati on data.

Characterization dataa acquired th hrough the execution e of the Plan waas used to m meet three priimary objectivees:

Proviide radiologiical inputs necessary n forr the design oof FRS, Deveelop the requ uired inputs for f LTP, and d Support the evaaluation of remediation r alternativess and technnologies andd estimate w waste volummes.

The deco ommissionin ng approach for LACBW WR calls for tthe demolitiion and remooval of all onn-site buildingss, structures,, and compo onents to a depth d of at lleast 3 feet bbelow gradee. Consequeently, characterrization effo orts focused d on open land areas and remainning structuures that wiill be subjectedd to FRS. Extensive E chharacterizatioon of equipm ment, system ms or structtures that will be removed prior to thee performancce of final surveys s is noot required iin accordancce with NUR REG-1757, Ap ppendix O.

The charracterization n surveys fo ocused on general g openn land areass including: site surfacee and subsurfacce soils, pavved surfaces,, and concrette pads. Cooncrete core samples werre taken from m the structural basementss that will reemain in thee end-state condition. In addition,, characterizzation surveys were w perform med in the LACBWR L Ad dministrationn Building aand several oof the G-3 sttation structures. Upon com mpletion, thee data was assessed for qquality and aadequacy. T The data wass then used to make m determ minations on whether w addditional charaacterization data is requuired, primarily of above grrade or subgrade structu ures, surface and subsurfface soils, orr beneath thhe concrete ffloors of the exxpected end--state structu ures at LAC CBWR. Conntinuing chaaracterizationn surveys w will be planned, executed an nd documen nted with thee same data quality andd the results included inn FRS planning.

A signifiicant questio on that must be answereed by the chaaracterizatioon is whetheer or not a suurvey unit is claassified corrrectly. The appropriate a classification c n of a surveyy unit is crittical to the suurvey design fo or FRS. A classificatio on which un nderestimatees the potenntial for contamination ccould result in a survey dessign that doees not obtain n adequate innformation too demonstraate that the suurvey unit meetts the releasee criteria. In n some casess, this can inncrease the ppotential for m making deciisions errors.

As site-specific Deriived Concen ntration Guid deline Levells (DCGLs) were not yeet establisheed for LACBW WR at the tim me the charaacterization survey was performed, alternate acction levels were selected. The screen ning DCGLss presented in i NUREG-11757 and the concentrattion values ffound in NURE EG/CR-5512 2 Volume 3, Residual Radioactive R Contaminaation from D Decommissiooning Parameteer Analysis (9), Table 6.91 (Pcrit = 0.10)0 for soills were usedd as alternate action leveels to assess thee correct claassification of o impacted openo land orr soil survey units.

2-13

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 For strucctures, the grross screeninng level thatt was used dduring charaacterization aas an action level to evaluate the classsification of o survey units u was thhe nuclide-specific scrreening valuue of 7,100 dpm m/100cm2 to otal gross beeta-gamma surface s activvity based onn Co-60 fromm NUREG-1757, Appendix x H. Use off the Co-60 screening valuev was coonservative aas it was annticipated thaat the radionuclide distribuution for surfface contam mination wouuld be princiipally Co-600 and Cs-1377 and the conseervative apprroach was to o assume a distribution d oof 100% Co-60 since thee screening vvalue for Cs-1337 is significcantly greateer.

2.2.1. Data D Qualityy Objectivess DQOs were w implemeented for ch haracterizatioon surveys inn a similar m manner as annticipated foor the FRS. Ho owever, the goal of charracterization n is to quantiify and delinneate contamminated areaas and to determ mine the radionuclide mixture, m wherreas the FRS S goal is coomparison off data againsst the unrestrictted use critteria to dem monstrate co ompliance w with 10 CFR R 20.1402. Characterizzation inspectio ons and surv veys of sufffficient qualiity and quaantity were performed tto determine the nature, extent and raange of radio oactive conttamination inn each appliicable surveey unit, incluuding applicablle structures, residues, sooils and surfface water.

Characterization surv veys were deesigned to gather g the appropriate daata using thee DQO proceess as outlined in MARSSIM M, Appendiix D. The seeven steps inn the DQO ddevelopment process are::

1) State the problem m,

2) Identtify the decission,

3) Identtify inputs to o the decision n,

4) Defin ne the study boundaries,

5) Deveelop a decisio on rule,

6) Speciify limits onn decision errrors, and

7) Optim mize the design for obtaiining data.

The DQO Os for site characterizaation includeed identifyinng the typess and quantiities of meddia to collect. No N structurees located ab bove 3 feet below b grade will remainn following ddecommissiooning and will therefore no ot be subjected to FRS. Consequenttly, sample ccollection waas focused oon the assessmeent of concreete in basem ments and su urrounding sooils. Buildiing concretee was sampleed by obtainingg core samp ples. Soils were samplled volumettrically. Suufficient measurements were obtained to determin ne the mean and maximu um activity aas well as thhe sample staandard deviaation.

Direct measurement m s and scanss of surface soils were made usingg the same instrumentss and Minimal Detectable Concentrations (MDC) as will be eemployed foor FSS. Volumetric sam mples that exhiibited the hiighest activiity were sen nt to an off--site laborattory for analysis of Harrd-to-Detect (H HTD) radion nuclide(s).

2.2.2. Survey Desig gn Characterization surrveys were designed and a perform med in accoordance witth all appliicable approved d proceduress and the Chaaracterizatio on Survey Pl an. Survey design incorrporated a grraded approachh based upon n the DQOs for f each surv vey unit. Foor example, an open landd survey uniit was 2-14

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 designateed as Class 1 because itt may contaain levels off radiologicaal contaminaation greaterr than the unresstricted releaase criteria. Therefore, the t characterrization survveys that werre performedd in a Class 1 survey s unit focused f on bounding b thee contaminattion where contamination was potenntially present. The survey design was based upon n the numberr of measureements and samples reqquired to identiffy the laterall and verticaal extent of th he contaminnation. Areaas classified as non-impaacted, Class 2 oro Class 3 reeceived surv veys develop ped to includde a combinnation of ranndom and bbiased survey measurement m locations annd scan areas. Biased suurvey designns used know wn informatiion to select loccations for static s measu urements and d/or sampless. Random survey desiggn selected static measurem ment and/or sample loccations at ran ndom. Thee decision off whether too use primarrily a biased su urvey design n or a random m approach was addresssed by the D DQO processs for each suurvey unit. A biased app proach was warranted when the ccharacterizattion effort w was designeed to delineatee the extent of o an area th hat requires remediationn. Alternativvely, a randoom approachh was warranted if the charracterization effort was designed d to vverify the baasis for the cclassificationn of a survey un nit.

The areaas and materials surveyeed and/or sam mpled in andd around thee licensed arrea as part oof the characterrization surv vey included:

Surface scanss and random m and biased d surface andd subsurfacee soils sampples were takken in alll Class 1, 2, 2 3, and no on-impacted open land aarea survey units with the exceptioon of su urvey unit L3012102 L (i.ee., the switchhyard).

Biased B subsurrface soil saamples were taken alonggside and underneath undderground ppiping sy ystems of concern in Class C 1 and 2 areas inclluding the ppiping systems as show wn on Figure 2-3.

Random R sammples were taaken from asphalt a and cconcrete from m pads and paved areas. In adddition, soil samples weere obtained directly beloow the asphaalt to a one m meter depth.

Scans and samples werre taken on n accessiblee roof surfaace areas off the LACB BWR Administratio A on Building and the G-3 Coal Plant.

Samples weree taken from m the septic taanks.

Scans and sam mples were taken on LA ACBWR Addministrationn Building suurfaces and drain arreas.

Scans and sam mples were taken t on G-33 Building aaccess and heeavily travelled surfaces.

Concrete C sam mples were taken in the basement arreas of the R Reactor Building, WTB B, and Piping and Ventillation tu unnels.

A backgroun nd radiation study was performed on materialls similar too those founnd at LACBWR L including: asp phalt, concrette, and soil.

2.2.2.1. Numb ber of Static Measuremen nts and/or S amples The num mber of measu urements an nd/or samples that were ttaken in eachh survey uniit was determ mined by assesssing the sample size neceessary to sattisfy the DQO Os.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 For the characterizat c tion of impaacted Class 1 and Class 2 open landd areas (pavved and unpaaved) that will be subjecteed to FSS, th he minimum m number off random orr biased direect measurem ments and/or saamples taken n in the surveey units werre commensuurate with thhe probabilitty of the pressence of residual radioactiv ve contaminaation in the survey s unit.

For the characterizaation of Class 1 structurres that wil l remain annd be subjeccted to FRS S, the sample size s was bassed upon thee necessary number n of ssamples neeeded to assesss the lateraal and vertical extent e of the contaminatiion.

For non-impacted an nd Class 3 op pen land surrvey units, thhe primary ccharacterizattion DQO w was to validate the basis of the classsification. Consequenntly, the nuumber of ssystematic static measurem ments and/o or samples wasw sufficieent to ensuree with reasoonable conffidence that only trivial levvels of licen nsee-generatted radionucclides are prresent in Cllass 3 areas and no liceensee-generated d radionuclid des are preseent in non-im mpacted areaas.

2.2.2.2. Determ mination of Static Measu urement andd Sample Loocations For the characterizat c tion of non--impacted an nd impactedd open land areas and C Class 2 strucctural survey units that willl be subjectted to FRS, sample locaations were primarily chhosen at ranndom.

Sample locations l weere determined by generating random m pairs of coordinates that correspoonded to specifiic locations within w the suurvey unit. The T locationn of biased m measurementts and/or sam mples that werre taken in each survey unit was determinedd by the prrofessional jjudgment oof the responsib ble Radiolog gical Protecttion Superv visor and/or the Project Health Phyysicist durinng the survey design d proccess. Consideration was w given to locationns that exhhibit measuurable radioactiv vity, depressions, disco olored areas,, cracks, low w point gravvity drain ppoints, actuaal and potential spill locatio ons, or areass where the ground hass been disturrbed. Histoorical inform mation from the HSA aided in the selecttion of biased d locations.

2.2.2.3. Scan Coverage C

Survey units u were sccanned to th he extent practical in acccordance w with their claassification. The area to be b scanned in each survey unit was determinedd during the survey desiign process. The area scan nned was contingent up pon the pro ofessional juudgment of the Radioloogical Proteection Supervisor and/or the Project Heealth Physicist during thhe survey deesign process. Considerration was giveen to inform mation from the initial walk w downs and the am mbient radiattion levels iin the survey un nit.

2.2.2.4. Typess of Measureements and Samples S

The charracterization n survey of building surrfaces consiisted of a coombination of surface scans (beta andd gamma); sttatic beta meeasurementss, material saamples and ssmears. Thee characterizzation survey off any concreete and/or asphalt-paved open land aareas that wiill remain annd be subjectted to FRS con nsisted of a combination c n of surface scans (beta and gammaa), static betta measurem ments, and volu umetric samp ples. The su urvey of thee open land areas consissted of gamm ma scans annd the sampling g of surface and subsurfface soil, sed diment and ssurface wateer for isotoppic analysis. The following g is a descripption of the different d pes of measuurements andd samples thaat were utilizzed.

typ 2-16

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.2.2.4.1. Gamm ma Surface Scans S

Gamma scans were performed over o open laand surfaces to identify locations off residual suurface activity. Sodium iodide (NaI) gamma g scin ntillation dettectors (typiccally 2 x 2) were typiically used for these scans. EnergySolutions Techn nical Supporrt Documentt (TSD) RS--TD-3131966-006, Ludlum Model M 44-10 0 Detector Sensitivity (10)

( examinnes the response and sccan MDC oof the Ludlum Model M 44-10 0 NaI detecto 0 and Cs-1377 when usedd for scanningg surface soiils.

ors to Co-60 Scanning g was perforrmed by mo oving the deetector in a sserpentine ppattern, whille advancingg at a rate not to t exceed 0..5 m (20 in) per second. The distannce betweenn the detectoor and the suurface was main ntained with hin 15 cm (6 in) of the surface if po ssible. Auddible signals were monittored; and, locaations of elev vated direct levels l were flagged f for ffurther invesstigation andd/or samplingg.

2.2.2.4.2. Beta Surface S Scanns Scanning g was perrformed in order to locate arreas of ressidual activvity above the 7,100 dpm m/100cm2 action a level. Beta scanss were perfoormed over aaccessible sttructural surrfaces includingg, but not liimited to; flloors, walls,, ceilings, rooofs, asphallt and concrrete paved aareas.

Hand-helld beta scin ntillation and ow proportioonal detectoors (typicallyy 126 cm2) were d/or gas-flo used.

Beta scan nning was performed p with w the detector positionn maintainedd within 1 ccm of the suurface and with h a scanning g speed of oneo detectorr active winndow per seecond. If suurface condiitions prevented d scanning ata the speciffied distancee, the detecttion sensitivvity for the aalternate disstance was deteermined, an nd the scan nning techniique adjusteed accordinngly. Scannning speed was calculated a priori too ensure thatt the MDC forf scanningg was approppriate for thee stated objeective of the surrvey.

If not im mpacted by high h ambientt noise levels, technicianns monitoredd the audible response oof the instrumen nt to identify locationss of elevated activity th that require further investigation aand/or evaluatioon. Any ideentified areass of elevated d contaminaation were m marked or flaagged for fuurther investigaation and pottential deconntamination.

2.2.2.4.3. Directt Measuremeents Direct measurement m ts were perrformed to detect total levels of contaminatiion on strucctural surfaces of the build dings or on o asphalt paaved areas. These measurements were n concrete or typically performed using ~10 00 cm2 or larger sized scintillatioon or gas-fllow proporttional detectorss.

Direct measurements m s were condu ucted by plaacing the dettector near tthe surface too be countedd and acquiringg data over a pre-determ mined coun nt time. A count time of one to ttwo minutess was typically used for suurface measu urements and d generally pprovided dettection levells well below w the designateed investigattion level orr MDC under consideraation. The iinstrument ccount times were adjusted as appropriaate to achiev ve an acceptaable MDC foor direct meaasurements.

2.2.2.4.4. Remo ovable Surfacce Contamin nation If applicable, remov vable beta an nd/or alpha contaminati on or smearr surveys w were perform med to verify looose surfacee contaminaation is lesss than the applicable action levell. A smeaar for 2-17

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 removable activity was w usually taken at eacch direct meeasurement llocation on non-asphaltt type surfaces. A 100 cm m2 surface areaa was saampled withh a circular cloth or paaper filter, uusing moderatee pressure. Smears S weree then analyzzed for the ppresence of ggross beta annd/or gross alpha activity as a appropriatte.

2.2.2.4.5. Concrrete and Asp phalt Core Saampling Concretee core boring g and the saampling of concrete weere used to assess the ddepth of surrficial contamin nation and th he presence of volumettric contami nation in cooncrete wallls and floorss that will remaain and be su ubjected to FRS.

F Core bore b samplinng of concreete was accoomplished ussing a diamond bit core driill. The con ncrete sample producedd by the coriing was typpically slicedd into 1/2-inch wide w puckss, represen nting a certaain depth innto the surfface. Conccrete pucks were pulverizeed and analy yzed for isoto opic content..

2.2.2.4.6. Materrial Sampling g Samples of soil, sediment, and sludges were obtained frrom designedd biased andd random saample locationss as well as other locatio ons in areass exhibiting elevated acttivity that wwere identifieed by scanning g. Surface so oil is defined d as the top 15 cm (6-innch) layer off soil while ssubsurface ssoil is defined asa soil beloww the top 15 cm layer in n 1 m increm ments. Surfaace soil was collected ussing a split spooon sampling g system or, byb using han nd trowels, bbucket augerrs, or other ssuitable sammpling tools.

Subsurfaace soil was sampled by y direct pushh sampling ssystems (e.gg. GeoProbe) or by manual hand aug gers. Subsurrface soil sam mpling was performed aas necessaryy to address tthe DQOs foor the survey un nit.

2.2.3. In nstrumenta ation Selectio on, Use andd Minimum Detectable Concentrattions (MDC Cs)

The radiation detecttion and measurement instrumentattion for charracterizationn was selectted to provide both b reliablee operation and a adequatee sensitivity tto detect thee initial suitee of radionucclides identifiedd for the deecommission ning of LAC CBWR at leevels sufficiiently below w the establlished action leevels. Detecctor selectio on was based d on detectiion sensitiviity, operatinng characteriistics, and expeected perform mance in the field. In all cases, thhe instrumennts and detecctors selecteed for static meeasurements and scanning were cap pable of dettecting the aanticipated R Radionucliddes of Concern (ROC) at a MDC of 50%  % of the appplicable actioon level.

Commercially availaable portablee and laborattory instrum ments and dettectors were typically ussed to perform the three baasic survey measuremen m ts: 1) surfacce scanning; 2) static meeasurementss; and

3) analyssis of materiaal samples.

Instrumentation and nominal MD DC values thhat were em mployed durinng characterrization are listed in Table 2-3.

2.2.3.1. Calibrration All data loggers, asssociated deteectors, and alla other porrtable instrum mentation thhat were useed for characterrization werre calibrated d on an annu ual basis ussing Nationaal Institute oof Standardss and 2-18

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Technolo ogy (NIST) traceable t sou urces. The calibration c oof instrumentts used for ccharacterizatiion is addressed d in the QAP PP.

2.2.3.2. Instru ument Use an nd Control The receiipt, inspectioon, issue, control, and acccountabilityy of portablee radiologicaal instrumenttation used for characterizaation was performed p in n accordancee with issuee and controol procedurees for portable radiologicaal instrumen ntation. The T issue aand controll of instruuments usedd for characterrization is ad ddressed in th he QAPP.

2.2.4. Laboratory L Instrument I Methods an nd Sensitiviities Gamma spectroscop py was prim marily perforrmed by thhe on-site raadiological laboratory. Gas proportioonal countin ng and liquid d scintillatio on analysis was perform med by an approved veendor laboratorry in accordaance with ap pproved labo oratory proceedures. EnerrgySolutionss ensured thaat the quality programs p of the contraccted off-site vendor labooratories thaat were usedd for the recceipt, preparatiion and analy ysis of charaacterization samples s provvided the sam me level of quality as thhe on-site laborratory under the QAPP.

In all caases, analytiical methodss were estab blished to eensure that required M MDC values were achieved d. The anallysis of rad diological co ontaminants used standdard approveed and geneerally accepted methodolog gies or otheer comparab ble methodoologies. Taable 2-4 provvides the tyypical analyticaal methods employed and the laaboratory M MDC achievved by the off-site veendor laboratorries used for characterizaation.

2.2.5. Quality Q Assuurance MARSSIIM, section 2.2 discussees the need for f a qualityy system to ensure the aadequacy off data used to demonstratee that site conditions c arre acceptablle for unresstricted release. Laborratory quality for fo sample an nalysis takenn to supportt characterizzation and F FRS is discussed in NUR REG-1576, Mu ulti-Agency Radiologica R al Laboratoryy Analyticall Protocols M Manual (MA ARLAP) (11) and Regulato ory Guide 4..15, Qualityy Assurance of Radioloogical Moniitoring Proggrams (Incep eption through Normal Operations to License Terrmination) - Effluent Sttreams and the Environnment (12). Fu urther, MAR RSSIM and MARLAP both b indicatee that a Quaality Assuraance Project Plan may be used in add dition to, orr in lieu of, existing quuality system ms to ensurre data quality is achieved d.

The QAP PP was prep pared and im mplemented to t ensure th e adequacy of data beinng developedd and used duriing the site characterizat c tion and FRS S process. T The QAPP deescribes poliicy, organizaation, functionaal activities, the DQO prrocess, and measures m neccessary to acchieve qualitty data.

All charaacterization activities esssential to data d quality wwere implem mented and performed uusing approved d proceduress. The effeective implementation oof characteriization was verified thrrough audit anda surveilllance activ vities, inclluding fielld walk-doowns by EnergySoluutions Characterization stafff and progrram self-asssessments, aas appropriatte. Correcttive actions were prescribeed, implemeented, and verified v whhen deficienccies were iidentified. These meaasures applied to any app plicable serv vices provid ded by off--site vendorrs, as well as on-site sub-contractoors.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 The Chaaracterization n Survey Pllan was dev veloped accoording to thhe essential elements oof the quality assurance a andd quality co ontrol (QA/Q QC) program m for the deccommissioniing of LACB BWR and is su ubject to the QAPP. Thee QA/QC program elem ments applicaable to charaacterization aare as follows:

Establishmen E nt/implementtation of plan ns, procedurres, and prottocols for thee field opperations.

Actions A to en nsure that thee procedures are understoood and folllowed by thee implementiing sttaff.

Documentatio D on of the datta collected.

Details of o the QA/QC C elements specific s to ch haracterizatiion are preseented in the Q QAPP, as w well as the proceedures and sample s plan instructions. The charaacterization ooperations annd the assocciated data acqu uisition and d recording was guided d and conduucted in com mpliance wiith these QA A/QC requiremments. The sp pecific QA/Q QC program m component s for site chaaracterizatioon are as follows:

Personnel quaalifications, experience, and trainingg.

Execution E in accordance with approv ved procedurres.

Proper docum mentation of survey data and sample analyses.

Selection of appropriate a instruments i to t perform thhe surveys.

Proper instrum ment calibraation and daiily functionaal checks.

Management M oversight off characterizzation activitties relative tto the adhereence to prrocedures, protocols, p and documentaation requireements.

All charaacterization activities were w conductted in accorrdance with the Charactterization Suurvey Plan, the QAPP, all applicable a im mplementing g procedures , and approvved sample pplan instructions.

2.3. Summary off Characteriization Surv vey Results In Octobber of 2005, Dairyland performed p a limited chaaracterizationn survey of the LSE priior to placing the t unit into o a SAFSTO OR condition n. This surrvey is docuumented in Reference 77. In October of 2014, Dairyland contracted EnergySollutions to perform a more dettailed characterrization of LACBWR L in n anticipationn of the deveelopment off this LTP annd the anticippated accelerattion of decommission ning activitiies. Charracterizationn activities,, performedd by EnergySo olutions in accordance a with w EnergyS Solutions chaaracterizatioon procedurees commenceed on October 9,9 2014. The T scheduleed EnergyS Solutions sitte characteriization effoort concludeed on August 6, 6 2015. Thee results of th he site charaacterization ssurveys perfformed by EnnergySolutioons is documen nted in two o separate reports, GG G-EO-3131996-RS-RP-001, LACBW WR Radioloogical Characteerization Surrvey Report for Octoberr and Novem mber 2014 F Field Work ((13) and LC C-RS-PN-1640 017-001, LACBWR Radiiological Ch haracterizatiion Survey R Report for JJune thru August 2015 Fieeld Work (14 4).

Radioacttive systemss that remaain at LAC CBWR affeccted the ability to acqquire meaniingful characterrization data in certain n areas du ue to ambieent radiatioon levels. In these ccases, characterrization has been deferreed until such h time that raadiological oor physical cconditions w would 2-20

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 allow thee survey of these survey units. Solutions intendss to continuee characterizzation througghout the decom mmissioning g process, inncluding folllowing the ssubmittal of this LTP. IIn the case w where significannt additional characterizzation data isi obtained, this chapterr of the LTP P will be updated by revisioon or addenddum as a parrt of the requ uired 2 year update of thhe approved LTP.

2.3.1. Background B Study During the t initial ch haracterization survey performed p inn October 2005, Dairyland perform med a backgrou und study foor soils at LA ACBWR. Reference R 7 states that a series of soil samples were acquired from vario ous location ns outside of o the owneer controlledd area. Thhe result off this backgrou und study is summarized d in Table 2-5.

As part ofo the 2014 characterizaation effort, EnergySoluutions perforrmed a limitted assessmeent of backgrou und levels ata LACBWR R. The purrpose of thee study wass to assess iif backgrounnd at LACBW WR fell within n nominal ex xpected leveels for soils, concrete, annd asphalt.

Normally y, backgroun nd reference areas should be reasonaably close too the decomm missioning ssite to be repressentative. However, H no suitable offf-site locatioon was identtified. Conssequently, ann on-site area was chosen.. The Energ gySolutions Project P Heallth Physicist and the Raddiation Proteection Supervisor selected an a area outsside of the LSE L but on the licensedd LACBWR site that seemed appropriaate for obtainning backgro ound measurements bas ed upon the previous radiological suurvey results. Although th he selected sample s locattions were iinside the LA ACBWR liccensed area,, they were con nsidered unafffected by paast LACBW WR operationns.

Concretee samples an nd direct measurements were taken in Class 3 ssurvey unit L L3012101, w which is locatedd north of thhe LSE. Asphalt samp ples and direect measurem ments were also collectted in non-impaacted survey y unit L4012 2106. Surfaace soil sampples were accquired from m a small arrea of approximmately 100 square meterrs of undistu urbed non-drrainage soil within non--impacted suurvey unit L4012108. Soill samples fro om non-imp pacted surveyy units L40112107 and oother areas w within L401210 08 were also evaluated forf use as baackground reeference soills. Analysiss results for these samples are a provided d in sections 2.3.3 and 2..3.5.3.

The analysis of thee backgroun nd soil sam mples in 20114 compareed favorablyy with the 2005 backgrou und study foor soils. Thee results did d report Cs-1137 at levelss slightly abbove MDC. This can be atttributed to global g fallou ut. For the two t backgrouund studies performed aat LACBWR R, the mean Cs-137 concen ntration of surface s sampples taken o n or aroundd the site prooduced a meean of 0.135 pCCi/g with a maximum m ob bserved con ncentration oof 0.268 pCii/g. The sttandard deviiation was 0.070 resulting ini the upperr range for th his data set aat a 95% connfidence leveel of 0.275 pCi/g.

Relevantt to LACBW WR is a study y performed for the decoommissioninng of the Zioon Nuclear P Power Station (ZZNPS) titledd ZionSolutio ons TSD 13-004, Examiination of Css-137 Globaal Fallout in Soils at Zion Station S (15). This docum ment was prrepared to coompare site soil sample Cs-137 resuults at Zion to Cs-137 C levels anticipateed from worrldwide fall out. The L LACBWR annd Zion sitees are geograph hically similaar. The docu ument prediccted ranges ffor backgrouund concentrrations of Css-137 for distu urbed soils asa well as undisturbed u soils and is presented iin Table 2-66. The obseerved backgrou und Cs-137 levels for th he site specific backgrouund studies performed aat LACBWR R fall within thhe expected range of disturbed d soils in non-ddrainage areeas. As theere were vaarious categoriees of soil in the non-im mpacted areas at LACBW WR, the uppper 95th percentile levells for drainage and non-draainage, distu urbed and un ndisturbed sooil from the Zion backgrround study were 2-21

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 considereed appropriaate backgro ound concen ntration leveels for the evaluation of non-imppacted areas, and Class 2 an nd 3 open lan nd area surveey units at L LACBWR.

2.3.2. Potential P Radionuclidess of Concern n EnergySo olutions TS SD RS-TD-3 313196-001,, Radionucclides of C Concern During LAC CBWR Decommissioning (16) ( establishes the baasis for an initial suitee of potentiial ROC foor the decommiissioning of LACBWR. Industry gu uidance was reviewed ass well as the analytical reesults from the sampling of o various media m from past p plant ooperations. Based on thhe eliminatioon of some of the t theoreticcal neutron activation a pro oducts, noblle gases and radionuclidees with a hallf-life less than n 2 years, an n initial suitee of potentiaal ROC for the decomm missioning of LACBWR R was prepared. The list off potential raadionuclides is listed in T Table 2-7.

2.3.3. Non-Impacte N ed Open La and Areas Based up pon the inforrmation com mpiled in thee HSA, a larrge portion oof the open land areas oon the 163.5 acrre licensed site surroun nding the LSE L and ISSFSI receiveed a classiffication as non-impacted d. The non-impacte n d areas haave no reaasonable pootential to contain ressidual contamin nation given that historiccal informatiion providess no indicatioon of impactt from LACB BWR operationns. The dettermination that the con ntiguous opeen land areaas surroundiing the LSE E and ISFSI were w not imp pacted by licensed l opeerations wass based on the locatioon(s) of liceensed operationns (i.e., withhin the LSE), site use, topography, t site discharrge pathwayys, and otheer site physical characteristics. The areeas designatted as non-im mpacted aree not requireed to be survveyed for comp pliance beyo ond the charaacterization surveys andd sampling pperformed too provide a basis for the cllassification..

The non--impacted op pen land area is approxim mately 352,3360 square m meters in sizze. This areaa was segregateed into five survey unitts. Non-imp pacted openn land surveey unit L4012109 is loocated inside off survey uniit L4012108 8 in a vegetated area w with minimall ground dissturbance eaast of Highway y 35. This survey s unit was formed d during chaaracterizatioon to facilitaate a backgrround study forr soils. The non-impacteed survey un nits are showwn in Figure 2-1. The G G-3 station reesides within suurvey unit L4 4012103. A majority off the surface area in survvey unit L40012105 is covvered in coal from f the G--3 station an nd survey un nit L40121006 completeely surroundds the LACB BWR ISFSI faccility, which h has not beeen characterizzed and is noot addressedd by this LTP P.

From Occtober 2014 to August 2015, charracterization surveys w were perform med in the non-impacted d open land areas of th he site. Thee survey uniits were oriiginally classsified as Cllass 3 survey un nits and werre characteriized as such h in Referencce 13. Baseed upon a revview of the HSA and the initial i results of the 201 14 characteriization, thesse survey unnits were recclassified as non-impacted d as it was determined d that t there is no reasonabble potentiaal for residuaal contaminaation.

To support this con nclusion, ad dditional chharacterizatioon was perfformed in 22015. A m major objectivee of the additional charaacterization surveys perrformed in 22015 was too evaluate ceertain open land d survey uniits given an initial i Class 3 classificattion for re-cllassificationn as non-imppacted by perforrming additional soil sam mpling and gamma g walkkover surveyys.

The 2015 5 characterizzation campaign was deesigned in acccordance w with Referencce 4. One oof the primary objectives of the additional charaacterization was to perrform sufficcient radioloogical surveys anda samplin ng to supporrt the non--impacted cclassificationn and to prrovide reasonable 2-22

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 assurancee that the non-impacted n d survey uniits do not ccontain plantt-derived raadioactivity. The 2015 chaaracterization n survey foccused primarrily on soils and asphaltt. The sampple locations were based on a random design to ensu ure an unbiaased survey.

During th he 2015 chaaracterization survey, a minimum oof 1% of thee surface sooil area in suurvey units L40 012103, L40 012105, L40 012106 and L4012108 was scannedd with a Moodel 2350-1 data logger with w a 2 by 2 2 NaI detecctor. In surv vey unit L40012107, lesss than 1% off the surfacee area was scan nned due to inaccessibiliity from thee presence o f tall, thick vegetation aand steep terrain.

Gamma surface s scannning focused d on undistu urbed soils w with minimall vegetation or disturbedd soils or gravell. Alarm seet-points forr the instrum ment were sset at the obbserved backkground pluus the Minimum m Detectable Count Raate (MDCR)) of the insstrument. A total of ffour alarms were evaluatedd during thee performan nce of the gamma g scann, one in suurvey unit L L4012106, tw wo in survey unnit L4012107 and one in n survey unitt L4012108. All scan allarms were innvestigated uusing an Explo oranium GR--135. The results of th he investigaation indicatted the elevvated scan reesults were duee to the preseence of naturral backgrou und activity.

Thirty-tw wo surface soils sampless were colleected from non-impacteed areas at locations bbiased toward discolored d areas or areas where the ground g had bbeen disturbeed. The sammple locationns are shown in n Figure 2-5 5. Cs-137 was positiv vely identiffied in conccentrations greater thann the instrumen nt MDC in 26 of the 32 2 samples. No other pootential plannt-derived raadionuclides were positivelyy identified by gamma spectroscopy s y. The averaage Cs-137 cconcentration observed iin the surface soil s samples was 0.131 pCi/g with a maximum m observed cconcentrationn of 0.463 ppCi/g.

These vaalues are within the expeected backgrround range for Cs-137 surface sam mples as discuussed in section n 2.3.1. Only one Cs-13 37 result excceeded the m maxium resuult of 0.268 pCi/g in thee site-specific background b data set. Thhis sample was w the maxiimum 0.463 pCi/g valuee and was loocated in the grrounds east of Highway y 35. The mean m of the nnon-impacteed and site-sspecific dataa sets were very y close at 0.135 pCi/g an nd 0.131 pCi/g, respectivvely.

Seventeeen subsurface soil samplles were tak ken at random mly selectedd locations tto a depth oof one meter. Of the 17 7 subsurfacee soil samp ples taken, Cs-137 w was positiveely identifieed in concentraations greateer than the instrument MDC in ei ght sampless. No otherr potential pplant-derived gamma-emit g tting radionuuclides weree positively iidentified byy gamma sppectroscopy. The average Cs-137 conccentration ob bserved in the t subsurfaace soil sam mples was 0.087 pCi/g w with a maximum m observed concentratiion of 0.40 09 pCi/g. Thhese valuees are withhin the exppected backgrou und range for Cs-137 as discussed in n section 2.33.1. Only onne subsurface sample had Cs-137 conccentrations th hat exceeded the maxim mum Cs-1377 concentratiion found inn the site-speecific surface soil s backgrou und. This sample s was thet maximuum 0.409 pC Ci/g value that was locatted in the Hwy 35/Railroad d Right of Way W Grounds.

Two asp phalt samplees were colllected from random loccations in ppaved areas in non-imppacted survey un nits. The asp phalt surfacee was first sccanned withh a beta-gamm mma detector. All scan reesults 2

were lesss than the MDC M of 1,93 38 dpm/100ccm . No plaant derived rradionuclides were posittively identified d by gamma spectroscop py in any of thet asphalt ssamples.

A summary of the gammag specttroscopy resu ults for eachh non-impaccted open laand survey uunit is presentedd in Table 2--8.

2-23

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 A coal assh sample frrom survey unit u L4012105, six surfa face soil sam mples and fivve subsurface soil samples were sent to o Test Ameerica Laboraatories for ggamma specttroscopy andd HTD anallyses.

The resullts of the anaalysis are preesented in Table T 2-9.

The lab boratory an nalysis sporradically id dentified seeveral plannt-derived rradionuclidees at concentraations exceeeding the MD DC, includin ng H-3, C-144, Fe-55, Nii-63, and Sr--90. Cs-1377 was also positively detectted but at lev vels that are consistent w with natural bbackground. In all casees, the concentraations of thee positively identified i rad dionuclides w were close tto the detectiion limits annd are considereed to very liikely be the result of cou unting uncerrtainty as oppposed to the actual pressence of the pllant-derived radionuclid des. This conclusion c w was supporteed by a revview of exppected radionuclide mixturre fractions. For exam mple, samp le L30121005-CR-GS-0002-SS indiicates positive results for Cs-137, C Sr-90 and Fe-5 55. Howevver, the Sr-990/Cs-137 annd Fe-55/Css-137 ratios arre 118 and 16, respecttively. Wh hen the ratiios from L33012105-CR R-GS-002-SS S are compared d to the sitee-specific miixture fractions in Chappter 6, Tablee 6-3, it is seen that theey are higher thhan expected d by factorss of 4,800 and a 10,700, respectivelly. In concclusion, baseed on operationnal history, the t radionuclide ratios, and a primarilyy the concenntrations of C Cs-137 whicch are consistennt with naturral backgrou und and com mprise 88% oof the site-sppecific radioonuclide mixxture, the sporaadic positive analytical results are veery unlikely to representt the actual ppresence of pplant-derived radionuclide r s in these suurvey units.

In surveyy unit L4012 2108, a reprresentative sample s of thhe rail road bed gravel was analyzeed by gamma spectroscopy s y. In additio on, gamma scan s readinggs were takeen of the raill road bed ggravel area to determine d iff there is a significant difference from site bbackground (which averraged approximmately 7,000 0 to 8,000 cp pm). The analysis a of tthe railroad bed gravel indicated naatural uranium and thorium m series nucclides with no plant deerived radioonuclides. T The gamma scan readings conducted during d the walkover surv vey averagedd 7,000-8,5000 cpm.

2.3.4. Im mpacted Op pen Land Areas A

The HSA A identified d the open land area inside the fenced LSE E as impaccted by reeactor operationns. The app proximate areea is 1.5 acrres. All opeen land surveey units insiide the LSE have been classsified as Class C 1. An approximattely 3.46 acrre area that surrounds tthe LSE hass also been iden ntified as iimpacted by reactor op perations. T This open laand area has been segregated into two Class 2 surv vey units. Three T impactted Class 3 ssurvey units were designnated for thee area north of the LSE, th he transmisssion switchy yard and thee area encom mpassing thhe site accesss off Highway y 35 and thee haul road used u to tran nsport dry fuuel casks to the ISFSI. The area oof the three Claass 3 survey units combin ned is approoximately 166.5 acres.

The charracterization of the impaccted open laand areas beggan in Octobber 2014. A sample plann was prepared for each surveys unit in accordaance with R Reference 44. Survey techniques were employed d to determine the laterral and vertical extent oof any contamination iddentified annd the radionuclide concenttrations in th he soil. Charracterizationn inspectionss and surveyss were perfoormed of sufficiient quantity y and quality y to quantify the potentiaal volumetricc contaminattion of accesssible surface and a subsurfface soils in n each open n land surveey unit. Liimited soil informationn was obtained from below w the structurres due to intterferences aand inaccessibility.

Survey techniques were emplloyed to deetermine thhe lateral aand verticall extent off any contamin nation identiified and th he radionucllide concenttrations in tthe soil. A combinatioon of 2-24

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 random anda biased survey locatiions were esstablished in each surveyy unit in acccordance witth the survey package. Thee locations of o biased meeasurementss and/or sam mples were ddetermined bby the professioonal judgmeent of the EnergySoluti E ions Project Health Phyysicist and the Radioloogical Protectioon Supervisor. Consideration waas given too locations that exhibbited measuurable radioactivvity, depressions, discolored areas, low point ggravity drainn areas, actuual and poteential spill locaations, or arreas where thet ground had h been diisturbed. Thhe number of random-bbased survey loocations wass also determ mined by areea classificattion. Random-based meeasurements were not requ uired for soiils in an op pen land areeas designat ated as Classs 1. Randoom measureement locationss were seleccted on asp phalt in Claass 1 surveyy units wheere there waas no historry of radiologiical contamin nation.

A surfacee soil samplee was taken at each selected biased aand random-based surveey location. Sub-surface soil samples were acquirred at severaal random lo cations or iff surface soil sample anaalysis or surfacce scans indiicated elevatted activity. Depending on the locaation, subsurface soil sam mples were takeen from 0.15 5 cm to deptths ranging from f 1 to 3 m below graade and com mposited over 1 m intervals.

Each surrface soil, coomposite sub bsurface soill sample or asphalt sam mple was anaalyzed by thhe on-site radioological laboratory by gamma-specctroscopy. Analysis coount times w were adjusteed as necessary y to achievee an isotopicc MDC equaal to or lesss than 0.10 ppCi/g for Css-137 and C Co-60.

All surfaace and subsurface com mposite samp ples were annalyzed afteer drying thhe sample m media.

Several soil s samples were selecteed at random m and were sshipped to T Test Americaa Laboratoriees for full isoto opic analysiss (HTD radiionuclides). Duplicate samples andd concrete w were collecteed by survey un nit per Refeerence 4.

2.3.4.1. Class 1 Open Lan nd Areas There aree four (4) op pen land surrvey units cllassified as Class 1 at L LACBWR tootaling 8,4433 m2.

The Classs 1 open lan nd survey un nits are show wn in Figure 2-1. A signnificant portiion of the suurface area in thhe Class 1 op pen land surrvey units is obstructed bby the preseence of builddings, namelly the Reactor Building, th he Turbine Building, th he WTB andd the LSA Building. The presence of radioactivvely contamminated build ding and sysstems, as weell as stored radioactive material in these areas, preevented the ability a to perrform surfacce scanning ddue to high bbackground..

Twenty-ttwo (22) surrface soil sam mples were taken at loccations biaseed toward sittes that exhiibited measurab ble radioacttivity, discolored areas,, buried pippe locationss, actual annd potential spill locationss, or areas where w the groound had beeen disturbedd. The locaations of surfface soil sam mples taken in Class 1 open n land surveey units are shown s in Figgure 2-6. O Of the 22 surface soil sam mples taken, Co-60 C was positively p id dentified in concentratiions greaterr than the M MDC in tw wo (2) samples and Cs-137 7 was posittively identtified in conncentrationss greater thhan the MD DC in 13 samplles. No oth her potentiaal plant-deriv ved gammaa-emitting raadionuclidess were posittively identifiedd by gamma spectroscop py. The averrage Co-60 cconcentratioon observed in the analysis of the surfface soil saamples wass 0.058 pCi//g with a maximum observed cconcentratioon of 0.287 pCCi/g. The average Cs-1 137 concenttration obserrved in the analysis off the surfacee soil samples was w 0.096 pCi/g with a maximum m ob bserved conccentration of 1.07 pCi/gg.

Seventy-nine (79) su ubsurface soil samples were w taken aat 10 surfacee soil locatioons to a deppth of one meteer, two (2) loocations biassed to areas ono the south and west sidde of the WG GTV and fivve (5) 2-25

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 locationss that accessed the soils under the Turbine Buildding throughh angled Geooprobe samppling.

The sam mples at the two t WGTV V locations were w acquireed to a deptth of five m meters in ordder to evaluate the subsurfaace soils alon ngside and underneath u thhe vault. Thhe samples uunder the Tuurbine Building were taken and composited at deptths of 10, 155 and 20 feeet. Of the 779 subsurfacee soil samples taken, Cs-1 137 was possitively iden ntified in cooncentrationns greater thhan the MD DC in 15 samplles. No oth her potentiaal plant-deriv ved gammaa-emitting raadionuclidess were posittively identifiedd by gammaa spectroscop py. The aveerage Cs-13 7 concentrattion observeed in the anaalysis of the su ubsurface sooil samples was 0.055 pCi/g p with a maximum m observed concentratioon of 0.161 pCCi/g. The asssessment of potential su ubsurface soiil contaminaation in the C Class 1 openn land areas is not currenttly completee. Soil in difficult too access areeas such ass under buiilding foundatio ons and surrrounding bu uried structu ures and pipping has beeen deferred until later in the decommiissioning pro ocess, when access will beb more readdily availablle.

Ten sam mples were taaken of asp phalt from paved p areas in Class 1 ssurvey unit L1010104. The asphalt was w taken fro om the samee location selected for thhe surface annd subsurfacce soil samplles in this survvey unit. Th he asphalt surface s was first scanneed with betaa-gamma deetector with scan results raanging from the instrumeent MDC off 2,771 dpm//100cm2 to a maximum of observedd scan measurem ment of 3,09 95 dpm/100 cm2. Of th he 10 asphallt samples ttaken, Cs-1337 was posittively identifiedd in concen ntrations greeater than MDC in onnly one sam mple at a concentratioon of 0.057 pCCi/g.

A summary of the fiindings of th he survey fo or each indivvidual Classs 1 open landd survey unnit are presented d in Table 2--10.

Nine surrface soil saamples, 11 subsurface s soil s sampless, one concrrete sample and two assphalt samples taken from Class 1 open n land surveey units werre sent to Teest Americaa Laboratoriees for gamma spectroscopy s y and HTD analyses.

a Th he results off the analysiss are presentted in Table 2-11.

In addition to detectting Co-60 and Cs-137, H-3, C-144, Fe-55 andd Ni-63 werre also posittively detected at concentraations greater than the innstrument MD DC.

