ML16200A086: Difference between revisions

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| number = ML16200A086
| number = ML16200A086
| issue date = 06/27/2016
| issue date = 06/27/2016
| title = Boiling Water Reactor License Termination Plan - Chapter 2 - Site Characterization, Rev. 0
| title = License Termination Plan - Chapter 2 - Site Characterization, Rev. 0
| author name =  
| author name =  
| author affiliation = LaCrosseSolutions, LLC
| author affiliation = LaCrosseSolutions, LLC
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=Text=
=Text=
{{#Wiki_filter:LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 2 SITE CHARACTERIZATION
{{#Wiki_filter: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
La Cross License T Revision 2.
: 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
Site 2.1.
: 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
2.1.
: 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
2.1.
: 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
2 2
2 2
2 2.1.
2.1.4 2
2 2.1.
2.1.
2 2
2 2
2 2
2 2
2.2.
2.2.
2.2.
2 2
2 2
2.2.
2 2
2.2.4 2.2.
2.3.
2.3.
2.3.
2.3.
2.3.4 2
2 se Boiling W Termination n 0 Characteriz Historical S 1.
Objecti 2.
Method
.1.2.1. Pre
.1.2.2. Doc
.1.2.3. Lic
.1.2.4. Per
.1.2.5. Pro 3.
Operati 4.
Inciden
.1.4.1. Rad
.1.4.2. Che 5.
Finding 6.
Initial S
.1.6.1. Sur
.1.6.2. Sur
.1.6.3. Cla
.1.6.4. Cla
.1.6.5. Cla
.1.6.6. Non
.1.6.7. Cla
.1.6.8. Cla Characteriz 1.
Data Q 2.
Survey
.2.2.1. Num
.2.2.2. Det
.2.2.3. Sca
.2.2.4. Typ 3.
Instrum Concen
.2.3.1. Cal
.2.3.2. Inst 4.
Labora 5.
Quality Summary o 1.
Backgr 2.
Potenti 3.
Non-Im 4.
Impact
.3.4.1. Cla
.3.4.2. Cla Water Reactor Plan zation..........
Site Assessm ives............
dology........
liminary Cla cument Revi enses, Perm rsonnel Inter operty Inspec ional History nts...............
diological Sp emical Spills gs and Conc Survey Area rvey Areas..
rvey Units...
ass 1 Open L ass 2 Open L ass 3 Open L n-Impacted O ass 1 Structur ass 2 and 3 S ation Appro Quality Objec y Design......
mber of Stat termination o an Coverage pes of Measu mentation Se ntrations (M libration......
trument Use atory Instrum y Assurance f Characteri round Study ial Radionuc mpacted Ope ed Open Lan ass 1 Open L ass 2 Open L r
TABLE O ment..............
assification..
iew..............
mits and Auth rviews..........
ctions...........
y..................
pills.............
s..................
lusions........
as/Units and Land Areas...
Land Areas...
Land Areas...
Open Land A res...............
Structures.....
ach..............
ctives...........
tic Measurem of Static Me urements and lection, Use MDCs)..........
e and Contro ment Method zation Surve clides of Con en Land Area nd Areas.....
Land Areas...
Land Areas...
2-i OF CONTE horizations...
Classificatio Areas..........
ments and/or easurement a d Samples...
and Minimu l..................
ds and Sensit ey Results...
ncern............
as................
ENTS on................
r Samples....
and Sample L um Detectab tivities.........
Locations....
ble
... 2-1
... 2-2
... 2-2
... 2-3
... 2-3
... 2-4
... 2-5
... 2-5
... 2-5
... 2-6
... 2-6
... 2-7
... 2-8
... 2-8
... 2-9
... 2-9
... 2-9
. 2-10
. 2-10
. 2-10
. 2-11
. 2-11
. 2-12
. 2-12
. 2-14
. 2-14
. 2-15
. 2-16
. 2-16
. 2-16
. 2-18
. 2-18
. 2-19
. 2-19
. 2-19
. 2-20
. 2-21
. 2-22
. 2-22
. 2-24
. 2-25
. 2-26


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 Cross License T Revision 2
2.3.
2.3.
2 2
2 2.3.
2 2
2 2
2 2.4.
2.5.
se Boiling W Termination n 0
.3.4.3. Cla 5.
Non-Im 6.
Impact
.3.6.1. Bas
.3.6.2. Tur
.3.6.3. LA 7.
Surface
.3.7.1. Are
.3.7.2. Gro
.3.7.3. Pre
.3.7.4. On-
.3.7.5. Sum Continuing References Water Reactor Plan ass 3 Open L mpacted Stru ed Structure sement Struc rbine Buildin ACBWR Adm e and Groun ea Groundwa oundwater F vious Invest
-Going Inve mmary of Gr Characteriza r
Land Areas...
uctures.........
es and System ctures Below ng Tunnel....
ministration dwater........
ater Use......
low.............
tigations......
stigations....
roundwater A ation...........
2-ii ms...............
w 636 foot El Building.....
Analytical R levation......
Results.........
. 2-27
. 2-29
. 2-30
. 2-30
. 2-31
. 2-31
. 2-32
. 2-32
. 2-33
. 2-34
. 2-35
. 2-35
. 2-36
. 2-37


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 Cross License T Revision Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-se Boiling W Termination n 0 1
LACBW 2
LACBW 3
Instrum 4
Off-Sit 5
2005 D 6
Investig 7
Initial S 8
Non-Im Survey 9
Non Im Labora 10 Impact Summa 11 Class 1 Labora 12 Impact Survey 13 Class 2 Labora 14 Impact Survey 15 Class 3 Labora 16 Concre 17 1983 G Buildin 18 2013 G 19 2014 G
-1 LACBW
-2 LACBW
-3 LACBW
-4 LACBW
-5 Non Im
-6 Class 1
-7 Class 2
-8 Class 3
-9 Concre
-10 LACB
-11 Ground Water Reactor Plan WR Open L WR Structur ment Types a te Laboratory Dairyland Ba gative Level Suite of LAC mpacted Ope y Summary.
mpacted Coa atory Analys ed Class 1 O ary.............
Concrete, A atory Analys ed Class 2 O y Summary.
2 Asphalt, Se atory Analys ed Class 3 O y Summary.
3 Asphalt, Se atory Analys ete Core Isot Groundwater ng...............
Groundwater Groundwater WR Site Ma WR Site Ma WR Site Dra WR LCE Ex mpacted Ope Open Land 2 Open Land 3 Open Land ete Core Sam WR Site - T dwater Samp r
LIST and Survey ral Survey U and Nominal y Analytical ackground St ls for Cs-137 CBWR Site-en Land Surv l Pile and So sis (pCi/g)....
Open Land S Asphalt, Sed sis (pCi/g)....
Open Land S ediment and sis................
Open Land S ediment and sis (pCi/g)....
opic Analys Analysis fro Monitoring Monitoring LIST O ap - Open La ap - Building ainage and S xclusion Are en Land Sam d Sampling L d Sampling L d Sampling L mpling Locat Typical Geolo pling Wells -
2-iii OF TABLE Units...........
Units.............
l MDCs.......
l Methods an tudy for Soil 7 Based on B
-Specific Ra vey Units - C oil Samples -
Survey Units diment and S Survey Units Soil Sample Survey Units Soil Sample is Results....
om Tempora Results......
Results (pC OF FIGURE and Survey U gs Identifica Sewer Map..
ea (Class 1)..
mpling Locati Locations.....
Locations.....
Locations.....
tions............
ogical Cross
- LACBWR ES nd Typical M ls.................


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
===Background===
dionuclides.
Characteriza
- Test Amer
- Character Soil Samples
  - Character es - Test Am
- Character es - Test Am ary Well-Po Ci/L)............
RES Units and Cl ation.............
ions.............
s-Section.....
R Site...........
MDCs..........
Studies.......
ation rica rization Surv
- Test Ame rization merica rization merica oint South of lassification vey erica f Turbine
. 2-39
. 2-40
. 2-42
. 2-43
. 2-44
. 2-45
. 2-46
. 2-47
. 2-49
. 2-50
. 2-51
. 2-52
. 2-53
. 2-54
. 2-55
. 2-56
. 2-60
. 2-61
. 2-62
. 2-64
. 2-65
. 2-66
. 2-67
. 2-68
. 2-69
. 2-70
. 2-71
. 2-72
. 2-75
. 2-76


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
La Cross License T Revision AEC ALARA bgs CRD DCGL DQO EPA FCP FESW FRS FSS G-1 G-3 HSA HTD IR ISFSI LACBW LER LSA LSE LTP MARLA MARSA MARSSI MDC MDCR MWe NIST se Boiling W Termination n 0 United As Lo Below Contr Deriv Data Q United Force Fuel E Final Final Genoa Genoa Histor Hard-Incide Indep WR La Cr Licen Low S LACB Licen AP Multi-AME Multi-Manu IM Multi-Minim Minim Megaw Nation Water Reactor Plan LIST OF d States Ato ow As Reaso w Ground Su ol Rod Driv ed Concentr Quality Obje d States Env d Circulation Element Stor Radiation Su Status Surve a 1 Coal/Oil a 3 Fossil St rical Site As to-Detect ent Reports endent Spen rosse Boiling see Event R Specific Act BWR Site En se Terminati
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
-Agency Rad
WTB            Wastee Treatment Building ZNPS          Zion Nuclear N        Pow wer Station 2-v
-Agency Rad ual
-Agency Rad mal Detectab mum Detecta watt Electric nal Institute r
ACRONYM mic Energy onably Achie urface e
ration Guide ective vironmental P n Pump rage Well urvey ey Station tation sessment nt Fuel Stora g Water Reac eports ivity nclosure ion Plan diological L diation Surv diation Surv ble Concentr able Count R c
of Standard 2-iv MS AND AB Commission evable line Levels Protection A age Installatio ctor Laboratory A vey and Asse vey and Site rations Rate ds and Techn BBREVIAT n
Agency on Analytical Pro essment of M Investigatio nology TIONS otocols Man Materials and n Manual nual d Equipmentt


La Crossse Boiling Water W     Reactorr License Termination T            Plan Revision n0 Page Intenttionally Left ft Blank 2-vi
La Cross License T Revision NRC ORC PSDAR QA QAPP QC RCA REMP ROC RPV SRC STS TSD WDNR WGTV WTB ZNPS se Boiling W Termination n 0 United Opera Post-S Qualit Qualit Qualit Radio Radio Radio React Safety Sourc Techn Wisco Waste Waste Zion N Water Reactor Plan d States Nuc ational Revie Shutdown D ty Assurance ty Assurance ty Control ologically Co oactive Efflu onuclides of or Pressure V y Review Co e Term Surv nical Suppor onsin Depart e Gas Tank V e Treatment Nuclear Pow r
clear Regula ew Committ ecommissio e
e Project Pla ontrolled Are ent Monitor Concern Vessel ommittee vey rt Document tment of Nat Vault Building wer Station 2-v atory Commi ee ning Activit an ea ing Reports tural Resour ission ties Report rces


La Crossse Boiling Water W       Reactorr License Termination T            Plan Revisionn0
La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan r
: 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.
Page Intent 2-vi tionally Leftft Blank
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.
La Cross License T Revision
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..
: 2.
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.
S In accor Regulato Nuclear character The purp conducte remain.
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.
License T of compl Survey (
2.1.1. Objectives O
1575, Mu Source T terminati The site quantify character site that classifica The cha NUREG-Decomm
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).
: Criteria, PG-EO-3 Reactor Characte the Data informati remediat at concen removed The deco waste of LACBW None of radiologi planned a G-3 pow minor str The majo basement se Boiling W Termination n 0 Site Chara rdance with ory Guide 1.
(        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.
Power Re rization perfo pose of site ed in all are The term F Termination liance survey FSS) for op ulti-Agency Term Surve ion. See LTP characteriz the extent a rization surv will require ation and vol aracterization
The scop  pe of the HSA included potentiial contaminnation from            m radioactivve materialss and hazardouus materials.
-1575 (MA issioning G Final Repor 313196-SV-P (4), and GP erization Pro Quality Obj ion obtained ion planning ntrations gre and properl ommissionin f all LACB WR Administ f the buildin ically impac and these str wer operation ructures will or sub-grade ts of the Re Water Reactor Plan acterization h the requi
The objectives of thee HSA were to:
.179, Standa eactors (1),
Id dentify potential, likely, or known sources of radioactive and chemical contamiinants based on exissting or deriv  ved informattion, 2-2
formed at the characteriza eas where co Final Radiat n Plan (LTP) ys that will b pen land are Radiation S ey (STS) fo P Chapter 5 ation incorp and nature o veys and ana remediation lumes, and e n survey w ARSSIM)
Guidance - C rt, (3). In ad PL-001, Ch P-EO-31319 oject (QAPP jective (DQO d from the
: g. Materials eater than th ly packaged ng approach BWR buildi tration build ngs and stru cted such th ructures, inc ns. The pub l also remain e structures t eactor Buildi r
n rements of ard Format
, this chap e La Crosse B ation is to en ontamination tion Survey
) in order to be performed eas and buri Survey and S or below gr for a descrip porates the r of contamin alyses have b n, as well as estimate cost was designed and NURE Characteriza ddition, surv haracterizatio 96-QA-PL-00 P) (5) which O) process, a characteriz which were he unrestricte for shipmen for LACBW ings, structu ding and Cri uctures asso hat they requ cluding the G blic roads an
: n.
that will be ing, Waste T 2-1 f 10 CFR 50 and Conte pter provide Boiling Wat nsure that th n existed, re is from 10 acknowledg d at LACBW ed piping b Site Investig round struct ption of the results of in ation at LA been and con s to plan rem ts.
d and exec EG-1757, ation, Surve veys were de on Survey P 01, Quality describes p and measure zation provi e shown to b ed release cr nt and dispos WR requires ures and co ib House) to ociated with uire remedi G-3 Crib Hou nd railways backfilled a Treatment B 0.82 (a)(9)(ii ents for Lic es a descr ter Reactor (
he Final Rad emains, or h 0 CFR 50.82 ge the distin WR. These ased on gui gation Manu tures to be FRS.
nvestigation ACBWR. In ntinue to be mediation m cuted using Volume 2, ey, and De esigned and Plan for th Assurance policy, organ es necessary des guidanc be contamina riteria have sal.
the demolit omponents o a depth of h the Genoa al actions; use, will rem that travers and remain a Building (W i)(A) and t ense Termin ription of (LACBWR) diation Surv has the pote (9)(ii)(D) an nction betwe surveys are; idance provi al (MARSS backfilled ns and surve n addition, th e used to ide methodologie the guidan Revision 1 termination executed in e La Cross Project Pla nization, fun to achieve q ce for deco ated with rad been and wi tion, remova (with the e f at least 3 f a 3 Fossil S therefore, n main intact a se the site a at license ter WTB), Waste the guidanc nation Plan the radiolo site.
ey (FRS) w ential to exi nd is used in een the two
: 1) a Final S ided in NUR SIM) (2) and prior to lic eys conduct he results o ntify areas o es, develop w nce provide 1,
Consolid of Radiolo n accordance se Boiling W an LACBWR nctional activ quality data.
ontamination dioactive ma ill continue al and dispos exception o feet below g Station (G-3 no remediati and function as well as se rmination ar Gas Tank V ce of ns for ogical will be ist or n this types Status REG-d 2) a cense ed to of site of the waste ed in dated ogical e with Water R Site
: vities, The n and aterial to be sal as f the grade.
: 3) are ion is al for everal re the Vault


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.
La Cross License T Revision (WGTV)
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..
(3 feet b Reactor/G sump and In the R removed removed elevation WTB, th concrete the rema cap and p following covered b remainin LTP Cha Independ shown in 2.1.
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.
H In accor Assessm informati
Relevantt informatio  on that beccomes availlable duringg any addiitional charracterizationn and remediation phases of  o the licensee termination  n plan will bbe evaluated..
: reports, marine f Environm compiled 2.1.1. O The HSA LACBW surround resulted Radiolog subsurfac the 1.5 a informati may also The scop hazardou The obje Id b
Also inclluded in the research asssociated with    h the developpment of thee HSA were::
se Boiling W Termination n 0
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.
) and the re elow grade)
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.
Generator P d the Turbin Reactor Bui
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
. All intern
, leaving on n (i.e., concr he only porti footers belo ining structu piles below t g the termina by at least 3 ng backfilled apter 1, sec dent Spent F n Figure 2-1)
Historical Si rdance with ent (HSA) ion, includin pre-operatio fauna and s mental Repo d for this inv Objectives A was a d WR activities dings. The in contamin gically Contr ce soils outs acre fenced ion compile o be used as pe of the us materials.
ctives of the dentify pote ased on exis Water Reactor Plan emainder of
). These re Plant, the on e pit.
lding, all in nal concrete nly the rema rete bowl on of the str ow the 636 fo ure will cons the 636 foot ation of the l feet of soil d structures to ction 1.3.1 d Fuel Storage
) is excluded te Assessme h the guida (6) was p ng any 10 C onal survey sediment su orts to the vestigation.
detailed inve related to r HSA focuse nation of pla rolled Area (
ide of the R LACBWR d by the HS input into th HSA inclu e HSA were ntial, likely sting or deriv r
f the baseme maining stru ne foot thick nternal stru will be rem aining struct below 636 ructure that oot elevation sist of the fl elevation. T license are c and physica o be plausibl describes th Installation d from the sc ent ance provid performed a CFR 50.75(g data, spill urveys), ope Nuclear Re estigation to radioactive m ed on histor ant systems, (RCA). It al RCA but with Site Enclos SA was used he developm ded potenti to:
, or known ved informat 2-2 ent structure uctures inclu k portion of uctural surfa moved to ex tural concre foot elevatio will remain
: n. In the WG loors and fou The structur constructed o ally altered t ly occupied.
e site licen (ISFSI) Fac cope of the L ded in MAR and docume g) files, emp reports, spe rational sur egulatory C o collect ex materials or rical events
, buildings, lso addresse hin the owne sure (LSE) d to establis ment of reme ial contamin sources of
: tion, es located b lude the Pip f the Chimn aces, system xpose the ste ete outside t on, concrete is the 630 a GTV and the undation wa ral surfaces t of steel reinf to a conditio nse boundary cility as loca LTP.
RSSIM, sec ented in Au ployee inter ecial survey rvey records Commission xisting info other conta and routin surface and d support str er controlled area share sh initial sur ediation plan nation from radioactive below the 63 ping and Ve ney Foundat ms and com eel liner, wh the liner be e pile cap an and 635 foot e other rema alls as well a that will rem forced concr on which wo
: y. The fen ated in Lot 7 ction 3.0, a ugust of 19 rviews, radi ys (e.g., site s, and Ann (NRC) wer ormation (fr aminants) fo ne operationa d subsurface ructures, ope d area. The e the same rvey units.
ns and the de m radioactiv and chemi 36 foot elev entilation Tu tion, the Tu mponents wi hich will als low the 636 nd piles.) I t floor, sump aining basem as concrete p main at LACB rete which w ould not allow nced area o 7 of the site a Historical 999. Histo ological inc e aerial sur nual Radiolo re reviewed rom the sta or the site an al processes e soils withi en land area current RCA boundary.
This inform esign of the ve materials cal contami vation
: unnel, urbine ill be so be 6 foot In the p and
: ments, piling BWR will be w the of the e (and Site orical cident
: rveys, ogical d and art of nd its s that in the as and A and The mation FRS.
s and inants


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.
La Cross License T Revision D
p               Potential chemical hhazards inciddents on ow    wner-controlled areas weree also docum    mented.
n P
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.
P P
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.
P M
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:
D 2.1.2. M The obje may have land area failures r material.
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),
contamin decontam their pote Each inc was furth
Operator O          Log gs including Reactor Opeerator and H    Health Physiccs entries, Annual A        Envirronmental Monitoring M            Reports, R
: analysis, sampling location.
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
Relevant remediat Also incl R
P p
S id Informat data, eva Units.
2.1.2.1.
The HSA classifica have a p se Boiling W Termination n 0 Distinguish p o threat to h rovide an as rovide infor rovide an in rovide a gra MARSSIM g Delineate init Methodology ective of the e significant as and struct resulting in Dependin nation varies mination acti ential for con ident identif her investiga any remed g, survey, an Historical r t informatio ion phases o luded in the Relevant exce ersonnel int lant personn ite inspectio dentify, locat ion from thi aluation of r Prelim A investiga ation of the potential for Water Reactor Plan portions of th uman health ssessment of rmation usefu nitial classific aded initial c guidance, and tial survey u y
HSA record tly impacted tures. These airborne rel ng upon pa s by area. In ivities and F ntamination.
fied that pos ated. This in dial actions nd analysis i records prov on that bec of the license research ass erpts from w terviews, inc nel to confir on, utilizing te, confirm, is research w results, docu minary Class ation was d site land are contaminati r
he site that m h,
f the likeliho ful to subsequ cation of are lassification d
unit boundari ds search and d the hazardo e included sy eases, liquid ast site ope n order to fac RS planning sed a realisti nvestigation taken to m in an attemp vided the sou comes avail e termination sociated with written report cluding the u rm documen g historic si and docume was used in umentation o sification designed to eas and struc ion (based o 2-3 may need fur od of contam uent continu eas and struc n for impacte ies and areas d interview ous material ystem, struc d spills or re erations and cilitate effec g, land areas ic potential t n focused on mitigate the s pt to identify urce of a vast lable during n plan will b h the develop ts and corres use of quest nted incident te drawings ent areas of c the HSA de of findings, o obtain su ctures as imp on historical rther action minant migra uing characte ctures as non ed soils and s s based upon process was l or radiolog cture, or area eleases, or t d processes, ctive charact s and structu to impact th n the scope o situation, an fy the as le t majority of g any addi be evaluated.
pment of the spondences, tionnaires, o ts and ident s, photograp concern.
evelopment, and the ide ufficient info pacted or no l data) or co from those
: ation, erization sur n-impacted o structures in n the initial c s to identify gical status o a contamina the loss of c
, the poten terization, an ures are class he characteri of contamina nd any post eft conditio f the docume itional char e HSA were:
of current, fo tify undocum phs, prints, including th entification formation to on-impacted ontain know that pose lit
: rveys, or impacted, n accordance classification those event of LACBWR ation from sy control over ntial for res nd to guide f sified based ization of th ant sampling t-remedial a n of the inc ents inspecte racterization ormer and re mented incid and diagram he compilati of initial Su o provide i
. Impacted wn contamin ttle or e with
: n.
s that R site ystem solid sidual future upon e site g and action cident ed.
n and etired
: dents, ms to on of urvey initial areas nation


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 Quality Q        Contrrol (QC) /Qu  uality Assuraance (QA) fi  finding type ddocuments.
La Cross License T Revision (based o through k is no rea impacted controlle If a land area clas was mad Initial cl historical initial cla at the tim prepared FRS desi classifica continuin surveillan classifica of comm 2.1.2.2.
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.
Records source of for LACB include:
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:
O S
United U      Statess Atomic Eneergy Commiission (AEC      C),
L S
United U      Statess Nuclear Reegulatory Co  ommission (N    NRC),
O A
United U      Statess Environmen  ntal Protectiion Agency ((EPA),
E R
Wisconsin W          Deepartment off Natural Reesources (WD      DNR),
D H
Local/County L            y Governmen  nts.
S R
From Au  ugust 28, 197 73 to the preesent, the faccility has beeen operated uunder NRC License DPR      R-45.
se Boiling W Termination n 0 on past or p knowledge o asonable po d from a ra d areas were area or struc ssification (e e based upon lassification l radiologica assification a me of identifi
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.
. Final clas ign. The ch ations indica ng characteri nce, and an ations (for ex mencement of Docum maintained f documenta BWR, many Operational R afety Review Licensee Eve ite Initiated Operator Log Annual Envir Environmenta Regulatory ac Documentatio Health Physic ite inspectio Radiological Water Reactor Plan preliminary of site history ssibility for adiological p e also docum cture was cla e.g. Class 1, n the inform of LACBW al survey dat and (2) final ication of the ssification is haracterizatio ated in the H ization surve ny other ap xample, from f the FRS.
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.
ment Review to satisfy t ation for the y record type Review Com w Committe ent Reports (
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.
Incident Rep gs including ronmental M al investigat ctions conce on from inte cs surveys an on and survei and environ r
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.
radiological y or previou residual ra perspective.
2.1.2.5.        Property Inspectio  ons Several on-site prop  perty inspecctions were made overr the coursee of the HS          SA developm    ment.
mented.
Several site s events off interest weere identified d which weree subsequenttly documennted in the H    HSA.
assified as im Class 2 or C mation obtain WR areas w ta. Classify l classificati e survey are s performed on data was HSA as descr eys, operatio pplicable sur m Class 3 to w
2-5
the requirem e HSA recor es were eval mmittee (ORC ee (SRC) Me LER) Summ ports (IR),
Reactor Ope Monitoring R tions perform erning the sit rviews cond nd sampling illance type nmental surv 2-4 l surveillanc us survey inf adioactive co Potential mpacted, the Class 3) in a ned.
was based o ying a survey ion. Initial c a using the i and verified used to val ribed in this onal surveys rvey data m o Class 2 and ments of 10 rds review p luated. A su C) Meeting M eeting Minut
: maries, erator and H
: Reports, med by indep te, ducted with r g results asso documents a ey documen ce). Non-im formation an ontamination chemical h en a determi accordance w on historica y area has a classification information d as a DQO lidate or upd Chapter. R s in support may cause d from Clas CFR Part 50 process. Dur ummary of t
: Minutes, tes, Health Physic pendent entit retired/separ ociated with associated w
: nts, mpacted are nd are those a
: n. Areas w hazards incid ination of the with MARS al informatio minimum o n of most ar available wh O during cha date, as nece Radiological of decommi an increase ss 2 to Class 0.75(g)(1) p ring the con the types of cs entries,
: ties, rated site per identified ev with identifie eas are iden areas where were classifie dents on ow e initial imp SSIM, sectio on and avai of two stage reas is perfo hen the HSA aracterization essary, the i survey data issioning, ro e in survey s 1) until the provided a m nduct of the records revi
: rsonnel, vents, ed events, ntified there ed as wner-pacted on 2.2 ilable s: (1) ormed A was n and initial from outine area e time major HSA iewed


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::
La Cross License T Revision Q
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),
2.1.2.3.
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.
LACBW permits.
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.
allowed D the site, activities Several g licensing U
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.
U U
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.
W L
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
From Au This peri 1987, and 2.1.2.4.
Interview about the The pers the partic personne terms be site know Between individua standardi site perso the perso memorie operation 2.1.2.5.
Several Several s se Boiling W Termination n 0 Quality Contr Licen WR was opera The NRC Dairyland P to support o
: s.
government g, constructio United States United States United States Wisconsin De Local/County ugust 28, 197 iod includes d ISFSI cons Person ws with curre e site and to onnel interv cipants as w el were chos ing investig wledge and e 2010 and als contacte ized personn onnel who w onnel observ s of other q nal period ex Prope on-site prop site events of Water Reactor Plan rol (QC) /Qu ses, Permits ated in accor Operating L ower Coope operations du and regulato on, operation s Atomic Ene s Nuclear Re s Environmen epartment of y Governmen 73 to the pre s power ope struction and nnel Intervie ent or previo verify or cl views includ well as indivi sen due to th ated for the experience th 2011, appr ed as part nel survey w worked at th vations docum questionnaire xperience, or rty Inspectio perty inspec f interest we r
uality Assura and Author rdance with License for erative (Dair uring its ope ory agencies ns, and decom ergy Commi egulatory Co ntal Protecti f Natural Re nts.
esent, the fac erations to 1 d spent fuel ews ous employe arify inform ded a combin idual and gro heir knowled assessment.
hat ranged fr roximately 4 of the HS which was c e LACBWR mented on th e completers r by docume ons ctions were ere identified 2-5 ance (QA) fi izations several Fed LACBWR a ryland) to us erating lifeti have provid mmissioning ission (AEC ommission (N ion Agency (
esources (WD cility has bee 1987, perma off-load whi ees were per mation gather nation of qu oup interview dge of and a
. A number rom the site c 40 recollecti SA question completed v R during its o he questionn s, current on ntation disco made over d which were finding type d deral and Sta and support se any quant ime, and to ded oversigh
: g. These age C),
NRC),
(EPA),
DNR),
en operated u anent shutdo ich was com rformed to c red from the uestionnaires ws with sev association r of the pers construction ions of inte nnaire progr voluntarily b operational naire were c n-site worki overed durin r the course e subsequent documents.
ate of Wisco ting Technic tity of radioa implement d ht at LACBW encies includ under NRC own for dec mpleted in 20 collect first-h e records tha s completed veral of the p with the sys sonnel interv n period to sh erest were l ram. This by retired/sep years. With corroborated ing staff tha ng the record e of the HS tly documen onsin license cal Specifica active mater decommissio WR during s de:
License DPR commissionin 012.
hand inform at were revie by a majori participants.
stems and so viewed poss hutdown.
logged from consisted parated staf h few except d either by lo at had LACB ds search.
SA developm nted in the H es and ations rial at oning
: siting, R-45.
ng in mation ewed.
ity of Key ource essed m the of a ff and
: tions, ogged BWR ment.
HSA.  


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.
La Cross License T Revision 2.1.3. O LACBW Dairylan Mississip bordered Mississip LSE com served as confirme road on t th fo an 1
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.
th a
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.
li The plan Chalmers provided LACBW 19 years defueling Operatin No. 56, d 333 irrad into five Limited d ongoing shipped internals Building removed undergro Condens Water Sy Building 2.1.4. In Based on notificati se Boiling W Termination n 0 Operational WR was a 5
In ncidents involving leakaage from thee resin regenneration wasste system tto the Circullating Water W      Dischaarge line werre noted from  m 1967 to 19973.
: d. This sing ppi River so d on the no ppi River an mprising app s the RCA b ed to be suit the south sid he land north ormer Genoa n operationa 75 feet from he fenced ISF small parce icensed site.
In n 1970, pottentially con    ntaminated Control Rodd Drive (C      CRD) oil waas used for dust suuppression on o the licenseed site roadss.
nt was one s Company d them with a WR achieved until it was g was compl g License D dated Augus diated fuel as (5) dry cask dismantleme at LACBW for disposal intact, and 2
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)
, and shippe
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)
, including t ound gas sto ate Storage ystem pump ncidents n the review ions, occurre Water Reactor Plan History 50 Megawatt gle unit, also outh of the orth by the nd Highway proximately boundary du table for unr de of the plan h of the LA a Station #1 al 350 MWe m the LSE, FSI facility t l of land to t of a series was the ori a provisional d initial criti s permanent leted on June DPR-45, pur st 4, 1987; a ssemblies, w ks and transfe ent of shutdo WR since 199 l in June 20 29 control ro ed for dispo the spent fue orage tanks)
On O Novembeer 24, 1980, residual rad        dioactive conntaminationn was detected in soils uunder th he Turbine Building.
Tank and s, heat exch w of existin ence reports r
B          (D DPC-80-93 Incident I          Repport, ORC-880-71, ORC--80-75, ORC    C          87, ORC-80-9  97, LER 80--12)
t Electric (
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)
o known as G Village of Mississippi
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.
: 35. The lic 1.5 acres of uring operat restricted us nt. Other pro ACBWR plan (G-1) coal (
T        (DPPC-80-106 Inncident Repoort) 2-7
fossil gener that is locate the east of H of demonst iginal licens l operating l icality on Ju tly shut dow e 11, 1987.
rsuant to 10 and a posses which were i ferred to the own and unu
: 94. Waste s 007. The R ods in place osal in June el storage rac
); Condensa condenser);
angers, pipin g plant reco s, and questi 2-6 (MWe) Boil Genoa Statio f Genoa, Ve i River and ensed site c the licensed tions. Mate e before rel ominent feat nt, including (and later oil rating station ed directly so Highway 35, tration plant see; the AEC icense.
uly 11, 1967 wn by Dairy The Dairyla 0 CFR 50, w ss but not-op in Fuel Elem sites ISFSI used systems stored in the Reactor Pres was filled w e 2007. Oth cks, Gaseou ate system Turbine an ng and comp ords (e.g. an ionnaires), i ling Water on #2, is loc ernon Coun d a narrow omprises a t d site. The erial leaving ease. The s tures on the g the site sw l) fueled pow n (G-3) loca outh of G-3, across from ts funded in C later sold 7, and was yland on Ap and authority was terminat perate status ment Storage by Septemb s and waste e FESW and sure Vessel with concret her systems us Waste Dis and Feedwa nd Generato ponents that nnual and s incidents wi Reactor th cated on the nty, Wiscons strip of la total of 163 LSE bounda g the LSE w site is acces site include:
witchyard an wer plant (re ated south an
, and m LACBWR n part by A d the plant t operated fo pril 30, 198 y to operate ated by Lice s was grante e Well (FES ber 2012.
disposal op d other Clas (RPV) wit te, removed and compo sposal System ater system or; and Com t were locate semi-annual ith radiologi hat is owne east shore o sin. The s and between
.5 acres, wit ary is fenced was surveyed sed by an a nd the site o moved in 19 nd approxim that is part o AEC. The A to Dairyland or approxim
: 7. Final re LACBWR u ense Amend ed by NRC.
SW), were p erations has ss B/C waste th head insta from the Re onents have m (except fo m (except fo mponent Co ed in the Tu reports, lice ical or hazar ed by of the ite is n the th the d and d and access of the 989),
mately of the Allis-d and mately eactor under dment The placed been e was
: alled, eactor been or the or the ooling urbine ensee rdous


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.
La Cross License T Revision material placing t the LSE the struct LSE, wh Special Monitori reports c shutdown around th posing a of LACB contamin 2.1.4.1.
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)
The hist involving potential chronolo T
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)
fl In W
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)
In su In d
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.
st O
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.
th 8
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.
O th 8
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.
O ap In O
b 2-8
in se Boiling W Termination n 0 implication the reactor in and, while c tures and so ich is alread emphasis w ing Reports covering the n in 1987.
he plant site significant p BWR site nation from s Radio torical revie g system lea to affect th gical order a The stainless loor. Inciden ncidents inv Water Discha n 1970, pot uppression o n
Septemb econtaminat team cleanin On Novembe he potential 0-84 Inciden On Novembe he Turbine B 7, ORC-80-9 On Decemb pproximately ncident Repo On December nto the Turbi Water Reactor Plan ns occurred n a SAFSTO contributing ils directly r dy known to was placed o (REMP), fo e periods o Available sa e were also probability o land areas system failur ological Spill ew indicated akages, radio e classificati as follows; steel liner nts involving olving leaka arge line wer tentially con on the license
: ber, 1977, tion of a Fo ng tank in the er 5, 1980, p for leakage nt Report, OR er 24, 1980, Building. (D 97, LER 80-ber 6, 1980 y 1/2 gallon ort, ORC-80 r 15, 1980, t ine Building r
between th OR conditio to the radiol related to the be impacte on obtainin focusing on of SAFSTOR ampling resu reviewed. T of impacting and structu res resulting ls d that betwe ological spill ion of LACB in the FESW g leakage of age from the re noted from ntaminated ed site roads removable orced Circul e Reactor Bu artial blocka of drain wa RC-80-71, O residual rad DPC-80-93 I
-12)  
, the Turb of waste w 0-71, ORC-8 the Turbine g Basement T 2-7 he commenc n in 1987.
logical conta e operation o ed.
g and revie gaseous an R and deco ults associat The objectiv g the radiolo ures. Thes g in airborne een 1967 a ls, and/or rad BWR structu W had a his f the FESW w e resin regen m 1967 to 19 Control Rod
: s.
e alpha c
ation Pump uilding 701 f age of drain ater into the ORC-80-75, dioactive con Incident Rep bine Build water to the 0-75, ORC-Building Wa Tunnel. (DP cement of p All of these amination an of the reacto ewing the a nd liquid rel ommissionin ted with soi ve was the i ogical status se included releases, liq and 1987, th dioactive liq ures or soils story of leak were noted f neration was 973.
d Drive (C contaminatio (FCP) duri foot elevatio lines under soil under th ORC-80-87 ntamination port, ORC-8 ding Waste Turbine Bu 80-87, ORC aste Water T PC-80-106 In plant operati e incidents t nd potential or, were con annual Radi leases since ng activities il and groun identification or hazardou system, st quid spills or here were s quid effluent
: s. The incid kage to the R from 1967 to ste system t CRD) oil wa on was d
ing mainten on. (ORC, 0 Turbine Bu he Turbine B 7, ORC-80-9 n was detect 80-71, ORC-Water T uilding floor C-80-97)
Tank overflo ncident Repo ion in 1967 took place w contaminati ntained withi ioactive Eff 1967, inclu s after the ndwater with n of those e us material s tructure, or r releases.
several inci releases wit dents are list Reactor Bui o 2012.
to the Circul as used for detected d
ance involv 09/27/77) uilding result Building. (D
: 97) ed in soils u 75, ORC Tank overfl
: r. (DPC-80 owed waste w ort) 7 and within ion of in the fluent uding plant hin or events status area idents th the ted in ilding lating dust during ving a ted in DPC-under C owed 0-102 water


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.
La Cross License T Revision In w
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 O
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.
un O
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.
co in O
The surv vey units esttablished by the HSA were  w      used as initial surveey units for characterizaation.
si co B
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.
to O
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.
ap b
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.
2.1.4.2.
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
Between release o ranged fr and fuel impacted policies releases.
2.1.5. F LACBW within its been imp post ope Survey fo for fissio Structure Turbine Stack. In to be dire An area s support b various w se Boiling W Termination n 0 ncidents invo waste water t Discharge lin On January nspecified v On May 31, ontaminated nto the basem On July 02, 1 ight flow se ontaminated Bay door. In o an unrestri On July 16, pproximately asement floo Chem 1967 and 20 of chemicals rom spills of oil from sy d buildings.
and proced Findings and WR was desig s many syste pacted due t erational his or SAFSTOR on products t es classified Building, W n addition to ectly impacte surrounding buildings su warehouses a Water Reactor Plan olving leaka tanks throug ne were noted 30, 1981, volume of wa 1982, a lid d water and ment. (DPC 1982, approx eal rupture t d water flow n addition, a cted area. (D 1983, a leak y 15,000 gal or. (LER 83 mical Spills 014, the HSA s and/or pote f acids and c ystems and These spills dures for id d Conclusio gned with mu ems, compon to routine op tory of the R (7) identifi to enter and i as impact WTB, Low S o the structur ed by the op the LSE ha uch as the L and storage b r
age of potent gh the norma d from 1980 the Turbin ater into the seal failed o spent resin 51 Incid ximately 1,2 o the Turbin wed into the approximatel DPC-82-58 I k in the Sea llons of reac 3-07)
A document entially haza caustics used storage tank s were contr dentification ns ultiple bound nents, and st perations an plant. Dai ied historica impact react ted by the Specific Act res, the soils peration of th s also been d LACBWR C buildings.
2-8 tially contam al effluent re 0 to 1986.
e Building laundry room on a spent r onto the flo dent Report) 200 gallons o ne Building soils outsid ly 25 gallons Incident Rep al Water Inj ctor coolant ted several in ardous liquid d in the plan ks. A majo rolled and re n, control a daries to con tructures. M nd maintenan iryland LAC al failed fuel tor and supp operation o tivity (LSA) s surrounding his facility. T designated a rib House, L minated liqui elease pathw Waste W
: m. (DPC-81 resin liner w oor of the S of condensat g floor, and de the Turbi s of contam port, LER 82 njection Syst to be discha ncidents inv ds to the en nts various ority of the emediated in and remedia ntrol and con Many of these nce activitie C-TR-138, I incidents at ort systems.
of the facilit
) Building, g these build This area is as impacted.
LACBWR A id from the T way to the C Water Tank 1-10 Inciden which resulte Spent Resin te water was approximate ine Building minated liquid 2-016) tem leak at arged to the volving the u nvironment.
systems to t incidents oc n accordance ation of haz ntain the rad e systems an es during the Initial Site t LACBWR ty include R WGTV, and dings have a defined by t This area i Administrati Turbine Bui Circulating W overflowed nt Report) ed in the sp Liner Room s released fr ely 20 gallo g door and T d was discha 1A FCP ca Reactor Bui unplanned sp These inci the spill of d ccurred insid e with the st zardous ma dioactive con nd structures e operationa Characteriz and the pote Reactor Buil d the Ventil also been de the LSE fenc includes anc ion Building ilding Water d and pill of m and rom a ons of Truck arged aused ilding pill or idents diesel de of tation aterial ntents have al and zation ential
: lding, lation emed ce.
cillary g and


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).
La Cross License T Revision In additi support impacted LSE whi the LSE 2.1.6. In As part o into preli and exist 2.1.6.1.
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.
The entir larger ph classifica efficient identified were clas and are id were clas current c 2.1.6.2.
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:
The surv or open l were deli radioactiv relatively appropria The surv Prior to accordan sizes for The deco segmenta the excep any struc survey u These ob volume c In additio the purpo se Boiling W Termination n 0 ion to the a buildings, t d to provide ich is consid areas compr nitial Surve of the HSA p iminary surv ting survey d Surve re 163.5 acr hysical sectio ation. Surv and practic d in the area ssified as n dentified in ssified as im lassification Surve vey areas wer land area tha ineated to ph vity to the e y compact sh ate for the si vey units est characteriza nce with the g survey units ommissionin ation, remov ption of stru cture will re units have be bjectives inc contained on on, the surve ose of chara Water Reactor Plan area within the open lan a buffer zon dered non-im rising approx ey Areas/Un process, the i vey areas an data.
Reacttor Building g, WTB, WG    GTV, Ventilaation Stack G  Grounds (L1010101),
y Areas res licensed ons of the sit vey area size cal size need
Turbiine Buildin  ng, Turbine Office Bu        uilding, 1B Diesel G    Generator Buuilding Groounds (L1010102),
: a. Survey ar on-impacted the HSA. S mpacted. F ns by area.
LSA Building, Maintenance M              Eat Shack Grounds G        (L10010103),
y Units re further di at is surveye hysical areas extent practi hapes and hi ite operation tablished by ation, survey guidance pro s for FSS.
North h LSE Area (L1010104).
ng approach val and dispo cture basem emain at sit een establish clude provid nsite, and dis ey units estab acterization p r
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.
the LSE an nd immedia ne between t mpacted. Th ximately 1.5 nits and Clas impacted LA nd assigned site was div te that may e was deter ded to boun reas that hav
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.
: d. These ar Survey areas Figure 2-1 p vided into su ed and evalu s with simila cal. To the ghly irregula nal history or the HSA w y unit sizes f ovided in M that will be osal of all im ment floors an te closure a hed for struc ding survey d sposition opt blished for s planning and 2-9 nd the open ately surroun the LSE and he licensed s acres of the ssification ACBWR stru area classifi vided into su contain one rmined base nd the latera ve no reason reas have no with reason provides an i urvey units.
c          Classs 1 open lannd survey unnits are showwn on Figuree 2-1.
uated as a sin ar operationa extent prac ar shapes we r the site top were used as for Class 1 o ARSSIM, se e implement mpacted sys nd walls that and consequ ctures to fac data for rem tions for the structures tha d do not cor land areas unding the L d the G-3 lan site comprise e owner cont uctures and o ications base urvey areas.
2.1.6.4.          Class 2 Open Lan  nd Areas The follo owing open land l    areas were w classifieed as impacteed Class 2:
or more sur ed upon the al and verti nable potenti o radiologica nable potenti illustration o A survey u ngle entity f al history or ctical, survey ere avoided u ography.
LACB  BWR Adm    ministration Building, LACBWR          R Crib Hoouse, Wareehouse Groounds (L2011101),
initial surve open land su ection 4.6 fo ted at LACB stems and ab t reside 3 fee uently, be su cilitate other mediation pla waste.
G-3 Crib C House, LACBWR Circ. Water Discharge L              Line, Area SSouth of LSE  E Fence Groounds (L2011102).
at are 3 feet rrespond to surroundin LSE fence nd and facil es a total of trolled area.
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.
open land ar ed on the op
Class 2 open o    land surrvey units arre shown on Figure 2-1.
. Survey ar rvey units de specific ar ical extent o al for residu al impact fro ial for residu of the LACB unit is a port following FR similar pote y units were unless the un ey units for urvey units or the sugges BWR calls bove-grade et below gra ubjected to r characteriz anning, estim below grade the survey u g the LACB is designate lities south o f 163.5 acres reas were div perational hi reas are typi epending on rea and the of contamin ual contamin om site opera ual contamin BWR site an tion of a stru RS. Survey ential for res e established nusual shape characteriza were adjust sted physical for the com structures.
2.1.6.5.          Class 3 Open Lan  nd Areas The follo owing open land l    areas were w classifieed as Class 3 :
ade, no porti FRS. How zation objec mating the w e are intende units that w BWR ed as of the s with vided istory ically n their most nation nation ations nation nd the ucture units sidual d with e was ation.
North h End of Liccensed Site (L  L3012101),
ted in l area mplete With ion of
Transsmission Sw  witchyard Areea (L301210    02),
: wever, tives.
Plantt Access, ISF FSI Haul Road Grounds (L3012109)).
waste ed for will be
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.
La Cross License T Revision used for section 5 Tables 2-impacted site struc 2.1.6.3.
Class 3 open o      land surrvey units arre shown on Figure 2-1.
The follo React Turbi (L10 LSA North The basis soil by r spills of packages Based on subsurfac the unres 2.1.6.4.
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..
The follo LACB (L20 G-3 C (L20 Based up surveys p radioactiv Class 2 o 2.1.6.5.
G-3 Coal C Plant Grounds G        (L40 012103)
The follo North Trans Plant se Boiling W Termination n 0 the FRS o
Coal Pile Ground  ds (L4012105)
.5.2 of Chap
Capp ped Ash Impoundment Grounds G          (L40012106)
-1 and 2-2 p d structures ctures. A sum Class owing open l tor Building ine Buildin 10102),
Grou unds East of Highway H        355 (L4012107)
Building, M h LSE Area s for this cla radioactive m radioactive s and contain n an assessm ce soils in th stricted use c Class owing open l BWR Adm 11101),
Hwy 35/Railroad  d Right of Way W Grounds (L4012108))
Crib House, 11102).
The non--impacted op  pen land surv vey units aree shown on F Figure 2-1.
pon a review performed in ve contamin open land sur Class owing open l h End of Lic smission Sw t Access, ISF Water Reactor Plan f remaining pter 5).
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.
provide a de respectively mmary of th 1 Open Lan land areas ha g, WTB, WG ng, Turbine Maintenance (L1010104) assification is material in t liquids and ners.
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:
ment of histor hese areas c criteria. Clas 2 Open Lan land areas w ministration LACBWR w of the hist n these area nation to exc rvey units ar 3 Open Lan land areas w censed Site (L witchyard Are FSI Haul Ro r
Reacttor Building g (B1010001)
g below grad etailed list o
Wastte Treatmentt Building (B  B1010002)
: y. Figure 2-2 he survey uni nd Areas ave been cla GTV, Ventila Office Bu Eat Shack G s due to a se these areas d resins, radi rical inciden could possibl ss 1 open lan nd Areas were classifie
Ventiilation Stack k (B1010003  3)
: Building, Circ. Water torical inform as as docume eed the unre re shown on nd Areas were classifie L3012101),
Wastte Gas Tank Vault (B101    10004)
ea (L301210 ad Grounds 2-10 de structure of the survey 2 provides a it classificati assified as im ation Stack G uilding, 1B Grounds (L10 ries of docum during facil ioactive sys nts and event ly contain re nd survey un ed as impacte LACBWR Discharge L mation and ented in the estricted rele Figure 2-1.
Turbiine Building g (B1010005  5)
ed as Class 3 02),
Dieseel Generatorr Building (B  B1010006)
(L3012109) es (designate y units for b a detailed in ions are pres mpacted Clas Grounds (L1 Diesel G 010103),
LSA Building (B  B1010007)
mented incid lity operation stem leakage ts, it was an esidual radio nits are show ed Class 2:
Main ntenance Eat Shack (B10    010008)
R Crib Ho Line, Area S operational HSA, there ease criteria.
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
ed as STS a both the ope nventory of sented as fol ss 1:
010101),
Generator Bu dents of the ns. These i e, and storag nticipated tha oactive mate wn on Figure ouse, Ware South of LSE radiation an e was a pote and discuss en land area the building llows.
uilding Gro contaminati incidents in ge of radioa at the surfac erial in exce e 2-1.
ehouse Gro E Fence Gro nd contamin ential for res ed in s and g and ounds ion of clude active e and ess of ounds ounds nation sidual