One sediiment samplle was taken n from the sanitary s solidds tank that is located iin Class 1 suurvey unit L1010103. Thiss sample waas also sent to t Test Amerrica Laborattory for gam mma spectrosscopy and HTD D analyses. Co-60 and C-137 weree detected inn this sample, both at a concentration of 0.136 pCCi/g.

2.3.4.2. Class 2 Open Lan nd Areas The impacted Class 2 open lan nd areas totaal approxim mately 13,996 m2 and arre located inn the immediatte area surro ounding the LSE. The Class C 2 impaacted open land area waas segregatedd into two survey units. Th hese are shoown in Figurre 2-1. The LACBWR Administrattion Buildingg, the LACBW WR Crib Hou use, the G-3 3 Crib Housse and the L LACBWR w warehouses aare all locatted in these two o survey unitts.

Approxim mately 1% ofo the surfacce soil area in i survey unnit L2011101 was scannned with a M Model 2350-1 data d logger with w a 2 by y 2 NaI deetector. Thiis area incluuded asphaltt paved surffaces.

Alarm seet-points for the instrumment were sett at the obseerved backgrround plus tthe MDCR oof the instrumen nt. No scan alarms weree observed.

2-26

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Twenty-tthree surface soil samp ples were tak ken at locattions biasedd toward sites that exhiibited measurab ble radioacttivity, discolored areas,, buried pippe locationss, actual annd potential spill locationss, or areas where w the groound had beeen disturbedd. The locaations of surfface soil sam mples taken in Class 2 open n land surveey units are shown s in Figgure 2-7. OOf the 23 surface soil sam mples taken, Css-137 was positively p ideentified at cooncentrationns greater thhan MDC in 14 samples. No other pottential plantt-derived rad dionuclides were positivvely identifiied by gamm ma spectrosccopy.

The averrage Cs-137 7 concentrattion observeed in the annalysis of thhe surface ssoil sampless was 0.077 pC Ci/g with a maximum m obsserved conceentration of 0.200 pCi/gg.

Twenty-tthree subsurface soil sam mples were taken t at 14 rrandom locaations to a deepth of one mmeter and threee locations biased b to areeas alongsidde and underrneath the S Storm Sewerr Water pipee that resides inn survey uniit L2011101 1. The biaseed samples w were acquireed to a deptth of five mmeters.

Of the 23 2 subsurfacce soil samp ples taken, Co-60 was positively identified aat concentraations greater thhan MDC in n one samplee and Cs-137 was positiively identiffied at conceentrations grreater than MD DC in four samples. No N other po otential plannt-derived raadionuclidess were posittively identifiedd by gamma spectroscop py. The sing gle sample w with detectabble Co-60 haad a concentrration of 0.112 pCi/g. The average Cs--137 concenttration obserrved in the aanalysis of thhe subsurface soil samples was 0.043 pCi/g with h a maximu um observe d concentraation of 0.0088 pCi/g. The assessmeent of poten ntial subsurfface soil con ntaminationn in the Claass 2 open lland areas is not currentlyy complete. Soil in diffficult to access areas ssuch as undder building foundationss and surround ding buried structures s an nd piping haas been defeerred until later in the ddecommissiooning process, when w accesss will be morre readily av vailable.

Twelve samples s weree taken of assphalt from paved p areas in Class 2 suurvey units. The asphallt was selected randomly. The asphaltt surface was first scannned with betta-gamma deetector withh scan results ranging r fro om the insstrument MDC M of 2,,529 dpm/1000cm2 to a maximum m of 2,748 dpm m/100cm2. Of the 12 2 asphalt samples takenn, Cs-137 w was positiveely identifieed in concentraations greatter than thee instrumen nt MDC in three sampples. The average Css-137 concentraation observ ved in the an nalysis of thee asphalt sam mples was 00.049 pCi/g with a maxiimum observed d concentration of 0.055 pCi/g.

A summary of the fiindings of th he survey fo or each indivvidual Classs 2 open landd survey unnit are presented d in Table 2--12.

Three surrface soil saamples, five subsurface soil s samples,, three asphaalt samples aand two sediiment samples taken from m an accesssible storm m sewer baasin manholle located in front off the Administtration Build ding were seent to Test America Laaboratories ffor gamma sspectroscopyy and HTD anaalyses. The results of th he analysis are a presentedd in Table 2-13. In adddition to deteecting Co-60 anda Cs-137, H-3, C-14 4, Fe-55 an nd Cm-243//244 were also positivvely detecteed at concentraations greateer than MD DC. As disccussed in seection 2.3.3 for non-imppacted areass, the HTD rad dionuclides exceeding e MDC M are likelly to be falsee positives.

2.3.4.3. Class 3 Open Lan nd Areas The impaacted Class 3 open land areas total approximatel a ly 66,765m2. The Class 3 impacted open land areaa was segreegated into three surveey units. T The Class 3 survey uniits are show wn in Figure 2--1. The Claass 3 impacteed open land d survey unnits include tthe north ennd of the liceensed site, the transmission t n switchyard for the LAC CBWR and G G-3 facilities, the LACBBWR plant aaccess 2-27

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 and rightt-of-way area and the haaul road to th he ISFSI faccility. The nnorth end off the licensed site was deem med impacteed by LACB BWR due to o the presennce of a sepptic system that servicees the LACBW WR Administtration Build ding and the presence off concrete fr from impacteed structuress (the Crib Hou use). The trransmission yard was deemedd as im mpacted as iit was part oof the LACB BWR facility during d operattions. The plant p access area, Highw way 35 rightt-of way andd ISFSI haull road were deeemed as imp pacted by thhe transit off packaged rradioactive m material throough these aareas.

These arreas were conservativelly classified d as impacteed. Howevver, it should be notedd that Solutionss maintains that t classifyiing these areeas as non-im mpacted wouuld have beeen appropriatte.

A minim mum of 1% of the surfface soil areea in surveyy units L30012101 and L3012109 were scanned with a Model 2350-1 daata logger with w a 2 by 2 NaI deteector. Surveey unit L30112102 was exclluded from gamma surrface scanniing for safeety reasons. Gamma surface scannning focused ono undisturb bed soils wiith minimal vegetation oor disturbedd soils or graavel. Alarm m set-points for the instrum ment were seet at the obseerved backgrround plus tthe MDCR oof the instrum ment.

No scan alarms weree observed in n these surveey units.

Thirty-twwo surface so oil samples were taken at locations biased toward discolorred areas or areas where th he ground haad been distturbed. Thee locations oof surface soil samples taken in Cllass 3 open land survey un nits are showwn in Figuree 2-8. Of thhe 32 surfacee soil samplles taken, Css-137 was positively identiified in conccentrations greater g than MDC in 26 samples. N No other poteential plant-derrived gammaa-emitting raadionuclidess were positiively identiffied by gamm ma spectrosccopy.

The averrage Cs-137 7 concentrattion observeed in the annalysis of thhe surface ssoil sampless was 0.131 pC Ci/g with a maximum m obsserved conceentration of 0.463 pCi/gg.

Seventeeen subsurface soil samplles were tak ken at random mly selectedd locations tto a depth oof one meter. Of the 17 7 subsurfacee soil samp ples taken, Cs-137 w was positiveely identifieed in concentraations greaater than MDC M in eiight sampless. No oth ther potentiial plant-deerived radionuclides were positively identified by gamma spectroscoopy. The average Css-137 concentraation observ ved in the analysis a of th he subsurfacce soil sampples was 0.0087 pCi/g w with a maximum m observed concentratio c on of 0.409 pCi/g.

p Two sam mples were taken of asph halt from paaved areas inn Class 3 suurvey units. The asphaltt was selected randomly. The asphalt surface was first scannned with betta-gamma deetector. Alll scan results were w less thaan instrumennt MDC of 1,9381 dpm/1100cm2. Noo plant derivved radionucclides were possitively identtified by gammma spectroscopy in anyy of these sam amples.

A summary of the fiindings of th he survey fo or each indivvidual Classs 3 open landd survey unnit are presented d in Table 2--14.

As part of o the characcterization off survey unitt L3012101,, samples weere taken froom several ppieces of concreete located in i the northh section of the survey uunit that oriiginated from m the LACB BWR Crib Hou use. In addiition, a sammple was takeen from a saanitary tankk that servicees the LACB BWR Administtration Build ding and twwo sedimentt samples w were taken frfrom a storm m sewer bassin in survey un nit L3012109. These sam mples were sent off-sitee for isotopicc analysis.

Three co oncrete samp ples from suurvey unit L3 3012101, thhe sanitary taank sample from surveyy unit L301210 01, the two seediment sam mples taken from f the storrm sewer baasin in surveyy unit L30122109, three surrface soil samples s and d two subssurface soil samples w were sent tto Test Am merica Laborato ories for gam mma spectrroscopy and d HTD anallyses. The results of the analysiis are 2-28

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 presented d in Table 2-15.

2 The analysis off these sampples positiveely identifieed several pplant-derived ROC R at residdual concenttrations greaater than thee instrument MDC, incluuding H-3, F Fe-55 and Ni-6 63. As disscussed in section s 2.3.33 for non-im mpacted areeas, the HT TD radionucclides exceedin ng MDC are likely to be false positiv ves. Cs-137 was also poositively deteected but at llevels consistennt with naturral backgroun nd.

2.3.5. Non-Impacte N ed Structures Based up pon the infformation co ompiled in the HSA, S Solutions cooncluded thhat the strucctures associateed with the G-3G Coal Plaant may be classified c as non-impaccted. Histoorical inform mation indicatedd that there was w no reaso onable poten ntial for residual contammination from m site operattions.

A full lisst of G-3 struuctures that have been designated d ass non-impaacted is provvided in Tabble 2-2.

The prim mary basis for f the non n-impacted classificatioon for the G G-3 station structures iis the informatiion documen nted in the HSA H that thee G-3 structuures were noot used for LLACBWR-reelated operation ns. Additionally, the potential p for windborne migration oof airborne effluent releeased from thee LACBWR R Stack du uring operaations to sstructure rooofs was evvaluated byy the characterrization of thet LACBW WR Administtration Buildding roof annd the G-3 Coal Plant roof.

The resu ults are prov vided in Reeference 13. Additionnal surveys of the G-3 structures were conducteed during thee 2015 charaacterization campaign w where the suurfaces subjeected to highh foot traffic in the major sttation buildin ngs were surrveyed.

The G-3 station ressides in non n-impacted survey s unit L4012103. There aree no documented incidentss of radioacttive contam mination of soils, s asphallt or concreete in this suurvey unit. The results off the characterization surrveys perform med in the G G-3 station aare summarizzed as follow ws:

A scan su urvey was performed p off the mid-lev vel roof of thhe G-3 Coall Plant buildding using a beta-gamma detector.

d In addition, six x (6) locatioons were seleected at randdom for direect measurem ments using an alpha/beta-g gamma prop portional deteector. A sm mear sample for removabble contaminnation was also taken at the location of each direct measuremen m nt. The resuults of the beeta scan idenntified gross betta-gamma activity rangiing from 2,3 302 dpm/10 0cm2 to 2,8816 dpm/1000cm2 with a scan 2

MDC off 2,816 dpm//100cm . The T results of o the direcct beta-gamm ma and alphha measurem ments 2

identifiedd gross beta--gamma actiivity ranging g from 1,6033 dpm/100cm m to 2,072 dpm/100cm m2 and gross alp pha activity y ranging from f 142 dp pm/100cm2 to 258 dpm m/100cm2. No removvable contamin nation was identified at concentratio ons greater tthan MDC bby the analyysis of the ssmear samples. The roof material m itseelf was samp pled on Junne 30, 2015. Cs-137 waas the only plant derived ROC that was w positiveely identifieed by gamm ma spectrosscopy at a concentratioon of 0.061 pC Ci/g. Based on the fact that t no otherr plant derivved ROC waas detected, it was conclluded that the elevated dirrect alpha measurements m s were due most likely to the pressence of coaal ash material on the roof.

Direct an nd removablle contamination survey ys were perfformed of reepresentativve high persoonnel traffic arreas of the G-3 Coal Plant. P Scan n measuremeents were pperformed ussing the Luudlum Model 23 360 instrumeent with 43--93 detector.. Approxim mately 5% off the concrette surfaces iin the areas of interest i weree scanned, in ncluding floo ors and loweer wall surfaaces. The avverage scan M MDC 2 2 ranged from f 2,540 dpm/100cm m to 2,617 7 dpm/100cm m . No oobserved scaan measureement exceeded d the MDC during d the co ourse of thiss survey. Teen (10) locattions were chhosen at ranndom, 2-29

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 primarilyy from the main lobby y area and the mainteenance area.. The resuults of all ddirect measurem ments for gross g activity was less than the M MDC of 74 dpm/100cm m2 for alphaa and 875 dpm/100cm2 for beta-gamma. No remov vable contammination waas identified at concentraations greater thhan MDC by y the analysis of the smear samples.

2.3.6. Im mpacted Strructures an nd Systems The deco ommissionin ng approach h for LACB BWR requirres the dem molition andd removal oof all impacted d buildings, structures, s syystems and components c to a depth oof at least 3 feet below ggrade.

In additioon, all systemms and expo osed metal below b 3 feet below gradde will also bbe removed. The accepted elevation fo or grade at LACBWR L is the 639 fooot elevation. The only sttructures thaat will remain and a be subjeected to STS S are the rem maining reinnforced conccrete walls aand floors oof the Reactor Building B thaat will be exp posed by thee removal off the interiorr concrete annd steel lineer, the remainin ng reinforcedd concrete walls w floors of o the WTB, the remainiing reinforceed concrete walls and floo ors of the WGTV, an nd the rem mainder of the Pipingg and Venttilation Tunnnels, Reactor/G Generator Plant basemeent, the one foot thick pportion of thhe Chimneyy Foundationn, the Turbine sump and th he Turbine pit. Conseq quently, all systems andd componennts and strucctural surfaces above the 636 foot eleevation willl be remediiated, disasssembled andd/or demoliished, segregateed by waste classificatio on and dispo osed of as cclean demoliition debris, clean salvaage or radioactivve waste. No extensiive characteerization waas or will bbe performeed of equipm ment, systems oro structuress that will bee removed prrior to the peerformance oof FRS.

Radiolog gical surveyss of the interriors of structures at LAC CBWR are rroutinely perrformed to ennsure complian nce with 10 0 CFR 20 reequirements regarding the postingg of areas and to ideentify radiologiical conditioons for the im mplementation of controols for the prrotection off workers in these areas. The radiolo ogical inforrmation from m these suurveys will provide thhe basis forr the disassemmbly and rem moval of systtems and thee demolition of impactedd structures aat the site. W When remediation has adeequately red duced radiollogical condditions to leevels suitablle for contrrolled demolitio on, the impaacted structu ures will be demolishedd, packaged and properlly disposed of as waste.

After com mmodity rem moval is com mplete, the structures thaat will remaiin at license terminationn, i.e.,

3 feet beelow grade,, will be re-surveyed r to determiine the conncentrations of the ressidual radioactivvity and thee extent of additional a reemediation rrequired, if aany, to meett the unrestrricted use criterria.

2.3.6.1. Basemment Structu ures Below 636 Foot Elevvation Characterization of the structurral surfaces of basemennts that willl remain inn the end-sstate consistedd primarily of o the acquisition and rad diological annalysis of cooncrete core samples from m the walls and floors of the Reactorr Building, WTB and the balancee of the bassement strucctures (primarilly the Pipingg Tunnels). In June and July of 20155, a series of concrete coore samples were taken froom the 615 foot elevation concrete floor and tthe concretee floor and east wall on the 621 foot elevation in n the Reactorr Building, th he 630 foot elevation cooncrete floorr of the WTB B and the 633 foot f elevatio on concrete floor f of the Piping P Tunnnels. A totall of twelve (12) concretee core samples were w collectted, six (6) in n the Reacto or Building, three (3) in the WTB annd three (3) iin the Piping Tu unnel. The locations l whhere the coree samples weere taken aree shown in F Figures 2-9.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The locaations selecteed for concrrete core sam mpling were biased tow ward locationns where phyysical conditionn or observ ved radiolog gical measu urements inndicated thee presence of fixed aand/or volumetrric contamination of the concrete. When W possiblle, locations were determ mined based upon elevated observed co ontact dose rates r or counnt rates. In aaddition, vissual observattions of flooor and wall surfaces were used to id dentify poten ntial locatioons of surfface contam mination, succh as discoloraation or stan nding water. The goal was w to identtify, to the eextent possibble, the locaations that exh hibited the highest h potential of reepresenting the worst case boundding radioloogical conditionn for concreete in each survey s unit. This judggmental samp mpling approach also ensured there wass sufficient source s term in the cores to achieve tthe sensitivitties requiredd to determinne the radionuclide fraction ns of gamma emitters as well w as HTD D radionucliddes.

The conccrete pucks representing r g the first 1/2 inch of conccrete at eachh sample loccation was seent to Test Ameerica Laboraatory for gam mma spectro oscopy and H HTD analysees for beta annd alpha em mitting ROC. In n addition, the concretee pucks rep presenting thhe concrete deeper thann 1/2 inch deeep at Reactor Building B mple locations #001, #003, #005 annd #006 and WTB sample locations #001 sam and #002 2 were also o sent for issotopic analy ysis. A sum mmary of tthe analyticaal results foor the concrete cores is prresented in Table 2-16. Significannt HTD raddionuclides iidentified byy the analysis of the concrete core saamples inclu ude Ni-63, H H-3 and Sr-990. The othher radionucclides positivelyy detected att concentratiions greater than their reespective MD DC include; C-14, Fe-555, Ni-59, Tc-99 9, Pu-238, Pu-239/240, P Pu-241, Am m-241 and A Am-243. An analysis of the results oof the concrete core samplees is presenteed in Referen nce 16.

2.3.6.2. Turbin ne Building Tunnel A concreete core wass obtained ass part of thee 2014 charaacterization survey from m the floor oof the Turbine Building Tunnel T to attempt to evaluate the possiblle extent oof a radioaactive contamin nation event cited in the HSA pertain ning to the ddiscovery off cracked draain system ppiping in the Turbine T Buillding and thet potentiall radiologiccal contaminnation of suurrounding soils.

Analysis of this sam mple indicateed detectablee concentrattions of Cs-1137 at 0.3522 pCi/g, Co--60 at 0.106 pCCi/g and H-3 at 1.71 pCi//g.

2.3.6.3. LACB BWR Admin nistration Buuilding As stated d previously y, the LACB BWR Admin nistration Buuilding and G-3 Crib H House will nnot be subjectedd to FRS. In nstead, thesee two structuures will be surveyed foor unrestricteed release ussing a graded su urvey approaach in accord dance with MARSAME M E guidance.

As reporrted in the HSA, H there was w no past history of thhe use of unnsealed radiooactive mateerials, radioactiv ve spills or radioactive contaminatiion in the LA ACBWR Administratioon Building. The building has primarilly been used d for office sp pace and reccords storagee. An enviroonmental labb was located ini the build ding that sup pported both h LACBWR R and G-3 operations. The LACB BWR Administtration Build ding was in nitially classsified as a M MARSSIM Class 2 struucture due tto its proximity y to the LSE E, occupancy y by LACBW WR personnnel and the presence of thhe environm mental laboratorry.

Characterization surv veys of the LACBWR Administrattion Buildinng included a scan for gross beta-gammma/alpha activity of in nterior floorrs surfaces aand the rooff. Direct m measurementts for gross betta-gamma/allpha activity were also performed p onn the roof, onn floor tiles and around floor 2-31

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 drain opeenings. A sm mear samplee for removaable contam mination was also taken at the location of each direect measurem ment.

The resu ults of the beta scans of the intterior surfacces ranged from 1,4200 dpm/100cm m2 to 4,915 dpm m/100cm2 with w a scan MDCM 00 dpm/100ccm2. Duringg the scan off the north eend of of 2,10 the secon nd floor haallway, a discrete radio oactive partiicle was disscovered. T The particlee was imbedded d in a floor tile. The contaminated c d portion off the tile waas removed and analyzeed by gamma spectroscopy s y. The analy ysis of the tiile identifiedd 0.005 uCi of Cs-137. An investiggation was then n performed involving th he acquisition of ten (10)) biased direect measurem ments on thee first and seco ond floor lam minated woo od, carpet, and a floor tille. Direct bbeta-gamma readings raanged from lesss than MDC of 329 dpm m/100cm2 to a maximum m observed reeading of 5,,743 dpm/1000cm2 and direct alpha readings rang ged from leess than MD DC of 39 ddpm/100cm2 to a maxiimum 2

observed d reading of 72 7 dpm/100ccm .

Beta sccans of th he roof areea indicateed results ranging frrom 1,872 dpm/100cm m2 to 2,261 dpm m/100cm2 with w a scan MDC M of 2,2661 dpm/100ccm2. Directt alpha meassurements raanged 2

from lesss than MDC C of 113 dpmm/100cm to o a maximum m observed reading of 1152 dpm/1000cm2.

Direct beeta-gamma measurement m ts taken on the t floor draain openingss ranged from m less than M MDC 2

of 243 dpm/100cm d to a maxim mum observ ved readingg of 333 dppm/100cm2 aand direct alpha measurem ments were all less than n MDC of 42 4 dpm/100ccm2. No reemovable coontaminationn was identifiedd concentratiions greater than MDC by b the analy sis of the sm mear sampless.

2.3.7. Surface and Groundwatter Section 8.5 8 in Chap pter 8 of this LTP contains a ssummary ddescription of the geoology, hydrogeo ology and hy ydrology of ZNPS and environs.

e T The informattion containeed in this seection was deriived directly y from Haley & Aldriich, Hydroggeological C Conceptual SSite Model (17).

Haley & Aldrich, Hyydrogeologiccal Investiga ation Reportt for the LaCCrosse Boilinng Water Reeactor (18) suppplements thee preliminary y findings in n Reference 117.

2.3.7.1. Area Grou undwater Usse For a distance of 40 0 miles dowwnstream of the site, virrtually all m municipal wwater suppliees for towns an nd cities alon ng the Mississsippi River are obtainedd from groun und water. TThe nearest uuse of river watter for indusstrial purposses, excludin ng the adjaccent G-3 plaant, is the cooal-fired plaant in Lansing, Iowa, aboutt 15 miles downstream d of o the site. There are nno other know wn users off river water fo or industriaal purposes between the t LACBW WR site annd Prairie du Chien, WI, approxim mately 40 miles downstreeam.

The LAC CBWR site has its own potable waater supply, pprovided thrrough a singgle ground w water well at th he site. Saniitary wastes are collected in a solidss holding tannk and pumpped off by a local state permmitted sanittary wastes hauler.

h Thiis includes a sanitary hoolding tank that servicees the LACBW WR Administration Buillding and a sanitary hholding tankk that serviices the Tuurbine Building. Storm waater runoff iss diverted diirectly to thhe Mississipppi River at ooutfalls. Reelease areas aree periodicallyy monitoredd for oil sheeen and discooloration. R Roof drains ddischarge dirrectly to the grround area su urrounding the t facility viav downspoouts or enter the normaal effluent reelease pathway after passing g through ann oil separato or located innside the LSEE.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 2.3.7.2. Groundwater Flow Regionallly, groundw water flows in i a westerlly direction from the blluffs on the east towardds the Mississipppi river. Closer C to th he shore, grroundwater may also hhave a flow componentt that parallels the river. Under U typical river stagge, groundw water gradiennts near the river are sliightly upward; however, th he vertical grradient reverrses during fflood stages.. The geologgical and hisstoric river stag ge data comp pared to water table eleevations meaasure in LAC CBWR site monitoring wells demonstrrates that thee shallow aq quifer is in diirect hydrauulic communnication withh the river annd the river stag ge impacts thhe water tablle elevation.

Groundw water beneath h the site is first encoun ntered at ann average deepth of 20 feeet below grround surface (bgs) and thee groundwatter is in direect hydraulicc communicaation with thhe adjacent river.

Groundw water in the shallow s depo osits and filll material floows towardss the west annd dischargess into the Missiissippi River. The deep per groundw water is also likely to floow towards tthe west butt then may turn n and flow parallel to the river. Because thhe potentiall releases off radiologiccal or chemicall constituents would occu ur at or nearr the surface , the releases would likeely be confinned to the shalloow system.

Based on n a review off the ground dwater elevattion measureements colleected during routine sam mpling of the G--3 Ash Land dfill area grou undwater mo onitoring weells (# B2/B33/B9A/B9/B B7/B8), whicch are located ini the soutth side of the t LACBW WR site, annd associateed backgrouund groundw water monitorin ng wells (B111AR/B11R) to the east of and up grradient of LA ACBWR, thhere appears to be a slightly y downward vertical graadient. Durin ng times of nnormal and low river staage, groundw water has a do ownward grradient at well w pairs B11R/B11AR B R and B2/B B3, with an upward veertical gradient at well pair B9/B9A. This T is expeccted as grouundwater floows generallyy from the bbluffs towards the t river bassin with a lo ocalized influuence at B9//B9A from tthe adjacentt inlet. How wever, there aree some perio ods where the t gradientss are reverssed; and thiss is likely ddue to high river stages. Groundwater G r flow throuugh the LAC CBWR site iss impacted bby deeper sttructures (i.ee., the Reactor Building B basement shell) as well ass the deep ppilings that ssupport the structures, w which are beloww the water table t during high and low w river stagee conditions..

During plant p construuction, and more m specifiically the insstallation off the supportt pilings, thee soil was com mpacted, redu ucing the efffective porossity and perm meability off the soils. TThis reductiion in permeabiility can deccrease the hydraulic h connductivity oof the aquifeer within thee footprint oof the buildingss. The resullting impact to groundw water flow iss that grounddwater withiin the comppacted soils willl flow at a slower s veloccity, and reggionally, a siignificant peercentage off the flow reegime will circcumnavigate the area, effectively e bypassing b these soils. The impliications of these th localizedd flow regimmes on contam minant fate and a transporrt are that pootential releaases that occcurred outside thhe footprint of these strructures willl likely be ddeflected andd flow arounnd them. O On the other hannd, potentiall releases thaat occurred within w the foootprint of thhe buildingss, via floor ddrains or buriedd piling, willl likely take much longeer to migratee both in the vadose zoone as well aas the underlyinng groundw water. This is further compounded c d as the oveerlying strucctures isolatte the shallow soils s from precipitation, p , creating ann area that w will likely reetain any potentially releeased contamin nation. The average shaallow aquiferr hydraulic cconductivityy is 313 feet per day. Foor the soils withhin the suppport pilings, the hydraulic conductivvity would bbe expected to be one too two orders off magnitude lower.

2-33

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The velo ocity of gro oundwater iss directly related to booth the hyddraulic condductivity andd the gradient. The gradieent of the waater table is influenced byy the topogrraphy; and, w with the flat areas across thhe site, grounndwater mon nitoring has shown that the water taable has a very low graddient.

Therefore, it is likelyy that the grooundwater velocity v acrooss the site iss also relativvely slow (i..e., in the inch hes and feeet/day range). Groundwater elevaation data from the G-3 Coal Plant Environm mental Moniitoring Prog gram wells agree a with tthe regional groundwateer flow, andd also show seaasonal variaation on upw ward and do ownward graadients that are influennced by the river stage. Th a not sufficcient to charracterize the groundwateer flow below hese wells are w and arounnd the LACBW WR site structtures or areaas where poteential releases associatedd with LACBWR (i.e., iin the vicinity of suspect broken draain lines) co ould have ooccurred. Inn these areaas, pilings, deep structures/foundation ns or variatiions in fill materials m coould locally influence ggroundwater flow directionns.

2.3.7.3. Previous Investigation I ns Historicaally, the LAC CBWR Liceensed Site haas had severral potable w water wells and groundw water monitorin ng wells. Figure 2-11 illustrates thee current loccation of pootable water and groundw water monitorin ng wells loccated on the LACBWR R site. Theere is no pootable waterr or groundw water monitorin ng wells offf the LACB BWR site that t are or have been monitored by Solutionns or Dairyland for radiolo ogical purposes.

Of the wells w shown n on Figure 2-11, only Potable P Waater Wells N Nos. 3 and 4 which servviced LACBW WR facilities were historrically monittored by Daairyland for radiologicall conditions on a routine basis.

b The grroundwater monitoring m wells w and baackground grroundwater monitoring wells designateed as B-2, B-3, B-7, B-8, B-9, B-9A, B11A AR, and B B11R are m monitored byy the Environm mental Moniitoring staff on a routinee basis for noon-radiologiical parameteers to suppoort the G-3 Fosssil Station op perational reequirements. During LA ACBWR opeerations, Potaable Water W Wells Nos. 3, 4 and 5 werre routinely monitored for f gross beeta activity. Typical grross beta acctivity levels reported durin ng this mon nitoring periiod was lesss than or eqqual to MD DC (ranging from 3.0E-08 µCi/ml

µ to 9.0E-08 µCi/m ml).

During th he recovery of a probable spill incid dent in 1983 , a temporarry well-poinnt was establlished to the south of thee Turbine Building.

B This T incidennt concerneed the poteential leakagge of radioactivve liquids frrom suspect broken drain n lines in th e Turbine BBuilding to suub-building soils.

The welll-point show wn on Figure 2-11 was esstablished doown gradiennt and below w the grade oof the suspected d leakage. The T well-point was sam mpled once oon May 3, 19983. The annalysis results for that samp ple are preseented in Tablle 2-17. Thiis well-pointt has since beeen abandonned.

As noted in the LACBWR L Decommissio D oning Plan and Post-SShutdown D Decommissiooning Activitiess Report (DD-Plan/PSDA AR) (19), Dairyland reccently installled groundw water monittoring wells to support gro oundwater evaluation.

e In Novembber 2012, fiive (5) pairss of groundw water monitorin ng wells (10 0 wells total)) were installled within tthe LACBW WR licensed site to deterrmine if ground dwater quality had beeen impacted by plant ooperations. The well ppairs which were located nominally n wiithin five (5)) feet of onee another connsist of one shallow welll with a screeened interval of o 15 to 25 feet f below grade g and onne deep well with a screeened intervaal of 45 to 555 feet below grrade. These wells are sh how on Figu ure 2-11 as M MW 200A annd B through MW-204A A and B.

2-34

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Two (2) rounds of grroundwater samples werre collected in 2013, duuring the seaasonal high w water in June 2013 and th hen during a seasonal low l groundw water level in Novembber 2013. T These groundw water sampless were sent to an off-sitte laboratoryy for radioloogical analyssis for Co-600, Sr-90 and Cs-137.

C Analy ysis for H-3 was perform med on site.

In June ofo 2014, a third t round of o groundwaater sampless was colleccted from: M MW-200A aand B through 204 2 A and B; B Potable Water W Wells #3,

1. 4, 5, and 7; and Monnitoring Wellls B2, B-3, B B11R and B11AR. Thesee collected groundwater g samples were sent offf for radioloogical analyssis of several radionuclide r s including HTD and transuranic t rradionuclidees. In Septeember of 20014 a fourth ro ound of gro oundwater were w collecteed from: M MW 200A annd B througgh 204A annd B, Potable Well #5, an nd Monitoriing Wells B11R B and B B11AR. T These colleccted groundw water samples were sent off o for radio ological anaalysis of sevveral radionnuclides inclluding HTD D and transurannic radionucllides. Tablees 2-18 and 2-192 providees a summarry of the radiiological anaalysis of the grooundwater saamples and results.

r Addition nal details, in ncluding thee off-site anaalytical laborratory reporrts are provided in Referrence 18.

2.3.7.4. On-Going g Investigatioons The LAC CBWR Site groundwater g r monitoring g program coonsists of obbtaining grouundwater sam mples twice peer year for radiological r analysis puurposes onlyy from existing monitooring wells w when groundw water is at rellatively high her and loweer elevations . The monitoring wellss sampled include the MW--200A/B thru u MW-204A A/B wells as shown on Figure 2-11.

The colleected informmation during g each monittoring intervval includes:

Depth D to grouund water in the respectiive monitorinng well.

Monitoring M well w groundw water pH/speecific conducctance/oxidaation and redduction potential/turb bidity/dissolvved oxygen/ttemperature..

Radiological R sample inforrmation inclluding a com mpleted chainn of custodyy following grroundwater sample colleection.

2.3.7.5. Summ mary of Grou undwater An nalytical Ressults Groundw water charactterization eff fforts commeenced througgh the installlation of 10 monitoring wells (5 pairs) within the LSE area in Novemb ber 2012 annd the com mmencement of groundw water sampling g in 2013. H-3 H was positively detectted at concenntration greaater than MD DC in monittoring wells MW W-201A and d B, MW-20 02-A and B, MW-203A and B and M MW-204A aand B in June and Novembeer of 2013 at concentraations rangiing from 1550 pCi/L to 660 pCi/L. Sr-90 wass also positively y detected in i the same wells durin ng the June 2013 samplling period aat concentraations ranging from 1.43 pCi/Lp to 2.1 18 pCi/L; ho owever, it w was not poositively deteected duringg the Novembeer 2013 sam mpling period d. Co-60 an nd Cs-137 w were not positively deteected in anyy well during thhe 2013 samp pling period.

During th he June 2014 sample peeriod, H-3 was w positivelyy detected inn four (4) w wells (MW-B B11R, MW-202 2A, MW-203 3A and MW W-203B) at concentrationns ranging fr from 245 pCi/L to 336 ppCi/L.

Sr-90 was w also positively detected in wells w MW-2002A, MW-2203A and MW-204A with 2-35

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 concentraations rangin ng from 1.1 12 pCi/L to 2.01 pCi/L. C-14, Tc-999, Eu-152, Pu-239/2400 and Am-241 were also po ositively detected at residual concenntrations in seeveral wells.

During the Septemb ber 2014 sam mple period,, H-3 was nnot positivelly detected aat concentraations greater th han MDC in n any well. Sr-90 was positively ddetected in oone (1) welll, MW-200A A at a concentraation of 1.14 4 pCi/L. Co o-60, Ni-63,, Cs-137, Euu-152, Eu-1554, Pu-239/2240 and Am m-241 were also o positively detected d at residual r conccentrations inn several weells.

2.4. Continuing C Characteriz C zation The surv vey of many inaccessiblee or not read dily accessibble subsurfaace soils or ssurfaces has been deferred. Exampless of areas where w survey ys are deferrrred include soils underr structures, soils under concrete or asp phalt coverinngs, structurral wall and floor surfacces in some of the basem ments that will remain and d be subjeccted to FRS, the underl rlying concrrete in the R Reactor Buiilding basementt after linerr removal an nd the interriors of burried pipe thaat may rem main. Figuree 2-3 illustrates buried pip ping systemss that may remain r in thhe end-state condition. The decision to defer thee characterizzation of a soil or stru ucture was bbased on onne or more of the folloowing condition ns:

ALARA consideratio ons (e.g., thee area is eithher a radiatiion or contaamination areea and addittional data wou uld likely nott change thee survey areaa or area classsification oof the locatioon or surrounnding areas),

Safetty considerattions, Histo orical data sh hows that thee area could be classifiedd without furrther charactterization, Access for characcterization would w requiree significantt deconstructtion of adjaccent systemss, structtures or otheer obstacles where w the reemoval couldd result in ann unsafe conndition or interffere with conntinued operration of opeerating system ms, or The ability a to usee engineeringg judgment in i assigning the area a cllassificationn based on physiical relationsship to surro ounding areas and the likkelihood of thhe area to haave radiologgical condiitions repressented by thee conditions in these adjaacent areas.

As accesss is gained to areas thaat were prev viously inacccessible, addditional charracterizationn data will be co ollected, evaaluated and stored s with-o other radioloogical surveyy data in a survey historry file for the survey s unit. This data will be useed along wiith existing data to upddate the typpes of radionuclides presentt and updatee the variabillity in the raadionuclide m mix for bothh gamma-em mitting and HTD D radionuclid des. In addiition, as the decommiss ioning progrresses, data from operattional events caaused by equ uipment failuures or perso onnel errors,, which mayy affect the raadiological sstatus of a surv vey unit(s) will w be reco orded. Thesse events w will be evaluuated and, w when approppriate, stored inn the characterization database. Th his additionaal characterrization dataa will be used in validating the initial classification and in plan nning for thee FRS.

As decom mmissioning g proceeds, areas will, as necessarry, be deconntaminated to remove loose surface decontamina d ation (as welll as fixed co ontaminationn) to levels that will meeet the condiitions for open n air demolittion or unreestricted releease. Whenn a structure is ready ffor demolitiion, a documen nted survey anda a formall turnover willw be made by the Radiological Prootection grouup for 2-36

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 the comp pany preform ming demoliition, validatting that thee radiologicaal conditions in the struucture are suitabble.

Followin ng the demollition and/orr remediation n, and whenn an area is bbelieved to bbe ready for FRS, a "turnov ver assessmeent" will be performed.

p If I the resultss of this asseessment indiicate that thee FRS acceptance criteria will w be met,, then physiical and adm ministrative control of the area wiill be transferreed to Characcterization/LLicense Term mination grouup personnel for preparaation, designn, and performaance of the FRS.

F Otherwwise, additioonal remediaation may bbe required. This assesssment may inclu ude a "turnoover survey,"" primarily for fo Class 1 annd 2 areas w within the LSSE.

The "turn nover surveey" process, together wiith any addiitional charaacterization and remediiation survey peerformed, reepresent at leeast one, butt possibly seeveral, oppoortunities to ccollect addittional survey daata prior to conducting c the t FRS. Fo or each type of survey (ccharacterizattion, remediaation, turnover,, and FRS), a documenteed survey plan will be ddeveloped using the DQO O process. T These survey plans will co ontain the ap ppropriate daata assessmeent to ensurre that severral objectivees are met. Theese objectivees include:

Apprropriate instrrument selecction to ensurre the properr sensitivity relative to thhe applicablle action n level and/oor release criiteria, Apprropriate instrrument qualiity control measures m to eensure operabbility, Apprropriate survey techniquees to ensure that the fieldd measurement techniquues are consiistent with the calibration methodollogies, Apprropriate samp ple collection and analyssis to determ mine spatial vvariability annd variabilityy in radionuclide ratioos, Data analysis critteria to identtify follow-u up actions suuch as remeddiation and thhe collectionn of additional samplees and, Apprropriate classsification of the survey area.

a 2.5. References R

1. U.S.

U Nuclear Regulatory Commission n, Regulatorry Guide 1.179, Standardd Format andd Content C of Liicense Termiination Plans for Nucleaar Power Reaactors, Revission 1 - Junee 2011.

2. U.S.

U Nuclear Regulatory Commission n, NUREG-11575, Revisiion 1, Multi--Agency Radiation R Surrvey and Sitee Investigatiion Manual ((MARSSIM M), August 20000.

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. EnergySoluti E ons PG-EO--313196-SV-PL-001, Chharacterizatioon Survey P Plan for the L La Crosse C Boilin ng Water Reaactor.

5. EnergySoluti E ons GP-EO--313196-QA A-PL-001, Quuality Assurrance Projectt Plan LACB BWR Site Characteerization Projject (QAPP)).

2-37

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

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

7. Dairyland D Power Corporaation LAC-T TR-138, Initiial Site Charracterizationn Survey for SAFSTOR - December 2009. 2

8. 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 20 006.

9. Sandia Nation nal Laborato ory, NUREG G/CR-5512, V Volume 3, R Residual Raddioactive Contaminatio C on From Deccommissioniing Parameteer Analysis - October 19999.

10. EnergySoluti E ons Techniccal Support Document D R RS-TD-3131996-006, Luddlum Model 444-10 Detector Sensitivity.

S

11. U.S.

U Nuclear Regulatory Commission n, NUREG-11576, Multi--Agency Raddiological Laboratory L Analytical A Prootocols Man nual (MARL LAP) - Auguust 2001.

12. U.S.

U Nuclear Regulatory Commission n Regulatoryy Guide 4.155, Quality Assurance or Radiological R Monitoring Programs (IInception Thhrough Norm mal Operations to Licensse Termination)

T - Effluent Streams S and the Environnment - July 2007.

13. EnergySoluti E ons GG-EO--313196-RS S-RP-001, LA ACBWR Raadiological C Characterizattion Survey Reporrt for Octobeer and Novem mber 2014 F Field Work - Novemberr 2015.

14. EnergySoluti E ons LC-RS-PN-164017--001, LACB BWR Radioloogical Charaacterization Survey Reporrt for June th hru August 2015 2 Field W Work - Noveember 2015.

15. ZionSolution Z s Technical Support Doccument 13-0004, Examinnation of Cs-137 Global Fallout in Soiils at Zion Sttation.

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

17. Haley H & Aldrrich, Hydrog geological Conceptual Siite Model, FFile No. 387005-001 - Auugust 30, 2012.

18. Haley H & Aldrrich Inc., Hy ydrogeologiccal Investigaation Report,, La Crosse BBoiling Watter Reactor, R Dairryland Power Cooperativ ve, Genoa W Wisconsin, Fiile No. 387005-008, January 2015.

19. Dairyland D Power Cooperaative, LACB BWR Decom mmissioning Plan and Poost Shutdownn Decommissio D oning Activitties Report (D-Plan/PSD

( DAR), Revission - Marchh 2014.

20. In nternational Standard ISO 7503-1, Part P 1, Evaluaation of Surfface Contam mination, Betta-Emitters E (maxximum beta energy greaater than 0.155 MeV) and Alpha-Emittters - Auguust 1998.

2-38

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-1 LACBW WR Open L Land Surveyy Units Survey Surveyy Unit Descrription Initial Approxim mate Unit ID # Cllassification n Survey U Unit Area (mm2)

LAACBWR Sitte Enclosuree Grounds Reactorr Building, WTB, W WGTV V, Ventilatioon L10101001 Class 1 1,9922 Stack Grounds G

Turbinee Building, Turbine T Office Building,, 1B L10101002 Class 1 2,3155 Diesel Generator G Buuilding Grouunds L10101003 LSA Bu uilding, Maintenance Eaat Shack Groounds Class 1 1,7499 L10101004 North LSE L Groundss Class 1 2,3877 LSE Bufffer Zone Groounds LACBW WR Adminisstration Buillding, LACB BWR L20111001 Class 2 7,2111 Crib Hoouse, Warehouse Ground ds G-3 Criib House, LAACBWR Cirrc. Water L20111002 Class 2 6,7855 Discharrge Line, Areea South of LSE L Fence Classs 3 Groundss L30121001 North End E of Licen nsed Site Class 3 24,042 L30121002 Transmmission Switcchyard Area Class 3 11,711 L30121009 Plant Access, A ISFSII Haul Road d Grounds Class 3 31,012 Non-Immpacted Grouunds L40121003 G-3 Coal Plant Gro ounds Noon-Impactedd 66,869 L40121005 Coal Pile Grounds Noon-Impactedd 82,894 L40121006 Cappedd Ash Impou undment Gro ounds Noon-Impactedd 111,8999 L40121007 Groundds East of Highway 35 Noon-Impactedd 81,254 L40121008 Hwy 35 5/Railroad Right R of Wayy Grounds Noon-Impactedd 9,4444 2-39

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-2 LACBW WR Structu ural Surveyy Units Surveey Unit Surrvey Area Description D Classsification B10110001 Reactor Bu uilding Cllass 1 B10110002 Waaste Treatmen nt Building Cllass 1 B10110003 LACCBWR Ventiilation Stackk Cllass 1 B10110004 Waste W Gas Taank Vault Cllass 1 LACBWR R Turbine Blddg./Turbine Office B10110005 Cllass 1 Bldg.