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.
La Cross License T Revision Historica in concen Class 3 o 2.1.6.6.
LACB BWR Crib House H        (B201 10101)
Based on in the HS contamin G-3 C Coal Capp Grou Hwy The non-2.1.6.7.
G-3 Crib C House (B2010102)
The follo structure These str radioactiv radioactiv majority React Wast Venti Wast Turbi Diese LSA Main Througho spread o were rou structure structura below gr subjected se Boiling W Termination n 0 al informatio ntrations in e open land sur Non-I n a review o SA, the bala nation and ha Coal Plant G Pile Ground ped Ash Imp unds East of H 35/Railroad
(
-impacted op Class owing is a li
LACB BWR Administration Bu        uilding (B20 010103)
: s. The com ructures con ve waste sy ve material of the curren tor Building te Treatment ilation Stack te Gas Tank ine Building el Generator Building (B ntenance Eat out facility o f loose surf utinely post s involves l material as rade, no por d to FRS. Th Water Reactor Plan on contained excess of the rvey units ar Impacted Op f the operati ance of the as been desig Grounds (L40 ds (L401210 oundment G Highway 35 d Right of W pen land surv 1 Structures ist of the m mplete list of ntain the nuc ystems, and n was routine nt radioactiv g (B1010001 t Building (B k (B1010003 Vault (B101 g (B1010005 r Building (B B1010007)
LACB BWR Wareh    house #1 (B2  2010104)
Shack (B10 operations, th face contam ted as cont the comple s waste. Wi rtion of the he Class 1 st r
LACB BWR Wareh    house #2 (B2  2010105)
d in the HSA e unrestricted re shown on pen Land Are ing history o 163.5 acre li gnated as no 012103)
LACB BWR Wareh    house #3 (B2  2010106)
: 5)
Backk-up Control Center (B30    012101)
Grounds (L40 5 (L4012107 Way Grounds vey units are s
Transsmission Sub  b-Station Sw witch House (B3012102))
major buildin f all impact clear reactor nuclear fuel ely handled, ve material in
G-1 Crib C House (B3012103)
)
(
B1010002)
Bargee Washing Break B      Room (B3012104))
: 3) 10004)
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.
: 5)
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.
B1010006) 010008) hese structur ination, and taminated a ete segment ith the excep se structure tructural surv 2-11 A indicated th d release cri 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),
eas of the facility icensed site on-impacted.
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.
012106)  
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
)
(L4012108) e shown on F ngs that were ted structura r, primary re l handling a
, transferred nventory at L res were sub d airborne ra areas. The tation, remo ption of stru s will rema vey units are hat the prese teria was no y and histor has no reas
)
Figure 2-1.
e initially cl al survey un eactor system and storage s d, and stored LACBWR r bjected to spi adioactive m decommis oval, and d uctural floor ain at site cl e depicted in ence of resid ot expected.
rical incident sonable pote lassified as nits is provid ms, reactor systems. D d within the resides in the ills of radioa material. St sioning app disposal of s and walls losure and a n Figure 2-1 dual radioac ts as docum ential for res impacted Cl ded in Table support sys uring operat ese building ese structure active liquid tructural sur proach for all systems that reside 3 are therefor ctivity ented sidual lass 1 e 2-2.
: tems, tions,
: s. A es:
ds, the rfaces these s and 3 feet re not


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.
La Cross License T Revision 2.1.6.8.
Characterization dataa acquired th  hrough the execution e            of the Plan waas used to m meet three priimary objectivees:
The follo Class 2 o complete LACB G-3 C LACB LACB LACB LACB Back Trans G-1 C Barge These str structure LACBW Washing structure Administ the decom LACBW structure The LAC Switch H unrestrict Supplem Manual depicted Based on in the H section 2 residual the G-3 C 2.2.
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.
C From Oc accordan se Boiling W Termination n 0 Class owing is a li or 3 structur e list of all im BWR Crib H Crib House (
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.
BWR Admi BWR Wareh BWR Wareh BWR Wareh k-up Control smission Sub Crib House (
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.
e Washing B ructures did s associated WR workers g Break Room s because th tration build mmissioning WR Class 2 or s will remain CBWR Adm House will n ted release ment 1, Multi (MARSAM in Figure 2-n a review o HSA, coup 2.3.5), the bu contaminatio Crib House, Characteriza ctober 2014 nce with th Water Reactor Plan 2 and 3 Stru ist of some res. All are mpacted stru House (B201 (B2010102) nistration Bu house #1 (B2 house #2 (B2 house #3 (B2 Center (B30 b-Station Sw (B3012103)
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.
Break Room not routinely d with LAC and therefo m were not a hey reside i ding, the G-3 g approach c r 3 systems n at site clos ministration b not be subj using a gr i-Agency Ra E) (8). The
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.
-1.
2-13
f the operati pled with t uildings ass on and have will remain ation Appro through Aug he Characte r
uctures of the major e located wi uctural surve 10101) uilding (B20 2010104) 2010105) 2010106) 012101) witch House (B3012104) y house radi CBWR listed re considere associated w in a Class 3 3 Crib Hous calls for the and structur sure and ther building, the ected to FR raded survey adiation Sur e Class 2 an ing history o the results sociated with e been desig intact and fu oach gust 2015, s erization Su 2-12 r buildings t ithin the lice y units is pro 010103)
(B3012102)
)
ioactive syst d above are ed Class 2 with LACBW 3 land area.
se and the T complete se ral material a refore will n e G-3 Crib H RS. Instead y approach rvey and As nd Class 3 s of the facility of charact h the G-3 s gnated as no unctional for site characte urvey Plan.
that were in ensed site b ovided in Ta
)
tems or mate outside of or 3. The WR operation With the Transmission egmentation, as waste or ot be subjec House and th d, these stru using the ssessment of structural su y and histor terization su station have on-impacted.
r G-3 power erization of L The Ch nitially classi but outside o able 2-2.
erials during the LSE bu G-1 Crib H ns but are co exception o n Sub-Statio
, removal, an salvage. No ted to FRS.
he Transmis uctures will guidance o of Materials urvey units rical incident urveys (as no reasona
. The G-3 s r operations.
LACBWR w haracterizatio ified as imp of the LSE.
g operations.
ut were use House and B onsidered Cl of the LACB on Switch H nd disposal o portion of ssion Sub-St be surveye f NUREG-s and Equip for building ts as docum summarize able potentia station, inclu was perform on Survey pacted The The ed by Barge lass 3 BWR
: House, of all these tation d for
: 1575, pment gs are ented ed in al for uding med in Plan


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.
La Cross License T Revision incorpora documen develope executing procedur safely an Characte objective Provi Deve Supp volum The deco buildings character subjected removed 1757, Ap The char subsurfac structura surveys w structure used to m above gr of the ex
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.
: planned, planning A signifi unit is cla design fo result in unit meet errors.
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::
As site-s LACBW selected.
: 1) State the problem m,
in NURE Paramete assess the se Boiling W Termination n 0 ated the pre nted in the su ed to provide g characteriz res and surv nd effectively rization data es:
: 2) Identtify the decission,
ide radiologi elop the requ ort the eva mes.
: 3) Identtify inputs to o the decision  n,
ommissionin s, structures, rization effo d to FRS. E prior to the ppendix O.
: 4) Defin ne the study boundaries,
racterization ce soils, pav l basements were perform
: 5) Deveelop a decisio  on rule,
: s. Upon com make determ rade or subg xpected end-executed an icant questio assified corr or FRS. A a survey des ts the release pecific Deri WR at the tim The screen EG/CR-5512 er Analysis e correct cla Water Reactor Plan evious histo urvey areas e guidance a zation survey ey unit spec y acquire the a acquired th ical inputs n uired inputs f aluation of r ng approach
: 6) Speciify limits onn decision errrors, and
, and compo orts focused Extensive ch e performanc n surveys fo ved surfaces, s that will re med in the L mpletion, the minations on w rade structu
: 7) Optim mize the design for obtaiining data.
-state structu nd documen on that must rectly. The a classificatio sign that doe e criteria. In ived Concen me the chara ning DCGLs 2 Volume 3 (9), Table 6 assification o r
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.
orical opera from the HS and direction y activities.
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).
cific survey e requisite ch hrough the e necessary for for LTP, and remediation for LACBW onents to a d d on open haracterizatio ce of final s ocused on g
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
, and concret emain in the LACBWR Ad e data was a whether add ures, surface ures at LAC nted with the be answere appropriate c on which un es not obtain n some cases ntration Guid acterization s presented i
, Residual R
.91 (Pcrit = 0 of impacted o 2-13 ational and SA and prev n to the pers The Plan w instructions haracterizati execution of r the design o d
alternatives WR calls for t depth of at l land areas on of equipm surveys is no general open te pads. Co e end-state dministration ssessed for q ditional chara and subsurf CBWR. Con e same data ed by the cha classification nderestimate n adequate in s, this can in deline Level survey was in NUREG-1 Radioactive 0.10) for soil open land or radiological vious site ch sonnel respo worked in co s (sample pl on data.
the Plan wa of FRS, s and techn the demoliti least 3 feet b and remain ment, system ot required i n land areas oncrete core condition.
n Building a quality and a acterization face soils, or ntinuing cha quality and aracterizatio n of a survey es the poten nformation to ncrease the p ls (DCGLs) performed, 1757 and th Contamina ls were used r soil survey l informatio aracterizatio onsible for im njunction w lans) that w as used to m nologies and ion and remo below grade ning structu ms or struct in accordanc s including:
samples wer In addition, and several o adequacy. T data is requ r beneath th aracterization d the results on is whethe y unit is crit ntial for con o demonstra potential for m were not ye alternate ac e concentrat ation from D d as alternat units.
on collected on efforts. I mplementing with impleme were develop meet three pri d estimate w oval of all on
: e. Conseque ures that wi tures that w ce with NUR site surface re taken from
, characteriz of the G-3 st The data was uired, primar he concrete f n surveys w included in er or not a su tical to the su tamination c ate that the su making deci et establishe ction levels tion values f Decommissio e action leve d and t was g and enting ped to imary waste n-site
: ently, ill be ill be REG-e and m the zation tation s then ily of floors will be n FRS urvey urvey could urvey isions ed for were found oning els to


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.
La Cross License T Revision For struc to evalu 7,100 dpm Appendix radionuc the conse for Cs-13 2.2.1. D DQOs w FRS. Ho to determ unrestrict inspectio nature, e applicabl Characte outlined
The areaas and materials surveyeed and/or sam      mpled in andd around thee licensed arrea as part oof the characterrization surv vey included:
: 1) State
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).
: 2) Ident
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.
: 3) Ident
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.
: 4) Defin
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.
: 5) Deve
Samples weree taken from  m the septic taanks.
: 6) Speci
Scans and sam  mples were taken on LA    ACBWR Addministrationn Building suurfaces and drain arreas.
: 7) Optim The DQO collect. N and will assessme obtaining obtained Direct m Minimal that exhi Detect (H 2.2.2. S Characte approved approach se Boiling W Termination n 0 ctures, the gr ate the clas m/100cm2 to x H. Use of lide distribu ervative appr 37 is signific Data Quality were impleme owever, the mine the rad ted use crit ons and surv xtent and ra le structures rization surv in MARSSIM the problem tify the decis tify inputs to ne the study elop a decisio ify limits on mize the des Os for site No structure therefore no ent of concre g core samp to determin measurement Detectable ibited the hi HTD) radion urvey Desig rization sur d procedures h based upon Water Reactor Plan ross screenin ssification o otal gross be f the Co-60 ution for surf roach was to cantly greate y Objectives ented for ch goal of char ionuclide m teria to dem veys of suff ange of radio
Scans and sam  mples were taken t      on G-33 Building aaccess and heeavily travelled surfaces.
, residues, so veys were de M, Appendi m,
Concrete C          sam mples were taken in the basement arreas of the R         Reactor Building, WTB    B, and Piping and Ventillation tu  unnels.
: sion, o the decision boundaries, on rule, n decision err ign for obtai characteriza es located ab ot be subject ete in basem ples. Soils ne the mean s and scans Concentrati ighest activi nuclide(s).
A backgroun    nd radiation study was performed on materialls similar too those founnd at LACBWR L            including: asp phalt, concrette, and soil.
gn rveys were s and the Cha n the DQOs f r
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.
ng level that of survey u eta-gamma s screening v face contam o assume a d er.
2-15
s haracterizatio racterization mixture, wher monstrate co fficient quali oactive cont oils and surf esigned to g ix D. The se n,
rors, and ining data.
ation include bove 3 feet b ed to FRS.
ments and su were sampl and maximu s of surface ons (MDC) ity were sen designed a aracterizatio for each surv 2-14 t was used d units was th surface activ value was co mination wou distribution o on surveys in n is to quanti reas the FRS ompliance w ity and qua tamination in face water.
gather the ap even steps in ed identifyin below grade Consequent urrounding so led volumet um activity a soils were as will be e nt to an off-and perform on Survey Pl vey unit. Fo during chara he nuclide-vity based on onservative a uld be princi of 100% Co n a similar m ify and delin S goal is co with 10 CFR antity were n each appli propriate da n the DQO d ng the types will remain tly, sample c oils. Buildi trically. Su as well as th made using employed fo
-site laborat med in acco an. Survey or example, acterization a specific scr n Co-60 from as it was an ipally Co-60
-60 since the manner as an neate contam omparison of R 20.1402.
performed t icable surve ata using the development s and quanti n following d collection wa ing concrete ufficient me he sample sta g the same or FSS. Vo tory for ana ordance wit design incor an open land as an action reening valu m NUREG-nticipated tha 0 and Cs-137 e screening v nticipated fo minated area f data agains Characteriz to determin ey unit, inclu e DQO proce process are:
ities of med decommissio as focused o e was sample asurements andard devia instruments lumetric sam lysis of Har th all appli rporated a gr d survey uni level ue of
: 1757, at the 7 and value or the as and st the zation e the uding ess as dia to oning on the ed by were ation.
s and mples rd-to-icable raded it was


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.
La Cross License T Revision designate the unres Class 1 s present.
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.
to identif Class 2 o survey m select loc measurem biased su unit. A delineate warrante survey un The area character S
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.
al su B
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.
sy F
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.
R ad S
2.2.2.3.         Scan Coverage C
A S
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.
S ar S
2.2.2.4.          Typess of Measureements and Samples S
C P
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.
A L
typ 2-16
2.2.2.1.
The num by assess se Boiling W Termination n 0 ed as Class stricted relea survey unit f The survey fy the lateral or Class 3 re measurement cations for s ment and/or urvey design A biased app e the extent o d if the char nit.
as and mater rization surv urface scans ll Class 1, 2 urvey unit L Biased subsur ystems of c igure 2-3.
Random sam ddition, soil cans and s Administratio amples were cans and sam reas.
cans and sam Concrete sam iping and V A backgroun LACBWR in Numb mber of measu sing the sam Water Reactor Plan 1 because it ase criteria.
focused on b design was l and vertica eceived surv locations an static measu sample loc n or a random proach was of an area th racterization ials surveye vey included s and random 2, 3, and no L3012102 (i.e rface soil sa oncern in C mples were ta samples we amples wer on Building e taken from mples were mples were t mples were t entillation tu nd radiation cluding: asp ber of Static urements an ple size nece r
t may conta Therefore, t bounding the based upon al extent of th veys develop nd scan area urements and cations at ran m approach warranted hat requires effort was d ed and/or sam m and biased on-impacted e., the switch amples were Class 1 and aken from a ere obtained re taken on and the G-3 m the septic ta taken on LA taken on G-3 aken in the unnels.
study was phalt, concret Measuremen nd/or sample essary to sat 2-15 ain levels of the character e contaminat n the number he contamin ped to includ
: s. Biased su d/or samples ndom. The was address when the c remediation designed to v mpled in and d surface and open land a hyard).
taken along 2 areas incl asphalt and c directly belo n accessible Coal Plant.
anks.
ACBWR Ad 3 Building a basement ar performed te, and soil.
nts and/or S s that were t tisfy the DQO f radiologica rization surv tion where c r of measure nation. Area de a combin urvey design
: s. Random e decision of sed by the D characterizat
: n. Alternativ verify the ba d around the d subsurface area survey gside and un luding the p concrete from ow the aspha e roof surfa dministration access and he reas of the R on material amples taken in each Os.
al contamina veys that wer ontaminatio ements and as classified nation of ran ns used know survey desig f whether to DQO process tion effort w vely, a rando asis for the c e licensed ar e soils samp units with derneath und piping syste m pads and alt to a one m ace areas of n Building su eavily travel Reactor Bui ls similar to h survey uni ation greater re performed n was poten samples req as non-impa ndom and b wn informati gn selected o use primar s for each su was designe om approach classification rea as part o ples were tak the exceptio derground p ms as show paved area meter depth.
f the LACB urfaces and led surfaces.
lding, WTB o those foun it was determ r than d in a ntially quired
: acted, biased ion to static rily a urvey ed to h was n of a of the ken in on of piping wn on
: s. In BWR drain B, and nd at mined


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revisionn0 2.2.2.4.1.     Gamm  ma Surface Scans S
La Cross License T Revision For the c that will and/or sa of residu For the sample s vertical e For non-validate measurem trivial lev generated 2.2.2.2.
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)
For the c survey u Sample l to specifi that wer responsib survey d radioactiv potential from the 2.2.2.3.
(    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.
Survey u area to b area scan Supervis was give survey un 2.2.2.4.
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.
The char (beta and survey of FRS con and volu sampling following se Boiling W Termination n 0 characterizat be subjecte amples taken al radioactiv characteriza size was bas extent of the impacted an the basis ments and/o vels of licen d radionuclid Determ characterizat nits that wil locations we ic locations w re taken in ble Radiolog design proc vity, depres spill locatio HSA aided Scan C units were sc be scanned i nned was c or and/or th en to inform nit.
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.
Types racterization d gamma); st f any concre nsisted of a c umetric samp g of surface g is a descrip Water Reactor Plan tion of impa ed to FSS, th n in the surve ve contamina ation of Cla sed upon the contaminati nd Class 3 op of the clas or samples w nsee-generat des are prese mination of tion of non-ll be subject ere determin within the su each surve gical Protect cess. Con sions, disco ons, or areas in the select Coverage canned to th n each surv ontingent up e Project He mation from s of Measure n survey of tatic beta me ete and/or as combination ples. The su and subsurf ption of the d r
Hand-helld beta scin  ntillation and           ow proportioonal detectoors (typicallyy 126 cm2) were d/or gas-flo used.
acted Class 1 he minimum ey units wer ation in the s ss 1 structur e necessary n ion.
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.
pen land sur ssification.
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.
was sufficie ted radionuc ent in non-im Static Measu
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.
-impacted an ted to FRS, ed by gener urvey unit. T y unit was tion Superv sideration w olored areas, s where the tion of biased he extent pr ey unit was pon the pro ealth Physic the initial w ements and S building sur easurements phalt-paved n of surface urvey of the face soil, sed different typ 2-16 1 and Class m number of re commensu survey unit.
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.
res that wil number of s rvey units, th Consequen ent to ensure clides are pr mpacted area urement and nd impacted sample loca ating random The location determined visor and/or was given
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
, cracks, low ground has d locations.
actical in ac determined ofessional ju ist during th walk downs Samples rfaces consi s, material sa open land a scans (beta e open land diment and s pes of measu 2 open land f random or urate with th l remain an samples nee he primary c ntly, the nu e with reaso resent in Cl as.
d Sample Lo d open land ations were m pairs of c n of biased m d by the pr the Project to location w point grav s been distur ccordance w d during the udgment of he survey de and the am isted of a co amples and s areas that wi and gamma areas consis surface wate urements and d areas (pav r biased dire he probabilit nd be subjec eded to asses characterizat umber of s onable conf lass 3 areas ocations areas and C primarily ch oordinates t measurement rofessional j Health Phy ns that exh vity drain p rbed. Histo with their cla survey desi the Radiolo esign proces mbient radiat ombination smears. The ill remain an a), static bet sted of gamm er for isotop d samples tha ved and unpa ect measurem ty of the pres cted to FRS ss the latera tion DQO w systematic fidence that and no lice Class 2 struc hosen at ran hat correspo ts and/or sam judgment o ysicist durin hibit measu points, actua orical inform assification.
ign process.
ogical Prote
: s. Consider tion levels i of surface e characteriz nd be subject ta measurem ma scans an pic analysis.
at were utiliz aved) ments sence S, the al and was to static only ensee-ctural ndom.
onded mples of the ng the urable al and mation The The ection ration in the scans zation ted to
: ments, nd the The zed.  


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.
La Cross License T Revision 2.2.2.4.1 Gamma activity.
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.
used for Ludlum M Ludlum M Scanning rate not t was main and, loca 2.2.2.4.2 Scanning 7,100 dpm including Hand-hel used.
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..
Beta scan and with prevented was dete calculate of the sur If not im instrumen evaluatio investiga 2.2.2.4.3 Direct m surfaces typically detectors Direct m acquiring typically designate adjusted 2.2.2.4.4 If applic verify lo se Boiling W Termination n 0 Gamm scans were Sodium io these scans.
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.
Model 44-10 Model 44-10 g was perfor to exceed 0.
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.
ntained with ations of elev Beta S g was per m/100cm2 a g, but not li ld beta scin nning was p h a scanning d scanning a ermined, an d a priori to rvey.
2.2.3. In nstrumenta  ation Selectio on, Use andd Minimum Detectable Concentrattions (MDC          Cs)
mpacted by h nt to identi on. Any ide ation and pot Direct measurement of the build performed
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.
: s.
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
measurements g data over used for su ed investigat as appropria Remo able, remov oose surface Water Reactor Plan ma Surface S performed o dide (NaI) g EnergySol 0 Detector 0 NaI detecto rmed by mo
: 3) analyssis of materiaal samples.
.5 m (20 in) hin 15 cm (6 vated direct l Surface Scan rformed in action level.
Instrumentation and nominal MD      DC values thhat were em mployed durinng characterrization are listed in Table 2-3.
imited to; fl ntillation and performed w g speed of o at the specif nd the scan o ensure that high ambient fy locations entified areas tential decon t Measureme ts were per dings or on using ~10 s were condu a pre-determ urface measu tion level or ate to achiev ovable Surfac vable beta an e contamina r
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
Scans over open la gamma scin utions Techn Sensitivity (
ors to Co-60 oving the de per second.
in) of the s levels were f ns order to Beta scans loors, walls, d/or gas-flo with the dete one detector fied distance nning techni t the MDC f t noise level s of elevate s of elevated ntamination.
ents rformed to n concrete o 00 cm2 or l ucted by pla mined coun urements and r MDC und ve an accepta ce Contamin nd/or alpha ation is less 2-17 and surfaces ntillation det nical Suppor (10) examin 0 and Cs-137 etector in a s The distan urface if po flagged for f locate ar s were perfo
, ceilings, ro ow proportio ctor position r active win e, the detect ique adjuste for scanning s, technician d activity th d contamina detect total or asphalt pa arger sized acing the det nt time. A d generally p er considera able MDC fo nation contaminati s than the to identify tectors (typic rt Document nes the resp 7 when used serpentine p nce between ssible. Aud further inves reas of res ormed over a oofs, asphal onal detecto n maintained ndow per se tion sensitiv ed accordin g was approp ns monitored that require ation were m levels of aved areas.
scintillatio tector near t count time provided det ation. The i or direct mea on or smear applicable locations of cally 2 x 2 t (TSD) RS-onse and sc d for scanning pattern, whil n the detecto dible signals stigation and sidual activ accessible st lt and concr ors (typically d within 1 c econd. If su vity for the a ngly. Scan priate for the d the audibl further inv marked or fla contaminati These me on or gas-fl the surface to of one to t tection level instrument c asurements.
r surveys w action level f residual su
) were typi
-TD-313196 can MDC o g surface soi le advancing or and the su were monit d/or sampling vity above tructural sur rete paved a y 126 cm2) cm of the su urface condi alternate dis nning speed e stated obje e response o estigation a agged for fu ion on struc asurements low proport o be counted two minutes ls well below count times were perform
: l. A smea urface ically 6-006, of the ils.
g at a urface tored;
: g.
the rfaces areas.
were urface itions stance was ective of the and/or urther ctural were tional d and s was w the were med to ar for


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.
La Cross License T Revision removab surfaces.
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.
moderate activity a 2.2.2.4.5 Concrete contamin will rema diamond 1/2-inch w pulverize 2.2.2.4.6 Samples locations scanning defined a split spoo tools.
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.
Subsurfa hand aug survey un 2.2.3. In The radi provide b identified action le and expe static me Concern Commer perform
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.
: 3) analys Instrume in Table 2.2.3.1.
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.
All data character se Boiling W Termination n 0 le activity w A 100 cm e pressure. S as appropriat Concr e core boring nation and th ain and be su bit core dri wide pucks ed and analy Mater of soil, sed s as well as
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.
: g. Surface so as soil below on sampling ace soil was gers. Subsur nit.
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.
nstrumenta ation detect both reliable d for the de evels. Detec ected perform easurements (ROC) at a cially availa the three ba sis of materia ntation and 2-3.
2-19
Calibr loggers, ass rization wer Water Reactor Plan was usually m2 surface a Smears were te.
rete and Asp g and the sa he presence ubjected to F ill. The con s, represen yzed for isoto rial Sampling iment, and s other locatio oil is defined w the top 15 g system or, b sampled by rface soil sam ation Selectio tion and me e operation a ecommission ctor selectio mance in th and scanni MDC of 50%
able portable asic survey m al samples.
nominal MD ration sociated dete re calibrated r
taken at eac area was sa e then analyz phalt Core Sa ampling of of volumet FRS. Core b ncrete samp nting a certa opic content.
g sludge were ons in areas d as the top cm layer in by using han y direct push mpling was on, Use and asurement i and adequate ning of LAC on was based e field. In ng were cap
% of the app e and laborat measuremen DC values th ectors, and a d on an annu 2-18 ch direct me ampled with zed for the p ampling concrete we tric contami bore samplin le produced ain depth in obtained fr s exhibiting 15 cm (6-in n 1 m increm nd trowels, b h sampling s performed a d Minimum nstrumentat e sensitivity t CBWR at le d on detecti all cases, th pable of det plicable actio tory instrum ts: 1) surfac hat were em all other por ual basis us easurement l h a circular presence of g ere used to nation in co ng of concre d by the cori nto the surf rom designed elevated act nch) layer of ments. Surfa bucket auger systems (e.g as necessary Detectable tion for char to detect the evels suffici ion sensitivi he instrumen tecting the a on level.
ments and det ce scanning; mployed durin rtable instrum sing Nationa location on cloth or pa gross beta an assess the d oncrete wall ete was acco ing was typ face. Conc d biased and tivity that w f soil while s ace soil was rs, or other s
: g. GeoProbe y to address t Concentrat racterization e initial suite iently below ity, operatin nts and detec anticipated R tectors were
: 2) static me ng character mentation th al Institute o non-asphalt aper filter, u nd/or gross depth of sur ls and floors omplished us pically sliced crete pucks d random sa were identifie subsurface s collected us suitable sam
) or by m the DQOs fo tions (MDC n was select e of radionuc w the establ ng characteri ctors selecte Radionuclid typically us easurements rization are hat were use of Standards t type using alpha rficial s that sing a d into were ample ed by soil is sing a mpling anual or the Cs) ted to clides lished
: istics, ed for des of sed to s; and listed ed for s and


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:
La Cross License T Revision Technolo addressed 2.2.3.2.
Establishmen E              nt/implementtation of plan  ns, procedurres, and prottocols for thee field opperations.
The recei used for portable character 2.2.4. L Gamma proportio laborator quality p preparati site labor In all ca achieved accepted analytica laborator 2.2.5. Q MARSSI used to quality fo 1576, Mu Regulato through (12). Fu may be achieved The QAP used duri functiona All chara approved audit a
Actions A        to en nsure that thee procedures are understoood and folllowed by thee implementiing sttaff.
Characte prescribe applied contracto se Boiling W Termination n 0 ogy (NIST) t d in the QAP Instru ipt, inspectio characteriza radiologica rization is ad Laboratory I spectroscop onal countin ry in accorda programs of ion and analy ratory under ases, analyti
Documentatio D              on of the datta collected.
: d. The anal methodolog al methods ries used for Quality Assu IM, section demonstrate for sample an ulti-Agency R ory Guide 4.
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:
Normal Op urther, MAR used in add
Personnel quaalifications, experience, and trainingg.
: d.
Execution E            in accordance with approv    ved procedurres.
PP was prep ing the site c al activities, acterization d procedures and surveil rization staf ed, impleme to any app ors.
Proper docum  mentation of survey data and sample analyses.
Water Reactor Plan traceable sou PP.
Selection of appropriate a            instruments i              to t perform thhe surveys.
ument Use an on, issue, co ation was p al instrumen ddressed in th Instrument py was prim ng and liquid ance with ap the contrac ysis of chara the QAPP.
Proper instrum  ment calibraation and daiily functionaal checks.
ical methods lysis of rad gies or othe employed characteriza urance 2.2 discusse e that site c nalysis taken Radiologica
Management M                oversight off characterizzation activitties relative tto the adhereence to prrocedures, protocols, p          and documentaation requireements.
.15, Quality erations to RSSIM and dition to, or pared and im characterizat the DQO pr activities es
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.
: s. The effe llance activ ff and progr ented, and v plicable serv r
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).
urces. The c nd Control ntrol, and ac performed in ntation. T he QAPP.
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
Methods an marily perfor d scintillatio pproved labo cted off-site acterization s s were estab diological co er comparab and the la ation.
es the need f conditions ar n to support al Laboratory y Assurance License Ter MARLAP b r in lieu of, mplemented t tion and FRS rocess, and m ssential to d ective imple
: vities, incl ram self-ass verified wh vices provid 2-19 calibration o ccountability n accordance The issue a nd Sensitivi rmed by th on analysis oratory proce vendor labo samples prov blished to e ontaminants ble methodo aboratory M for a quality re acceptabl t characteriz y Analytical of Radiolo rmination) -
both indicate existing qu to ensure th S process. T measures nec data quality w mentation o luding fiel sessments, a hen deficienc ded by off-of instrument y of portable e with issue and control ities he on-site ra was perform edures. Ener oratories tha vided the sam ensure that used stand ologies. Ta MDC achiev y system to le for unres zation and F l Protocols M ogical Moni
- Effluent St e that a Qua uality system e adequacy The QAPP de cessary to ac were implem of characteri ld walk-do as appropriat cies were i
-site vendor ts used for c e radiologica e and contro l of instru adiological med by an rgySolutions at were used me level of required M dard approve able 2-4 prov ved by the ensure the a stricted rele FRS is discu Manual (MA itoring Prog treams and ality Assura ms to ensur of data bein escribes poli chieve qualit mented and ization was owns by te. Correct identified.
rs, as well characterizati al instrument ol procedure uments used laboratory.
approved ve s ensured tha d for the rec quality as th MDC values ed and gene vides the ty off-site ve adequacy of ase. Labor ssed in NUR ARLAP) (11 grams (Incep the Environ ance Project re data qual ng developed icy, organiza ty data.
performed u verified thr EnergySolu tive actions These mea as on-site ion is tation es for d for Gas endor at the
: ceipt, he on-were erally ypical endor f data ratory REG-
) and eption nment Plan ity is d and
: ation, using rough utions were asures sub-


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.
La Cross License T Revision The Cha quality a and is su follows:
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.
E op A
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.
st D
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.
Details o the proce data acqu requirem P
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.
E P
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.
S P
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
M pr All chara Plan, the 2.3.
S In Octob placing t October character accelerat EnergySo October 9 August 6 documen Characte PN-1640 2015 Fie Radioact character character se Boiling W Termination n 0 aracterization assurance and ubject to the Establishmen perations.
Actions to en taff.
Documentatio of the QA/QC edures and s uisition and ments. The sp ersonnel qua Execution in roper docum election of a roper instrum Management rocedures, p acterization QAPP, all a ummary of ber of 2005, the unit into of 2014, rization of L tion of de olutions in a 9, 2014. T 6, 2015. The nted in two erization Sur 017-001, LA eld Work (14 tive systems rization dat rization has Water Reactor Plan n Survey Pl d quality co QAPP. The nt/implement nsure that the on of the dat C elements s sample plan d recording pecific QA/Q alifications, accordance mentation of appropriate i ment calibra oversight of protocols, an activities w applicable im f Characteri Dairyland p o a SAFSTO Dairyland LACBWR in commission accordance w The schedule e results of th o separate rvey Report CBWR Radi 4).
s that rema a in certain been deferre r
lan was dev ontrol (QA/Q e QA/QC pr tation of plan e procedures ta collected.
specific to ch instructions was guided QC program experience, with approv survey data instruments t ation and dai f characteriz d documenta were conduct mplementing ization Surv performed a OR condition contracted n anticipation ning activiti with EnergyS ed EnergyS he site chara reports, GG for October iological Ch ain at LAC n areas du ed until such 2-20 veloped acco QC) program ogram elem ns, procedur are understo haracterizati
. The chara d and condu m component and training ved procedur and sample to perform th ily functiona zation activit ation require ted in accor g procedures vey Results limited cha
: n. This sur EnergySol n of the deve ies. Char Solutions cha Solutions sit acterization s G-EO-31319 r and Novem haracterizati CBWR affec ue to ambie h time that ra ording to th m for the dec ments applica res, and prot ood and foll ion are prese acterization o ucted in com s for site cha
: g.
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ties relative t ements.
rdance with
, and approv aracterization rvey is docu lutions to elopment of racterization aracterizatio te characteri surveys perf 96-RS-RP-0 mber 2014 F ion Survey R cted the ab ent radiatio adiological o he essential commissioni able to chara tocols for the lowed by the ented in the Q operations an mpliance wi aracterizatio to the adhere the Charact ved sample p n survey of umented in perform a f this LTP an n activities, on procedure ization effo formed by En 01, LACBW Field Work (
Report for J ility to acq on levels.
or physical c elements o ing of LACB acterization a e field e implementi QAPP, as w nd the assoc ith these QA on are as foll ence to terization Su plan instruct the LSE pri Reference 7 a more det nd the anticip
, performed es commence ort conclude nergySolutio WR Radiolo (13) and LC June thru A quire meani In these c conditions w of the BWR are as ing well as ciated A/QC ows:
urvey ions.
ior to
: 7. In tailed pated d by ed on ed on ons is ogical C-RS-ugust ingful
: cases, would


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.
La Cross License T Revision allow the the decom significan by revisio 2.3.1. B During t backgrou acquired backgrou As part o backgrou LACBW Normally be repres site area Supervis appropria results.
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.
were con Concrete is located non-impa approxim unit L40 L401210 samples a The ana backgrou can be at mean Cs 0.135 pC was 0.07 Relevant Station (Z at Zion S Zion to C geograph for distu backgrou within th categorie drainage se Boiling W Termination n 0 e survey of t mmissioning nt additiona on or addend
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.
===Background===
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.
the initial ch und study fo from vario und study is of the 2014 und levels a WR fell within y, backgroun sentative. H was chosen.
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.
or selected a ate for obtain Although th nsidered unaf e samples an d north of th acted survey mately 100 s 12108. Soil 08 were also are provided lysis of the und study fo ttributed to g
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.
-137 concen Ci/g with a m 0 resulting i t to LACBW ZNPS) titled Station (15).
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.
Cs-137 leve hically simila urbed soils a und Cs-137 he expected es of soil in and non-dra Water Reactor Plan hese survey g process, in l characteriz dum as a par Study haracterizati or soils at LA ous location summarized characteriza at LACBWR n nominal ex nd reference However, no
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.
. The Energ an area outs ning backgro he selected s ffected by pa nd direct me he LSE. A y unit L4012 quare meter l samples fro evaluated f d in sections e backgroun or soils. The global fallou ntration of s maximum ob in the upper WR is a study d ZionSolutio This docum ls anticipate ar. The docu as well as u levels for th range of d the non-im ainage, distu r
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
units. Solu ncluding foll zation data i rt of the requ on survey p ACBWR. R ns outside o d in Table 2-ation effort, R. The pur xpected leve areas shoul suitable off gySolutions P side of the L ound measu sample locat ast LACBW asurements sphalt samp 2106. Surfa rs of undistu om non-imp for use as ba 2.3.3 and 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.
nd soil sam e results did ut. For the t surface samp bserved con r range for th y performed ons TSD 13 ment was pr ed from wor ument predic undisturbed he site speci disturbed so mpacted area urbed and un 2-21 tions intends lowing the s is obtained, uired 2 year performed in Reference 7 of the owne
A summary of the gammag        specttroscopy resu  ults for eachh non-impaccted open laand survey uunit is presentedd in Table 2--8.
: 5.
2-23
EnergySolu rpose of the els for soils, d be reasona f-site locatio Project Heal LSE but on rements bas tions were i WR operation were taken ples and dire ace soil samp urbed non-dr pacted survey ackground re
.3.5.3.
mples in 201 d report Cs-1 two backgrou ples taken o ncentration o his data set a for the deco
-004, Exami repared to co rldwide fall cted ranges f soils and is fic backgrou ils in non-d s at LACBW ndisturbed so s to continue submittal of this chapter update of th n October 2 states that a er controlled utions perfor e study was concrete, an ably close to on was ident lth Physicist the licensed ed upon the inside the LA ns.
in Class 3 s ect measurem ples were ac rainage soil y units L401 eference soil 14 compare 137 at levels und studies n or around of 0.268 pCi at a 95% con ommissionin ination of Cs ompare site out. The L for backgrou presented i und studies drainage are WR, the upp oil from the e characteriz this LTP. I r of the LTP he approved 005, Dairyl a series of s d area. Th rmed a limit s to assess i nd asphalt.
o the decomm tified. Cons and the Rad d LACBWR previous ra ACBWR lic survey unit L ments were cquired from within non-12107 and o ls. Analysis ed favorably s slightly ab performed a d the site pro i/g. The st nfidence leve ng of the Zio s-137 Globa soil sample LACBWR an und concentr in Table 2-6 performed a eas. As the per 95th per Zion backgr zation throug In the case w P will be up LTP.
and perform oil samples he result of ted assessme if backgroun missioning s sequently, an diation Prote site that se diological su censed area, L3012101, w also collect m a small ar
-impacted su other areas w s results for y with the bove MDC.
at LACBWR oduced a me tandard devi el of 0.275 p on Nuclear P al Fallout in Cs-137 resu nd Zion site rations of Cs
: 6. The obse at LACBWR ere were va centile level round study ghout where dated med a were f this ent of nd at site to n on-ection emed urvey
, they which ted in rea of urvey within these 2005 This R, the ean of iation Ci/g.
Power Soils ults at es are s-137 erved R fall arious ls for were


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.
La Cross License T Revision considere areas, an 2.3.2. P EnergySo Decomm decommi from the some of t less than prepared 2.3.3. N Based up 163.5 acr impacted contamin operation ISFSI w operation physical for comp for the cl The non-segregate inside of Highway study for within su in coal f ISFSI fac From Oc impacted survey un and the i impacted To supp objective open land by perfor The 2015 primary surveys a se Boiling W Termination n 0 ed appropria d Class 2 an Potential Ra olutions TS issioning (
The resullts of the anaalysis are preesented in Table T      2-9.
issioning of sampling o the theoretic n 2 years, an
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.
. The list of Non-Impacte pon the infor re licensed
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.
: d. The n nation given ns. The det were not imp ns (i.e., with characterist pliance beyo lassification.
2.3.4. Im mpacted Op  pen Land Areas A
-impacted op ed into five f survey uni y 35. This s r soils. The urvey unit L4 from the G-cility, which ctober 2014 d open land nits and wer initial result d as it was d ort this con e of the add d survey uni rming additi 5 characteriz objectives and samplin Water Reactor Plan ate backgro nd 3 open lan dionuclides SD RS-TD-3 (16) establi LACBWR.
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.
of various m cal neutron a n initial suite f potential ra ed Open La rmation com site surroun non-impacte that historic termination pacted by l hin the LSE ics. The are ond the chara pen land are survey unit it L4012108 survey unit non-impacte 4012103. A
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.
-3 station an h has not bee to August areas of th re characteri s of the 201 determined t nclusion, ad itional chara its given an i onal soil sam zation camp of the addi ng to suppor r
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
ound concen nd area surve s of Concern 313196-001, shes the ba Industry gu media from p activation pro e of potentia adionuclides and Areas mpiled in the nding the L d areas ha cal informati that the con licensed ope
), site use, t eas designat acterization a is approxim ts. Non-imp 8 in a veget was formed ed survey un A majority of nd survey un en characteriz 2015, char he site. The ized as such 14 characteri that there is dditional ch acterization initial Class mpling and g aign was de tional chara rt the non-2-22 ntration leve ey units at L n
, Radionuc asis for an uidance was past plant o oducts, nobl al ROC for is listed in T e HSA, a lar LSE and IS ave no rea ion provides ntiguous ope erations was topography, ted as non-im surveys and mately 352,3 pacted open ated area w d during cha nits are show f the surface nit L401210 zed and is no racterization e survey uni h in Referenc ization, thes no reasonab haracterizatio surveys per 3 classificat gamma walk esigned in ac acterization
-impacted c els for the LACBWR.
clides of C initial suite reviewed as operations.
le gases and the decomm Table 2-7.
rge portion o SFSI receive asonable po s no indicatio en land area s based on site dischar mpacted are d sampling p 360 square m n land surve with minimal aracterizatio wn in Figure area in surv 06 complete ot addressed surveys w its were ori ce 13. Base se survey un ble potentia on was perf rformed in 2 tion for re-cl kover survey ccordance w was to per classification evaluation Concern D e of potenti s well as the Based on th radionuclide missioning o of the open ed a classif otential to on of impact as surroundi the locatio rge pathway e not require performed to meters in siz ey unit L40 l ground dis on to facilita 2-1. The G vey unit L40 ely surround d by this LTP were perform iginally clas ed upon a rev nits were rec al for residua formed in 2 2015 was to lassification ys.
with Referenc rform suffic n and to pr of non-imp uring LAC ial ROC fo analytical re he eliminatio es with a hal f LACBWR land areas o fication as contain res t from LACB ing the LSE on(s) of lice ys, and othe ed to be surv o provide a ze. This area 12109 is lo sturbance ea ate a backgr G-3 station re 012105 is cov ds the LACB P.
med in the ssified as Cl view of the classified as al contamina 2015. A m o evaluate ce n as non-imp ce 4. One o cient radiolo rovide reaso pacted CBWR or the esults on of lf-life R was on the non-sidual BWR E and ensed er site veyed basis a was ocated ast of round esides vered BWR non-lass 3 HSA non-ation.
major ertain pacted of the ogical nable


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.
La Cross License T Revision assurance 2015 cha based on During th units L40 logger w was scan Gamma s or gravel Minimum evaluated survey un an Explo were due Thirty-tw toward d shown in instrumen positively surface s These va in section specific b in the gr were very Seventee meter.
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.
concentra derived g average maximum backgrou 137 conc surface s the Hwy Two asp survey un were less identified A summ presented se Boiling W Termination n 0 e that the n aracterization a random d he 2015 cha 012103, L40 with a 2 by 2 nned due to surface scan
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.
: l. Alarm se m Detectabl d during the nit L401210 oranium GR-e to the prese wo surface s discolored ar n Figure 2-5 nt MDC in y identified soil samples alues are wit n 2.3.1. On background rounds east y close at 0.
All surfaace and subsurface com    mposite samp  ples were annalyzed afteer drying thhe sample m   media.
en subsurfac Of the 17 ations greate gamma-emit Cs-137 conc m observed und range fo centrations th soil backgrou 35/Railroad phalt sample nits. The asp s than the M d by gamma ary of the g d in Table 2-Water Reactor Plan non-impacted n survey foc esign to ensu aracterizatio 012105, L40 2 NaI detec inaccessibili nning focused et-points for e Count Ra e performan 7 and one in
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.
-135. The ence of natur soil samples eas or areas
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.
: 5. Cs-137 26 of the 32 by gamma s was 0.131 hin the expe ly one Cs-13 data set. Th of Highway 135 pCi/g an e soil sampl 7 subsurface er than the tting radionu centration ob concentrati r Cs-137 as hat exceede und. This s d Right of W es were coll phalt surface MDC of 1,93 spectroscop gamma spect
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..
-8.
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.
r d survey uni cused primar ure an unbia n survey, a 012106 and ctor. In surv ity from the d on undistu r the instrum ate (MDCR) nce of the g n survey unit results of th ral backgrou s were colle where the g was positiv 2 samples.
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
spectroscopy pCi/g with ected backgr 37 result exc his sample w y 35. The m nd 0.131 pC les were tak e soil samp instrument uclides were bserved in t ion of 0.40 discussed in d the maxim sample was t Way Grounds lected from e was first sc 38 dpm/100c py in any of t troscopy resu 2-23 its do not c rily on soils ased survey.
minimum o L4012108 vey unit L40 e presence o urbed soils w ment were s
) of the ins gamma scan t L4012108.
he investiga und activity.
ected from ground had b vely identif No other po
: y. The avera a maximum round range ceeded the m was the maxi mean of the n i/g, respectiv ken at random ples taken, MDC in ei e positively i the subsurfa 09 pCi/g. Th n section 2.3 mum Cs-137 the maximu random loc canned with cm2. No pla the asphalt s ults for each contain plant and asphalt of 1% of the was scanned 012107, less f tall, thick with minimal set at the ob strument. A n, one in su All scan al ation indicat non-impacte been disturbe fied in conc otential plan age Cs-137 c m observed c for Cs-137 maxium resu imum 0.463 non-impacte vely.
mly selected Cs-137 w ght samples identified by ace soil sam hese value 3.1. Only on 7 concentrati um 0.409 pC cations in p h a beta-gamm ant derived r samples.
h non-impac t-derived ra
: t. The samp e surface so d with a Mo s than 1% of vegetation a l vegetation bserved back A total of f urvey unit L larms were in ted the elev ed areas at ed. The sam centrations nt-derived ra concentratio concentration surface sam ult of 0.268 pCi/g value ed and site-s d locations t was positive
: s. No other y gamma sp mples was 0.
es are with ne subsurfac ion found in Ci/g value th paved areas mma detector radionuclide cted open la adioactivity.
ple locations oil area in su odel 2350-1 f the surface and steep te or disturbed kground plu four alarms L4012106, tw nvestigated u vated scan re locations b mple location greater than adionuclides n observed i n of 0.463 p mples as discu pCi/g in the e and was lo specific data to a depth o ely identifie r potential p pectroscopy.
087 pCi/g w hin the exp e sample ha n the site-spe at was locat in non-imp
. All scan re s were posit and survey u The were urvey data e area rrain.
d soils us the were wo in using esults biased ns are n the were in the pCi/g.
ussed e site-ocated a sets of one ed in plant-The with a pected d Cs-ecific ted in pacted esults tively unit is


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.
La Cross License T Revision A coal as samples The resul The lab concentra also posi concentra considere of the pl radionuc positive ratios ar compared higher th operation consisten the spora derived r In survey gamma s area to d approxim uranium readings 2.3.4. Im The HSA operation been clas been iden into two north of Highway three Cla The char prepared employed radionuc of suffici surface a obtained Survey contamin se Boiling W Termination n 0 sh sample fr were sent to lts of the ana boratory an ations excee tively detect ations of the ed to very li lant-derived lide mixtur results for C re 118 and d to the site han expected nal history, t nt with natur adic positive radionuclide y unit L4012 spectroscopy determine if mately 7,000 and thorium conducted d mpacted Op A identified ns. The app ssified as C ntified as i Class 2 surv the LSE, th y 35 and the ass 3 survey racterization for each s d to determ lide concent ient quantity and subsurf from below techniques nation identi Water Reactor Plan rom survey u o Test Ame alysis are pre nalysis spor eding the MD ted but at lev e positively i ikely be the radionuclid re fractions Cs-137, Sr-16, respect e-specific mi d by factors the radionuc ral backgrou analytical r s in these su 2108, a repr
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-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.
: y. In additio f there is a 0 to 8,000 cp m series nuc during the w pen Land A d the open proximate are Class 1. An impacted b vey units. T he transmiss e haul road u units combin of the impac survey unit ine the later trations in th y and quality face soils in w the structur were empl ified and th r
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.
unit L40121 erica Labora esented in T radically id DC, includin vels that are identified rad result of cou des. This c
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.
. For exam 90 and Fe-5 tively. Wh ixture fracti s of 4,800 a lide ratios, a und and com esults are ve urvey units.
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.
resentative s on, gamma s significant pm). The a clides with alkover surv Areas land area ea is 1.5 acr approximat y reactor op Three impact sion switchy used to tran ned is appro cted open la in accorda ral and vert he soil. Char y to quantify n each open res due to int loyed to de he radionucl 2-24 05, six surfa atories for g Table 2-9.
a          Th he results off the analysiss are presentted in Table 2-11.
dentified se ng H-3, C-14 consistent w dionuclides w unting uncer conclusion w mple, samp
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.
: 55. Howev hen the rati ons in Chap and 10,700, and primarily mprise 88% o ery unlikely sample of th scan reading difference analysis of t no plant de vey averaged inside the res. All ope tely 3.46 acr perations. T ted Class 3 s yard and the nsport dry fu oximately 16 and areas beg ance with R ical extent o racterization the potentia n land surve terferences a etermine th lide concent face soil sam gamma spect everal plan 4, Fe-55, Ni with natural b were close t rtainty as op was supporte le L301210 ver, the Sr-9 ios from L3 pter 6, Table respectivel y the concen of the site-sp to represent he rail road gs were take from site b the railroad erived radio d 7,000-8,50 fenced LSE en land surve re area that This open la survey units e area encom uel casks to 6.5 acres.
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.
gan in Octob Reference 4 of any cont n inspections al volumetric ey unit. Li and inaccess he lateral a trations in t mples and fiv troscopy and nt-derived r i-63, and Sr-background to the detecti pposed to th ed by a rev 05-CR-GS-0 90/Cs-137 an 3012105-CR e 6-3, it is s ly. In conc ntrations of C pecific radio t the actual p bed gravel en of the rail background bed gravel onuclides. T 00 cpm.
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.
E as impac ey units insi surrounds t and area has were design mpassing th the ISFSI.
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.
ber 2014. A
Alarm seet-points for the instrumment were sett at the obseerved backgrround plus tthe MDCR oof the instrumen  nt. No scan alarms weree observed.
: 4. Survey amination id s and surveys c contaminat imited soil ibility.
2-26
and vertical the soil. A ve subsurfac d HTD anal radionuclide
-90. Cs-137
. In all case ion limits an e actual pres view of exp 002-SS indi nd Fe-55/Cs R-GS-002-SS een that the clusion, base Cs-137 whic onuclide mix presence of p was analyze l road bed g (which aver indicated na The gamma cted by re ide the LSE the LSE has been segre nated for the he site acces The area o A sample plan techniques dentified an s were perfo tion of acces information l extent of A combinatio e soil lyses.
es at 7 was es, the nd are sence pected icates s-137 S are ey are ed on ch are
: xture, plant-ed by gravel raged atural scan eactor have s also gated e area ss off of the n was were nd the ormed ssible n was f any on of


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.
La Cross License T Revision random a survey p professio Protectio radioactiv spill loca survey lo not requ locations radiologi A surface surface s or surfac were take intervals Each sur site radio necessary All surfa Several s full isoto survey un 2.3.4.1.
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.
There are The Clas area in th Reactor radioactiv areas, pre Twenty-t measurab locations taken in taken, C samples 13 sampl identified the surf 0.287 pC samples w Seventy-one mete se Boiling W Termination n 0 and biased s ackage. The onal judgme on Supervis vity, depres ations, or ar ocations was uired for soi s were selec ical contamin e soil sample oil samples ce scans indi en from 0.15 rface soil, co ological lab y to achieve ace and sub soil samples opic analysis nit per Refe Class e four (4) op ss 1 open lan he Class 1 op Building, th vely contam evented the a two (22) sur ble radioact s, or areas w Class 1 open Co-60 was p and Cs-137 les. No oth d by gamma face soil sa Ci/g. The a was 0.096 p nine (79) su er, two (2) lo Water Reactor Plan urvey locati e locations o ent of the E or. Consi sions, disco reas where t s also determ ils in an op cted on asp nation.
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.
e was taken were acquir icated elevat 5 cm to dept omposite sub oratory by e an isotopic surface com were selecte s (HTD radi erence 4.
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.
1 Open Lan pen land sur nd survey un pen land sur he Turbine minated build ability to per rface soil sam tivity, disco where the gro n land surve positively id 7 was posit her potentia spectroscop amples was verage Cs-1 Ci/g with a m ubsurface so ocations bias r
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.
ions were es of biased me EnergySoluti deration wa lored areas, the ground h mined by are pen land are phalt in Cla at each sele red at severa ted activity.
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.
ths ranging f bsurface soil gamma-spec c MDC equa mposite samp ed at random ionuclides).
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.
nd Areas rvey units cl nits are show rvey units is Building, th ding and sys rform surfac mples were lored areas, ound had be ey units are s dentified in tively ident al plant-deriv py. The aver s 0.058 pCi/
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
137 concent maximum ob il samples w sed to areas o 2-25 stablished in easurements ions Project as given to low point g had been di ea classificat eas designat ass 1 survey cted biased a al random lo Depending from 1 to 3 m l sample or ctroscopy.
al to or less ples were an m and were s Duplicate lassified as wn in Figure obstructed b he WTB and stems, as we ce scanning d taken at loc
, buried pip een disturbed shown in Fig concentrati tified in con ved gamma rage Co-60 c
/g with a tration obser bserved conc were taken a on the south each survey s and/or sam Health Phy o locations gravity drain isturbed. Th tion. Rando ated as Clas y units whe and random cations or if on the loca m below gra asphalt sam Analysis co s than 0.10 p nalyzed afte shipped to T samples and Class 1 at L 2-1. A sign by the prese d the LSA ell as stored due to high b cations biase pe locations
: d. The loca gure 2-6. O ions greater ncentrations a-emitting ra concentratio maximum rved in the centration o at 10 surface and west sid y unit in acc mples were d ysicist and that exhib n areas, actu he number m-based me ss 1. Rando ere there wa
-based surve f surface soi ation, subsur ade and com mple was ana ount times w pCi/g for Cs er drying th Test America d concrete w LACBWR to nificant porti ence of build Building.
radioactive background.
ed toward sit s, actual an ations of surf Of the 22 sur r than the M s greater th adionuclides on observed observed c analysis of f 1.07 pCi/g e soil locatio de of the WG cordance wit determined b the Radiolo bited measu ual and pote of random-b easurements om measure as no histor ey location.
l sample ana face soil sam mposited ove alyzed by th were adjuste s-137 and C he sample m a Laboratorie were collecte otaling 8,443 ion of the su dings, namel The presen material in tes that exhi nd potential face soil sam face soil sam MDC in tw han the MD s were posit in the analy concentratio f the surface
: g.
ons to a dep GTV and fiv th the by the ogical urable ential based were ement ry of Sub-alysis mples r 1 m he on-ed as Co-60.
media.
es for ed by 3 m2.
urface ly the ce of these ibited spill mples mples wo (2)
DC in tively sis of on of e soil pth of ve (5)


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.
La Cross License T Revision locations The sam evaluate Building samples 15 sampl identified of the su 0.161 pC areas is foundatio decommi Ten sam asphalt w this surv results ra measurem identified 0.057 pC A summ presented Nine sur samples gamma s In additi detected One sedi unit L10 and HTD 0.136 pC 2.3.4.2.
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.
The imp immediat two surv LACBW these two Approxim 2350-1 d Alarm se instrumen se Boiling W Termination n 0 s that access mples at the t the subsurfa were taken taken, Cs-1 les. No oth d by gamma ubsurface so Ci/g. The ass not current ons and surr issioning pro mples were ta was taken fro vey unit. Th anging from ment of 3,09 d in concen Ci/g.
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.
ary of the fi d in Table 2-rface soil sa taken from spectroscopy on to detect at concentra iment sampl 10103. This D analyses.
No scan alarms weree observed in  n these surveey units.
Ci/g.
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.
Class acted Class te area surro ey units. Th WR Crib Hou o survey unit mately 1% o data logger w et-points for nt. No scan Water Reactor Plan ed the soils two WGTV ace soils alon and compo 137 was pos her potentia a spectroscop oil samples sessment of tly complete rounding bu ocess, when aken of asp om the same he asphalt s the instrume 95 dpm/100 ntrations gre indings of th
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.
-10.
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 with a maximum  m observed concentratio c          on of 0.409 pCi/g.
amples, 11 s Class 1 open y and HTD a ting Co-60 ations greate le was taken s sample wa Co-60 and 2 Open Lan 2 open lan ounding the hese are sho use, the G-3 ts.
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.
of the surfac with a 2 by the instrum alarms were r
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.
under the T V locations w ngside and u sited at dept sitively iden al plant-deriv py. The ave was 0.055 p potential su
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.
: e. Soil in uried structu access will b phalt from p e location se surface was ent MDC of cm2. Of th eater than he survey fo subsurface s n land surve analyses. Th and Cs-137 r than the in n from the s as also sent t C-137 were nd Areas nd areas tota LSE. The C own in Figur 3 Crib Hous ce soil area i y 2 NaI de ment were set e observed.
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
2-26 urbine Build were acquire underneath th ths of 10, 15 ntified in co ved gamma erage Cs-13 pCi/g with ubsurface soi difficult to ures and pip be more read paved areas lected for th first scanne f 2,771 dpm/
he 10 asphal MDC in on or each indiv soil samples ey units wer he results of
, H-3, C-14 nstrument MD sanitary solid to Test Amer e detected in al approxim Class 2 impa re 2-1. The se and the L in survey un etector. Thi t at the obse ding through ed to a dept he vault. Th 5 and 20 fee oncentration a-emitting ra 7 concentrat a maximum il contamina o access are ping has bee dily availabl in Class 1 s he surface an ed with beta
/100cm2 to a lt samples t nly one sam vidual Class s, one concr re sent to Te f the analysis 4, Fe-55 and DC.
ds tank that rica Laborat n this sampl mately 13,99 acted open l LACBWR LACBWR w nit L201110 is area inclu erved backgr h angled Geo th of five m he samples u et. Of the 7 ns greater th adionuclides tion observe m observed ation in the C eas such as en deferred le.
survey unit nd subsurfac a-gamma de a maximum taken, Cs-13 mple at a s 1 open land rete sample est America s are present d Ni-63 wer is located i tory for gam e, both at a 6 m2 and ar and area wa Administrat warehouses a 1 was scann uded asphalt round plus t oprobe samp meters in ord under the Tu 79 subsurface han the MD s were posit ed in the ana concentratio Class 1 open s under bui until later i L1010104.
ce soil sampl etector with of observed 37 was posit concentratio d survey un and two as a Laboratorie ted in Table re also posit in Class 1 su mma spectros concentrati re located in as segregated tion Building are all locat ned with a M t paved surf the MDCR o pling.
der to urbine e soil DC in tively alysis on of n land ilding n the The les in scan d scan tively on of nit are sphalt es for 2-11.
tively urvey scopy on of n the d into g, the ted in Model faces.
of the


La Crossse Boiling Water W      Reactorr License Termination T               Plan Revision n0 presented d in Table 2-15.
La Cross License T Revision Twenty-t measurab locations taken in taken, Cs other pot The aver 0.077 pC Twenty-t and three resides in Of the 2 greater th than MD identified of 0.112 samples assessme currently surround process, w Twelve s selected results r 2,748 dpm concentra concentra observed A summ presented Three sur samples Administ HTD ana Co-60 a concentra HTD rad 2.3.4.3.
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.
The impa land area Figure 2-site, the t se Boiling W Termination n 0 three surfac ble radioact s, or areas w Class 2 open s-137 was p tential plant rage Cs-137 Ci/g with a m three subsur e locations b n survey uni 23 subsurfac han MDC in DC in four d by gamma pCi/g. The was 0.043 ent of poten y complete.
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.
ding buried s when access samples were randomly.
A full lisst of G-3 struuctures that have been designated d           ass non-impaacted is provvided in Tabble 2-2.
ranging fro m/100cm2.
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.
ations great ation observ d concentrati ary of the fi d in Table 2-rface soil sa taken from tration Build alyses. The and Cs-137, ations greate dionuclides e Class acted Class 3 a was segre
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.
-1. The Cla transmission Water Reactor Plan e soil samp tivity, disco where the gro n land surve positively ide t-derived rad 7 concentrat maximum obs face soil sam biased to are it L2011101 ce soil samp n one sample samples. N spectroscop average Cs-pCi/g with ntial subsurf Soil in dif structures an s will be mor e taken of as The asphalt om the ins Of the 12 ter than the ved in the an on of 0.055 indings of th
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:
-12.
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.
amples, five m an acces ding were se results of th H-3, C-14 er than MD exceeding M 3 Open Lan 3 open land egated into ass 3 impacte n switchyard r
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
ples were tak lored areas, ound had be ey units are s entified at co dionuclides tion observe served conce mples were t eas alongsid
MDC off 2,816 dpm//100cm . The       T results of   o the direcct beta-gamm   ma and alphha measurem    ments 2
: 1. The biase ples taken, e and Cs-13 No other po py. The sing
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.
-137 concent h a maximu face soil con fficult to ac nd piping ha re readily av sphalt from p t surface wa strument M 2 asphalt sa e instrumen nalysis of the pCi/g.
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
he survey fo subsurface s ssible storm ent to Test he analysis a 4, Fe-55 an DC. As disc MDC are likel nd Areas areas total a three surve ed open land for the LAC 2-27 ken at locat
, buried pip een disturbed shown in Fig oncentration were positiv ed in the an entration of taken at 14 r de and under ed samples w Co-60 was 7 was positi otential plan gle sample w tration obser um observe ntamination cess areas s as been defe vailable.
paved areas s first scann MDC of 2, mples taken nt MDC in e asphalt sam or each indiv soil samples, m sewer ba America La are presented nd Cm-243/
cussed in se ly to be false approximatel ey units. T d survey un CBWR and G tions biased pe locations
: d. The loca gure 2-7. O ns greater th vely identifi nalysis of th 0.200 pCi/g random loca rneath the S were acquire positively ively identif nt-derived ra with detectab rved in the a d concentra n in the Cla such as und erred until l in Class 2 su ned with bet
,529 dpm/10 n, Cs-137 w three samp mples was 0 vidual Class
, three aspha asin manhol aboratories f d in Table 2
/244 were ection 2.3.3 e positives.
ly 66,765m2 The Class 3 nits include t G-3 facilitie d toward sit s, actual an ations of surf Of the 23 sur han MDC in ied by gamm he surface s
: g.
ations to a de Storm Sewer ed to a dept identified a fied at conce adionuclides ble Co-60 ha analysis of th ation of 0.0 ass 2 open l der building ater in the d urvey units.
ta-gamma de 00cm2 to a was positive ples. The 0.049 pCi/g s 2 open land alt samples a le located for gamma s
-13. In add also positiv for non-imp
: 2. The Class survey uni the north en s, the LACB es that exhi nd potential face soil sam face soil sam 14 samples ma spectrosc soil samples epth of one m r Water pipe th of five m at concentra entrations gr s were posit ad a concentr he subsurfac 088 pCi/g.
land areas i foundations decommissio The asphal etector with a maximum ely identifie average Cs with a maxi d survey un and two sedi in front of spectroscopy dition to dete vely detecte pacted areas 3 impacted its are show nd of the lice BWR plant a ibited spill mples mples
. No copy.
s was meter e that meters.
ations reater tively ration e soil The s not s and oning lt was h scan m of ed in s-137 imum nit are iment f the y and ecting ed at s, the open wn in ensed access


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.
La Cross License T Revision and right was deem LACBW Crib Hou facility d were dee These ar Solutions A minim scanned was excl focused o points fo No scan Thirty-tw where th open lan was posi plant-der The aver 0.131 pC Seventee meter.
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.
concentra radionuc concentra maximum Two sam selected results w were pos A summ presented As part o of concre Crib Hou Administ survey un Three co L301210 three sur Laborato se Boiling W Termination n 0 t-of-way are med impacte WR Administ use). The tr during operat emed as imp reas were c s maintains t mum of 1%
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.
with a Mod luded from on undisturb r the instrum alarms were wo surface so he ground ha d survey un tively identi rived gamma rage Cs-137 Ci/g with a m en subsurfac Of the 17 ations grea lides were ation observ m observed c mples were t randomly.
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.
were less tha sitively ident ary of the fi d in Table 2-of the charac ete located i use. In addi tration Build nit L301210 oncrete samp 01, the two se rface soil s ories for gam Water Reactor Plan a and the ha ed by LACB tration Build ransmission tions. The p pacted by th onservativel that classifyi of the surf el 2350-1 da gamma sur bed soils wi ment were se e observed in oil samples ad been dist nits are show ified in conc a-emitting ra 7 concentrat maximum obs e soil sampl 7 subsurface ater than M positively ved in the a concentratio aken of asph The asphalt an instrumen tified by gam indings of th
After com mmodity rem  moval is com  mplete, the structures thaat will remaiin at license terminationn, i.e.,
-14.
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.
cterization of in the north ition, a sam ding and tw
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.
: 9. These sam ples from su ediment sam samples and mma spectr r
2-30
aul road to th BWR due to ding and the yard was d plant access he transit of ly classified ing these are face soil are ata logger w rface scanni ith minimal et at the obse n these surve were taken turbed. The wn in Figure centrations g adionuclides tion observe served conce les were tak e soil samp MDC in ei identified analysis of th on of 0.409 p halt from pa surface wa nt MDC of 1 mma spectro he survey fo f survey unit h section of mple was take wo sediment mples were urvey unit L3 mples taken f d two subs roscopy and 2-28 he ISFSI fac o the presen presence of deemed as im area, Highw f packaged r d as impacte eas as non-im ea in survey with a 2 by ing for safe vegetation o erved backgr ey units.
at locations e locations o e 2-8. Of th greater than s were positi ed in the an entration of ken at random ples taken, ight samples by gamma he subsurfac pCi/g.
aved areas in s first scann 1,938 dpm/1 scopy in any or each indiv t L3012101, the survey u en from a sa t samples w sent off-site 3012101, th from the stor surface soil d HTD anal cility. The n nce of a sep f concrete fr mpacted as i way 35 right radioactive m ed. Howev mpacted wou y units L30 2 NaI dete ety reasons.
or disturbed round plus t biased tow of surface s he 32 surface MDC in 26 ively identif nalysis of th 0.463 pCi/g mly selected Cs-137 w
: s. No oth spectrosco ce soil samp n Class 3 su ned with bet 100cm2. No y of these sam vidual Class
, samples we unit that ori anitary tank were taken fr e for isotopic he sanitary ta rm sewer ba samples w lyses. The north end of ptic system from impacte it was part o t-of way and material thro ver, it shou uld have bee 012101 and ector. Surve Gamma d soils or gra the MDCR o ard discolor oil samples e soil sampl samples. N fied by gamm he surface s
: g.
d locations t was positive ther potenti opy. The ples was 0.0 urvey units.
ta-gamma de o plant deriv amples.
s 3 open land ere taken fro iginated from k that service from a storm c analysis.
ank sample asin in survey were sent t results of f the license that service ed structures of the LACB d ISFSI haul ough these a ld be noted en appropriat L3012109 ey unit L301 surface scan avel. Alarm of the instrum red areas or taken in Cl les taken, Cs No other pote ma spectrosc soil samples to a depth o ely identifie ial plant-de average Cs 087 pCi/g w The asphalt etector. All ved radionuc d survey un om several p m the LACB es the LACB m sewer bas from survey y unit L3012 to Test Am the analysi d site es the s (the BWR l road areas.
d that te.
were 12102 nning m set-ment.
areas lass 3 s-137 ential copy.
s was of one ed in erived s-137 with a t was l scan clides nit are pieces BWR BWR sin in y unit
: 2109, merica is are


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.
La Cross License T Revision presented derived R and Ni-6 exceedin consisten 2.3.5. N Based up associate indicated A full lis
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.
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.
The prim informati operation from the character The resu conducte traffic in The G-3 incidents results of A scan su gamma d using an was also gross bet MDC of identified gross alp contamin samples.
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.
derived 0.061 pC that the material Direct an traffic ar Model 23 areas of i ranged f exceeded se Boiling W Termination n 0 d in Table 2 ROC at resid
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.
: 63. As dis ng MDC are nt with natur Non-Impacte pon the inf ed with the G d that there w st of G-3 stru mary basis f ion documen ns. Additio e LACBWR rization of t ults are prov ed during the the major st station res s of radioact f the charact urvey was p detector. In alpha/beta-g taken at the ta-gamma a f 2,816 dpm/
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.
d gross beta-pha activity nation was i The roof m ROC that w Ci/g. Based elevated dir on the roof.
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
nd removabl reas of the 360 instrume interest were from 2,540 d the MDC d Water Reactor Plan 2-15. The dual concent scussed in s likely to be ral backgroun ed Structur formation co G-3 Coal Pla was no reaso uctures that for the non nted in the H nally, the p R Stack du the LACBW vided in Re e 2015 chara tation buildin sides in non tive contam erization sur performed of addition, six gamma prop location of ctivity rangi
/100cm2. T
-gamma acti y ranging f dentified at material itse was positive on the fact t rect alpha m le contamin G-3 Coal P ent with 43-e scanned, in dpm/100cm during the co r
analysis of trations grea section 2.3.3 false positiv nd.
es ompiled in ant may be c onable poten have been d n-impacted HSA that the potential for uring opera WR Administ eference 13 acterization ngs were sur n-impacted s mination of s rveys perform f the mid-lev x (6) locatio portional dete each direct m ing from 2,3 The results o ivity ranging from 142 dp concentratio elf was samp ely identifie that no other measurements ation survey Plant. Scan
-93 detector.
ncluding floo m2 to 2,617 ourse of this 2-29 f these samp ater than the 3 for non-im ves. Cs-137 the HSA, S classified as ntial for resi designated as classificatio e G-3 structu windborne ations to s tration Build
. Addition campaign w rveyed.
survey unit soils, asphal med in the G vel roof of th ons were sele ector. A sm measuremen 302 dpm/10 of the direc g from 1,603 pm/100cm2 ons greater t pled on Jun ed by gamm r plant deriv s were due ys were perf n measureme
. Approxim ors and lowe 7 dpm/100cm s survey. Te ples positive e instrument mpacted are was also po Solutions co non-impac dual contam s non-impa on for the G ures were no migration o structure roo ding roof an nal surveys where the su L4012103.
lt or concre G-3 station a he G-3 Coal ected at rand mear sample nt. The resu 0cm2 to 2,8 ct beta-gamm 3 dpm/100cm to 258 dpm than MDC b ne 30, 2015.
ma spectros ved ROC wa most likely formed of re ents were p mately 5% of er wall surfa m2. No o en (10) locat ely identifie MDC, inclu eas, the HT ositively dete oncluded th cted. Histo mination from acted is prov G-3 station ot used for L of airborne ofs was ev nd the G-3 of the G-3 urfaces subje There are ete in this su are summariz l Plant build dom for dire for removab ults of the be 816 dpm/100 ma and alph m2 to 2,072 m/100cm2.
by the analy Cs-137 wa scopy at a as detected, to the pres epresentativ performed us f the concret aces. The av observed sca tions were ch ed several p uding H-3, F TD radionuc ected but at l hat the struc orical inform m site operat vided in Tab structures i LACBWR-re effluent rele valuated by Coal Plant structures ected to high e no docum urvey unit.
zed as follow ding using a ect measurem ble contamin eta scan iden 0cm2 with a ha measurem dpm/100cm No remov ysis of the s as the only concentratio it was concl sence of coa ve high perso sing the Lu te surfaces i verage scan M an measure hosen at ran plant-Fe-55 clides levels ctures mation tions.
ble 2-is the elated eased y the roof.
were h foot ented The ws:
beta-ments nation ntified scan ments m2 and vable smear plant on of luded al ash onnel udlum in the MDC ement
: ndom,  


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.
La Cross License T Revision primarily measurem 875 dpm greater th 2.3.6. Im The deco impacted In additio accepted remain a Reactor B remainin and floo Reactor/G Turbine surfaces segregate radioactiv systems o Radiolog complian radiologi areas.
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
disassem remediat demolitio waste.
observed d reading of 72 7 dpm/100ccm .
After com 3 feet be radioactiv use criter 2.3.6.1.
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
Characte consisted walls an (primaril taken fro 621 foot the 633 f samples w Piping Tu se Boiling W Termination n 0 y from the ments for g
from lesss than MDC   C of 113 dpmm/100cm to   o a maximum    m observed reading of 1152 dpm/1000cm2.
/100cm2 for han MDC by mpacted Str ommissionin d buildings, s on, all system elevation fo and be subje Building tha ng reinforced ors of the Generator P sump and th above the ed by waste ve waste.
Direct beeta-gamma measurement m            ts taken on the t floor draain openingss ranged from m less than M MDC 2
or structures gical surveys nce with 10 ical conditio The radiolo mbly and rem ion has ade on, the impa mmodity rem elow grade, vity and the ria.
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.
Basem rization of d primarily o d floors of ly the Piping om the 615 elevation in foot elevatio were collect unnel. The l Water Reactor Plan main lobby gross activit beta-gamm y the analysi ructures an ng approach structures, sy ms and expo or grade at L ected to STS at will be exp d concrete w WGTV, an lant baseme he Turbine 636 foot ele classificatio No extensi s that will be s of the inter 0 CFR 20 re ons for the im ogical infor moval of syst equately red acted structu moval is com
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.
, will be r e extent of a ment Structu the structur of the acquis the Reactor g Tunnels).
e           T The informattion containeed in this seection was deriived directly  y from Haley & Aldriich, Hydroggeological C      Conceptual SSite Model (17).
foot elevati n the Reactor on concrete f ted, six (6) in locations wh r
Haley & Aldrich, Hyydrogeologiccal Investiga    ation Reportt for the LaCCrosse Boilinng Water Reeactor (18) suppplements thee preliminary y findings in n Reference 117.
y area and y was less
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.
: a. No remov s of the sme nd Systems h for LACB ystems and c osed metal b LACBWR is S are the rem posed by the walls floors o nd the rem ent, the one pit. Conseq evation will on and dispo ive characte e removed pr riors of struc equirements mplementati rmation from tems and the duced radiol ures will be mplete, the s re-surveyed additional re ures Below 6 ral surfaces ition and rad r Building, In June and on concrete r Building, th floor of the P n the Reacto here the core 2-30 the mainte than the M vable contam ar samples.
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.
BWR requir components below 3 feet the 639 foo maining rein e removal of of the WTB, mainder of foot thick p quently, all l be remedi osed of as c erization wa rior to the pe tures at LAC regarding on of contro m these su e demolition logical cond demolished tructures tha to determi emediation r 36 Foot Elev of basemen diological an WTB and July of 2015 floor and t he 630 foot Piping Tunn or Building, e samples we enance area.
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.
MDC of 74 mination wa res the dem to a depth o below grad ot elevation.
2-32
nforced conc f the interior the remaini the Piping portion of th systems and iated, disass clean demoli as or will b erformance o CBWR are r the posting ols for the pr urveys will of impacted ditions to le d, packaged at will remai ine the con required, if a vation nts that wil nalysis of co the balance 5, a series o the concrete elevation co nels. A total three (3) in ere taken are
. The resu dpm/100cm as identified molition and of at least 3 de will also b The only st crete walls a r concrete an ing reinforce g and Vent he Chimney d componen sembled and ition debris, be performe of FRS.
routinely per g of areas rotection of provide th d structures a evels suitabl and properl in at license ncentrations any, to meet ll remain in oncrete core e of the bas f concrete co e floor and oncrete floor l of twelve (
the WTB an e shown in F ults of all d m2 for alpha at concentra d removal o feet below g be removed.
tructures tha and floors o nd steel line ed concrete tilation Tun y Foundation nts and struc d/or demoli clean salva ed of equipm rformed to en and to ide f workers in he basis for at the site. W le for contr ly disposed termination of the res t the unrestr n the end-s samples from sement struc ore samples east wall o r of the WTB
: 12) concrete nd three (3) i Figures 2-9.
direct a and ations of all grade.
The at will of the er, the walls
: nnels, n, the ctural
: ished, age or
: ment, nsure entify these r the When rolled of as n, i.e.,
sidual ricted state m the ctures were n the B and e core in the  


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.
La Cross License T Revision The loca condition volumetr elevated wall sur discolora that exh condition there was radionuc The conc Test Ame ROC. In Reactor B and #002 concrete analysis positively 59, Tc-99 concrete 2.3.6.2.
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.
A concre Turbine contamin in the T Analysis 0.106 pC 2.3.6.3.
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.
As stated subjected graded su As repor radioactiv building located i Administ proximity laborator Characte beta-gam gross bet se Boiling W Termination n 0 ations selecte n or observ ric contamin observed co faces were ation or stan hibited the h n for concre s sufficient s lide fraction crete pucks r erica Labora n addition, Building sam 2 were also cores is pr of the conc y detected at 9, Pu-238, P core sample Turbin ete core was Building T nation event Turbine Buil of this sam Ci/g and H-3 LACB d previously d to FRS. In urvey approa rted in the H ve spills or has primaril in the build tration Build y to the LSE ry.
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..
rization surv mma/alpha a ta-gamma/al Water Reactor Plan ed for concr ved radiolog ation of the ontact dose r used to id nding water.
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.
highest pot ete in each s source term ns of gamma representing atory for gam the concrete mple locatio o sent for is resented in rete core sa t concentrati Pu-239/240, es is presente ne Building s obtained as Tunnel to cited in the lding and t mple indicate at 1.71 pCi/
2-33
BWR Admin y, the LACB nstead, these ach in accord HSA, there w radioactive ly been used ding that sup ding was in E, occupancy veys of the ctivity of in lpha activity r
rete core sam gical measu concrete. W rates or coun dentify poten The goal w ential of re survey unit.
in the cores emitters as w g the first 1/2 mma spectro e pucks rep ns #001, #0 sotopic analy Table 2-16.
amples inclu ions greater Pu-241, Am ed in Referen Tunnel s part of the attempt to HSA pertain the potential ed detectable
/g.
nistration Bu BWR Admin e two structu dance with M was no past contaminati d for office sp pported both nitially class y by LACBW LACBWR nterior floor were also p 2-31 mpling were urements in When possibl nt rates. In a ntial locatio was to ident epresenting This judg to achieve t well as HTD inch of conc oscopy and H presenting th 03, #005 an ysis. A sum Significan ude Ni-63, H than their re m-241 and A nce 16.
e 2014 chara evaluate ning to the d l radiologic e concentrat uilding nistration Bu ures will be MARSAME history of th ion in the LA pace and rec h LACBWR sified as a M WR personn Administrat rs surfaces a performed on biased tow ndicated the le, locations addition, vis ons of surf tify, to the e the worst gmental samp the sensitivit D radionuclid crete at each HTD analyse he concrete nd #006 and mmary of t nt HTD rad H-3 and Sr-9 espective MD Am-243. An acterization the possibl discovery of cal contamin tions of Cs-1 uilding and surveyed fo E guidance.
he use of un ACBWR A cords storage R and G-3 MARSSIM nel and the p tion Buildin and the roof n the roof, on ward location e presence were determ sual observat face contam extent possib case bound mpling appro ties required des.
h sample loc es for beta an deeper than WTB samp the analytica dionuclides i
: 90. The oth DC include; analysis of survey from le extent o f cracked dra nation of su 137 at 0.352 G-3 Crib H or unrestricte nsealed radio dministratio
: e. An enviro operations.
Class 2 stru resence of th ng included
: f. Direct m n floor tiles ns where phy of fixed a mined based tions of floo mination, suc ble, the loca ding radiolo ach also en d to determin cation was se nd alpha em n 1/2 inch de le locations al results fo identified by her radionuc C-14, Fe-55 the results o m the floor o of a radioa ain system p urrounding 2 pCi/g, Co-House will n ed release us oactive mate on Building.
onmental lab The LACB ucture due t he environm a scan for measurement and around ysical and/or upon or and ch as ations ogical sured ne the ent to mitting eep at
#001 or the y the clides 5, Ni-of the of the active piping soils.  
-60 at not be sing a
: erials, The b was BWR to its mental gross ts for floor


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.
La Cross License T Revision drain ope each dire The resu 4,915 dpm the secon imbedded gamma s was then and seco from less and dire observed Beta sc 2,261 dpm from less Direct be of 243 d measurem identified 2.3.7. S Section 8 hydrogeo was deri Haley &
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.
(18) supp 2.3.7.1.
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.
For a di towns an river wat
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.
: Lansing, water fo approxim The LAC well at th state perm LACBW Building areas are to the gr pathway se Boiling W Termination n 0 enings. A sm ect measurem ults of the m/100cm2 w nd floor ha d in a floor spectroscopy n performed ond floor lam s than MDC ct alpha re d reading of 7 cans of th m/100cm2 w s than MDC eta-gamma m dpm/100cm2 ments were d concentrati urface and 8.5 in Chap ology and hy ived directly Aldrich, Hy plements the Area Grou stance of 40 nd cities alon ter for indus Iowa, about or industria mately 40 mi CBWR site he site. Sani mitted sanit WR Adminis
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
. Storm wa e periodically round area su after passing Water Reactor Plan mear sample ment.
          µ      to 9.0E-08 µCi/m  ml).
beta scans with a scan M allway, a di tile. The c
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.
: y. The analy involving th minated woo of 329 dpm adings rang 72 dpm/100c he roof are with a scan M C of 113 dpm measurement to a maxim all less than ions greater Groundwat pter 8 of t ydrology of y from Hal ydrogeologic e preliminary undwater Us 0 miles dow ng the Missis strial purpos t 15 miles d al purposes les downstre has its own itary wastes tary wastes h tration Buil ater runoff is y monitored urrounding t g through an r
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.
e for remova of the int MDC of 2,10 screte radio contaminated ysis of the ti he acquisitio od, carpet, a m/100cm2 to ged from le cm2.
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.
ea indicate MDC of 2,26 m/100cm2 to ts taken on t mum observ n MDC of 4 than MDC b ter his LTP c ZNPS and e ey & Aldri cal Investiga y findings in se wnstream of ssippi River ses, excludin downstream o between t eam.
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.
potable wa are collecte hauler. Thi lding and a s diverted di d for oil shee the facility v n oil separato 2-32 able contam terior surfac 00 dpm/100c oactive parti d portion of ile identified n of ten (10) and floor til a maximum ess than MD ed results 61 dpm/100c o a maximum the floor dra ved reading 42 dpm/100c by the analy ontains a s environs. T ich, Hydrog ation Report n Reference 1 the site, vir are obtained ng the adjac of the site.
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.
the LACBW ater supply, p d in a solids is includes a a sanitary h irectly to th en and disco via downspo or located in mination was ces ranged cm2. During icle was dis f the tile wa d 0.005 uCi
2-34
) biased dire le. Direct b m observed re DC of 39 d ranging fr cm2. Direct m observed ain openings g of 333 dp cm2. No re sis of the sm summary d The informat geological C t for the LaC
: 17.
rtually all m d from groun cent G-3 pla There are n WR site an provided thr s holding tan a sanitary ho holding tank he Mississipp oloration. R outs or ente nside the LSE also taken from 1,420 g the scan of scovered. T as removed of Cs-137.
ect measurem beta-gamma eading of 5, dpm/100cm2 rom 1,872 t alpha meas reading of 1 s ranged from pm/100cm2 a emovable co mear samples description tion containe Conceptual S Crosse Boilin municipal w und water. T ant, is the co no other know nd Prairie rough a sing nk and pump olding tank k that servi pi River at o Roof drains d r the norma E.
at the locati 0 dpm/100cm f the north e The particle and analyze An investig ments on the readings ra
,743 dpm/10 to a maxi dpm/100cm surements ra 152 dpm/100 m less than M and direct ontamination
: s.
of the geo ed in this se Site Model ng Water Re water supplie The nearest u oal-fired pla wn users of du Chien, gle ground w ped off by a that service ices the Tu outfalls. Re discharge dir al effluent re on of m2 to end of e was ed by gation e first anged 00cm2 imum m2 to anged 0cm2.
MDC alpha n was
: ology, ection (17).
eactor es for use of ant in f river WI, water local es the urbine elease rectly elease


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.
La Cross License T Revision 2.3.7.2.
C        Analy ysis for H-3 was perform  med on site.
Regional Mississip parallels upward; river stag demonstr river stag Groundw surface (
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,
Groundw the Missi may turn chemical the shallo Based on of the G-located i monitorin a slightly has a do gradient towards t there are stages. G Reactor B are below During p was com permeabi buildings soils will will circ localized outside th other han or buried underlyin shallow s contamin soils with orders of se Boiling W Termination n 0 Groundw lly, groundw ppi river. C the river. U however, th ge data comp rates that the ge impacts th water beneath bgs) and the water in the s issippi Rive n and flow l constituent ow system.
                                                  # 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.
n a review of
r Addition nal details, in ncluding thee off-site anaalytical laborratory reporrts are provided in Referrence 18.
-3 Ash Land in the sout ng wells (B1 y downward ownward gr at well pair the river bas e some perio Groundwater Building ba w the water t plant constru mpacted, redu ility can dec
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.
: s. The resul l flow at a s cumnavigate d flow regim he footprint nd, potential d piling, will ng groundw soils from p nation. The hin the supp f magnitude Water Reactor Plan ater Flow water flows i Closer to th Under typic he vertical gr pared to wa e shallow aq he water tabl h the site is e groundwat shallow depo
The colleected informmation during g each monittoring intervval includes:
: r. The deep parallel to s would occu f the ground dfill area grou th side of t 11AR/B11R vertical gra radient at w B9/B9A. T sin with a lo ods where t r flow throu sement shel table during uction, and m ucing the eff crease the h lting impact slower veloc the area, e mes on contam of these str l releases tha l likely take water. This precipitation, average sha port pilings, lower.
Depth D      to grouund water in the respectiive monitorinng well.
r in a westerl he shore, gr al river stag radient rever ter table ele quifer is in di le elevation.
Monitoring M            well w groundw   water pH/speecific conducctance/oxidaation and redduction potential/turb bidity/dissolvved oxygen/ttemperature..
first encoun ter is in dire osits and fill per groundw the river.
Radiological R              sample inforrmation inclluding a com  mpleted chainn of custodyy following grroundwater sample colleection.
ur at or near dwater elevat undwater mo the LACBW
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.
) to the east adient. Durin well pairs B This is expec ocalized influ the gradients ugh the LAC l) as well as high and low more specifi fective poros hydraulic con to groundw city, and reg effectively b minant fate a ructures will at occurred w much longe is further c
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.
, creating an allow aquifer the hydraul 2-33 ly direction roundwater ge, groundw rses during f evations mea irect hydrau ntered at an ect hydraulic l material flo water is also Because th r the surface tion measure onitoring we WR site, an of and up gr ng times of n B11R/B11AR cted as grou uence at B9/
Sr-90 was w also positively detected in wells     w        MW-2002A, MW-2203A and MW-204A with 2-35
s are revers CBWR site is s the deep p w river stage ically the ins sity and perm nductivity o water flow is gionally, a si bypassing th and transpor l likely be d within the fo er to migrate compounded n area that w r hydraulic c ic conductiv from the bl may also h water gradien flood stages.
asure in LAC ulic commun n average de c communica ows towards likely to flo he potential
, the release ements colle ells (# B2/B3 nd associate radient of LA normal and R and B2/B undwater flo
/B9A from t sed; and this s impacted b pilings that s e conditions.
stallation of meability of of the aquife s that ground ignificant pe these soils.
rt are that po deflected and ootprint of th e both in th d as the ove will likely re conductivity vity would b luffs on the have a flow nts near the  
. The geolog CBWR site nication with epth of 20 fe ation with th s the west an ow towards t l releases of s would like ected during 3/B9A/B9/B ed backgrou ACBWR, th low river sta B3, with an ows generally the adjacent s is likely d by deeper st support the f the support f the soils. T er within the dwater withi ercentage of The impli otential relea d flow aroun he buildings e vadose zo erlying struc etain any po y is 313 feet be expected east toward component river are sli gical and his monitoring h the river an eet below gr he adjacent nd discharges the west but f radiologic ely be confin routine sam B7/B8), whic und groundw here appears age, groundw upward ve y from the b t inlet. How due to high tructures (i.e structures, w t pilings, the This reducti e footprint o in the comp f the flow re ications of ases that occ nd them. O s, via floor d one as well a ctures isolat tentially rele per day. Fo to be one to ds the t that ightly storic wells nd the round river.
s into t then cal or ned to mpling ch are water to be water ertical bluffs
: wever, river e., the which e soil ion in of the pacted egime these curred On the drains as the te the eased or the o two