B10110006 LACBWR 1B Diesel Generator G Strructure Cllass 1 B10110007 LSA Buillding Cllass 1 B10110008 Maintenance M Eat E Shack Cllass 1 B10110009 Pipe Tunnnel Cllass 1 B20110101 LACBWR Crrib House Cllass 2 B20110102 G-3 Crib House H Cllass 2 B20110103 LACBW WR Administtration Buildding Cllass 2 B20110104 LAACBWR Warrehouse #1 Cllass 2 B20110105 LAACBWR Warrehouse #2 Cllass 2 B20110106 LAACBWR Warrehouse #3 Cllass 2 B30112101 Baack-up Contrrol Center Cllass 3 B30112102 Transmissiion Sub-Stattion Switch HHouse Cllass 3 B30112103 G-1 Crib House H Cllass 3 B30112104 Barg ge Washing Break B Roomm Cllass 3 2-40

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tablee 2-2 (continnued) LACBWR Structural Survey Uniits Non Imp pacted Strucctures G-3 Reclaim R Buillding G-3 Annnex Buildinng G-3 Stock S Out Trransfer Buildding G-3 Booiler Fuel Oiil Pump Building G-3 Coal C Unloading Tower G-3 Exxplosive Gass Storage Rooom G-3 Transfer T Tow wer A G-3 Gaas Room G-3 Electrical E Ro oom G-3 Suub Station Shhed G-3 Crusher C Towwer G-3 Suub Station Shhed G-3 Conveyor C #6 6 (2) G-3 Liime Storage Silo G-4 Warehouse W and a Electricaal Room G-3 W Weigh Stationn G-3 LRAPB L Buillding G-3 Acctive Reclaimm Buildingss/ Tunnel G-3 Lime L Silo Electrical Buillding G-3 Assh Coordinaators Office G-3 CAT C Buildinng G-3 Baag Houses (55)

G-3 Coal C Plant G-3 Fl ammable Sttorage Shed G-3 Vehicle V Storaage Building g #7 We ll House G-3 Train T Shed G-3 Cooal Scale G-3 Bottom B Ash Dewatering Buildings G-3 Saample Buildiing G-3 Fly F Ash Silo G-3 Sttock Out Traansfer Buildiing G-3 Fly F Ash Elecctrical Buildiing G-3 Grrid Shed G-3 Waste W Silo G-3 Assh handling Blower Buillding G-3 Surge S Tank Main PPollution Coontrol Electriical Buildingg G-3 Settling S Tankk S03 Taank Buildingg

1. 6 Well W House 2-41

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2-3 Instrumeent Types aand Nominaal MDCs Ty Typical Detection Sensittivity Deteector Modell b Meeter Model Applicaation MDCscan MDCsttatica (dp pm/100cm ) (dpm/100cm2) 2 Ludlumm 44-9 Ludllum 3 scaan 1,0000 to 2,0000 N/AA Ludlumm 43-68 mo ode Ludllum 2350-1 static & scan 1,8800 to 2,0000 600 to 700 Ludlumm 43-68 mo ode Ludllum 2350-1 stattic N/A 80 to 90 Ludlumm 43-93 mo ode 1,8800 to 2,0000 800 to 900 Ludllum 2360 static & scan Ludlumm 43-89 mo ode 2,0000 to 2,2000 800 to 900 Ludlumm 43-93 mo ode 90 to 1100 Ludllum 2360 stattic N/A Ludlumm 43-89 mo ode 90 to 1100 3.55 pCi/g 60Coo Ludlumm 44-10 Ludllum 2350-1 scaan N/AA 6.55 pCi/g 137Css Ludlumm 43-37 Ludllum 2350-1 scaan 2,0000 to 2,2000 N/AA and/ or -15 Ludlumm 43-10-1 Ludllum 2929 N/A smeaar -80

~0.10 ppCi/g Gammaa Spectroscop py N/A Anallysis N/A for Co-660 and System Cs-1337 a Based on 1-minutee count time; and a default valu ues for surface efficiencies (s) as specified in Internationaal ndard, ISO 750 Stan 03-1 (20).

b Fun nctional equivallent instrumenttation may be used u

2-42

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-4 Off-Sitee Laboratory y Analyticaal Methods aand Typicall MDCs Analysis / Analytes Technique Method and d Sensitivity Soils (pCi//g) Watter (pCi/L)

Gamma Gamma G Spec DOE EML E HASL 3000 EPA Method 901.1 Radionucliides < 0.1pC Ci/g 10.0 pCi/L Isotopic Neptunium Alpha A Spec DOE EML E HASL 3000 (Np-237) < 0.04 pCi/g p

Isotopic Pllutonium Alpha A Spec DOE EML E HASL 3000 EML Pu-02 M Modified (Pu-238/2339/240) < 0.05 pCi/g p 1.0 pCi/L Isotopic Thhorium Alpha A Spec DOE EML E HASL 3000 (Th-228/23 30/232) < 0.05 pCi/g p

Isotopic Urranium Alpha A Spec DOE EML E HASL 3000 (U-234/235 5/238) < 0.06 pCi/g p

Isotopic Cuurium Alpha A Spec DOE EML E HASL 3000 (Cm-243/2 244) < 0.03 pCi/g p

Isotopic Am mericium Alpha A Spec DOE EML E HASL 3000 (Am-241/2 243) < 0.04 pCi/g p

C-14 LS SC EPA EE ERF C-01 ENIC Modifiied

< 5.0 pC Ci/g 50.0 pCi/L Tritium LS SC EPA 90 06.0 EPA 906.0

< 10.0 pCi/g p 300.0 pCi/L Sr-90 GFPC G DOE EML E HASL 3000 EICHROM M Modified Methood

< 1.0 pC Ci/ 2.0 pCi/L Pu-241 LS SC DOE EML E HASL 3000 EML Pu-01

< 10.0 pCi/g p 50.0 pCi/L Tc-99 LS SC DOE EML E HASL 3000 EICHROM T Tc-01

< 2.0 pC Ci/g 15.0 pCi/L Gross Alph ha / Beta GFPC G EPA 900.0 5.0 pCi/L Fe-55 LS SC DOE EML E HASL 3000 EML Fe-01 M Modified

< 10.0 pCi/g p 100.0 pCi/L Ni-63 LS SC DOE EML E HASL 3000 (SRW01) EML Ni-01 M Modified

< 2.0 pC Ci/g 15.0 pCi/L Ni-59 LS SC DOE EML E HASL 3000 (SRW01) EML Ni-01 M Modified

< 50.0 pCi/g p 100.0 pCi/L 2-43

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Taable 2-5 2005 Dairyyland Backgground Stud dy for Soils Co-60 Cs--137 Location (pCi/g) (pCCi/g)

(on Licensed L Sitee)

Area West ofo #2 Warehhouse <MDC 0.0077 Area South of Parking Lot L <MDC 0.0026 Area North of LACBWR Admin Bu uilding <MDC 0.149 Area at G-3 Gas Silo <MDC 0.0038 Area Outsidde G-3 Offices <MDC 0.0076 Area at G-3 Outfall <MDC 0.0017 (off Licensed L Sitee) 33 miles South at Bad Axe A Boat Lan nding 0.023 0.3381 Pedretti Farm Substationn East of LAACBWR <MDC 0.2227 Radio Toweer Northeast of LACBW WR <MDC 0.0035 Junction of Hwy O and Hwy K <MDC 0.188 East of Stod ddard at Hwyy O Junction n <MDC 0.0065 2-44

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table T 2-6 Investiga ative Levels for Cs-137 Based on B Background d Studies Meassured Rangge R Range for 955% Distribu ution Conditioon and Deptth (pCi/g) (p pCi/g)

Drainage D Areas Surfacee 0-10 cm Undisturbbed 0.00 to 2.80 0.455 to 3.63 Disturbedd 0.00 to 1.67 0.355 to 2.86 Nonn-Drainage Areas Surfaace 0-10 cm m

Undisturbbed 0.23 to 0.66 0.155 to 0.77 Disturbedd 0.27 to 0.34 0.23 to 0.42 2-45

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-7 Initia al Suite of LACBWR L SSite-Specificc Radionucllides Radio onuclide Haalf Life (Yeaars)

H-3 H 1.24E+01 C-14 C 5.73E+03 Fee-55 2.70E+00 Ni-59 7.50E+04 Co o-60 5.27E+00 Ni-63 9.60E+01 Srr-90 2.91E+01 Nb b-94 2.03E+04 Tcc-99 2.13E+05 Cs-137 3.00E+01 Eu u-152 1.33E+01 Eu u-154 8.80E+00 Eu u-155 4.76E+00 Np p-237 2.14E+06 Puu-238 8.78E+01 Puu-239 2.41E+04 Puu-240 6.60E+03 Puu-241 1.44E+01 Am m-241 4.32E+02 Cm-24 43/244* 1.81E+01

• L Listed half life is i the shortest half h life for thee radionuclidess in the pair 2-46

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-8 Non-Impacted Open Land Survey Units - Characterizattion Survey Su ummary S

Survey Unit Survey Unitt L4012103 Survey Unit L4012105 Survey Unit L L4012106 Survey Unit L L4012107 2 2 2 Surface Area 66,869 m 82,894 m 111,899 m 1 881,254m2 C

Capped Ash Immpoundment G Grounds East off Description G-3 Coal Plannt Grounds Coal Pile Grounds G

Grounds H Highway 35 S

Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 3 3 3 3 3 3

1. >CL 0 1 0 1 0 2 0 3 M

Mean (pCi/g) 0.070 0.082 0.071 0.061 0.082 0.100 0.080 0.264 M

Median (pCi/g) 0.075 0.083 0.072 0.060 0.084 0.099 0.079 0.263 M

Max (pCi/g) 0.078 0.092 0.084 0.068 0.090 0.121 0.089 0.463 M

Min (pCi/g) 0.057 0.071 0.057 0.055 0.072 0.079 0.072 0.065 S

SD 0.011 0.011 0.014 0.006 0.009 0.021 0.009 0.199 S

Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 4 4 3 3 4 4 3 3

1. >CL 0 1 0 1 0 2 0 2 M

Mean (pCi/g) 0.060 0.048 0.061 0.042 0.081 0.088 0.081 0.068 M

Median (pCi/g) 0.056 0.038 0.063 0.040 0.083 0.084 0.069 0.057 M

Max (pCi/g) 0.084 0.081 0.068 0.056 0.102 0.130 0.106 0.091 M

Min (pCi/g) 0.047 0.036 0.052 0.030 0.056 0.054 0.068 0.056 S

SD 0.016 0.022 0.008 0.013 0.021 0.037 0.022 0.020 A

Asphalt Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 2 2

1. >CL 0 0 M

Mean (pCi/g) 0.073 0.062 M

Median (pCi/g) None Taken None Taken 0.073 0.062 None Takken M

Max (pCi/g) 0.082 0.084 M

Min (pCi/g) 0.065 0.040 S

SD 0.012 0.031 Surface Scans

% Scanned 1% 1% 1%

1 1%

M Mean Scan (cpm) 5,550 5,050 8 8,340 8,000 M

Max Scan (cpm) 6,700 8,800 1 12,000 9,080 2-47

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Tablle 2-8 (continueed) Non-IImpacted Open n Land Survey Units - Charaacterization Surrvey Summaryy Survey Unit Survey Unit L4012108 Survey Unit LL4012109 Surface Area 9,444 m2 1 m2 100 Hwy 35/Railroad Right of Background B Soiils Test Description Way Grounds Area (inside L40012108)

A Surface Soil Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 17 17

1. >CL 0 2 0 17 Mean M (pCi/g) 0.079 0.119 0.087 0.160 Median M (pCi/g) 0.075 0.108 0.086 0.161 Max M (pCi/g) 0.095 0.156 0.101 0.268 Min M (pCi/g) 0.068 0.093 0.077 0.059 SDD 0.014 0.033 0.007 0.059 Subsurface Soil Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3

1. >CL 0 2 Mean M (pCi/g) 0.086 0.189 Median M (pCi/g) 0.092 0.091 None Taaken Max M (pCi/g) 0.107 0.409 Min M (pCi/g) 0.060 0.067 SDD 0.024 0.191 Asphalt A Co-60 Cs-137 Co-60 Cs-137

1. of Samples

1. >CL Mean M (pCi/g)

Median M (pCi/g) None Taken None Taaken Max M (pCi/g)

Min M (pCi/g)

SDD Surface Scans

% Scanned 1%

Mean M Scan (cpm) 8,124 No Scanning PPerformed Max M Scan (cpm) 9,200 2-48

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 2-9 Non Impa acted Coal Pile and Soil Samp ples - Test Ameerica Laboratorry Analysis (pC Ci/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 N Ni-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L3012103-QJ-GS-001-S SB 4.390 1.230 3.430 1 .470 0.026 2.140 0.321 0 0.018 0.820 0.024 0 0.714 0 0.071 0.190 00.095 0.025 0.046 0 0.015 11.730 0.032 0.022 0 0.010 L

L3012103-QJ-GS-001-S SS 3.570 0..671 2.790 1 .870 0.027 3.380 0.391 0 0.022 0.628 0.018 0 0.847 0 0.060 0.167 00.096 0.024 0.040 0 0.021 11.650 0.025 0.024 0 0.019 L

L3012105-Genoa Coal Pile P 0.018 0 0.022 0.019 0 0 0.052 0.152 00.048 0.041 L

L3012105-CR-GS-002- -SS 0.533 0..675 2.130 1 .730 0.025 2.950 0.289 0 0.016 0.587 0.018 0 0.698 0 0.051 0.137 00.056 0.023 0.036 0 0.029 11.670 0.018 0.025 0 0.006 L

L3012105-QJ-GS-001-S SB 0.026 0 0.020 0.023 0 0 0.049 0.166 00.055 0.048 L

L3012105-QJ-GS-001-S SS 0.030 0 0.020 0.028 0 0 0.072 0.199 00.074 0.061 L

L3012106-QJ-GS-001-S SB 14.600 0..713 2.300 2 .370 0.037 3.950 0.348 0 0.030 0.611 0.319 1.500 0 0.115 0.223 00.080 0.035 0.036 0 0.014 22.550 0.019 0.034 0 0.006 L

L3012106-QJ-GS-001-S SS 0.813 0..713 3.550 2 .560 0.037 3.580 0.338 0 0.028 0.616 0.096 0.826 0 0.079 0.232 00.112 0.027 0.044 0 0.026 22.740 0.025 0.013 0 0.019 L

L3012107-QJ-GS-001-S SB 0.019 0 0.013 0.021 0 0 0.045 0.115 00.038 0.034 L

L3012107-QJ-GS-001-S SS 1.420 0..719 3.610 2 .800 0.025 3.940 0.293 0 0.019 0.593 0.018 1.450 0 0.049 0.156 00.048 0.040 0.021 0 0.024 22.580 0.020 0.035 0 0.006 L

L3012108-QJ-GS-001-S SB 2.350 0..705 1.920 3 .110 0.018 4.440 0.278 0 0.016 0.604 0.033 1.310 0 0.041 0.128 00.044 0.030 0.026 0 0.021 22.670 0.017 0.036 0 0.017 L

L3012108-QJ-GS-001-S SS 6.490 0..728 2.260 3 .200 0.030 4.710 0.271 0 0.020 0.576 0.182 0.770 0 0.059 0.176 00.060 0.020 0.028 0 0.029 22.740 0.015 0.024 0 0.015 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value b Survey units originally classified as Class 3 at time of sampple 2-49

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-10 Impacted Cla ass 1 Open Land d Survey Unitss - Characterizzation Survey SSummary S

Survey Unit Survey Unitt L1010101 Survey Unit L1010102 Survey Unit L L1010103 Survey Unit L L1010104 2 2 2 Surface Area 1,992 m 2,315 m 1,749 m 1 22,387 m2 Reactor Buillding, WTB, Turbine, Officee, Diesel L LSA Building, Description WGTV, Venttilation Stack Generator Building M Maintenance Eaat Shack NNorth LSE Grouunds Grounds Grounds G Grounds S

Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 12 12 2 2 7 7 1 1

1. >CL 2 12 0 0 0 1 0 0 M

Mean (pCi/g) 0.080 0.215 0.049 0.050 0.059 0.069 0.045 0.049 M

Median (pCi/g) 0.058 0.100 0.049 0.050 0.050 0.054 0.045 0.049 M

Max (pCi/g) 0.287 1.070 0.054 0.051 0.099 0.161 0.045 0.049 M

Min (pCi/g) 0.048 0.032 0.044 0.050 0.048 0.048 0.045 0.049 S

SD 0.066 0.296 0.007 0.001 0.019 0.041 N/A N/A S

Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 18 18 22 22 25 25 14 14

1. >CL 0 8 0 4 0 0 0 3 M

Mean (pCi/g) 0.078 0.066 0.058 0.064 0.046 0.049 0.048 0.041 M

Median (pCi/g) 0.052 0.054 0.058 0.065 0.046 0.049 0.048 0.042 M

Max (pCi/g) 0.516 0.161 0.080 0.130 0.055 0.054 0.050 0.051 M

Min (pCi/g) 0.047 0.033 0.043 0.044 0.025 0.042 0.043 0.027 S

SD 0.109 0.035 0.010 0.017 0.005 0.003 0.002 0.009 A

Asphalt Co-60 Cs-137

1. of Samples 10 10

1. >CL 0 1 M

Mean (pCi/g) 0.053 0.051 M

Median (pCi/g) None Taken None Taken N None Taken 0.054 0.053 M

Max (pCi/g) 0.062 0.057 M

Min (pCi/g) 0.042 0.037 S

SD 0.006 0.006 S

Surface Scans

% Scanned M

Mean Scan (cpm) No Scanning Performed P No Scanning Performed N Scanning Peerformed No No Scanning Peerformed M

Max Scan (cpm) a MDC vaalue used for anaalytical results less l than MDC.

2-50

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 T

Table 2-11 Class 1 Concretee, Asphalt, Sed diment and Soill Samples - Tesst America Lab boratory Analyysis (pCi/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 NNi-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L1010101-CJ-GS-002-SSS 0.024 0 0.020 0.233 0 0.056 0.161 00.066 0.058 L

L1010101-CJ-GS-009-SSS 0.040 0 0.020 0.185 0 0.056 0.181 00.050 0.042 L

L1010101-CJ-GS-010-SSS 0.286 0 0.025 0.413 0 0.062 0.247 00.057 0.051 L

L1010101-QJ-GS-001-SSB 0.364 0.896 2.430 1 .850 0.024 3.040 0.335 0 0.015 0.579 0.020 0 0.800 0 0.050 0.143 00.044 0.019 0.046 0 0.023 11.970 0.015 0.023 0 0.021 L

L1010101-QJ-GS-001-SSS 0.441 0..676 2.190 1 .900 0.018 3.040 0.440 0 0.012 0.587 0.147 3.170 0 0.034 0.112 00.044 0.006 0.039 0 0.023 11.830 0.016 0.021 0 0.019 L

L1010101-QJ-GS-002-SSB 0.377 0..679 2.150 1 .750 0.017 2.930 0.338 0 0.011 0.620 0.149 0.772 0 0.040 0.109 00.040 0.019 0.041 0 0.022 11.950 0.017 0.029 0 0.014 L

L1010101-QJ-GS-002-SSS 1.380 0..677 4.190 2 .010 0.015 3.320 0.357 0 0.010 0.521 0.059 0.978 0 0.033 0.096 00.036 0.016 0.040 0 0.016 22.090 0.020 0.017 0 0.022 L

L1010102-CJ-FC-001-CCV 1.710 0..727 1.650 2 .630 0.106 3.920 0.292 0 0.022 0.536 0.352 1.290 0 0.061 0.239 00.062 0.029 0.041 0 0.028 22.490 0.018 0.019 0 0.021 L

L1010102-CJ-GS-013-SSB 0.030 0 0.016 0.021 0 0 0.044 0.170 00.041 0.036 L

L1010102-QJ-GS-001-SSB 8.740 0..726 2.120 2 .620 0.015 4.000 0.310 0 0.011 0.539 0.012 0 0.961 0 0.030 0.101 00.028 0.028 0.040 0 0.026 22.780 0.015 0.020 0 0.021 L

L1010102-QJ-GS-001-SSS 0.022 0 0.015 0.018 0 0 0.036 0.113 00.042 0.039 L

L1010102-QJ-GS-002-SSB 24.700 0..715 2.230 2 .760 0.021 3.920 0.316 0 0.014 0.537 0.016 0 0.722 0 0.043 0.139 00.042 0.032 0.042 0 0.029 22.660 0.015 0.021 0 0.018 L

L1010103-CJ-GS-002-SSB 0.011 0 0.017 0.021 0 0 0.044 0.181 00.046 0.044 L

L1010103-QJ-SL-001-SSM 0.354 0.453 0.689 00.711 0.136 1.090 0.132 0 0.018 0.432 0.136 0.360 0 0.054 0.199 00.049 0.018 0.015 0 0.015 00.867 0.008 0.019 0 0.008 L

L1010103-QJ-GS-001-SSB 3.260 0..715 1.830 2 .850 0.017 4.240 0.333 0 0.011 0.606 0.015 0 0.740 0 0.036 0.117 00.039 0.026 0.029 0 0.017 11.430 0.009 0.024 0 0.005 L

L1010103-QJ-GS-001-SSS 0.025 0 0.015 0.020 0 0 0.046 0.174 00.047 0.043 L

L1010103-QJ-GS-002-SSB 0.649 0..702 2.100 2 .620 0.014 3.710 0.325 0 0.012 0.645 0.012 0 0.838 0 0.029 0.103 00.034 0.020 0.034 0 0.024 22.570 0.018 0.024 0 0.014 L

L1010103-QJ-GS-002-SSS 0.019 0 0.017 0.017 0 0 0.040 0.139 00.045 0.024 L

L1010103-QJ-GS-003-SSB 0.654 0..717 2.340 2 .630 0.012 3.660 0.300 0 0.009 0.557 0.011 0 0.713 0 0.029 0.092 00.034 0.040 0.028 0 0.028 22.470 0.018 0.022 0 0.005 L

L1010103-QJ-GS-003-SSS 0.023 0 0.019 0.091 0 0.057 0.186 00.063 0.052 L

L1010104-CJ-GS-003-SSB 0.015 0 0.008 0.013 0 0 0.032 0.078 00.036 0.034 L

L1010104-CR-PA-007- -AV 0.021 0 0.014 0.016 0 0 0.042 0.141 00.044 0.040 L

L1010104-QQ-PA-001- -AV 0.025 0 0.025 0.028 0 0 0.058 0.218 00.061 0.050 L1010104-QR-GS-001--SB L 0.017 0 0.011 0.012 0 0 0.038 0.132 00.032 0.032 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value.

2-51

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tablle 2-12 Im mpacted Cla ass 2 Open Land L Surveey Units - CCharacterizaation Surveey Summary S

Surrvey Unit Surrvey Unit L201 11101 Surrvey Unit L20111102 Surface Area 7,211 m2 6,785 m2 LACBWR R Admministration G-3 Cribb House, LACBWR Description Building, LACBW WR Crib Circ. Waater Dischaarge Line, House, Warehouse W Grrounds Area Soutth of LSE Feence Surrface Soil Co-600 Cs-137 Co-600 Cs-137

1. off Samples 13 13 10 10

1. >CCL 0 8 0 6 Meaan (pCi/g) 0.0733 0.090 0.0644 0.065 Med dian (pCi/g) 0.0777 0.100 0.0644 0.054 Max x (pCi/g) 0.1066 0.139 0.081 0.200 Minn (pCi/g) 0.0533 0.041 0.0522 0.030 SD 0.0166 0.030 0.0099 0.049 Subbsurface Soil Co-600 Cs-137 Co-600 Cs-137

1. off Samples 16 16 7 7

1. >CCL 1 2 0 2 Meaan (pCi/g) 0.0522 0.049 0.0499 0.038 Med dian (pCi/g) 0.0466 0.048 0.0488 0.033 Max x (pCi/g) 0.1122 0.088 0.0555 0.052 Minn (pCi/g) 0.0400 0.034 0.0422 0.029 SD 0.0188 0.012 0.0044 0.009 Aspphalt Co-600 Cs-137 Co-600 Cs-137

1. off Samples 6 6 6 6

1. >CCL 0 0 0 3 Meaan (pCi/g) 0.051 0.051 0.0566 0.048 Med dian (pCi/g) 0.051 0.051 0.0577 0.051 Max x (pCi/g) 0.0544 0.054 0.0599 0.055 Minn (pCi/g) 0.0477 0.047 0.0499 0.009 SD 0.0022 0.003 0.0033 0.008 Surrface Scans

% Scanned S 50% 50%

Meaan Scan (cpm) 7,500 to 8,000 7,500 to 8,0000 Max x Scan (cpm) 11,500 to 12 2,000 111,500 to 12,0000 2-52

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 22-13 Class 2 Asphalt, Sedim ment and Soil Samples S - Test America Labooratory Analysiis Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 N Ni-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L2011101-CJ-GS-001-S SM 0.096 0 0.011 0.137 0 0.041 0.098 00.033 0.031 L

L2011101-CR-PA-003--AV 0.023 0 0.016 0.017 0 0 0.039 0.131 00.039 0.038 L

L2011101-QJ-GS-001-S SB 0.518 0..727 2.290 2 .660 0.016 4.030 0.273 0 0.014 0.643 0.015 0 0.705 0 0.033 0.108 00.040 0.022 0.028 0 0.025 22.470 0.015 0.022 0 0.019 L

L2011101-QJ-GS-001-S SM 2.040 0..707 2.240 2 .950 0.049 4.140 0.523 0 0.018 0.585 0.107 0.615 0 0.048 0.178 00.049 0.026 0.045 0 0.021 33.100 0.037 0.036 0 0.034 L

L2011101-QJ-GS-001-S SS 0.012 0 0.020 0.080 0 0.060 0.188 00.091 0.042 L

L2011101-QQ-GS-001--SB 0.017 0 0.012 0.013 0 0 0.040 0.127 00.037 0.031 L

L2011101-QQ-GS-001--SS 11.810 0..726 2.590 2 .600 0.035 3.720 0.255 0 0.035 0.532 0.103 0.779 0 0.097 0.205 00.102 0.023 0.037 0 0.024 22.800 0.019 0.015 0 0.015 L

L2011101-QQ-GS-002--SB 2.500 0..731 1.940 2 .680 0.017 3.870 0.314 0 0.014 0.616 0.016 0 0.697 0 0.037 0.119 00.041 0.019 0.039 0 0.016 22.920 0.020 0.028 0 0.016 L

L2011101-QQ-PA-001--AV 0.022 0 0.015 0.015 0 0 0.046 0.135 00.042 0.040 L

L2011102-QQ-GS-001--SB 1.370 1.560 2.260 3 .040 0.007 4.390 0.291 0 0.018 0.537 0.021 0 0.672 0 0.044 0.173 00.055 0.031 0.026 0 0.018 22.680 0.029 0.028 0 0.024 L

L2011102-QQ-GS-001--SS 0.533 0..713 2.330 2 .820 0.019 4.300 0.361 0 0.014 0.595 0.014 0 0.772 0 0.039 0.111 00.045 0.017 0.036 0 0.026 22.880 0.026 0.034 0 0.021 L

L2011102-QQ-GS-002--SB 0.525 0..702 3.890 2 .880 0.031 3.950 0.327 0 0.016 0.568 0.018 0 0.717 0 0.052 0.183 00.051 0.022 0.028 0 0.020 11.710 0.010 0.028 0 0.006 L

L2011102-QQ-PA-001--AV 0.027 0 0.017 0.018 0 0 0.051 0.142 00.038 0.036 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

2-53

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-14 Impacted Cla ass 3 Open Land d Survey Unitss - Characterizzation Survey S Summary Survey Unit Survey Unitt L3012101 Survey Unit L3012102 Survey Unit LL3012109 Surface Area 24,042 m2 11,711 m2 331,012 m2 PPlant Access, ISFSI Haul Road Description North End of Liccensed Site Transmission Switchyard Area GGrounds Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 5 5

1. >CL 0 0 0 5 Mean M (pCi/g) 0.070 0.073 0.063 0.152 Median M (pCi/g) 0.076 0.072 None Taken T 0.064 0.143 Max M (pCi/g) 0.077 0.083 0.078 0.267 Min M (pCi/g) 0.058 0.065 0.053 0.075 SD 0.011 0.009 0.010 0.078 Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 4 4

1. >CL 0 0 0 0 Mean M (pCi/g) 0.051 0.051 0.072 0.066 Median M (pCi/g) 0.053 0.052 None Taken T 0.072 0.059 Max M (pCi/g) 0.054 0.052 0.100 0.101 Min M (pCi/g) 0.046 0.051 0.046 0.045 SD 0.004 0.001 0.023 0.025 Concrete/Asphalt C Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 7 7

1. >CL 0 0 0 0 Mean M (pCi/g) 0.031 0.029 0.062 0.059 Median M (pCi/g) 0.031 0.027 None Taken 0.055 0.052 Max M (pCi/g) 0.035 0.033 0.080 0.079 Min M (pCi/g) 0.028 0.026 0.047 0.028 SD 0.003 0.004 0.013 0.019 Surface Scans

% Scanned 1%% 1%

Mean M Scan (cpm) 9,000 No Scanning Performed 5,8900 Max M Scan (cpm) 10,000 6,4000 2-54

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 2-155 Class 3 Asp phalt, Sedimentt and Soil Samp ples - Test Am merica Laboratoory Analysis (ppCi/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 NNi-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L3012101-CR-GC-001- -CV 0.028 0 0.030 0.026 0 0 0.043 0.221 00.059 0.053 L

L3012101-CR-GC-002- -CV 0.035 0 0.026 0.033 0 0 0.062 0.271 00.056 0.055 L

L3012101-CR-GC-003- -CV 0..669 2.180 2 .020 0.031 3.590 0.374 0 0.027 0.521 0.027 0 1.480 0 0.056 0.249 00.069 0.025 0.046 0 0.018 11.690 0.019 0.021 0 0.006 L

L3012101-CR-GS-003- -SS 0.025 0 0.017 0.113 0 0.052 0.157 00.059 0.052 L

L3012101-QQ-GS-001- -SB 18.400 0..717 2.390 2 .870 0.016 5.640 0.309 0 0.014 0.550 0.015 0 0.899 0 0.036 0.128 00.036 0.039 0.035 0 0.022 22.590 0.023 0.029 0 0.027 L

L3012101-QQ-GS-001- -SS 15.500 0..708 2.330 2 .660 0.020 3.890 0.295 0 0.017 0.603 0.059 1.090 0 0.047 0.116 00.054 0.028 0.028 0 0.022 22.640 0.019 0.021 0 0.006 L

L3012101-QQ-SL-001- -SM 0.364 0..342 2.710 00.739 0.022 1.090 0.152 0 0.017 0.360 0.020 0 0.333 0 0.042 0.153 00.034 0.009 0.016 0 0.013 00.797 0.009 0.009 0 0.011 L

L3012104-CR-GS-002- -SM 0.015 0 0.013 0.066 0 0.035 0.128 00.047 0.036 L

L3012104-QJ-GS-001-SSB 2.160 0..670 1.950 1 .750 0.021 3.060 0.325 0 0.018 0.469 0.025 0 0.818 0 0.053 0.160 00.054 0.022 0.027 0 0.021 11.610 0.016 0.018 0 0.016 L

L3012104-QJ-GS-001-SSM 2.890 0..672 2.720 1 .990 0.037 3.500 0.298 0 0.020 0.651 0.094 0.818 0 0.074 0.217 00.071 0.006 0.031 0 0.017 11.560 0.016 0.016 0 0.015 L3012104-QJ-GS-001-S L SS 2.190 0..676 4.240 1 .880 0.029 3.300 0.329 0 0.020 0.631 0.138 0.667 0 0.068 0.181 00.080 0.020 0.043 0 0.026 11.580 0.019 0.019 0 0.021 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value 2-55

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table T 2-16 Concrete Core Isotop pic Analysiss Results B1001101-C CJ-FC-001-CV 0-1/2 0 B1001101-CJ-FC B C-001-CV 1/2-1 B1001101-CJ-FC-002-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 3.950 1.590 1.350 9.720 9 1.5660 1.950 3.640 1.620 1.330 C-14 -0.162 1.400 0.793 -0 0.346 1.4440 0.806 -0.2700 1.410 0.794 Fe-55 9.130 16.000 7.880 10 0.400 21.3300 10.2000 11.3000 9.950 5.540 Ni-59 0.000 0.254 0.325 0.000 0 0.2664 0.151 0.000 0.289 0.183 Co-60 11.500 0.377 1.250 0.082 0 0.1668 0.078 0.800 0.117 0.172 Ni-63 39.300 0.402 4.110 3.850 3 0.4225 0.474 4.860 0.492 0.581 Sr-90 6.910 0.043 0.680 0.162 0 0.0551 0.041 11.6000 0.046 1.130 Nb-94 -0.120 0.312 0.189 0.001 0 0.1339 0.078 -0.0177 0.165 0.095 Tc-99 0.024 0.566 0.330 0.076 0 0.5226 0.310 -0.1044 0.564 0.322 Cs-137 7500 7.090 781.000 9.660 9 0.1552 1.100 450.000 0.597 46.900 Eu-152 2.580 9.020 5.230 -0 0.039 0.5111 0.055 0.173 2.150 0.924 Eu-154 0.266 2.410 0.398 0.025 0 1.2660 0.171 -0.0088 1.460 0.820 Eu-155 0.369 4.440 1.140 0.071 0 0.3776 0.118 0.145 0.837 0.503 Np-237 0.009 0.042 0.021 -0 0.002 0.0445 0.017 -0.0100 0.042 0.009 Pu-238 0.176 0.056 0.065 -0 0.017 0.0666 0.026 0.575 0.617 0.436 Pu-239/240 0.132 0.048 0.055 -0 0.006 0.0449 0.018 0.715 0.466 0.413 Pu-241 0.902 2.700 1.660 -1 1.510 2.5000 1.360 13.2000 23.500 15.100 Am-241 0.407 0.048 0.107 0.011 0 0.0337 0.020 0.550 0.401 0.419 Am-243 0.028 0.046 0.030 0.014 0 0.0330 0.019 -0.0366 0.433 0.140 Cm-243/244 0.0579 0.0302 0.0371 -0.0081 0.04478 0.00944 0.15400 0.4670 0.2600 B1001101-C CJ-FC-003-CV 0-1/2 0 B1001101-CJ-FC B C-003-CV 1/2-1 B1001101-CJ-FC-004-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 7.240 1.360 1.580 12 2.600 1.5770 2.240 4.490 1.590 1.420 C-14 -0.492 1.460 0.806 -0 0.566 1.3990 0.765 -0.5555 1.450 0.795 Fe-55 9.450 9.040 4.950 6.160 6 14.3300 6.960 7.600 7.070 4.040 Ni-59 0.000 0.365 0.806 0.000 0 0.2557 0.157 0.000 0.276 0.467 Co-60 57.700 0.333 5.880 0.435 0 0.0557 0.096 28.1000 0.190 2.950 Ni-63 202.000 0.593 211.100 2.990 2 0.4000 0.392 88.3000 0.467 9.200 Sr-90 34.500 0.040 3.330 0.304 0 0.0551 0.052 11.0000 0.045 1.070 Nb-94 0.191 0.392 0.203 -0 0.001 0.1553 0.086 -0.0166 0.264 0.155 Tc-99 -0.189 0.586 0.330 -0 0.129 0.5996 0.339 0.153 0.592 0.352 Cs-137 614.000 0.732 644.000 2.450 2 0.1113 0.348 213.000 0.439 22.200 Eu-152 0.768 2.870 1.300 0.045 0 0.3446 0.154 0.162 1.570 0.611 Eu-154 0.335 5.460 0.536 0.179 0 1.0220 0.383 0.557 3.070 0.863 Eu-155 -0.429 1.510 0.914 -0 0.007 0.2882 0.164 0.108 0.850 0.138 Np-237 0.000 0.041 0.016 -0 0.010 0.0551 0.018 -0.0200 0.060 0.020 Pu-238 0.528 0.058 0.111 -0 0.005 0.0664 0.029 0.413 0.426 0.320 Pu-239/240 0.491 0.030 0.104 -0 0.004 0.0447 0.017 0.336 0.325 0.265 Pu-241 7.470 2.640 2.160 -1 1.320 2.6660 1.480 -7.7200 26.000 14.400 Am-241 1.450 0.047 0.250 0.018 0 0.0338 0.024 0.614 0.441 0.436 Am-243 0.052 0.027 0.033 0.009 0 0.0330 0.016 0.052 0.292 0.136 Cm-243/244 0.0879 0.0408 0.0496 0..0000 0.01 68 0.00477 -0.05477 0.4320 0.0776 2-56

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continuued) Cooncrete Corre Isotopic A Analysis Reesults B1001101-C CJ-FC-005-CV 0-1/2 0 B1001101-CJ-FC B C-005-CV 1/2-1 B1001101-CJ-WC-0066-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (ppCi/g) (p pCi/g) (pCi/

i/g) (pCi/g) (pCi/g)) (pCi/g) (pCi/g)

H-3 2.960 1.520 1.200 4.180 4 1.8550 1.520 4.210 1.700 1.440 C-14 -0.077 1.410 0.810 -0 0.701 1.3550 0.733 0.077 1.440 0.832 Fe-55 8.070 9.770 5.230 8.170 8 9.8770 5.340 11.7000 9.320 5.530 Ni-59 2.590 0.267 0.813 0.000 0 0.2770 0.165 0.000 0.263 0.230 Co-60 73.900 0.372 7.510 0.075 0 0.1771 0.080 2.040 0.047 0.264 Ni-63 221.000 0.427 23 3.000 4.870 4 0.4330 0.570 13.4000 0.420 1.430 Sr-90 32.800 0.043 3.170 0.423 0 0.0551 0.063 7.150 0.034 0.703 Nb-94 -0.089 0.531 0.317 -0 0.015 0.1228 0.074 0.026 0.154 0.090 Tc-99 0.178 0.562 0.336 -0 0.124 0.5440 0.307 0.083 0.580 0.341 Cs-137 65.700 0.569 6.970 0.801 0 0.1117 0.172 1490 0.721 155.000 Eu-152 0.395 1.240 0.746 0.001 0 0.3773 0.005 0.031 3.660 2.210 Eu-154 0.637 5.650 0.831 0.119 0 0.9223 0.245 0.128 1.190 0.679 Eu-155 0.011 0.699 0.414 0.013 0 0.2555 0.148 0.737 1.470 0.896 Np-237 0.005 0.015 0.010 -0 0.017 0.0554 0.016 -0.013 0.044 0.010 Pu-238 0.706 0.065 0.134 -0 0.003 0.0553 0.023 0.029 0.037 0.027 Pu-239/240 0.489 0.035 0.106 -0 0.008 0.0338 0.008 0.035 0.025 0.026 Pu-241 9.090 2.540 2.270 0.337 0 2.5330 1.510 -1.380 2.650 1.470 Am-241 1.590 0.045 0.273 0.012 0 0.0118 0.017 0.048 0.052 0.041 Am-243 0.048 0.031 0.034 -0 0.002 0.0554 0.022 0.003 0.029 0.011 Cm-243/244 0.1160 0.0443 0.0590 0.0000 0.01 76 0.0049 -0.00533 0.0419 0.0075 B1001101-C CJ-WC-006-CV 1/2-1 B1008101-CJ--FC-002-CV B10008101-CJ-FC-0003-CV Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (ppCi/g) (p pCi/g) (pCi/

i/g) (pCi/g) (pCi/g)) (pCi/g) (pCi/g)

H-3 3.590 1.640 1.350 0.382 0 0.9440 0.559 1.300 1.020 0.713 C-14 -0.246 1.490 0.836 0.053 0 1.3770 0.794 -0.296 1.440 0.810 Fe-55 6.030 14.500 7.050 1.610 1 6.5550 3.370 6.460 14.500 7.050 Ni-59 0.000 0.257 0.147 0.000 0 0.2334 0.151 0.000 0.241 0.171 Co-60 -0.026 0.207 0.240 0.662 0 0.0665 0.131 0.974 0.142 0.162 Ni-63 2.310 0.396 0.335 2.730 2 0.3553 0.355 4.400 0.356 0.510 Sr-90 0.146 0.038 0.034 0.154 0 0.0553 0.041 0.235 0.035 0.041 Nb-94 0.019 0.141 0.060 0.000 0 0.2111 0.066 0.016 0.141 0.081 Tc-99 0.024 0.556 0.324 -0 0.010 0.5779 0.335 -0.005 0.592 0.343 Cs-137 1.410 0.153 0.258 166.000 0.1777 1.780 10.0000 0.154 1.130 Eu-152 0.021 0.434 0.113 0.034 0 0.6333 0.056 0.291 0.470 0.270 Eu-154 0.055 1.270 0.137 0.060 0 1.2000 0.239 0.019 1.410 0.052 Eu-155 0.003 0.336 0.196 0.140 0 0.3557 0.215 0.101 0.348 0.208 Np-237 0.003 0.045 0.021 0.003 0 0.0448 0.022 -0.024 0.068 0.025 Pu-238 -0.004 0.043 0.016 0.018 0 0.0660 0.033 0.042 0.057 0.038 Pu-239/240 0.035 0.033 0.028 -0 0.011 0.0554 0.019 0.008 0.034 0.017 Pu-241 -1.890 2.360 1.270 -1 1.120 2.7110 1.480 -0.194 2.550 1.470 Am-241 0.006 0.036 0.017 0.020 0 0.0442 0.027 0.019 0.051 0.029 Am-243 -0.002 0.031 0.005 -0 0.002 0.0444 0.017 -0.001 0.052 0.023 Cm-243/244 -0.0036 0.0287 0.0052 0.0062 0.01 87 0.0125 -0.00566 0.0444 0.0080 2-57

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continu ued) Cooncrete Corre Isotopic A Analysis Reesults B100810 01-CJ-FC-004-C CV B1002101-CJ-FC B C-001-CV 0-1/2 B10022101-CJ-FC-001-CV 1/2-1 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 1.200 0.990 0.685 0.820 0 0.9885 0.637 0.275 0.931 0.543 C-14 0.077 1.430 0.829 0.505 0 1.4110 0.850 -0.0188 1.440 0.824 Fe-55 6.520 11.500 5.820 15 5.400 13.8800 7.430 0.547 5.510 2.840 Ni-59 0.000 0.229 0.162 65 5.500 0.3110 8.690 0.000 0.245 0.170 Co-60 1.390 0.095 0.255 95 5.000 0.4220 9.600 1.010 0.149 0.168 Ni-63 4.260 0.339 0.492 817.000 0.4772 85.0000 5.640 0.367 0.633 Sr-90 0.216 0.040 0.041 99 9.800 0.0445 9.600 0.253 0.053 0.049 Nb-94 0.001 0.143 0.081 0.098 0 0.4775 0.149 0.029 0.102 0.054 Tc-99 0.043 0.599 0.350 0.113 0 0.5664 0.333 -0.1011 0.507 0.289 Cs-137 19.800 0.166 2.150 4710 4 1.6990 491.0000 3.870 0.137 0.496 Eu-152 -0.119 0.580 0.344 0.815 0 5.9440 1.410 0.039 0.444 0.107 Eu-154 -0.061 1.370 0.296 1.250 5.4660 1.980 -0.2600 1.480 0.859 Eu-155 0.006 0.376 0.220 0.073 0 2.1220 1.280 0.077 0.272 0.162 Np-237 0.014 0.065 0.035 -0 0.012 0.0660 0.023 -0.0222 0.064 0.023 Pu-238 0.020 0.052 0.030 0.920 0 0.6220 0.511 0.017 0.059 0.033 Pu-239/240 0.025 0.042 0.028 1.280 0.4669 0.537 -0.0055 0.042 0.013 Pu-241 -1.610 2.610 1.430 5.240 5 26.7700 16.2000 -0.9844 2.680 1.510 Am-241 0.052 0.034 0.035 3.200 3 0.4228 0.989 0.035 0.037 0.031 Am-243 -0.004 0.032 0.006 0.406 0 0.2996 0.310 -0.0188 0.054 0.013 Cm-243/244 0.0100 0.0150 0.0142 0..2020 0.42200 0.26700 -0.00466 0.0366 0.0066 B1002101-C CJ-FC-001-CV 1-1.5 B1002101-CJ-FC B C-001-CV 1.5-2 B10022101-CJ-FC-002-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 0.763 1.000 0.638 0.094 0 0.9117 0.512 1.710 1.180 0.846 C-14 -0.776 1.410 0.763 0.372 0 1.3880 0.819 15.4000 1.510 2.310 Fe-55 3.540 5.670 3.150 7.770 7 25.0000 11.4000 8.960 5.860 3.640 Ni-59 0.000 0.228 0.159 0.000 0 0.2559 0.188 423.000 0.446 55.200 Co-60 0.742 0.069 0.148 0.872 0 0.1338 0.161 300.000 0.762 30.200 Ni-63 3.360 0.333 0.407 5.730 5 0.3888 0.646 2360 0.661 245.000 Sr-90 2.410 0.050 0.250 0.106 0 0.0441 0.032 220.000 0.052 21.100 Nb-94 0.035 0.149 0.066 -0 0.034 0.1442 0.083 -0.3500 0.935 0.567 Tc-99 0.259 0.564 0.342 0.032 0 0.5228 0.308 0.792 0.562 0.373 Cs-137 3.630 0.150 0.493 2.440 2 0.1446 0.343 254000 4.140 2650 Eu-152 0.156 0.420 0.236 0.125 0 0.3883 0.195 0.510 13.700 0.956 Eu-154 0.119 1.400 0.382 0.271 0 0.9556 0.406 4.650 7.170 4.390 Eu-155 0.159 0.335 0.204 0.099 0 0.3226 0.196 1.060 7.370 0.988 Np-237 0.000 0.045 0.018 -0 0.007 0.0552 0.019 0.024 0.042 0.027 Pu-238 0.023 0.061 0.035 0.004 0 0.0661 0.030 3.200 0.497 0.825 Pu-239/240 0.000 0.049 0.021 0.009 0 0.0441 0.021 2.580 0.287 0.713 Pu-241 -0.052 2.820 1.640 -2 2.090 2.7000 1.460 36.9000 24.000 17.100 Am-241 0.020 0.015 0.020 0.017 0 0.0441 0.025 9.080 0.682 2.030 Am-243 0.013 0.029 0.018 0.029 0 0.0229 0.026 0.305 0.388 0.286 Cm-243/244 0.0048 0.0143 0.0096 0..0059 0.03331 0.01544 0.42800 0.5450 0.4200 2-58

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continu ued) Cooncrete Corre Isotopic A Analysis Reesults B1002101-C CJ-FC-002-CV 1/2-1 1 B1002101-CJ-FC B C-003-CV 0-1/2 Result MDC Result R MD DC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g)

H-3 0.846 1.120 0.716 0.836 0 0.9662 0.624 C-14 6.180 1.420 1.340 -0 0.405 1.4440 0.803 Fe-55 5.270 25.300 11 1.400 8.430 8 17.0000 8.210 Ni-59 0.000 0.269 0.616 0.000 0 0.3334 0.484 Co-60 8.270 0.114 0.907 8.570 8 0.1448 0.940 Ni-63 175.000 0.442 18 8.300 70 0.600 0.5448 7.370 Sr-90 3.520 0.047 0.356 7.000 7 0.0550 0.691 Nb-94 -0.041 0.230 0.135 0.038 0 0.2111 0.060 Tc-99 0.165 0.522 0.312 0.062 0 0.5443 0.318 Cs-137 208.000 0.362 21 1.700 1240 1 0.8117 129.0000 Eu-152 -0.280 1.580 0.950 0.176 0 2.6000 0.514 Eu-154 0.255 1.900 0.259 0.090 0 2.3220 0.202 Eu-155 0.116 0.864 0.205 -0 0.004 1.7110 1.030 Np-237 -0.019 0.056 0.017 -0 0.011 0.0444 0.009 Pu-238 0.059 0.064 0.046 0.105 0 0.0556 0.051 Pu-239/240 0.056 0.049 0.040 0.126 0 0.0339 0.051 Pu-241 -0.965 2.970 1.690 1.500 2.5660 1.640 Am-241 0.238 0.048 0.080 0.339 0 0.0444 0.099 Am-243 0.005 0.060 0.028 -0 0.001 0.0337 0.012 Cm-243/244 0.0018 0.0438 0.0179 0..0175 0.01 75 0.02033 2-59

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tab ble 2-17 19883 Groundw water Analyysis from Teemporary Weell-Point So outh of Turb bine Buildin ng AActivity Radion nuclide (p

pCi/L)

Mn--54 63.4 Co--57 6.4 Co--60 508 Nb--95 21.4 Cs-1137 21.7 Ce-1141 18.9 2-60

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-18 2 2013 Grroundwater Monitoring Resu ults June 2013 MW-20 01-A MW-201-B B MW-202-A MW-202-B MW W-203-A MW-2203-B MW-204--A MW-204-B (pCi/LL) (pCi/L) (pCi/L) (pCi/L) (ppCi/L) (pCii/L) (pCi/L) (pCi/L)

H-3 5722 506 660 484 N/A 4220 397 420 Co-660 4.00 0 5.01 4.76 4.51 4.95 4.112 4.36 4.26 Sr-9 90 5 2.05 2.00 1.82 1.43 2.06 2.006 2.18 2.08 Cs-1 137 3.97 7 3.84 4.05 3.91 4.52 4.331 4.11 3.96 a Bold B values indiicate concentratiion greater than n MDC. Italicizeed values indicaate MDC value.