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.
La Cross License T Revision The velo gradient.
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.
across th Therefor the inch Environm show sea stage. Th LACBW vicinity structure direction 2.3.7.3.
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:
Historica monitorin monitorin monitorin Dairylan Of the w LACBW routine b designate Environm G-3 Foss Nos. 3, 4 levels re 3.0E-08 µ During th to the s radioactiv The well suspected that samp As note Activities wells to monitorin if ground located n interval o below gr B.
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),
se Boiling W Termination n 0 ocity of gro The gradie he site, groun e, it is likely hes and fee mental Moni asonal varia hese wells a WR site struct of suspect s/foundation ns.
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.
Previous I ally, the LAC ng wells. F ng wells loc ng wells of d for radiolo wells shown WR facilities basis. The gr ed as B-2, mental Moni sil Station op 4 and 5 wer ported durin
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.
µCi/ml to 9.
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
he recovery outh of the ve liquids fr l-point show d leakage. T ple are prese d in the L s Report (D support gro ng wells (10 dwater qual nominally wi of 15 to 25 f rade. These Water Reactor Plan oundwater is ent of the wa ndwater mon y that the gro et/day rang itoring Prog ation on upw are not suffic tures or area broken dra ns or variati Investigation CBWR Lice igure 2-11 i cated on th ff the LACB ogical purpo n on Figure were histor roundwater m B-3, B-7, itoring staff perational re re routinely ng this mon 0E-08 µCi/m of a probab e Turbine B rom suspect wn on Figure The well-po ented in Tabl LACBWR D D-Plan/PSDA oundwater e 0 wells total) ity had bee ithin five (5) feet below g wells are sh r
s directly r ater table is i nitoring has oundwater v e). Ground gram wells a ward and do cient to char as where pote ain lines) co ions in fill m ns ensed Site ha llustrates the e LACBWR BWR site t ses.
2-11, only P rically monit monitoring w B-8, B-9, on a routine equirements.
monitored f nitoring peri ml).
le spill incid Building. T broken drain 2-11 was es int was sam le 2-17. Thi Decommissio AR) (19), D evaluation.  
) were instal en impacted
) feet of one grade and on how on Figu 2-34 elated to bo nfluenced by shown that velocity acro water eleva agree with t ownward gra racterize the ential releas ould have o materials co as had sever e current loc R site. The that are or Potable Wa tored by Da wells and ba B-9A, B11A e basis for no During LA for gross be iod was less dent in 1983 This inciden n lines in th stablished do mpled once o is well-point oning Plan airyland rec In Novemb lled within t by plant o e another con ne deep well ure 2-11 as M oth the hyd y the topogr the water ta oss the site is ation data the regional adients that groundwate es associated occurred. In ould locally ral potable w cation of po ere is no po have been ater Wells N airyland for ackground gr AR, and B on-radiologi ACBWR ope eta activity.
s than or eq
, a temporar nt concerne e Turbine B own gradien on May 3, 19 t has since be and Post-S cently instal ber 2012, fi the LACBW operations.
nsist of one with a scree MW 200A an draulic cond raphy; and, w able has a v s also relativ from the groundwate are influen er flow below d with LAC n these area influence g water wells otable water otable water monitored Nos. 3 and 4 radiological roundwater B11R are m ical paramete erations, Pota Typical gr qual to MD ry well-poin ed the pote Building to su nt and below 983. The an een abandon Shutdown D lled groundw ive (5) pairs WR licensed The well p shallow wel ened interva nd B throug ductivity and with the flat ery low grad vely slow (i.
G-3 Coal er flow, and nced by the w and aroun BWR (i.e., i as, pilings, groundwater and groundw and groundw r or groundw by Solution 4 which serv l conditions monitoring monitored by ers to suppo able Water W ross beta ac DC (ranging nt was establ ential leakag ub-building w the grade o nalysis resul ned.
Decommissio water monit s of groundw site to deter pairs which ll with a scre al of 45 to 55 h MW-204A d the areas dient.  
.e., in Plant d also river nd the in the deep flow water water water ns or viced on a wells y the ort the Wells ctivity from lished ge of soils.
of the ts for oning toring water rmine were eened 5 feet A and


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.
La Cross License T Revision Two (2) in June groundw 90 and C In June o through 2 and B11 several r fourth ro Potable samples transuran of the gro Addition
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.
: 18.
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.
2.3.7.4.
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 LAC twice pe groundw the MW-The colle D
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:
M p
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.
R gr 2.3.7.5.
a 2.5. References R
Groundw (5 pairs) sampling wells MW Novembe positively ranging Novembe during th During th MW-202 Sr-90 w se Boiling W Termination n 0 rounds of gr 2013 and th water samples Cs-137. Analy of 2014, a t 204 A and B AR. These radionuclide ound of gro Well #5, an were sent o nic radionucl oundwater sa nal details, in On-Going CBWR Site g er year for r water is at rel
: 1.      U.S.
-200A/B thru ected inform Depth to grou Monitoring w otential/turb Radiological roundwater Summ water charact within the g in 2013. H W-201A and er of 2013 y detected i from 1.43 p er 2013 sam he 2013 samp he June 201 2A, MW-203 was also po Water Reactor Plan roundwater hen during s were sent ysis for H-3 third round o B; Potable W e collected g s including oundwater w nd Monitori off for radio lides. Table amples and r ncluding the g Investigatio groundwater radiological latively high u MW-204A mation during und water in well groundw bidity/dissolv sample infor sample colle mary of Grou terization eff LSE area H-3 was posi d B, MW-20 at concentra in the same pCi/L to 2.1 mpling period pling period 4 sample pe 3A and MW sitively det r
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.
samples wer a seasonal l to an off-sit was perform of groundwa Water Wells #
: 2.      U.S.
groundwater HTD and t were collecte ing Wells B ological ana es 2-18 and 2 results.
U Nuclear Regulatory Commission          n, NUREG-11575, Revisiion 1, Multi--Agency Radiation R          Surrvey and Sitee Investigatiion Manual ((MARSSIM      M), August 20000.
e off-site ana ons r monitoring analysis pu her and lowe A/B wells as g each monit the respecti water pH/spe ved oxygen/t rmation incl ection.
: 3.       U.S.
undwater An fforts comme in Novemb tively detect 02-A and B, ations rangi wells durin 18 pCi/L; ho
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.
: d. Co-60 an eriod, H-3 w W-203B) at c ected in w 2-35 re collected low groundw te laboratory med on site.
: 4.       EnergySoluti E              ons PG-EO--313196-SV-PL-001, Chharacterizatioon Survey P        Plan for the L La Crosse C      Boilin ng Water Reaactor.
ater samples
: 5.      EnergySoluti E              ons GP-EO--313196-QA    A-PL-001, Quuality Assurrance Projectt Plan LACB      BWR Site Characteerization Projject (QAPP)).
#3, 4, 5, and samples w transuranic r ed from: M B11R and B alysis of sev 2-19 provide alytical labor g program co urposes only er elevations shown on F toring interv ive monitorin ecific conduc temperature.
2-37
luding a com nalytical Res enced throug ber 2012 an ted at concen MW-203A ing from 15 ng the June owever, it w nd Cs-137 w was positively oncentration wells MW-20 in 2013, du water level y for radiolo s was collec 7; and Mon ere sent off radionuclide MW 200A an B11AR. T veral radion es a summar ratory repor onsists of ob y from exis
. The moni igure 2-11.
val includes:
ng well.
ctance/oxida mpleted chain sults gh the install nd the com ntration grea and B and M 50 pCi/L to 2013 sampl was not po were not po y detected in ns ranging fr 02A, MW-2 uring the sea in Novemb ogical analys cted from: M nitoring Well f for radiolo es. In Septe nd B throug These collec nuclides incl ry of the radi rts are provi btaining grou ting monito toring wells ation and red n of custody lation of 10 mmencement ater than MD MW-204A a 660 pCi/L.
ling period a ositively dete sitively dete n four (4) w from 245 pC 203A and asonal high w ber 2013. T sis for Co-60 MW-200A a ls B2, B-3, B ogical analys ember of 20 gh 204A an cted groundw luding HTD iological ana ded in Refer undwater sam oring wells w s sampled in duction y following monitoring of groundw DC in monit and B in Jun Sr-90 was at concentra ected during ected in any wells (MW-B i/L to 336 p MW-204A water These 0, Sr-and B B11R sis of 014 a nd B, water D and alysis rence mples when clude wells water toring e and s also ations g the y well
: B11R, pCi/L.
with


La Crossse Boiling Water W        Reactorr License Termination T             Plan Revision n0
La Cross License T Revision concentra Am-241 During t greater th concentra were also 2.4.
: 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)).
C The surv deferred.
: 7. Dairyland D          Power Corporaation LAC-T  TR-138, Initiial Site Charracterizationn Survey for SAFSTOR - December 2009. 2
under co that will basement illustrate defer the condition ALARA data wou areas),
: 8. U.S.
Safet Histo Acce struct interf The a physi condi As acces will be co for the s radionuc and HTD events ca of a surv stored in validatin As decom surface d for open documen se Boiling W Termination n 0 ations rangin were also po he Septemb han MDC in ation of 1.14 o positively d Continuing C vey of many Examples ncrete or asp remain and t after liner s buried pip e characteriz ns:
U Nuclear Regulatory Commission        n NUREG-11575, Suppleement 1, Muulti-Agency Radiation R          Surrvey and Assessment of Materials annd Equipmennt Manual (M      MARSAME  E) -
consideratio uld likely not ty considerat orical data sh ss for charac tures or othe fere with con ability to use ical relations itions repres ss is gained ollected, eva survey unit.
December D          20 006.
lides present D radionuclid aused by equ vey unit(s) w n the charac g the initial mmissioning decontamina n air demolit nted survey a Water Reactor Plan ng from 1.1 ositively det ber 2014 sam n any well.
: 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.
4 pCi/L. Co detected at r Characteriz inaccessible s of areas w phalt coverin d be subjec r removal an ping systems zation of a ons (e.g., the t change the
: 10. EnergySoluti E              ons Techniccal Support Document D          R RS-TD-3131996-006, Luddlum Model 444-10 Detector Sensitivity.
: tions, hows that the cterization w er obstacles w ntinued oper e engineering ship to surro sented by the to areas tha aluated and s This data t and update des. In addi uipment failu will be reco terization d classificatio g proceeds, ation (as wel tion or unre and a formal r
S
12 pCi/L to ected at resi mple period, Sr-90 was o-60, Ni-63, residual conc zation e or not read where survey ngs, structur cted to FRS nd the inter s that may r soil or stru e area is eith e survey area e area could would require where the re ration of ope g judgment i ounding area e conditions at were prev stored with-o will be use e the variabil ition, as the ures or perso orded. Thes atabase. Th n and in plan areas will, ll as fixed co estricted rele l turnover w 2-36 2.01 pCi/L.
: 11. U.S.
dual concen
U Nuclear Regulatory Commission        n, NUREG-11576, Multi--Agency Raddiological Laboratory L          Analytical A            Prootocols Man nual (MARL  LAP) - Auguust 2001.
, H-3 was n positively d
: 12. U.S.
, Cs-137, Eu centrations in dily accessib ys are deferr ral wall and
U Nuclear Regulatory Commission        n Regulatoryy Guide 4.155, Quality Assurance or Radiological R              Monitoring Programs (IInception Thhrough Norm  mal Operations to Licensse Termination)
, the underl riors of bur remain in th ucture was b her a radiati a or area clas be classified e significant emoval could erating system in assigning s and the lik in these adja viously inacc other radiolo ed along wi lity in the ra decommiss onnel errors, se events w his additiona nning for the as necessar ontamination ease. When will be made C-14, Tc-9 ntrations in se not positivel detected in o u-152, Eu-15 n several we ble subsurfa rred include floor surfac rlying concr ried pipe tha he end-state based on on ion or conta ssification o d without fur t deconstruct d result in an ms, or the area a cl kelihood of th acent areas.
T              - Effluent Streams S        and the Environnment - July 2007.
cessible, add ogical survey ith existing adionuclide m ioning progr
: 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.
, which may will be evalu al character e FRS.
: 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.
ry, be decon n) to levels n a structur by the Radi 99, Eu-152, everal wells ly detected a one (1) well 54, Pu-239/2 ells.
: 15. ZionSolution Z              s Technical Support Doccument 13-0004, Examinnation of Cs-137 Global Fallout in Soiils at Zion Sttation.
ace soils or s soils under ces in some rete in the R at may rem condition.
: 16. EnergySoluti E              ons Techniccal Support Document D          R RS-TD-3131996-001, Raddionuclides oof Concern C        Duriing LACBW  WR Decomm  missioning.
ne or more amination are of the locatio rther charact tion of adjac n unsafe con lassification he area to ha ditional char y data in a s data to upd mix for both resses, data y affect the ra uated and, w rization data ntaminated that will me e is ready f ological Pro Pu-239/240 at concentra l, MW-200A 240 and Am surfaces has r structures, of the basem Reactor Bui main. Figure The decisi of the follo ea and addit on or surroun terization, cent systems ndition or n based on ave radiolog racterization urvey histor date the typ h gamma-em from operat adiological s when approp a will be us to remove eet the condi for demoliti otection grou 0 and ations A at a m-241 been soils ments ilding e 2-3 on to owing tional nding s,
: 17. Haley H      & Aldrrich, Hydrog  geological Conceptual Siite Model, FFile No. 387005-001 - Auugust 30, 2012.
gical n data ry file pes of mitting tional status
: 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.
: priate, ed in loose itions ion, a up for
: 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)
La Cross License T Revision the comp are suitab Followin a "turnov acceptan transferre performa may inclu The "turn survey pe survey da
LAACBWR Sitte Enclosuree Grounds Reactorr Building, WTB, W      WGTV  V, Ventilatioon L10101001                                                          Class 1        1,9922 Stack Grounds G
: turnover, survey p met. The Appr action Appr Appr with Appr radio Data addit Appr 2.5.
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
R
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se Boiling W Termination n 0 pany preform ble.
ng the demol ver assessme ce criteria w ed to Charac ance of the F ude a "turno nover surve erformed, re ata prior to c
, and FRS), a lans will co ese objective ropriate instr n level and/o ropriate instr ropriate surv the calibrati ropriate samp nuclide ratio analysis crit ional sample ropriate class References U.S. Nuclear Content of Li 011.
U.S. Nuclear Radiation Sur U.S. Nuclear Consolidated f Radiologic EnergySoluti Crosse Boilin EnergySoluti ite Characte Water Reactor Plan ming demoli lition and/or ent" will be p will be met, cterization/L FRS. Otherw over survey,"
ey" process, epresent at le conducting t a documente ontain the ap es include:
rument selec or release cri rument quali ey technique on methodol ple collectio os, teria to ident es and, sification of Regulatory icense Termi Regulatory rvey and Site Regulatory Decommiss cal Criteria, F ons PG-EO-ng Water Rea ons GP-EO-erization Proj r
ition, validat r remediation performed. I
, then physi License Term wise, additio
" primarily fo together wi east one, but the FRS. Fo ed survey pl ppropriate da ction to ensur
: iteria, ity control m es to ensure
: logies, n and analys tify follow-u the survey a Commission ination Plan Commission e Investigati Commission sioning Guid Final Report
-313196-SV actor.
-313196-QA ject (QAPP) 2-37 ting that the n, and when If the results ical and adm mination grou onal remedia for Class 1 an ith any addi t possibly se or each type an will be d ata assessme re the proper measures to e that the field sis to determ up actions su area.
n, Regulator s for Nuclea n, NUREG-1 ion Manual (
n, NUREG-1 dance - Char t - Septembe
-PL-001, Ch A-PL-001, Qu
).
e radiologica n an area is b s of this asse ministrative up personne ation may b nd 2 areas w itional chara everal, oppo of survey (c developed us ent to ensur r sensitivity ensure operab d measurem mine spatial v uch as remed ry Guide 1.1 ar Power Rea 1575, Revisi (MARSSIM 1757, Volum racterization er 2006.
haracterizatio uality Assur al condition believed to b essment indi control of l for prepara be required.
within the LS acterization ortunities to c characterizat ing the DQO re that sever relative to th
: bility, ent techniqu variability an diation and th 79, Standard actors, Revis ion 1, Multi-M), August 20 me 2, Revisio
, Survey, an on Survey P rance Project s in the stru be ready for icate that the the area wi ation, design This assess SE.
and remedi collect addit tion, remedia O process. T ral objective he applicabl ues are consi nd variability he collection d Format and sion 1 - June
-Agency 000.
on 1, nd Determina Plan for the L t Plan LACB ucture
: FRS, e FRS ill be n, and sment iation tional
: ation, These es are le istent y in n of d
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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.
La Cross License T Revision
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
: 6.
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: 17.
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: 18.
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: 19.
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: 20.
In E
1 se Boiling W Termination n 0 EnergySoluti Water Reacto Dairyland Po AFSTOR -
U.S. Nuclear Radiation Sur December 20 andia Nation Contaminatio EnergySoluti 0 Detector S U.S. Nuclear Laboratory A U.S. Nuclear Radiological Termination)
EnergySoluti urvey Repor EnergySoluti urvey Repor ZionSolution allout in Soi EnergySoluti Concern Duri Haley & Aldr 0, 2012.
Haley & Aldr Reactor, Dair 015.
Dairyland Po Decommissio nternational Emitters (max 998.
Water Reactor Plan ons Technic or Historical wer Corpora December 2 Regulatory rvey and As 006.
nal Laborato on From Dec ons Technic Sensitivity.
Regulatory Analytical Pro Regulatory Monitoring
- Effluent S ons GG-EO-rt for Octobe ons LC-RS-rt for June th s Technical ils at Zion St ons Technic ing LACBW rich, Hydrog rich Inc., Hy ryland Powe wer Coopera oning Activit Standard IS ximum beta r
cal Support D Site Assessm ation LAC-T 2009.
Commission sessment of ory, NUREG commissioni cal Support D Commission otocols Man Commission Programs (I Streams and
-313196-RS er and Novem PN-164017-hru August 2 Support Doc tation.
cal Support D WR Decomm geological C ydrogeologic r Cooperativ ative, LACB ties Report (
O 7503-1, P energy grea 2-38 Document R ment (HSA)
TR-138, Initi n NUREG-1 Materials an G/CR-5512, V ing Paramete Document R n, NUREG-1 nual (MARL n Regulatory Inception Th the Environ S-RP-001, LA mber 2014 F
-001, LACB 2015 Field W cument 13-0 Document R missioning.
onceptual Si cal Investiga ve, Genoa W BWR Decom (D-Plan/PSD Part 1, Evalua ater than 0.15 RS-TD-31319
).
ial Site Char 1575, Supple nd Equipmen Volume 3, R er Analysis -
RS-TD-31319 1576, Multi-LAP) - Augu y Guide 4.15 hrough Norm nment - July ACBWR Ra Field Work -
BWR Radiolo Work - Nove 004, Examin RS-TD-31319 ite Model, F ation Report, Wisconsin, Fi mmissioning DAR), Revis ation of Surf 5 MeV) and 96-003, La C racterization ement 1, Mu nt Manual (M Residual Rad
- October 19 96-006, Lud
-Agency Rad ust 2001.
5, Quality A mal Operatio 2007.
adiological C
- November ogical Chara ember 2015.
nation of Cs-96-001, Rad File No. 3870
, La Crosse B ile No. 3870 Plan and Po sion - March face Contam Alpha-Emit Crosse Boilin n Survey for ulti-Agency MARSAME dioactive 999.
dlum Model 4 diological ssurance or ns to Licens Characterizat r 2015.
acterization 137 Global dionuclides o 05-001 - Au Boiling Wat 05-008, Janu ost Shutdown h 2014.
mination, Bet tters - Augu ng E) -
44-se tion of ugust ter ary n
ta-ust


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)
La Cross License T Revision Survey Unit ID #
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
L101010 L101010 L101010 L101010 L201110 L201110 L301210 L301210 L301210 L401210 L401210 L401210 L401210 L401210 se Boiling W Termination n 0 Survey 01 Reactor Stack G 02 Turbine Diesel G 03 LSA Bu 04 North L 01 LACBW Crib Ho 02 G-3 Cri Dischar 01 North E 02 Transm 09 Plant A 03 G-3 Co 05 Coal Pi 06 Capped 07 Ground 08 Hwy 35 Water Reactor Plan Table 2-1 y Unit Descr LA r Building, W Grounds e Building, T Generator Bu uilding, Mai LSE Grounds WR Adminis ouse, Wareh ib House, LA rge Line, Are End of Licen mission Switc Access, ISFSI al Plant Gro le Grounds d Ash Impou ds East of Hi 5/Railroad R r
  #6 Well W House 2-41
LACBW ription ACBWR Sit WTB, WGTV Turbine Offi uilding Grou ntenance Ea s
LSE Buff stration Buil ouse Ground ACBWR Cir ea South of L Clas nsed Site chyard Area I Haul Road Non-Im ounds undment Gro ghway 35 Right of Way 2-39 WR Open L te Enclosure V, Ventilatio ce Building, unds at Shack Gro fer Zone Gro lding, LACB ds rc. Water LSE Fence ss 3 Grounds d Grounds mpacted Grou ounds y Grounds Land Survey Cl e Grounds on
, 1B ounds ounds BWR s
unds No No No No No y Units Initial lassification Class 1 Class 1 Class 1 Class 1 Class 2 Class 2 Class 3 Class 3 Class 3 on-Impacted on-Impacted on-Impacted on-Impacted on-Impacted n
Approxim Survey U Area (m 1,992 2,315 1,749 2,387 7,211 6,785 24,04 11,71 31,01 d
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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
La Cross License T Revision Surve B101 B101 B101 B101 B101 B101 B101 B101 B101 B201 B201 B201 B201 B201 B201 B301 B301 B301 B301 se Boiling W Termination n 0 ey Unit 10001 10002 10003 10004 10005 10006 10007 10008 10009 10101 10102 10103 10104 10105 10106 12101 12102 12103 12104 Water Reactor Plan Table 2-2 Sur Wa LAC W
                                                                                                          ~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).
LACBWR LACBWR M
b    Fun nctional equivallent instrumenttation may be used u
L LACBW LA LA LA Ba Transmissi Barg r
2-42
LACBW rvey Area D Reactor Bu aste Treatmen CBWR Venti Waste Gas Ta R Turbine Bld Bldg 1B Diesel G LSA Buil Maintenance E Pipe Tun ACBWR Cr G-3 Crib H WR Administ ACBWR War ACBWR War ACBWR War ack-up Contr ion Sub-Stat G-1 Crib H ge Washing B 2-40 WR Structu Description uilding nt Building ilation Stack ank Vault dg./Turbine Generator Str lding Eat Shack nnel rib House House tration Build rehouse #1 rehouse #2 rehouse #3 rol Center tion Switch H House Break Room ural Survey k
Office ructure ding House m
y Units Class Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl sification lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 2 lass 2 lass 2 lass 2 lass 2 lass 2 lass 3 lass 3 lass 3 lass 3


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)
La Cross License T Revision G-3 R G-3 S G-3 C G-3 T G-3 E G-3 C G-3 C G-4 W G-3 L G-3 L G-3 C G-3 C G-3 V G-3 T G-3 B G-3 F G-3 F G-3 W G-3 S G-3 S
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
#6 W se Boiling W Termination n 0 Table Reclaim Buil Stock Out Tr Coal Unload Transfer Tow Electrical Ro Crusher Tow Conveyor #6 Warehouse a LRAPB Buil Lime Silo El CAT Buildin Coal Plant Vehicle Stora Train Shed Bottom Ash Fly Ash Silo Fly Ash Elec Waste Silo Surge Tank Settling Tank Well House Water Reactor Plan e 2-2 (contin lding ransfer Build ing Tower wer A oom wer 6 (2) and Electrica lding ectrical Buil ng age Building Dewatering ctrical Buildi k
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
r nued)
Isotopic Urranium    Alpha A    Spec        DOE EML E    HASL 3000 (U-234/235  5/238)                      < 0.06 pCi/g p
Non Imp ding al Room lding g
Isotopic Cuurium      Alpha A     Spec        DOE EML E    HASL 3000 (Cm-243/2 244)                           < 0.03 pCi/g p
Buildings ing 2-41 LACBWR pacted Struc G-3 An G-3 Bo G-3 Ex G-3 Ga G-3 Su G-3 Su G-3 Li G-3 W G-3 Ac G-3 As G-3 Ba G-3 Fl
Isotopic Am mericium  Alpha A    Spec        DOE EML E    HASL 3000 (Am-241/2 243)                           < 0.04 pCi/g p
#7 We G-3 Co G-3 Sa G-3 St G-3 Gr G-3 As Main P S03 Ta Structural ctures nnex Buildin oiler Fuel Oi xplosive Gas as Room ub Station Sh ub Station Sh ime Storage Weigh Station ctive Reclaim sh Coordina ag Houses (5 ammable St ll House oal Scale ample Buildi tock Out Tra rid Shed sh handling Pollution Co ank Building Survey Uni ng il Pump Bui s Storage Ro hed hed Silo n
C-14                  LS SC                EPA EE ERF C-01                    ENIC Modifiied
m Buildings ators Office
                                        < 5.0 pC Ci/g                        50.0 pCi/L Tritium              LS SC                EPA 90 06.0                        EPA 906.0
: 5) torage Shed ing ansfer Buildi Blower Buil ontrol Electri g
                                        < 10.0 pCi/g p                          300.0 pCi/L Sr-90                GFPC G                 DOE EML E    HASL 3000              EICHROM M  Modified Methood
its lding oom s/ Tunnel ing lding ical Buildingg
                                        < 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)
La Cross License T Revision Dete Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Gamma System a
(on Licensed L        Sitee)
Bas Stan b
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
Fun se Boiling W Termination n 0 ector Model m 44-9 m 43-68 mo m 43-68 mo m 43-93 mo m 43-89 mo m 43-93 mo m 43-89 mo m 44-10 m 43-37 m 43-10-1 a Spectroscop ed on 1-minute ndard, ISO 750 nctional equival Water Reactor Plan Table 2-3 l b Me Ludl ode Ludl ode Ludl ode ode Ludl ode ode Ludl Ludl Ludl Ludl py e count time; a 03-1 (20).
lent instrument r
Instrume eter Model lum 3 lum 2350-1 lum 2350-1 lum 2360 lum 2360 lum 2350-1 lum 2350-1 lum 2929 N/A and default valu tation may be u 2-42 ent Types a Applica sca static &
stat static &
stat sca sca and/
smea Anal ues for surface used and Nomina ation Ty (dp an 1,0
& scan 1,8 tic
& scan 1,8 2,0 tic an 3.5 6.5 an 2,0 or ar lysis efficiencies (
al MDCs Typical Dete MDCscan pm/100cm2) 000 to 2,000 800 to 2,000 N/A 800 to 2,000 000 to 2,200 N/A 5 pCi/g 60Co 5 pCi/g 137Cs 000 to 2,200 N/A N/A s) as specified ction Sensit
)
MDCst (dpm/10 0
N/A 0
600 to 80 to 0
0 800 to 800 to 90 to 1 90 to 1 o
s N/A 0
N/A
~0.10 p for Co-6 Cs-13 in Internationa tivity tatic a
0cm2)
A 700 90 900 900 100 100 A
A
-15
-80 pCi/g 60 and 37 al


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)
La Cross License T Revision Analysis /
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
Gamma Radionucli Isotopic N (Np-237)
Undisturbbed                            0.23 to 0.66                  0.155 to 0.77 Disturbedd                              0.27 to 0.34                  0.23 to 0.42 2-45
Isotopic Pl (Pu-238/23 Isotopic Th (Th-228/23 Isotopic Ur (U-234/235 Isotopic Cu (Cm-243/2 Isotopic Am (Am-241/2 C-14 Tritium Sr-90 Pu-241 Tc-99 Gross Alph Fe-55 Ni-63 Ni-59 se Boiling W Termination n 0 Table 2-4 Analytes ides G
eptunium A
lutonium 39/240)
A horium 30/232)
A ranium 5/238)
A urium 244)
A mericium 243)
A LS LS G
LS LS ha / Beta G
LS LS LS Water Reactor Plan Off-Site Technique Gamma Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec SC SC GFPC SC SC GFPC SC SC SC r
e Laboratory DOE E
< 0.1pC DOE E
< 0.04 p DOE E
< 0.05 p DOE E
< 0.05 p DOE E
< 0.06 p DOE E
< 0.03 p DOE E
< 0.04 p EPA EE
< 5.0 pC EPA 90
< 10.0 p DOE E
< 1.0 pC DOE E
< 10.0 p DOE E
< 2.0 pC DOE E
< 10.0 p DOE E
< 2.0 pC DOE E
< 50.0 p 2-43 y Analytica Soils (pCi/
EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g ERF C-01 Ci/g 06.0 pCi/g EML HASL 300 Ci/
EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g al Methods a Method and
/g) 0 0
0 0
0 0
0 0
0 0
0 0 (SRW01) 0 (SRW01) and Typical d Sensitivity Wat EPA Method 10.0 pCi/L EML Pu-02 M 1.0 pCi/L ENIC Modifi 50.0 pCi/L EPA 906.0 300.0 pCi/L EICHROM M 2.0 pCi/L EML Pu-01 50.0 pCi/L EICHROM T 15.0 pCi/L EPA 900.0 5.0 pCi/L EML Fe-01 M 100.0 pCi/L EML Ni-01 M 15.0 pCi/L EML Ni-01 M 100.0 pCi/L l MDCs ter (pCi/L) 901.1 Modified ied Modified Metho Tc-01 Modified Modified Modified od


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)
La Cross License T Revision se Boiling W Termination n 0 Ta Location Area West o Area South Area North Area at G-3 Area Outsid Area at G-3 33 miles So Pedretti Far Radio Towe Junction of East of Stod Water Reactor Plan able 2-5 of #2 Wareh of Parking L of LACBW Gas Silo de G-3 Offic Outfall uth at Bad A m Substation er Northeast Hwy O and ddard at Hwy r
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
2005 Dairy (on L house Lot R Admin Bu es (off L Axe Boat Lan n East of LA of LACBW Hwy K y O Junction 2-44 yland Backg Licensed Site uilding Licensed Site nding ACBWR WR n
                  *L Listed half life is i the shortest half h life for thee radionuclidess in the pair 2-46
ground Stud Co-60 (pCi/g) e)
<MDC
<MDC
<MDC
<MDC
<MDC
<MDC e) 0.023
<MDC
<MDC
<MDC
<MDC dy for Soils Cs-(pC 0.0 0.0 0.
0.0 0.0 0.0 0.3 0.2 0.0 0.
0.0
-137 Ci/g) 077 026 149 038 076 017 381 227 035 188 065


L La Crosse Boilin  ng Water Reactor L
La Cross License T Revision T
License Termination Plan R
Conditio Undisturb Disturbed Undisturb Disturbed se Boiling W Termination n 0 Table 2-6 on and Dept bed d
Revision 0 Table 2-8      Non-Impacted Open Land Survey Units - Characterizattion Survey Su ummary S
bed d
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
Water Reactor Plan Investiga th D
Capped  Ash Immpoundment G Grounds East off Description  G-3 Coal Plannt Grounds    Coal Pile Grounds G
Non r
Grounds                    H Highway 35 S
ative Levels Meas Drainage Ar 0.
Surface Soil          Co-60            Cs-137      Co-60          Cs-137    Co-60          Cs-137      Co-60          Cs-137
0.
# of Samples            3              3          3              3          3              3            3                3
n-Drainage 0.
# >CL                    0              1          0              1          0              2            0                3 M
0.
Mean (pCi/g)          0.070          0.082      0.071          0.061      0.082          0.100        0.080            0.264 M
2-45 for Cs-137 sured Rang (pCi/g) eas Surface 00 to 2.80 00 to 1.67 Areas Surfa 23 to 0.66 27 to 0.34 Based on B ge R e 0-10 cm ace 0-10 cm
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
# of Samples            4              4          3              3          4              4            3                3
# >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
# of Samples                                                                  2              2
# >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
===Background===
License Termination Plan R
Range for 95 (p
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)
0.45 0.35 m
A Surface Soil            Co-60          Cs-137      Co-60            Cs-137
0.15 0.23 d Studies 5% Distribu pCi/g) 5 to 3.63 5 to 2.86 5 to 0.77 to 0.42 ution
                            # of Samples              3              3          17                17
                            # >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
                            # of Samples              3              3
                            # >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
                            # of Samples
                            # >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
La Cross License T Revision se Boiling W Termination n 0 Table 2
License   Termination Plan R
*L Water Reactor Plan
Revision    0 Table 2-9            Non Impa      acted Coal Pile and Soil Samp  ples - Test Ameerica Laboratorry Analysis (pC Ci/g)
-7 Initia Radio H
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
C Fe N
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
Co N
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
Sr Nb Tc Cs Eu Eu Eu Np Pu Pu Pu Pu Am Cm-24 Listed half life i r
L3012105-Genoa Coal Pile P                                                        0.018                        0 0.022        0.019 0              0 0.052  0.152  00.048                              0.041 L
al Suite of L onuclide H-3 C-14 e-55 i-59 o-60 i-63 r-90 b-94 c-99  
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
-137 u-152 u-154 u-155 p-237 u-238 u-239 u-240 u-241 m-241 43/244*
L3012105-QJ-GS-001-S SB                                                        0.026                        0 0.020        0.023 0              0 0.049  0.166  00.055                              0.048 L
is the shortest h 2-46 LACBWR S Ha half life for the Site-Specific alf Life (Yea 1.24E+01 5.73E+03 2.70E+00 7.50E+04 5.27E+00 9.60E+01 2.91E+01 2.03E+04 2.13E+05 3.00E+01 1.33E+01 8.80E+00 4.76E+00 2.14E+06 8.78E+01 2.41E+04 6.60E+03 1.44E+01 4.32E+02 1.81E+01 e radionuclides c Radionucl ars) s in the pair lides
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
L L
License Termination Plan R
R S
Revision 0 Table 2-10      Impacted Cla ass 1 Open Land  d Survey Unitss - Characterizzation Survey SSummary S
S M
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
M M
Surface Soil         Co-60            Cs-137          Co-60          Cs-137        Co-60          Cs-137      Co-60            Cs-137
M S
# of Samples           12              12              2              2            7              7            1                1
S M
# >CL                   2              12              0              0            0              1            0                0 M
M M
Mean (pCi/g)         0.080          0.215          0.049          0.050          0.059          0.069        0.045            0.049 M
M S
Median (pCi/g)        0.058          0.100          0.049          0.050          0.050          0.054        0.045            0.049 M
A M
Max (pCi/g)          0.287          1.070          0.054          0.051          0.099          0.161        0.045            0.049 M
M M
Min (pCi/g)          0.048          0.032          0.044          0.050         0.048          0.048        0.045            0.049 S
M S
SD                    0.066          0.296          0.007          0.001          0.019          0.041          N/A              N/A S
M M
Subsurface Soil      Co-60            Cs-137         Co-60          Cs-137        Co-60           Cs-137      Co-60            Cs-137
La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil
# of Samples          18              18            22              22            25              25          14                14
# of Samples
# >CL                  0               8              0               4            0               0           0                3 M
# >CL Mean (pCi/g)
Mean (pCi/g)          0.078          0.066          0.058          0.064          0.046          0.049        0.048            0.041 M
Median (pCi/g)
Median (pCi/g)        0.052          0.054          0.058          0.065         0.046          0.049        0.048            0.042 M
Max (pCi/g)
Max (pCi/g)          0.516          0.161          0.080          0.130          0.055          0.054         0.050            0.051 M
Min (pCi/g)
Min (pCi/g)          0.047          0.033          0.043          0.044          0.025          0.042        0.043            0.027 S
SD Subsurface Soil  
SD                    0.109          0.035          0.010          0.017          0.005          0.003        0.002            0.009 A
# of Samples  
Asphalt                                                                                                        Co-60             Cs-137
# >CL Mean (pCi/g)
# of Samples                                                                                                      10                10
Median (pCi/g)
# >CL                                                                                                              0                 1 M
Max (pCi/g)
Mean (pCi/g)                                                                                                    0.053            0.051 M
Min (pCi/g)
Median (pCi/g)    None Taken                      None Taken                  N None  Taken                      0.054            0.053 M
SD Asphalt
Max (pCi/g)                                                                                                      0.062            0.057 M
# of Samples
Min (pCi/g)                                                                                                      0.042            0.037 S
# >CL Mean (pCi/g)
SD                                                                                                              0.006            0.006 S
Median (pCi/g)
Surface Scans
Max (pCi/g)
% Scanned M
Min (pCi/g)
Mean Scan (cpm)  No Scanning Performed P                  No Scanning Performed        N Scanning Peerformed No                                No Scanning Peerformed M
SD Surface Scans
Max Scan (cpm) a        MDC vaalue used for anaalytical results less l than MDC.
% Scanned Mean Scan (cpm)
2-50
Max Scan (cpm) ng Water React ation Plan Table 2-8 Survey Unit 66,869 m2 G-3 Coal Plan Co-60 3
0 0.070 0.075 0.078 0.057 0.011 Co-60 4
0 0.060 0.056 0.084 0.047 0.016 Co-60 None Taken 1%
5,550 6,700 or Non-Impact t L4012103 nt Grounds Cs-137 3
1 0.082 0.083 0.092 0.071 0.011 Cs-137 4
1 0.048 0.038 0.081 0.036 0.022 Cs-137 ed Open Land Survey Unit 82,894 m2 Coal Pile Grou Co-60 3
0 0.071 0.072 0.084 0.057 0.014 Co-60 3
0 0.061 0.063 0.068 0.052 0.008 Co-60 None Taken 1%
5,050 8,800 2-47 Survey Units -
L4012105 1
nds C
G Cs-137 3
1 0.061 0.060 0.068 0.055 0.006 Cs-137 3
1 0.042 0.040 0.056 0.030 0.013 Cs-137 1
8 1
- Characterizat Survey Unit L 111,899 m2 Capped Ash Im Grounds Co-60 3
0 0.082 0.084 0.090 0.072 0.009 Co-60 4
0 0.081 0.083 0.102 0.056 0.021 Co-60 2
0 0.073 0.073 0.082 0.065 0.012 1%
8,340 12,000 tion Survey Su L4012106 8
mpoundment G H
Cs-137 3
2 0.100 0.099 0.121 0.079 0.021 Cs-137 4
2 0.088 0.084 0.130 0.054 0.037 Cs-137 2
0 0.062 0.062 0.084 0.040 0.031 ummary Survey Unit L 81,254m2 Grounds East of Highway 35 Co-60 3
0 0.080 0.079 0.089 0.072 0.009 Co-60 3
0 0.081 0.069 0.106 0.068 0.022 Co-60 None Tak 1%
8,000 9,080 L4012107 f
Cs-137 3
3 0.264 0.263 0.463 0.065 0.199 Cs-137 3
2 0.068 0.057 0.091 0.056 0.020 Cs-137 ken


La Crosse Boilin L                    ng Water Reacttor L
L L
License    Termination Plan R
R La Crosse Boilin License Termin Revision 0 Tabl ng Water React ation Plan le 2-8 (continue S
Revision    0 T
S M
Table      2-11      Class 1 Concretee, Asphalt, Sed            diment and Soill Samples - Tesst America Lab boratory Analyysis (pCi/g)
M M
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
M SD S
L1010101-CJ-GS-002-SSS                                                        0.024                        0 0.020          0.233          0 0.056  0.161  00.066                              0.058 L
M M
L1010101-CJ-GS-009-SSS                                                        0.040                        0 0.020          0.185          0 0.056  0.181  00.050                              0.042 L
M M
L1010101-CJ-GS-010-SSS                                                        0.286                        0 0.025          0.413          0 0.062  0.247  00.057                              0.051 L
SD A
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
M M
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
M M
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
SD S
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
M M
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
or ed)
L1010102-CJ-GS-013-SSB                                                        0.030                        0 0.016          0.021 0              0 0.044  0.170  00.041                              0.036 L
Non-I urvey Unit Surface Area Description urface Soil of Samples
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
>CL Mean (pCi/g)
L1010102-QJ-GS-001-SSS                                                        0.022                        0 0.015          0.018 0              0 0.036  0.113  00.042                              0.039 L
Median (pCi/g)
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
Max (pCi/g)
L1010103-CJ-GS-002-SSB                                                        0.011                        0 0.017          0.021 0              0 0.044  0.181  00.046                              0.044 L
Min (pCi/g)
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
D ubsurface Soil of Samples  
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
>CL Mean (pCi/g)
L1010103-QJ-GS-001-SSS                                                        0.025                        0 0.015          0.020 0              0 0.046  0.174  00.047                              0.043 L
Median (pCi/g)
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
Max (pCi/g)
L1010103-QJ-GS-002-SSS                                                        0.019                        0 0.017          0.017 0              0 0.040  0.139  00.045                              0.024 L
Min (pCi/g)
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
D Asphalt of Samples
L1010103-QJ-GS-003-SSS                                                        0.023                        0 0.019          0.091         0 0.057  0.186  00.063                              0.052 L
>CL Mean (pCi/g)
L1010104-CJ-GS-003-SSB                                                        0.015                        0 0.008          0.013 0              0 0.032  0.078  00.036                              0.034 L
Median (pCi/g)
L1010104-CR-PA-007- -AV                                                      0.021                        0 0.014          0.016 0              0 0.042  0.141  00.044                              0.040 L
Max (pCi/g)
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.
Min (pCi/g)
2-51
D urface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm)
Impacted Open Survey Unit 9,444 m2 Hwy 35/Railro Way Grounds Co-60 3
0 0.079 0.075 0.095 0.068 0.014 Co-60 3
0 0.086 0.092 0.107 0.060 0.024 Co-60 None Taken 1%
8,124 9,200 2-48 n Land Survey L4012108 1
ad Right of B A
Cs-137 3
2 0.119 0.108 0.156 0.093 0.033 Cs-137 3
2 0.189 0.091 0.409 0.067 0.191 Cs-137 Units - Chara Survey Unit L 100 m2 Background Soi Area (inside L40 Co-60 17 0
0.087 0.086 0.101 0.077 0.007 Co-60 None Ta Co-60 None Ta No Scanning P acterization Sur L4012109 ils Test 012108)
Cs-137 17 17 0.160 0.161 0.268 0.059 0.059 Cs-137 aken Cs-137 aken Performed rvey Summaryy


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
L L
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
R R
    # off Samples              13                  13                10                    10
L L
    # >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
L L
    # off Samples              16                  16                7                      7
L L
    # >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
L L
    # off Samples                6                  6                6                      6
L L
    # >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
L L
    % Scanned S                50%                                                    50%
a b
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 License Termin Revision 0 Radionuclide L3012103-QJ-GS-001-S L3012103-QJ-GS-001-S L3012105-Genoa Coal P L3012105-CR-GS-002-L3012105-QJ-GS-001-S L3012105-QJ-GS-001-S L3012106-QJ-GS-001-S L3012106-QJ-GS-001-S L3012107-QJ-GS-001-S L3012107-QJ-GS-001-S L3012108-QJ-GS-001-S L3012108-QJ-GS-001-S a
Bold values b
Survey units ng Water React ation Plan H-3 C
SB 4.390 1
SS 3.570 0.
Pile
-SS 0.533 0.
SB SS SB 14.600 0.
SS 0.813 0.
SB SS 1.420 0.
SB 2.350 0.
SS 6.490 0.
indicate concentration g originally classified as tor Table 2-9 C-14 Fe-55 N
.230 3.430 1
.671 2.790 1
.675 2.130 1
.713 2.300 2
.713 3.550 2
.719 3.610 2
.705 1.920 3
.728 2.260 3
greater than MDC. Itali Class 3 at time of samp Non Impa Ni-59 Co-60 N
.470 0.026 2
.870 0.027 3
0.018
.730 0.025 2
0.026 0.030
.370 0.037 3
.560 0.037 3
0.019
.800 0.025 3
.110 0.018 4
.200 0.030 4
icized values indicate M ple acted Coal Pile Ni-63 Sr-90 N
.140 0.321 0
.380 0.391 0
0
.950 0.289 0
0 0
.950 0.348 0
.580 0.338 0
0
.940 0.293 0
.440 0.278 0
.710 0.271 0
MDC value 2-49 and Soil Samp Nb-94 Tc-99 Cs 0.018 0.820 0
0.022 0.628 0
0.022 0
0.016 0.587 0
0.020 0
0.020 0
0.030 0.611 0
0.028 0.616 0
0.013 0
0.019 0.593 0
0.016 0.604 0
0.020 0.576 0
ples - Test Ame s-137 Pm-147 Eu 0.024 0.714 0
0.018 0.847 0
0.019 0
0.018 0.698 0
0.023 0
0.028 0
.319 1.500 0
.096 0.826 0
0.021 0
.018 1.450 0
.033 1.310 0
.182 0.770 0
erica Laborator u-152 Eu-154 Eu 0.071 0.190 0
0.060 0.167 0
0.052 0.152 0
0.051 0.137 0
0.049 0.166 0
0.072 0.199 0
0.115 0.223 0
0.079 0.232 0
0.045 0.115 0
0.049 0.156 0
0.041 0.128 0
0.059 0.176 0
ry Analysis (pC u-155 Np-237 Pu 0.095 0.025 0
0.096 0.024 0
0.048 0.056 0.023 0
0.055 0.074 0.080 0.035 0
0.112 0.027 0
0.038 0.048 0.040 0
0.044 0.030 0
0.060 0.020 0
Ci/g) u-238 Pu-239/240 Pu 0.046 0.015 1
0.040 0.021 1
0.036 0.029 1
0.036 0.014 2
0.044 0.026 2
0.021 0.024 2
0.026 0.021 2
0.028 0.029 2
u-241 Am-241 A
1.730 0.032 0
1.650 0.025 0
0.041 1.670 0.018 0
0.048 0.061 2.550 0.019 0
2.740 0.025 0
0.034 2.580 0.020 0
2.670 0.017 0
2.740 0.015 0
Am-243 Cm-243/244 0.022 0.010 0.024 0.019 0.025 0.006 0.034 0.006 0.013 0.019 0.035 0.006 0.036 0.017 0.024 0.015


La Crosse Boilin L                   ng Water Reacttor L
L L
License    Termination Plan R
R S
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
S M
L2011101-CJ-GS-001-S SM                                    0.096                0 0.011            0.137            0 0.041  0.098  00.033                              0.031 L
M M
L2011101-CR-PA-003--AV                                    0.023                0 0.016            0.017 0                0 0.039  0.131  00.039                              0.038 L
M S
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
S M
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
M M
L2011101-QJ-GS-001-S SS                                    0.012                0 0.020            0.080           0 0.060  0.188  00.091                              0.042 L
M S
L2011101-QQ-GS-001--SB                                    0.017                0 0.012            0.013 0                0 0.040  0.127  00.037                              0.031 L
A M
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
M M
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
M S
L2011101-QQ-PA-001--AV                                    0.022                0 0.015            0.015 0                0 0.046  0.135  00.042                              0.040 L
S M
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
M a
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
La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil
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
# of Samples
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.
# >CL Mean (pCi/g)
2-53
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Subsurface Soil
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Asphalt
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Surface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm) a MDC va ng Water React ation Plan Table 2-10 Survey Unit 1,992 m2 Reactor Buil WGTV, Vent Grounds Co-60 12 2
0.080 0.058 0.287 0.048 0.066 Co-60 18 0
0.078 0.052 0.516 0.047 0.109 None Taken No Scanning P alue used for ana or Impacted Cla t L1010101 lding, WTB, tilation Stack Cs-137 12 12 0.215 0.100 1.070 0.032 0.296 Cs-137 18 8
0.066 0.054 0.161 0.033 0.035 Performed alytical results l ass 1 Open Land Survey Unit 2,315 m2 Turbine, Office Generator Buil Grounds Co-60 2
0 0.049 0.049 0.054 0.044 0.007 Co-60 22 0
0.058 0.058 0.080 0.043 0.010 None Taken No Scanning P less than MDC.
2-50 d Survey Units L1010102 1
e, Diesel ding L
M G
Cs-137 2
0 0.050 0.050 0.051 0.050 0.001 Cs-137 22 4
0.064 0.065 0.130 0.044 0.017 N
erformed N
s - Characteriz Survey Unit L 1,749 m2 LSA Building, Maintenance Ea Grounds Co-60 7
0 0.059 0.050 0.099 0.048 0.019 Co-60 25 0
0.046 0.046 0.055 0.025 0.005 None Taken No Scanning Pe zation Survey S L1010103 2
at Shack N
Cs-137 7
1 0.069 0.054 0.161 0.048 0.041 Cs-137 25 0
0.049 0.049 0.054 0.042 0.003 erformed Summary Survey Unit L 2,387 m2 North LSE Grou Co-60 1
0 0.045 0.045 0.045 0.045 N/A Co-60 14 0
0.048 0.048 0.050 0.043 0.002 Co-60 10 0
0.053 0.054 0.062 0.042 0.006 No Scanning Pe L1010104 unds Cs-137 1
0 0.049 0.049 0.049 0.049 N/A Cs-137 14 3
0.041 0.042 0.051 0.027 0.009 Cs-137 10 1
0.051 0.053 0.057 0.037 0.006 erformed


L La Crosse Boilin ng Water Reactor L
L L
License Termination Plan R
R 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
L L
            # of Samples            3                3                                        5              5
L L
            # >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
L L
            # of Samples            3                3                                        4              4
L L
            # >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
L L
            # of Samples            3                3                                        7              7
L L
            # >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
L L
                % Scanned                  1%%                                                      1%
L L
Mean M    Scan (cpm)  9,000                          No Scanning Performed                  5,8900 Max M Scan (cpm)      10,000                                                                6,4000 2-54
L L
L L
L L
L L
a La Crosse Boilin License Termin Revision 0 Radionuclide L1010101-CJ-GS-002-S L1010101-CJ-GS-009-S L1010101-CJ-GS-010-S L1010101-QJ-GS-001-S L1010101-QJ-GS-001-S L1010101-QJ-GS-002-S L1010101-QJ-GS-002-S L1010102-CJ-FC-001-C L1010102-CJ-GS-013-S L1010102-QJ-GS-001-S L1010102-QJ-GS-001-S L1010102-QJ-GS-002-S L1010103-CJ-GS-002-S L1010103-QJ-SL-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-002-S L1010103-QJ-GS-002-S L1010103-QJ-GS-003-S L1010103-QJ-GS-003-S L1010104-CJ-GS-003-S L1010104-CR-PA-007-L1010104-QQ-PA-001-L1010104-QR-GS-001-a Bold values ng Water React ation Plan T
H-3 C
SS SS SS SB 0.364 0
SS 0.441 0.
SB 0.377 0.
SS 1.380 0.
CV 1.710 0.
SB SB 8.740 0.
SS SB 24.700 0.
SB SM 0.354 0
SB 3.260 0.
SS SB 0.649 0.
SS SB 0.654 0.
SS SB
-AV
-AV
-SB indicate concentration g tor Table 2-11 C
C-14 Fe-55 N
.896 2.430 1
.676 2.190 1
.679 2.150 1
.677 4.190 2
.727 1.650 2
.726 2.120 2
.715 2.230 2
.453 0.689 0
.715 1.830 2
.702 2.100 2
.717 2.340 2
greater than MDC. Itali lass 1 Concrete Ni-59 Co-60 N
0.024 0.040 0.286
.850 0.024 3
.900 0.018 3
.750 0.017 2
.010 0.015 3
.630 0.106 3
0.030
.620 0.015 4
0.022
.760 0.021 3
0.011 0.711 0.136 1
.850 0.017 4
0.025
.620 0.014 3
0.019
.630 0.012 3
0.023 0.015 0.021 0.025 0.017 icized values indicate M e, Asphalt, Sed Ni-63 Sr-90 N
0 0
0
.040 0.335 0
.040 0.440 0
.930 0.338 0
.320 0.357 0
.920 0.292 0
0
.000 0.310 0
0
.920 0.316 0
0
.090 0.132 0
.240 0.333 0
0
.710 0.325 0
0
.660 0.300 0
0 0
0 0
0 MDC value.
2-51 diment and Soil Nb-94 Tc-99 Cs 0.020 0
0.020 0
0.025 0
0.015 0.579 0
0.012 0.587 0
0.011 0.620 0
0.010 0.521 0
0.022 0.536 0
0.016 0
0.011 0.539 0
0.015 0
0.014 0.537 0
0.017 0
0.018 0.432 0
0.011 0.606 0
0.015 0
0.012 0.645 0
0.017 0
0.009 0.557 0
0.019 0
0.008 0
0.014 0
0.025 0
0.011 0
l Samples - Tes s-137 Pm-147 Eu
.233 0
.185 0
.413 0
0.020 0.800 0
.147 3.170 0
.149 0.772 0
.059 0.978 0
.352 1.290 0
0.021 0
0.012 0.961 0
0.018 0
0.016 0.722 0
0.021 0
.136 0.360 0
0.015 0.740 0
0.020 0
0.012 0.838 0
0.017 0
0.011 0.713 0
.091 0
0.013 0
0.016 0
0.028 0
0.012 0
st America Lab u-152 Eu-154 Eu 0.056 0.161 0
0.056 0.181 0
0.062 0.247 0
0.050 0.143 0
0.034 0.112 0
0.040 0.109 0
0.033 0.096 0
0.061 0.239 0
0.044 0.170 0
0.030 0.101 0
0.036 0.113 0
0.043 0.139 0
0.044 0.181 0
0.054 0.199 0
0.036 0.117 0
0.046 0.174 0
0.029 0.103 0
0.040 0.139 0
0.029 0.092 0
0.057 0.186 0
0.032 0.078 0
0.042 0.141 0
0.058 0.218 0
0.038 0.132 0
boratory Analy u-155 Np-237 Pu 0.066 0.050 0.057 0.044 0.019 0
0.044 0.006 0
0.040 0.019 0
0.036 0.016 0
0.062 0.029 0
0.041 0.028 0.028 0
0.042 0.042 0.032 0
0.046 0.049 0.018 0
0.039 0.026 0
0.047 0.034 0.020 0
0.045 0.034 0.040 0
0.063 0.036 0.044 0.061 0.032 ysis (pCi/g) u-238 Pu-239/240 Pu 0.046 0.023 1
0.039 0.023 1
0.041 0.022 1
0.040 0.016 2
0.041 0.028 2
0.040 0.026 2
0.042 0.029 2
0.015 0.015 0
0.029 0.017 1
0.034 0.024 2
0.028 0.028 2
u-241 Am-241 A
0.058 0.042 0.051 1.970 0.015 0
1.830 0.016 0
1.950 0.017 0
2.090 0.020 0
2.490 0.018 0
0.036 2.780 0.015 0
0.039 2.660 0.015 0
0.044 0.867 0.008 0
1.430 0.009 0
0.043 2.570 0.018 0
0.024 2.470 0.018 0
0.052 0.034 0.040 0.050 0.032 Am-243 Cm-243/244 0.023 0.021 0.021 0.019 0.029 0.014 0.017 0.022 0.019 0.021 0.020 0.021 0.021 0.018 0.019 0.008 0.024 0.005 0.024 0.014 0.022 0.005


La Crosse Boilin L                    ng Water Reacttor L
La Cross License T Revision Tabl Sur Sur
License    Termination Plan R
# of
Revision    0 Table 2-155          Class 3 Asp      phalt, Sedimentt and Soil Samp  ples - Test Am merica Laboratoory Analysis (ppCi/g)
# >C Mea Med Max Min SD Sub
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
# of
L3012101-CR-GC-001- -CV                                                      0.028                        0 0.030        0.026 0              0 0.043  0.221  00.059                              0.053 L
# >C Mea Med Max Min SD Asp
L3012101-CR-GC-002- -CV                                                      0.035                        0 0.026        0.033 0              0 0.062  0.271  00.056                              0.055 L
# of
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
# >C Mea Med Max Min SD Sur
L3012101-CR-GS-003- -SS                                                      0.025                        0 0.017        0.113          0 0.052  0.157  00.059                              0.052 L
% S Mea Max se Boiling W Termination n 0 le 2-12 Im rvey Unit Surface Area Description rface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) bsurface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) phalt f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) rface Scans Scanned an Scan (cpm) x Scan (cpm)
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
Water Reactor Plan mpacted Cla Sur 7,211 m2 LACBWR
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
: Building, House, W Co-60 13 0
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
0.073 0.077 0.106 0.053 0.016 Co-60 16 1
L3012104-CR-GS-002- -SM                                                      0.015                        0 0.013        0.066          0 0.035  0.128  00.047                              0.036 L
0.052 0.046 0.112 0.040 0.018 Co-60 6
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
0 0.051 0.051 0.054 0.047 0.002 50%
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
7,500 to 8,0 11,500 to 12 r
ass 2 Open L S
rvey Unit L201 R
Adm LACBW Warehouse Gr 0
3 7
6 3
6 0
2 6
2 0
8 0
4 7
2 00 2,000 2-52 Land Surve Summary 11101 ministration WR Crib rounds Cs-137 13 8
0.090 0.100 0.139 0.041 0.030 Cs-137 16 2
0.049 0.048 0.088 0.034 0.012 Cs-137 6
0 0.051 0.051 0.054 0.047 0.003 ey Units - C Sur 6,785 m2 G-3 Crib Circ. Wa Area Sout Co-60 10 0
0.064 0.064 0.081 0.052 0.009 Co-60 7
0 0.049 0.048 0.055 0.042 0.004 Co-60 6
0 0.056 0.057 0.059 0.049 0.003 1
Characteriza rvey Unit L201 b House, ater Discha th of LSE Fe 0
4 4
2 9
0 9
8 5
2 4
0 6
7 9
9 3
50%
7,500 to 8,000 11,500 to 12,00 ation Surve 11102 LACBWR arge Line, ence Cs-137 10 6
0.065 0.054 0.200 0.030 0.049 Cs-137 7
2 0.038 0.033 0.052 0.029 0.009 Cs-137 6
3 0.048 0.051 0.055 0.009 0.008 0
00 ey


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)
L L
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)
R R
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
L L
L L
L L
L L
L L
L L
L a
La Crosse Boilin License Termin Revision 0 Radionuclide L2011101-CJ-GS-001-S L2011101-CR-PA-003-L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QQ-GS-001-L2011101-QQ-GS-001-L2011101-QQ-GS-002-L2011101-QQ-PA-001-L2011102-QQ-GS-001-L2011102-QQ-GS-001-L2011102-QQ-GS-002-L2011102-QQ-PA-001-a Bold val ng Water React ation Plan H-3 C
SM
-AV SB 0.518 0.
SM 2.040 0.
SS
-SB
-SS 11.810 0.
-SB 2.500 0.
-AV
-SB 1.370 1
-SS 0.533 0.
-SB 0.525 0.
-AV lues indicate con tor Table 2 C-14 Fe-55 N
.727 2.290 2
.707 2.240 2
.726 2.590 2
.731 1.940 2
.560 2.260 3
.713 2.330 2
.702 3.890 2
ncentration grea 2-13 Class 2 Ni-59 Co-60 N
0.096 0.023
.660 0.016 4
.950 0.049 4
0.012 0.017
.600 0.035 3
.680 0.017 3
0.022
.040 0.007 4
.820 0.019 4
.880 0.031 3
0.027 ater than MDC.
Asphalt, Sedim Ni-63 Sr-90 N
0 0
.030 0.273 0
.140 0.523 0
0 0
.720 0.255 0
.870 0.314 0
0
.390 0.291 0
.300 0.361 0
.950 0.327 0
0 Italicized value 2-53 ment and Soil S Nb-94 Tc-99 Cs 0.011 0
0.016 0
0.014 0.643 0
0.018 0.585 0
0.020 0
0.012 0
0.035 0.532 0
0.014 0.616 0
0.015 0
0.018 0.537 0
0.014 0.595 0
0.016 0.568 0
0.017 0
es indicate MDC Samples - Test s-137 Pm-147 Eu
.137 0
0.017 0
0.015 0.705 0
.107 0.615 0
.080 0
0.013 0
.103 0.779 0
0.016 0.697 0
0.015 0
0.021 0.672 0
0.014 0.772 0
0.018 0.717 0
0.018 0
C value.
America Labo u-152 Eu-154 Eu 0.041 0.098 0
0.039 0.131 0
0.033 0.108 0
0.048 0.178 0
0.060 0.188 0
0.040 0.127 0
0.097 0.205 0
0.037 0.119 0
0.046 0.135 0
0.044 0.173 0
0.039 0.111 0
0.052 0.183 0
0.051 0.142 0
oratory Analysi u-155 Np-237 Pu 0.033 0.039 0.040 0.022 0
0.049 0.026 0
0.091 0.037 0.102 0.023 0
0.041 0.019 0
0.042 0.055 0.031 0
0.045 0.017 0
0.051 0.022 0
0.038 is u-238 Pu-239/240 Pu 0.028 0.025 2
0.045 0.021 3
0.037 0.024 2
0.039 0.016 2
0.026 0.018 2
0.036 0.026 2
0.028 0.020 1
u-241 Am-241 A
0.031 0.038 2.470 0.015 0
3.100 0.037 0
0.042 0.031 2.800 0.019 0
2.920 0.020 0
0.040 2.680 0.029 0
2.880 0.026 0
1.710 0.010 0
0.036 Am-243 Cm-243/244 0.022 0.019 0.036 0.034 0.015 0.015 0.028 0.016 0.028 0.024 0.034 0.021 0.028 0.006


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/
L L
i/g)   (pCi/g)     (pCi/g))    (pCi/g)     (pCi/g)
R La Crosse Boilin License Termin Revision 0 S
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/
S M
i/g)    (pCi/g)      (pCi/g))    (pCi/g)    (pCi/g)
M M
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
M S
S M
M M
M S
C M
M M
M S
S M
M ng Water React ation Plan Table 2-14 urvey Unit Surface Area Description urface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D ubsurface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D Concrete/Asphalt of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D urface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm) or Impacted Cla Survey Unit 24,042 m2 North End of Lic Co-60 3
0 0.070 0.076 0.077 0.058 0.011 Co-60 3
0 0.051 0.053 0.054 0.046 0.004 Co-60 3
0 0.031 0.031 0.035 0.028 0.003 1%
9,000 10,000 ass 3 Open Land t L3012101 censed Site Cs-137 3
0 0.073 0.072 0.083 0.065 0.009 Cs-137 3
0 0.051 0.052 0.052 0.051 0.001 Cs-137 3
0 0.029 0.027 0.033 0.026 0.004 2-54 d Survey Units Survey Unit 11,711 m2 Transmission Swi Co-60 None T Co-60 None T Co-60 None Taken No Scanning s - Characteriz L3012102 3
tchyard Area P
G Cs-137 Taken Cs-137 Taken Cs-137 Performed zation Survey S Survey Unit L 31,012 m2 Plant Access, ISF Grounds Co-60 5
0 0.063 0.064 0.078 0.053 0.010 Co-60 4
0 0.072 0.072 0.100 0.046 0.023 Co-60 7
0 0.062 0.055 0.080 0.047 0.013 1%
5,890 6,400 Summary L3012109 SI Haul Road Cs-137 5
5 0.152 0.143 0.267 0.075 0.078 Cs-137 4
0 0.066 0.059 0.101 0.045 0.025 Cs-137 7
0 0.059 0.052 0.079 0.028 0.019 0
0  


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)
L L
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)
R R
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
L L
L L
L L
L L
L L
L a
La Crosse Boilin License Termin Revision 0 Radionuclide L3012101-CR-GC-001-L3012101-CR-GC-002-L3012101-CR-GC-003-L3012101-CR-GS-003-L3012101-QQ-GS-001-L3012101-QQ-GS-001-L3012101-QQ-SL-001-L3012104-CR-GS-002-L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S a
Bold values ng Water React ation Plan H-3 C
-CV
-CV
-CV 0.
-SS
-SB 18.400 0.
-SS 15.500 0.
-SM 0.364 0.
-SM SB 2.160 0.
SM 2.890 0.
SS 2.190 0.
indicate concentration g tor Table 2-15 C-14 Fe-55 N
.669 2.180 2
.717 2.390 2
.708 2.330 2
.342 2.710 0
.670 1.950 1
.672 2.720 1
.676 4.240 1
greater than MDC. Itali 5
Class 3 Asp Ni-59 Co-60 N
0.028 0.035
.020 0.031 3
0.025
.870 0.016 5
.660 0.020 3
0.739 0.022 1
0.015
.750 0.021 3
.990 0.037 3
.880 0.029 3
icized values indicate M phalt, Sediment Ni-63 Sr-90 N
0 0
.590 0.374 0
0
.640 0.309 0
.890 0.295 0
.090 0.152 0
0
.060 0.325 0
.500 0.298 0
.300 0.329 0
MDC value 2-55 t and Soil Samp Nb-94 Tc-99 Cs 0.030 0
0.026 0
0.027 0.521 0
0.017 0
0.014 0.550 0
0.017 0.603 0
0.017 0.360 0
0.013 0
0.018 0.469 0
0.020 0.651 0
0.020 0.631 0
ples - Test Am s-137 Pm-147 Eu 0.026 0
0.033 0
0.027 1.480 0
.113 0
0.015 0.899 0
.059 1.090 0
0.020 0.333 0
.066 0
0.025 0.818 0
.094 0.818 0
.138 0.667 0
merica Laborato u-152 Eu-154 Eu 0.043 0.221 0
0.062 0.271 0
0.056 0.249 0
0.052 0.157 0
0.036 0.128 0
0.047 0.116 0
0.042 0.153 0
0.035 0.128 0
0.053 0.160 0
0.074 0.217 0
0.068 0.181 0
ory Analysis (p u-155 Np-237 Pu 0.059 0.056 0.069 0.025 0
0.059 0.036 0.039 0
0.054 0.028 0
0.034 0.009 0
0.047 0.054 0.022 0
0.071 0.006 0
0.080 0.020 0
pCi/g) u-238 Pu-239/240 Pu 0.046 0.018 1
0.035 0.022 2
0.028 0.022 2
0.016 0.013 0
0.027 0.021 1
0.031 0.017 1
0.043 0.026 1
u-241 Am-241 A
0.053 0.055 1.690 0.019 0
0.052 2.590 0.023 0
2.640 0.019 0
0.797 0.009 0
0.036 1.610 0.016 0
1.560 0.016 0
1.580 0.019 0
Am-243 Cm-243/244 0.021 0.006 0.029 0.027 0.021 0.006 0.009 0.011 0.018 0.016 0.016 0.015 0.019 0.021


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)
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 T
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
B1001101-C Result (pCi/g) 3.950
-0.162 9.130 0.000 11.500 39.300 6.910
-0.120 0.024 7500 2.580 0.266 0.369 0.009 0.176 0.132 0.902 0.407 0.028 0.0579 B1001101-C Result (pCi/g) 7.240
-0.492 9.450 0.000 57.700 202.000 34.500 0.191
-0.189 614.000 0.768 0.335
-0.429 0.000 0.528 0.491 7.470 1.450 0.052 0.0879 Water Reactor Plan Table 2-16 CJ-FC-001-CV 0 MDC (pCi/g)
(p 1.590 1
1.400 0
16.000 7
0.254 0
0.377 1
0.402 4
0.043 0
0.312 0
0.566 0
7.090 78 9.020 5
2.410 0
4.440 1
0.042 0
0.056 0
0.048 0
2.700 1
0.048 0
0.046 0
0.0302 0.
CJ-FC-003-CV 0 MDC (pCi/g)
(p 1.360 1
1.460 0
9.040 4
0.365 0
0.333 5
0.593 21 0.040 3
0.392 0
0.586 0
0.732 64 2.870 1
5.460 0
1.510 0
0.041 0
0.058 0
0.030 0
2.640 2
0.047 0
0.027 0
0.0408 0.
r Concrete 0-1/2 B
R pCi/g)
(p
.350 9
.793
-0
.880 10
.325 0
.250 0
.110 3
.680 0
.189 0
.330 0
1.000 9
.230
-0
.398 0
.140 0
.021
-0
.065
-0
.055
-0
.660
-1
.107 0
.030 0
0371
-0 0-1/2 B
R pCi/g)
(p
.580 12
.806
-0
.950 6
.806 0
.880 0
1.100 2
.330 0
.203
-0
.330
-0 4.000 2
.300 0
.536 0
.914
-0
.016
-0
.111
-0
.104
-0
.160
-1
.250 0
.033 0
0496 0.
2-56 Core Isotop B1001101-CJ-FC Result MD pCi/g)
(pCi/
9.720 1.56 0.346 1.44 0.400 21.3 0.000 0.26 0.082 0.16 3.850 0.42 0.162 0.05 0.001 0.13 0.076 0.52 9.660 0.15 0.039 0.51 0.025 1.26 0.071 0.37 0.002 0.04 0.017 0.06 0.006 0.04 1.510 2.50 0.011 0.03 0.014 0.03
.0081 0.04 B1001101-CJ-FC Result MD pCi/g)
(pCi/
2.600 1.57 0.566 1.39 6.160 14.3 0.000 0.25 0.435 0.05 2.990 0.40 0.304 0.05 0.001 0.15 0.129 0.59 2.450 0.11 0.045 0.34 0.179 1.02 0.007 0.28 0.010 0.05 0.005 0.06 0.004 0.04 1.320 2.66 0.018 0.03 0.009 0.03
.0000 0.01 pic Analysis C-001-CV 1/2-1 DC


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
/g)
pCi/L)
(pCi/g) 60 1.950 40 0.806 300 10.200 64 0.151 68 0.078 25 0.474 51 0.041 39 0.078 26 0.310 52 1.100 11 0.055 60 0.171 76 0.118 45 0.017 66 0.026 49 0.018 00 1.360 37 0.020 30 0.019 478 0.0094 C-003-CV 1/2-1 DC
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
/g)
License Termination Plan R
(pCi/g) 70 2.240 90 0.765 300 6.960 57 0.157 57 0.096 00 0.392 51 0.052 53 0.086 96 0.339 13 0.348 46 0.154 20 0.383 82 0.164 51 0.018 64 0.029 47 0.017 60 1.480 38 0.024 30 0.016 68 0.0047 s Results B1001 Result (pCi/g) 3.640
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)
-0.270 0
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.
11.300 0.000 0.800 4.860 11.600
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)
-0.017
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.
-0.104 450.00 0.173
2-61
-0.008 0.145
-0.010 0.575 0.715 13.200 0.550
-0.036 4
0.1540 B1001 Result (pCi/g) 4.490
-0.555 7.600 0.000 28.100 88.300 11.000
-0.016 0.153 213.00 0.162 0.557 0.108
-0.020 0.413 0.336
-7.720 0.614 0.052 7
-0.0547 101-CJ-FC-002 t
MDC (pCi/g) 1.620 0
1.410 0
9.950 0.289 0.117 0.492 0
0.046 7
0.165 4
0.564 0
0.597 2.150 8
1.460 0.837 0
0.042 0.617 0.466 0
23.500 0.401 6
0.433 0
0.4670 101-CJ-FC-004 t
MDC (pCi/g) 1.590 5
1.450 7.070 0.276 0
0.190 0
0.467 0
0.045 6
0.264 0.592 0
0.439 1.570 3.070 0.850 0
0.060 0.426 0.325 0
26.000 0.441 0.292 7
0.4320
-CV 0-1/2  


La Crosse Boilin L                  ng Water Reacttor L
(pCi/g) 1.330 0.794 5.540 0.183 0.172 0.581 1.130 0.095 0.322 46.900 0.924 0.820 0.503 0.009 0.436 0.413 15.100 0.419 0.140 0.2600
License  Termination Plan R
-CV 0-1/2  
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.
2-62


La Crosse Boilin L                  ng Water Reacttor L
(pCi/g) 1.420 0.795 4.040 0.467 2.950 9.200 1.070 0.155 0.352 22.200 0.611 0.863 0.138 0.020 0.320 0.265 14.400 0.436 0.136 0.0776
License    Termination Plan R
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


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1001101-C Result (pCi/g) 2.960
License Termination Plan R
-0.077 8.070 2.590 73.900 221.000 32.800
Revision 0 Figuree 2-1 LACBWR Site Map - Open Land Survey Units an nd Classificatioon 2-64
-0.089 0.178 65.700 0.395 0.637 0.011 0.005 0.706 0.489 9.090 1.590 0.048 0.1160 B1001101-C Result (pCi/g) 3.590
-0.246 6.030 0.000
-0.026 2.310 0.146 0.019 0.024 1.410 0.021 0.055 0.003 0.003
-0.004 0.035
-1.890 0.006
-0.002
-0.0036 Water Reactor Plan
-16 (continu CJ-FC-005-CV 0 MDC (pCi/g)
(p 1.520 1
1.410 0
9.770 5
0.267 0
0.372 7
0.427 23 0.043 3
0.531 0
0.562 0
0.569 6
1.240 0
5.650 0
0.699 0
0.015 0
0.065 0
0.035 0
2.540 2
0.045 0
0.031 0
0.0443 0.
CJ-WC-006-CV MDC (pCi/g)
(p 1.640 1
1.490 0
14.500 7
0.257 0
0.207 0
0.396 0
0.038 0
0.141 0
0.556 0
0.153 0
0.434 0
1.270 0
0.336 0
0.045 0
0.043 0
0.033 0
2.360 1
0.036 0
0.031 0
0.0287 0.
r ued)
Co 0-1/2 B
R pCi/g)
(p
.200 4
.810
-0
.230 8
.813 0
.510 0
3.000 4
.170 0
.317
-0
.336
-0
.970 0
.746 0
.831 0
.414 0
.010
-0
.134
-0
.106
-0
.270 0
.273 0
.034
-0 0590 0
1/2-1 R
pCi/g)
(p
.350 0
.836 0
.050 1
.147 0
.240 0
.335 2
.034 0
.060 0
.324
-0
.258 16
.113 0
.137 0
.196 0
.021 0
.016 0
.028
-0
.270
-1
.017 0
.005
-0 0052 0
2-57 oncrete Cor B1001101-CJ-FC Result MD pCi/g)
(pCi/
4.180 1.85 0.701 1.35 8.170 9.87 0.000 0.27 0.075 0.17 4.870 0.43 0.423 0.05 0.015 0.12 0.124 0.54 0.801 0.11 0.001 0.37 0.119 0.92 0.013 0.25 0.017 0.05 0.003 0.05 0.008 0.03 0.337 2.53 0.012 0.01 0.002 0.05
.0000 0.01 B1008101-CJ-Result MD pCi/g)
(pCi/
0.382 0.94 0.053 1.37 1.610 6.55 0.000 0.23 0.662 0.06 2.730 0.35 0.154 0.05 0.000 0.21 0.010 0.57 6.000 0.17 0.034 0.63 0.060 1.20 0.140 0.35 0.003 0.04 0.018 0.06 0.011 0.05 1.120 2.71 0.020 0.04 0.002 0.04
.0062 0.01 re Isotopic A C-005-CV 1/2-1 DC


L La Crosse Boilin ng Water Reactor L
i/g)
License Termination Plan R
(pCi/g) 50 1.520 50 0.733 70 5.340 70 0.165 71 0.080 30 0.570 51 0.063 28 0.074 40 0.307 17 0.172 73 0.005 23 0.245 55 0.148 54 0.016 53 0.023 38 0.008 30 1.510 18 0.017 54 0.022 76 0.0049
Revision 0 Figure 2-2 LACBWR Site Map - Buiildings Identifiication 2-65
-FC-002-CV DC


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
i/g)
(pCi/g) 40 0.559 70 0.794 50 3.370 34 0.151 65 0.131 53 0.355 53 0.041 11 0.066 79 0.335 77 1.780 33 0.056 00 0.239 57 0.215 48 0.022 60 0.033 54 0.019 10 1.480 42 0.027 44 0.017 87 0.0125 Analysis Re B1001 Result (pCi/g) 4.210 0.077 11.700 0.000 2.040 13.400 7.150 0.026 0.083 1490 0.031 0.128 0.737
-0.013 0.029 0.035
-1.380 0.048 0.003
-0.0053 B10 Result (pCi/g) 1.300
-0.296 6.460 0.000 0.974 4.400 0.235 0.016
-0.005 10.000 0.291 0.019 0.101
-0.024 0.042 0.008
-0.194 0.019
-0.001
-0.0056 esults 101-CJ-WC-006 t
MDC
)
(pCi/g) 1.700 1.440 0
9.320 0.263 0.047 0
0.420 0.034 0.154 0.580 0.721 3.660 1.190 1.470 0.044 0.037 0.025 2.650 0.052 0.029 3
0.0419 008101-CJ-FC-0 t
MDC
)
(pCi/g) 1.020 1.440 14.500 0.241 0.142 0.356 0.035 0.141 0.592 0
0.154 0.470 1.410 0.348 0.068 0.057 0.034 2.550 0.051 0.052 6
0.0444 6-CV 0-1/2


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
(pCi/g) 1.440 0.832 5.530 0.230 0.264 1.430 0.703 0.090 0.341 155.000 2.210 0.679 0.896 0.010 0.027 0.026 1.470 0.041 0.011 0.0075 003-CV


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
(pCi/g) 0.713 0.810 7.050 0.171 0.162 0.510 0.041 0.081 0.343 1.130 0.270 0.052 0.208 0.025 0.038 0.017 1.470 0.029 0.023 0.0080


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 Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B100810 Result (pCi/g) 1.200 0.077 6.520 0.000 1.390 4.260 0.216 0.001 0.043 19.800
-0.119
-0.061 0.006 0.014 0.020 0.025
-1.610 0.052
-0.004 0.0100 B1002101-C Result (pCi/g) 0.763
-0.776 3.540 0.000 0.742 3.360 2.410 0.035 0.259 3.630 0.156 0.119 0.159 0.000 0.023 0.000
-0.052 0.020 0.013 0.0048 Water Reactor Plan  
-16 (continu 01-CJ-FC-004-C MDC (pCi/g)
(p 0.990 0
1.430 0
11.500 5
0.229 0
0.095 0
0.339 0
0.040 0
0.143 0
0.599 0
0.166 2
0.580 0
1.370 0
0.376 0
0.065 0
0.052 0
0.042 0
2.610 1
0.034 0
0.032 0
0.0150 0.
CJ-FC-001-CV MDC (pCi/g)
(p 1.000 0
1.410 0
5.670 3
0.228 0
0.069 0
0.333 0
0.050 0
0.149 0
0.564 0
0.150 0
0.420 0
1.400 0
0.335 0
0.045 0
0.061 0
0.049 0
2.820 1
0.015 0
0.029 0
0.0143 0.
r ued)
Co CV B
R pCi/g)
(p
.685 0
.829 0
.820 15
.162 65
.255 95
.492 81
.041 99
.081 0
.350 0
.150 4
.344 0
.296 1
.220 0
.035
-0
.030 0
.028 1
.430 5
.035 3
.006 0
0142 0.
1-1.5 B
R pCi/g)
(p
.638 0
.763 0
.150 7
.159 0
.148 0
.407 5
.250 0
.066
-0
.342 0
.493 2
.236 0
.382 0
.204 0
.018
-0
.035 0
.021 0
.640
-2
.020 0
.018 0
0096 0.
2-58 oncrete Cor B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.820 0.98 0.505 1.41 5.400 13.8 5.500 0.31 5.000 0.42 7.000 0.47 9.800 0.04 0.098 0.47 0.113 0.56 4710 1.69 0.815 5.94
.250 5.46 0.073 2.12 0.012 0.06 0.920 0.62
.280 0.46 5.240 26.7 3.200 0.42 0.406 0.29
.2020 0.42 B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.094 0.91 0.372 1.38 7.770 25.0 0.000 0.25 0.872 0.13 5.730 0.38 0.106 0.04 0.034 0.14 0.032 0.52 2.440 0.14 0.125 0.38 0.271 0.95 0.099 0.32 0.007 0.05 0.004 0.06 0.009 0.04 2.090 2.70 0.017 0.04 0.029 0.02
.0059 0.03 re Isotopic A C-001-CV 0-1/2 DC


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
/g)
(pCi/g) 85 0.637 10 0.850 800 7.430 10 8.690 20 9.600 72 85.000 45 9.600 75 0.149 64 0.333 90 491.000 40 1.410 60 1.980 20 1.280 60 0.023 20 0.511 69 0.537 700 16.200 28 0.989 96 0.310 200 0.2670 C-001-CV 1.5-2 DC


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
/g)
(pCi/g) 17 0.512 80 0.819 000 11.400 59 0.188 38 0.161 88 0.646 41 0.032 42 0.083 28 0.308 46 0.343 83 0.195 56 0.406 26 0.196 52 0.019 61 0.030 41 0.021 00 1.460 41 0.025 29 0.026 331 0.0154 Analysis Re B1002 Result (pCi/g) 0.275
-0.018 0.547 0.000 1.010 0
5.640 0.253 0.029
-0.101 0
3.870 0.039
-0.260 0.077
-0.022 0.017
-0.005 0
-0.984 0.035
-0.018 0
-0.0046 B1002 Result (pCi/g) 1.710 15.400 0
8.960 423.00 300.00 2360 220.00
-0.350 0.792 25400 0.510 4.650 1.060 0.024 3.200 2.580 36.900 9.080 0.305 4
0.4280 esults 2101-CJ-FC-001 t
MDC (pCi/g) 0.931 8
1.440 5.510 0.245 0.149 0.367 0.053 0.102 1
0.507 0.137 0.444 0
1.480 0.272 2
0.064 0.059 5
0.042 4
2.680 0.037 8
0.054 6
0.0366 2101-CJ-FC-002 t
MDC (pCi/g) 1.180 0
1.510 5.860 0
0.446 0
0.762 0.661 0
0.052 0
0.935 0.562 0
4.140 13.700 7.170 7.370 0.042 0.497 0.287 0
24.000 0.682 0.388 0
0.5450
-CV 1/2-1


La Crossse Boiling Water W    Reactorr License Termination T            Plan Revision n0 Figure 2-9 9  Concreete Core Sam mpling Loccations 2-72
(pCi/g) 0.543 0.824 2.840 0.170 0.168 0.633 0.049 0.054 0.289 0.496 0.107 0.859 0.162 0.023 0.033 0.013 1.510 0.031 0.013 0.0066
-CV 0-1/2  


La Crossse Boiling Water W      Reactorr License Termination T            Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-73
(pCi/g) 0.846 2.310 3.640 55.200 30.200 245.000 21.100 0.567 0.373 2650 0.956 4.390 0.988 0.027 0.825 0.713 17.100 2.030 0.286 0.4200


La Crossse Boiling Water W     Reactorr License Termination T            Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-74
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1002101-C Result (pCi/g) 0.846 6.180 5.270 0.000 8.270 175.000 3.520
-0.041 0.165 208.000
-0.280 0.255 0.116
-0.019 0.059 0.056
-0.965 0.238 0.005 0.0018 Water Reactor Plan  
-16 (continu CJ-FC-002-CV 1 MDC (pCi/g)
(p 1.120 0
1.420 1
25.300 11 0.269 0
0.114 0
0.442 18 0.047 0
0.230 0
0.522 0
0.362 21 1.580 0
1.900 0
0.864 0
0.056 0
0.064 0
0.049 0
2.970 1
0.048 0
0.060 0
0.0438 0.
r ued)
Co 1/2-1 B
R pCi/g)
(p
.716 0
.340
-0 1.400 8
.616 0
.907 8
8.300 70
.356 7
.135 0
.312 0
1.700 1
.950 0
.259 0
.205
-0
.017
-0
.046 0
.040 0
.690 1
.080 0
.028
-0 0179 0.
2-59 oncrete Cor B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.836 0.96 0.405 1.44 8.430 17.0 0.000 0.33 8.570 0.14 0.600 0.54 7.000 0.05 0.038 0.21 0.062 0.54 1240 0.81 0.176 2.60 0.090 2.32 0.004 1.71 0.011 0.04 0.105 0.05 0.126 0.03
.500 2.56 0.339 0.04 0.001 0.03
.0175 0.01 re Isotopic A C-003-CV 0-1/2 DC


L La Crosse Boilin ng Water Reactor L
/g)
License Termination Plan R
(pCi/g) 62 0.624 40 0.803 000 8.210 34 0.484 48 0.940 48 7.370 50 0.691 11 0.060 43 0.318 17 129.000 00 0.514 20 0.202 10 1.030 44 0.009 56 0.051 39 0.051 60 1.640 44 0.099 37 0.012 75 0.0203 Analysis Re 0
Revision 0 Figure 2-10 LACBWR Siite - Typical Geeological Crosss-Section 2-75
3 esults


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision se Boiling W Termination n 0 Tab Water Reactor Plan ble 2-17 198 We Radion Mn-Co-Co-Nb-Cs-1 Ce-1 r
License Termination Plan R
83 Groundw ell-Point So nuclide
Revision 0 Figure 2-11 1 Groundwatter Sampling Wells - LACBW WR Site 2-76
-54
-57
-60
-95 137 141 2-60 water Analy outh of Turb A
(p ysis from Te bine Buildin Activity pCi/L) 63.4 6.4 508 21.4 21.7 18.9 emporary ng


LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 2 SITE CHARACTERIZATION
L L
R La Crosse Boilin License Termin Revision 0 Jun H-3 Co-6 Sr-9 Cs-1 a
B Nov H-3 Co-6 Sr-9 Cs-1 a
B ng Water React ation Plan e 2013 MW-20 (pCi/L 572 60 4.00 90 2.05 137 3.97 Bold values indi vember 2013 MW-20 (pCi/L 235 60 4.64 90 1.18 137 4.64 Bold values indi or Table 2 01-A MW-201-B L)
(pCi/L) 2 506 0
5.01 5
2.00 7
3.84 icate concentrati 01-A MW-201-B L)
(pCi/L) 5 150 4
3.80 8
3.73 4
1.90 icate concentrati 2-18 2013 Gr B
MW-202-A (pCi/L) 660 4.76 1.82 4.05 ion greater than B
MW-202-A (pCi/L) 257 5.26 1.18 6.54 ion greater than 2-61 roundwater M MW-202-B MW (pCi/L)
(p 484 4.51 1.43 3.91 n MDC. Italicize MW-202-B MW (pCi/L)
(p 278 5.41 1.61 4.70 n MDC. Italicize onitoring Resu W-203-A MW-2 pCi/L)
(pCi N/A 42 4.95 4.1 2.06 2.0 4.52 4.3 ed values indica W-203-A MW-2 pCi/L)
(pCi 449 23 4.43 3.8 1.87 2.4 4.41 3.9 ed values indica ults 203-B MW-204-i/L)
(pCi/L) 20 397 12 4.36 06 2.18 31 4.11 ate MDC value.
203-B MW-204-i/L)
(pCi/L) 35 193 89 4.52 40 1.18 98 4.77 ate MDC value.
-A MW-204-B (pCi/L) 420 4.26 2.08 3.96
-A MW-204-B (pCi/L) 171 8.24 1.51 7.92


La Crossse Boiling Water W        Reactorr License Termination T            Plan Revision n0 TABLE OF      O CONTE            ENTS
L L
: 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
R J
: 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
G A
: 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
G B
: 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
H C
F N
C N
S N
T C
E E
E P
P 2
P A
a La Crosse Boilin License Termin Revision 0 JUNE 2014 MW-DW3 Gross Alpha 1.26E-01 Gross Beta 1.48E+0 H-3 1.05E+0 C-14 2.79E+0 Fe-55
-2.00E+0 Ni-59 1.83E+0 Co-60 1.02E+0 Ni-63
-1.78E+0 Sr-90 6.09E-01 Nb-94 4.40E-01 Tc-99
-8.28E+0 Cs-137
-5.97E-0 Eu-152 9.48E+00 Eu-154
-5.24E+0 Eu-155
-2.67E+0 Pu-238 2.83E-02 Pu-239/240
-9.61E-02 Pu-241 3.51E+0 Am-241 5.39E-02 a
Bold val ng Water React ation Plan MW-DW4 M
D 1
-1.33E-01 4.44 0
3.13E+00 1.93 2
1.59E+02 1.94 0
0.00E+00
-3.9 01
-3.12E+01
-2.6 1
3.96E+01
-4.7 0
3.94E-01 2.5 00
-6.14E+00
-7.4 1
8.99E-02 8.9 1
1.43E-01
-1.2 00
-7.37E+00
-8.2 1
-3.47E-01
-7.4 0
2.34E+00
-7.4 00 3.16E+00 1.35 00 1.46E+00
-1.5 2
-4.77E-02
-2.2 2
3.36E-02 3.1 0
2.70E+00
-8.3 2
3.42E-02 4.6 lues indicate con tor MW-DW5 MW-DW7 4E+00
-3.78E-01 3E+00 0.00E+00 4E+02 1.23E+02 97E+00
-5.08E+00 66E+01
-3.86E+01 75E+01 2.60E+01 0E+00
-2.42E+00 40E+00
-4.38E+00 99E-02 1.78E-02 26E+00 7.49E-01 26E+00
-9.36E+00 45E-01
-1.83E+00 43E+00
-5.51E+00 5E+00
-4.73E+00 54E-01
-1.07E+02 22E-02 8.22E-02 13E-02 4.07E-01 39E+00 2.62E+00 65E-03
-1.01E-02 ncentration grea Tabl MW-B11R MW B11A 0.00E+00 7.33E 3.59E+00
-2.70E 2.45E+02 1.61E+
9.06E+00 6.83E+
-3.19E+01
-3.75E
-4.16E+00 2.53E+
8.76E-01
-1.94E
-3.57E+00 0.00E+
7.34E-01 6.11E
-6.99E-01 1.53E+
-5.52E+00
-8.46E 1.24E+00 1.84E+
-9.93E-01 1.48E+
1.63E+00
-2.61E 1.60E+00
-4.47E 0.00E+00 4.09E
-2.54E-02
-3.39E
-5.72E+00 8.38E 1.22E-02 8.37E ater than MDC.
le 2-19 2014 W-AR MW-B2
-01
-2.13E+00 6
E-01 1.12E+01 4
+02 1.60E+02 1
+00 1.94E+00
-2 E+01
-9.20E+00
-4
+00
-7.13E+00 3
E+00
-1.39E+00
-1
+00
-7.94E+00 1
E-01 6.52E-01 6
+00 1.77E+00 6
E+00
-7.41E+00
-8
+00 1.37E+00 2
+00 1.07E-01 1
E+00 2.36E+00 1
E+00 1.60E+00
-3 E-02 5.40E-02 8
E-02 3.40E-02 1
E-01 0.00E+00 E-02 3.98E-03 2
Italicized value 2-62 Groundwater MW-B3 MW-200-A 6.46E-01 4.04E+00 4.14E+00 8.66E+00 1.94E+02 5.23E+01 2.05E+00 9.26E+00 4.39E+01 1.93E+01 3.15E+01
-2.18E+0 1.13E+00 1.01E+00 1.50E+00
-1.97E+0 6.12E-01 9.86E-01 6.65E-01 1.08E+00 8.10E+00 3.55E+00 2.14E+00 1.77E-01 1.42E+01 9.71E+00 1.69E+00 5.77E-01 3.17E+00
-3.63E+0 8.29E-02
-1.38E-02 1.46E-01 2.68E-02
-7.39E-01 0.00E+00 2.28E-02 1.72E-01 es indicate MDC Monitoring Re MW-200-B M
20 0
-2.26E-01 3.84 0
-1.79E+00 7.26 1
1.24E+02 7.03 0
4.84E+00 4.84 1
-4.16E+01
-3.20 1
3.32E+01
-1.6 0
-1.27E+00
-6.0 0
-4.69E+00 1.82 1
9.98E-01 6.86 0
8.47E-01 3.73 0
5.08E+00 3.92 1
-3.64E-01 3.10 0
-1.16E+01 4.15 1
5.60E-01
-2.39 0
-3.44E+00
-2.92 2
1.51E-02 5.33 2
-1.57E-02
-6.8 0
4.49E+00
-4.8 1
9.71E-01 9.46 C value.
esults (pCi/L)
MW-01-A MW-201-B 4E-01
-1.04E+00 6E+00
-1.04E+00 3E+01 1.05E+02 4E+00 4.51E+00 0E+01 1.58E+01 7E+01
-7.11E+01 04E-02 1.73E+00 2E+00
-1.91E+00 6E-02 1.02E+00 3E-01 1.80E+00 2E+00 1.17E+00 0E-01
-6.21E-01 5E+00 1.12E+01 9E+00
-2.43E+00 2E+00
-2.60E+00 3E-02
-5.02E-02 86E-03 2.36E-02 85E-01
-1.42E+00 6E-02 3.99E-03 MW-202-A MW 202-1.06E+00 4.07E-4.34E+00 1.49E+
3.36E+02 1.06E+
0.00E+00 4.70E+
-3.26E+00
-4.54E+
2.49E+01
-1.05E+
-8.91E-01 1.02E+
-1.94E+00
-3.73E+
1.12E+00 6.05E-
-3.55E-01 1.04E-3.88E-01 2.73E+
-4.64E-01 2.86E+
4.11E+00 1.08E+
-1.12E+00
-1.18E+
-1.59E+00
-3.49E+
-8.46E-03 1.48E-
-2.27E-02
-4.54E 2.20E+00 2.72E+
1.16E-01 3.92E-W-
B MW-203-A
-01 1.74E+00
-2
+00 2.27E+00 5
+02 2.79E+02 2
+00 4.54E+00 4
+01
-4.95E+01
-4
+01
-2.71E+01
-4
+00 3.48E-02
-9
+00
-3.70E+00
-3
-01 1.17E+00 8
-01 1.59E+00 1
+00 4.36E+00 4
+00 1.48E+00 1
+01
-9.59E-01 4
+00 1.93E+00
-3
+00
-4.91E+00 4
-01
-5.67E-02
-5
-02
-2.27E-02
-3
+00 4.07E+00 1
-02 2.94E-02 7
MW-203-B MW-204-A 2.29E-01 7.58E-01 5.53E+00 2.69E+00 2.79E+02 1.06E+02 4.55E+00 4.66E+00 4.96E+01
-4.03E+01 4.66E+00
-6.22E+00 9.55E-01 1.91E-01 3.80E+00 0.00E+00 8.23E-01 2.01E+00
.50E+00 2.26E-01 4.17E+00 6.95E+00
.39E+00
-3.04E-01 4.99E+00 2.12E+00 3.69E+00 2.36+00 4.05E+00
-4.34E-01 5.87E-02
-5.12E-02 3.95E-02
-2.49E-02
.03E+01 4.07E+00 7.64E-02 1.56E-01 MW-204-B 1.27E+00 0
2.57E-01 2
3.49E+01 0
1.30E+01 1
-3.98E+00 0
-2.47E+01
-2.31E-01 0
-1.97E+00 0
6.11E-01 1.28E+00 0
6.31E+00 1.93E+00 0
7.68E+00 6.06E-01 1.66E+00 2
-9.28E-03 2
6.28E-02 0
-1.89E+00 8.24E-02