Novvember 2013 MW-20 01-A MW-201-B B MW-202-A MW-202-B MW W-203-A MW-2203-B MW-204--A MW-204-B (pCi/LL) (pCi/L) (pCi/L) (pCi/L) (ppCi/L) (pCii/L) (pCi/L) (pCi/L)

H-3 2355 150 257 278 449 2335 193 171 Co-660 4.64 4 3.80 5.26 5.41 4.43 3.889 4.52 8.24 Sr-9 90 1.18 8 3.73 1.18 1.61 1.87 2.440 1.18 1.51 Cs-1 137 4.64 4 1.90 6.54 4.70 4.41 3.998 4.77 7.92 a Bold B values indiicate concentratiion greater than n MDC. Italicizeed values indicaate MDC value.

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Revision 0 Tablle 2-19 2014 Groundwater Monitoring Reesults (pCi/L)

J JUNE 2014 MW- MW- MW-M MW- MW- MW W- MW- MW- MW- MW- M MW- MW- MW- MWW- MW- MW- MW- MW-DW3 DW4 D DW5 DW7 B11R B11AAR B2 B3 200-A 200-B 2001-A 201-B 202-A 202-B 203-A 203-B 204-A 204-B Gross G

1.26E-011 -1.33E-01 4.444E+00 -3.78E-01 0.00E+00 7.33E-01 -2.13E+00 6 6.46E-01 4.04E+000 -2.26E-01 3.844E-01 -1.04E+00 1.06E+00 4.07E--01 1.74E+00 -22.29E-01 7.58E-01 1.27E+00 A

Alpha G

Gross 1.48E+00 3.13E+00 1.933E+00 0.00E+00 3.59E+00 -2.70E E-01 1.12E+01 4 4.14E+00 8.66E+000 -1.79E+00 7.266E+00 -1.04E+00 4.34E+00 1.49E++00 2.27E+00 55.53E+00 2.69E+00 0 2.57E-01 B

Beta H

H-3 1.05E+02 1.59E+02 1.944E+02 1.23E+02 2.45E+02 1.61E++02 1.60E+02 1 1.94E+02 5.23E+011 1.24E+02 7.033E+01 1.05E+02 3.36E+02 1.06E++02 2.79E+02 22.79E+02 1.06E+02 2 3.49E+01 C

C-14 2.79E+00 0.00E+00 -3.997E+00 -5.08E+00 9.06E+00 6.83E++00 1.94E+00 -22.05E+00 9.26E+000 4.84E+00 4.844E+00 4.51E+00 0.00E+00 4.70E+

+00 4.54E+00 44.55E+00 4.66E+000 1.30E+01 F

Fe-55 -2.00E+001 -3.12E+01 -2.666E+01 -3.86E+01 -3.19E+01 -3.75EE+01 -9.20E+00 -44.39E+01 1.93E+011 -4.16E+01 -3.200E+01 1.58E+01 -3.26E+00 -4.54E+

+01 -4.95E+01 -44.96E+01 -4.03E+01 1 -3.98E+00 N

Ni-59 1.83E+01 3.96E+01 -4.775E+01 2.60E+01 -4.16E+00 2.53E++00 -7.13E+00 3 3.15E+01 -2.18E+01 3.32E+01 -1.67E+01 -7.11E+01 2.49E+01 -1.05E+

+01 -2.71E+01 -44.66E+00 -6.22E+00 0 -2.47E+01 C

Co-60 1.02E+00 3.94E-01 2.50E+00 -2.42E+00 8.76E-01 -1.94EE+00 -1.39E+00 -11.13E+00 1.01E+000 -1.27E+00 -6.004E-02 1.73E+00 -8.91E-01 1.02E++00 3.48E-02 -99.55E-01 1.91E-01 -2.31E-01 N

Ni-63 -1.78E+000 -6.14E+00 -7.440E+00 -4.38E+00 -3.57E+00 0.00E++00 -7.94E+00 1 1.50E+00 -1.97E+00 -4.69E+00 1.822E+00 -1.91E+00 -1.94E+00 -3.73E+

+00 -3.70E+00 -33.80E+00 0.00E+000 -1.97E+00 S

Sr-90 6.09E-011 8.99E-02 8.999E-02 1.78E-02 7.34E-01 6.11E E-01 6.52E-01 6 6.12E-01 9.86E-01 1 9.98E-01 6.866E-02 1.02E+00 1.12E+00 6.05E--01 1.17E+00 88.23E-01 2.01E+000 6.11E-01 N

Nb-94 4.40E-011 1.43E-01 -1.226E+00 7.49E-01 -6.99E-01 1.53E++00 1.77E+00 6 6.65E-01 1.08E+00 0 8.47E-01 3.733E-01 1.80E+00 -3.55E-01 1.04E--01 1.59E+00 1.50E+00 2.26E-01 1.28E+00 T

Tc-99 -8.28E+000 -7.37E+00 -8.226E+00 -9.36E+00 -5.52E+00 -8.46EE+00 -7.41E+00 -88.10E+00 3.55E+000 5.08E+00 3.922E+00 1.17E+00 3.88E-01 2.73E++00 4.36E+00 44.17E+00 6.95E+000 6.31E+00 C

Cs-137 -5.97E-01 -3.47E-01 -7.445E-01 -1.83E+00 1.24E+00 1.84E++00 1.37E+00 2 2.14E+00 1.77E-01 1 -3.64E-01 3.100E-01 -6.21E-01 -4.64E-01 2.86E++00 1.48E+00 1.39E+00 -3.04E-01 1.93E+00 E

Eu-152 9.48E+000 2.34E+00 -7.443E+00 -5.51E+00 -9.93E-01 1.48E++00 1.07E-01 1 1.42E+01 9.71E+000 -1.16E+01 4.155E+00 1.12E+01 4.11E+00 +01 1.08E+ -9.59E-01 44.99E+00 2.12E+000 7.68E+00 E

Eu-154 -5.24E+000 3.16E+00 1.355E+00 -4.73E+00 1.63E+00 -2.61EE+00 2.36E+00 1 1.69E+00 5.77E-01 1 5.60E-01 -2.399E+00 -2.43E+00 -1.12E+00 -1.18E+

+00 1.93E+00 -33.69E+00 2.36+00 6.06E-01 E

Eu-155 -2.67E+000 1.46E+00 -1.554E-01 -1.07E+02 1.60E+00 -4.47EE+00 1.60E+00 -33.17E+00 -3.63E+00 -3.44E+00 -2.922E+00 -2.60E+00 -1.59E+00 -3.49E+

+00 -4.91E+00 44.05E+00 -4.34E-01 1.66E+00 P

Pu-238 2.83E-022 -4.77E-02 -2.222E-02 8.22E-02 0.00E+00 4.09E E-02 5.40E-02 8 8.29E-02 -1.38E-02 2 1.51E-02 5.333E-02 -5.02E-02 -8.46E-03 1.48E--01 -5.67E-02 -55.87E-02 -5.12E-022 -9.28E-03 Pu-P

-9.61E-02 2 3.36E-02 3.113E-02 4.07E-01 -2.54E-02 -3.39E E-02 3.40E-02 1 1.46E-01 2.68E-02 2 -1.57E-02 -6.886E-03 2.36E-02 -2.27E-02 -4.54E-02 -2.27E-02 -33.95E-02 -2.49E-022 6.28E-02 2

239/240 P

Pu-241 3.51E+00 2.70E+00 -8.339E+00 2.62E+00 -5.72E+00 8.38E E-01 0.00E+00 -

-7.39E-01 0.00E+00 0 4.49E+00 -4.885E-01 -1.42E+00 2.20E+00 2.72E+

+00 4.07E+00 1.03E+01 4.07E+000 -1.89E+00 A

Am-241 5.39E-022 3.42E-02 4.665E-03 -1.01E-02 1.22E-02 8.37E E-02 3.98E-03 2 2.28E-02 1.72E-011 9.71E-01 9.466E-02 3.99E-03 1.16E-01 3.92E--02 2.94E-02 77.64E-02 1.56E-01 8.24E-02 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

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Revision 0 Table 2-19 (continued) 2014 Ground dwater Monitooring Results (p pCi/L)

S September 20144 MW-DW5 M MW--B11R MW-B11A AR MW-200-A MW-200-B MW-201-A MW-201-B M MW W-202-A MW-2002-B MW-203-A A MW-203-B MW-204-A MW-204-B G

Gross Alpha 8.47E-01 8 3.09EE+00 2.07E-001 2.42E-01 2.01E+00 1.18E+00 1.43E+00 1.04E+00 -2.10E-E-01 1.37E+00 -6.68E-01 6.00E-01 3.53E+00 G

Gross Beta 2.96E+00 1.45EE+01 3.04E-001 2.41E+00 9.11E+00 7.36E+00 3.67E+00 4.886E-01 2.30E++00 1.52E+00 1.00E+00 5.28E+00 0.00E+00 H

H-3 3.43E+01 0.00EE+00 3.44E+001 6.86E+01 5.17E+01 8.67E+01 -3.42E+01 -5.118E+01 1.04E++02 -3.44E+01 1.21E+02 6.88E+01 -1.21E+02 C

C-14 -9 9.44E-01 -2.70E E+00 0.00E+000 -4.56E-01 -4.98E+00 2.69E+00 9.28E-01 4.944E+00 -2.72E+ +00 -3.95E+00 0 4.89E-01 4.73E-01 9.46E-01 F

Fe-55 9.39E+00 9 -3.10E E+01 -3.49E+001 -3.35E+01 -4.56E+01 -2.18E+01 2.77E+01 -5.443E+01 3.37E++01 -4.95E+01 4.32E+01 3.45E+01 -9.25E+01 N

Ni-59 3.13E+00 1.64EE+01 -8.49E+000 7.84E+00 2.37E+01 -1.99E+01 3.09E+01 -1.118E+01 -4.46E+ +01 5.30E+01 -4.34E+01 -3.13E+01 -1.87E+01 C

Co-60 2.17E+00 1.32EE+00 1.22E+000 3.56E+00 6.20E-01 -7.23E-02 9.50E-01 9.772E-01 1.18E++00 3.67E+00 1.99E+00 -3.77E-01 2.05E+00 N

Ni-63 2.79E+00 2.48EE+00 -4.14E-001 3.62E+00 -7.87E-01 5.00E+00 2.15E+00 8.225E-01 -8.30E-E-01 1.62E+00 -1.77E+00 -1.84E-01 3.94E-01 S

Sr-90 -1 1.06E+00 5.90EE-01 2.80E-001 1.14E+00 5.10E-01 -1.19E-01 -4.99E-01 6.770E-01 5.40E--01 4.80E-01 8.70E-01 9.00E-01 2.30E-01 N

Nb-94 -9 9.45E-01 -1.39E E+00 -1.29E-001 -1.43E+00 -2.68E-01 6.56E-01 6.44E-01 -6.448E-02 -1.02E+ +00 8.53E-02 2.16E+00 1.18E-01 -1.88E+00 T

Tc-99 -1 1.54E+00 -4.000E-01 -1.56E+000 -1.57E+00 -1.54E+00 -7.94E-01 -1.95E+00 7.997E-01 -1.95E-E-01 -1.24E+00 0 -3.32E+00 -1.96E+00 3.89E-01 C

Cs-137 3.97E+00 -7.244E-01 9.72E-001 2.17E+01 1.94E+00 -1.09E+00 1.84E+00 -4.334E-01 2.31E++00 1.56E+00 6.84E-01 -1.14E+00 1.24E+00 E

Eu-152 2.48E+00 3.00EE+00 6.42E+000 -2.39E+00 -1.34E+01 4.79E+00 2.53E+00 9.40E+00 6.51E++00 4.06E+00 -1.15E+00 -1.92E+01 2.23E+00 E

Eu-154 -3 3.31E+00 -3.93E E+00 1.10E+000 -6.57E-01 -1.54E+00 -3.09E+00 1.94E+00 -3.667E-01 4.18E++00 -3.33E+00 0 -2.31E-01 -4.95E+00 2.36E+00 E

Eu-155 2.69E+00 1.95EE+00 1.69E+000 -8.16E-01 -1.64E+00 -1.48E+00 4.13E+00 -2.008E+00 -8.41E-E-01 -9.54E-02 -3.66E-01 -2.02E+00 9.46E-01 P

Pu-238 1.71E-02 1 3.69E E-02 -5.50E-003 2.65E-02 -6.50E-03 -3.59E-02 8.55E-02 1.113E-02 3.63E--02 7.08E-02 8.12E-02 -6.45E-04 -3.26E-02 P

Pu-239/240 9.28E-02 9 0.00E E+00 -1.10E-002 5.83E-02 0.00E+00 0.00E+00 1.41E-01 5.887E-02 5.25E--02 9.15E-02 5.97E-02 -5.48E-03 7.02E-02 P

Pu-241 3.18E+00 -3.68E E+00 -2.29E+000 -2.23E+00 8.49E+00 -6.92E-01 -5.85E-01 0.00E+00 -1.76E+ +00 5.04E-01 -3.71E+00 -3.97E+00 -6.46E+00 A

Am-241 1.28E-01 1 3.69E E-02 -1.69E-002 1.10E-01 2.29E-01 1.40E-01 2.80E-02 6.662E-02 9.48E--02 2.51E-01 1.03E-01 1.06E-01 2.69E-01 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

2-63

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Revision 0 Figuree 2-1 LACBWR Site Map - Open Land Survey Units an nd Classificatioon 2-64

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-2 LACBWR Site Map - Buiildings Identifiication 2-65

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-3 LACBWR R Site Drain nage and Seewer Map 2-66

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-4 LACBWR R LCE Excllusion Area (Class 1) 2-67

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figu ure 2-5 Non N Impacteed Open Laand Samplin ng Locations 2-68

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-6 Class 1 Open O Land Sampling Locations 2-69

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-7 Class 2 Open O Land Sampling Locations 2-70

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-8 Class 3 Open O Land Sampling Locations 2-71

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 2-9 9 Concreete Core Sam mpling Loccations 2-72

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-73

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-74

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-10 LACBWR Siite - Typical Geeological Crosss-Section 2-75

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-11 1 Groundwatter Sampling Wells - LACBW WR Site 2-76

LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 2 SITE CHARACTERIZATION

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

2. Site Characterizzation ................................................................................................................. 2-1 2.1. Historical Site S Assessm ment ................................................................................................. 2-2 2.1.1. Objectiives ................................................................................................................... 2-2 2.1.2. Method dology ............................................................................................................... 2-3 2.1.2.1. Preliminary Claassification ..................................................................................... 2-3 2.1.2.2. Doccument Reviiew ................................................................................................. 2-4 2.1.2.3. Licenses, Perm mits and Auth horizations .................................................................. 2-5 2.1.2.4. Perrsonnel Interrviews ............................................................................................. 2-5 2.1.2.5. Prooperty Inspecctions.............................................................................................. 2-5 2.1.3. Operatiional History y..................................................................................................... 2-6

4. Inciden 2.1.4 nts ...................................................................................................................... 2-6 2.1.4.1. Rad diological Sp pills ................................................................................................ 2-7 2.1.4.2. Cheemical Spillss ..................................................................................................... 2-8 2.1.5. Finding gs and Conclusions ........................................................................................... 2-8 2.1.6. Initial Survey S Areaas/Units and Classificatioon ........................................................... 2-9 2.1.6.1. Surrvey Areas ......................................................................................................... 2-9 2.1.6.2. Surrvey Units.......................................................................................................... 2-9 2.1.6.3. Claass 1 Open Land L Areas .................................................................................... 2-10 2.1.6.4. Claass 2 Open Land L Areas .................................................................................... 2-10 2.1.6.5. Claass 3 Open Land L Areas .................................................................................... 2-10 2.1.6.6. Non n-Impacted Open O Land Areas A ....................................................................... 2-11 2.1.6.7. Claass 1 Structurres................................................................................................ 2-11 2.1.6.8. Claass 2 and 3 Structures S ...................................................................................... 2-12 2.2. Characterization Approach ............................................................................................... 2-12 2.2.1. Data Quality Q Objecctives ............................................................................................ 2-14 2.2.2. Survey y Design ........................................................................................................... 2-14 2.2.2.1. Num mber of Stattic Measurem ments and/orr Samples ............................................. 2-15 2.2.2.2. Dettermination of o Static Meeasurement aand Sample L Locations ......................... 2-16 2.2.2.3. Scaan Coverage .................................................................................................... 2-16 2.2.2.4. Typ pes of Measu urements and d Samples ................................................................ 2-16 2.2.3. Instrummentation Selection, Use and Minimuum Detectabble Concenntrations (M MDCs) ........................................................................................... 2-18 2.2.3.1. Callibration........................................................................................................... 2-18 2.2.3.2. Insttrument Usee and Control ............................................................................... 2-19

4. Laboraatory Instrum 2.2.4 ment Method ds and Sensittivities .................................................. 2-19 2.2.5. Quality y Assurance ..................................................................................................... 2-19 2.3. Summary of Characterization Surveey Results ................................................................ 2-20 2.3.1. Backgrround Study..................................................................................................... 2-21 2.3.2. Potentiial Radionucclides of Con ncern......................................................................... 2-22 2.3.3. Non-Im mpacted Opeen Land Areaas ............................................................................. 2-22

4. Impacted Open Lan 2.3.4 nd Areas ...................................................................................... 2-24 2.3.4.1. Claass 1 Open Land L Areas .................................................................................... 2-25 2.3.4.2. Claass 2 Open Land L Areas .................................................................................... 2-26 2-i

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.3.4.3. Claass 3 Open Land L Areas .................................................................................... 2-27 2.3.5. Non-Im mpacted Stru uctures .......................................................................................... 2-29 2.3.6. Impacted Structurees and System ms ............................................................................ 2-30 2.3.6.1. Bassement Strucctures Below w 636 foot Ellevation ............................................... 2-30 2.3.6.2. Turrbine Buildin ng Tunnel..................................................................................... 2-31 2.3.6.3. LA ACBWR Adm ministration Building .................................................................. 2-31 2.3.7. Surfacee and Groundwater ......................................................................................... 2-32 2.3.7.1. Areea Groundwaater Use ....................................................................................... 2-32 2.3.7.2. Gro oundwater Flow .............................................................................................. 2-33 2.3.7.3. Previous Investtigations ....................................................................................... 2-34 2.3.7.4. On--Going Investigations ..................................................................................... 2-35 2.3.7.5. Sum mmary of Grroundwater Analytical A R Results .................................................. 2-35 2.4. Continuing Characterizaation ............................................................................................ 2-36 2.5. References ........................................................................................................................ 2-37 2-ii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF TABLE ES Table 2-1 1 LACBW WR Open Land Survey Units........................................................................ 2-39 Table 2-2 2 LACBW WR Structurral Survey Units U .......................................................................... 2-40 Table 2-3 3 Instrumment Types and a Nominall MDCs .................................................................... 2-42 Table 2-4 4 Off-Sitte Laboratory y Analyticall Methods annd Typical M MDCs ............................... 2-43 Table 2-5 5 2005 Dairyland D Baackground Sttudy for Soills .......................................................... 2-44 Table 2-6 6 Investiggative Levells for Cs-137 7 Based on B Background Studies ............................ 2-45 Table 2-7 7 Initial Suite S of LAC CBWR Site--Specific Ra dionuclides .......................................... 2-46 Table 2-8 8 Non-Im mpacted Opeen Land Surv vey Units - C Characterizaation Surveyy Summary ...................................................................................................... 2-47 Table 2-9 9 Non Im mpacted Coal Pile and So oil Samples - Test Amerrica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-49 Table 2-1 10 Impacted Class 1 Open O Land Survey S Units - Characterrization Survvey Summaary .................................................................................................................. 2-50 Table 2-1 11 Class 1 Concrete, Asphalt, A Sed diment and S Soil Samples - Test Ameerica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-51 Table 2-1 12 Impacted Class 2 Open O Land Survey S Units - Characterrization Surveyy Summary ...................................................................................................... 2-52 Table 2-1 13 Class 2 Asphalt, Seediment and Soil Samplees - Test Am merica Laboraatory Analyssis ................................................................................................. 2-53 Table 2-1 14 Impacted Class 3 Open O Land Survey S Units - Characterrization Surveyy Summary ...................................................................................................... 2-54 Table 2-1 15 Class 3 Asphalt, Seediment and Soil Samplees - Test Am merica Laboraatory Analyssis (pCi/g) ..................................................................................... 2-55 Table 2-1 16 Concreete Core Isotopic Analysis Results................................................................. 2-56 Table 2-1 17 1983 Groundwater G Analysis fro om Temporaary Well-Pooint South off Turbine Buildinng .................................................................................................................... 2-60 Table 2-1 18 2013 Groundwater G Monitoring Results ................................................................... 2-61 Table 2-1 19 2014 Groundwater G Monitoring Results (pC Ci/L) ..................................................... 2-62 LIST OF O FIGURE RES Figure 2--1 LACBW WR Site Maap - Open Laand Survey U Units and Cllassification .................... 2-64 Figure 2--2 LACBW WR Site Maap - Building gs Identificaation ...................................................... 2-65 Figure 2--3 LACBW WR Site Draainage and Sewer S Map ............................................................... 2-66 Figure 2--4 LACBW WR LCE Ex xclusion Areea (Class 1) ............................................................... 2-67 Figure 2--5 Non Im mpacted Opeen Land Sam mpling Locatiions ...................................................... 2-68 Figure 2--6 Class 1 Open Land d Sampling Locations L .................................................................. 2-69 Figure 2--7 Class 2 Open Land d Sampling Locations L .................................................................. 2-70 Figure 2--8 Class 3 Open Land d Sampling Locations L .................................................................. 2-71 Figure 2--9 Concreete Core Sam mpling Locattions ......................................................................... 2-72 Figure 2--10 LACBWR Site - Typical T Geolo ogical Crosss-Section .............................................. 2-75 Figure 2--11 Ground dwater Samp pling Wells - LACBWR R Site .................................................... 2-76 2-iii

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 LIST OF ACRONYM MS AND AB BBREVIAT TIONS AEC Unitedd States Atomic Energy Commissionn ALARA As Loow As Reaso onably Achieevable bgs Beloww Ground Su urface CRD Control Rod Drive DCGL Derived Concentrration Guideline Levels DQO Data Quality Q Objeective EPA Unitedd States Env vironmental Protection P A Agency FCP Forced Circulation n Pump FESW Fuel Element E Storrage Well FRS Final Radiation Su urvey FSS Final Status Surveey G-1 Genoaa 1 Coal/Oil Station G-3 Genoaa 3 Fossil Sttation HSA Historrical Site Assessment HTD Hard-to-Detect IR Incideent Reports ISFSI Independent Spen nt Fuel Storaage Installatioon LACBW WR La Crrosse Boiling g Water Reacctor LER Licensee Event Reports LSA Low Specific S Activity LSE LACB BWR Site En nclosure LTP License Terminatiion Plan MARLA AP Multi--Agency Rad diological Laboratory L A Analytical Prootocols Mannual MARSA AME Multi--Agency Rad diation Surv vey and Asseessment of MMaterials andd Equipmentt Manu ual MARSSIIM Multi--Agency Rad diation Surv vey and Site Investigation Manual MDC Minimmal Detectab ble Concentrrations MDCR Minimmum Detectaable Count RateR MWe Megaw watt Electricc NIST Nationnal Institute of Standardds and Technnology 2-iv

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 NRC Unitedd States Nucclear Regulaatory Commiission ORC Operaational Revieew Committee PSDAR Shutdown Decommissioning Activitties Report Post-S QA Qualitty Assurancee QAPP Qualitty Assurancee Project Plaan QC Qualitty Control RCA Radio ologically Coontrolled Areea REMP oactive Effluent Monitoring Reports Radio ROC Radio onuclides of Concern RPV Reactor Pressure Vessel V

SRC Safety y Review Co ommittee STS Source Term Surv vey TSD Technnical Supporrt Document WDNR Wiscoonsin Departtment of Nattural Resourrces WGTV Wastee Gas Tank Vault V

WTB Wastee Treatment Building ZNPS Zion Nuclear N Pow wer Station 2-v

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Page Intenttionally Left ft Blank 2-vi

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0

2. Site S Chara acterization n In accorrdance with h the requirements off 10 CFR 500.82 (a)(9)(iii)(A) and tthe guidancce of Regulato ory Guide 1..179, Standa ard Format and Conteents for License Terminnation Planns for Nuclear Power Reeactors (1),, this chap pter providees a descrription of the radioloogical characterrization perfo formed at thee La Crosse Boiling B Watter Reactor ((LACBWR) site.

The purp pose of site characterizaation is to ennsure that thhe Final Raddiation Survey (FRS) w will be conducteed in all areeas where co ontamination n existed, reemains, or hhas the poteential to exiist or remain. The term F Final Radiattion Survey is from 100 CFR 50.82(9)(ii)(D) annd is used inn this License Termination T n Plan (LTP)) in order to acknowledgge the distinnction betweeen the two types of complliance survey ys that will be b performed d at LACBW WR. These surveys are; 1) a Final S Status Survey (FSS) for op pen land areeas and buried piping b ased on guiidance proviided in NUR REG-1575, Mu ulti-Agency Radiation Survey S and Site S Investiggation Manual (MARSS SIM) (2) andd 2) a Source Term T Surveey (STS) fo or below grround structtures to be backfilled prior to liccense terminatiion. See LTP P Chapter 5 for a descripption of the FRS.

The site characterization incorp porates the results r of innvestigationns and surveeys conducted to quantify the extent anda nature of o contamination at LA ACBWR. Inn addition, thhe results oof site characterrization survveys and anaalyses have been b and conntinue to bee used to identify areas oof the site that will require remediation n, as well ass to plan rem mediation m methodologiees, develop w waste classificaation and vollumes, and estimate e costts.

The chaaracterization n survey wasw designed d and execcuted using the guidannce provideed in NUREG--1575 (MA ARSSIM) and NURE EG-1757, Volume 2, Revision 11, Consoliddated Decommissioning Guidance G - Characteriza C ation, Surveey, and Determination of Radioloogical Criteria, Final Reporrt, (3). In ad ddition, surv veys were deesigned and executed inn accordancee with PG-EO-3 313196-SV-P PL-001, Ch haracterizatioon Survey P Plan for the La Crossse Boiling W Water Reactor (4), and GP P-EO-31319 96-QA-PL-00 01, Quality Assurance Project Plaan LACBWR R Site Characteerization Pro oject (QAPP P) (5) which describes ppolicy, organnization, funnctional activvities, the Data Quality Objjective (DQO O) process, and a measurees necessary to achieve qquality data. The informatiion obtained d from the characterizzation provi des guidancce for decoontaminationn and remediation planning g. Materials which weree shown to bbe contaminaated with raddioactive maaterial at concen ntrations greeater than th he unrestricteed release crriteria have been and wiill continue to be removed and properlly packaged for shipmen nt and dispossal.

The deco ommissionin ng approach for LACBW WR requires the demolittion, removaal and dispossal as waste off all LACB BWR buildiings, structu ures and coomponents (with the eexception of the LACBW WR Administtration build ding and Criib House) too a depth off at least 3 ffeet below ggrade.

None off the buildin ngs and stru uctures assoociated withh the Genoaa 3 Fossil S Station (G-33) are radiologiically impaccted such th hat they requ uire remedi al actions; therefore, nno remediatiion is planned and a these strructures, inccluding the G-3 G Crib Houuse, will rem main intact aand functional for G-3 pow wer operation ns. The pub blic roads annd railways that traversse the site aas well as seeveral minor strructures willl also remainn.

The majo or sub-gradee structures that t will be backfilled aand remain aat license terrmination arre the basementts of the Reeactor Buildiing, Waste Treatment T B Building (W WTB), Waste Gas Tank V Vault 2-1

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 (WGTV)) and the reemainder off the basemeent structurees located bbelow the 6336 foot elevvation (3 feet below grade)). These remaining stru uctures inclu lude the Pipping and Veentilation Tuunnel, Reactor/GGenerator Plant, P the onne foot thick k portion off the Chimnney Foundattion, the Tuurbine sump and d the Turbine pit.

In the Reactor R Building, all in nternal struuctural surfaaces, system ms and com mponents wiill be removed. All intern nal concrete will be rem moved to exxpose the steeel liner, whhich will alsso be removed, leaving on nly the remaaining structtural concreete outside tthe liner below the 6366 foot elevation n (i.e., concrrete bowl below 636 foot elevatioon, concretee pile cap annd piles.) IIn the WTB, th he only portion of the strructure that will remain is the 630 aand 635 foott floor, sumpp and concrete footers belo ow the 636 fo oot elevationn. In the WG GTV and thee other remaaining basem ments, the remaining structu ure will conssist of the flloors and fouundation waalls as well aas concrete ppiling cap and piles p below the t 636 foot elevation. The T structurral surfaces tthat will remmain at LACB BWR followingg the terminaation of the license l are constructed c oof steel reinfforced concrrete which w will be covered byb at least 3 feet of soil and physicaally altered tto a conditioon which woould not allow w the remaininng backfilled d structures too be plausiblly occupied..

LTP Chaapter 1, secction 1.3.1 describes d the site licennse boundaryy. The fennced area oof the Independ dent Spent Fuel F Storage Installation (ISFSI) Faccility as locaated in Lot 7 of the sitee (and shown inn Figure 2-1)) is excluded d from the sccope of the LLTP.

2.1. Historical H Site Assessmeent In accorrdance with h the guidaance provid ded in MAR RSSIM, secction 3.0, a Historical Site Assessment (HSA) (6) was performed p and a documeented in Auugust of 19999. Histoorical informatiion, includin ng any 10 CFR C 50.75(g g) files, empployee interrviews, radiological inccident reports, pre-operatio onal survey data, spill reports, speecial surveyys (e.g., sitee aerial surrveys, marine fauna f and sediment s su urveys), operational surrvey recordss, and Annnual Radioloogical Environm mental Repo orts to the Nuclear Reegulatory C Commission (NRC) werre reviewedd and compiled d for this inv vestigation.

2.1.1. Objectives O

The HSA A was a detailed d inveestigation to o collect exxisting infoormation (frrom the staart of LACBW WR activities related to radioactive r materials m or other contaaminants) foor the site annd its surrounddings. The HSA focuseed on historrical events and routinne operationaal processess that resulted in contamin nation of plaant systems,, buildings, surface andd subsurfacee soils withiin the Radiologgically Contrrolled Area (RCA).

( It allso addresse d support strructures, opeen land areaas and subsurfacce soils outside of the RCAR but withhin the owneer controlledd area. The current RCA A and the 1.5 acre a fenced LACBWR Site Enclossure (LSE) area sharee the same boundary. The informatiion compiled by the HS SA was used d to establissh initial surrvey units. This inform mation may alsoo be used as input into th he developm ment of remeediation planns and the deesign of the FRS.

The scop pe of the HSA included potentiial contaminnation from m radioactivve materialss and hazardouus materials.

The objectives of thee HSA were to:

Id dentify potential, likely, or known sources of radioactive and chemical contamiinants based on exissting or deriv ved informattion, 2-2

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Distinguish D portions p of th he site that may m need furrther action from those that pose litttle or no threat to human health h, Provide an asssessment off the likelihood of contam minant migraation, Provide inforrmation usefu ful to subsequ uent continuuing characteerization surrveys, Provide an in nitial classificcation of areeas and strucctures as nonn-impacted oor impacted, Provide a graaded initial classification n for impacteed soils and sstructures inn accordancee with MARSSIM M guidance, g andd Delineate D inittial survey unit u boundariies and areass based uponn the initial cclassificationn.

2.1.2. Methodology M y The objeective of the HSA record ds search and d interview process wass to identify those events that may havee significanttly impacted d the hazardo ous materiall or radiologgical status oof LACBWR R site land areaas and structtures. Thesee included sy ystem, struccture, or areaa contaminaation from syystem failures resulting r in airborne releases, liquid d spills or reeleases, or tthe loss of ccontrol over solid material. Dependin ng upon paast site opeerations andd processes,, the potenntial for ressidual contamin nation variess by area. In n order to faccilitate effecctive charactterization, annd to guide ffuture decontam mination actiivities and FRS planning g, land areass and structuures are classsified based upon their poteential for con ntamination..

Each incident identiffied that possed a realistiic potential tto impact thhe characteriization of the site was furth her investigaated. This in nvestigationn focused onn the scope oof contaminaant samplingg and analysis, any remed dial actions taken to mitigate m the ssituation, annd any postt-remedial aaction sampling g, survey, an nd analysis in i an attemp pt to identify fy the as leeft condition of the inccident location. Historical records r prov vided the sou urce of a vastt majority off the documeents inspecteed.

Relevantt informatio on that beccomes availlable duringg any addiitional charracterizationn and remediation phases of o the licensee termination n plan will bbe evaluated..

Also inclluded in the research asssociated with h the developpment of thee HSA were::

Relevant R exceerpts from written w reportts and corresspondences, Personnel intterviews, inccluding the use u of questtionnaires, oof current, foormer and reetired plant personn nel to confirrm documen nted incidentts and identtify undocum mented inciddents, Site inspectio on, utilizing g historic site drawingss, photograpphs, prints, and diagram ms to id dentify, locatte, confirm, and documeent areas of cconcern.

Information from thiis research was w used in the HSA deevelopment, including thhe compilation of data, evaaluation of results, r docuumentation of o findings, and the ideentification of initial Suurvey Units.

2.1.2.1. Prelimminary Classsification The HSA A investigaation was designed d to o obtain suufficient info formation too provide iinitial classificaation of the site land areeas and strucctures as imppacted or noon-impacted. Impacted areas have a potential p for contaminatiion (based on o historicall data) or coontain know wn contaminnation 2-3

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 (based ono past or preliminary p radiologicall surveillancce). Non-im mpacted areeas are idenntified through knowledge k of o site history y or previouus survey infformation annd are those aareas where there is no reaasonable possibility for residual raadioactive coontaminationn. Areas w were classifieed as impacted d from a raadiological perspective.

p Potential chemical hhazards inciddents on ow wner-controlled areas weree also docum mented.

If a land area or struccture was claassified as im mpacted, theen a determiination of thee initial imppacted area classsification (ee.g. Class 1, Class 2 or Class C 3) in aaccordance wwith MARS SSIM, sectioon 2.2 was made based upon n the inform mation obtain ned.

Initial cllassification of LACBW WR areas was w based oon historicaal informatioon and avaiilable historicall radiologicaal survey datta. Classify ying a surveyy area has a minimum oof two stages: (1) initial claassification and a (2) finall classificatiion. Initial cclassificationn of most arreas is perfoormed at the tim me of identifiication of thee survey area using the iinformation available whhen the HSA A was prepared. Final classsification iss performed and verifiedd as a DQO O during chaaracterizationn and FRS desiign. The ch haracterizatio on data was used to vallidate or upddate, as neceessary, the iinitial classificaations indicaated in the HSA H as descrribed in this Chapter. RRadiological survey data from continuin ng characteriization surveeys, operatio onal surveyss in support of decommiissioning, rooutine surveillan nce, and an ny other ap pplicable surrvey data m may cause an increasee in survey area classificaations (for ex xample, from m Class 3 to o Class 2 andd from Classs 2 to Classs 1) until thee time of comm mencement off the FRS.

2.1.2.2. Docum ment Review w Records maintained to satisfy the t requirem ments of 10 CFR Part 500.75(g)(1) pprovided a m major source off documentaation for thee HSA recorrds review pprocess. Durring the connduct of the HSA for LACB BWR, many y record typees were evalluated. A suummary of tthe types of records reviiewed include:

Operational O Review R Commmittee (ORC C) Meeting M Minutes, Safety Review w Committeee (SRC) Meeeting Minuttes, Licensee L Eveent Reports (LER) Summ maries, Site Initiated Incident Rep ports (IR),

Operator O Log gs including Reactor Opeerator and H Health Physiccs entries, Annual A Envirronmental Monitoring M Reports, R

Environmenta E al investigattions performmed by indeppendent entitties, Regulatory R acctions conceerning the sitte, Documentatio D on from interviews cond ducted with rretired/separrated site perrsonnel, Health H Physiccs surveys an nd sampling g results assoociated with identified evvents, Site inspectioon and surveiillance type documents aassociated w with identifieed events, Radiological R and environ nmental survey documennts, 2-4

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Quality Q Contrrol (QC) /Qu uality Assuraance (QA) fi finding type ddocuments.

2.1.2.3. Licenses, Permits and Authorizations LACBW WR was operaated in accorrdance with several Fedderal and Staate of Wiscoonsin licensees and permits. The NRC Operating License L for LACBWR aand supportting Techniccal Specificaations allowed Dairyland D Power Coopeerative (Dairryland) to usse any quanttity of radioaactive materrial at the site, to support operations o du uring its opeerating lifetiime, and to implement ddecommissiooning activitiess.

Several government g and regulato ory agencies have providded oversighht at LACBW WR during ssiting, licensingg, constructioon, operation ns, and decom mmissioningg. These ageencies includde:

United U Statess Atomic Eneergy Commiission (AEC C),

United U Statess Nuclear Reegulatory Co ommission (N NRC),

United U Statess Environmen ntal Protectiion Agency ((EPA),

Wisconsin W Deepartment off Natural Reesources (WD DNR),

Local/County L y Governmen nts.

From Au ugust 28, 197 73 to the preesent, the faccility has beeen operated uunder NRC License DPR R-45.