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
L L
R S
G G
H C
F N
C N
S N
T C
E E
E P
P P
A a
La Crosse Boilin License Termin Revision 0 September 2014 M
Gross Alpha 8
Gross Beta 2
H-3 3
C-14
-9 Fe-55 9
Ni-59 3
Co-60 2
Ni-63 2
Sr-90
-1 Nb-94
-9 Tc-99
-1 Cs-137 3
Eu-152 2
Eu-154
-3 Eu-155 2
Pu-238 1
Pu-239/240 9
Pu-241 3
Am-241 1
a Bold val ng Water React ation Plan 4
MW-DW5 MW-8.47E-01 3.09E
.96E+00 1.45E
.43E+01 0.00E 9.44E-01
-2.70E 9.39E+00
-3.10E
.13E+00 1.64E
.17E+00 1.32E
.79E+00 2.48E 1.06E+00 5.90E 9.45E-01
-1.39E 1.54E+00
-4.00
.97E+00
-7.24
.48E+00 3.00E 3.31E+00
-3.93E
.69E+00 1.95E 1.71E-02 3.69E 9.28E-02 0.00E
.18E+00
-3.68E 1.28E-01 3.69E lues indicate con tor
-B11R MW-B11A E+00 2.07E-0 E+01 3.04E-0 E+00 3.44E+0 E+00 0.00E+0 E+01
-3.49E+0 E+01
-8.49E+0 E+00 1.22E+0 E+00
-4.14E-0 E-01 2.80E-0 E+00
-1.29E-0 0E-01
-1.56E+0 4E-01 9.72E-0 E+00 6.42E+0 E+00 1.10E+0 E+00 1.69E+0 E-02
-5.50E-0 E+00
-1.10E-0 E+00
-2.29E+0 E-02
-1.69E-0 ncentration grea Table 2-19 AR MW-200-A 01 2.42E-01 01 2.41E+00 01 6.86E+01 00
-4.56E-01 01
-3.35E+01 00 7.84E+00 00 3.56E+00 01 3.62E+00 01 1.14E+00 01
-1.43E+00 00
-1.57E+00 01 2.17E+01 00
-2.39E+00 00
-6.57E-01 00
-8.16E-01 03 2.65E-02 02 5.83E-02 00
-2.23E+00 02 1.10E-01 ater than MDC.
(continued)
MW-200-B 2.01E+00 9.11E+00 5.17E+01
-4.98E+00
-4.56E+01 2.37E+01 6.20E-01
-7.87E-01 5.10E-01
-2.68E-01
-1.54E+00 1.94E+00
-1.34E+01
-1.54E+00
-1.64E+00
-6.50E-03 0.00E+00 8.49E+00 2.29E-01 Italicized value 2-63 2014 Ground MW-201-A M
1.18E+00 7.36E+00 8.67E+01 2.69E+00
-2.18E+01
-1.99E+01
-7.23E-02 5.00E+00
-1.19E-01 6.56E-01
-7.94E-01
-1.09E+00 4.79E+00
-3.09E+00
-1.48E+00
-3.59E-02 0.00E+00
-6.92E-01 1.40E-01 es indicate MDC dwater Monito MW-201-B MW 1.43E+00 1.0 3.67E+00 4.8
-3.42E+01
-5.1 9.28E-01 4.94 2.77E+01
-5.4 3.09E+01
-1.1 9.50E-01 9.7 2.15E+00 8.2
-4.99E-01 6.7 6.44E-01
-6.4
-1.95E+00 7.9 1.84E+00
-4.3 2.53E+00 9.4 1.94E+00
-3.6 4.13E+00
-2.0 8.55E-02 1.1 1.41E-01 5.8
-5.85E-01 0.0 2.80E-02 6.6 C value.
oring Results (p W-202-A MW-20 4E+00
-2.10E-86E-01 2.30E+
18E+01 1.04E+
4E+00
-2.72E+
43E+01 3.37E+
18E+01
-4.46E+
72E-01 1.18E+
25E-01
-8.30E-70E-01 5.40E-48E-02
-1.02E+
97E-01
-1.95E-34E-01 2.31E+
0E+00 6.51E+
67E-01 4.18E+
08E+00
-8.41E-13E-02 3.63E-87E-02 5.25E-0E+00
-1.76E+
62E-02 9.48E-pCi/L) 02-B MW-203-A E-01 1.37E+00
+00 1.52E+00
+02
-3.44E+01
+00
-3.95E+00
+01
-4.95E+01
+01 5.30E+01
+00 3.67E+00 E-01 1.62E+00
-01 4.80E-01
+00 8.53E-02 E-01
-1.24E+00
+00 1.56E+00
+00 4.06E+00
+00
-3.33E+00 E-01
-9.54E-02
-02 7.08E-02
-02 9.15E-02
+00 5.04E-01
-02 2.51E-01 A
MW-203-B
-6.68E-01 1.00E+00 1.21E+02 0
4.89E-01 4.32E+01
-4.34E+01 1.99E+00
-1.77E+00 8.70E-01 2.16E+00 0
-3.32E+00 6.84E-01
-1.15E+00 0
-2.31E-01
-3.66E-01 8.12E-02 5.97E-02
-3.71E+00 1.03E-01 MW-204-A 6.00E-01 5.28E+00 6.88E+01 4.73E-01 3.45E+01
-3.13E+01
-3.77E-01
-1.84E-01 9.00E-01 1.18E-01
-1.96E+00
-1.14E+00
-1.92E+01
-4.95E+00
-2.02E+00
-6.45E-04
-5.48E-03
-3.97E+00 1.06E-01 MW-204-B 3.53E+00 0.00E+00
-1.21E+02 9.46E-01
-9.25E+01
-1.87E+01 2.05E+00 3.94E-01 2.30E-01
-1.88E+00 3.89E-01 1.24E+00 2.23E+00 2.36E+00 9.46E-01
-3.26E-02 7.02E-02
-6.46E+00 2.69E-01


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
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan Figure or e 2-1 LACBWR Site Map -
2-64
- Open Land Survey Units annd Classificatioon


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
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-2 LACBWR 2-65 Site Map - Buildings Identifiication


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
La Cross License T Revision se Boiling W Termination n 0 F
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
Water Reactor Plan Figure 2-3 r
WTB            Wastee Treatment Building ZNPS          Zion Nuclear N        Pow wer Station 2-v
LACBWR 2-66 R Site Drainnage and Seewer Map


La Crossse Boiling Water W     Reactorr License Termination T            Plan Revision n0 Page Intenttionally Left ft Blank 2-vi
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-4 r
LACBWR 2-67 R LCE Excllusion Area (Class 1)


La Crossse Boiling Water W       Reactorr License Termination T            Plan Revisionn0
La Cross License T Revision se Boiling W Termination n 0 Figu Water Reactor Plan ure 2-5 N
: 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.
r Non Impacte 2-68 ed Open Laand Samplinng Locations
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.
La Cross License T Revision se Boiling W Termination n 0 F
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..
Water Reactor Plan Figure 2-6 r
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.
Class 1 O 2-69 Open Land SSampling LLocations
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.
La Cross License T Revision se Boiling W Termination n 0 F
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..
Water Reactor Plan Figure 2-7 r
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.
Class 2 O 2-70 Open Land SSampling LLocations
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.
La Cross License T Revision se Boiling W Termination n 0 F
p                Potential chemical hhazards inciddents on ow    wner-controlled areas weree also docum    mented.
Water Reactor Plan Figure 2-8 r
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.
Class 3 O 2-71 Open Land SSampling LLocations
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.
La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan Figure 2-9 r
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.
9 Concre 2-72 ete Core Sam mpling Loccations
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::
La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r
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),
inued) 2-73 Concrete CCore Sampliing Locationns
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.
La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r
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.
inued) 2-74 Concrete CCore Sampliing Locationns
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.
L L
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)
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-10 LACBWR Si 2-75 ite - Typical Geological Crosss-Section
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.
L L
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.
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-111 Groundwat 2-76 ter Sampling Wells - LACBW WR Site
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).
LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 2 SITE CHARACTERIZATION
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.
La Cross License T Revision 2.
Class 3 open o      land surrvey units arre shown on Figure 2-1.
Site 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..
2.1.
G-3 Coal C Plant Grounds G        (L40 012103)
2.1.
Coal Pile Ground  ds (L4012105)
2 2
Capp ped Ash Impoundment Grounds G          (L40012106)
2 2
Grou unds East of Highway H        355 (L4012107)
2 2.1.
Hwy 35/Railroad  d Right of Way W Grounds (L4012108))
2.1.4 2
The non--impacted op  pen land surv vey units aree shown on F Figure 2-1.
2 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.
2.1.
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:
2 2
Reacttor Building g (B1010001)
2 2
Wastte Treatmentt Building (B  B1010002)
2 2
Ventiilation Stack k (B1010003  3)
2 2
Wastte Gas Tank Vault (B101    10004)
2.2.
Turbiine Building g (B1010005  5)
2.2.
Dieseel Generatorr Building (B  B1010006)
2.2.
LSA Building (B  B1010007)
2 2
Main ntenance Eat Shack (B10    010008)
2 2
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.
2.2.
2-11
2 2
2.2.4 2.2.
2.3.
2.3.
2.3.
2.3.
2.3.4 2
2 se Boiling W Termination n 0 Characteriz Historical S 1.
Objecti 2.
Method
.1.2.1. Pre
.1.2.2. Doc
.1.2.3. Lic
.1.2.4. Per
.1.2.5. Pro 3.
Operati 4.
Inciden
.1.4.1. Rad
.1.4.2. Che 5.
Finding 6.
Initial S
.1.6.1. Sur
.1.6.2. Sur
.1.6.3. Cla
.1.6.4. Cla
.1.6.5. Cla
.1.6.6. Non
.1.6.7. Cla
.1.6.8. Cla Characteriz 1.
Data Q 2.
Survey
.2.2.1. Num
.2.2.2. Det
.2.2.3. Sca
.2.2.4. Typ 3.
Instrum Concen
.2.3.1. Cal
.2.3.2. Inst 4.
Labora 5.
Quality Summary o 1.
Backgr 2.
Potenti 3.
Non-Im 4.
Impact
.3.4.1. Cla
.3.4.2. Cla Water Reactor Plan zation..........
Site Assessm ives............
dology........
liminary Cla cument Revi enses, Perm rsonnel Inter operty Inspec ional History nts...............
diological Sp emical Spills gs and Conc Survey Area rvey Areas..
rvey Units...
ass 1 Open L ass 2 Open L ass 3 Open L n-Impacted O ass 1 Structur ass 2 and 3 S ation Appro Quality Objec y Design......
mber of Stat termination o an Coverage pes of Measu mentation Se ntrations (M libration......
trument Use atory Instrum y Assurance f Characteri round Study ial Radionuc mpacted Ope ed Open Lan ass 1 Open L ass 2 Open L r
TABLE O ment..............
assification..
iew..............
mits and Auth rviews..........
ctions...........
y..................
pills.............
s..................
lusions........
as/Units and Land Areas...
Land Areas...
Land Areas...
Open Land A res...............
Structures.....
ach..............
ctives...........
tic Measurem of Static Me urements and lection, Use MDCs)..........
e and Contro ment Method zation Surve clides of Con en Land Area nd Areas.....
Land Areas...
Land Areas...
2-i OF CONTE horizations...
Classificatio Areas..........
ments and/or easurement a d Samples...
and Minimu l..................
ds and Sensit ey Results...
ncern............
as................
ENTS on................
r Samples....
and Sample L um Detectab tivities.........
Locations....
ble
... 2-1
... 2-2
... 2-2
... 2-3
... 2-3
... 2-4
... 2-5
... 2-5
... 2-5
... 2-6
... 2-6
... 2-7
... 2-8
... 2-8
... 2-9
... 2-9
... 2-9
. 2-10
. 2-10
. 2-10
. 2-11
. 2-11
. 2-12
. 2-12
. 2-14
. 2-14
. 2-15
. 2-16
. 2-16
. 2-16
. 2-18
. 2-18
. 2-19
. 2-19
. 2-19
. 2-20
. 2-21
. 2-22
. 2-22
. 2-24
. 2-25
. 2-26


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.
La Cross License T Revision 2
LACB BWR Crib House H        (B201 10101)
2.3.
G-3 Crib C House (B2010102)
2.3.
(
2 2
LACB BWR Administration Bu        uilding (B20 010103)
2 2.3.
LACB BWR Wareh    house #1 (B2  2010104)
2 2
LACB BWR Wareh    house #2 (B2  2010105)
2 2
LACB BWR Wareh    house #3 (B2  2010106)
2 2.4.
Backk-up Control Center (B30    012101)
2.5.
Transsmission Sub  b-Station Sw witch House (B3012102))
se Boiling W Termination n 0
G-1 Crib C House (B3012103)
.3.4.3. Cla 5.
(
Non-Im 6.
Bargee Washing Break B      Room (B3012104))
Impact
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.
.3.6.1. Bas
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.
.3.6.2. Tur
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),
.3.6.3. LA 7.
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.
Surface
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
.3.7.1. Are
.3.7.2. Gro
.3.7.3. Pre
.3.7.4. On-
.3.7.5. Sum Continuing References Water Reactor Plan ass 3 Open L mpacted Stru ed Structure sement Struc rbine Buildin ACBWR Adm e and Groun ea Groundwa oundwater F vious Invest
-Going Inve mmary of Gr Characteriza r
Land Areas...
uctures.........
es and System ctures Below ng Tunnel....
ministration dwater........
ater Use......
low.............
tigations......
stigations....
roundwater A ation...........
2-ii ms...............
w 636 foot El Building.....
Analytical R levation......
Results.........
. 2-27
. 2-29
. 2-30
. 2-30
. 2-31
. 2-31
. 2-32
. 2-32
. 2-33
. 2-34
. 2-35
. 2-35
. 2-36
. 2-37


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.
La Cross License T Revision Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-se Boiling W Termination n 0 1
Characterization dataa acquired th  hrough the execution e            of the Plan waas used to m meet three priimary objectivees:
LACBW 2
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.
LACBW 3
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.
Instrum 4
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.
Off-Sit 5
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.
2005 D 6
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.
Investig 7
2-13
Initial S 8
Non-Im Survey 9
Non Im Labora 10 Impact Summa 11 Class 1 Labora 12 Impact Survey 13 Class 2 Labora 14 Impact Survey 15 Class 3 Labora 16 Concre 17 1983 G Buildin 18 2013 G 19 2014 G
-1 LACBW
-2 LACBW
-3 LACBW
-4 LACBW
-5 Non Im
-6 Class 1
-7 Class 2
-8 Class 3
-9 Concre
-10 LACB
-11 Ground Water Reactor Plan WR Open L WR Structur ment Types a te Laboratory Dairyland Ba gative Level Suite of LAC mpacted Ope y Summary.
mpacted Coa atory Analys ed Class 1 O ary.............
Concrete, A atory Analys ed Class 2 O y Summary.
2 Asphalt, Se atory Analys ed Class 3 O y Summary.
3 Asphalt, Se atory Analys ete Core Isot Groundwater ng...............
Groundwater Groundwater WR Site Ma WR Site Ma WR Site Dra WR LCE Ex mpacted Ope Open Land 2 Open Land 3 Open Land ete Core Sam WR Site - T dwater Samp r
LIST and Survey ral Survey U and Nominal y Analytical ackground St ls for Cs-137 CBWR Site-en Land Surv l Pile and So sis (pCi/g)....
Open Land S Asphalt, Sed sis (pCi/g)....
Open Land S ediment and sis................
Open Land S ediment and sis (pCi/g)....
opic Analys Analysis fro Monitoring Monitoring LIST O ap - Open La ap - Building ainage and S xclusion Are en Land Sam d Sampling L d Sampling L d Sampling L mpling Locat Typical Geolo pling Wells -
2-iii OF TABLE Units...........
Units.............
l MDCs.......
l Methods an tudy for Soil 7 Based on B
-Specific Ra vey Units - C oil Samples -
Survey Units diment and S Survey Units Soil Sample Survey Units Soil Sample is Results....
om Tempora Results......
Results (pC OF FIGURE and Survey U gs Identifica Sewer Map..
ea (Class 1)..
mpling Locati Locations.....
Locations.....
Locations.....
tions............
ogical Cross
- LACBWR ES nd Typical M ls.................


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.
===Background===
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.
dionuclides.
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::
Characteriza
: 1) State the problem m,
- Test Amer
: 2) Identtify the decission,
  - Character Soil Samples
: 3) Identtify inputs to o the decision  n,
  - Character es - Test Am
: 4) Defin ne the study boundaries,
  - Character es - Test Am ary Well-Po Ci/L)............
: 5) Deveelop a decisio  on rule,
RES Units and Cl ation.............
: 6) Speciify limits onn decision errrors, and
ions.............
: 7) Optim mize the design for obtaiining data.
s-Section.....
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.
R Site...........
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).
MDCs..........
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
Studies.......
ation rica rization Surv
  - Test Ame rization merica rization merica oint South of lassification vey erica f Turbine
. 2-39
. 2-40
. 2-42
. 2-43
. 2-44
. 2-45
. 2-46
. 2-47
. 2-49
. 2-50
. 2-51
. 2-52
. 2-53
. 2-54
. 2-55
. 2-56
. 2-60
. 2-61
. 2-62
. 2-64
. 2-65
. 2-66
. 2-67
. 2-68
. 2-69
. 2-70
. 2-71
. 2-72
. 2-75
. 2-76


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.
La Cross License T Revision AEC ALARA bgs CRD DCGL DQO EPA FCP FESW FRS FSS G-1 G-3 HSA HTD IR ISFSI LACBW LER LSA LSE LTP MARLA MARSA MARSSI MDC MDCR MWe NIST se Boiling W Termination n 0 United As Lo Below Contr Deriv Data Q United Force Fuel E Final Final Genoa Genoa Histor Hard-Incide Indep WR La Cr Licen Low S LACB Licen AP Multi-AME Multi-Manu IM Multi-Minim Minim Megaw Nation Water Reactor Plan LIST OF d States Ato ow As Reaso w Ground Su ol Rod Driv ed Concentr Quality Obje d States Env d Circulation Element Stor Radiation Su Status Surve a 1 Coal/Oil a 3 Fossil St rical Site As to-Detect ent Reports endent Spen rosse Boiling see Event R Specific Act BWR Site En se Terminati
The areaas and materials surveyeed and/or sam      mpled in andd around thee licensed arrea as part oof the characterrization surv vey included:
-Agency Rad
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).
-Agency Rad ual
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.
-Agency Rad mal Detectab mum Detecta watt Electric nal Institute r
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.
ACRONYM mic Energy onably Achie urface e
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.
ration Guide ective vironmental P n Pump rage Well urvey ey Station tation sessment nt Fuel Stora g Water Reac eports ivity nclosure ion Plan diological L diation Surv diation Surv ble Concentr able Count R c
Samples weree taken from  m the septic taanks.
of Standard 2-iv MS AND AB Commission evable line Levels Protection A age Installatio ctor Laboratory A vey and Asse vey and Site rations Rate ds and Techn BBREVIAT n
Scans and sam  mples were taken on LA    ACBWR Addministrationn Building suurfaces and drain arreas.
Agency on Analytical Pro essment of M Investigatio nology TIONS otocols Man Materials and n Manual nual d Equipmentt
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.
2-15


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.
La Cross License T Revision NRC ORC PSDAR QA QAPP QC RCA REMP ROC RPV SRC STS TSD WDNR WGTV WTB ZNPS se Boiling W Termination n 0 United Opera Post-S Qualit Qualit Qualit Radio Radio Radio React Safety Sourc Techn Wisco Waste Waste Zion N Water Reactor Plan d States Nuc ational Revie Shutdown D ty Assurance ty Assurance ty Control ologically Co oactive Efflu onuclides of or Pressure V y Review Co e Term Surv nical Suppor onsin Depart e Gas Tank V e Treatment Nuclear Pow r
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.
clear Regula ew Committ ecommissio e
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.
e Project Pla ontrolled Are ent Monitor Concern Vessel ommittee vey rt Document tment of Nat Vault Building wer Station 2-v atory Commi ee ning Activit an ea ing Reports tural Resour ission ties Report rces
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
La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan r
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)
Page Intent 2-vi tionally Leftft Blank
(    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.
La Cross License T Revision
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.
: 2.
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..
S In accor Regulato Nuclear character The purp conducte remain.
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.
License T of compl Survey (
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.
1575, Mu Source T terminati The site quantify character site that classifica The cha NUREG-Decomm
2.2.3. In nstrumenta  ation Selectio on, Use andd Minimum Detectable Concentrattions (MDC          Cs)
: Criteria, PG-EO-3 Reactor Characte the Data informati remediat at concen removed The deco waste of LACBW None of radiologi planned a G-3 pow minor str The majo basement se Boiling W Termination n 0 Site Chara rdance with ory Guide 1.
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.
Power Re rization perfo pose of site ed in all are The term F Termination liance survey FSS) for op ulti-Agency Term Surve ion. See LTP characteriz the extent a rization surv will require ation and vol aracterization
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
-1575 (MA issioning G Final Repor 313196-SV-P (4), and GP erization Pro Quality Obj ion obtained ion planning ntrations gre and properl ommissionin f all LACB WR Administ f the buildin ically impac and these str wer operation ructures will or sub-grade ts of the Re Water Reactor Plan acterization h the requi
: 3) analyssis of materiaal samples.
.179, Standa eactors (1),
Instrumentation and nominal MD      DC values thhat were em mployed durinng characterrization are listed in Table 2-3.
formed at the characteriza eas where co Final Radiat n Plan (LTP) ys that will b pen land are Radiation S ey (STS) fo P Chapter 5 ation incorp and nature o veys and ana remediation lumes, and e n survey w ARSSIM)
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
Guidance - C rt, (3). In ad PL-001, Ch P-EO-31319 oject (QAPP jective (DQO d from the
: g. Materials eater than th ly packaged ng approach BWR buildi tration build ngs and stru cted such th ructures, inc ns. The pub l also remain e structures t eactor Buildi r
n rements of ard Format
, this chap e La Crosse B ation is to en ontamination tion Survey
) in order to be performed eas and buri Survey and S or below gr for a descrip porates the r of contamin alyses have b n, as well as estimate cost was designed and NURE Characteriza ddition, surv haracterizatio 96-QA-PL-00 P) (5) which O) process, a characteriz which were he unrestricte for shipmen for LACBW ings, structu ding and Cri uctures asso hat they requ cluding the G blic roads an
: n.
that will be ing, Waste T 2-1 f 10 CFR 50 and Conte pter provide Boiling Wat nsure that th n existed, re is from 10 acknowledg d at LACBW ed piping b Site Investig round struct ption of the results of in ation at LA been and con s to plan rem ts.
d and exec EG-1757, ation, Surve veys were de on Survey P 01, Quality describes p and measure zation provi e shown to b ed release cr nt and dispos WR requires ures and co ib House) to ociated with uire remedi G-3 Crib Hou nd railways backfilled a Treatment B 0.82 (a)(9)(ii ents for Lic es a descr ter Reactor (
he Final Rad emains, or h 0 CFR 50.82 ge the distin WR. These ased on gui gation Manu tures to be FRS.
nvestigation ACBWR. In ntinue to be mediation m cuted using Volume 2, ey, and De esigned and Plan for th Assurance policy, organ es necessary des guidanc be contamina riteria have sal.
the demolit omponents o a depth of h the Genoa al actions; use, will rem that travers and remain a Building (W i)(A) and t ense Termin ription of (LACBWR) diation Surv has the pote (9)(ii)(D) an nction betwe surveys are; idance provi al (MARSS backfilled ns and surve n addition, th e used to ide methodologie the guidan Revision 1 termination executed in e La Cross Project Pla nization, fun to achieve q ce for deco ated with rad been and wi tion, remova (with the e f at least 3 f a 3 Fossil S therefore, n main intact a se the site a at license ter WTB), Waste the guidanc nation Plan the radiolo site.
ey (FRS) w ential to exi nd is used in een the two
: 1) a Final S ided in NUR SIM) (2) and prior to lic eys conduct he results o ntify areas o es, develop w nce provide 1,
Consolid of Radiolo n accordance se Boiling W an LACBWR nctional activ quality data.
ontamination dioactive ma ill continue al and dispos exception o feet below g Station (G-3 no remediati and function as well as se rmination ar Gas Tank V ce of ns for ogical will be ist or n this types Status REG-d 2) a cense ed to of site of the waste ed in dated ogical e with Water R Site
: vities, The n and aterial to be sal as f the grade.
: 3) are ion is al for everal re the Vault


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.
La Cross License T Revision (WGTV)
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.
(3 feet b Reactor/G sump and In the R removed removed elevation WTB, th concrete the rema cap and p following covered b remainin LTP Cha Independ shown in 2.1.
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.
H In accor Assessm informati
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.
: reports, marine f Environm compiled 2.1.1. O The HSA LACBW surround resulted Radiolog subsurfac the 1.5 a informati may also The scop hazardou The obje Id b
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.
se Boiling W Termination n 0
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.
) and the re elow grade)
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.
Generator P d the Turbin Reactor Bui
2-19
. All intern
, leaving on n (i.e., concr he only porti footers belo ining structu piles below t g the termina by at least 3 ng backfilled apter 1, sec dent Spent F n Figure 2-1)
Historical Si rdance with ent (HSA) ion, includin pre-operatio fauna and s mental Repo d for this inv Objectives A was a d WR activities dings. The in contamin gically Contr ce soils outs acre fenced ion compile o be used as pe of the us materials.
ctives of the dentify pote ased on exis Water Reactor Plan emainder of
). These re Plant, the on e pit.
lding, all in nal concrete nly the rema rete bowl on of the str ow the 636 fo ure will cons the 636 foot ation of the l feet of soil d structures to ction 1.3.1 d Fuel Storage
) is excluded te Assessme h the guida (6) was p ng any 10 C onal survey sediment su orts to the vestigation.
detailed inve related to r HSA focuse nation of pla rolled Area (
ide of the R LACBWR d by the HS input into th HSA inclu e HSA were ntial, likely sting or deriv r
f the baseme maining stru ne foot thick nternal stru will be rem aining struct below 636 ructure that oot elevation sist of the fl elevation. T license are c and physica o be plausibl describes th Installation d from the sc ent ance provid performed a CFR 50.75(g data, spill urveys), ope Nuclear Re estigation to radioactive m ed on histor ant systems, (RCA). It al RCA but with Site Enclos SA was used he developm ded potenti to:
, or known ved informat 2-2 ent structure uctures inclu k portion of uctural surfa moved to ex tural concre foot elevatio will remain
: n. In the WG loors and fou The structur constructed o ally altered t ly occupied.
e site licen (ISFSI) Fac cope of the L ded in MAR and docume g) files, emp reports, spe rational sur egulatory C o collect ex materials or rical events
, buildings, lso addresse hin the owne sure (LSE) d to establis ment of reme ial contamin sources of
: tion, es located b lude the Pip f the Chimn aces, system xpose the ste ete outside t on, concrete is the 630 a GTV and the undation wa ral surfaces t of steel reinf to a conditio nse boundary cility as loca LTP.
RSSIM, sec ented in Au ployee inter ecial survey rvey records Commission xisting info other conta and routin surface and d support str er controlled area share sh initial sur ediation plan nation from radioactive below the 63 ping and Ve ney Foundat ms and com eel liner, wh the liner be e pile cap an and 635 foot e other rema alls as well a that will rem forced concr on which wo
: y. The fen ated in Lot 7 ction 3.0, a ugust of 19 rviews, radi ys (e.g., site s, and Ann (NRC) wer ormation (fr aminants) fo ne operationa d subsurface ructures, ope d area. The e the same rvey units.
ns and the de m radioactiv and chemi 36 foot elev entilation Tu tion, the Tu mponents wi hich will als low the 636 nd piles.) I t floor, sump aining basem as concrete p main at LACB rete which w ould not allow nced area o 7 of the site a Historical 999. Histo ological inc e aerial sur nual Radiolo re reviewed rom the sta or the site an al processes e soils withi en land area current RCA boundary.
This inform esign of the ve materials cal contami vation
: unnel, urbine ill be so be 6 foot In the p and
: ments, piling BWR will be w the of the e (and Site orical cident
: rveys, ogical d and art of nd its s that in the as and A and The mation FRS.
s and inants


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:
La Cross License T Revision D
Establishmen E              nt/implementtation of plan  ns, procedurres, and prottocols for thee field opperations.
n P
Actions A        to en nsure that thee procedures are understoood and folllowed by thee implementiing sttaff.
P P
Documentatio D              on of the datta collected.
P M
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:
D 2.1.2. M The obje may have land area failures r material.
Personnel quaalifications, experience, and trainingg.
contamin decontam their pote Each inc was furth
Execution E            in accordance with approv    ved procedurres.
: analysis, sampling location.
Proper docum  mentation of survey data and sample analyses.
Relevant remediat Also incl R
Selection of appropriate a            instruments i              to t perform thhe surveys.
P p
Proper instrum  ment calibraation and daiily functionaal checks.
S id Informat data, eva Units.
Management M                oversight off characterizzation activitties relative tto the adhereence to prrocedures, protocols, p          and documentaation requireements.
2.1.2.1.
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.
The HSA classifica have a p se Boiling W Termination n 0 Distinguish p o threat to h rovide an as rovide infor rovide an in rovide a gra MARSSIM g Delineate init Methodology ective of the e significant as and struct resulting in Dependin nation varies mination acti ential for con ident identif her investiga any remed g, survey, an Historical r t informatio ion phases o luded in the Relevant exce ersonnel int lant personn ite inspectio dentify, locat ion from thi aluation of r Prelim A investiga ation of the potential for Water Reactor Plan portions of th uman health ssessment of rmation usefu nitial classific aded initial c guidance, and tial survey u y
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).
HSA record tly impacted tures. These airborne rel ng upon pa s by area. In ivities and F ntamination.
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
fied that pos ated. This in dial actions nd analysis i records prov on that bec of the license research ass erpts from w terviews, inc nel to confir on, utilizing te, confirm, is research w results, docu minary Class ation was d site land are contaminati r
he site that m h,
f the likeliho ful to subsequ cation of are lassification d
unit boundari ds search and d the hazardo e included sy eases, liquid ast site ope n order to fac RS planning sed a realisti nvestigation taken to m in an attemp vided the sou comes avail e termination sociated with written report cluding the u rm documen g historic si and docume was used in umentation o sification designed to eas and struc ion (based o 2-3 may need fur od of contam uent continu eas and struc n for impacte ies and areas d interview ous material ystem, struc d spills or re erations and cilitate effec g, land areas ic potential t n focused on mitigate the s pt to identify urce of a vast lable during n plan will b h the develop ts and corres use of quest nted incident te drawings ent areas of c the HSA de of findings, o obtain su ctures as imp on historical rther action minant migra uing characte ctures as non ed soils and s s based upon process was l or radiolog cture, or area eleases, or t d processes, ctive charact s and structu to impact th n the scope o situation, an fy the as le t majority of g any addi be evaluated.
pment of the spondences, tionnaires, o ts and ident s, photograp concern.
evelopment, and the ide ufficient info pacted or no l data) or co from those
: ation, erization sur n-impacted o structures in n the initial c s to identify gical status o a contamina the loss of c
, the poten terization, an ures are class he characteri of contamina nd any post eft conditio f the docume itional char e HSA were:
of current, fo tify undocum phs, prints, including th entification formation to on-impacted ontain know that pose lit
: rveys, or impacted, n accordance classification those event of LACBWR ation from sy control over ntial for res nd to guide f sified based ization of th ant sampling t-remedial a n of the inc ents inspecte racterization ormer and re mented incid and diagram he compilati of initial Su o provide i
. Impacted wn contamin ttle or e with
: n.
s that R site ystem solid sidual future upon e site g and action cident ed.
n and etired
: dents, ms to on of urvey initial areas nation


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.
La Cross License T Revision (based o through k is no rea impacted controlle If a land area clas was mad Initial cl historical initial cla at the tim prepared FRS desi classifica continuin surveillan classifica of comm 2.1.2.2.
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.
Records source of for LACB include:
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.
O S
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.
L S
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.
O A
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.
E R
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
D H
S R
se Boiling W Termination n 0 on past or p knowledge o asonable po d from a ra d areas were area or struc ssification (e e based upon lassification l radiologica assification a me of identifi
. Final clas ign. The ch ations indica ng characteri nce, and an ations (for ex mencement of Docum maintained f documenta BWR, many Operational R afety Review Licensee Eve ite Initiated Operator Log Annual Envir Environmenta Regulatory ac Documentatio Health Physic ite inspectio Radiological Water Reactor Plan preliminary of site history ssibility for adiological p e also docum cture was cla e.g. Class 1, n the inform of LACBW al survey dat and (2) final ication of the ssification is haracterizatio ated in the H ization surve ny other ap xample, from f the FRS.
ment Review to satisfy t ation for the y record type Review Com w Committe ent Reports (
Incident Rep gs including ronmental M al investigat ctions conce on from inte cs surveys an on and survei and environ r
radiological y or previou residual ra perspective.
mented.
assified as im Class 2 or C mation obtain WR areas w ta. Classify l classificati e survey are s performed on data was HSA as descr eys, operatio pplicable sur m Class 3 to w
the requirem e HSA recor es were eval mmittee (ORC ee (SRC) Me LER) Summ ports (IR),
Reactor Ope Monitoring R tions perform erning the sit rviews cond nd sampling illance type nmental surv 2-4 l surveillanc us survey inf adioactive co Potential mpacted, the Class 3) in a ned.
was based o ying a survey ion. Initial c a using the i and verified used to val ribed in this onal surveys rvey data m o Class 2 and ments of 10 rds review p luated. A su C) Meeting M eeting Minut
: maries, erator and H
: Reports, med by indep te, ducted with r g results asso documents a ey documen ce). Non-im formation an ontamination chemical h en a determi accordance w on historica y area has a classification information d as a DQO lidate or upd Chapter. R s in support may cause d from Clas CFR Part 50 process. Dur ummary of t
: Minutes, tes, Health Physic pendent entit retired/separ ociated with associated w
: nts, mpacted are nd are those a
: n. Areas w hazards incid ination of the with MARS al informatio minimum o n of most ar available wh O during cha date, as nece Radiological of decommi an increase ss 2 to Class 0.75(g)(1) p ring the con the types of cs entries,
: ties, rated site per identified ev with identifie eas are iden areas where were classifie dents on ow e initial imp SSIM, sectio on and avai of two stage reas is perfo hen the HSA aracterization essary, the i survey data issioning, ro e in survey s 1) until the provided a m nduct of the records revi
: rsonnel, vents, ed events, ntified there ed as wner-pacted on 2.2 ilable s: (1) ormed A was n and initial from outine area e time major HSA iewed


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.
La Cross License T Revision Q
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.
2.1.2.3.
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..
LACBW permits.
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.
allowed D the site, activities Several g licensing U
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.
U U
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.
W L
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
From Au This peri 1987, and 2.1.2.4.
Interview about the The pers the partic personne terms be site know Between individua standardi site perso the perso memorie operation 2.1.2.5.
Several Several s se Boiling W Termination n 0 Quality Contr Licen WR was opera The NRC Dairyland P to support o
: s.
government g, constructio United States United States United States Wisconsin De Local/County ugust 28, 197 iod includes d ISFSI cons Person ws with curre e site and to onnel interv cipants as w el were chos ing investig wledge and e 2010 and als contacte ized personn onnel who w onnel observ s of other q nal period ex Prope on-site prop site events of Water Reactor Plan rol (QC) /Qu ses, Permits ated in accor Operating L ower Coope operations du and regulato on, operation s Atomic Ene s Nuclear Re s Environmen epartment of y Governmen 73 to the pre s power ope struction and nnel Intervie ent or previo verify or cl views includ well as indivi sen due to th ated for the experience th 2011, appr ed as part nel survey w worked at th vations docum questionnaire xperience, or rty Inspectio perty inspec f interest we r
uality Assura and Author rdance with License for erative (Dair uring its ope ory agencies ns, and decom ergy Commi egulatory Co ntal Protecti f Natural Re nts.
esent, the fac erations to 1 d spent fuel ews ous employe arify inform ded a combin idual and gro heir knowled assessment.
hat ranged fr roximately 4 of the HS which was c e LACBWR mented on th e completers r by docume ons ctions were ere identified 2-5 ance (QA) fi izations several Fed LACBWR a ryland) to us erating lifeti have provid mmissioning ission (AEC ommission (N ion Agency (
esources (WD cility has bee 1987, perma off-load whi ees were per mation gather nation of qu oup interview dge of and a
. A number rom the site c 40 recollecti SA question completed v R during its o he questionn s, current on ntation disco made over d which were finding type d deral and Sta and support se any quant ime, and to ded oversigh
: g. These age C),
NRC),
(EPA),
DNR),
en operated u anent shutdo ich was com rformed to c red from the uestionnaires ws with sev association r of the pers construction ions of inte nnaire progr voluntarily b operational naire were c n-site worki overed durin r the course e subsequent documents.
ate of Wisco ting Technic tity of radioa implement d ht at LACBW encies includ under NRC own for dec mpleted in 20 collect first-h e records tha s completed veral of the p with the sys sonnel interv n period to sh erest were l ram. This by retired/sep years. With corroborated ing staff tha ng the record e of the HS tly documen onsin license cal Specifica active mater decommissio WR during s de:
License DPR commissionin 012.
hand inform at were revie by a majori participants.
stems and so viewed poss hutdown.
logged from consisted parated staf h few except d either by lo at had LACB ds search.
SA developm nted in the H es and ations rial at oning
: siting, R-45.
ng in mation ewed.
ity of Key ource essed m the of a ff and
: tions, ogged BWR ment.
HSA.


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.
La Cross License T Revision 2.1.3. O LACBW Dairylan Mississip bordered Mississip LSE com served as confirme road on t th fo an 1
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.
th a
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.
li The plan Chalmers provided LACBW 19 years defueling Operatin No. 56, d 333 irrad into five Limited d ongoing shipped internals Building removed undergro Condens Water Sy Building 2.1.4. In Based on notificati se Boiling W Termination n 0 Operational WR was a 5
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.
: d. This sing ppi River so d on the no ppi River an mprising app s the RCA b ed to be suit the south sid he land north ormer Genoa n operationa 75 feet from he fenced ISF small parce icensed site.
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.
nt was one s Company d them with a WR achieved until it was g was compl g License D dated Augus diated fuel as (5) dry cask dismantleme at LACBW for disposal intact, and 2
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.
, and shippe
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
, including t ound gas sto ate Storage ystem pump ncidents n the review ions, occurre Water Reactor Plan History 50 Megawatt gle unit, also outh of the orth by the nd Highway proximately boundary du table for unr de of the plan h of the LA a Station #1 al 350 MWe m the LSE, FSI facility t l of land to t of a series was the ori a provisional d initial criti s permanent leted on June DPR-45, pur st 4, 1987; a ssemblies, w ks and transfe ent of shutdo WR since 199 l in June 20 29 control ro ed for dispo the spent fue orage tanks)
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.
Tank and s, heat exch w of existin ence reports r
A summary of the gammag        specttroscopy resu  ults for eachh non-impaccted open laand survey uunit is presentedd in Table 2--8.
t Electric (
2-23
o known as G Village of Mississippi
: 35. The lic 1.5 acres of uring operat restricted us nt. Other pro ACBWR plan (G-1) coal (
fossil gener that is locate the east of H of demonst iginal licens l operating l icality on Ju tly shut dow e 11, 1987.
rsuant to 10 and a posses which were i ferred to the own and unu
: 94. Waste s 007. The R ods in place osal in June el storage rac
); Condensa condenser);
angers, pipin g plant reco s, and questi 2-6 (MWe) Boil Genoa Statio f Genoa, Ve i River and ensed site c the licensed tions. Mate e before rel ominent feat nt, including (and later oil rating station ed directly so Highway 35, tration plant see; the AEC icense.
uly 11, 1967 wn by Dairy The Dairyla 0 CFR 50, w ss but not-op in Fuel Elem sites ISFSI used systems stored in the Reactor Pres was filled w e 2007. Oth cks, Gaseou ate system Turbine an ng and comp ords (e.g. an ionnaires), i ling Water on #2, is loc ernon Coun d a narrow omprises a t d site. The erial leaving ease. The s tures on the g the site sw l) fueled pow n (G-3) loca outh of G-3, across from ts funded in C later sold 7, and was yland on Ap and authority was terminat perate status ment Storage by Septemb s and waste e FESW and sure Vessel with concret her systems us Waste Dis and Feedwa nd Generato ponents that nnual and s incidents wi Reactor th cated on the nty, Wiscons strip of la total of 163 LSE bounda g the LSE w site is acces site include:
witchyard an wer plant (re ated south an
, and m LACBWR n part by A d the plant t operated fo pril 30, 198 y to operate ated by Lice s was grante e Well (FES ber 2012.
disposal op d other Clas (RPV) wit te, removed and compo sposal System ater system or; and Com t were locate semi-annual ith radiologi hat is owne east shore o sin. The s and between
.5 acres, wit ary is fenced was surveyed sed by an a nd the site o moved in 19 nd approxim that is part o AEC. The A to Dairyland or approxim
: 7. Final re LACBWR u ense Amend ed by NRC.
SW), were p erations has ss B/C waste th head insta from the Re onents have m (except fo m (except fo mponent Co ed in the Tu reports, lice ical or hazar ed by of the ite is n the th the d and d and access of the 989),
mately of the Allis-d and mately eactor under dment The placed been e was
: alled, eactor been or the or the ooling urbine ensee rdous


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.
La Cross License T Revision material placing t the LSE the struct LSE, wh Special Monitori reports c shutdown around th posing a of LACB contamin 2.1.4.1.
The resullts of the anaalysis are preesented in Table T      2-9.
The hist involving potential chronolo T
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.
fl In W
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.
In su In d
2.3.4. Im mpacted Op  pen Land Areas A
st O
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.
th 8
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.
O th 8
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
O ap In O
in se Boiling W Termination n 0 implication the reactor in and, while c tures and so ich is alread emphasis w ing Reports covering the n in 1987.
he plant site significant p BWR site nation from s Radio torical revie g system lea to affect th gical order a The stainless loor. Inciden ncidents inv Water Discha n 1970, pot uppression o n
Septemb econtaminat team cleanin On Novembe he potential 0-84 Inciden On Novembe he Turbine B 7, ORC-80-9 On Decemb pproximately ncident Repo On December nto the Turbi Water Reactor Plan ns occurred n a SAFSTO contributing ils directly r dy known to was placed o (REMP), fo e periods o Available sa e were also probability o land areas system failur ological Spill ew indicated akages, radio e classificati as follows; steel liner nts involving olving leaka arge line wer tentially con on the license
: ber, 1977, tion of a Fo ng tank in the er 5, 1980, p for leakage nt Report, OR er 24, 1980, Building. (D 97, LER 80-ber 6, 1980 y 1/2 gallon ort, ORC-80 r 15, 1980, t ine Building r
between th OR conditio to the radiol related to the be impacte on obtainin focusing on of SAFSTOR ampling resu reviewed. T of impacting and structu res resulting ls d that betwe ological spill ion of LACB in the FESW g leakage of age from the re noted from ntaminated ed site roads removable orced Circul e Reactor Bu artial blocka of drain wa RC-80-71, O residual rad DPC-80-93 I
-12)
, the Turb of waste w 0-71, ORC-8 the Turbine g Basement T 2-7 he commenc n in 1987.
logical conta e operation o ed.
g and revie gaseous an R and deco ults associat The objectiv g the radiolo ures. Thes g in airborne een 1967 a ls, and/or rad BWR structu W had a his f the FESW w e resin regen m 1967 to 19 Control Rod
: s.
e alpha c
ation Pump uilding 701 f age of drain ater into the ORC-80-75, dioactive con Incident Rep bine Build water to the 0-75, ORC-Building Wa Tunnel. (DP cement of p All of these amination an of the reacto ewing the a nd liquid rel ommissionin ted with soi ve was the i ogical status se included releases, liq and 1987, th dioactive liq ures or soils story of leak were noted f neration was 973.
d Drive (C contaminatio (FCP) duri foot elevatio lines under soil under th ORC-80-87 ntamination port, ORC-8 ding Waste Turbine Bu 80-87, ORC aste Water T PC-80-106 In plant operati e incidents t nd potential or, were con annual Radi leases since ng activities il and groun identification or hazardou system, st quid spills or here were s quid effluent
: s. The incid kage to the R from 1967 to ste system t CRD) oil wa on was d
ing mainten on. (ORC, 0 Turbine Bu he Turbine B 7, ORC-80-9 n was detect 80-71, ORC-Water T uilding floor C-80-97)
Tank overflo ncident Repo ion in 1967 took place w contaminati ntained withi ioactive Eff 1967, inclu s after the ndwater with n of those e us material s tructure, or r releases.
several inci releases wit dents are list Reactor Bui o 2012.
to the Circul as used for detected d
ance involv 09/27/77) uilding result Building. (D
: 97) ed in soils u 75, ORC Tank overfl
: r. (DPC-80 owed waste w ort) 7 and within ion of in the fluent uding plant hin or events status area idents th the ted in ilding lating dust during ving a ted in DPC-under C owed 0-102 water