This periiod includess power opeerations to 1987, 1 permaanent shutdoown for deccommissioninng in 1987, and d ISFSI consstruction and d spent fuel off-load whiich was com mpleted in 20012.

2.1.2.4. Person nnel Intervieews Interviewws with curreent or previo ous employeees were perrformed to ccollect first-hhand inform mation about thee site and to verify or clarify inform mation gatherred from thee records thaat were revieewed.

The personnel interv views includ ded a combin nation of quuestionnairess completed by a majoriity of the particcipants as well w as indiviidual and gro oup interview ws with sevveral of the pparticipants. Key personneel were chossen due to th heir knowled dge of and aassociation with the sysstems and soource terms being investigated for the assessment.. A numberr of the perssonnel intervviewed possessed site knowwledge and experience e th hat ranged frrom the site cconstructionn period to shhutdown.

Between 2010 and 2011, apprroximately 40 4 recollectiions of inteerest were llogged from m the individuaals contacteed as part of the HS SA questionnnaire progrram. This consisted of a standardiized personn nel survey which w was completed c vvoluntarily bby retired/sepparated stafff and site persoonnel who worked w at the LACBWR R during its ooperational years. Withh few excepttions, the persoonnel observ vations docum mented on th he questionnnaire were ccorroboratedd either by loogged memories of other questionnaire q e completerss, current onn-site workiing staff thaat had LACB BWR operation nal period exxperience, orr by documentation discoovered durinng the recordds search.

2.1.2.5. Property Inspectio ons Several on-site prop perty inspecctions were made overr the coursee of the HS SA developm ment.

Several site s events off interest weere identified d which weree subsequenttly documennted in the H HSA.

2-5

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.1.3. Operational O History LACBW WR was a 50 5 Megawattt Electric (MWe)( Boilling Water Reactor thhat is owneed by Dairyland. This sing gle unit, also o known as Genoa G Statioon #2, is loccated on the east shore oof the Mississip ppi River so outh of the Village off Genoa, Veernon Counnty, Wisconssin. The site is borderedd on the no orth by the Mississippii River andd a narrow strip of laand betweenn the Mississip ppi River annd Highway 35. The licensed site c omprises a ttotal of 163.5 acres, witth the LSE com mprising app proximately 1.5 acres of the licensedd site. The LSE boundaary is fencedd and served ass the RCA boundary b duuring operattions. Mateerial leavingg the LSE w was surveyedd and confirmeed to be suittable for unrrestricted use before release. The ssite is accessed by an aaccess road on the t south sid de of the plannt. Other pro ominent feattures on the site include::

th he land north h of the LAACBWR plan nt, includingg the site sw witchyard annd the site oof the foormer Genoaa Station #1 (G-1) coal (and( later oill) fueled powwer plant (removed in 19989),

an n operationaal 350 MWe fossil generrating stationn (G-3) locaated south annd approxim mately 175 feet fromm the LSE, th he fenced ISF FSI facility that t is locateed directly soouth of G-3,, and a small parcel of land to thet east of Highway H 35, across from m LACBWR that is part oof the liicensed site.

The plan nt was one of a series of demonsttration plantts funded inn part by A AEC. The A Allis-Chalmerss Company was the oriiginal licenssee; the AEC C later soldd the plant tto Dairylandd and providedd them with a provisionall operating license.

LACBW WR achieved d initial critiicality on Juuly 11, 19677, and was operated foor approxim mately 19 years until it wass permanenttly shut dow wn by Dairyyland on Appril 30, 1987. Final reeactor defuelingg was complleted on Junee 11, 1987. The Dairylaand authorityy to operate LACBWR uunder Operating License DPR-45, D purrsuant to 100 CFR 50, w was terminat ated by Liceense Amenddment No. 56, dated d Augusst 4, 1987; anda a possesss but not-opperate statuss was granteed by NRC. The 333 irrad diated fuel asssemblies, which w were in i Fuel Elem ment Storagee Well (FES SW), were pplaced into five (5) dry caskks and transfeferred to the sites ISFSI by Septembber 2012.

Limited dismantleme d ent of shutdo own and unu used systemss and waste disposal operations has been ongoing at LACBW WR since 199 94. Waste stored s in thee FESW andd other Classs B/C wastee was shipped for disposall in June 20 007. The Reactor R Pressure Vessel (RPV) witth head instaalled, internals intact, and 292 control ro ods in place was filled w with concrette, removed from the Reeactor Building, and shippeed for dispo osal in Junee 2007. Othher systems and compoonents have been removed, including the t spent fueel storage raccks, Gaseouus Waste Dissposal System m (except foor the undergroound gas sto orage tanks)); Condensaate system and Feedwaater system m (except foor the Condensate Storage Tank and condenser); Turbine annd Generatoor; and Com mponent Coooling Water Sy ystem pumps, heat exchangers, pipin ng and compponents thatt were locateed in the Tuurbine Building.

2.1.4. In ncidents Based on n the revieww of existing plant reco ords (e.g. annnual and ssemi-annual reports, liceensee notificatiions, occurreence reportss, and questiionnaires), iincidents wiith radiologiical or hazarrdous 2-6

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 material implication ns occurred between th he commenccement of pplant operatiion in 19677 and placing the t reactor in n a SAFSTO OR condition in 1987. All of thesee incidents ttook place w within the LSE and, while contributing c to the radiollogical contaamination annd potential contaminatiion of the structtures and soils directly related r to thee operation oof the reactoor, were conntained withiin the LSE, which is alread dy known to be impacteed.

Special emphasis was w placed on o obtaining and revieewing the aannual Radiioactive Efffluent Monitoriing Reports (REMP), focusing fo on gaseous annd liquid relleases since 1967, incluuding reports covering c thee periods of o SAFSTOR R and decoommissioninng activitiess after the plant shutdown n in 1987. Available saampling resu ults associatted with soiil and grounndwater withhin or around th he plant sitee were also reviewed. The T objectivve was the iidentificationn of those eevents posing a significant probability p of o impacting g the radioloogical status or hazardouus material sstatus of LACB BWR site land areas and structu ures. Thesse included system, sttructure, or area contamin nation from system s failurres resultingg in airborne releases, liqquid spills orr releases.

2.1.4.1. Radioological Spillls The histtorical revieew indicated d that betweeen 1967 aand 1987, thhere were sseveral inciidents involving g system leaakages, radio ological spillls, and/or raddioactive liqquid effluent releases witth the potential to affect the classificatiion of LACB BWR structuures or soilss. The inciddents are listted in chronological order as a follows; The T stainless steel liner in the FESW W had a hisstory of leakkage to the R Reactor Buiilding flloor. Incidennts involving g leakage off the FESW w were noted ffrom 1967 too 2012.

In ncidents involving leakaage from thee resin regenneration wasste system tto the Circullating Water W Dischaarge line werre noted from m 1967 to 19973.

In n 1970, pottentially con ntaminated Control Rodd Drive (C CRD) oil waas used for dust suuppression on o the licenseed site roadss.

In n Septemb ber, 1977, removablee alpha ccontaminatioon was ddetected dduring decontaminattion of a Fo orced Circulation Pump (FCP) duriing maintenance involvving a stteam cleaninng tank in thee Reactor Bu uilding 701 ffoot elevatioon. (ORC, 009/27/77)

On O Novembeer 5, 1980, partial blockaage of drain lines under Turbine Buuilding resultted in th he potential for leakage of drain waater into the soil under thhe Turbine B Building. (DDPC-80-84 Inciden nt Report, OR RC-80-71, ORC-80-75, O ORC-80-877, ORC-80-997)

On O Novembeer 24, 1980, residual rad dioactive conntaminationn was detected in soils uunder th he Turbine Building.

B (D DPC-80-93 Incident I Repport, ORC-880-71, ORC--80-75, ORC C 87, ORC-80-9 97, LER 80--12)

On O Decemb ber 6, 1980, the Turb bine Buildding Waste Water T Tank overflowed appproximately y 1/2 gallon of waste water w to the Turbine Buuilding floorr. (DPC-800-102 In ncident Repo ort, ORC-80 0-71, ORC-80-75, ORC- 80-87, ORC C-80-97)

On O Decemberr 15, 1980, the t Turbine Building Waaste Water T Tank overfloowed waste w water in nto the Turbiine Building g Basement Tunnel.

T (DPPC-80-106 Inncident Repoort) 2-7

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 In ncidents invo olving leakaage of potenttially contam minated liquiid from the T Turbine Buiilding waste w water tanks t throug gh the normaal effluent reelease pathw way to the CCirculating WWater Discharge D lin ne were noted d from 1980 0 to 1986.

On O January 30, 1981, the Turbine Building Waste W Water Tank overflowedd and unnspecified volume v of waater into the laundry room m. (DPC-811-10 Incidennt Report)

On O May 31, 1982, a lid seal failed on o a spent rresin liner w which resulteed in the sppill of coontaminated d water and spent resin onto the flooor of the S Spent Resin Liner Room m and in nto the basemment. (DPC-82-51 Incid dent Report)

On O July 02, 1982, 1 approxximately 1,2 200 gallons oof condensatte water wass released frrom a siight flow seeal rupture to the Turbin ne Buildingg floor, and approximateely 20 galloons of coontaminated d water flowwed into the soils outsidde the Turbiine Buildingg door and T Truck Bay B door. In n addition, approximatel a ly 25 gallonss of contam minated liquidd was dischaarged to o an unrestricted area. (D DPC-82-58 Incident I Repport, LER 822-016)

On O July 16, 1983, a leak k in the Seaal Water Inj njection Systtem leak at 1A FCP caaused appproximately y 15,000 galllons of reacctor coolant to be dischaarged to the Reactor Buiilding basement floo or. (LER 83 3-07) 2.1.4.2. Chemmical Spills Between 1967 and 20 014, the HSA A documentted several inncidents invvolving the uunplanned sppill or release ofo chemicalss and/or poteentially hazaardous liquidds to the ennvironment. These inciidents ranged frrom spills off acids and caustics c usedd in the plannts various systems to tthe spill of ddiesel and fuel oil from sy ystems and storage tank ks. A majoority of the incidents occcurred insidde of impacted d buildings. These spillss were contrrolled and reemediated inn accordancee with the sttation policies and proced dures for id dentificationn, control aand remediaation of hazzardous maaterial releases.

2.1.5. Findings F andd Conclusions LACBW WR was desig gned with mu ultiple bound daries to conntrol and conntain the raddioactive conntents within itss many systeems, compon nents, and sttructures. M Many of thesee systems annd structures have been imp pacted due tot routine op perations annd maintenannce activitiees during thee operationaal and post opeerational history of the plant. Daiiryland LAC C-TR-138, IInitial Site Characterizzation Survey fo or SAFSTOR R (7) identifiied historicaal failed fuel incidents att LACBWR and the poteential for fissio on products tot enter and impact i reacttor and support systems.

Structurees classified as impactted by the operation oof the facilitty include R Reactor Buillding, Turbine Building, WTB, W Low Specific S Acttivity (LSA)) Building, WGTV, andd the Ventillation Stack. In n addition too the structurres, the soilss surroundingg these builddings have aalso been deemed to be direectly impacteed by the op peration of thhis facility. T This area is defined by tthe LSE fencce.

An area surrounding s the LSE has also been designated d aas impacted. This area iincludes anccillary support buildings b su uch as the LACBWR L Crib House, L LACBWR A Administratiion Buildingg and various warehouses w and a storage buildings.

b 2-8

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 In additiion to the area a within the LSE an nd the open land areas surrounding the LACB BWR support buildings, the t open lan nd immediaately surroun unding the L LSE fence is designateed as impacted d to provide a buffer zon ne between thet LSE andd the G-3 lannd and facillities south oof the LSE whiich is consid dered non-im mpacted. Th he licensed ssite comprisees a total off 163.5 acress with the LSE areas comprrising approx ximately 1.5 acres of thee owner conttrolled area.

2.1.6. In nitial Surveey Areas/Un nits and Classsification As part of o the HSA process, p the impacted i ACBWR struuctures and oopen land arreas were divvided LA into preliiminary surv vey areas an nd assigned area classifiications baseed on the opperational hiistory and existting survey data.

d 2.1.6.1. Survey Areas The entirre 163.5 acrres licensed site was div vided into suurvey areas.. Survey arreas are typiically larger phhysical sectioons of the sitte that may contain one or more surrvey units deepending onn their classificaation. Surv vey area sizee was deterrmined baseed upon the specific arrea and the most efficient and practiccal size need ded to boun nd the lateraal and vertiical extent oof contaminnation identifiedd in the areaa. Survey arreas that hav ve no reasonnable potential for residuual contaminnation were classsified as non-impacted d. These arreas have noo radiologicaal impact froom site operaations and are iddentified in the HSA. Survey S areas with reasonnable potentiial for residuual contaminnation were classsified as im mpacted. Figure F 2-1 provides p an iillustration oof the LACB BWR site annd the current classificationns by area.

2.1.6.2. Survey Units The surv vey areas werre further divided into su urvey units. A survey uunit is a porttion of a struucture or open land l area thaat is surveyeed and evalu uated as a sinngle entity ffollowing FR RS. Survey units were deliineated to ph hysical areass with similaar operationaal history or similar poteential for ressidual radioactiv vity to the extent e practical. To the extent pracctical, surveyy units weree establishedd with relatively y compact sh hapes and highly irregulaar shapes weere avoided uunless the unnusual shapee was appropriaate for the siite operation nal history orr the site top ography.

The surv vey units esttablished by the HSA were w used as initial surveey units for characterizaation.

Prior to characterizaation, survey y unit sizes for f Class 1 oopen land suurvey units were adjustted in accordan nce with the guidance g pro ovided in MARSSIM, seection 4.6 foor the suggessted physicall area sizes for survey unitss for FSS.

The deco ommissionin ng approach that will bee implementted at LACB BWR calls for the com mplete segmentaation, remov val and dispo osal of all immpacted sysstems and abbove-grade structures. With the excep ption of structure basem ment floors an nd walls thatt reside 3 feeet below graade, no portiion of any struccture will reemain at sitte closure and a consequuently, be suubjected to FRS. How wever, survey units u have beeen establish hed for strucctures to faccilitate otherr characterizzation objectives.

These ob bjectives incclude provid ding survey data d for rem mediation plaanning, estim mating the w waste volume contained c onnsite, and dissposition opttions for the waste.

In additioon, the surveey units estab blished for structures s thaat are 3 feet below gradee are intendeed for the purpo ose of charaacterization planning p andd do not corrrespond to the survey uunits that w will be 2-9

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 used for the FRS of remaining g below grad de structurees (designateed as STS aand discussed in section 5.5.2 of Chap pter 5).

Tables 2--1 and 2-2 provide p a deetailed list of o the surveyy units for bboth the opeen land areas and impacted d structures respectively y. Figure 2-2 2 provides a detailed innventory of the buildingg and site strucctures. A sum mmary of th he survey uniit classificatiions are pressented as folllows.

2.1.6.3. Class 1 Open Lan nd Areas The follo owing open land l areas haave been claassified as im mpacted Classs 1:

Reacttor Building g, WTB, WG GTV, Ventilaation Stack G Grounds (L1010101),

Turbiine Buildin ng, Turbine Office Bu uilding, 1B Diesel G Generator Buuilding Groounds (L1010102),

LSA Building, Maintenance M Eat Shack Grounds G (L10010103),

North h LSE Area (L1010104).

The basiss for this claassification iss due to a series of docummented inciddents of the contaminatiion of soil by radioactive r material m in these t areas during facillity operationns. These iincidents include spills of radioactive liquids and d resins, radiioactive sysstem leakagee, and storagge of radioaactive packagess and contain ners.

Based on n an assessmment of historrical inciden nts and eventts, it was annticipated thaat the surface and subsurfacce soils in th hese areas could c possiblly contain reesidual radiooactive mateerial in exceess of the unresstricted use criteria.

c Classs 1 open lannd survey unnits are showwn on Figuree 2-1.

2.1.6.4. Class 2 Open Lan nd Areas The follo owing open land l areas were w classifieed as impacteed Class 2:

LACB BWR Adm ministration Building, LACBWR R Crib Hoouse, Wareehouse Groounds (L2011101),

G-3 Crib C House, LACBWR Circ. Water Discharge L Line, Area SSouth of LSE E Fence Groounds (L2011102).

Based up pon a review w of the histtorical inform mation and operational radiation annd contaminnation surveys performed p n these areaas as documeented in the HSA, theree was a poteential for ressidual in radioactiv ve contamin nation to exceed the unreestricted releease criteria.

Class 2 open o land surrvey units arre shown on Figure 2-1.

2.1.6.5. Class 3 Open Lan nd Areas The follo owing open land l areas were w classifieed as Class 3 :

North h End of Liccensed Site (L L3012101),

Transsmission Sw witchyard Areea (L301210 02),

Plantt Access, ISF FSI Haul Road Grounds (L3012109)).

2-10

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Historicaal informatio on contained d in the HSA A indicated thhat the preseence of residdual radioacctivity in concen ntrations in excess e of thee unrestricted d release cri teria was noot expected.

Class 3 open o land surrvey units arre shown on Figure 2-1.

2.1.6.6. Non-IImpacted Op pen Land Areeas Based on n a review of the operatiing history of o the facilityy and historrical incidentts as documented in the HS SA, the balaance of the 163.5 acre liicensed site has no reassonable poteential for ressidual contamin nation and haas been desig gnated as noon-impacted..

G-3 Coal C Plant Grounds G (L40 012103)

Coal Pile Ground ds (L4012105)

Capp ped Ash Impoundment Grounds G (L40012106)

Grou unds East of Highway H 355 (L4012107)

Hwy 35/Railroad d Right of Way W Grounds (L4012108))

The non--impacted op pen land surv vey units aree shown on F Figure 2-1.

2.1.6.7. Class 1 Structuress The follo owing is a liist of the major m buildinngs that weree initially cllassified as impacted Cllass 1 structures. The com mplete list off all impactted structuraal survey unnits is providded in Tablee 2-2.

These strructures con ntain the nucclear reactorr, primary reeactor system ms, reactor support systems, radioactivve waste sy ystems, and nuclear n fuell handling aand storage ssystems. During operattions, radioactivve material was routineely handled,, transferredd, and storedd within theese buildings. A majority of the curren nt radioactiv ve material innventory at L LACBWR rresides in theese structurees:

Reacttor Building g (B1010001)

Wastte Treatmentt Building (B B1010002)

Ventiilation Stack k (B1010003 3)

Wastte Gas Tank Vault (B101 10004)

Turbiine Building g (B1010005 5)

Dieseel Generatorr Building (B B1010006)

LSA Building (B B1010007)

Main ntenance Eat Shack (B10 010008)

Througho out facility operations, o th hese structurres were subbjected to spiills of radioaactive liquidds, the spread of loose surfface contamination, and d airborne raadioactive m material. Sttructural surrfaces were rou utinely postted as conttaminated areas.a The decommissioning appproach for these structures involves the compleete segmenttation, remooval, and ddisposal of all systemss and structural material ass waste. Wiith the excep ption of struuctural floors and walls that reside 3 feet below grrade, no porrtion of these structures will remaain at site cllosure and aare thereforre not subjectedd to FRS. Th he Class 1 sttructural surv vey units aree depicted inn Figure 2-1.

2-11

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 2.1.6.8. Class 2 and 3 Stru uctures The folloowing is a liist of some of the majorr buildings tthat were innitially classiified as imppacted Class 2 oro 3 structurres. All aree located wiithin the liceensed site bbut outside oof the LSE. The completee list of all im mpacted stru uctural survey units is proovided in Taable 2-2.

LACB BWR Crib House H (B201 10101)

G-3 Crib C House (B2010102)

(

LACB BWR Administration Bu uilding (B20 010103)

LACB BWR Wareh house #1 (B2 2010104)

LACB BWR Wareh house #2 (B2 2010105)

LACB BWR Wareh house #3 (B2 2010106)

Backk-up Control Center (B30 012101)

Transsmission Sub b-Station Sw witch House (B3012102))

G-1 Crib C House (B3012103)

(

Bargee Washing Break B Room (B3012104))

These strructures did not routinely y house radiioactive systtems or mateerials duringg operations. The structures associated d with LAC CBWR listed d above are outside of the LSE buut were useed by LACBW WR workers and therefore considereed Class 2 or 3. The G-1 Crib H House and B Barge Washing g Break Room m were not associated a with w LACBW WR operationns but are coonsidered Cllass 3 structures because th hey reside in i a Class 3 land area. With the exception oof the LACB BWR Administtration build ding, the G-3 3 Crib Housse and the T Transmissionn Sub-Statioon Switch H House, the decom mmissioning g approach calls c for the complete seegmentation,, removal, annd disposal of all LACBW WR Class 2 orr 3 systems and structurral material aas waste or salvage. Noo portion of these structures will remain n at site clossure and therrefore will not be subjected to FRS.

The LAC CBWR Adm ministration building, b thee G-3 Crib HHouse and thhe Transmisssion Sub-Sttation Switch House H will not n be subjected to FR RS. Insteadd, these struuctures will be surveyed for unrestrictted release using a grraded survey y approach using the guidance of NUREG-1575, Supplem ment 1, Multii-Agency Ra adiation Surrvey and Asssessment of Materialss and Equippment Manual (MARSAME) (8). Thee Class 2 an nd Class 3 sstructural suurvey units for buildinggs are depicted in Figure 2--1.

Based on n a review of the operatiing history of o the facilityy and historrical incidentts as documented in the HSA, H coup pled with the t results of charactterization suurveys (as summarizeed in section 2.3.5),

2 the bu uildings asssociated with h the G-3 sstation have no reasonaable potentiaal for residual contaminatio on and havee been desig gnated as noon-impacted.. The G-3 sstation, incluuding the G-3 Crib C House, will remain intact and fu unctional forr G-3 powerr operations.

2.2. Characteriza C ation Appro oach From Occtober 2014 through Aug gust 2015, site s characteerization of L LACBWR w was performmed in accordan nce with th he Characteerization Su urvey Plan. The Chharacterizatioon Survey Plan 2-12

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 incorporaated the preevious histo orical operaational and radiologicall informatioon collectedd and documen nted in the su urvey areas from the HS SA and prevvious site characterizatioon efforts. It was developeed to providee guidance and a direction n to the perssonnel respoonsible for im mplementingg and executing g characterizzation survey y activities. The Plan w worked in conjunction w with implemeenting procedurres and survey unit speccific survey instructionss (sample pllans) that w were developped to safely annd effectively y acquire thee requisite ch haracterizati on data.

Characterization dataa acquired th hrough the execution e of the Plan waas used to m meet three priimary objectivees:

Proviide radiologiical inputs necessary n forr the design oof FRS, Deveelop the requ uired inputs for f LTP, and d Support the evaaluation of remediation r alternativess and technnologies andd estimate w waste volummes.

The deco ommissionin ng approach for LACBW WR calls for tthe demolitiion and remooval of all onn-site buildingss, structures,, and compo onents to a depth d of at lleast 3 feet bbelow gradee. Consequeently, characterrization effo orts focused d on open land areas and remainning structuures that wiill be subjectedd to FRS. Extensive E chharacterizatioon of equipm ment, system ms or structtures that will be removed prior to thee performancce of final surveys s is noot required iin accordancce with NUR REG-1757, Ap ppendix O.

The charracterization n surveys fo ocused on general g openn land areass including: site surfacee and subsurfacce soils, pavved surfaces,, and concrette pads. Cooncrete core samples werre taken from m the structural basementss that will reemain in thee end-state condition. In addition,, characterizzation surveys were w perform med in the LACBWR L Ad dministrationn Building aand several oof the G-3 sttation structures. Upon com mpletion, thee data was assessed for qquality and aadequacy. T The data wass then used to make m determ minations on whether w addditional charaacterization data is requuired, primarily of above grrade or subgrade structu ures, surface and subsurfface soils, orr beneath thhe concrete ffloors of the exxpected end--state structu ures at LAC CBWR. Conntinuing chaaracterizationn surveys w will be planned, executed an nd documen nted with thee same data quality andd the results included inn FRS planning.

A signifiicant questio on that must be answereed by the chaaracterizatioon is whetheer or not a suurvey unit is claassified corrrectly. The appropriate a classification c n of a surveyy unit is crittical to the suurvey design fo or FRS. A classificatio on which un nderestimatees the potenntial for contamination ccould result in a survey dessign that doees not obtain n adequate innformation too demonstraate that the suurvey unit meetts the releasee criteria. In n some casess, this can inncrease the ppotential for m making deciisions errors.

As site-specific Deriived Concen ntration Guid deline Levells (DCGLs) were not yeet establisheed for LACBW WR at the tim me the charaacterization survey was performed, alternate acction levels were selected. The screen ning DCGLss presented in i NUREG-11757 and the concentrattion values ffound in NURE EG/CR-5512 2 Volume 3, Residual Radioactive R Contaminaation from D Decommissiooning Parameteer Analysis (9), Table 6.91 (Pcrit = 0.10)0 for soills were usedd as alternate action leveels to assess thee correct claassification of o impacted openo land orr soil survey units.

2-13

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 For strucctures, the grross screeninng level thatt was used dduring charaacterization aas an action level to evaluate the classsification of o survey units u was thhe nuclide-specific scrreening valuue of 7,100 dpm m/100cm2 to otal gross beeta-gamma surface s activvity based onn Co-60 fromm NUREG-1757, Appendix x H. Use off the Co-60 screening valuev was coonservative aas it was annticipated thaat the radionuclide distribuution for surfface contam mination wouuld be princiipally Co-600 and Cs-1377 and the conseervative apprroach was to o assume a distribution d oof 100% Co-60 since thee screening vvalue for Cs-1337 is significcantly greateer.

2.2.1. Data D Qualityy Objectivess DQOs were w implemeented for ch haracterizatioon surveys inn a similar m manner as annticipated foor the FRS. Ho owever, the goal of charracterization n is to quantiify and delinneate contamminated areaas and to determ mine the radionuclide mixture, m wherreas the FRS S goal is coomparison off data againsst the unrestrictted use critteria to dem monstrate co ompliance w with 10 CFR R 20.1402. Characterizzation inspectio ons and surv veys of sufffficient qualiity and quaantity were performed tto determine the nature, extent and raange of radio oactive conttamination inn each appliicable surveey unit, incluuding applicablle structures, residues, sooils and surfface water.

Characterization surv veys were deesigned to gather g the appropriate daata using thee DQO proceess as outlined in MARSSIM M, Appendiix D. The seeven steps inn the DQO ddevelopment process are::

1) State the problem m,

2) Identtify the decission,

3) Identtify inputs to o the decision n,

4) Defin ne the study boundaries,

5) Deveelop a decisio on rule,

6) Speciify limits onn decision errrors, and

7) Optim mize the design for obtaiining data.

The DQO Os for site characterizaation includeed identifyinng the typess and quantiities of meddia to collect. No N structurees located ab bove 3 feet below b grade will remainn following ddecommissiooning and will therefore no ot be subjected to FRS. Consequenttly, sample ccollection waas focused oon the assessmeent of concreete in basem ments and su urrounding sooils. Buildiing concretee was sampleed by obtainingg core samp ples. Soils were samplled volumettrically. Suufficient measurements were obtained to determin ne the mean and maximu um activity aas well as thhe sample staandard deviaation.

Direct measurement m s and scanss of surface soils were made usingg the same instrumentss and Minimal Detectable Concentrations (MDC) as will be eemployed foor FSS. Volumetric sam mples that exhiibited the hiighest activiity were sen nt to an off--site laborattory for analysis of Harrd-to-Detect (H HTD) radion nuclide(s).

2.2.2. Survey Desig gn Characterization surrveys were designed and a perform med in accoordance witth all appliicable approved d proceduress and the Chaaracterizatio on Survey Pl an. Survey design incorrporated a grraded approachh based upon n the DQOs for f each surv vey unit. Foor example, an open landd survey uniit was 2-14

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 designateed as Class 1 because itt may contaain levels off radiologicaal contaminaation greaterr than the unresstricted releaase criteria. Therefore, the t characterrization survveys that werre performedd in a Class 1 survey s unit focused f on bounding b thee contaminattion where contamination was potenntially present. The survey design was based upon n the numberr of measureements and samples reqquired to identiffy the laterall and verticaal extent of th he contaminnation. Areaas classified as non-impaacted, Class 2 oro Class 3 reeceived surv veys develop ped to includde a combinnation of ranndom and bbiased survey measurement m locations annd scan areas. Biased suurvey designns used know wn informatiion to select loccations for static s measu urements and d/or sampless. Random survey desiggn selected static measurem ment and/or sample loccations at ran ndom. Thee decision off whether too use primarrily a biased su urvey design n or a random m approach was addresssed by the D DQO processs for each suurvey unit. A biased app proach was warranted when the ccharacterizattion effort w was designeed to delineatee the extent of o an area th hat requires remediationn. Alternativvely, a randoom approachh was warranted if the charracterization effort was designed d to vverify the baasis for the cclassificationn of a survey un nit.

The areaas and materials surveyeed and/or sam mpled in andd around thee licensed arrea as part oof the characterrization surv vey included:

Surface scanss and random m and biased d surface andd subsurfacee soils sampples were takken in alll Class 1, 2, 2 3, and no on-impacted open land aarea survey units with the exceptioon of su urvey unit L3012102 L (i.ee., the switchhyard).

Biased B subsurrface soil saamples were taken alonggside and underneath undderground ppiping sy ystems of concern in Class C 1 and 2 areas inclluding the ppiping systems as show wn on Figure 2-3.

Random R sammples were taaken from asphalt a and cconcrete from m pads and paved areas. In adddition, soil samples weere obtained directly beloow the asphaalt to a one m meter depth.

Scans and samples werre taken on n accessiblee roof surfaace areas off the LACB BWR Administratio A on Building and the G-3 Coal Plant.

Samples weree taken from m the septic taanks.

Scans and sam mples were taken on LA ACBWR Addministrationn Building suurfaces and drain arreas.

Scans and sam mples were taken t on G-33 Building aaccess and heeavily travelled surfaces.

Concrete C sam mples were taken in the basement arreas of the R Reactor Building, WTB B, and Piping and Ventillation tu unnels.

A backgroun nd radiation study was performed on materialls similar too those founnd at LACBWR L including: asp phalt, concrette, and soil.

2.2.2.1. Numb ber of Static Measuremen nts and/or S amples The num mber of measu urements an nd/or samples that were ttaken in eachh survey uniit was determ mined by assesssing the sample size neceessary to sattisfy the DQO Os.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 For the characterizat c tion of impaacted Class 1 and Class 2 open landd areas (pavved and unpaaved) that will be subjecteed to FSS, th he minimum m number off random orr biased direect measurem ments and/or saamples taken n in the surveey units werre commensuurate with thhe probabilitty of the pressence of residual radioactiv ve contaminaation in the survey s unit.

For the characterizaation of Class 1 structurres that wil l remain annd be subjeccted to FRS S, the sample size s was bassed upon thee necessary number n of ssamples neeeded to assesss the lateraal and vertical extent e of the contaminatiion.

For non-impacted an nd Class 3 op pen land surrvey units, thhe primary ccharacterizattion DQO w was to validate the basis of the classsification. Consequenntly, the nuumber of ssystematic static measurem ments and/o or samples wasw sufficieent to ensuree with reasoonable conffidence that only trivial levvels of licen nsee-generatted radionucclides are prresent in Cllass 3 areas and no liceensee-generated d radionuclid des are preseent in non-im mpacted areaas.

2.2.2.2. Determ mination of Static Measu urement andd Sample Loocations For the characterizat c tion of non--impacted an nd impactedd open land areas and C Class 2 strucctural survey units that willl be subjectted to FRS, sample locaations were primarily chhosen at ranndom.

Sample locations l weere determined by generating random m pairs of coordinates that correspoonded to specifiic locations within w the suurvey unit. The T locationn of biased m measurementts and/or sam mples that werre taken in each survey unit was determinedd by the prrofessional jjudgment oof the responsib ble Radiolog gical Protecttion Superv visor and/or the Project Health Phyysicist durinng the survey design d proccess. Consideration was w given to locationns that exhhibit measuurable radioactiv vity, depressions, disco olored areas,, cracks, low w point gravvity drain ppoints, actuaal and potential spill locatio ons, or areass where the ground hass been disturrbed. Histoorical inform mation from the HSA aided in the selecttion of biased d locations.

2.2.2.3. Scan Coverage C

Survey units u were sccanned to th he extent practical in acccordance w with their claassification. The area to be b scanned in each survey unit was determinedd during the survey desiign process. The area scan nned was contingent up pon the pro ofessional juudgment of the Radioloogical Proteection Supervisor and/or the Project Heealth Physicist during thhe survey deesign process. Considerration was giveen to inform mation from the initial walk w downs and the am mbient radiattion levels iin the survey un nit.

2.2.2.4. Typess of Measureements and Samples S

The charracterization n survey of building surrfaces consiisted of a coombination of surface scans (beta andd gamma); sttatic beta meeasurementss, material saamples and ssmears. Thee characterizzation survey off any concreete and/or asphalt-paved open land aareas that wiill remain annd be subjectted to FRS con nsisted of a combination c n of surface scans (beta and gammaa), static betta measurem ments, and volu umetric samp ples. The su urvey of thee open land areas consissted of gamm ma scans annd the sampling g of surface and subsurfface soil, sed diment and ssurface wateer for isotoppic analysis. The following g is a descripption of the different d pes of measuurements andd samples thaat were utilizzed.

typ 2-16

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 2.2.2.4.1. Gamm ma Surface Scans S

Gamma scans were performed over o open laand surfaces to identify locations off residual suurface activity. Sodium iodide (NaI) gamma g scin ntillation dettectors (typiccally 2 x 2) were typiically used for these scans. EnergySolutions Techn nical Supporrt Documentt (TSD) RS--TD-3131966-006, Ludlum Model M 44-10 0 Detector Sensitivity (10)

( examinnes the response and sccan MDC oof the Ludlum Model M 44-10 0 NaI detecto 0 and Cs-1377 when usedd for scanningg surface soiils.

ors to Co-60 Scanning g was perforrmed by mo oving the deetector in a sserpentine ppattern, whille advancingg at a rate not to t exceed 0..5 m (20 in) per second. The distannce betweenn the detectoor and the suurface was main ntained with hin 15 cm (6 in) of the surface if po ssible. Auddible signals were monittored; and, locaations of elev vated direct levels l were flagged f for ffurther invesstigation andd/or samplingg.

2.2.2.4.2. Beta Surface S Scanns Scanning g was perrformed in order to locate arreas of ressidual activvity above the 7,100 dpm m/100cm2 action a level. Beta scanss were perfoormed over aaccessible sttructural surrfaces includingg, but not liimited to; flloors, walls,, ceilings, rooofs, asphallt and concrrete paved aareas.

Hand-helld beta scin ntillation and ow proportioonal detectoors (typicallyy 126 cm2) were d/or gas-flo used.

Beta scan nning was performed p with w the detector positionn maintainedd within 1 ccm of the suurface and with h a scanning g speed of oneo detectorr active winndow per seecond. If suurface condiitions prevented d scanning ata the speciffied distancee, the detecttion sensitivvity for the aalternate disstance was deteermined, an nd the scan nning techniique adjusteed accordinngly. Scannning speed was calculated a priori too ensure thatt the MDC forf scanningg was approppriate for thee stated objeective of the surrvey.

If not im mpacted by high h ambientt noise levels, technicianns monitoredd the audible response oof the instrumen nt to identify locationss of elevated activity th that require further investigation aand/or evaluatioon. Any ideentified areass of elevated d contaminaation were m marked or flaagged for fuurther investigaation and pottential deconntamination.

2.2.2.4.3. Directt Measuremeents Direct measurement m ts were perrformed to detect total levels of contaminatiion on strucctural surfaces of the build dings or on o asphalt paaved areas. These measurements were n concrete or typically performed using ~10 00 cm2 or larger sized scintillatioon or gas-fllow proporttional detectorss.

Direct measurements m s were condu ucted by plaacing the dettector near tthe surface too be countedd and acquiringg data over a pre-determ mined coun nt time. A count time of one to ttwo minutess was typically used for suurface measu urements and d generally pprovided dettection levells well below w the designateed investigattion level orr MDC under consideraation. The iinstrument ccount times were adjusted as appropriaate to achiev ve an acceptaable MDC foor direct meaasurements.

2.2.2.4.4. Remo ovable Surfacce Contamin nation If applicable, remov vable beta an nd/or alpha contaminati on or smearr surveys w were perform med to verify looose surfacee contaminaation is lesss than the applicable action levell. A smeaar for 2-17

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 removable activity was w usually taken at eacch direct meeasurement llocation on non-asphaltt type surfaces. A 100 cm m2 surface areaa was saampled withh a circular cloth or paaper filter, uusing moderatee pressure. Smears S weree then analyzzed for the ppresence of ggross beta annd/or gross alpha activity as a appropriatte.

2.2.2.4.5. Concrrete and Asp phalt Core Saampling Concretee core boring g and the saampling of concrete weere used to assess the ddepth of surrficial contamin nation and th he presence of volumettric contami nation in cooncrete wallls and floorss that will remaain and be su ubjected to FRS.

F Core bore b samplinng of concreete was accoomplished ussing a diamond bit core driill. The con ncrete sample producedd by the coriing was typpically slicedd into 1/2-inch wide w puckss, represen nting a certaain depth innto the surfface. Conccrete pucks were pulverizeed and analy yzed for isoto opic content..

2.2.2.4.6. Materrial Sampling g Samples of soil, sediment, and sludges were obtained frrom designedd biased andd random saample locationss as well as other locatio ons in areass exhibiting elevated acttivity that wwere identifieed by scanning g. Surface so oil is defined d as the top 15 cm (6-innch) layer off soil while ssubsurface ssoil is defined asa soil beloww the top 15 cm layer in n 1 m increm ments. Surfaace soil was collected ussing a split spooon sampling g system or, byb using han nd trowels, bbucket augerrs, or other ssuitable sammpling tools.

Subsurfaace soil was sampled by y direct pushh sampling ssystems (e.gg. GeoProbe) or by manual hand aug gers. Subsurrface soil sam mpling was performed aas necessaryy to address tthe DQOs foor the survey un nit.

2.2.3. In nstrumenta ation Selectio on, Use andd Minimum Detectable Concentrattions (MDC Cs)

The radiation detecttion and measurement instrumentattion for charracterizationn was selectted to provide both b reliablee operation and a adequatee sensitivity tto detect thee initial suitee of radionucclides identifiedd for the deecommission ning of LAC CBWR at leevels sufficiiently below w the establlished action leevels. Detecctor selectio on was based d on detectiion sensitiviity, operatinng characteriistics, and expeected perform mance in the field. In all cases, thhe instrumennts and detecctors selecteed for static meeasurements and scanning were cap pable of dettecting the aanticipated R Radionucliddes of Concern (ROC) at a MDC of 50%  % of the appplicable actioon level.

Commercially availaable portablee and laborattory instrum ments and dettectors were typically ussed to perform the three baasic survey measuremen m ts: 1) surfacce scanning; 2) static meeasurementss; and

3) analyssis of materiaal samples.

Instrumentation and nominal MD DC values thhat were em mployed durinng characterrization are listed in Table 2-3.

2.2.3.1. Calibrration All data loggers, asssociated deteectors, and alla other porrtable instrum mentation thhat were useed for characterrization werre calibrated d on an annu ual basis ussing Nationaal Institute oof Standardss and 2-18

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Technolo ogy (NIST) traceable t sou urces. The calibration c oof instrumentts used for ccharacterizatiion is addressed d in the QAP PP.

2.2.3.2. Instru ument Use an nd Control The receiipt, inspectioon, issue, control, and acccountabilityy of portablee radiologicaal instrumenttation used for characterizaation was performed p in n accordancee with issuee and controol procedurees for portable radiologicaal instrumen ntation. The T issue aand controll of instruuments usedd for characterrization is ad ddressed in th he QAPP.

2.2.4. Laboratory L Instrument I Methods an nd Sensitiviities Gamma spectroscop py was prim marily perforrmed by thhe on-site raadiological laboratory. Gas proportioonal countin ng and liquid d scintillatio on analysis was perform med by an approved veendor laboratorry in accordaance with ap pproved labo oratory proceedures. EnerrgySolutionss ensured thaat the quality programs p of the contraccted off-site vendor labooratories thaat were usedd for the recceipt, preparatiion and analy ysis of charaacterization samples s provvided the sam me level of quality as thhe on-site laborratory under the QAPP.

In all caases, analytiical methodss were estab blished to eensure that required M MDC values were achieved d. The anallysis of rad diological co ontaminants used standdard approveed and geneerally accepted methodolog gies or otheer comparab ble methodoologies. Taable 2-4 provvides the tyypical analyticaal methods employed and the laaboratory M MDC achievved by the off-site veendor laboratorries used for characterizaation.

2.2.5. Quality Q Assuurance MARSSIIM, section 2.2 discussees the need for f a qualityy system to ensure the aadequacy off data used to demonstratee that site conditions c arre acceptablle for unresstricted release. Laborratory quality for fo sample an nalysis takenn to supportt characterizzation and F FRS is discussed in NUR REG-1576, Mu ulti-Agency Radiologica R al Laboratoryy Analyticall Protocols M Manual (MA ARLAP) (11) and Regulato ory Guide 4..15, Qualityy Assurance of Radioloogical Moniitoring Proggrams (Incep eption through Normal Operations to License Terrmination) - Effluent Sttreams and the Environnment (12). Fu urther, MAR RSSIM and MARLAP both b indicatee that a Quaality Assuraance Project Plan may be used in add dition to, orr in lieu of, existing quuality system ms to ensurre data quality is achieved d.

The QAP PP was prep pared and im mplemented to t ensure th e adequacy of data beinng developedd and used duriing the site characterizat c tion and FRS S process. T The QAPP deescribes poliicy, organizaation, functionaal activities, the DQO prrocess, and measures m neccessary to acchieve qualitty data.

All charaacterization activities esssential to data d quality wwere implem mented and performed uusing approved d proceduress. The effeective implementation oof characteriization was verified thrrough audit anda surveilllance activ vities, inclluding fielld walk-doowns by EnergySoluutions Characterization stafff and progrram self-asssessments, aas appropriatte. Correcttive actions were prescribeed, implemeented, and verified v whhen deficienccies were iidentified. These meaasures applied to any app plicable serv vices provid ded by off--site vendorrs, as well as on-site sub-contractoors.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 The Chaaracterization n Survey Pllan was dev veloped accoording to thhe essential elements oof the quality assurance a andd quality co ontrol (QA/Q QC) program m for the deccommissioniing of LACB BWR and is su ubject to the QAPP. Thee QA/QC program elem ments applicaable to charaacterization aare as follows:

Establishmen E nt/implementtation of plan ns, procedurres, and prottocols for thee field opperations.

Actions A to en nsure that thee procedures are understoood and folllowed by thee implementiing sttaff.

Documentatio D on of the datta collected.

Details of o the QA/QC C elements specific s to ch haracterizatiion are preseented in the Q QAPP, as w well as the proceedures and sample s plan instructions. The charaacterization ooperations annd the assocciated data acqu uisition and d recording was guided d and conduucted in com mpliance wiith these QA A/QC requiremments. The sp pecific QA/Q QC program m component s for site chaaracterizatioon are as follows:

Personnel quaalifications, experience, and trainingg.

Execution E in accordance with approv ved procedurres.

Proper docum mentation of survey data and sample analyses.

Selection of appropriate a instruments i to t perform thhe surveys.

Proper instrum ment calibraation and daiily functionaal checks.

Management M oversight off characterizzation activitties relative tto the adhereence to prrocedures, protocols, p and documentaation requireements.

All charaacterization activities were w conductted in accorrdance with the Charactterization Suurvey Plan, the QAPP, all applicable a im mplementing g procedures , and approvved sample pplan instructions.

2.3. Summary off Characteriization Surv vey Results In Octobber of 2005, Dairyland performed p a limited chaaracterizationn survey of the LSE priior to placing the t unit into o a SAFSTO OR condition n. This surrvey is docuumented in Reference 77. In October of 2014, Dairyland contracted EnergySollutions to perform a more dettailed characterrization of LACBWR L in n anticipationn of the deveelopment off this LTP annd the anticippated accelerattion of decommission ning activitiies. Charracterizationn activities,, performedd by EnergySo olutions in accordance a with w EnergyS Solutions chaaracterizatioon procedurees commenceed on October 9,9 2014. The T scheduleed EnergyS Solutions sitte characteriization effoort concludeed on August 6, 6 2015. Thee results of th he site charaacterization ssurveys perfformed by EnnergySolutioons is documen nted in two o separate reports, GG G-EO-3131996-RS-RP-001, LACBW WR Radioloogical Characteerization Surrvey Report for Octoberr and Novem mber 2014 F Field Work ((13) and LC C-RS-PN-1640 017-001, LACBWR Radiiological Ch haracterizatiion Survey R Report for JJune thru August 2015 Fieeld Work (14 4).

Radioacttive systemss that remaain at LAC CBWR affeccted the ability to acqquire meaniingful characterrization data in certain n areas du ue to ambieent radiatioon levels. In these ccases, characterrization has been deferreed until such h time that raadiological oor physical cconditions w would 2-20

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 allow thee survey of these survey units. Solutions intendss to continuee characterizzation througghout the decom mmissioning g process, inncluding folllowing the ssubmittal of this LTP. IIn the case w where significannt additional characterizzation data isi obtained, this chapterr of the LTP P will be updated by revisioon or addenddum as a parrt of the requ uired 2 year update of thhe approved LTP.

2.3.1. Background B Study During the t initial ch haracterization survey performed p inn October 2005, Dairyland perform med a backgrou und study foor soils at LA ACBWR. Reference R 7 states that a series of soil samples were acquired from vario ous location ns outside of o the owneer controlledd area. Thhe result off this backgrou und study is summarized d in Table 2-5.

As part ofo the 2014 characterizaation effort, EnergySoluutions perforrmed a limitted assessmeent of backgrou und levels ata LACBWR R. The purrpose of thee study wass to assess iif backgrounnd at LACBW WR fell within n nominal ex xpected leveels for soils, concrete, annd asphalt.

Normally y, backgroun nd reference areas should be reasonaably close too the decomm missioning ssite to be repressentative. However, H no suitable offf-site locatioon was identtified. Conssequently, ann on-site area was chosen.. The Energ gySolutions Project P Heallth Physicist and the Raddiation Proteection Supervisor selected an a area outsside of the LSE L but on the licensedd LACBWR site that seemed appropriaate for obtainning backgro ound measurements bas ed upon the previous radiological suurvey results. Although th he selected sample s locattions were iinside the LA ACBWR liccensed area,, they were con nsidered unafffected by paast LACBW WR operationns.

Concretee samples an nd direct measurements were taken in Class 3 ssurvey unit L L3012101, w which is locatedd north of thhe LSE. Asphalt samp ples and direect measurem ments were also collectted in non-impaacted survey y unit L4012 2106. Surfaace soil sampples were accquired from m a small arrea of approximmately 100 square meterrs of undistu urbed non-drrainage soil within non--impacted suurvey unit L4012108. Soill samples fro om non-imp pacted surveyy units L40112107 and oother areas w within L401210 08 were also evaluated forf use as baackground reeference soills. Analysiss results for these samples are a provided d in sections 2.3.3 and 2..3.5.3.

The analysis of thee backgroun nd soil sam mples in 20114 compareed favorablyy with the 2005 backgrou und study foor soils. Thee results did d report Cs-1137 at levelss slightly abbove MDC. This can be atttributed to global g fallou ut. For the two t backgrouund studies performed aat LACBWR R, the mean Cs-137 concen ntration of surface s sampples taken o n or aroundd the site prooduced a meean of 0.135 pCCi/g with a maximum m ob bserved con ncentration oof 0.268 pCii/g. The sttandard deviiation was 0.070 resulting ini the upperr range for th his data set aat a 95% connfidence leveel of 0.275 pCi/g.

Relevantt to LACBW WR is a study y performed for the decoommissioninng of the Zioon Nuclear P Power Station (ZZNPS) titledd ZionSolutio ons TSD 13-004, Examiination of Css-137 Globaal Fallout in Soils at Zion Station S (15). This docum ment was prrepared to coompare site soil sample Cs-137 resuults at Zion to Cs-137 C levels anticipateed from worrldwide fall out. The L LACBWR annd Zion sitees are geograph hically similaar. The docu ument prediccted ranges ffor backgrouund concentrrations of Css-137 for distu urbed soils asa well as undisturbed u soils and is presented iin Table 2-66. The obseerved backgrou und Cs-137 levels for th he site specific backgrouund studies performed aat LACBWR R fall within thhe expected range of disturbed d soils in non-ddrainage areeas. As theere were vaarious categoriees of soil in the non-im mpacted areas at LACBW WR, the uppper 95th percentile levells for drainage and non-draainage, distu urbed and un ndisturbed sooil from the Zion backgrround study were 2-21

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 considereed appropriaate backgro ound concen ntration leveels for the evaluation of non-imppacted areas, and Class 2 an nd 3 open lan nd area surveey units at L LACBWR.

2.3.2. Potential P Radionuclidess of Concern n EnergySo olutions TS SD RS-TD-3 313196-001,, Radionucclides of C Concern During LAC CBWR Decommissioning (16) ( establishes the baasis for an initial suitee of potentiial ROC foor the decommiissioning of LACBWR. Industry gu uidance was reviewed ass well as the analytical reesults from the sampling of o various media m from past p plant ooperations. Based on thhe eliminatioon of some of the t theoreticcal neutron activation a pro oducts, noblle gases and radionuclidees with a hallf-life less than n 2 years, an n initial suitee of potentiaal ROC for the decomm missioning of LACBWR R was prepared. The list off potential raadionuclides is listed in T Table 2-7.

2.3.3. Non-Impacte N ed Open La and Areas Based up pon the inforrmation com mpiled in thee HSA, a larrge portion oof the open land areas oon the 163.5 acrre licensed site surroun nding the LSE L and ISSFSI receiveed a classiffication as non-impacted d. The non-impacte n d areas haave no reaasonable pootential to contain ressidual contamin nation given that historiccal informatiion providess no indicatioon of impactt from LACB BWR operationns. The dettermination that the con ntiguous opeen land areaas surroundiing the LSE E and ISFSI were w not imp pacted by licensed l opeerations wass based on the locatioon(s) of liceensed operationns (i.e., withhin the LSE), site use, topography, t site discharrge pathwayys, and otheer site physical characteristics. The areeas designatted as non-im mpacted aree not requireed to be survveyed for comp pliance beyo ond the charaacterization surveys andd sampling pperformed too provide a basis for the cllassification..

The non--impacted op pen land area is approxim mately 352,3360 square m meters in sizze. This areaa was segregateed into five survey unitts. Non-imp pacted openn land surveey unit L4012109 is loocated inside off survey uniit L4012108 8 in a vegetated area w with minimall ground dissturbance eaast of Highway y 35. This survey s unit was formed d during chaaracterizatioon to facilitaate a backgrround study forr soils. The non-impacteed survey un nits are showwn in Figure 2-1. The G G-3 station reesides within suurvey unit L4 4012103. A majority off the surface area in survvey unit L40012105 is covvered in coal from f the G--3 station an nd survey un nit L40121006 completeely surroundds the LACB BWR ISFSI faccility, which h has not beeen characterizzed and is noot addressedd by this LTP P.

From Occtober 2014 to August 2015, charracterization surveys w were perform med in the non-impacted d open land areas of th he site. Thee survey uniits were oriiginally classsified as Cllass 3 survey un nits and werre characteriized as such h in Referencce 13. Baseed upon a revview of the HSA and the initial i results of the 201 14 characteriization, thesse survey unnits were recclassified as non-impacted d as it was determined d that t there is no reasonabble potentiaal for residuaal contaminaation.

To support this con nclusion, ad dditional chharacterizatioon was perfformed in 22015. A m major objectivee of the additional charaacterization surveys perrformed in 22015 was too evaluate ceertain open land d survey uniits given an initial i Class 3 classificattion for re-cllassificationn as non-imppacted by perforrming additional soil sam mpling and gamma g walkkover surveyys.

The 2015 5 characterizzation campaign was deesigned in acccordance w with Referencce 4. One oof the primary objectives of the additional charaacterization was to perrform sufficcient radioloogical surveys anda samplin ng to supporrt the non--impacted cclassificationn and to prrovide reasonable 2-22

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 assurancee that the non-impacted n d survey uniits do not ccontain plantt-derived raadioactivity. The 2015 chaaracterization n survey foccused primarrily on soils and asphaltt. The sampple locations were based on a random design to ensu ure an unbiaased survey.

During th he 2015 chaaracterization survey, a minimum oof 1% of thee surface sooil area in suurvey units L40 012103, L40 012105, L40 012106 and L4012108 was scannedd with a Moodel 2350-1 data logger with w a 2 by 2 2 NaI detecctor. In surv vey unit L40012107, lesss than 1% off the surfacee area was scan nned due to inaccessibiliity from thee presence o f tall, thick vegetation aand steep terrain.

Gamma surface s scannning focused d on undistu urbed soils w with minimall vegetation or disturbedd soils or gravell. Alarm seet-points forr the instrum ment were sset at the obbserved backkground pluus the Minimum m Detectable Count Raate (MDCR)) of the insstrument. A total of ffour alarms were evaluatedd during thee performan nce of the gamma g scann, one in suurvey unit L L4012106, tw wo in survey unnit L4012107 and one in n survey unitt L4012108. All scan allarms were innvestigated uusing an Explo oranium GR--135. The results of th he investigaation indicatted the elevvated scan reesults were duee to the preseence of naturral backgrou und activity.

Thirty-tw wo surface soils sampless were colleected from non-impacteed areas at locations bbiased toward discolored d areas or areas where the ground g had bbeen disturbeed. The sammple locationns are shown in n Figure 2-5 5. Cs-137 was positiv vely identiffied in conccentrations greater thann the instrumen nt MDC in 26 of the 32 2 samples. No other pootential plannt-derived raadionuclides were positivelyy identified by gamma spectroscopy s y. The averaage Cs-137 cconcentration observed iin the surface soil s samples was 0.131 pCi/g with a maximum m observed cconcentrationn of 0.463 ppCi/g.

These vaalues are within the expeected backgrround range for Cs-137 surface sam mples as discuussed in section n 2.3.1. Only one Cs-13 37 result excceeded the m maxium resuult of 0.268 pCi/g in thee site-specific background b data set. Thhis sample was w the maxiimum 0.463 pCi/g valuee and was loocated in the grrounds east of Highway y 35. The mean m of the nnon-impacteed and site-sspecific dataa sets were very y close at 0.135 pCi/g an nd 0.131 pCi/g, respectivvely.

Seventeeen subsurface soil samplles were tak ken at random mly selectedd locations tto a depth oof one meter. Of the 17 7 subsurfacee soil samp ples taken, Cs-137 w was positiveely identifieed in concentraations greateer than the instrument MDC in ei ght sampless. No otherr potential pplant-derived gamma-emit g tting radionuuclides weree positively iidentified byy gamma sppectroscopy. The average Cs-137 conccentration ob bserved in the t subsurfaace soil sam mples was 0.087 pCi/g w with a maximum m observed concentratiion of 0.40 09 pCi/g. Thhese valuees are withhin the exppected backgrou und range for Cs-137 as discussed in n section 2.33.1. Only onne subsurface sample had Cs-137 conccentrations th hat exceeded the maxim mum Cs-1377 concentratiion found inn the site-speecific surface soil s backgrou und. This sample s was thet maximuum 0.409 pC Ci/g value that was locatted in the Hwy 35/Railroad d Right of Way W Grounds.

Two asp phalt samplees were colllected from random loccations in ppaved areas in non-imppacted survey un nits. The asp phalt surfacee was first sccanned withh a beta-gamm mma detector. All scan reesults 2

were lesss than the MDC M of 1,93 38 dpm/100ccm . No plaant derived rradionuclides were posittively identified d by gamma spectroscop py in any of thet asphalt ssamples.

A summary of the gammag specttroscopy resu ults for eachh non-impaccted open laand survey uunit is presentedd in Table 2--8.

2-23

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 A coal assh sample frrom survey unit u L4012105, six surfa face soil sam mples and fivve subsurface soil samples were sent to o Test Ameerica Laboraatories for ggamma specttroscopy andd HTD anallyses.

The resullts of the anaalysis are preesented in Table T 2-9.

The lab boratory an nalysis sporradically id dentified seeveral plannt-derived rradionuclidees at concentraations exceeeding the MD DC, includin ng H-3, C-144, Fe-55, Nii-63, and Sr--90. Cs-1377 was also positively detectted but at lev vels that are consistent w with natural bbackground. In all casees, the concentraations of thee positively identified i rad dionuclides w were close tto the detectiion limits annd are considereed to very liikely be the result of cou unting uncerrtainty as oppposed to the actual pressence of the pllant-derived radionuclid des. This conclusion c w was supporteed by a revview of exppected radionuclide mixturre fractions. For exam mple, samp le L30121005-CR-GS-0002-SS indiicates positive results for Cs-137, C Sr-90 and Fe-5 55. Howevver, the Sr-990/Cs-137 annd Fe-55/Css-137 ratios arre 118 and 16, respecttively. Wh hen the ratiios from L33012105-CR R-GS-002-SS S are compared d to the sitee-specific miixture fractions in Chappter 6, Tablee 6-3, it is seen that theey are higher thhan expected d by factorss of 4,800 and a 10,700, respectivelly. In concclusion, baseed on operationnal history, the t radionuclide ratios, and a primarilyy the concenntrations of C Cs-137 whicch are consistennt with naturral backgrou und and com mprise 88% oof the site-sppecific radioonuclide mixxture, the sporaadic positive analytical results are veery unlikely to representt the actual ppresence of pplant-derived radionuclide r s in these suurvey units.

In surveyy unit L4012 2108, a reprresentative sample s of thhe rail road bed gravel was analyzeed by gamma spectroscopy s y. In additio on, gamma scan s readinggs were takeen of the raill road bed ggravel area to determine d iff there is a significant difference from site bbackground (which averraged approximmately 7,000 0 to 8,000 cp pm). The analysis a of tthe railroad bed gravel indicated naatural uranium and thorium m series nucclides with no plant deerived radioonuclides. T The gamma scan readings conducted during d the walkover surv vey averagedd 7,000-8,5000 cpm.

2.3.4. Im mpacted Op pen Land Areas A

The HSA A identified d the open land area inside the fenced LSE E as impaccted by reeactor operationns. The app proximate areea is 1.5 acrres. All opeen land surveey units insiide the LSE have been classsified as Class C 1. An approximattely 3.46 acrre area that surrounds tthe LSE hass also been iden ntified as iimpacted by reactor op perations. T This open laand area has been segregated into two Class 2 surv vey units. Three T impactted Class 3 ssurvey units were designnated for thee area north of the LSE, th he transmisssion switchy yard and thee area encom mpassing thhe site accesss off Highway y 35 and thee haul road used u to tran nsport dry fuuel casks to the ISFSI. The area oof the three Claass 3 survey units combin ned is approoximately 166.5 acres.

The charracterization of the impaccted open laand areas beggan in Octobber 2014. A sample plann was prepared for each surveys unit in accordaance with R Reference 44. Survey techniques were employed d to determine the laterral and vertical extent oof any contamination iddentified annd the radionuclide concenttrations in th he soil. Charracterizationn inspectionss and surveyss were perfoormed of sufficiient quantity y and quality y to quantify the potentiaal volumetricc contaminattion of accesssible surface and a subsurfface soils in n each open n land surveey unit. Liimited soil informationn was obtained from below w the structurres due to intterferences aand inaccessibility.

Survey techniques were emplloyed to deetermine thhe lateral aand verticall extent off any contamin nation identiified and th he radionucllide concenttrations in tthe soil. A combinatioon of 2-24

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 random anda biased survey locatiions were esstablished in each surveyy unit in acccordance witth the survey package. Thee locations of o biased meeasurementss and/or sam mples were ddetermined bby the professioonal judgmeent of the EnergySoluti E ions Project Health Phyysicist and the Radioloogical Protectioon Supervisor. Consideration waas given too locations that exhibbited measuurable radioactivvity, depressions, discolored areas, low point ggravity drainn areas, actuual and poteential spill locaations, or arreas where thet ground had h been diisturbed. Thhe number of random-bbased survey loocations wass also determ mined by areea classificattion. Random-based meeasurements were not requ uired for soiils in an op pen land areeas designat ated as Classs 1. Randoom measureement locationss were seleccted on asp phalt in Claass 1 surveyy units wheere there waas no historry of radiologiical contamin nation.

A surfacee soil samplee was taken at each selected biased aand random-based surveey location. Sub-surface soil samples were acquirred at severaal random lo cations or iff surface soil sample anaalysis or surfacce scans indiicated elevatted activity. Depending on the locaation, subsurface soil sam mples were takeen from 0.15 5 cm to deptths ranging from f 1 to 3 m below graade and com mposited over 1 m intervals.

Each surrface soil, coomposite sub bsurface soill sample or asphalt sam mple was anaalyzed by thhe on-site radioological laboratory by gamma-specctroscopy. Analysis coount times w were adjusteed as necessary y to achievee an isotopicc MDC equaal to or lesss than 0.10 ppCi/g for Css-137 and C Co-60.

All surfaace and subsurface com mposite samp ples were annalyzed afteer drying thhe sample m media.

Several soil s samples were selecteed at random m and were sshipped to T Test Americaa Laboratoriees for full isoto opic analysiss (HTD radiionuclides). Duplicate samples andd concrete w were collecteed by survey un nit per Refeerence 4.

2.3.4.1. Class 1 Open Lan nd Areas There aree four (4) op pen land surrvey units cllassified as Class 1 at L LACBWR tootaling 8,4433 m2.

The Classs 1 open lan nd survey un nits are show wn in Figure 2-1. A signnificant portiion of the suurface area in thhe Class 1 op pen land surrvey units is obstructed bby the preseence of builddings, namelly the Reactor Building, th he Turbine Building, th he WTB andd the LSA Building. The presence of radioactivvely contamminated build ding and sysstems, as weell as stored radioactive material in these areas, preevented the ability a to perrform surfacce scanning ddue to high bbackground..

Twenty-ttwo (22) surrface soil sam mples were taken at loccations biaseed toward sittes that exhiibited measurab ble radioacttivity, discolored areas,, buried pippe locationss, actual annd potential spill locationss, or areas where w the groound had beeen disturbedd. The locaations of surfface soil sam mples taken in Class 1 open n land surveey units are shown s in Figgure 2-6. O Of the 22 surface soil sam mples taken, Co-60 C was positively p id dentified in concentratiions greaterr than the M MDC in tw wo (2) samples and Cs-137 7 was posittively identtified in conncentrationss greater thhan the MD DC in 13 samplles. No oth her potentiaal plant-deriv ved gammaa-emitting raadionuclidess were posittively identifiedd by gamma spectroscop py. The averrage Co-60 cconcentratioon observed in the analysis of the surfface soil saamples wass 0.058 pCi//g with a maximum observed cconcentratioon of 0.287 pCCi/g. The average Cs-1 137 concenttration obserrved in the analysis off the surfacee soil samples was w 0.096 pCi/g with a maximum m ob bserved conccentration of 1.07 pCi/gg.

Seventy-nine (79) su ubsurface soil samples were w taken aat 10 surfacee soil locatioons to a deppth of one meteer, two (2) loocations biassed to areas ono the south and west sidde of the WG GTV and fivve (5) 2-25

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 locationss that accessed the soils under the Turbine Buildding throughh angled Geooprobe samppling.

The sam mples at the two t WGTV V locations were w acquireed to a deptth of five m meters in ordder to evaluate the subsurfaace soils alon ngside and underneath u thhe vault. Thhe samples uunder the Tuurbine Building were taken and composited at deptths of 10, 155 and 20 feeet. Of the 779 subsurfacee soil samples taken, Cs-1 137 was possitively iden ntified in cooncentrationns greater thhan the MD DC in 15 samplles. No oth her potentiaal plant-deriv ved gammaa-emitting raadionuclidess were posittively identifiedd by gammaa spectroscop py. The aveerage Cs-13 7 concentrattion observeed in the anaalysis of the su ubsurface sooil samples was 0.055 pCi/g p with a maximum m observed concentratioon of 0.161 pCCi/g. The asssessment of potential su ubsurface soiil contaminaation in the C Class 1 openn land areas is not currenttly completee. Soil in difficult too access areeas such ass under buiilding foundatio ons and surrrounding bu uried structu ures and pipping has beeen deferred until later in the decommiissioning pro ocess, when access will beb more readdily availablle.

Ten sam mples were taaken of asp phalt from paved p areas in Class 1 ssurvey unit L1010104. The asphalt was w taken fro om the samee location selected for thhe surface annd subsurfacce soil samplles in this survvey unit. Th he asphalt surface s was first scanneed with betaa-gamma deetector with scan results raanging from the instrumeent MDC off 2,771 dpm//100cm2 to a maximum of observedd scan measurem ment of 3,09 95 dpm/100 cm2. Of th he 10 asphallt samples ttaken, Cs-1337 was posittively identifiedd in concen ntrations greeater than MDC in onnly one sam mple at a concentratioon of 0.057 pCCi/g.

A summary of the fiindings of th he survey fo or each indivvidual Classs 1 open landd survey unnit are presented d in Table 2--10.

Nine surrface soil saamples, 11 subsurface s soil s sampless, one concrrete sample and two assphalt samples taken from Class 1 open n land surveey units werre sent to Teest Americaa Laboratoriees for gamma spectroscopy s y and HTD analyses.

a Th he results off the analysiss are presentted in Table 2-11.

In addition to detectting Co-60 and Cs-137, H-3, C-144, Fe-55 andd Ni-63 werre also posittively detected at concentraations greater than the innstrument MD DC.

One sediiment samplle was taken n from the sanitary s solidds tank that is located iin Class 1 suurvey unit L1010103. Thiss sample waas also sent to t Test Amerrica Laborattory for gam mma spectrosscopy and HTD D analyses. Co-60 and C-137 weree detected inn this sample, both at a concentration of 0.136 pCCi/g.

2.3.4.2. Class 2 Open Lan nd Areas The impacted Class 2 open lan nd areas totaal approxim mately 13,996 m2 and arre located inn the immediatte area surro ounding the LSE. The Class C 2 impaacted open land area waas segregatedd into two survey units. Th hese are shoown in Figurre 2-1. The LACBWR Administrattion Buildingg, the LACBW WR Crib Hou use, the G-3 3 Crib Housse and the L LACBWR w warehouses aare all locatted in these two o survey unitts.

Approxim mately 1% ofo the surfacce soil area in i survey unnit L2011101 was scannned with a M Model 2350-1 data d logger with w a 2 by y 2 NaI deetector. Thiis area incluuded asphaltt paved surffaces.

Alarm seet-points for the instrumment were sett at the obseerved backgrround plus tthe MDCR oof the instrumen nt. No scan alarms weree observed.

2-26

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Twenty-tthree surface soil samp ples were tak ken at locattions biasedd toward sites that exhiibited measurab ble radioacttivity, discolored areas,, buried pippe locationss, actual annd potential spill locationss, or areas where w the groound had beeen disturbedd. The locaations of surfface soil sam mples taken in Class 2 open n land surveey units are shown s in Figgure 2-7. OOf the 23 surface soil sam mples taken, Css-137 was positively p ideentified at cooncentrationns greater thhan MDC in 14 samples. No other pottential plantt-derived rad dionuclides were positivvely identifiied by gamm ma spectrosccopy.

The averrage Cs-137 7 concentrattion observeed in the annalysis of thhe surface ssoil sampless was 0.077 pC Ci/g with a maximum m obsserved conceentration of 0.200 pCi/gg.

Twenty-tthree subsurface soil sam mples were taken t at 14 rrandom locaations to a deepth of one mmeter and threee locations biased b to areeas alongsidde and underrneath the S Storm Sewerr Water pipee that resides inn survey uniit L2011101 1. The biaseed samples w were acquireed to a deptth of five mmeters.

Of the 23 2 subsurfacce soil samp ples taken, Co-60 was positively identified aat concentraations greater thhan MDC in n one samplee and Cs-137 was positiively identiffied at conceentrations grreater than MD DC in four samples. No N other po otential plannt-derived raadionuclidess were posittively identifiedd by gamma spectroscop py. The sing gle sample w with detectabble Co-60 haad a concentrration of 0.112 pCi/g. The average Cs--137 concenttration obserrved in the aanalysis of thhe subsurface soil samples was 0.043 pCi/g with h a maximu um observe d concentraation of 0.0088 pCi/g. The assessmeent of poten ntial subsurfface soil con ntaminationn in the Claass 2 open lland areas is not currentlyy complete. Soil in diffficult to access areas ssuch as undder building foundationss and surround ding buried structures s an nd piping haas been defeerred until later in the ddecommissiooning process, when w accesss will be morre readily av vailable.

Twelve samples s weree taken of assphalt from paved p areas in Class 2 suurvey units. The asphallt was selected randomly. The asphaltt surface was first scannned with betta-gamma deetector withh scan results ranging r fro om the insstrument MDC M of 2,,529 dpm/1000cm2 to a maximum m of 2,748 dpm m/100cm2. Of the 12 2 asphalt samples takenn, Cs-137 w was positiveely identifieed in concentraations greatter than thee instrumen nt MDC in three sampples. The average Css-137 concentraation observ ved in the an nalysis of thee asphalt sam mples was 00.049 pCi/g with a maxiimum observed d concentration of 0.055 pCi/g.

A summary of the fiindings of th he survey fo or each indivvidual Classs 2 open landd survey unnit are presented d in Table 2--12.

Three surrface soil saamples, five subsurface soil s samples,, three asphaalt samples aand two sediiment samples taken from m an accesssible storm m sewer baasin manholle located in front off the Administtration Build ding were seent to Test America Laaboratories ffor gamma sspectroscopyy and HTD anaalyses. The results of th he analysis are a presentedd in Table 2-13. In adddition to deteecting Co-60 anda Cs-137, H-3, C-14 4, Fe-55 an nd Cm-243//244 were also positivvely detecteed at concentraations greateer than MD DC. As disccussed in seection 2.3.3 for non-imppacted areass, the HTD rad dionuclides exceeding e MDC M are likelly to be falsee positives.

2.3.4.3. Class 3 Open Lan nd Areas The impaacted Class 3 open land areas total approximatel a ly 66,765m2. The Class 3 impacted open land areaa was segreegated into three surveey units. T The Class 3 survey uniits are show wn in Figure 2--1. The Claass 3 impacteed open land d survey unnits include tthe north ennd of the liceensed site, the transmission t n switchyard for the LAC CBWR and G G-3 facilities, the LACBBWR plant aaccess 2-27

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 and rightt-of-way area and the haaul road to th he ISFSI faccility. The nnorth end off the licensed site was deem med impacteed by LACB BWR due to o the presennce of a sepptic system that servicees the LACBW WR Administtration Build ding and the presence off concrete fr from impacteed structuress (the Crib Hou use). The trransmission yard was deemedd as im mpacted as iit was part oof the LACB BWR facility during d operattions. The plant p access area, Highw way 35 rightt-of way andd ISFSI haull road were deeemed as imp pacted by thhe transit off packaged rradioactive m material throough these aareas.

These arreas were conservativelly classified d as impacteed. Howevver, it should be notedd that Solutionss maintains that t classifyiing these areeas as non-im mpacted wouuld have beeen appropriatte.

A minim mum of 1% of the surfface soil areea in surveyy units L30012101 and L3012109 were scanned with a Model 2350-1 daata logger with w a 2 by 2 NaI deteector. Surveey unit L30112102 was exclluded from gamma surrface scanniing for safeety reasons. Gamma surface scannning focused ono undisturb bed soils wiith minimal vegetation oor disturbedd soils or graavel. Alarm m set-points for the instrum ment were seet at the obseerved backgrround plus tthe MDCR oof the instrum ment.

No scan alarms weree observed in n these surveey units.

Thirty-twwo surface so oil samples were taken at locations biased toward discolorred areas or areas where th he ground haad been distturbed. Thee locations oof surface soil samples taken in Cllass 3 open land survey un nits are showwn in Figuree 2-8. Of thhe 32 surfacee soil samplles taken, Css-137 was positively identiified in conccentrations greater g than MDC in 26 samples. N No other poteential plant-derrived gammaa-emitting raadionuclidess were positiively identiffied by gamm ma spectrosccopy.

The averrage Cs-137 7 concentrattion observeed in the annalysis of thhe surface ssoil sampless was 0.131 pC Ci/g with a maximum m obsserved conceentration of 0.463 pCi/gg.

Seventeeen subsurface soil samplles were tak ken at random mly selectedd locations tto a depth oof one meter. Of the 17 7 subsurfacee soil samp ples taken, Cs-137 w was positiveely identifieed in concentraations greaater than MDC M in eiight sampless. No oth ther potentiial plant-deerived radionuclides were positively identified by gamma spectroscoopy. The average Css-137 concentraation observ ved in the analysis a of th he subsurfacce soil sampples was 0.0087 pCi/g w with a maximum m observed concentratio c on of 0.409 pCi/g.

p Two sam mples were taken of asph halt from paaved areas inn Class 3 suurvey units. The asphaltt was selected randomly. The asphalt surface was first scannned with betta-gamma deetector. Alll scan results were w less thaan instrumennt MDC of 1,9381 dpm/1100cm2. Noo plant derivved radionucclides were possitively identtified by gammma spectroscopy in anyy of these sam amples.

A summary of the fiindings of th he survey fo or each indivvidual Classs 3 open landd survey unnit are presented d in Table 2--14.

As part of o the characcterization off survey unitt L3012101,, samples weere taken froom several ppieces of concreete located in i the northh section of the survey uunit that oriiginated from m the LACB BWR Crib Hou use. In addiition, a sammple was takeen from a saanitary tankk that servicees the LACB BWR Administtration Build ding and twwo sedimentt samples w were taken frfrom a storm m sewer bassin in survey un nit L3012109. These sam mples were sent off-sitee for isotopicc analysis.

Three co oncrete samp ples from suurvey unit L3 3012101, thhe sanitary taank sample from surveyy unit L301210 01, the two seediment sam mples taken from f the storrm sewer baasin in surveyy unit L30122109, three surrface soil samples s and d two subssurface soil samples w were sent tto Test Am merica Laborato ories for gam mma spectrroscopy and d HTD anallyses. The results of the analysiis are 2-28

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 presented d in Table 2-15.

2 The analysis off these sampples positiveely identifieed several pplant-derived ROC R at residdual concenttrations greaater than thee instrument MDC, incluuding H-3, F Fe-55 and Ni-6 63. As disscussed in section s 2.3.33 for non-im mpacted areeas, the HT TD radionucclides exceedin ng MDC are likely to be false positiv ves. Cs-137 was also poositively deteected but at llevels consistennt with naturral backgroun nd.

2.3.5. Non-Impacte N ed Structures Based up pon the infformation co ompiled in the HSA, S Solutions cooncluded thhat the strucctures associateed with the G-3G Coal Plaant may be classified c as non-impaccted. Histoorical inform mation indicatedd that there was w no reaso onable poten ntial for residual contammination from m site operattions.

A full lisst of G-3 struuctures that have been designated d ass non-impaacted is provvided in Tabble 2-2.

The prim mary basis for f the non n-impacted classificatioon for the G G-3 station structures iis the informatiion documen nted in the HSA H that thee G-3 structuures were noot used for LLACBWR-reelated operation ns. Additionally, the potential p for windborne migration oof airborne effluent releeased from thee LACBWR R Stack du uring operaations to sstructure rooofs was evvaluated byy the characterrization of thet LACBW WR Administtration Buildding roof annd the G-3 Coal Plant roof.

The resu ults are prov vided in Reeference 13. Additionnal surveys of the G-3 structures were conducteed during thee 2015 charaacterization campaign w where the suurfaces subjeected to highh foot traffic in the major sttation buildin ngs were surrveyed.

The G-3 station ressides in non n-impacted survey s unit L4012103. There aree no documented incidentss of radioacttive contam mination of soils, s asphallt or concreete in this suurvey unit. The results off the characterization surrveys perform med in the G G-3 station aare summarizzed as follow ws:

A scan su urvey was performed p off the mid-lev vel roof of thhe G-3 Coall Plant buildding using a beta-gamma detector.

d In addition, six x (6) locatioons were seleected at randdom for direect measurem ments using an alpha/beta-g gamma prop portional deteector. A sm mear sample for removabble contaminnation was also taken at the location of each direct measuremen m nt. The resuults of the beeta scan idenntified gross betta-gamma activity rangiing from 2,3 302 dpm/10 0cm2 to 2,8816 dpm/1000cm2 with a scan 2

MDC off 2,816 dpm//100cm . The T results of o the direcct beta-gamm ma and alphha measurem ments 2

identifiedd gross beta--gamma actiivity ranging g from 1,6033 dpm/100cm m to 2,072 dpm/100cm m2 and gross alp pha activity y ranging from f 142 dp pm/100cm2 to 258 dpm m/100cm2. No removvable contamin nation was identified at concentratio ons greater tthan MDC bby the analyysis of the ssmear samples. The roof material m itseelf was samp pled on Junne 30, 2015. Cs-137 waas the only plant derived ROC that was w positiveely identifieed by gamm ma spectrosscopy at a concentratioon of 0.061 pC Ci/g. Based on the fact that t no otherr plant derivved ROC waas detected, it was conclluded that the elevated dirrect alpha measurements m s were due most likely to the pressence of coaal ash material on the roof.

Direct an nd removablle contamination survey ys were perfformed of reepresentativve high persoonnel traffic arreas of the G-3 Coal Plant. P Scan n measuremeents were pperformed ussing the Luudlum Model 23 360 instrumeent with 43--93 detector.. Approxim mately 5% off the concrette surfaces iin the areas of interest i weree scanned, in ncluding floo ors and loweer wall surfaaces. The avverage scan M MDC 2 2 ranged from f 2,540 dpm/100cm m to 2,617 7 dpm/100cm m . No oobserved scaan measureement exceeded d the MDC during d the co ourse of thiss survey. Teen (10) locattions were chhosen at ranndom, 2-29

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 primarilyy from the main lobby y area and the mainteenance area.. The resuults of all ddirect measurem ments for gross g activity was less than the M MDC of 74 dpm/100cm m2 for alphaa and 875 dpm/100cm2 for beta-gamma. No remov vable contammination waas identified at concentraations greater thhan MDC by y the analysis of the smear samples.

2.3.6. Im mpacted Strructures an nd Systems The deco ommissionin ng approach h for LACB BWR requirres the dem molition andd removal oof all impacted d buildings, structures, s syystems and components c to a depth oof at least 3 feet below ggrade.

In additioon, all systemms and expo osed metal below b 3 feet below gradde will also bbe removed. The accepted elevation fo or grade at LACBWR L is the 639 fooot elevation. The only sttructures thaat will remain and a be subjeected to STS S are the rem maining reinnforced conccrete walls aand floors oof the Reactor Building B thaat will be exp posed by thee removal off the interiorr concrete annd steel lineer, the remainin ng reinforcedd concrete walls w floors of o the WTB, the remainiing reinforceed concrete walls and floo ors of the WGTV, an nd the rem mainder of the Pipingg and Venttilation Tunnnels, Reactor/G Generator Plant basemeent, the one foot thick pportion of thhe Chimneyy Foundationn, the Turbine sump and th he Turbine pit. Conseq quently, all systems andd componennts and strucctural surfaces above the 636 foot eleevation willl be remediiated, disasssembled andd/or demoliished, segregateed by waste classificatio on and dispo osed of as cclean demoliition debris, clean salvaage or radioactivve waste. No extensiive characteerization waas or will bbe performeed of equipm ment, systems oro structuress that will bee removed prrior to the peerformance oof FRS.

Radiolog gical surveyss of the interriors of structures at LAC CBWR are rroutinely perrformed to ennsure complian nce with 10 0 CFR 20 reequirements regarding the postingg of areas and to ideentify radiologiical conditioons for the im mplementation of controols for the prrotection off workers in these areas. The radiolo ogical inforrmation from m these suurveys will provide thhe basis forr the disassemmbly and rem moval of systtems and thee demolition of impactedd structures aat the site. W When remediation has adeequately red duced radiollogical condditions to leevels suitablle for contrrolled demolitio on, the impaacted structu ures will be demolishedd, packaged and properlly disposed of as waste.

After com mmodity rem moval is com mplete, the structures thaat will remaiin at license terminationn, i.e.,

3 feet beelow grade,, will be re-surveyed r to determiine the conncentrations of the ressidual radioactivvity and thee extent of additional a reemediation rrequired, if aany, to meett the unrestrricted use criterria.

2.3.6.1. Basemment Structu ures Below 636 Foot Elevvation Characterization of the structurral surfaces of basemennts that willl remain inn the end-sstate consistedd primarily of o the acquisition and rad diological annalysis of cooncrete core samples from m the walls and floors of the Reactorr Building, WTB and the balancee of the bassement strucctures (primarilly the Pipingg Tunnels). In June and July of 20155, a series of concrete coore samples were taken froom the 615 foot elevation concrete floor and tthe concretee floor and east wall on the 621 foot elevation in n the Reactorr Building, th he 630 foot elevation cooncrete floorr of the WTB B and the 633 foot f elevatio on concrete floor f of the Piping P Tunnnels. A totall of twelve (12) concretee core samples were w collectted, six (6) in n the Reacto or Building, three (3) in the WTB annd three (3) iin the Piping Tu unnel. The locations l whhere the coree samples weere taken aree shown in F Figures 2-9.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The locaations selecteed for concrrete core sam mpling were biased tow ward locationns where phyysical conditionn or observ ved radiolog gical measu urements inndicated thee presence of fixed aand/or volumetrric contamination of the concrete. When W possiblle, locations were determ mined based upon elevated observed co ontact dose rates r or counnt rates. In aaddition, vissual observattions of flooor and wall surfaces were used to id dentify poten ntial locatioons of surfface contam mination, succh as discoloraation or stan nding water. The goal was w to identtify, to the eextent possibble, the locaations that exh hibited the highest h potential of reepresenting the worst case boundding radioloogical conditionn for concreete in each survey s unit. This judggmental samp mpling approach also ensured there wass sufficient source s term in the cores to achieve tthe sensitivitties requiredd to determinne the radionuclide fraction ns of gamma emitters as well w as HTD D radionucliddes.

The conccrete pucks representing r g the first 1/2 inch of conccrete at eachh sample loccation was seent to Test Ameerica Laboraatory for gam mma spectro oscopy and H HTD analysees for beta annd alpha em mitting ROC. In n addition, the concretee pucks rep presenting thhe concrete deeper thann 1/2 inch deeep at Reactor Building B mple locations #001, #003, #005 annd #006 and WTB sample locations #001 sam and #002 2 were also o sent for issotopic analy ysis. A sum mmary of tthe analyticaal results foor the concrete cores is prresented in Table 2-16. Significannt HTD raddionuclides iidentified byy the analysis of the concrete core saamples inclu ude Ni-63, H H-3 and Sr-990. The othher radionucclides positivelyy detected att concentratiions greater than their reespective MD DC include; C-14, Fe-555, Ni-59, Tc-99 9, Pu-238, Pu-239/240, P Pu-241, Am m-241 and A Am-243. An analysis of the results oof the concrete core samplees is presenteed in Referen nce 16.

2.3.6.2. Turbin ne Building Tunnel A concreete core wass obtained ass part of thee 2014 charaacterization survey from m the floor oof the Turbine Building Tunnel T to attempt to evaluate the possiblle extent oof a radioaactive contamin nation event cited in the HSA pertain ning to the ddiscovery off cracked draain system ppiping in the Turbine T Buillding and thet potentiall radiologiccal contaminnation of suurrounding soils.

Analysis of this sam mple indicateed detectablee concentrattions of Cs-1137 at 0.3522 pCi/g, Co--60 at 0.106 pCCi/g and H-3 at 1.71 pCi//g.

2.3.6.3. LACB BWR Admin nistration Buuilding As stated d previously y, the LACB BWR Admin nistration Buuilding and G-3 Crib H House will nnot be subjectedd to FRS. In nstead, thesee two structuures will be surveyed foor unrestricteed release ussing a graded su urvey approaach in accord dance with MARSAME M E guidance.

As reporrted in the HSA, H there was w no past history of thhe use of unnsealed radiooactive mateerials, radioactiv ve spills or radioactive contaminatiion in the LA ACBWR Administratioon Building. The building has primarilly been used d for office sp pace and reccords storagee. An enviroonmental labb was located ini the build ding that sup pported both h LACBWR R and G-3 operations. The LACB BWR Administtration Build ding was in nitially classsified as a M MARSSIM Class 2 struucture due tto its proximity y to the LSE E, occupancy y by LACBW WR personnnel and the presence of thhe environm mental laboratorry.

Characterization surv veys of the LACBWR Administrattion Buildinng included a scan for gross beta-gammma/alpha activity of in nterior floorrs surfaces aand the rooff. Direct m measurementts for gross betta-gamma/allpha activity were also performed p onn the roof, onn floor tiles and around floor 2-31

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 drain opeenings. A sm mear samplee for removaable contam mination was also taken at the location of each direect measurem ment.

The resu ults of the beta scans of the intterior surfacces ranged from 1,4200 dpm/100cm m2 to 4,915 dpm m/100cm2 with w a scan MDCM 00 dpm/100ccm2. Duringg the scan off the north eend of of 2,10 the secon nd floor haallway, a discrete radio oactive partiicle was disscovered. T The particlee was imbedded d in a floor tile. The contaminated c d portion off the tile waas removed and analyzeed by gamma spectroscopy s y. The analy ysis of the tiile identifiedd 0.005 uCi of Cs-137. An investiggation was then n performed involving th he acquisition of ten (10)) biased direect measurem ments on thee first and seco ond floor lam minated woo od, carpet, and a floor tille. Direct bbeta-gamma readings raanged from lesss than MDC of 329 dpm m/100cm2 to a maximum m observed reeading of 5,,743 dpm/1000cm2 and direct alpha readings rang ged from leess than MD DC of 39 ddpm/100cm2 to a maxiimum 2

observed d reading of 72 7 dpm/100ccm .

Beta sccans of th he roof areea indicateed results ranging frrom 1,872 dpm/100cm m2 to 2,261 dpm m/100cm2 with w a scan MDC M of 2,2661 dpm/100ccm2. Directt alpha meassurements raanged 2

from lesss than MDC C of 113 dpmm/100cm to o a maximum m observed reading of 1152 dpm/1000cm2.

Direct beeta-gamma measurement m ts taken on the t floor draain openingss ranged from m less than M MDC 2

of 243 dpm/100cm d to a maxim mum observ ved readingg of 333 dppm/100cm2 aand direct alpha measurem ments were all less than n MDC of 42 4 dpm/100ccm2. No reemovable coontaminationn was identifiedd concentratiions greater than MDC by b the analy sis of the sm mear sampless.