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.
La Cross License T Revision In w
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.
D O
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.
un O
All surfaace and subsurface com    mposite samp  ples were annalyzed afteer drying thhe sample m  media.
co in O
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.
si co B
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.
to O
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..
ap b
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.
2.1.4.2.
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
Between release o ranged fr and fuel impacted policies releases.
2.1.5. F LACBW within its been imp post ope Survey fo for fissio Structure Turbine Stack. In to be dire An area s support b various w se Boiling W Termination n 0 ncidents invo waste water t Discharge lin On January nspecified v On May 31, ontaminated nto the basem On July 02, 1 ight flow se ontaminated Bay door. In o an unrestri On July 16, pproximately asement floo Chem 1967 and 20 of chemicals rom spills of oil from sy d buildings.
and proced Findings and WR was desig s many syste pacted due t erational his or SAFSTOR on products t es classified Building, W n addition to ectly impacte surrounding buildings su warehouses a Water Reactor Plan olving leaka tanks throug ne were noted 30, 1981, volume of wa 1982, a lid d water and ment. (DPC 1982, approx eal rupture t d water flow n addition, a cted area. (D 1983, a leak y 15,000 gal or. (LER 83 mical Spills 014, the HSA s and/or pote f acids and c ystems and These spills dures for id d Conclusio gned with mu ems, compon to routine op tory of the R (7) identifi to enter and i as impact WTB, Low S o the structur ed by the op the LSE ha uch as the L and storage b r
age of potent gh the norma d from 1980 the Turbin ater into the seal failed o spent resin 51 Incid ximately 1,2 o the Turbin wed into the approximatel DPC-82-58 I k in the Sea llons of reac 3-07)
A document entially haza caustics used storage tank s were contr dentification ns ultiple bound nents, and st perations an plant. Dai ied historica impact react ted by the Specific Act res, the soils peration of th s also been d LACBWR C buildings.
2-8 tially contam al effluent re 0 to 1986.
e Building laundry room on a spent r onto the flo dent Report) 200 gallons o ne Building soils outsid ly 25 gallons Incident Rep al Water Inj ctor coolant ted several in ardous liquid d in the plan ks. A majo rolled and re n, control a daries to con tructures. M nd maintenan iryland LAC al failed fuel tor and supp operation o tivity (LSA) s surrounding his facility. T designated a rib House, L minated liqui elease pathw Waste W
: m. (DPC-81 resin liner w oor of the S of condensat g floor, and de the Turbi s of contam port, LER 82 njection Syst to be discha ncidents inv ds to the en nts various ority of the emediated in and remedia ntrol and con Many of these nce activitie C-TR-138, I incidents at ort systems.
of the facilit
) Building, g these build This area is as impacted.
LACBWR A id from the T way to the C Water Tank 1-10 Inciden which resulte Spent Resin te water was approximate ine Building minated liquid 2-016) tem leak at arged to the volving the u nvironment.
systems to t incidents oc n accordance ation of haz ntain the rad e systems an es during the Initial Site t LACBWR ty include R WGTV, and dings have a defined by t This area i Administrati Turbine Bui Circulating W overflowed nt Report) ed in the sp Liner Room s released fr ely 20 gallo g door and T d was discha 1A FCP ca Reactor Bui unplanned sp These inci the spill of d ccurred insid e with the st zardous ma dioactive con nd structures e operationa Characteriz and the pote Reactor Buil d the Ventil also been de the LSE fenc includes anc ion Building ilding Water d and pill of m and rom a ons of Truck arged aused ilding pill or idents diesel de of tation aterial ntents have al and zation ential
: lding, lation emed ce.
cillary g and  


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.
La Cross License T Revision In additi support impacted LSE whi the LSE 2.1.6. In As part o into preli and exist 2.1.6.1.
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.
The entir larger ph classifica efficient identified were clas and are id were clas current c 2.1.6.2.
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.
The surv or open l were deli radioactiv relatively appropria The surv Prior to accordan sizes for The deco segmenta the excep any struc survey u These ob volume c In additio the purpo se Boiling W Termination n 0 ion to the a buildings, t d to provide ich is consid areas compr nitial Surve of the HSA p iminary surv ting survey d Surve re 163.5 acr hysical sectio ation. Surv and practic d in the area ssified as n dentified in ssified as im lassification Surve vey areas wer land area tha ineated to ph vity to the e y compact sh ate for the si vey units est characteriza nce with the g survey units ommissionin ation, remov ption of stru cture will re units have be bjectives inc contained on on, the surve ose of chara Water Reactor Plan area within the open lan a buffer zon dered non-im rising approx ey Areas/Un process, the i vey areas an data.
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.
y Areas res licensed ons of the sit vey area size cal size need
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. Survey ar on-impacted the HSA. S mpacted. F ns by area.
a          Th he results off the analysiss are presentted in Table 2-11.
y Units re further di at is surveye hysical areas extent practi hapes and hi ite operation tablished by ation, survey guidance pro s for FSS.
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.
ng approach val and dispo cture basem emain at sit een establish clude provid nsite, and dis ey units estab acterization p r
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.
the LSE an nd immedia ne between t mpacted. Th ximately 1.5 nits and Clas impacted LA nd assigned site was div te that may e was deter ded to boun reas that hav
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.
: d. These ar Survey areas Figure 2-1 p vided into su ed and evalu s with simila cal. To the ghly irregula nal history or the HSA w y unit sizes f ovided in M that will be osal of all im ment floors an te closure a hed for struc ding survey d sposition opt blished for s planning and 2-9 nd the open ately surroun the LSE and he licensed s acres of the ssification ACBWR stru area classifi vided into su contain one rmined base nd the latera ve no reason reas have no with reason provides an i urvey units.
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.
uated as a sin ar operationa extent prac ar shapes we r the site top were used as for Class 1 o ARSSIM, se e implement mpacted sys nd walls that and consequ ctures to fac data for rem tions for the structures tha d do not cor land areas unding the L d the G-3 lan site comprise e owner cont uctures and o ications base urvey areas.
Alarm seet-points for the instrumment were sett at the obseerved backgrround plus tthe MDCR oof the instrumen  nt. No scan alarms weree observed.
or more sur ed upon the al and verti nable potenti o radiologica nable potenti illustration o A survey u ngle entity f al history or ctical, survey ere avoided u ography.
2-26
initial surve open land su ection 4.6 fo ted at LACB stems and ab t reside 3 fee uently, be su cilitate other mediation pla waste.
at are 3 feet rrespond to surroundin LSE fence nd and facil es a total of trolled area.
open land ar ed on the op
. Survey ar rvey units de specific ar ical extent o al for residu al impact fro ial for residu of the LACB unit is a port following FR similar pote y units were unless the un ey units for urvey units or the sugges BWR calls bove-grade et below gra ubjected to r characteriz anning, estim below grade the survey u g the LACB is designate lities south o f 163.5 acres reas were div perational hi reas are typi epending on rea and the of contamin ual contamin om site opera ual contamin BWR site an tion of a stru RS. Survey ential for res e established nusual shape characteriza were adjust sted physical for the com structures.
ade, no porti FRS. How zation objec mating the w e are intende units that w BWR ed as of the s with vided istory ically n their most nation nation ations nation nd the ucture units sidual d with e was ation.
ted in l area mplete With ion of
: wever, tives.
waste ed for will be


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.
La Cross License T Revision used for section 5 Tables 2-impacted site struc 2.1.6.3.
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.
The follo React Turbi (L10 LSA North The basis soil by r spills of packages Based on subsurfac the unres 2.1.6.4.
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.
The follo LACB (L20 G-3 C (L20 Based up surveys p radioactiv Class 2 o 2.1.6.5.
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.
The follo North Trans Plant se Boiling W Termination n 0 the FRS o
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.
.5.2 of Chap
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.
-1 and 2-2 p d structures ctures. A sum Class owing open l tor Building ine Buildin 10102),
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.
Building, M h LSE Area s for this cla radioactive m radioactive s and contain n an assessm ce soils in th stricted use c Class owing open l BWR Adm 11101),
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
Crib House, 11102).
pon a review performed in ve contamin open land sur Class owing open l h End of Lic smission Sw t Access, ISF Water Reactor Plan f remaining pter 5).
provide a de respectively mmary of th 1 Open Lan land areas ha g, WTB, WG ng, Turbine Maintenance (L1010104) assification is material in t liquids and ners.
ment of histor hese areas c criteria. Clas 2 Open Lan land areas w ministration LACBWR w of the hist n these area nation to exc rvey units ar 3 Open Lan land areas w censed Site (L witchyard Are FSI Haul Ro r
g below grad etailed list o
: y. Figure 2-2 he survey uni nd Areas ave been cla GTV, Ventila Office Bu Eat Shack G s due to a se these areas d resins, radi rical inciden could possibl ss 1 open lan nd Areas were classifie
: Building, Circ. Water torical inform as as docume eed the unre re shown on nd Areas were classifie L3012101),
ea (L301210 ad Grounds 2-10 de structure of the survey 2 provides a it classificati assified as im ation Stack G uilding, 1B Grounds (L10 ries of docum during facil ioactive sys nts and event ly contain re nd survey un ed as impacte LACBWR Discharge L mation and ented in the estricted rele Figure 2-1.
ed as Class 3 02),
(L3012109) es (designate y units for b a detailed in ions are pres mpacted Clas Grounds (L1 Diesel G 010103),
mented incid lity operation stem leakage ts, it was an esidual radio nits are show ed Class 2:
R Crib Ho Line, Area S operational HSA, there ease criteria.  
).
ed as STS a both the ope nventory of sented as fol ss 1:
010101),
Generator Bu dents of the ns. These i e, and storag nticipated tha oactive mate wn on Figure ouse, Ware South of LSE radiation an e was a pote and discuss en land area the building llows.
uilding Gro contaminati incidents in ge of radioa at the surfac erial in exce e 2-1.
ehouse Gro E Fence Gro nd contamin ential for res ed in s and g and ounds ion of clude active e and ess of ounds ounds nation sidual


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.
La Cross License T Revision Historica in concen Class 3 o 2.1.6.6.
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.
Based on in the HS contamin G-3 C Coal Capp Grou Hwy The non-2.1.6.7.
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.
The follo structure These str radioactiv radioactiv majority React Wast Venti Wast Turbi Diese LSA Main Througho spread o were rou structure structura below gr subjected se Boiling W Termination n 0 al informatio ntrations in e open land sur Non-I n a review o SA, the bala nation and ha Coal Plant G Pile Ground ped Ash Imp unds East of H 35/Railroad
No scan alarms weree observed in  n these surveey units.
-impacted op Class owing is a li
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.
: s. The com ructures con ve waste sy ve material of the curren tor Building te Treatment ilation Stack te Gas Tank ine Building el Generator Building (B ntenance Eat out facility o f loose surf utinely post s involves l material as rade, no por d to FRS. Th Water Reactor Plan on contained excess of the rvey units ar Impacted Op f the operati ance of the as been desig Grounds (L40 ds (L401210 oundment G Highway 35 d Right of W pen land surv 1 Structures ist of the m mplete list of ntain the nuc ystems, and n was routine nt radioactiv g (B1010001 t Building (B k (B1010003 Vault (B101 g (B1010005 r Building (B B1010007)
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.
Shack (B10 operations, th face contam ted as cont the comple s waste. Wi rtion of the he Class 1 st r
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.
d in the HSA e unrestricted re shown on pen Land Are ing history o 163.5 acre li gnated as no 012103)
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.
: 5)
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.
Grounds (L40 5 (L4012107 Way Grounds vey units are s
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.
major buildin f all impact clear reactor nuclear fuel ely handled, ve material in
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
)
B1010002)
: 3) 10004)
: 5)
B1010006) 010008) hese structur ination, and taminated a ete segment ith the excep se structure tructural surv 2-11 A indicated th d release cri Figure 2-1.
eas of the facility icensed site on-impacted.
012106)
)
(L4012108) e shown on F ngs that were ted structura r, primary re l handling a
, transferred nventory at L res were sub d airborne ra areas. The tation, remo ption of stru s will rema vey units are hat the prese teria was no y and histor has no reas
)
Figure 2-1.
e initially cl al survey un eactor system and storage s d, and stored LACBWR r bjected to spi adioactive m decommis oval, and d uctural floor ain at site cl e depicted in ence of resid ot expected.
rical incident sonable pote lassified as nits is provid ms, reactor systems. D d within the resides in the ills of radioa material. St sioning app disposal of s and walls losure and a n Figure 2-1 dual radioac ts as docum ential for res impacted Cl ded in Table support sys uring operat ese building ese structure active liquid tructural sur proach for all systems that reside 3 are therefor ctivity ented sidual lass 1 e 2-2.
: tems, tions,
: s. A es:
ds, the rfaces these s and 3 feet re not


La Crossse Boiling Water W      Reactorr License Termination T               Plan Revision n0 presented d in Table 2-15.
La Cross License T Revision 2.1.6.8.
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.
The follo Class 2 o complete LACB G-3 C LACB LACB LACB LACB Back Trans G-1 C Barge These str structure LACBW Washing structure Administ the decom LACBW structure The LAC Switch H unrestrict Supplem Manual depicted Based on in the H section 2 residual the G-3 C 2.2.
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.
C From Oc accordan se Boiling W Termination n 0 Class owing is a li or 3 structur e list of all im BWR Crib H Crib House (
A full lisst of G-3 struuctures that have been designated d            ass non-impaacted is provvided in Tabble 2-2.
BWR Admi BWR Wareh BWR Wareh BWR Wareh k-up Control smission Sub Crib House (
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.
e Washing B ructures did s associated WR workers g Break Room s because th tration build mmissioning WR Class 2 or s will remain CBWR Adm House will n ted release ment 1, Multi (MARSAM in Figure 2-n a review o HSA, coup 2.3.5), the bu contaminatio Crib House, Characteriza ctober 2014 nce with th Water Reactor Plan 2 and 3 Stru ist of some res. All are mpacted stru House (B201 (B2010102) nistration Bu house #1 (B2 house #2 (B2 house #3 (B2 Center (B30 b-Station Sw (B3012103)
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.
Break Room not routinely d with LAC and therefo m were not a hey reside i ding, the G-3 g approach c r 3 systems n at site clos ministration b not be subj using a gr i-Agency Ra E) (8). The
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:
-1.
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.
f the operati pled with t uildings ass on and have will remain ation Appro through Aug he Characte r
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
uctures of the major e located wi uctural surve 10101) uilding (B20 2010104) 2010105) 2010106) 012101) witch House (B3012104) y house radi CBWR listed re considere associated w in a Class 3 3 Crib Hous calls for the and structur sure and ther building, the ected to FR raded survey adiation Sur e Class 2 an ing history o the results sociated with e been desig intact and fu oach gust 2015, s erization Su 2-12 r buildings t ithin the lice y units is pro 010103)
MDC off 2,816 dpm//100cm . The       T results of  o the direcct beta-gamm  ma and alphha measurem    ments 2
(B3012102)
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
ioactive syst d above are ed Class 2 with LACBW 3 land area.
se and the T complete se ral material a refore will n e G-3 Crib H RS. Instead y approach rvey and As nd Class 3 s of the facility of charact h the G-3 s gnated as no unctional for site characte urvey Plan.
that were in ensed site b ovided in Ta
)
tems or mate outside of or 3. The WR operation With the Transmission egmentation, as waste or ot be subjec House and th d, these stru using the ssessment of structural su y and histor terization su station have on-impacted.
r G-3 power erization of L The Ch nitially classi but outside o able 2-2.
erials during the LSE bu G-1 Crib H ns but are co exception o n Sub-Statio
, removal, an salvage. No ted to FRS.
he Transmis uctures will guidance o of Materials urvey units rical incident urveys (as no reasona
. The G-3 s r operations.
LACBWR w haracterizatio ified as imp of the LSE.
g operations.
ut were use House and B onsidered Cl of the LACB on Switch H nd disposal o portion of ssion Sub-St be surveye f NUREG-s and Equip for building ts as docum summarize able potentia station, inclu was perform on Survey pacted The The ed by Barge lass 3 BWR
: House, of all these tation d for
: 1575, pment gs are ented ed in al for uding med in Plan


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.
La Cross License T Revision incorpora documen develope executing procedur safely an Characte objective Provi Deve Supp volum The deco buildings character subjected removed 1757, Ap The char subsurfac structura surveys w structure used to m above gr of the ex
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.
: planned, planning A signifi unit is cla design fo result in unit meet errors.
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.
As site-s LACBW selected.
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.
in NURE Paramete assess the se Boiling W Termination n 0 ated the pre nted in the su ed to provide g characteriz res and surv nd effectively rization data es:
After com mmodity rem  moval is com  mplete, the structures thaat will remaiin at license terminationn, i.e.,
ide radiologi elop the requ ort the eva mes.
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.
ommissionin s, structures, rization effo d to FRS. E prior to the ppendix O.
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.
racterization ce soils, pav l basements were perform
2-30
: s. Upon com make determ rade or subg xpected end-executed an icant questio assified corr or FRS. A a survey des ts the release pecific Deri WR at the tim The screen EG/CR-5512 er Analysis e correct cla Water Reactor Plan evious histo urvey areas e guidance a zation survey ey unit spec y acquire the a acquired th ical inputs n uired inputs f aluation of r ng approach
, and compo orts focused Extensive ch e performanc n surveys fo ved surfaces, s that will re med in the L mpletion, the minations on w rade structu
-state structu nd documen on that must rectly. The a classificatio sign that doe e criteria. In ived Concen me the chara ning DCGLs 2 Volume 3 (9), Table 6 assification o r
orical opera from the HS and direction y activities.
cific survey e requisite ch hrough the e necessary for for LTP, and remediation for LACBW onents to a d d on open haracterizatio ce of final s ocused on g
, and concret emain in the LACBWR Ad e data was a whether add ures, surface ures at LAC nted with the be answere appropriate c on which un es not obtain n some cases ntration Guid acterization s presented i
, Residual R
.91 (Pcrit = 0 of impacted o 2-13 ational and SA and prev n to the pers The Plan w instructions haracterizati execution of r the design o d
alternatives WR calls for t depth of at l land areas on of equipm surveys is no general open te pads. Co e end-state dministration ssessed for q ditional chara and subsurf CBWR. Con e same data ed by the cha classification nderestimate n adequate in s, this can in deline Level survey was in NUREG-1 Radioactive 0.10) for soil open land or radiological vious site ch sonnel respo worked in co s (sample pl on data.
the Plan wa of FRS, s and techn the demoliti least 3 feet b and remain ment, system ot required i n land areas oncrete core condition.
n Building a quality and a acterization face soils, or ntinuing cha quality and aracterizatio n of a survey es the poten nformation to ncrease the p ls (DCGLs) performed, 1757 and th Contamina ls were used r soil survey l informatio aracterizatio onsible for im njunction w lans) that w as used to m nologies and ion and remo below grade ning structu ms or struct in accordanc s including:
samples wer In addition, and several o adequacy. T data is requ r beneath th aracterization d the results on is whethe y unit is crit ntial for con o demonstra potential for m were not ye alternate ac e concentrat ation from D d as alternat units.
on collected on efforts. I mplementing with impleme were develop meet three pri d estimate w oval of all on
: e. Conseque ures that wi tures that w ce with NUR site surface re taken from
, characteriz of the G-3 st The data was uired, primar he concrete f n surveys w included in er or not a su tical to the su tamination c ate that the su making deci et establishe ction levels tion values f Decommissio e action leve d and t was g and enting ped to imary waste n-site
: ently, ill be ill be REG-e and m the zation tation s then ily of floors will be n FRS urvey urvey could urvey isions ed for were found oning els to


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.
La Cross License T Revision For struc to evalu 7,100 dpm Appendix radionuc the conse for Cs-13 2.2.1. D DQOs w FRS. Ho to determ unrestrict inspectio nature, e applicabl Characte outlined
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.
: 1) State
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.
: 2) Ident
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.
: 3) Ident
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.
: 4) Defin
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.
: 5) Deve
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
: 6) Speci
: 7) Optim The DQO collect. N and will assessme obtaining obtained Direct m Minimal that exhi Detect (H 2.2.2. S Characte approved approach se Boiling W Termination n 0 ctures, the gr ate the clas m/100cm2 to x H. Use of lide distribu ervative appr 37 is signific Data Quality were impleme owever, the mine the rad ted use crit ons and surv xtent and ra le structures rization surv in MARSSIM the problem tify the decis tify inputs to ne the study elop a decisio ify limits on mize the des Os for site No structure therefore no ent of concre g core samp to determin measurement Detectable ibited the hi HTD) radion urvey Desig rization sur d procedures h based upon Water Reactor Plan ross screenin ssification o otal gross be f the Co-60 ution for surf roach was to cantly greate y Objectives ented for ch goal of char ionuclide m teria to dem veys of suff ange of radio
, residues, so veys were de M, Appendi m,
: sion, o the decision boundaries, on rule, n decision err ign for obtai characteriza es located ab ot be subject ete in basem ples. Soils ne the mean s and scans Concentrati ighest activi nuclide(s).
gn rveys were s and the Cha n the DQOs f r
ng level that of survey u eta-gamma s screening v face contam o assume a d er.
s haracterizatio racterization mixture, wher monstrate co fficient quali oactive cont oils and surf esigned to g ix D. The se n,
rors, and ining data.
ation include bove 3 feet b ed to FRS.
ments and su were sampl and maximu s of surface ons (MDC) ity were sen designed a aracterizatio for each surv 2-14 t was used d units was th surface activ value was co mination wou distribution o on surveys in n is to quanti reas the FRS ompliance w ity and qua tamination in face water.
gather the ap even steps in ed identifyin below grade Consequent urrounding so led volumet um activity a soils were as will be e nt to an off-and perform on Survey Pl vey unit. Fo during chara he nuclide-vity based on onservative a uld be princi of 100% Co n a similar m ify and delin S goal is co with 10 CFR antity were n each appli propriate da n the DQO d ng the types will remain tly, sample c oils. Buildi trically. Su as well as th made using employed fo
-site laborat med in acco an. Survey or example, acterization a specific scr n Co-60 from as it was an ipally Co-60
-60 since the manner as an neate contam omparison of R 20.1402.
performed t icable surve ata using the development s and quanti n following d collection wa ing concrete ufficient me he sample sta g the same or FSS. Vo tory for ana ordance wit design incor an open land as an action reening valu m NUREG-nticipated tha 0 and Cs-137 e screening v nticipated fo minated area f data agains Characteriz to determin ey unit, inclu e DQO proce process are:
ities of med decommissio as focused o e was sample asurements andard devia instruments lumetric sam lysis of Har th all appli rporated a gr d survey uni level ue of
: 1757, at the 7 and value or the as and st the zation e the uding ess as dia to oning on the ed by were ation.
s and mples rd-to-icable raded it was


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.
La Cross License T Revision designate the unres Class 1 s present.
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
to identif Class 2 o survey m select loc measurem biased su unit. A delineate warrante survey un The area character S
observed d reading of 72 7 dpm/100ccm .
al su B
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
sy F
from lesss than MDC  C of 113 dpmm/100cm to   o a maximum    m observed reading of 1152 dpm/1000cm2.
R ad S
Direct beeta-gamma measurement m            ts taken on the t floor draain openingss ranged from m less than M MDC 2
A S
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.
S ar S
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.
C P
e            T The informattion containeed in this seection was deriived directly  y from Haley & Aldriich, Hydroggeological C      Conceptual SSite Model (17).
A L
Haley & Aldrich, Hyydrogeologiccal Investiga    ation Reportt for the LaCCrosse Boilinng Water Reeactor (18) suppplements thee preliminary y findings in n Reference 117.
2.2.2.1.
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 num by assess se Boiling W Termination n 0 ed as Class stricted relea survey unit f The survey fy the lateral or Class 3 re measurement cations for s ment and/or urvey design A biased app e the extent o d if the char nit.
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.
as and mater rization surv urface scans ll Class 1, 2 urvey unit L Biased subsur ystems of c igure 2-3.
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.
Random sam ddition, soil cans and s Administratio amples were cans and sam reas.
2-32
cans and sam Concrete sam iping and V A backgroun LACBWR in Numb mber of measu sing the sam Water Reactor Plan 1 because it ase criteria.
focused on b design was l and vertica eceived surv locations an static measu sample loc n or a random proach was of an area th racterization ials surveye vey included s and random 2, 3, and no L3012102 (i.e rface soil sa oncern in C mples were ta samples we amples wer on Building e taken from mples were mples were t mples were t entillation tu nd radiation cluding: asp ber of Static urements an ple size nece r
t may conta Therefore, t bounding the based upon al extent of th veys develop nd scan area urements and cations at ran m approach warranted hat requires effort was d ed and/or sam m and biased on-impacted e., the switch amples were Class 1 and aken from a ere obtained re taken on and the G-3 m the septic ta taken on LA taken on G-3 aken in the unnels.
study was phalt, concret Measuremen nd/or sample essary to sat 2-15 ain levels of the character e contaminat n the number he contamin ped to includ
: s. Biased su d/or samples ndom. The was address when the c remediation designed to v mpled in and d surface and open land a hyard).
taken along 2 areas incl asphalt and c directly belo n accessible Coal Plant.
anks.
ACBWR Ad 3 Building a basement ar performed te, and soil.
nts and/or S s that were t tisfy the DQO f radiologica rization surv tion where c r of measure nation. Area de a combin urvey design
: s. Random e decision of sed by the D characterizat
: n. Alternativ verify the ba d around the d subsurface area survey gside and un luding the p concrete from ow the aspha e roof surfa dministration access and he reas of the R on material amples taken in each Os.
al contamina veys that wer ontaminatio ements and as classified nation of ran ns used know survey desig f whether to DQO process tion effort w vely, a rando asis for the c e licensed ar e soils samp units with derneath und piping syste m pads and alt to a one m ace areas of n Building su eavily travel Reactor Bui ls similar to h survey uni ation greater re performed n was poten samples req as non-impa ndom and b wn informati gn selected o use primar s for each su was designe om approach classification rea as part o ples were tak the exceptio derground p ms as show paved area meter depth.
f the LACB urfaces and led surfaces.
lding, WTB o those foun it was determ r than d in a ntially quired
: acted, biased ion to static rily a urvey ed to h was n of a of the ken in on of piping wn on
: s. In BWR drain B, and nd at mined


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.
La Cross License T Revision For the c that will and/or sa of residu For the sample s vertical e For non-validate measurem trivial lev generated 2.2.2.2.
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.
For the c survey u Sample l to specifi that wer responsib survey d radioactiv potential from the 2.2.2.3.
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.
Survey u area to b area scan Supervis was give survey un 2.2.2.4.
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..
The char (beta and survey of FRS con and volu sampling following se Boiling W Termination n 0 characterizat be subjecte amples taken al radioactiv characteriza size was bas extent of the impacted an the basis ments and/o vels of licen d radionuclid Determ characterizat nits that wil locations we ic locations w re taken in ble Radiolog design proc vity, depres spill locatio HSA aided Scan C units were sc be scanned i nned was c or and/or th en to inform nit.
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.
Types racterization d gamma); st f any concre nsisted of a c umetric samp g of surface g is a descrip Water Reactor Plan tion of impa ed to FSS, th n in the surve ve contamina ation of Cla sed upon the contaminati nd Class 3 op of the clas or samples w nsee-generat des are prese mination of tion of non-ll be subject ere determin within the su each surve gical Protect cess. Con sions, disco ons, or areas in the select Coverage canned to th n each surv ontingent up e Project He mation from s of Measure n survey of tatic beta me ete and/or as combination ples. The su and subsurf ption of the d r
2-33
acted Class 1 he minimum ey units wer ation in the s ss 1 structur e necessary n ion.
pen land sur ssification.
was sufficie ted radionuc ent in non-im Static Measu
-impacted an ted to FRS, ed by gener urvey unit. T y unit was tion Superv sideration w olored areas, s where the tion of biased he extent pr ey unit was pon the pro ealth Physic the initial w ements and S building sur easurements phalt-paved n of surface urvey of the face soil, sed different typ 2-16 1 and Class m number of re commensu survey unit.
res that wil number of s rvey units, th Consequen ent to ensure clides are pr mpacted area urement and nd impacted sample loca ating random The location determined visor and/or was given
, cracks, low ground has d locations.
actical in ac determined ofessional ju ist during th walk downs Samples rfaces consi s, material sa open land a scans (beta e open land diment and s pes of measu 2 open land f random or urate with th l remain an samples nee he primary c ntly, the nu e with reaso resent in Cl as.
d Sample Lo d open land ations were m pairs of c n of biased m d by the pr the Project to location w point grav s been distur ccordance w d during the udgment of he survey de and the am isted of a co amples and s areas that wi and gamma areas consis surface wate urements and d areas (pav r biased dire he probabilit nd be subjec eded to asses characterizat umber of s onable conf lass 3 areas ocations areas and C primarily ch oordinates t measurement rofessional j Health Phy ns that exh vity drain p rbed. Histo with their cla survey desi the Radiolo esign proces mbient radiat ombination smears. The ill remain an a), static bet sted of gamm er for isotop d samples tha ved and unpa ect measurem ty of the pres cted to FRS ss the latera tion DQO w systematic fidence that and no lice Class 2 struc hosen at ran hat correspo ts and/or sam judgment o ysicist durin hibit measu points, actua orical inform assification.
ign process.
ogical Prote
: s. Consider tion levels i of surface e characteriz nd be subject ta measurem ma scans an pic analysis.
at were utiliz aved) ments sence S, the al and was to static only ensee-ctural ndom.
onded mples of the ng the urable al and mation The The ection ration in the scans zation ted to
: ments, nd the The zed.  


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.
La Cross License T Revision 2.2.2.4.1 Gamma activity.
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.
used for Ludlum M Ludlum M Scanning rate not t was main and, loca 2.2.2.4.2 Scanning 7,100 dpm including Hand-hel used.
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.
Beta scan and with prevented was dete calculate of the sur If not im instrumen evaluatio investiga 2.2.2.4.3 Direct m surfaces typically detectors Direct m acquiring typically designate adjusted 2.2.2.4.4 If applic verify lo se Boiling W Termination n 0 Gamm scans were Sodium io these scans.
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.
Model 44-10 Model 44-10 g was perfor to exceed 0.
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 &#xb5;Ci/ml
ntained with ations of elev Beta S g was per m/100cm2 a g, but not li ld beta scin nning was p h a scanning d scanning a ermined, an d a priori to rvey.
          &#xb5;      to 9.0E-08 &#xb5;Ci/m  ml).
mpacted by h nt to identi on. Any ide ation and pot Direct measurement of the build performed
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.
: s.
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.
measurements g data over used for su ed investigat as appropria Remo able, remov oose surface Water Reactor Plan ma Surface S performed o dide (NaI) g EnergySol 0 Detector 0 NaI detecto rmed by mo
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.
.5 m (20 in) hin 15 cm (6 vated direct l Surface Scan rformed in action level.
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.
imited to; fl ntillation and performed w g speed of o at the specif nd the scan o ensure that high ambient fy locations entified areas tential decon t Measureme ts were per dings or on using ~10 s were condu a pre-determ urface measu tion level or ate to achiev ovable Surfac vable beta an e contamina r
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.
Scans over open la gamma scin utions Techn Sensitivity (
2-34
ors to Co-60 oving the de per second.
in) of the s levels were f ns order to Beta scans loors, walls, d/or gas-flo with the dete one detector fied distance nning techni t the MDC f t noise level s of elevate s of elevated ntamination.
ents rformed to n concrete o 00 cm2 or l ucted by pla mined coun urements and r MDC und ve an accepta ce Contamin nd/or alpha ation is less 2-17 and surfaces ntillation det nical Suppor (10) examin 0 and Cs-137 etector in a s The distan urface if po flagged for f locate ar s were perfo
, ceilings, ro ow proportio ctor position r active win e, the detect ique adjuste for scanning s, technician d activity th d contamina detect total or asphalt pa arger sized acing the det nt time. A d generally p er considera able MDC fo nation contaminati s than the to identify tectors (typic rt Document nes the resp 7 when used serpentine p nce between ssible. Aud further inves reas of res ormed over a oofs, asphal onal detecto n maintained ndow per se tion sensitiv ed accordin g was approp ns monitored that require ation were m levels of aved areas.
scintillatio tector near t count time provided det ation. The i or direct mea on or smear applicable locations of cally 2 x 2 t (TSD) RS-onse and sc d for scanning pattern, whil n the detecto dible signals stigation and sidual activ accessible st lt and concr ors (typically d within 1 c econd. If su vity for the a ngly. Scan priate for the d the audibl further inv marked or fla contaminati These me on or gas-fl the surface to of one to t tection level instrument c asurements.
r surveys w action level f residual su
) were typi
-TD-313196 can MDC o g surface soi le advancing or and the su were monit d/or sampling vity above tructural sur rete paved a y 126 cm2) cm of the su urface condi alternate dis nning speed e stated obje e response o estigation a agged for fu ion on struc asurements low proport o be counted two minutes ls well below count times were perform
: l. A smea urface ically 6-006, of the ils.
g at a urface tored;
: g.
the rfaces areas.
were urface itions stance was ective of the and/or urther ctural were tional d and s was w the were med to ar for


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.
La Cross License T Revision removab surfaces.
C        Analy ysis for H-3 was perform med on site.
moderate activity a 2.2.2.4.5 Concrete contamin will rema diamond 1/2-inch w pulverize 2.2.2.4.6 Samples locations scanning defined a split spoo tools.
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,
Subsurfa hand aug survey un 2.2.3. In The radi provide b identified action le and expe static me Concern Commer perform
                                                  # 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.
: 3) analys Instrume in Table 2.2.3.1.
r Addition nal details, in ncluding thee off-site anaalytical laborratory reporrts are provided in Referrence 18.
All data character se Boiling W Termination n 0 le activity w A 100 cm e pressure. S as appropriat Concr e core boring nation and th ain and be su bit core dri wide pucks ed and analy Mater of soil, sed s as well as
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.
: g. Surface so as soil below on sampling ace soil was gers. Subsur nit.
The colleected informmation during g each monittoring intervval includes:
nstrumenta ation detect both reliable d for the de evels. Detec ected perform easurements (ROC) at a cially availa the three ba sis of materia ntation and 2-3.
Depth D      to grouund water in the respectiive monitorinng well.
Calibr loggers, ass rization wer Water Reactor Plan was usually m2 surface a Smears were te.
Monitoring M            well w groundw    water pH/speecific conducctance/oxidaation and redduction potential/turb bidity/dissolvved oxygen/ttemperature..
rete and Asp g and the sa he presence ubjected to F ill. The con s, represen yzed for isoto rial Sampling iment, and s other locatio oil is defined w the top 15 g system or, b sampled by rface soil sam ation Selectio tion and me e operation a ecommission ctor selectio mance in th and scanni MDC of 50%
Radiological R              sample inforrmation inclluding a com  mpleted chainn of custodyy following grroundwater sample colleection.
able portable asic survey m al samples.
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.
nominal MD ration sociated dete re calibrated r
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.
taken at eac area was sa e then analyz phalt Core Sa ampling of of volumet FRS. Core b ncrete samp nting a certa opic content.
Sr-90 was w also positively detected in wells    w        MW-2002A, MW-2203A and MW-204A with 2-35
g sludge were ons in areas d as the top cm layer in by using han y direct push mpling was on, Use and asurement i and adequate ning of LAC on was based e field. In ng were cap
% of the app e and laborat measuremen DC values th ectors, and a d on an annu 2-18 ch direct me ampled with zed for the p ampling concrete we tric contami bore samplin le produced ain depth in obtained fr s exhibiting 15 cm (6-in n 1 m increm nd trowels, b h sampling s performed a d Minimum nstrumentat e sensitivity t CBWR at le d on detecti all cases, th pable of det plicable actio tory instrum ts: 1) surfac hat were em all other por ual basis us easurement l h a circular presence of g ere used to nation in co ng of concre d by the cori nto the surf rom designed elevated act nch) layer of ments. Surfa bucket auger systems (e.g as necessary Detectable tion for char to detect the evels suffici ion sensitivi he instrumen tecting the a on level.
ments and det ce scanning; mployed durin rtable instrum sing Nationa location on cloth or pa gross beta an assess the d oncrete wall ete was acco ing was typ face. Conc d biased and tivity that w f soil while s ace soil was rs, or other s
: g. GeoProbe y to address t Concentrat racterization e initial suite iently below ity, operatin nts and detec anticipated R tectors were
: 2) static me ng character mentation th al Institute o non-asphalt aper filter, u nd/or gross depth of sur ls and floors omplished us pically sliced crete pucks d random sa were identifie subsurface s collected us suitable sam
) or by m the DQOs fo tions (MDC n was select e of radionuc w the establ ng characteri ctors selecte Radionuclid typically us easurements rization are hat were use of Standards t type using alpha rficial s that sing a d into were ample ed by soil is sing a mpling anual or the Cs) ted to clides lished
: istics, ed for des of sed to s; and listed ed for s and  


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.
La Cross License T Revision Technolo addressed 2.2.3.2.
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.
The recei used for portable character 2.2.4. L Gamma proportio laborator quality p preparati site labor In all ca achieved accepted analytica laborator 2.2.5. Q MARSSI used to quality fo 1576, Mu Regulato through (12). Fu may be achieved The QAP used duri functiona All chara approved audit a
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:
Characte prescribe applied contracto se Boiling W Termination n 0 ogy (NIST) t d in the QAP Instru ipt, inspectio characteriza radiologica rization is ad Laboratory I spectroscop onal countin ry in accorda programs of ion and analy ratory under ases, analyti
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),
: d. The anal methodolog al methods ries used for Quality Assu IM, section demonstrate for sample an ulti-Agency R ory Guide 4.
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.
Normal Op urther, MAR used in add
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.
: d.
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
PP was prep ing the site c al activities, acterization d procedures and surveil rization staf ed, impleme to any app ors.
Water Reactor Plan traceable sou PP.
ument Use an on, issue, co ation was p al instrumen ddressed in th Instrument py was prim ng and liquid ance with ap the contrac ysis of chara the QAPP.
ical methods lysis of rad gies or othe employed characteriza urance 2.2 discusse e that site c nalysis taken Radiologica
.15, Quality erations to RSSIM and dition to, or pared and im characterizat the DQO pr activities es
: s. The effe llance activ ff and progr ented, and v plicable serv r
urces. The c nd Control ntrol, and ac performed in ntation. T he QAPP.
Methods an marily perfor d scintillatio pproved labo cted off-site acterization s s were estab diological co er comparab and the la ation.
es the need f conditions ar n to support al Laboratory y Assurance License Ter MARLAP b r in lieu of, mplemented t tion and FRS rocess, and m ssential to d ective imple
: vities, incl ram self-ass verified wh vices provid 2-19 calibration o ccountability n accordance The issue a nd Sensitivi rmed by th on analysis oratory proce vendor labo samples prov blished to e ontaminants ble methodo aboratory M for a quality re acceptabl t characteriz y Analytical of Radiolo rmination) -
both indicate existing qu to ensure th S process. T measures nec data quality w mentation o luding fiel sessments, a hen deficienc ded by off-of instrument y of portable e with issue and control ities he on-site ra was perform edures. Ener oratories tha vided the sam ensure that used stand ologies. Ta MDC achiev y system to le for unres zation and F l Protocols M ogical Moni
- Effluent St e that a Qua uality system e adequacy The QAPP de cessary to ac were implem of characteri ld walk-do as appropriat cies were i
-site vendor ts used for c e radiologica e and contro l of instru adiological med by an rgySolutions at were used me level of required M dard approve able 2-4 prov ved by the ensure the a stricted rele FRS is discu Manual (MA itoring Prog treams and ality Assura ms to ensur of data bein escribes poli chieve qualit mented and ization was owns by te. Correct identified.
rs, as well characterizati al instrument ol procedure uments used laboratory.
approved ve s ensured tha d for the rec quality as th MDC values ed and gene vides the ty off-site ve adequacy of ase. Labor ssed in NUR ARLAP) (11 grams (Incep the Environ ance Project re data qual ng developed icy, organiza ty data.
performed u verified thr EnergySolu tive actions These mea as on-site ion is tation es for d for Gas endor at the
: ceipt, he on-were erally ypical endor f data ratory REG-
) and eption nment Plan ity is d and
: ation, using rough utions were asures sub-


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.
La Cross License T Revision The Cha quality a and is su follows:
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.
E op A
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.
st D
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.
Details o the proce data acqu requirem P
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:
E P
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.
S P
a 2.5. References R
M pr All chara Plan, the 2.3.
: 1.       U.S.
S In Octob placing t October character accelerat EnergySo October 9 August 6 documen Characte PN-1640 2015 Fie Radioact character character se Boiling W Termination n 0 aracterization assurance and ubject to the Establishmen perations.
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.
Actions to en taff.
: 2.       U.S.
Documentatio of the QA/QC edures and s uisition and ments. The sp ersonnel qua Execution in roper docum election of a roper instrum Management rocedures, p acterization QAPP, all a ummary of ber of 2005, the unit into of 2014, rization of L tion of de olutions in a 9, 2014. T 6, 2015. The nted in two erization Sur 017-001, LA eld Work (14 tive systems rization dat rization has Water Reactor Plan n Survey Pl d quality co QAPP. The nt/implement nsure that the on of the dat C elements s sample plan d recording pecific QA/Q alifications, accordance mentation of appropriate i ment calibra oversight of protocols, an activities w applicable im f Characteri Dairyland p o a SAFSTO Dairyland LACBWR in commission accordance w The schedule e results of th o separate rvey Report CBWR Radi 4).
U Nuclear Regulatory Commission          n, NUREG-11575, Revisiion 1, Multi--Agency Radiation R          Surrvey and Sitee Investigatiion Manual ((MARSSIM      M), August 20000.
s that rema a in certain been deferre r
: 3.       U.S.
lan was dev ontrol (QA/Q e QA/QC pr tation of plan e procedures ta collected.
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.
specific to ch instructions was guided QC program experience, with approv survey data instruments t ation and dai f characteriz d documenta were conduct mplementing ization Surv performed a OR condition contracted n anticipation ning activiti with EnergyS ed EnergyS he site chara reports, GG for October iological Ch ain at LAC n areas du ed until such 2-20 veloped acco QC) program ogram elem ns, procedur are understo haracterizati
: 4.      EnergySoluti E              ons PG-EO--313196-SV-PL-001, Chharacterizatioon Survey P        Plan for the L La Crosse C      Boilin ng Water Reaactor.
. The chara d and condu m component and training ved procedur and sample to perform th ily functiona zation activit ation require ted in accor g procedures vey Results limited cha
: 5.       EnergySoluti E              ons GP-EO--313196-QA    A-PL-001, Quuality Assurrance Projectt Plan LACB      BWR Site Characteerization Projject (QAPP)).
: n. This sur EnergySol n of the deve ies. Char Solutions cha Solutions sit acterization s G-EO-31319 r and Novem haracterizati CBWR affec ue to ambie h time that ra ording to th m for the dec ments applica res, and prot ood and foll ion are prese acterization o ucted in com s for site cha
2-37
: g.
res.
analyses.
he surveys.
al checks.
ties relative t ements.
rdance with
, and approv aracterization rvey is docu lutions to elopment of racterization aracterizatio te characteri surveys perf 96-RS-RP-0 mber 2014 F ion Survey R cted the ab ent radiatio adiological o he essential commissioni able to chara tocols for the lowed by the ented in the Q operations an mpliance wi aracterizatio to the adhere the Charact ved sample p n survey of umented in perform a f this LTP an n activities, on procedure ization effo formed by En 01, LACBW Field Work (
Report for J ility to acq on levels.
or physical c elements o ing of LACB acterization a e field e implementi QAPP, as w nd the assoc ith these QA on are as foll ence to terization Su plan instruct the LSE pri Reference 7 a more det nd the anticip
, performed es commence ort conclude nergySolutio WR Radiolo (13) and LC June thru A quire meani In these c conditions w of the BWR are as ing well as ciated A/QC ows:
urvey ions.
ior to
: 7. In tailed pated d by ed on ed on ons is ogical C-RS-ugust ingful
: cases, would