2.3.7. Surface and Groundwatter Section 8.5 8 in Chap pter 8 of this LTP contains a ssummary ddescription of the geoology, hydrogeo ology and hy ydrology of ZNPS and environs.

e T The informattion containeed in this seection was deriived directly y from Haley & Aldriich, Hydroggeological C Conceptual SSite Model (17).

Haley & Aldrich, Hyydrogeologiccal Investiga ation Reportt for the LaCCrosse Boilinng Water Reeactor (18) suppplements thee preliminary y findings in n Reference 117.

2.3.7.1. Area Grou undwater Usse For a distance of 40 0 miles dowwnstream of the site, virrtually all m municipal wwater suppliees for towns an nd cities alon ng the Mississsippi River are obtainedd from groun und water. TThe nearest uuse of river watter for indusstrial purposses, excludin ng the adjaccent G-3 plaant, is the cooal-fired plaant in Lansing, Iowa, aboutt 15 miles downstream d of o the site. There are nno other know wn users off river water fo or industriaal purposes between the t LACBW WR site annd Prairie du Chien, WI, approxim mately 40 miles downstreeam.

The LAC CBWR site has its own potable waater supply, pprovided thrrough a singgle ground w water well at th he site. Saniitary wastes are collected in a solidss holding tannk and pumpped off by a local state permmitted sanittary wastes hauler.

h Thiis includes a sanitary hoolding tank that servicees the LACBW WR Administration Buillding and a sanitary hholding tankk that serviices the Tuurbine Building. Storm waater runoff iss diverted diirectly to thhe Mississipppi River at ooutfalls. Reelease areas aree periodicallyy monitoredd for oil sheeen and discooloration. R Roof drains ddischarge dirrectly to the grround area su urrounding the t facility viav downspoouts or enter the normaal effluent reelease pathway after passing g through ann oil separato or located innside the LSEE.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 2.3.7.2. Groundwater Flow Regionallly, groundw water flows in i a westerlly direction from the blluffs on the east towardds the Mississipppi river. Closer C to th he shore, grroundwater may also hhave a flow componentt that parallels the river. Under U typical river stagge, groundw water gradiennts near the river are sliightly upward; however, th he vertical grradient reverrses during fflood stages.. The geologgical and hisstoric river stag ge data comp pared to water table eleevations meaasure in LAC CBWR site monitoring wells demonstrrates that thee shallow aq quifer is in diirect hydrauulic communnication withh the river annd the river stag ge impacts thhe water tablle elevation.

Groundw water beneath h the site is first encoun ntered at ann average deepth of 20 feeet below grround surface (bgs) and thee groundwatter is in direect hydraulicc communicaation with thhe adjacent river.

Groundw water in the shallow s depo osits and filll material floows towardss the west annd dischargess into the Missiissippi River. The deep per groundw water is also likely to floow towards tthe west butt then may turn n and flow parallel to the river. Because thhe potentiall releases off radiologiccal or chemicall constituents would occu ur at or nearr the surface , the releases would likeely be confinned to the shalloow system.

Based on n a review off the ground dwater elevattion measureements colleected during routine sam mpling of the G--3 Ash Land dfill area grou undwater mo onitoring weells (# B2/B33/B9A/B9/B B7/B8), whicch are located ini the soutth side of the t LACBW WR site, annd associateed backgrouund groundw water monitorin ng wells (B111AR/B11R) to the east of and up grradient of LA ACBWR, thhere appears to be a slightly y downward vertical graadient. Durin ng times of nnormal and low river staage, groundw water has a do ownward grradient at well w pairs B11R/B11AR B R and B2/B B3, with an upward veertical gradient at well pair B9/B9A. This T is expeccted as grouundwater floows generallyy from the bbluffs towards the t river bassin with a lo ocalized influuence at B9//B9A from tthe adjacentt inlet. How wever, there aree some perio ods where the t gradientss are reverssed; and thiss is likely ddue to high river stages. Groundwater G r flow throuugh the LAC CBWR site iss impacted bby deeper sttructures (i.ee., the Reactor Building B basement shell) as well ass the deep ppilings that ssupport the structures, w which are beloww the water table t during high and low w river stagee conditions..

During plant p construuction, and more m specifiically the insstallation off the supportt pilings, thee soil was com mpacted, redu ucing the efffective porossity and perm meability off the soils. TThis reductiion in permeabiility can deccrease the hydraulic h connductivity oof the aquifeer within thee footprint oof the buildingss. The resullting impact to groundw water flow iss that grounddwater withiin the comppacted soils willl flow at a slower s veloccity, and reggionally, a siignificant peercentage off the flow reegime will circcumnavigate the area, effectively e bypassing b these soils. The impliications of these th localizedd flow regimmes on contam minant fate and a transporrt are that pootential releaases that occcurred outside thhe footprint of these strructures willl likely be ddeflected andd flow arounnd them. O On the other hannd, potentiall releases thaat occurred within w the foootprint of thhe buildingss, via floor ddrains or buriedd piling, willl likely take much longeer to migratee both in the vadose zoone as well aas the underlyinng groundw water. This is further compounded c d as the oveerlying strucctures isolatte the shallow soils s from precipitation, p , creating ann area that w will likely reetain any potentially releeased contamin nation. The average shaallow aquiferr hydraulic cconductivityy is 313 feet per day. Foor the soils withhin the suppport pilings, the hydraulic conductivvity would bbe expected to be one too two orders off magnitude lower.

2-33

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 The velo ocity of gro oundwater iss directly related to booth the hyddraulic condductivity andd the gradient. The gradieent of the waater table is influenced byy the topogrraphy; and, w with the flat areas across thhe site, grounndwater mon nitoring has shown that the water taable has a very low graddient.

Therefore, it is likelyy that the grooundwater velocity v acrooss the site iss also relativvely slow (i..e., in the inch hes and feeet/day range). Groundwater elevaation data from the G-3 Coal Plant Environm mental Moniitoring Prog gram wells agree a with tthe regional groundwateer flow, andd also show seaasonal variaation on upw ward and do ownward graadients that are influennced by the river stage. Th a not sufficcient to charracterize the groundwateer flow below hese wells are w and arounnd the LACBW WR site structtures or areaas where poteential releases associatedd with LACBWR (i.e., iin the vicinity of suspect broken draain lines) co ould have ooccurred. Inn these areaas, pilings, deep structures/foundation ns or variatiions in fill materials m coould locally influence ggroundwater flow directionns.

2.3.7.3. Previous Investigation I ns Historicaally, the LAC CBWR Liceensed Site haas had severral potable w water wells and groundw water monitorin ng wells. Figure 2-11 illustrates thee current loccation of pootable water and groundw water monitorin ng wells loccated on the LACBWR R site. Theere is no pootable waterr or groundw water monitorin ng wells offf the LACB BWR site that t are or have been monitored by Solutionns or Dairyland for radiolo ogical purposes.

Of the wells w shown n on Figure 2-11, only Potable P Waater Wells N Nos. 3 and 4 which servviced LACBW WR facilities were historrically monittored by Daairyland for radiologicall conditions on a routine basis.

b The grroundwater monitoring m wells w and baackground grroundwater monitoring wells designateed as B-2, B-3, B-7, B-8, B-9, B-9A, B11A AR, and B B11R are m monitored byy the Environm mental Moniitoring staff on a routinee basis for noon-radiologiical parameteers to suppoort the G-3 Fosssil Station op perational reequirements. During LA ACBWR opeerations, Potaable Water W Wells Nos. 3, 4 and 5 werre routinely monitored for f gross beeta activity. Typical grross beta acctivity levels reported durin ng this mon nitoring periiod was lesss than or eqqual to MD DC (ranging from 3.0E-08 µCi/ml

µ to 9.0E-08 µCi/m ml).

During th he recovery of a probable spill incid dent in 1983 , a temporarry well-poinnt was establlished to the south of thee Turbine Building.

B This T incidennt concerneed the poteential leakagge of radioactivve liquids frrom suspect broken drain n lines in th e Turbine BBuilding to suub-building soils.

The welll-point show wn on Figure 2-11 was esstablished doown gradiennt and below w the grade oof the suspected d leakage. The T well-point was sam mpled once oon May 3, 19983. The annalysis results for that samp ple are preseented in Tablle 2-17. Thiis well-pointt has since beeen abandonned.

As noted in the LACBWR L Decommissio D oning Plan and Post-SShutdown D Decommissiooning Activitiess Report (DD-Plan/PSDA AR) (19), Dairyland reccently installled groundw water monittoring wells to support gro oundwater evaluation.

e In Novembber 2012, fiive (5) pairss of groundw water monitorin ng wells (10 0 wells total)) were installled within tthe LACBW WR licensed site to deterrmine if ground dwater quality had beeen impacted by plant ooperations. The well ppairs which were located nominally n wiithin five (5)) feet of onee another connsist of one shallow welll with a screeened interval of o 15 to 25 feet f below grade g and onne deep well with a screeened intervaal of 45 to 555 feet below grrade. These wells are sh how on Figu ure 2-11 as M MW 200A annd B through MW-204A A and B.

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La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Two (2) rounds of grroundwater samples werre collected in 2013, duuring the seaasonal high w water in June 2013 and th hen during a seasonal low l groundw water level in Novembber 2013. T These groundw water sampless were sent to an off-sitte laboratoryy for radioloogical analyssis for Co-600, Sr-90 and Cs-137.

C Analy ysis for H-3 was perform med on site.

In June ofo 2014, a third t round of o groundwaater sampless was colleccted from: M MW-200A aand B through 204 2 A and B; B Potable Water W Wells #3,

1. 4, 5, and 7; and Monnitoring Wellls B2, B-3, B B11R and B11AR. Thesee collected groundwater g samples were sent offf for radioloogical analyssis of several radionuclide r s including HTD and transuranic t rradionuclidees. In Septeember of 20014 a fourth ro ound of gro oundwater were w collecteed from: M MW 200A annd B througgh 204A annd B, Potable Well #5, an nd Monitoriing Wells B11R B and B B11AR. T These colleccted groundw water samples were sent off o for radio ological anaalysis of sevveral radionnuclides inclluding HTD D and transurannic radionucllides. Tablees 2-18 and 2-192 providees a summarry of the radiiological anaalysis of the grooundwater saamples and results.

r Addition nal details, in ncluding thee off-site anaalytical laborratory reporrts are provided in Referrence 18.

2.3.7.4. On-Going g Investigatioons The LAC CBWR Site groundwater g r monitoring g program coonsists of obbtaining grouundwater sam mples twice peer year for radiological r analysis puurposes onlyy from existing monitooring wells w when groundw water is at rellatively high her and loweer elevations . The monitoring wellss sampled include the MW--200A/B thru u MW-204A A/B wells as shown on Figure 2-11.

The colleected informmation during g each monittoring intervval includes:

Depth D to grouund water in the respectiive monitorinng well.

Monitoring M well w groundw water pH/speecific conducctance/oxidaation and redduction potential/turb bidity/dissolvved oxygen/ttemperature..

Radiological R sample inforrmation inclluding a com mpleted chainn of custodyy following grroundwater sample colleection.

2.3.7.5. Summ mary of Grou undwater An nalytical Ressults Groundw water charactterization eff fforts commeenced througgh the installlation of 10 monitoring wells (5 pairs) within the LSE area in Novemb ber 2012 annd the com mmencement of groundw water sampling g in 2013. H-3 H was positively detectted at concenntration greaater than MD DC in monittoring wells MW W-201A and d B, MW-20 02-A and B, MW-203A and B and M MW-204A aand B in June and Novembeer of 2013 at concentraations rangiing from 1550 pCi/L to 660 pCi/L. Sr-90 wass also positively y detected in i the same wells durin ng the June 2013 samplling period aat concentraations ranging from 1.43 pCi/Lp to 2.1 18 pCi/L; ho owever, it w was not poositively deteected duringg the Novembeer 2013 sam mpling period d. Co-60 an nd Cs-137 w were not positively deteected in anyy well during thhe 2013 samp pling period.

During th he June 2014 sample peeriod, H-3 was w positivelyy detected inn four (4) w wells (MW-B B11R, MW-202 2A, MW-203 3A and MW W-203B) at concentrationns ranging fr from 245 pCi/L to 336 ppCi/L.

Sr-90 was w also positively detected in wells w MW-2002A, MW-2203A and MW-204A with 2-35

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 concentraations rangin ng from 1.1 12 pCi/L to 2.01 pCi/L. C-14, Tc-999, Eu-152, Pu-239/2400 and Am-241 were also po ositively detected at residual concenntrations in seeveral wells.

During the Septemb ber 2014 sam mple period,, H-3 was nnot positivelly detected aat concentraations greater th han MDC in n any well. Sr-90 was positively ddetected in oone (1) welll, MW-200A A at a concentraation of 1.14 4 pCi/L. Co o-60, Ni-63,, Cs-137, Euu-152, Eu-1554, Pu-239/2240 and Am m-241 were also o positively detected d at residual r conccentrations inn several weells.

2.4. Continuing C Characteriz C zation The surv vey of many inaccessiblee or not read dily accessibble subsurfaace soils or ssurfaces has been deferred. Exampless of areas where w survey ys are deferrrred include soils underr structures, soils under concrete or asp phalt coverinngs, structurral wall and floor surfacces in some of the basem ments that will remain and d be subjeccted to FRS, the underl rlying concrrete in the R Reactor Buiilding basementt after linerr removal an nd the interriors of burried pipe thaat may rem main. Figuree 2-3 illustrates buried pip ping systemss that may remain r in thhe end-state condition. The decision to defer thee characterizzation of a soil or stru ucture was bbased on onne or more of the folloowing condition ns:

ALARA consideratio ons (e.g., thee area is eithher a radiatiion or contaamination areea and addittional data wou uld likely nott change thee survey areaa or area classsification oof the locatioon or surrounnding areas),

Safetty considerattions, Histo orical data sh hows that thee area could be classifiedd without furrther charactterization, Access for characcterization would w requiree significantt deconstructtion of adjaccent systemss, structtures or otheer obstacles where w the reemoval couldd result in ann unsafe conndition or interffere with conntinued operration of opeerating system ms, or The ability a to usee engineeringg judgment in i assigning the area a cllassificationn based on physiical relationsship to surro ounding areas and the likkelihood of thhe area to haave radiologgical condiitions repressented by thee conditions in these adjaacent areas.

As accesss is gained to areas thaat were prev viously inacccessible, addditional charracterizationn data will be co ollected, evaaluated and stored s with-o other radioloogical surveyy data in a survey historry file for the survey s unit. This data will be useed along wiith existing data to upddate the typpes of radionuclides presentt and updatee the variabillity in the raadionuclide m mix for bothh gamma-em mitting and HTD D radionuclid des. In addiition, as the decommiss ioning progrresses, data from operattional events caaused by equ uipment failuures or perso onnel errors,, which mayy affect the raadiological sstatus of a surv vey unit(s) will w be reco orded. Thesse events w will be evaluuated and, w when approppriate, stored inn the characterization database. Th his additionaal characterrization dataa will be used in validating the initial classification and in plan nning for thee FRS.

As decom mmissioning g proceeds, areas will, as necessarry, be deconntaminated to remove loose surface decontamina d ation (as welll as fixed co ontaminationn) to levels that will meeet the condiitions for open n air demolittion or unreestricted releease. Whenn a structure is ready ffor demolitiion, a documen nted survey anda a formall turnover willw be made by the Radiological Prootection grouup for 2-36

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 the comp pany preform ming demoliition, validatting that thee radiologicaal conditions in the struucture are suitabble.

Followin ng the demollition and/orr remediation n, and whenn an area is bbelieved to bbe ready for FRS, a "turnov ver assessmeent" will be performed.

p If I the resultss of this asseessment indiicate that thee FRS acceptance criteria will w be met,, then physiical and adm ministrative control of the area wiill be transferreed to Characcterization/LLicense Term mination grouup personnel for preparaation, designn, and performaance of the FRS.

F Otherwwise, additioonal remediaation may bbe required. This assesssment may inclu ude a "turnoover survey,"" primarily for fo Class 1 annd 2 areas w within the LSSE.

The "turn nover surveey" process, together wiith any addiitional charaacterization and remediiation survey peerformed, reepresent at leeast one, butt possibly seeveral, oppoortunities to ccollect addittional survey daata prior to conducting c the t FRS. Fo or each type of survey (ccharacterizattion, remediaation, turnover,, and FRS), a documenteed survey plan will be ddeveloped using the DQO O process. T These survey plans will co ontain the ap ppropriate daata assessmeent to ensurre that severral objectivees are met. Theese objectivees include:

Apprropriate instrrument selecction to ensurre the properr sensitivity relative to thhe applicablle action n level and/oor release criiteria, Apprropriate instrrument qualiity control measures m to eensure operabbility, Apprropriate survey techniquees to ensure that the fieldd measurement techniquues are consiistent with the calibration methodollogies, Apprropriate samp ple collection and analyssis to determ mine spatial vvariability annd variabilityy in radionuclide ratioos, Data analysis critteria to identtify follow-u up actions suuch as remeddiation and thhe collectionn of additional samplees and, Apprropriate classsification of the survey area.

a 2.5. References R

1. U.S.

U Nuclear Regulatory Commission n, Regulatorry Guide 1.179, Standardd Format andd Content C of Liicense Termiination Plans for Nucleaar Power Reaactors, Revission 1 - Junee 2011.

2. U.S.

U Nuclear Regulatory Commission n, NUREG-11575, Revisiion 1, Multi--Agency Radiation R Surrvey and Sitee Investigatiion Manual ((MARSSIM M), August 20000.

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. EnergySoluti E ons PG-EO--313196-SV-PL-001, Chharacterizatioon Survey P Plan for the L La Crosse C Boilin ng Water Reaactor.

5. EnergySoluti E ons GP-EO--313196-QA A-PL-001, Quuality Assurrance Projectt Plan LACB BWR Site Characteerization Projject (QAPP)).

2-37

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

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

7. Dairyland D Power Corporaation LAC-T TR-138, Initiial Site Charracterizationn Survey for SAFSTOR - December 2009. 2

8. 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 20 006.

9. Sandia Nation nal Laborato ory, NUREG G/CR-5512, V Volume 3, R Residual Raddioactive Contaminatio C on From Deccommissioniing Parameteer Analysis - October 19999.

10. EnergySoluti E ons Techniccal Support Document D R RS-TD-3131996-006, Luddlum Model 444-10 Detector Sensitivity.

S

11. U.S.

U Nuclear Regulatory Commission n, NUREG-11576, Multi--Agency Raddiological Laboratory L Analytical A Prootocols Man nual (MARL LAP) - Auguust 2001.

12. U.S.

U Nuclear Regulatory Commission n Regulatoryy Guide 4.155, Quality Assurance or Radiological R Monitoring Programs (IInception Thhrough Norm mal Operations to Licensse Termination)

T - Effluent Streams S and the Environnment - July 2007.

13. EnergySoluti E ons GG-EO--313196-RS S-RP-001, LA ACBWR Raadiological C Characterizattion Survey Reporrt for Octobeer and Novem mber 2014 F Field Work - Novemberr 2015.

14. EnergySoluti E ons LC-RS-PN-164017--001, LACB BWR Radioloogical Charaacterization Survey Reporrt for June th hru August 2015 2 Field W Work - Noveember 2015.

15. ZionSolution Z s Technical Support Doccument 13-0004, Examinnation of Cs-137 Global Fallout in Soiils at Zion Sttation.

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

17. Haley H & Aldrrich, Hydrog geological Conceptual Siite Model, FFile No. 387005-001 - Auugust 30, 2012.

18. Haley H & Aldrrich Inc., Hy ydrogeologiccal Investigaation Report,, La Crosse BBoiling Watter Reactor, R Dairryland Power Cooperativ ve, Genoa W Wisconsin, Fiile No. 387005-008, January 2015.

19. Dairyland D Power Cooperaative, LACB BWR Decom mmissioning Plan and Poost Shutdownn Decommissio D oning Activitties Report (D-Plan/PSD

( DAR), Revission - Marchh 2014.

20. In nternational Standard ISO 7503-1, Part P 1, Evaluaation of Surfface Contam mination, Betta-Emitters E (maxximum beta energy greaater than 0.155 MeV) and Alpha-Emittters - Auguust 1998.

2-38

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-1 LACBW WR Open L Land Surveyy Units Survey Surveyy Unit Descrription Initial Approxim mate Unit ID # Cllassification n Survey U Unit Area (mm2)

LAACBWR Sitte Enclosuree Grounds Reactorr Building, WTB, W WGTV V, Ventilatioon L10101001 Class 1 1,9922 Stack Grounds G

Turbinee Building, Turbine T Office Building,, 1B L10101002 Class 1 2,3155 Diesel Generator G Buuilding Grouunds L10101003 LSA Bu uilding, Maintenance Eaat Shack Groounds Class 1 1,7499 L10101004 North LSE L Groundss Class 1 2,3877 LSE Bufffer Zone Groounds LACBW WR Adminisstration Buillding, LACB BWR L20111001 Class 2 7,2111 Crib Hoouse, Warehouse Ground ds G-3 Criib House, LAACBWR Cirrc. Water L20111002 Class 2 6,7855 Discharrge Line, Areea South of LSE L Fence Classs 3 Groundss L30121001 North End E of Licen nsed Site Class 3 24,042 L30121002 Transmmission Switcchyard Area Class 3 11,711 L30121009 Plant Access, A ISFSII Haul Road d Grounds Class 3 31,012 Non-Immpacted Grouunds L40121003 G-3 Coal Plant Gro ounds Noon-Impactedd 66,869 L40121005 Coal Pile Grounds Noon-Impactedd 82,894 L40121006 Cappedd Ash Impou undment Gro ounds Noon-Impactedd 111,8999 L40121007 Groundds East of Highway 35 Noon-Impactedd 81,254 L40121008 Hwy 35 5/Railroad Right R of Wayy Grounds Noon-Impactedd 9,4444 2-39

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-2 LACBW WR Structu ural Surveyy Units Surveey Unit Surrvey Area Description D Classsification B10110001 Reactor Bu uilding Cllass 1 B10110002 Waaste Treatmen nt Building Cllass 1 B10110003 LACCBWR Ventiilation Stackk Cllass 1 B10110004 Waste W Gas Taank Vault Cllass 1 LACBWR R Turbine Blddg./Turbine Office B10110005 Cllass 1 Bldg.

B10110006 LACBWR 1B Diesel Generator G Strructure Cllass 1 B10110007 LSA Buillding Cllass 1 B10110008 Maintenance M Eat E Shack Cllass 1 B10110009 Pipe Tunnnel Cllass 1 B20110101 LACBWR Crrib House Cllass 2 B20110102 G-3 Crib House H Cllass 2 B20110103 LACBW WR Administtration Buildding Cllass 2 B20110104 LAACBWR Warrehouse #1 Cllass 2 B20110105 LAACBWR Warrehouse #2 Cllass 2 B20110106 LAACBWR Warrehouse #3 Cllass 2 B30112101 Baack-up Contrrol Center Cllass 3 B30112102 Transmissiion Sub-Stattion Switch HHouse Cllass 3 B30112103 G-1 Crib House H Cllass 3 B30112104 Barg ge Washing Break B Roomm Cllass 3 2-40

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tablee 2-2 (continnued) LACBWR Structural Survey Uniits Non Imp pacted Strucctures G-3 Reclaim R Buillding G-3 Annnex Buildinng G-3 Stock S Out Trransfer Buildding G-3 Booiler Fuel Oiil Pump Building G-3 Coal C Unloading Tower G-3 Exxplosive Gass Storage Rooom G-3 Transfer T Tow wer A G-3 Gaas Room G-3 Electrical E Ro oom G-3 Suub Station Shhed G-3 Crusher C Towwer G-3 Suub Station Shhed G-3 Conveyor C #6 6 (2) G-3 Liime Storage Silo G-4 Warehouse W and a Electricaal Room G-3 W Weigh Stationn G-3 LRAPB L Buillding G-3 Acctive Reclaimm Buildingss/ Tunnel G-3 Lime L Silo Electrical Buillding G-3 Assh Coordinaators Office G-3 CAT C Buildinng G-3 Baag Houses (55)

G-3 Coal C Plant G-3 Fl ammable Sttorage Shed G-3 Vehicle V Storaage Building g #7 We ll House G-3 Train T Shed G-3 Cooal Scale G-3 Bottom B Ash Dewatering Buildings G-3 Saample Buildiing G-3 Fly F Ash Silo G-3 Sttock Out Traansfer Buildiing G-3 Fly F Ash Elecctrical Buildiing G-3 Grrid Shed G-3 Waste W Silo G-3 Assh handling Blower Buillding G-3 Surge S Tank Main PPollution Coontrol Electriical Buildingg G-3 Settling S Tankk S03 Taank Buildingg

1. 6 Well W House 2-41

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2-3 Instrumeent Types aand Nominaal MDCs Ty Typical Detection Sensittivity Deteector Modell b Meeter Model Applicaation MDCscan MDCsttatica (dp pm/100cm ) (dpm/100cm2) 2 Ludlumm 44-9 Ludllum 3 scaan 1,0000 to 2,0000 N/AA Ludlumm 43-68 mo ode Ludllum 2350-1 static & scan 1,8800 to 2,0000 600 to 700 Ludlumm 43-68 mo ode Ludllum 2350-1 stattic N/A 80 to 90 Ludlumm 43-93 mo ode 1,8800 to 2,0000 800 to 900 Ludllum 2360 static & scan Ludlumm 43-89 mo ode 2,0000 to 2,2000 800 to 900 Ludlumm 43-93 mo ode 90 to 1100 Ludllum 2360 stattic N/A Ludlumm 43-89 mo ode 90 to 1100 3.55 pCi/g 60Coo Ludlumm 44-10 Ludllum 2350-1 scaan N/AA 6.55 pCi/g 137Css Ludlumm 43-37 Ludllum 2350-1 scaan 2,0000 to 2,2000 N/AA and/ or -15 Ludlumm 43-10-1 Ludllum 2929 N/A smeaar -80

~0.10 ppCi/g Gammaa Spectroscop py N/A Anallysis N/A for Co-660 and System Cs-1337 a Based on 1-minutee count time; and a default valu ues for surface efficiencies (s) as specified in Internationaal ndard, ISO 750 Stan 03-1 (20).

b Fun nctional equivallent instrumenttation may be used u

2-42

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-4 Off-Sitee Laboratory y Analyticaal Methods aand Typicall MDCs Analysis / Analytes Technique Method and d Sensitivity Soils (pCi//g) Watter (pCi/L)

Gamma Gamma G Spec DOE EML E HASL 3000 EPA Method 901.1 Radionucliides < 0.1pC Ci/g 10.0 pCi/L Isotopic Neptunium Alpha A Spec DOE EML E HASL 3000 (Np-237) < 0.04 pCi/g p

Isotopic Pllutonium Alpha A Spec DOE EML E HASL 3000 EML Pu-02 M Modified (Pu-238/2339/240) < 0.05 pCi/g p 1.0 pCi/L Isotopic Thhorium Alpha A Spec DOE EML E HASL 3000 (Th-228/23 30/232) < 0.05 pCi/g p

Isotopic Urranium Alpha A Spec DOE EML E HASL 3000 (U-234/235 5/238) < 0.06 pCi/g p

Isotopic Cuurium Alpha A Spec DOE EML E HASL 3000 (Cm-243/2 244) < 0.03 pCi/g p

Isotopic Am mericium Alpha A Spec DOE EML E HASL 3000 (Am-241/2 243) < 0.04 pCi/g p

C-14 LS SC EPA EE ERF C-01 ENIC Modifiied

< 5.0 pC Ci/g 50.0 pCi/L Tritium LS SC EPA 90 06.0 EPA 906.0

< 10.0 pCi/g p 300.0 pCi/L Sr-90 GFPC G DOE EML E HASL 3000 EICHROM M Modified Methood

< 1.0 pC Ci/ 2.0 pCi/L Pu-241 LS SC DOE EML E HASL 3000 EML Pu-01

< 10.0 pCi/g p 50.0 pCi/L Tc-99 LS SC DOE EML E HASL 3000 EICHROM T Tc-01

< 2.0 pC Ci/g 15.0 pCi/L Gross Alph ha / Beta GFPC G EPA 900.0 5.0 pCi/L Fe-55 LS SC DOE EML E HASL 3000 EML Fe-01 M Modified

< 10.0 pCi/g p 100.0 pCi/L Ni-63 LS SC DOE EML E HASL 3000 (SRW01) EML Ni-01 M Modified

< 2.0 pC Ci/g 15.0 pCi/L Ni-59 LS SC DOE EML E HASL 3000 (SRW01) EML Ni-01 M Modified

< 50.0 pCi/g p 100.0 pCi/L 2-43

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Taable 2-5 2005 Dairyyland Backgground Stud dy for Soils Co-60 Cs--137 Location (pCi/g) (pCCi/g)

(on Licensed L Sitee)

Area West ofo #2 Warehhouse <MDC 0.0077 Area South of Parking Lot L <MDC 0.0026 Area North of LACBWR Admin Bu uilding <MDC 0.149 Area at G-3 Gas Silo <MDC 0.0038 Area Outsidde G-3 Offices <MDC 0.0076 Area at G-3 Outfall <MDC 0.0017 (off Licensed L Sitee) 33 miles South at Bad Axe A Boat Lan nding 0.023 0.3381 Pedretti Farm Substationn East of LAACBWR <MDC 0.2227 Radio Toweer Northeast of LACBW WR <MDC 0.0035 Junction of Hwy O and Hwy K <MDC 0.188 East of Stod ddard at Hwyy O Junction n <MDC 0.0065 2-44

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table T 2-6 Investiga ative Levels for Cs-137 Based on B Background d Studies Meassured Rangge R Range for 955% Distribu ution Conditioon and Deptth (pCi/g) (p pCi/g)

Drainage D Areas Surfacee 0-10 cm Undisturbbed 0.00 to 2.80 0.455 to 3.63 Disturbedd 0.00 to 1.67 0.355 to 2.86 Nonn-Drainage Areas Surfaace 0-10 cm m

Undisturbbed 0.23 to 0.66 0.155 to 0.77 Disturbedd 0.27 to 0.34 0.23 to 0.42 2-45

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Table 2-7 Initia al Suite of LACBWR L SSite-Specificc Radionucllides Radio onuclide Haalf Life (Yeaars)

H-3 H 1.24E+01 C-14 C 5.73E+03 Fee-55 2.70E+00 Ni-59 7.50E+04 Co o-60 5.27E+00 Ni-63 9.60E+01 Srr-90 2.91E+01 Nb b-94 2.03E+04 Tcc-99 2.13E+05 Cs-137 3.00E+01 Eu u-152 1.33E+01 Eu u-154 8.80E+00 Eu u-155 4.76E+00 Np p-237 2.14E+06 Puu-238 8.78E+01 Puu-239 2.41E+04 Puu-240 6.60E+03 Puu-241 1.44E+01 Am m-241 4.32E+02 Cm-24 43/244* 1.81E+01

• L Listed half life is i the shortest half h life for thee radionuclidess in the pair 2-46

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-8 Non-Impacted Open Land Survey Units - Characterizattion Survey Su ummary S

Survey Unit Survey Unitt L4012103 Survey Unit L4012105 Survey Unit L L4012106 Survey Unit L L4012107 2 2 2 Surface Area 66,869 m 82,894 m 111,899 m 1 881,254m2 C

Capped Ash Immpoundment G Grounds East off Description G-3 Coal Plannt Grounds Coal Pile Grounds G

Grounds H Highway 35 S

Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 3 3 3 3 3 3

1. >CL 0 1 0 1 0 2 0 3 M

Mean (pCi/g) 0.070 0.082 0.071 0.061 0.082 0.100 0.080 0.264 M

Median (pCi/g) 0.075 0.083 0.072 0.060 0.084 0.099 0.079 0.263 M

Max (pCi/g) 0.078 0.092 0.084 0.068 0.090 0.121 0.089 0.463 M

Min (pCi/g) 0.057 0.071 0.057 0.055 0.072 0.079 0.072 0.065 S

SD 0.011 0.011 0.014 0.006 0.009 0.021 0.009 0.199 S

Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 4 4 3 3 4 4 3 3

1. >CL 0 1 0 1 0 2 0 2 M

Mean (pCi/g) 0.060 0.048 0.061 0.042 0.081 0.088 0.081 0.068 M

Median (pCi/g) 0.056 0.038 0.063 0.040 0.083 0.084 0.069 0.057 M

Max (pCi/g) 0.084 0.081 0.068 0.056 0.102 0.130 0.106 0.091 M

Min (pCi/g) 0.047 0.036 0.052 0.030 0.056 0.054 0.068 0.056 S

SD 0.016 0.022 0.008 0.013 0.021 0.037 0.022 0.020 A

Asphalt Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 2 2

1. >CL 0 0 M

Mean (pCi/g) 0.073 0.062 M

Median (pCi/g) None Taken None Taken 0.073 0.062 None Takken M

Max (pCi/g) 0.082 0.084 M

Min (pCi/g) 0.065 0.040 S

SD 0.012 0.031 Surface Scans

% Scanned 1% 1% 1%

1 1%

M Mean Scan (cpm) 5,550 5,050 8 8,340 8,000 M

Max Scan (cpm) 6,700 8,800 1 12,000 9,080 2-47

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Tablle 2-8 (continueed) Non-IImpacted Open n Land Survey Units - Charaacterization Surrvey Summaryy Survey Unit Survey Unit L4012108 Survey Unit LL4012109 Surface Area 9,444 m2 1 m2 100 Hwy 35/Railroad Right of Background B Soiils Test Description Way Grounds Area (inside L40012108)

A Surface Soil Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 17 17

1. >CL 0 2 0 17 Mean M (pCi/g) 0.079 0.119 0.087 0.160 Median M (pCi/g) 0.075 0.108 0.086 0.161 Max M (pCi/g) 0.095 0.156 0.101 0.268 Min M (pCi/g) 0.068 0.093 0.077 0.059 SDD 0.014 0.033 0.007 0.059 Subsurface Soil Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3

1. >CL 0 2 Mean M (pCi/g) 0.086 0.189 Median M (pCi/g) 0.092 0.091 None Taaken Max M (pCi/g) 0.107 0.409 Min M (pCi/g) 0.060 0.067 SDD 0.024 0.191 Asphalt A Co-60 Cs-137 Co-60 Cs-137

1. of Samples

1. >CL Mean M (pCi/g)

Median M (pCi/g) None Taken None Taaken Max M (pCi/g)

Min M (pCi/g)

SDD Surface Scans

% Scanned 1%

Mean M Scan (cpm) 8,124 No Scanning PPerformed Max M Scan (cpm) 9,200 2-48

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 2-9 Non Impa acted Coal Pile and Soil Samp ples - Test Ameerica Laboratorry Analysis (pC Ci/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 N Ni-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L3012103-QJ-GS-001-S SB 4.390 1.230 3.430 1 .470 0.026 2.140 0.321 0 0.018 0.820 0.024 0 0.714 0 0.071 0.190 00.095 0.025 0.046 0 0.015 11.730 0.032 0.022 0 0.010 L

L3012103-QJ-GS-001-S SS 3.570 0..671 2.790 1 .870 0.027 3.380 0.391 0 0.022 0.628 0.018 0 0.847 0 0.060 0.167 00.096 0.024 0.040 0 0.021 11.650 0.025 0.024 0 0.019 L

L3012105-Genoa Coal Pile P 0.018 0 0.022 0.019 0 0 0.052 0.152 00.048 0.041 L

L3012105-CR-GS-002- -SS 0.533 0..675 2.130 1 .730 0.025 2.950 0.289 0 0.016 0.587 0.018 0 0.698 0 0.051 0.137 00.056 0.023 0.036 0 0.029 11.670 0.018 0.025 0 0.006 L

L3012105-QJ-GS-001-S SB 0.026 0 0.020 0.023 0 0 0.049 0.166 00.055 0.048 L

L3012105-QJ-GS-001-S SS 0.030 0 0.020 0.028 0 0 0.072 0.199 00.074 0.061 L

L3012106-QJ-GS-001-S SB 14.600 0..713 2.300 2 .370 0.037 3.950 0.348 0 0.030 0.611 0.319 1.500 0 0.115 0.223 00.080 0.035 0.036 0 0.014 22.550 0.019 0.034 0 0.006 L

L3012106-QJ-GS-001-S SS 0.813 0..713 3.550 2 .560 0.037 3.580 0.338 0 0.028 0.616 0.096 0.826 0 0.079 0.232 00.112 0.027 0.044 0 0.026 22.740 0.025 0.013 0 0.019 L

L3012107-QJ-GS-001-S SB 0.019 0 0.013 0.021 0 0 0.045 0.115 00.038 0.034 L

L3012107-QJ-GS-001-S SS 1.420 0..719 3.610 2 .800 0.025 3.940 0.293 0 0.019 0.593 0.018 1.450 0 0.049 0.156 00.048 0.040 0.021 0 0.024 22.580 0.020 0.035 0 0.006 L

L3012108-QJ-GS-001-S SB 2.350 0..705 1.920 3 .110 0.018 4.440 0.278 0 0.016 0.604 0.033 1.310 0 0.041 0.128 00.044 0.030 0.026 0 0.021 22.670 0.017 0.036 0 0.017 L

L3012108-QJ-GS-001-S SS 6.490 0..728 2.260 3 .200 0.030 4.710 0.271 0 0.020 0.576 0.182 0.770 0 0.059 0.176 00.060 0.020 0.028 0 0.029 22.740 0.015 0.024 0 0.015 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value b Survey units originally classified as Class 3 at time of sampple 2-49

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-10 Impacted Cla ass 1 Open Land d Survey Unitss - Characterizzation Survey SSummary S

Survey Unit Survey Unitt L1010101 Survey Unit L1010102 Survey Unit L L1010103 Survey Unit L L1010104 2 2 2 Surface Area 1,992 m 2,315 m 1,749 m 1 22,387 m2 Reactor Buillding, WTB, Turbine, Officee, Diesel L LSA Building, Description WGTV, Venttilation Stack Generator Building M Maintenance Eaat Shack NNorth LSE Grouunds Grounds Grounds G Grounds S

Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 12 12 2 2 7 7 1 1

1. >CL 2 12 0 0 0 1 0 0 M

Mean (pCi/g) 0.080 0.215 0.049 0.050 0.059 0.069 0.045 0.049 M

Median (pCi/g) 0.058 0.100 0.049 0.050 0.050 0.054 0.045 0.049 M

Max (pCi/g) 0.287 1.070 0.054 0.051 0.099 0.161 0.045 0.049 M

Min (pCi/g) 0.048 0.032 0.044 0.050 0.048 0.048 0.045 0.049 S

SD 0.066 0.296 0.007 0.001 0.019 0.041 N/A N/A S

Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 18 18 22 22 25 25 14 14

1. >CL 0 8 0 4 0 0 0 3 M

Mean (pCi/g) 0.078 0.066 0.058 0.064 0.046 0.049 0.048 0.041 M

Median (pCi/g) 0.052 0.054 0.058 0.065 0.046 0.049 0.048 0.042 M

Max (pCi/g) 0.516 0.161 0.080 0.130 0.055 0.054 0.050 0.051 M

Min (pCi/g) 0.047 0.033 0.043 0.044 0.025 0.042 0.043 0.027 S

SD 0.109 0.035 0.010 0.017 0.005 0.003 0.002 0.009 A

Asphalt Co-60 Cs-137

1. of Samples 10 10

1. >CL 0 1 M

Mean (pCi/g) 0.053 0.051 M

Median (pCi/g) None Taken None Taken N None Taken 0.054 0.053 M

Max (pCi/g) 0.062 0.057 M

Min (pCi/g) 0.042 0.037 S

SD 0.006 0.006 S

Surface Scans

% Scanned M

Mean Scan (cpm) No Scanning Performed P No Scanning Performed N Scanning Peerformed No No Scanning Peerformed M

Max Scan (cpm) a MDC vaalue used for anaalytical results less l than MDC.

2-50

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 T

Table 2-11 Class 1 Concretee, Asphalt, Sed diment and Soill Samples - Tesst America Lab boratory Analyysis (pCi/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 NNi-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L1010101-CJ-GS-002-SSS 0.024 0 0.020 0.233 0 0.056 0.161 00.066 0.058 L

L1010101-CJ-GS-009-SSS 0.040 0 0.020 0.185 0 0.056 0.181 00.050 0.042 L

L1010101-CJ-GS-010-SSS 0.286 0 0.025 0.413 0 0.062 0.247 00.057 0.051 L

L1010101-QJ-GS-001-SSB 0.364 0.896 2.430 1 .850 0.024 3.040 0.335 0 0.015 0.579 0.020 0 0.800 0 0.050 0.143 00.044 0.019 0.046 0 0.023 11.970 0.015 0.023 0 0.021 L

L1010101-QJ-GS-001-SSS 0.441 0..676 2.190 1 .900 0.018 3.040 0.440 0 0.012 0.587 0.147 3.170 0 0.034 0.112 00.044 0.006 0.039 0 0.023 11.830 0.016 0.021 0 0.019 L

L1010101-QJ-GS-002-SSB 0.377 0..679 2.150 1 .750 0.017 2.930 0.338 0 0.011 0.620 0.149 0.772 0 0.040 0.109 00.040 0.019 0.041 0 0.022 11.950 0.017 0.029 0 0.014 L

L1010101-QJ-GS-002-SSS 1.380 0..677 4.190 2 .010 0.015 3.320 0.357 0 0.010 0.521 0.059 0.978 0 0.033 0.096 00.036 0.016 0.040 0 0.016 22.090 0.020 0.017 0 0.022 L

L1010102-CJ-FC-001-CCV 1.710 0..727 1.650 2 .630 0.106 3.920 0.292 0 0.022 0.536 0.352 1.290 0 0.061 0.239 00.062 0.029 0.041 0 0.028 22.490 0.018 0.019 0 0.021 L

L1010102-CJ-GS-013-SSB 0.030 0 0.016 0.021 0 0 0.044 0.170 00.041 0.036 L

L1010102-QJ-GS-001-SSB 8.740 0..726 2.120 2 .620 0.015 4.000 0.310 0 0.011 0.539 0.012 0 0.961 0 0.030 0.101 00.028 0.028 0.040 0 0.026 22.780 0.015 0.020 0 0.021 L

L1010102-QJ-GS-001-SSS 0.022 0 0.015 0.018 0 0 0.036 0.113 00.042 0.039 L

L1010102-QJ-GS-002-SSB 24.700 0..715 2.230 2 .760 0.021 3.920 0.316 0 0.014 0.537 0.016 0 0.722 0 0.043 0.139 00.042 0.032 0.042 0 0.029 22.660 0.015 0.021 0 0.018 L

L1010103-CJ-GS-002-SSB 0.011 0 0.017 0.021 0 0 0.044 0.181 00.046 0.044 L

L1010103-QJ-SL-001-SSM 0.354 0.453 0.689 00.711 0.136 1.090 0.132 0 0.018 0.432 0.136 0.360 0 0.054 0.199 00.049 0.018 0.015 0 0.015 00.867 0.008 0.019 0 0.008 L

L1010103-QJ-GS-001-SSB 3.260 0..715 1.830 2 .850 0.017 4.240 0.333 0 0.011 0.606 0.015 0 0.740 0 0.036 0.117 00.039 0.026 0.029 0 0.017 11.430 0.009 0.024 0 0.005 L

L1010103-QJ-GS-001-SSS 0.025 0 0.015 0.020 0 0 0.046 0.174 00.047 0.043 L

L1010103-QJ-GS-002-SSB 0.649 0..702 2.100 2 .620 0.014 3.710 0.325 0 0.012 0.645 0.012 0 0.838 0 0.029 0.103 00.034 0.020 0.034 0 0.024 22.570 0.018 0.024 0 0.014 L

L1010103-QJ-GS-002-SSS 0.019 0 0.017 0.017 0 0 0.040 0.139 00.045 0.024 L

L1010103-QJ-GS-003-SSB 0.654 0..717 2.340 2 .630 0.012 3.660 0.300 0 0.009 0.557 0.011 0 0.713 0 0.029 0.092 00.034 0.040 0.028 0 0.028 22.470 0.018 0.022 0 0.005 L

L1010103-QJ-GS-003-SSS 0.023 0 0.019 0.091 0 0.057 0.186 00.063 0.052 L

L1010104-CJ-GS-003-SSB 0.015 0 0.008 0.013 0 0 0.032 0.078 00.036 0.034 L

L1010104-CR-PA-007- -AV 0.021 0 0.014 0.016 0 0 0.042 0.141 00.044 0.040 L

L1010104-QQ-PA-001- -AV 0.025 0 0.025 0.028 0 0 0.058 0.218 00.061 0.050 L1010104-QR-GS-001--SB L 0.017 0 0.011 0.012 0 0 0.038 0.132 00.032 0.032 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value.

2-51

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tablle 2-12 Im mpacted Cla ass 2 Open Land L Surveey Units - CCharacterizaation Surveey Summary S

Surrvey Unit Surrvey Unit L201 11101 Surrvey Unit L20111102 Surface Area 7,211 m2 6,785 m2 LACBWR R Admministration G-3 Cribb House, LACBWR Description Building, LACBW WR Crib Circ. Waater Dischaarge Line, House, Warehouse W Grrounds Area Soutth of LSE Feence Surrface Soil Co-600 Cs-137 Co-600 Cs-137

1. off Samples 13 13 10 10

1. >CCL 0 8 0 6 Meaan (pCi/g) 0.0733 0.090 0.0644 0.065 Med dian (pCi/g) 0.0777 0.100 0.0644 0.054 Max x (pCi/g) 0.1066 0.139 0.081 0.200 Minn (pCi/g) 0.0533 0.041 0.0522 0.030 SD 0.0166 0.030 0.0099 0.049 Subbsurface Soil Co-600 Cs-137 Co-600 Cs-137

1. off Samples 16 16 7 7

1. >CCL 1 2 0 2 Meaan (pCi/g) 0.0522 0.049 0.0499 0.038 Med dian (pCi/g) 0.0466 0.048 0.0488 0.033 Max x (pCi/g) 0.1122 0.088 0.0555 0.052 Minn (pCi/g) 0.0400 0.034 0.0422 0.029 SD 0.0188 0.012 0.0044 0.009 Aspphalt Co-600 Cs-137 Co-600 Cs-137

1. off Samples 6 6 6 6

1. >CCL 0 0 0 3 Meaan (pCi/g) 0.051 0.051 0.0566 0.048 Med dian (pCi/g) 0.051 0.051 0.0577 0.051 Max x (pCi/g) 0.0544 0.054 0.0599 0.055 Minn (pCi/g) 0.0477 0.047 0.0499 0.009 SD 0.0022 0.003 0.0033 0.008 Surrface Scans

% Scanned S 50% 50%

Meaan Scan (cpm) 7,500 to 8,000 7,500 to 8,0000 Max x Scan (cpm) 11,500 to 12 2,000 111,500 to 12,0000 2-52

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 22-13 Class 2 Asphalt, Sedim ment and Soil Samples S - Test America Labooratory Analysiis Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 N Ni-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L2011101-CJ-GS-001-S SM 0.096 0 0.011 0.137 0 0.041 0.098 00.033 0.031 L

L2011101-CR-PA-003--AV 0.023 0 0.016 0.017 0 0 0.039 0.131 00.039 0.038 L

L2011101-QJ-GS-001-S SB 0.518 0..727 2.290 2 .660 0.016 4.030 0.273 0 0.014 0.643 0.015 0 0.705 0 0.033 0.108 00.040 0.022 0.028 0 0.025 22.470 0.015 0.022 0 0.019 L

L2011101-QJ-GS-001-S SM 2.040 0..707 2.240 2 .950 0.049 4.140 0.523 0 0.018 0.585 0.107 0.615 0 0.048 0.178 00.049 0.026 0.045 0 0.021 33.100 0.037 0.036 0 0.034 L

L2011101-QJ-GS-001-S SS 0.012 0 0.020 0.080 0 0.060 0.188 00.091 0.042 L

L2011101-QQ-GS-001--SB 0.017 0 0.012 0.013 0 0 0.040 0.127 00.037 0.031 L

L2011101-QQ-GS-001--SS 11.810 0..726 2.590 2 .600 0.035 3.720 0.255 0 0.035 0.532 0.103 0.779 0 0.097 0.205 00.102 0.023 0.037 0 0.024 22.800 0.019 0.015 0 0.015 L

L2011101-QQ-GS-002--SB 2.500 0..731 1.940 2 .680 0.017 3.870 0.314 0 0.014 0.616 0.016 0 0.697 0 0.037 0.119 00.041 0.019 0.039 0 0.016 22.920 0.020 0.028 0 0.016 L

L2011101-QQ-PA-001--AV 0.022 0 0.015 0.015 0 0 0.046 0.135 00.042 0.040 L

L2011102-QQ-GS-001--SB 1.370 1.560 2.260 3 .040 0.007 4.390 0.291 0 0.018 0.537 0.021 0 0.672 0 0.044 0.173 00.055 0.031 0.026 0 0.018 22.680 0.029 0.028 0 0.024 L

L2011102-QQ-GS-001--SS 0.533 0..713 2.330 2 .820 0.019 4.300 0.361 0 0.014 0.595 0.014 0 0.772 0 0.039 0.111 00.045 0.017 0.036 0 0.026 22.880 0.026 0.034 0 0.021 L

L2011102-QQ-GS-002--SB 0.525 0..702 3.890 2 .880 0.031 3.950 0.327 0 0.016 0.568 0.018 0 0.717 0 0.052 0.183 00.051 0.022 0.028 0 0.020 11.710 0.010 0.028 0 0.006 L

L2011102-QQ-PA-001--AV 0.027 0 0.017 0.018 0 0 0.051 0.142 00.038 0.036 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

2-53

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-14 Impacted Cla ass 3 Open Land d Survey Unitss - Characterizzation Survey S Summary Survey Unit Survey Unitt L3012101 Survey Unit L3012102 Survey Unit LL3012109 Surface Area 24,042 m2 11,711 m2 331,012 m2 PPlant Access, ISFSI Haul Road Description North End of Liccensed Site Transmission Switchyard Area GGrounds Surface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 5 5

1. >CL 0 0 0 5 Mean M (pCi/g) 0.070 0.073 0.063 0.152 Median M (pCi/g) 0.076 0.072 None Taken T 0.064 0.143 Max M (pCi/g) 0.077 0.083 0.078 0.267 Min M (pCi/g) 0.058 0.065 0.053 0.075 SD 0.011 0.009 0.010 0.078 Subsurface Soil Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 4 4

1. >CL 0 0 0 0 Mean M (pCi/g) 0.051 0.051 0.072 0.066 Median M (pCi/g) 0.053 0.052 None Taken T 0.072 0.059 Max M (pCi/g) 0.054 0.052 0.100 0.101 Min M (pCi/g) 0.046 0.051 0.046 0.045 SD 0.004 0.001 0.023 0.025 Concrete/Asphalt C Co-60 Cs-137 Co-60 Cs-137 Co-60 Cs-137

1. of Samples 3 3 7 7

1. >CL 0 0 0 0 Mean M (pCi/g) 0.031 0.029 0.062 0.059 Median M (pCi/g) 0.031 0.027 None Taken 0.055 0.052 Max M (pCi/g) 0.035 0.033 0.080 0.079 Min M (pCi/g) 0.028 0.026 0.047 0.028 SD 0.003 0.004 0.013 0.019 Surface Scans

% Scanned 1%% 1%

Mean M Scan (cpm) 9,000 No Scanning Performed 5,8900 Max M Scan (cpm) 10,000 6,4000 2-54

La Crosse Boilin L ng Water Reacttor L

License Termination Plan R

Revision 0 Table 2-155 Class 3 Asp phalt, Sedimentt and Soil Samp ples - Test Am merica Laboratoory Analysis (ppCi/g)

Pu- Am- Am-A Cm-R Radionuclide H-3 C C-14 Fe-55 NNi-59 Co-60 Ni-63 N Sr-90 N Nb-94 Tc-99 Css-137 Pm-147 Euu-152 Eu-154 Euu-155 Np-237 Pu u-238 Puu-241 239/240 241 243 243/244 L

L3012101-CR-GC-001- -CV 0.028 0 0.030 0.026 0 0 0.043 0.221 00.059 0.053 L

L3012101-CR-GC-002- -CV 0.035 0 0.026 0.033 0 0 0.062 0.271 00.056 0.055 L

L3012101-CR-GC-003- -CV 0..669 2.180 2 .020 0.031 3.590 0.374 0 0.027 0.521 0.027 0 1.480 0 0.056 0.249 00.069 0.025 0.046 0 0.018 11.690 0.019 0.021 0 0.006 L

L3012101-CR-GS-003- -SS 0.025 0 0.017 0.113 0 0.052 0.157 00.059 0.052 L

L3012101-QQ-GS-001- -SB 18.400 0..717 2.390 2 .870 0.016 5.640 0.309 0 0.014 0.550 0.015 0 0.899 0 0.036 0.128 00.036 0.039 0.035 0 0.022 22.590 0.023 0.029 0 0.027 L

L3012101-QQ-GS-001- -SS 15.500 0..708 2.330 2 .660 0.020 3.890 0.295 0 0.017 0.603 0.059 1.090 0 0.047 0.116 00.054 0.028 0.028 0 0.022 22.640 0.019 0.021 0 0.006 L

L3012101-QQ-SL-001- -SM 0.364 0..342 2.710 00.739 0.022 1.090 0.152 0 0.017 0.360 0.020 0 0.333 0 0.042 0.153 00.034 0.009 0.016 0 0.013 00.797 0.009 0.009 0 0.011 L

L3012104-CR-GS-002- -SM 0.015 0 0.013 0.066 0 0.035 0.128 00.047 0.036 L

L3012104-QJ-GS-001-SSB 2.160 0..670 1.950 1 .750 0.021 3.060 0.325 0 0.018 0.469 0.025 0 0.818 0 0.053 0.160 00.054 0.022 0.027 0 0.021 11.610 0.016 0.018 0 0.016 L

L3012104-QJ-GS-001-SSM 2.890 0..672 2.720 1 .990 0.037 3.500 0.298 0 0.020 0.651 0.094 0.818 0 0.074 0.217 00.071 0.006 0.031 0 0.017 11.560 0.016 0.016 0 0.015 L3012104-QJ-GS-001-S L SS 2.190 0..676 4.240 1 .880 0.029 3.300 0.329 0 0.020 0.631 0.138 0.667 0 0.068 0.181 00.080 0.020 0.043 0 0.026 11.580 0.019 0.019 0 0.021 a Bold values indicate concentration greater g than MDC. Italiicized values indicate MDC M value 2-55

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table T 2-16 Concrete Core Isotop pic Analysiss Results B1001101-C CJ-FC-001-CV 0-1/2 0 B1001101-CJ-FC B C-001-CV 1/2-1 B1001101-CJ-FC-002-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 3.950 1.590 1.350 9.720 9 1.5660 1.950 3.640 1.620 1.330 C-14 -0.162 1.400 0.793 -0 0.346 1.4440 0.806 -0.2700 1.410 0.794 Fe-55 9.130 16.000 7.880 10 0.400 21.3300 10.2000 11.3000 9.950 5.540 Ni-59 0.000 0.254 0.325 0.000 0 0.2664 0.151 0.000 0.289 0.183 Co-60 11.500 0.377 1.250 0.082 0 0.1668 0.078 0.800 0.117 0.172 Ni-63 39.300 0.402 4.110 3.850 3 0.4225 0.474 4.860 0.492 0.581 Sr-90 6.910 0.043 0.680 0.162 0 0.0551 0.041 11.6000 0.046 1.130 Nb-94 -0.120 0.312 0.189 0.001 0 0.1339 0.078 -0.0177 0.165 0.095 Tc-99 0.024 0.566 0.330 0.076 0 0.5226 0.310 -0.1044 0.564 0.322 Cs-137 7500 7.090 781.000 9.660 9 0.1552 1.100 450.000 0.597 46.900 Eu-152 2.580 9.020 5.230 -0 0.039 0.5111 0.055 0.173 2.150 0.924 Eu-154 0.266 2.410 0.398 0.025 0 1.2660 0.171 -0.0088 1.460 0.820 Eu-155 0.369 4.440 1.140 0.071 0 0.3776 0.118 0.145 0.837 0.503 Np-237 0.009 0.042 0.021 -0 0.002 0.0445 0.017 -0.0100 0.042 0.009 Pu-238 0.176 0.056 0.065 -0 0.017 0.0666 0.026 0.575 0.617 0.436 Pu-239/240 0.132 0.048 0.055 -0 0.006 0.0449 0.018 0.715 0.466 0.413 Pu-241 0.902 2.700 1.660 -1 1.510 2.5000 1.360 13.2000 23.500 15.100 Am-241 0.407 0.048 0.107 0.011 0 0.0337 0.020 0.550 0.401 0.419 Am-243 0.028 0.046 0.030 0.014 0 0.0330 0.019 -0.0366 0.433 0.140 Cm-243/244 0.0579 0.0302 0.0371 -0.0081 0.04478 0.00944 0.15400 0.4670 0.2600 B1001101-C CJ-FC-003-CV 0-1/2 0 B1001101-CJ-FC B C-003-CV 1/2-1 B1001101-CJ-FC-004-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 7.240 1.360 1.580 12 2.600 1.5770 2.240 4.490 1.590 1.420 C-14 -0.492 1.460 0.806 -0 0.566 1.3990 0.765 -0.5555 1.450 0.795 Fe-55 9.450 9.040 4.950 6.160 6 14.3300 6.960 7.600 7.070 4.040 Ni-59 0.000 0.365 0.806 0.000 0 0.2557 0.157 0.000 0.276 0.467 Co-60 57.700 0.333 5.880 0.435 0 0.0557 0.096 28.1000 0.190 2.950 Ni-63 202.000 0.593 211.100 2.990 2 0.4000 0.392 88.3000 0.467 9.200 Sr-90 34.500 0.040 3.330 0.304 0 0.0551 0.052 11.0000 0.045 1.070 Nb-94 0.191 0.392 0.203 -0 0.001 0.1553 0.086 -0.0166 0.264 0.155 Tc-99 -0.189 0.586 0.330 -0 0.129 0.5996 0.339 0.153 0.592 0.352 Cs-137 614.000 0.732 644.000 2.450 2 0.1113 0.348 213.000 0.439 22.200 Eu-152 0.768 2.870 1.300 0.045 0 0.3446 0.154 0.162 1.570 0.611 Eu-154 0.335 5.460 0.536 0.179 0 1.0220 0.383 0.557 3.070 0.863 Eu-155 -0.429 1.510 0.914 -0 0.007 0.2882 0.164 0.108 0.850 0.138 Np-237 0.000 0.041 0.016 -0 0.010 0.0551 0.018 -0.0200 0.060 0.020 Pu-238 0.528 0.058 0.111 -0 0.005 0.0664 0.029 0.413 0.426 0.320 Pu-239/240 0.491 0.030 0.104 -0 0.004 0.0447 0.017 0.336 0.325 0.265 Pu-241 7.470 2.640 2.160 -1 1.320 2.6660 1.480 -7.7200 26.000 14.400 Am-241 1.450 0.047 0.250 0.018 0 0.0338 0.024 0.614 0.441 0.436 Am-243 0.052 0.027 0.033 0.009 0 0.0330 0.016 0.052 0.292 0.136 Cm-243/244 0.0879 0.0408 0.0496 0..0000 0.01 68 0.00477 -0.05477 0.4320 0.0776 2-56

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continuued) Cooncrete Corre Isotopic A Analysis Reesults B1001101-C CJ-FC-005-CV 0-1/2 0 B1001101-CJ-FC B C-005-CV 1/2-1 B1001101-CJ-WC-0066-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (ppCi/g) (p pCi/g) (pCi/

i/g) (pCi/g) (pCi/g)) (pCi/g) (pCi/g)

H-3 2.960 1.520 1.200 4.180 4 1.8550 1.520 4.210 1.700 1.440 C-14 -0.077 1.410 0.810 -0 0.701 1.3550 0.733 0.077 1.440 0.832 Fe-55 8.070 9.770 5.230 8.170 8 9.8770 5.340 11.7000 9.320 5.530 Ni-59 2.590 0.267 0.813 0.000 0 0.2770 0.165 0.000 0.263 0.230 Co-60 73.900 0.372 7.510 0.075 0 0.1771 0.080 2.040 0.047 0.264 Ni-63 221.000 0.427 23 3.000 4.870 4 0.4330 0.570 13.4000 0.420 1.430 Sr-90 32.800 0.043 3.170 0.423 0 0.0551 0.063 7.150 0.034 0.703 Nb-94 -0.089 0.531 0.317 -0 0.015 0.1228 0.074 0.026 0.154 0.090 Tc-99 0.178 0.562 0.336 -0 0.124 0.5440 0.307 0.083 0.580 0.341 Cs-137 65.700 0.569 6.970 0.801 0 0.1117 0.172 1490 0.721 155.000 Eu-152 0.395 1.240 0.746 0.001 0 0.3773 0.005 0.031 3.660 2.210 Eu-154 0.637 5.650 0.831 0.119 0 0.9223 0.245 0.128 1.190 0.679 Eu-155 0.011 0.699 0.414 0.013 0 0.2555 0.148 0.737 1.470 0.896 Np-237 0.005 0.015 0.010 -0 0.017 0.0554 0.016 -0.013 0.044 0.010 Pu-238 0.706 0.065 0.134 -0 0.003 0.0553 0.023 0.029 0.037 0.027 Pu-239/240 0.489 0.035 0.106 -0 0.008 0.0338 0.008 0.035 0.025 0.026 Pu-241 9.090 2.540 2.270 0.337 0 2.5330 1.510 -1.380 2.650 1.470 Am-241 1.590 0.045 0.273 0.012 0 0.0118 0.017 0.048 0.052 0.041 Am-243 0.048 0.031 0.034 -0 0.002 0.0554 0.022 0.003 0.029 0.011 Cm-243/244 0.1160 0.0443 0.0590 0.0000 0.01 76 0.0049 -0.00533 0.0419 0.0075 B1001101-C CJ-WC-006-CV 1/2-1 B1008101-CJ--FC-002-CV B10008101-CJ-FC-0003-CV Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (ppCi/g) (p pCi/g) (pCi/

i/g) (pCi/g) (pCi/g)) (pCi/g) (pCi/g)

H-3 3.590 1.640 1.350 0.382 0 0.9440 0.559 1.300 1.020 0.713 C-14 -0.246 1.490 0.836 0.053 0 1.3770 0.794 -0.296 1.440 0.810 Fe-55 6.030 14.500 7.050 1.610 1 6.5550 3.370 6.460 14.500 7.050 Ni-59 0.000 0.257 0.147 0.000 0 0.2334 0.151 0.000 0.241 0.171 Co-60 -0.026 0.207 0.240 0.662 0 0.0665 0.131 0.974 0.142 0.162 Ni-63 2.310 0.396 0.335 2.730 2 0.3553 0.355 4.400 0.356 0.510 Sr-90 0.146 0.038 0.034 0.154 0 0.0553 0.041 0.235 0.035 0.041 Nb-94 0.019 0.141 0.060 0.000 0 0.2111 0.066 0.016 0.141 0.081 Tc-99 0.024 0.556 0.324 -0 0.010 0.5779 0.335 -0.005 0.592 0.343 Cs-137 1.410 0.153 0.258 166.000 0.1777 1.780 10.0000 0.154 1.130 Eu-152 0.021 0.434 0.113 0.034 0 0.6333 0.056 0.291 0.470 0.270 Eu-154 0.055 1.270 0.137 0.060 0 1.2000 0.239 0.019 1.410 0.052 Eu-155 0.003 0.336 0.196 0.140 0 0.3557 0.215 0.101 0.348 0.208 Np-237 0.003 0.045 0.021 0.003 0 0.0448 0.022 -0.024 0.068 0.025 Pu-238 -0.004 0.043 0.016 0.018 0 0.0660 0.033 0.042 0.057 0.038 Pu-239/240 0.035 0.033 0.028 -0 0.011 0.0554 0.019 0.008 0.034 0.017 Pu-241 -1.890 2.360 1.270 -1 1.120 2.7110 1.480 -0.194 2.550 1.470 Am-241 0.006 0.036 0.017 0.020 0 0.0442 0.027 0.019 0.051 0.029 Am-243 -0.002 0.031 0.005 -0 0.002 0.0444 0.017 -0.001 0.052 0.023 Cm-243/244 -0.0036 0.0287 0.0052 0.0062 0.01 87 0.0125 -0.00566 0.0444 0.0080 2-57

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continu ued) Cooncrete Corre Isotopic A Analysis Reesults B100810 01-CJ-FC-004-C CV B1002101-CJ-FC B C-001-CV 0-1/2 B10022101-CJ-FC-001-CV 1/2-1 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 1.200 0.990 0.685 0.820 0 0.9885 0.637 0.275 0.931 0.543 C-14 0.077 1.430 0.829 0.505 0 1.4110 0.850 -0.0188 1.440 0.824 Fe-55 6.520 11.500 5.820 15 5.400 13.8800 7.430 0.547 5.510 2.840 Ni-59 0.000 0.229 0.162 65 5.500 0.3110 8.690 0.000 0.245 0.170 Co-60 1.390 0.095 0.255 95 5.000 0.4220 9.600 1.010 0.149 0.168 Ni-63 4.260 0.339 0.492 817.000 0.4772 85.0000 5.640 0.367 0.633 Sr-90 0.216 0.040 0.041 99 9.800 0.0445 9.600 0.253 0.053 0.049 Nb-94 0.001 0.143 0.081 0.098 0 0.4775 0.149 0.029 0.102 0.054 Tc-99 0.043 0.599 0.350 0.113 0 0.5664 0.333 -0.1011 0.507 0.289 Cs-137 19.800 0.166 2.150 4710 4 1.6990 491.0000 3.870 0.137 0.496 Eu-152 -0.119 0.580 0.344 0.815 0 5.9440 1.410 0.039 0.444 0.107 Eu-154 -0.061 1.370 0.296 1.250 5.4660 1.980 -0.2600 1.480 0.859 Eu-155 0.006 0.376 0.220 0.073 0 2.1220 1.280 0.077 0.272 0.162 Np-237 0.014 0.065 0.035 -0 0.012 0.0660 0.023 -0.0222 0.064 0.023 Pu-238 0.020 0.052 0.030 0.920 0 0.6220 0.511 0.017 0.059 0.033 Pu-239/240 0.025 0.042 0.028 1.280 0.4669 0.537 -0.0055 0.042 0.013 Pu-241 -1.610 2.610 1.430 5.240 5 26.7700 16.2000 -0.9844 2.680 1.510 Am-241 0.052 0.034 0.035 3.200 3 0.4228 0.989 0.035 0.037 0.031 Am-243 -0.004 0.032 0.006 0.406 0 0.2996 0.310 -0.0188 0.054 0.013 Cm-243/244 0.0100 0.0150 0.0142 0..2020 0.42200 0.26700 -0.00466 0.0366 0.0066 B1002101-C CJ-FC-001-CV 1-1.5 B1002101-CJ-FC B C-001-CV 1.5-2 B10022101-CJ-FC-002-CV 0-1/2 Result MDC Result R MD DC Resultt MDC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g) (pCi/g) (pCi/g) (pCi/g)

H-3 0.763 1.000 0.638 0.094 0 0.9117 0.512 1.710 1.180 0.846 C-14 -0.776 1.410 0.763 0.372 0 1.3880 0.819 15.4000 1.510 2.310 Fe-55 3.540 5.670 3.150 7.770 7 25.0000 11.4000 8.960 5.860 3.640 Ni-59 0.000 0.228 0.159 0.000 0 0.2559 0.188 423.000 0.446 55.200 Co-60 0.742 0.069 0.148 0.872 0 0.1338 0.161 300.000 0.762 30.200 Ni-63 3.360 0.333 0.407 5.730 5 0.3888 0.646 2360 0.661 245.000 Sr-90 2.410 0.050 0.250 0.106 0 0.0441 0.032 220.000 0.052 21.100 Nb-94 0.035 0.149 0.066 -0 0.034 0.1442 0.083 -0.3500 0.935 0.567 Tc-99 0.259 0.564 0.342 0.032 0 0.5228 0.308 0.792 0.562 0.373 Cs-137 3.630 0.150 0.493 2.440 2 0.1446 0.343 254000 4.140 2650 Eu-152 0.156 0.420 0.236 0.125 0 0.3883 0.195 0.510 13.700 0.956 Eu-154 0.119 1.400 0.382 0.271 0 0.9556 0.406 4.650 7.170 4.390 Eu-155 0.159 0.335 0.204 0.099 0 0.3226 0.196 1.060 7.370 0.988 Np-237 0.000 0.045 0.018 -0 0.007 0.0552 0.019 0.024 0.042 0.027 Pu-238 0.023 0.061 0.035 0.004 0 0.0661 0.030 3.200 0.497 0.825 Pu-239/240 0.000 0.049 0.021 0.009 0 0.0441 0.021 2.580 0.287 0.713 Pu-241 -0.052 2.820 1.640 -2 2.090 2.7000 1.460 36.9000 24.000 17.100 Am-241 0.020 0.015 0.020 0.017 0 0.0441 0.025 9.080 0.682 2.030 Am-243 0.013 0.029 0.018 0.029 0 0.0229 0.026 0.305 0.388 0.286 Cm-243/244 0.0048 0.0143 0.0096 0..0059 0.03331 0.01544 0.42800 0.5450 0.4200 2-58

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 Table 2--16 (continu ued) Cooncrete Corre Isotopic A Analysis Reesults B1002101-C CJ-FC-002-CV 1/2-1 1 B1002101-CJ-FC B C-003-CV 0-1/2 Result MDC Result R MD DC (pCi/g) (pCi/g) (p pCi/g) (p pCi/g) (pCi//g) (pCi/g)

H-3 0.846 1.120 0.716 0.836 0 0.9662 0.624 C-14 6.180 1.420 1.340 -0 0.405 1.4440 0.803 Fe-55 5.270 25.300 11 1.400 8.430 8 17.0000 8.210 Ni-59 0.000 0.269 0.616 0.000 0 0.3334 0.484 Co-60 8.270 0.114 0.907 8.570 8 0.1448 0.940 Ni-63 175.000 0.442 18 8.300 70 0.600 0.5448 7.370 Sr-90 3.520 0.047 0.356 7.000 7 0.0550 0.691 Nb-94 -0.041 0.230 0.135 0.038 0 0.2111 0.060 Tc-99 0.165 0.522 0.312 0.062 0 0.5443 0.318 Cs-137 208.000 0.362 21 1.700 1240 1 0.8117 129.0000 Eu-152 -0.280 1.580 0.950 0.176 0 2.6000 0.514 Eu-154 0.255 1.900 0.259 0.090 0 2.3220 0.202 Eu-155 0.116 0.864 0.205 -0 0.004 1.7110 1.030 Np-237 -0.019 0.056 0.017 -0 0.011 0.0444 0.009 Pu-238 0.059 0.064 0.046 0.105 0 0.0556 0.051 Pu-239/240 0.056 0.049 0.040 0.126 0 0.0339 0.051 Pu-241 -0.965 2.970 1.690 1.500 2.5660 1.640 Am-241 0.238 0.048 0.080 0.339 0 0.0444 0.099 Am-243 0.005 0.060 0.028 -0 0.001 0.0337 0.012 Cm-243/244 0.0018 0.0438 0.0179 0..0175 0.01 75 0.02033 2-59

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Tab ble 2-17 19883 Groundw water Analyysis from Teemporary Weell-Point So outh of Turb bine Buildin ng AActivity Radion nuclide (p

pCi/L)

Mn--54 63.4 Co--57 6.4 Co--60 508 Nb--95 21.4 Cs-1137 21.7 Ce-1141 18.9 2-60

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Table 2-18 2 2013 Grroundwater Monitoring Resu ults June 2013 MW-20 01-A MW-201-B B MW-202-A MW-202-B MW W-203-A MW-2203-B MW-204--A MW-204-B (pCi/LL) (pCi/L) (pCi/L) (pCi/L) (ppCi/L) (pCii/L) (pCi/L) (pCi/L)

H-3 5722 506 660 484 N/A 4220 397 420 Co-660 4.00 0 5.01 4.76 4.51 4.95 4.112 4.36 4.26 Sr-9 90 5 2.05 2.00 1.82 1.43 2.06 2.006 2.18 2.08 Cs-1 137 3.97 7 3.84 4.05 3.91 4.52 4.331 4.11 3.96 a Bold B values indiicate concentratiion greater than n MDC. Italicizeed values indicaate MDC value.

Novvember 2013 MW-20 01-A MW-201-B B MW-202-A MW-202-B MW W-203-A MW-2203-B MW-204--A MW-204-B (pCi/LL) (pCi/L) (pCi/L) (pCi/L) (ppCi/L) (pCii/L) (pCi/L) (pCi/L)

H-3 2355 150 257 278 449 2335 193 171 Co-660 4.64 4 3.80 5.26 5.41 4.43 3.889 4.52 8.24 Sr-9 90 1.18 8 3.73 1.18 1.61 1.87 2.440 1.18 1.51 Cs-1 137 4.64 4 1.90 6.54 4.70 4.41 3.998 4.77 7.92 a Bold B values indiicate concentratiion greater than n MDC. Italicizeed values indicaate MDC value.

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Revision 0 Tablle 2-19 2014 Groundwater Monitoring Reesults (pCi/L)

J JUNE 2014 MW- MW- MW-M MW- MW- MW W- MW- MW- MW- MW- M MW- MW- MW- MWW- MW- MW- MW- MW-DW3 DW4 D DW5 DW7 B11R B11AAR B2 B3 200-A 200-B 2001-A 201-B 202-A 202-B 203-A 203-B 204-A 204-B Gross G

1.26E-011 -1.33E-01 4.444E+00 -3.78E-01 0.00E+00 7.33E-01 -2.13E+00 6 6.46E-01 4.04E+000 -2.26E-01 3.844E-01 -1.04E+00 1.06E+00 4.07E--01 1.74E+00 -22.29E-01 7.58E-01 1.27E+00 A

Alpha G

Gross 1.48E+00 3.13E+00 1.933E+00 0.00E+00 3.59E+00 -2.70E E-01 1.12E+01 4 4.14E+00 8.66E+000 -1.79E+00 7.266E+00 -1.04E+00 4.34E+00 1.49E++00 2.27E+00 55.53E+00 2.69E+00 0 2.57E-01 B

Beta H

H-3 1.05E+02 1.59E+02 1.944E+02 1.23E+02 2.45E+02 1.61E++02 1.60E+02 1 1.94E+02 5.23E+011 1.24E+02 7.033E+01 1.05E+02 3.36E+02 1.06E++02 2.79E+02 22.79E+02 1.06E+02 2 3.49E+01 C

C-14 2.79E+00 0.00E+00 -3.997E+00 -5.08E+00 9.06E+00 6.83E++00 1.94E+00 -22.05E+00 9.26E+000 4.84E+00 4.844E+00 4.51E+00 0.00E+00 4.70E+

+00 4.54E+00 44.55E+00 4.66E+000 1.30E+01 F

Fe-55 -2.00E+001 -3.12E+01 -2.666E+01 -3.86E+01 -3.19E+01 -3.75EE+01 -9.20E+00 -44.39E+01 1.93E+011 -4.16E+01 -3.200E+01 1.58E+01 -3.26E+00 -4.54E+

+01 -4.95E+01 -44.96E+01 -4.03E+01 1 -3.98E+00 N

Ni-59 1.83E+01 3.96E+01 -4.775E+01 2.60E+01 -4.16E+00 2.53E++00 -7.13E+00 3 3.15E+01 -2.18E+01 3.32E+01 -1.67E+01 -7.11E+01 2.49E+01 -1.05E+

+01 -2.71E+01 -44.66E+00 -6.22E+00 0 -2.47E+01 C

Co-60 1.02E+00 3.94E-01 2.50E+00 -2.42E+00 8.76E-01 -1.94EE+00 -1.39E+00 -11.13E+00 1.01E+000 -1.27E+00 -6.004E-02 1.73E+00 -8.91E-01 1.02E++00 3.48E-02 -99.55E-01 1.91E-01 -2.31E-01 N

Ni-63 -1.78E+000 -6.14E+00 -7.440E+00 -4.38E+00 -3.57E+00 0.00E++00 -7.94E+00 1 1.50E+00 -1.97E+00 -4.69E+00 1.822E+00 -1.91E+00 -1.94E+00 -3.73E+

+00 -3.70E+00 -33.80E+00 0.00E+000 -1.97E+00 S

Sr-90 6.09E-011 8.99E-02 8.999E-02 1.78E-02 7.34E-01 6.11E E-01 6.52E-01 6 6.12E-01 9.86E-01 1 9.98E-01 6.866E-02 1.02E+00 1.12E+00 6.05E--01 1.17E+00 88.23E-01 2.01E+000 6.11E-01 N

Nb-94 4.40E-011 1.43E-01 -1.226E+00 7.49E-01 -6.99E-01 1.53E++00 1.77E+00 6 6.65E-01 1.08E+00 0 8.47E-01 3.733E-01 1.80E+00 -3.55E-01 1.04E--01 1.59E+00 1.50E+00 2.26E-01 1.28E+00 T

Tc-99 -8.28E+000 -7.37E+00 -8.226E+00 -9.36E+00 -5.52E+00 -8.46EE+00 -7.41E+00 -88.10E+00 3.55E+000 5.08E+00 3.922E+00 1.17E+00 3.88E-01 2.73E++00 4.36E+00 44.17E+00 6.95E+000 6.31E+00 C

Cs-137 -5.97E-01 -3.47E-01 -7.445E-01 -1.83E+00 1.24E+00 1.84E++00 1.37E+00 2 2.14E+00 1.77E-01 1 -3.64E-01 3.100E-01 -6.21E-01 -4.64E-01 2.86E++00 1.48E+00 1.39E+00 -3.04E-01 1.93E+00 E

Eu-152 9.48E+000 2.34E+00 -7.443E+00 -5.51E+00 -9.93E-01 1.48E++00 1.07E-01 1 1.42E+01 9.71E+000 -1.16E+01 4.155E+00 1.12E+01 4.11E+00 +01 1.08E+ -9.59E-01 44.99E+00 2.12E+000 7.68E+00 E

Eu-154 -5.24E+000 3.16E+00 1.355E+00 -4.73E+00 1.63E+00 -2.61EE+00 2.36E+00 1 1.69E+00 5.77E-01 1 5.60E-01 -2.399E+00 -2.43E+00 -1.12E+00 -1.18E+

+00 1.93E+00 -33.69E+00 2.36+00 6.06E-01 E

Eu-155 -2.67E+000 1.46E+00 -1.554E-01 -1.07E+02 1.60E+00 -4.47EE+00 1.60E+00 -33.17E+00 -3.63E+00 -3.44E+00 -2.922E+00 -2.60E+00 -1.59E+00 -3.49E+

+00 -4.91E+00 44.05E+00 -4.34E-01 1.66E+00 P

Pu-238 2.83E-022 -4.77E-02 -2.222E-02 8.22E-02 0.00E+00 4.09E E-02 5.40E-02 8 8.29E-02 -1.38E-02 2 1.51E-02 5.333E-02 -5.02E-02 -8.46E-03 1.48E--01 -5.67E-02 -55.87E-02 -5.12E-022 -9.28E-03 Pu-P

-9.61E-02 2 3.36E-02 3.113E-02 4.07E-01 -2.54E-02 -3.39E E-02 3.40E-02 1 1.46E-01 2.68E-02 2 -1.57E-02 -6.886E-03 2.36E-02 -2.27E-02 -4.54E-02 -2.27E-02 -33.95E-02 -2.49E-022 6.28E-02 2

239/240 P

Pu-241 3.51E+00 2.70E+00 -8.339E+00 2.62E+00 -5.72E+00 8.38E E-01 0.00E+00 -

-7.39E-01 0.00E+00 0 4.49E+00 -4.885E-01 -1.42E+00 2.20E+00 2.72E+

+00 4.07E+00 1.03E+01 4.07E+000 -1.89E+00 A

Am-241 5.39E-022 3.42E-02 4.665E-03 -1.01E-02 1.22E-02 8.37E E-02 3.98E-03 2 2.28E-02 1.72E-011 9.71E-01 9.466E-02 3.99E-03 1.16E-01 3.92E--02 2.94E-02 77.64E-02 1.56E-01 8.24E-02 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

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Revision 0 Table 2-19 (continued) 2014 Ground dwater Monitooring Results (p pCi/L)

S September 20144 MW-DW5 M MW--B11R MW-B11A AR MW-200-A MW-200-B MW-201-A MW-201-B M MW W-202-A MW-2002-B MW-203-A A MW-203-B MW-204-A MW-204-B G

Gross Alpha 8.47E-01 8 3.09EE+00 2.07E-001 2.42E-01 2.01E+00 1.18E+00 1.43E+00 1.04E+00 -2.10E-E-01 1.37E+00 -6.68E-01 6.00E-01 3.53E+00 G

Gross Beta 2.96E+00 1.45EE+01 3.04E-001 2.41E+00 9.11E+00 7.36E+00 3.67E+00 4.886E-01 2.30E++00 1.52E+00 1.00E+00 5.28E+00 0.00E+00 H

H-3 3.43E+01 0.00EE+00 3.44E+001 6.86E+01 5.17E+01 8.67E+01 -3.42E+01 -5.118E+01 1.04E++02 -3.44E+01 1.21E+02 6.88E+01 -1.21E+02 C

C-14 -9 9.44E-01 -2.70E E+00 0.00E+000 -4.56E-01 -4.98E+00 2.69E+00 9.28E-01 4.944E+00 -2.72E+ +00 -3.95E+00 0 4.89E-01 4.73E-01 9.46E-01 F

Fe-55 9.39E+00 9 -3.10E E+01 -3.49E+001 -3.35E+01 -4.56E+01 -2.18E+01 2.77E+01 -5.443E+01 3.37E++01 -4.95E+01 4.32E+01 3.45E+01 -9.25E+01 N

Ni-59 3.13E+00 1.64EE+01 -8.49E+000 7.84E+00 2.37E+01 -1.99E+01 3.09E+01 -1.118E+01 -4.46E+ +01 5.30E+01 -4.34E+01 -3.13E+01 -1.87E+01 C

Co-60 2.17E+00 1.32EE+00 1.22E+000 3.56E+00 6.20E-01 -7.23E-02 9.50E-01 9.772E-01 1.18E++00 3.67E+00 1.99E+00 -3.77E-01 2.05E+00 N

Ni-63 2.79E+00 2.48EE+00 -4.14E-001 3.62E+00 -7.87E-01 5.00E+00 2.15E+00 8.225E-01 -8.30E-E-01 1.62E+00 -1.77E+00 -1.84E-01 3.94E-01 S

Sr-90 -1 1.06E+00 5.90EE-01 2.80E-001 1.14E+00 5.10E-01 -1.19E-01 -4.99E-01 6.770E-01 5.40E--01 4.80E-01 8.70E-01 9.00E-01 2.30E-01 N

Nb-94 -9 9.45E-01 -1.39E E+00 -1.29E-001 -1.43E+00 -2.68E-01 6.56E-01 6.44E-01 -6.448E-02 -1.02E+ +00 8.53E-02 2.16E+00 1.18E-01 -1.88E+00 T

Tc-99 -1 1.54E+00 -4.000E-01 -1.56E+000 -1.57E+00 -1.54E+00 -7.94E-01 -1.95E+00 7.997E-01 -1.95E-E-01 -1.24E+00 0 -3.32E+00 -1.96E+00 3.89E-01 C

Cs-137 3.97E+00 -7.244E-01 9.72E-001 2.17E+01 1.94E+00 -1.09E+00 1.84E+00 -4.334E-01 2.31E++00 1.56E+00 6.84E-01 -1.14E+00 1.24E+00 E

Eu-152 2.48E+00 3.00EE+00 6.42E+000 -2.39E+00 -1.34E+01 4.79E+00 2.53E+00 9.40E+00 6.51E++00 4.06E+00 -1.15E+00 -1.92E+01 2.23E+00 E

Eu-154 -3 3.31E+00 -3.93E E+00 1.10E+000 -6.57E-01 -1.54E+00 -3.09E+00 1.94E+00 -3.667E-01 4.18E++00 -3.33E+00 0 -2.31E-01 -4.95E+00 2.36E+00 E

Eu-155 2.69E+00 1.95EE+00 1.69E+000 -8.16E-01 -1.64E+00 -1.48E+00 4.13E+00 -2.008E+00 -8.41E-E-01 -9.54E-02 -3.66E-01 -2.02E+00 9.46E-01 P

Pu-238 1.71E-02 1 3.69E E-02 -5.50E-003 2.65E-02 -6.50E-03 -3.59E-02 8.55E-02 1.113E-02 3.63E--02 7.08E-02 8.12E-02 -6.45E-04 -3.26E-02 P

Pu-239/240 9.28E-02 9 0.00E E+00 -1.10E-002 5.83E-02 0.00E+00 0.00E+00 1.41E-01 5.887E-02 5.25E--02 9.15E-02 5.97E-02 -5.48E-03 7.02E-02 P

Pu-241 3.18E+00 -3.68E E+00 -2.29E+000 -2.23E+00 8.49E+00 -6.92E-01 -5.85E-01 0.00E+00 -1.76E+ +00 5.04E-01 -3.71E+00 -3.97E+00 -6.46E+00 A

Am-241 1.28E-01 1 3.69E E-02 -1.69E-002 1.10E-01 2.29E-01 1.40E-01 2.80E-02 6.662E-02 9.48E--02 2.51E-01 1.03E-01 1.06E-01 2.69E-01 a Bold vallues indicate conncentration greaater than MDC. Italicized valuees indicate MDC C value.

2-63

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Revision 0 Figuree 2-1 LACBWR Site Map - Open Land Survey Units an nd Classificatioon 2-64

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-2 LACBWR Site Map - Buiildings Identifiication 2-65

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-3 LACBWR R Site Drain nage and Seewer Map 2-66

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-4 LACBWR R LCE Excllusion Area (Class 1) 2-67

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figu ure 2-5 Non N Impacteed Open Laand Samplin ng Locations 2-68

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-6 Class 1 Open O Land Sampling Locations 2-69

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-7 Class 2 Open O Land Sampling Locations 2-70

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure F 2-8 Class 3 Open O Land Sampling Locations 2-71

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figure 2-9 9 Concreete Core Sam mpling Loccations 2-72

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-73

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-74

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-10 LACBWR Siite - Typical Geeological Crosss-Section 2-75

L La Crosse Boilin ng Water Reactor L

License Termination Plan R

Revision 0 Figure 2-11 1 Groundwatter Sampling Wells - LACBW WR Site 2-76