La Crossse Boiling Water W        Reactorr License Termination T             Plan Revision n0
La Cross License T Revision allow the the decom significan by revisio 2.3.1. B During t backgrou acquired backgrou As part o backgrou LACBW Normally be repres site area Supervis appropria results.
: 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)).
were con Concrete is located non-impa approxim unit L40 L401210 samples a The ana backgrou can be at mean Cs 0.135 pC was 0.07 Relevant Station (Z at Zion S Zion to C geograph for distu backgrou within th categorie drainage se Boiling W Termination n 0 e survey of t mmissioning nt additiona on or addend
: 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)
===Background===
LAACBWR Sitte Enclosuree Grounds Reactorr Building, WTB, W      WGTV  V, Ventilatioon L10101001                                                          Class 1        1,9922 Stack Grounds G
the initial ch und study fo from vario und study is of the 2014 und levels a WR fell within y, backgroun sentative. H was chosen.
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
or selected a ate for obtain Although th nsidered unaf e samples an d north of th acted survey mately 100 s 12108. Soil 08 were also are provided lysis of the und study fo ttributed to g
-137 concen Ci/g with a m 0 resulting i t to LACBW ZNPS) titled Station (15).
Cs-137 leve hically simila urbed soils a und Cs-137 he expected es of soil in and non-dra Water Reactor Plan hese survey g process, in l characteriz dum as a par Study haracterizati or soils at LA ous location summarized characteriza at LACBWR n nominal ex nd reference However, no
. The Energ an area outs ning backgro he selected s ffected by pa nd direct me he LSE. A y unit L4012 quare meter l samples fro evaluated f d in sections e backgroun or soils. The global fallou ntration of s maximum ob in the upper WR is a study d ZionSolutio This docum ls anticipate ar. The docu as well as u levels for th range of d the non-im ainage, distu r
units. Solu ncluding foll zation data i rt of the requ on survey p ACBWR. R ns outside o d in Table 2-ation effort, R. The pur xpected leve areas shoul suitable off gySolutions P side of the L ound measu sample locat ast LACBW asurements sphalt samp 2106. Surfa rs of undistu om non-imp for use as ba 2.3.3 and 2.
nd soil sam e results did ut. For the t surface samp bserved con r range for th y performed ons TSD 13 ment was pr ed from wor ument predic undisturbed he site speci disturbed so mpacted area urbed and un 2-21 tions intends lowing the s is obtained, uired 2 year performed in Reference 7 of the owne
: 5.
EnergySolu rpose of the els for soils, d be reasona f-site locatio Project Heal LSE but on rements bas tions were i WR operation were taken ples and dire ace soil samp urbed non-dr pacted survey ackground re
.3.5.3.
mples in 201 d report Cs-1 two backgrou ples taken o ncentration o his data set a for the deco
-004, Exami repared to co rldwide fall cted ranges f soils and is fic backgrou ils in non-d s at LACBW ndisturbed so s to continue submittal of this chapter update of th n October 2 states that a er controlled utions perfor e study was concrete, an ably close to on was ident lth Physicist the licensed ed upon the inside the LA ns.
in Class 3 s ect measurem ples were ac rainage soil y units L401 eference soil 14 compare 137 at levels und studies n or around of 0.268 pCi at a 95% con ommissionin ination of Cs ompare site out. The L for backgrou presented i und studies drainage are WR, the upp oil from the e characteriz this LTP. I r of the LTP he approved 005, Dairyl a series of s d area. Th rmed a limit s to assess i nd asphalt.
o the decomm tified. Cons and the Rad d LACBWR previous ra ACBWR lic survey unit L ments were cquired from within non-12107 and o ls. Analysis ed favorably s slightly ab performed a d the site pro i/g. The st nfidence leve ng of the Zio s-137 Globa soil sample LACBWR an und concentr in Table 2-6 performed a eas. As the per 95th per Zion backgr zation throug In the case w P will be up LTP.
and perform oil samples he result of ted assessme if backgroun missioning s sequently, an diation Prote site that se diological su censed area, L3012101, w also collect m a small ar
-impacted su other areas w s results for y with the bove MDC.
at LACBWR oduced a me tandard devi el of 0.275 p on Nuclear P al Fallout in Cs-137 resu nd Zion site rations of Cs
: 6. The obse at LACBWR ere were va centile level round study ghout where dated med a were f this ent of nd at site to n on-ection emed urvey
, they which ted in rea of urvey within these 2005 This R, the ean of iation Ci/g.
Power Soils ults at es are s-137 erved R fall arious ls for were


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.
La Cross License T Revision considere areas, an 2.3.2. P EnergySo Decomm decommi from the some of t less than prepared 2.3.3. N Based up 163.5 acr impacted contamin operation ISFSI w operation physical for comp for the cl The non-segregate inside of Highway study for within su in coal f ISFSI fac From Oc impacted survey un and the i impacted To supp objective open land by perfor The 2015 primary surveys a se Boiling W Termination n 0 ed appropria d Class 2 an Potential Ra olutions TS issioning (
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
issioning of sampling o the theoretic n 2 years, an
. The list of Non-Impacte pon the infor re licensed
: d. The n nation given ns. The det were not imp ns (i.e., with characterist pliance beyo lassification.
-impacted op ed into five f survey uni y 35. This s r soils. The urvey unit L4 from the G-cility, which ctober 2014 d open land nits and wer initial result d as it was d ort this con e of the add d survey uni rming additi 5 characteriz objectives and samplin Water Reactor Plan ate backgro nd 3 open lan dionuclides SD RS-TD-3 (16) establi LACBWR.
of various m cal neutron a n initial suite f potential ra ed Open La rmation com site surroun non-impacte that historic termination pacted by l hin the LSE ics. The are ond the chara pen land are survey unit it L4012108 survey unit non-impacte 4012103. A
-3 station an h has not bee to August areas of th re characteri s of the 201 determined t nclusion, ad itional chara its given an i onal soil sam zation camp of the addi ng to suppor r
ound concen nd area surve s of Concern 313196-001, shes the ba Industry gu media from p activation pro e of potentia adionuclides and Areas mpiled in the nding the L d areas ha cal informati that the con licensed ope
), site use, t eas designat acterization a is approxim ts. Non-imp 8 in a veget was formed ed survey un A majority of nd survey un en characteriz 2015, char he site. The ized as such 14 characteri that there is dditional ch acterization initial Class mpling and g aign was de tional chara rt the non-2-22 ntration leve ey units at L n
, Radionuc asis for an uidance was past plant o oducts, nobl al ROC for is listed in T e HSA, a lar LSE and IS ave no rea ion provides ntiguous ope erations was topography, ted as non-im surveys and mately 352,3 pacted open ated area w d during cha nits are show f the surface nit L401210 zed and is no racterization e survey uni h in Referenc ization, thes no reasonab haracterizatio surveys per 3 classificat gamma walk esigned in ac acterization
-impacted c els for the LACBWR.
clides of C initial suite reviewed as operations.
le gases and the decomm Table 2-7.
rge portion o SFSI receive asonable po s no indicatio en land area s based on site dischar mpacted are d sampling p 360 square m n land surve with minimal aracterizatio wn in Figure area in surv 06 complete ot addressed surveys w its were ori ce 13. Base se survey un ble potentia on was perf rformed in 2 tion for re-cl kover survey ccordance w was to per classification evaluation Concern D e of potenti s well as the Based on th radionuclide missioning o of the open ed a classif otential to on of impact as surroundi the locatio rge pathway e not require performed to meters in siz ey unit L40 l ground dis on to facilita 2-1. The G vey unit L40 ely surround d by this LTP were perform iginally clas ed upon a rev nits were rec al for residua formed in 2 2015 was to lassification ys.
with Referenc rform suffic n and to pr of non-imp uring LAC ial ROC fo analytical re he eliminatio es with a hal f LACBWR land areas o fication as contain res t from LACB ing the LSE on(s) of lice ys, and othe ed to be surv o provide a ze. This area 12109 is lo sturbance ea ate a backgr G-3 station re 012105 is cov ds the LACB P.
med in the ssified as Cl view of the classified as al contamina 2015. A m o evaluate ce n as non-imp ce 4. One o cient radiolo rovide reaso pacted CBWR or the esults on of lf-life R was on the non-sidual BWR E and ensed er site veyed basis a was ocated ast of round esides vered BWR non-lass 3 HSA non-ation.
major ertain pacted of the ogical nable


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)
La Cross License T Revision assurance 2015 cha based on During th units L40 logger w was scan Gamma s or gravel Minimum evaluated survey un an Explo were due Thirty-tw toward d shown in instrumen positively surface s These va in section specific b in the gr were very Seventee meter.
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
concentra derived g average maximum backgrou 137 conc surface s the Hwy Two asp survey un were less identified A summ presented se Boiling W Termination n 0 e that the n aracterization a random d he 2015 cha 012103, L40 with a 2 by 2 nned due to surface scan
  #6 Well W House 2-41
: l. Alarm se m Detectabl d during the nit L401210 oranium GR-e to the prese wo surface s discolored ar n Figure 2-5 nt MDC in y identified soil samples alues are wit n 2.3.1. On background rounds east y close at 0.
en subsurfac Of the 17 ations greate gamma-emit Cs-137 conc m observed und range fo centrations th soil backgrou 35/Railroad phalt sample nits. The asp s than the M d by gamma ary of the g d in Table 2-Water Reactor Plan non-impacted n survey foc esign to ensu aracterizatio 012105, L40 2 NaI detec inaccessibili nning focused et-points for e Count Ra e performan 7 and one in
-135. The ence of natur soil samples eas or areas
: 5. Cs-137 26 of the 32 by gamma s was 0.131 hin the expe ly one Cs-13 data set. Th of Highway 135 pCi/g an e soil sampl 7 subsurface er than the tting radionu centration ob concentrati r Cs-137 as hat exceede und. This s d Right of W es were coll phalt surface MDC of 1,93 spectroscop gamma spect
-8.
r d survey uni cused primar ure an unbia n survey, a 012106 and ctor. In surv ity from the d on undistu r the instrum ate (MDCR) nce of the g n survey unit results of th ral backgrou s were colle where the g was positiv 2 samples.
spectroscopy pCi/g with ected backgr 37 result exc his sample w y 35. The m nd 0.131 pC les were tak e soil samp instrument uclides were bserved in t ion of 0.40 discussed in d the maxim sample was t Way Grounds lected from e was first sc 38 dpm/100c py in any of t troscopy resu 2-23 its do not c rily on soils ased survey.
minimum o L4012108 vey unit L40 e presence o urbed soils w ment were s
) of the ins gamma scan t L4012108.
he investiga und activity.
ected from ground had b vely identif No other po
: y. The avera a maximum round range ceeded the m was the maxi mean of the n i/g, respectiv ken at random ples taken, MDC in ei e positively i the subsurfa 09 pCi/g. Th n section 2.3 mum Cs-137 the maximu random loc canned with cm2. No pla the asphalt s ults for each contain plant and asphalt of 1% of the was scanned 012107, less f tall, thick with minimal set at the ob strument. A n, one in su All scan al ation indicat non-impacte been disturbe fied in conc otential plan age Cs-137 c m observed c for Cs-137 maxium resu imum 0.463 non-impacte vely.
mly selected Cs-137 w ght samples identified by ace soil sam hese value 3.1. Only on 7 concentrati um 0.409 pC cations in p h a beta-gamm ant derived r samples.
h non-impac t-derived ra
: t. The samp e surface so d with a Mo s than 1% of vegetation a l vegetation bserved back A total of f urvey unit L larms were in ted the elev ed areas at ed. The sam centrations nt-derived ra concentratio concentration surface sam ult of 0.268 pCi/g value ed and site-s d locations t was positive
: s. No other y gamma sp mples was 0.
es are with ne subsurfac ion found in Ci/g value th paved areas mma detector radionuclide cted open la adioactivity.
ple locations oil area in su odel 2350-1 f the surface and steep te or disturbed kground plu four alarms L4012106, tw nvestigated u vated scan re locations b mple location greater than adionuclides n observed i n of 0.463 p mples as discu pCi/g in the e and was lo specific data to a depth o ely identifie r potential p pectroscopy.
087 pCi/g w hin the exp e sample ha n the site-spe at was locat in non-imp
. All scan re s were posit and survey u The were urvey data e area rrain.
d soils us the were wo in using esults biased ns are n the were in the pCi/g.
ussed e site-ocated a sets of one ed in plant-The with a pected d Cs-ecific ted in pacted esults tively unit is


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
La Cross License T Revision A coal as samples The resul The lab concentra also posi concentra considere of the pl radionuc positive ratios ar compared higher th operation consisten the spora derived r In survey gamma s area to d approxim uranium readings 2.3.4. Im The HSA operation been clas been iden into two north of Highway three Cla The char prepared employed radionuc of suffici surface a obtained Survey contamin se Boiling W Termination n 0 sh sample fr were sent to lts of the ana boratory an ations excee tively detect ations of the ed to very li lant-derived lide mixtur results for C re 118 and d to the site han expected nal history, t nt with natur adic positive radionuclide y unit L4012 spectroscopy determine if mately 7,000 and thorium conducted d mpacted Op A identified ns. The app ssified as C ntified as i Class 2 surv the LSE, th y 35 and the ass 3 survey racterization for each s d to determ lide concent ient quantity and subsurf from below techniques nation identi Water Reactor Plan rom survey u o Test Ame alysis are pre nalysis spor eding the MD ted but at lev e positively i ikely be the radionuclid re fractions Cs-137, Sr-16, respect e-specific mi d by factors the radionuc ral backgrou analytical r s in these su 2108, a repr
                                                                                                          ~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).
: y. In additio f there is a 0 to 8,000 cp m series nuc during the w pen Land A d the open proximate are Class 1. An impacted b vey units. T he transmiss e haul road u units combin of the impac survey unit ine the later trations in th y and quality face soils in w the structur were empl ified and th r
b    Fun nctional equivallent instrumenttation may be used u
unit L40121 erica Labora esented in T radically id DC, includin vels that are identified rad result of cou des. This c
2-42
. For exam 90 and Fe-5 tively. Wh ixture fracti s of 4,800 a lide ratios, a und and com esults are ve urvey units.
resentative s on, gamma s significant pm). The a clides with alkover surv Areas land area ea is 1.5 acr approximat y reactor op Three impact sion switchy used to tran ned is appro cted open la in accorda ral and vert he soil. Char y to quantify n each open res due to int loyed to de he radionucl 2-24 05, six surfa atories for g Table 2-9.
dentified se ng H-3, C-14 consistent w dionuclides w unting uncer conclusion w mple, samp
: 55. Howev hen the rati ons in Chap and 10,700, and primarily mprise 88% o ery unlikely sample of th scan reading difference analysis of t no plant de vey averaged inside the res. All ope tely 3.46 acr perations. T ted Class 3 s yard and the nsport dry fu oximately 16 and areas beg ance with R ical extent o racterization the potentia n land surve terferences a etermine th lide concent face soil sam gamma spect everal plan 4, Fe-55, Ni with natural b were close t rtainty as op was supporte le L301210 ver, the Sr-9 ios from L3 pter 6, Table respectivel y the concen of the site-sp to represent he rail road gs were take from site b the railroad erived radio d 7,000-8,50 fenced LSE en land surve re area that This open la survey units e area encom uel casks to 6.5 acres.
gan in Octob Reference 4 of any cont n inspections al volumetric ey unit. Li and inaccess he lateral a trations in t mples and fiv troscopy and nt-derived r i-63, and Sr-background to the detecti pposed to th ed by a rev 05-CR-GS-0 90/Cs-137 an 3012105-CR e 6-3, it is s ly. In conc ntrations of C pecific radio t the actual p bed gravel en of the rail background bed gravel onuclides. T 00 cpm.
E as impac ey units insi surrounds t and area has were design mpassing th the ISFSI.
ber 2014. A
: 4. Survey amination id s and surveys c contaminat imited soil ibility.
and vertical the soil. A ve subsurfac d HTD anal radionuclide
-90. Cs-137
. In all case ion limits an e actual pres view of exp 002-SS indi nd Fe-55/Cs R-GS-002-SS een that the clusion, base Cs-137 whic onuclide mix presence of p was analyze l road bed g (which aver indicated na The gamma cted by re ide the LSE the LSE has been segre nated for the he site acces The area o A sample plan techniques dentified an s were perfo tion of acces information l extent of A combinatio e soil lyses.
es at 7 was es, the nd are sence pected icates s-137 S are ey are ed on ch are
: xture, plant-ed by gravel raged atural scan eactor have s also gated e area ss off of the n was were nd the ormed ssible n was f any on of


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)
La Cross License T Revision random a survey p professio Protectio radioactiv spill loca survey lo not requ locations radiologi A surface surface s or surfac were take intervals Each sur site radio necessary All surfa Several s full isoto survey un 2.3.4.1.
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
There are The Clas area in th Reactor radioactiv areas, pre Twenty-t measurab locations taken in taken, C samples 13 sampl identified the surf 0.287 pC samples w Seventy-one mete se Boiling W Termination n 0 and biased s ackage. The onal judgme on Supervis vity, depres ations, or ar ocations was uired for soi s were selec ical contamin e soil sample oil samples ce scans indi en from 0.15 rface soil, co ological lab y to achieve ace and sub soil samples opic analysis nit per Refe Class e four (4) op ss 1 open lan he Class 1 op Building, th vely contam evented the a two (22) sur ble radioact s, or areas w Class 1 open Co-60 was p and Cs-137 les. No oth d by gamma face soil sa Ci/g. The a was 0.096 p nine (79) su er, two (2) lo Water Reactor Plan urvey locati e locations o ent of the E or. Consi sions, disco reas where t s also determ ils in an op cted on asp nation.
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
e was taken were acquir icated elevat 5 cm to dept omposite sub oratory by e an isotopic surface com were selecte s (HTD radi erence 4.
Isotopic Urranium    Alpha A    Spec        DOE EML E    HASL 3000 (U-234/235  5/238)                       < 0.06 pCi/g p
1 Open Lan pen land sur nd survey un pen land sur he Turbine minated build ability to per rface soil sam tivity, disco where the gro n land surve positively id 7 was posit her potentia spectroscop amples was verage Cs-1 Ci/g with a m ubsurface so ocations bias r
Isotopic Cuurium      Alpha A    Spec        DOE EML E    HASL 3000 (Cm-243/2 244)                          < 0.03 pCi/g p
ions were es of biased me EnergySoluti deration wa lored areas, the ground h mined by are pen land are phalt in Cla at each sele red at severa ted activity.
Isotopic Am mericium  Alpha A    Spec        DOE EML E    HASL 3000 (Am-241/2 243)                          < 0.04 pCi/g p
ths ranging f bsurface soil gamma-spec c MDC equa mposite samp ed at random ionuclides).
C-14                  LS SC                EPA EE ERF C-01                    ENIC Modifiied
nd Areas rvey units cl nits are show rvey units is Building, th ding and sys rform surfac mples were lored areas, ound had be ey units are s dentified in tively ident al plant-deriv py. The aver s 0.058 pCi/
                                        < 5.0 pC Ci/g                       50.0 pCi/L Tritium              LS SC                EPA 90 06.0                       EPA 906.0
137 concent maximum ob il samples w sed to areas o 2-25 stablished in easurements ions Project as given to low point g had been di ea classificat eas designat ass 1 survey cted biased a al random lo Depending from 1 to 3 m l sample or ctroscopy.
                                        < 10.0 pCi/g p                           300.0 pCi/L Sr-90                GFPC G                  DOE EML E    HASL 3000              EICHROM M  Modified Methood
al to or less ples were an m and were s Duplicate lassified as wn in Figure obstructed b he WTB and stems, as we ce scanning d taken at loc
                                        < 1.0 pC Ci/                        2.0 pCi/L Pu-241                LS SC                DOE EML E    HASL 3000              EML Pu-01
, buried pip een disturbed shown in Fig concentrati tified in con ved gamma rage Co-60 c
                                        < 10.0 pCi/g p                          50.0 pCi/L Tc-99                LS SC                DOE EML E    HASL 3000              EICHROM T  Tc-01
/g with a tration obser bserved conc were taken a on the south each survey s and/or sam Health Phy o locations gravity drain isturbed. Th tion. Rando ated as Clas y units whe and random cations or if on the loca m below gra asphalt sam Analysis co s than 0.10 p nalyzed afte shipped to T samples and Class 1 at L 2-1. A sign by the prese d the LSA ell as stored due to high b cations biase pe locations
                                        < 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
: d. The loca gure 2-6. O ions greater ncentrations a-emitting ra concentratio maximum rved in the centration o at 10 surface and west sid y unit in acc mples were d ysicist and that exhib n areas, actu he number m-based me ss 1. Rando ere there wa
                                        < 10.0 pCi/g p                          100.0 pCi/L Ni-63                LS SC                DOE EML E    HASL 3000 (SRW01)      EML Ni-01 M Modified
-based surve f surface soi ation, subsur ade and com mple was ana ount times w pCi/g for Cs er drying th Test America d concrete w LACBWR to nificant porti ence of build Building.
                                        < 2.0 pC Ci/g                        15.0 pCi/L Ni-59                LS SC                DOE EML E    HASL 3000 (SRW01)     EML Ni-01 M Modified
radioactive background.
                                        < 50.0 pCi/g p                          100.0 pCi/L 2-43
ed toward sit s, actual an ations of surf Of the 22 sur r than the M s greater th adionuclides on observed observed c analysis of f 1.07 pCi/g e soil locatio de of the WG cordance wit determined b the Radiolo bited measu ual and pote of random-b easurements om measure as no histor ey location.
l sample ana face soil sam mposited ove alyzed by th were adjuste s-137 and C he sample m a Laboratorie were collecte otaling 8,443 ion of the su dings, namel The presen material in tes that exhi nd potential face soil sam face soil sam MDC in tw han the MD s were posit in the analy concentratio f the surface
: g.
ons to a dep GTV and fiv th the by the ogical urable ential based were ement ry of Sub-alysis mples r 1 m he on-ed as Co-60.
media.
es for ed by 3 m2.
urface ly the ce of these ibited spill mples mples wo (2)
DC in tively sis of on of e soil pth of ve (5)


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)
La Cross License T Revision locations The sam evaluate Building samples 15 sampl identified of the su 0.161 pC areas is foundatio decommi Ten sam asphalt w this surv results ra measurem identified 0.057 pC A summ presented Nine sur samples gamma s In additi detected One sedi unit L10 and HTD 0.136 pC 2.3.4.2.
(on Licensed L        Sitee)
The imp immediat two surv LACBW these two Approxim 2350-1 d Alarm se instrumen se Boiling W Termination n 0 s that access mples at the t the subsurfa were taken taken, Cs-1 les. No oth d by gamma ubsurface so Ci/g. The ass not current ons and surr issioning pro mples were ta was taken fro vey unit. Th anging from ment of 3,09 d in concen Ci/g.
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
ary of the fi d in Table 2-rface soil sa taken from spectroscopy on to detect at concentra iment sampl 10103. This D analyses.
Ci/g.
Class acted Class te area surro ey units. Th WR Crib Hou o survey unit mately 1% o data logger w et-points for nt. No scan Water Reactor Plan ed the soils two WGTV ace soils alon and compo 137 was pos her potentia a spectroscop oil samples sessment of tly complete rounding bu ocess, when aken of asp om the same he asphalt s the instrume 95 dpm/100 ntrations gre indings of th
-10.
amples, 11 s Class 1 open y and HTD a ting Co-60 ations greate le was taken s sample wa Co-60 and 2 Open Lan 2 open lan ounding the hese are sho use, the G-3 ts.
of the surfac with a 2 by the instrum alarms were r
under the T V locations w ngside and u sited at dept sitively iden al plant-deriv py. The ave was 0.055 p potential su
: e. Soil in uried structu access will b phalt from p e location se surface was ent MDC of cm2. Of th eater than he survey fo subsurface s n land surve analyses. Th and Cs-137 r than the in n from the s as also sent t C-137 were nd Areas nd areas tota LSE. The C own in Figur 3 Crib Hous ce soil area i y 2 NaI de ment were set e observed.
2-26 urbine Build were acquire underneath th ths of 10, 15 ntified in co ved gamma erage Cs-13 pCi/g with ubsurface soi difficult to ures and pip be more read paved areas lected for th first scanne f 2,771 dpm/
he 10 asphal MDC in on or each indiv soil samples ey units wer he results of
, H-3, C-14 nstrument MD sanitary solid to Test Amer e detected in al approxim Class 2 impa re 2-1. The se and the L in survey un etector. Thi t at the obse ding through ed to a dept he vault. Th 5 and 20 fee oncentration a-emitting ra 7 concentrat a maximum il contamina o access are ping has bee dily availabl in Class 1 s he surface an ed with beta
/100cm2 to a lt samples t nly one sam vidual Class s, one concr re sent to Te f the analysis 4, Fe-55 and DC.
ds tank that rica Laborat n this sampl mately 13,99 acted open l LACBWR LACBWR w nit L201110 is area inclu erved backgr h angled Geo th of five m he samples u et. Of the 7 ns greater th adionuclides tion observe m observed ation in the C eas such as en deferred le.
survey unit nd subsurfac a-gamma de a maximum taken, Cs-13 mple at a s 1 open land rete sample est America s are present d Ni-63 wer is located i tory for gam e, both at a 6 m2 and ar and area wa Administrat warehouses a 1 was scann uded asphalt round plus t oprobe samp meters in ord under the Tu 79 subsurface han the MD s were posit ed in the ana concentratio Class 1 open s under bui until later i L1010104.
ce soil sampl etector with of observed 37 was posit concentratio d survey un and two as a Laboratorie ted in Table re also posit in Class 1 su mma spectros concentrati re located in as segregated tion Building are all locat ned with a M t paved surf the MDCR o pling.
der to urbine e soil DC in tively alysis on of n land ilding n the The les in scan d scan tively on of nit are sphalt es for 2-11.
tively urvey scopy on of n the d into g, the ted in Model faces.
of the


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)
La Cross License T Revision Twenty-t measurab locations taken in taken, Cs other pot The aver 0.077 pC Twenty-t and three resides in Of the 2 greater th than MD identified of 0.112 samples assessme currently surround process, w Twelve s selected results r 2,748 dpm concentra concentra observed A summ presented Three sur samples Administ HTD ana Co-60 a concentra HTD rad 2.3.4.3.
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
The impa land area Figure 2-site, the t se Boiling W Termination n 0 three surfac ble radioact s, or areas w Class 2 open s-137 was p tential plant rage Cs-137 Ci/g with a m three subsur e locations b n survey uni 23 subsurfac han MDC in DC in four d by gamma pCi/g. The was 0.043 ent of poten y complete.
Undisturbbed                            0.23 to 0.66                   0.155 to 0.77 Disturbedd                              0.27 to 0.34                  0.23 to 0.42 2-45
ding buried s when access samples were randomly.
ranging fro m/100cm2.
ations great ation observ d concentrati ary of the fi d in Table 2-rface soil sa taken from tration Build alyses. The and Cs-137, ations greate dionuclides e Class acted Class 3 a was segre
-1. The Cla transmission Water Reactor Plan e soil samp tivity, disco where the gro n land surve positively ide t-derived rad 7 concentrat maximum obs face soil sam biased to are it L2011101 ce soil samp n one sample samples. N spectroscop average Cs-pCi/g with ntial subsurf Soil in dif structures an s will be mor e taken of as The asphalt om the ins Of the 12 ter than the ved in the an on of 0.055 indings of th
-12.
amples, five m an acces ding were se results of th H-3, C-14 er than MD exceeding M 3 Open Lan 3 open land egated into ass 3 impacte n switchyard r
ples were tak lored areas, ound had be ey units are s entified at co dionuclides tion observe served conce mples were t eas alongsid
: 1. The biase ples taken, e and Cs-13 No other po py. The sing
-137 concent h a maximu face soil con fficult to ac nd piping ha re readily av sphalt from p t surface wa strument M 2 asphalt sa e instrumen nalysis of the pCi/g.
he survey fo subsurface s ssible storm ent to Test he analysis a 4, Fe-55 an DC. As disc MDC are likel nd Areas areas total a three surve ed open land for the LAC 2-27 ken at locat
, buried pip een disturbed shown in Fig oncentration were positiv ed in the an entration of taken at 14 r de and under ed samples w Co-60 was 7 was positi otential plan gle sample w tration obser um observe ntamination cess areas s as been defe vailable.
paved areas s first scann MDC of 2, mples taken nt MDC in e asphalt sam or each indiv soil samples, m sewer ba America La are presented nd Cm-243/
cussed in se ly to be false approximatel ey units. T d survey un CBWR and G tions biased pe locations
: d. The loca gure 2-7. O ns greater th vely identifi nalysis of th 0.200 pCi/g random loca rneath the S were acquire positively ively identif nt-derived ra with detectab rved in the a d concentra n in the Cla such as und erred until l in Class 2 su ned with bet
,529 dpm/10 n, Cs-137 w three samp mples was 0 vidual Class
, three aspha asin manhol aboratories f d in Table 2
/244 were ection 2.3.3 e positives.
ly 66,765m2 The Class 3 nits include t G-3 facilitie d toward sit s, actual an ations of surf Of the 23 sur han MDC in ied by gamm he surface s
: g.
ations to a de Storm Sewer ed to a dept identified a fied at conce adionuclides ble Co-60 ha analysis of th ation of 0.0 ass 2 open l der building ater in the d urvey units.
ta-gamma de 00cm2 to a was positive ples. The 0.049 pCi/g s 2 open land alt samples a le located for gamma s
-13. In add also positiv for non-imp
: 2. The Class survey uni the north en s, the LACB es that exhi nd potential face soil sam face soil sam 14 samples ma spectrosc soil samples epth of one m r Water pipe th of five m at concentra entrations gr s were posit ad a concentr he subsurfac 088 pCi/g.
land areas i foundations decommissio The asphal etector with a maximum ely identifie average Cs with a maxi d survey un and two sedi in front of spectroscopy dition to dete vely detecte pacted areas 3 impacted its are show nd of the lice BWR plant a ibited spill mples mples
. No copy.
s was meter e that meters.
ations reater tively ration e soil The s not s and oning lt was h scan m of ed in s-137 imum nit are iment f the y and ecting ed at s, the open wn in ensed access


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)
La Cross License T Revision and right was deem LACBW Crib Hou facility d were dee These ar Solutions A minim scanned was excl focused o points fo No scan Thirty-tw where th open lan was posi plant-der The aver 0.131 pC Seventee meter.
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
concentra radionuc concentra maximum Two sam selected results w were pos A summ presented As part o of concre Crib Hou Administ survey un Three co L301210 three sur Laborato se Boiling W Termination n 0 t-of-way are med impacte WR Administ use). The tr during operat emed as imp reas were c s maintains t mum of 1%
                  *L Listed half life is i the shortest half h life for thee radionuclidess in the pair 2-46
with a Mod luded from on undisturb r the instrum alarms were wo surface so he ground ha d survey un tively identi rived gamma rage Cs-137 Ci/g with a m en subsurfac Of the 17 ations grea lides were ation observ m observed c mples were t randomly.
were less tha sitively ident ary of the fi d in Table 2-of the charac ete located i use. In addi tration Build nit L301210 oncrete samp 01, the two se rface soil s ories for gam Water Reactor Plan a and the ha ed by LACB tration Build ransmission tions. The p pacted by th onservativel that classifyi of the surf el 2350-1 da gamma sur bed soils wi ment were se e observed in oil samples ad been dist nits are show ified in conc a-emitting ra 7 concentrat maximum obs e soil sampl 7 subsurface ater than M positively ved in the a concentratio aken of asph The asphalt an instrumen tified by gam indings of th
-14.
cterization of in the north ition, a sam ding and tw
: 9. These sam ples from su ediment sam samples and mma spectr r
aul road to th BWR due to ding and the yard was d plant access he transit of ly classified ing these are face soil are ata logger w rface scanni ith minimal et at the obse n these surve were taken turbed. The wn in Figure centrations g adionuclides tion observe served conce les were tak e soil samp MDC in ei identified analysis of th on of 0.409 p halt from pa surface wa nt MDC of 1 mma spectro he survey fo f survey unit h section of mple was take wo sediment mples were urvey unit L3 mples taken f d two subs roscopy and 2-28 he ISFSI fac o the presen presence of deemed as im area, Highw f packaged r d as impacte eas as non-im ea in survey with a 2 by ing for safe vegetation o erved backgr ey units.
at locations e locations o e 2-8. Of th greater than s were positi ed in the an entration of ken at random ples taken, ight samples by gamma he subsurfac pCi/g.
aved areas in s first scann 1,938 dpm/1 scopy in any or each indiv t L3012101, the survey u en from a sa t samples w sent off-site 3012101, th from the stor surface soil d HTD anal cility. The n nce of a sep f concrete fr mpacted as i way 35 right radioactive m ed. Howev mpacted wou y units L30 2 NaI dete ety reasons.
or disturbed round plus t biased tow of surface s he 32 surface MDC in 26 ively identif nalysis of th 0.463 pCi/g mly selected Cs-137 w
: s. No oth spectrosco ce soil samp n Class 3 su ned with bet 100cm2. No y of these sam vidual Class
, samples we unit that ori anitary tank were taken fr e for isotopic he sanitary ta rm sewer ba samples w lyses. The north end of ptic system from impacte it was part o t-of way and material thro ver, it shou uld have bee 012101 and ector. Surve Gamma d soils or gra the MDCR o ard discolor oil samples e soil sampl samples. N fied by gamm he surface s
: g.
d locations t was positive ther potenti opy. The ples was 0.0 urvey units.
ta-gamma de o plant deriv amples.
s 3 open land ere taken fro iginated from k that service from a storm c analysis.
ank sample asin in survey were sent t results of f the license that service ed structures of the LACB d ISFSI haul ough these a ld be noted en appropriat L3012109 ey unit L301 surface scan avel. Alarm of the instrum red areas or taken in Cl les taken, Cs No other pote ma spectrosc soil samples to a depth o ely identifie ial plant-de average Cs 087 pCi/g w The asphalt etector. All ved radionuc d survey un om several p m the LACB es the LACB m sewer bas from survey y unit L3012 to Test Am the analysi d site es the s (the BWR l road areas.
d that te.
were 12102 nning m set-ment.
areas lass 3 s-137 ential copy.
s was of one ed in erived s-137 with a t was l scan clides nit are pieces BWR BWR sin in y unit
: 2109, merica is are


L La Crosse Boilin  ng Water Reactor L
La Cross License T Revision presented derived R and Ni-6 exceedin consisten 2.3.5. N Based up associate indicated A full lis
License Termination Plan R
: 2.
Revision 0 Table 2-8      Non-Impacted Open Land Survey Units - Characterizattion Survey Su ummary S
The prim informati operation from the character The resu conducte traffic in The G-3 incidents results of A scan su gamma d using an was also gross bet MDC of identified gross alp contamin samples.
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
derived 0.061 pC that the material Direct an traffic ar Model 23 areas of i ranged f exceeded se Boiling W Termination n 0 d in Table 2 ROC at resid
Capped  Ash Immpoundment G Grounds East off Description  G-3 Coal Plannt Grounds    Coal Pile Grounds G
: 63. As dis ng MDC are nt with natur Non-Impacte pon the inf ed with the G d that there w st of G-3 stru mary basis f ion documen ns. Additio e LACBWR rization of t ults are prov ed during the the major st station res s of radioact f the charact urvey was p detector. In alpha/beta-g taken at the ta-gamma a f 2,816 dpm/
Grounds                    H Highway 35 S
d gross beta-pha activity nation was i The roof m ROC that w Ci/g. Based elevated dir on the roof.
Surface Soil          Co-60            Cs-137      Co-60          Cs-137    Co-60          Cs-137      Co-60          Cs-137
nd removabl reas of the 360 instrume interest were from 2,540 d the MDC d Water Reactor Plan 2-15. The dual concent scussed in s likely to be ral backgroun ed Structur formation co G-3 Coal Pla was no reaso uctures that for the non nted in the H nally, the p R Stack du the LACBW vided in Re e 2015 chara tation buildin sides in non tive contam erization sur performed of addition, six gamma prop location of ctivity rangi
# of Samples            3              3          3              3          3              3            3                3
/100cm2. T
# >CL                    0              1          0              1          0              2           0                3 M
-gamma acti y ranging f dentified at material itse was positive on the fact t rect alpha m le contamin G-3 Coal P ent with 43-e scanned, in dpm/100cm during the co r
Mean (pCi/g)          0.070          0.082      0.071          0.061      0.082          0.100        0.080            0.264 M
analysis of trations grea section 2.3.3 false positiv nd.
Median (pCi/g)        0.075          0.083      0.072          0.060      0.084          0.099        0.079            0.263 M
es ompiled in ant may be c onable poten have been d n-impacted HSA that the potential for uring opera WR Administ eference 13 acterization ngs were sur n-impacted s mination of s rveys perform f the mid-lev x (6) locatio portional dete each direct m ing from 2,3 The results o ivity ranging from 142 dp concentratio elf was samp ely identifie that no other measurements ation survey Plant. Scan
Max (pCi/g)            0.078          0.092      0.084          0.068      0.090          0.121        0.089            0.463 M
-93 detector.
Min (pCi/g)           0.057          0.071      0.057          0.055      0.072          0.079        0.072            0.065 S
ncluding floo m2 to 2,617 ourse of this 2-29 f these samp ater than the 3 for non-im ves. Cs-137 the HSA, S classified as ntial for resi designated as classificatio e G-3 structu windborne ations to s tration Build
SD                    0.011          0.011      0.014          0.006      0.009          0.021        0.009            0.199 S
. Addition campaign w rveyed.
Subsurface Soil      Co-60            Cs-137      Co-60          Cs-137   Co-60          Cs-137      Co-60          Cs-137
survey unit soils, asphal med in the G vel roof of th ons were sele ector. A sm measuremen 302 dpm/10 of the direc g from 1,603 pm/100cm2 ons greater t pled on Jun ed by gamm r plant deriv s were due ys were perf n measureme
# of Samples            4              4          3              3          4              4            3                3
. Approxim ors and lowe 7 dpm/100cm s survey. Te ples positive e instrument mpacted are was also po Solutions co non-impac dual contam s non-impa on for the G ures were no migration o structure roo ding roof an nal surveys where the su L4012103.
# >CL                    0              1          0              1          0              2            0                2 M
lt or concre G-3 station a he G-3 Coal ected at rand mear sample nt. The resu 0cm2 to 2,8 ct beta-gamm 3 dpm/100cm to 258 dpm than MDC b ne 30, 2015.
Mean (pCi/g)          0.060          0.048      0.061          0.042      0.081          0.088        0.081            0.068 M
ma spectros ved ROC wa most likely formed of re ents were p mately 5% of er wall surfa m2. No o en (10) locat ely identifie MDC, inclu eas, the HT ositively dete oncluded th cted. Histo mination from acted is prov G-3 station ot used for L of airborne ofs was ev nd the G-3 of the G-3 urfaces subje There are ete in this su are summariz l Plant build dom for dire for removab ults of the be 816 dpm/100 ma and alph m2 to 2,072 m/100cm2.
Median (pCi/g)        0.056          0.038      0.063          0.040      0.083          0.084        0.069            0.057 M
by the analy Cs-137 wa scopy at a as detected, to the pres epresentativ performed us f the concret aces. The av observed sca tions were ch ed several p uding H-3, F TD radionuc ected but at l hat the struc orical inform m site operat vided in Tab structures i LACBWR-re effluent rele valuated by Coal Plant structures ected to high e no docum urvey unit.
Max (pCi/g)            0.084          0.081      0.068          0.056      0.102          0.130        0.106            0.091 M
zed as follow ding using a ect measurem ble contamin eta scan iden 0cm2 with a ha measurem dpm/100cm No remov ysis of the s as the only concentratio it was concl sence of coa ve high perso sing the Lu te surfaces i verage scan M an measure hosen at ran plant-Fe-55 clides levels ctures mation tions.
Min (pCi/g)           0.047          0.036      0.052          0.030      0.056          0.054        0.068            0.056 S
ble 2-is the elated eased y the roof.
SD                    0.016          0.022      0.008          0.013      0.021          0.037        0.022            0.020 A
were h foot ented The ws:
Asphalt              Co-60            Cs-137      Co-60          Cs-137    Co-60          Cs-137      Co-60          Cs-137
beta-ments nation ntified scan ments m2 and vable smear plant on of luded al ash onnel udlum in the MDC ement
# of Samples                                                                  2             2
: ndom,  
# >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
La Cross License T Revision primarily measurem 875 dpm greater th 2.3.6. Im The deco impacted In additio accepted remain a Reactor B remainin and floo Reactor/G Turbine surfaces segregate radioactiv systems o Radiolog complian radiologi areas.
License Termination Plan R
disassem remediat demolitio waste.
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)
After com 3 feet be radioactiv use criter 2.3.6.1.
A Surface Soil            Co-60          Cs-137      Co-60            Cs-137
Characte consisted walls an (primaril taken fro 621 foot the 633 f samples w Piping Tu se Boiling W Termination n 0 y from the ments for g
                            # of Samples              3              3           17                17
/100cm2 for han MDC by mpacted Str ommissionin d buildings, s on, all system elevation fo and be subje Building tha ng reinforced ors of the Generator P sump and th above the ed by waste ve waste.
                            # >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
or structures gical surveys nce with 10 ical conditio The radiolo mbly and rem ion has ade on, the impa mmodity rem elow grade, vity and the ria.
                            # of Samples              3              3
Basem rization of d primarily o d floors of ly the Piping om the 615 elevation in foot elevatio were collect unnel. The l Water Reactor Plan main lobby gross activit beta-gamm y the analysi ructures an ng approach structures, sy ms and expo or grade at L ected to STS at will be exp d concrete w WGTV, an lant baseme he Turbine 636 foot ele classificatio No extensi s that will be s of the inter 0 CFR 20 re ons for the im ogical infor moval of syst equately red acted structu moval is com
                            # >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
, will be r e extent of a ment Structu the structur of the acquis the Reactor g Tunnels).
                            # of Samples
foot elevati n the Reactor on concrete f ted, six (6) in locations wh r
                            # >CL Mean M      (pCi/g)
y area and y was less
Median M        (pCi/g)    None Taken                            None Taaken Max M (pCi/g)
: a. No remov s of the sme nd Systems h for LACB ystems and c osed metal b LACBWR is S are the rem posed by the walls floors o nd the rem ent, the one pit. Conseq evation will on and dispo ive characte e removed pr riors of struc equirements mplementati rmation from tems and the duced radiol ures will be mplete, the s re-surveyed additional re ures Below 6 ral surfaces ition and rad r Building, In June and on concrete r Building, th floor of the P n the Reacto here the core 2-30 the mainte than the M vable contam ar samples.
Min M (pCi/g)
BWR requir components below 3 feet the 639 foo maining rein e removal of of the WTB, mainder of foot thick p quently, all l be remedi osed of as c erization wa rior to the pe tures at LAC regarding on of contro m these su e demolition logical cond demolished tructures tha to determi emediation r 36 Foot Elev of basemen diological an WTB and July of 2015 floor and t he 630 foot Piping Tunn or Building, e samples we enance area.
SDD Surface Scans
MDC of 74 mination wa res the dem to a depth o below grad ot elevation.
                            % Scanned          1%
nforced conc f the interior the remaini the Piping portion of th systems and iated, disass clean demoli as or will b erformance o CBWR are r the posting ols for the pr urveys will of impacted ditions to le d, packaged at will remai ine the con required, if a vation nts that wil nalysis of co the balance 5, a series o the concrete elevation co nels. A total three (3) in ere taken are
Mean M      Scan (cpm)  8,124                          No Scanning PPerformed Max M Scan (cpm)        9,200 2-48
. The resu dpm/100cm as identified molition and of at least 3 de will also b The only st crete walls a r concrete an ing reinforce g and Vent he Chimney d componen sembled and ition debris, be performe of FRS.
routinely per g of areas rotection of provide th d structures a evels suitabl and properl in at license ncentrations any, to meet ll remain in oncrete core e of the bas f concrete co e floor and oncrete floor l of twelve (
the WTB an e shown in F ults of all d m2 for alpha at concentra d removal o feet below g be removed.
tructures tha and floors o nd steel line ed concrete tilation Tun y Foundation nts and struc d/or demoli clean salva ed of equipm rformed to en and to ide f workers in he basis for at the site. W le for contr ly disposed termination of the res t the unrestr n the end-s samples from sement struc ore samples east wall o r of the WTB
: 12) concrete nd three (3) i Figures 2-9.
direct a and ations of all grade.
The at will of the er, the walls
: nnels, n, the ctural
: ished, age or
: ment, nsure entify these r the When rolled of as n, i.e.,
sidual ricted state m the ctures were n the B and e core in the


La Crosse Boilin L                    ng Water Reacttor L
La Cross License T Revision The loca condition volumetr elevated wall sur discolora that exh condition there was radionuc The conc Test Ame ROC. In Reactor B and #002 concrete analysis positively 59, Tc-99 concrete 2.3.6.2.
License   Termination Plan R
A concre Turbine contamin in the T Analysis 0.106 pC 2.3.6.3.
Revision     0 Table 2-9            Non Impa      acted Coal Pile and Soil Samp  ples - Test Ameerica Laboratorry Analysis (pC Ci/g)
As stated subjected graded su As repor radioactiv building located i Administ proximity laborator Characte beta-gam gross bet se Boiling W Termination n 0 ations selecte n or observ ric contamin observed co faces were ation or stan hibited the h n for concre s sufficient s lide fraction crete pucks r erica Labora n addition, Building sam 2 were also cores is pr of the conc y detected at 9, Pu-238, P core sample Turbin ete core was Building T nation event Turbine Buil of this sam Ci/g and H-3 LACB d previously d to FRS. In urvey approa rted in the H ve spills or has primaril in the build tration Build y to the LSE ry.
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
rization surv mma/alpha a ta-gamma/al Water Reactor Plan ed for concr ved radiolog ation of the ontact dose r used to id nding water.
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
highest pot ete in each s source term ns of gamma representing atory for gam the concrete mple locatio o sent for is resented in rete core sa t concentrati Pu-239/240, es is presente ne Building s obtained as Tunnel to cited in the lding and t mple indicate at 1.71 pCi/
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
BWR Admin y, the LACB nstead, these ach in accord HSA, there w radioactive ly been used ding that sup ding was in E, occupancy veys of the ctivity of in lpha activity r
L3012105-Genoa Coal Pile P                                                        0.018                        0 0.022        0.019 0              0 0.052  0.152  00.048                              0.041 L
rete core sam gical measu concrete. W rates or coun dentify poten The goal w ential of re survey unit.
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
in the cores emitters as w g the first 1/2 mma spectro e pucks rep ns #001, #0 sotopic analy Table 2-16.
L3012105-QJ-GS-001-S SB                                                        0.026                        0 0.020        0.023 0              0 0.049  0.166  00.055                              0.048 L
amples inclu ions greater Pu-241, Am ed in Referen Tunnel s part of the attempt to HSA pertain the potential ed detectable
L3012105-QJ-GS-001-S SS                                                        0.030                        0 0.020        0.028 0              0 0.072  0.199  00.074                              0.061 L
/g.
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
nistration Bu BWR Admin e two structu dance with M was no past contaminati d for office sp pported both nitially class y by LACBW LACBWR nterior floor were also p 2-31 mpling were urements in When possibl nt rates. In a ntial locatio was to ident epresenting This judg to achieve t well as HTD inch of conc oscopy and H presenting th 03, #005 an ysis. A sum Significan ude Ni-63, H than their re m-241 and A nce 16.
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
e 2014 chara evaluate ning to the d l radiologic e concentrat uilding nistration Bu ures will be MARSAME history of th ion in the LA pace and rec h LACBWR sified as a M WR personn Administrat rs surfaces a performed on biased tow ndicated the le, locations addition, vis ons of surf tify, to the e the worst gmental samp the sensitivit D radionuclid crete at each HTD analyse he concrete nd #006 and mmary of t nt HTD rad H-3 and Sr-9 espective MD Am-243. An acterization the possibl discovery of cal contamin tions of Cs-1 uilding and surveyed fo E guidance.
L3012107-QJ-GS-001-S SB                                                        0.019                        0 0.013        0.021 0              0 0.045  0.115  00.038                              0.034 L
he use of un ACBWR A cords storage R and G-3 MARSSIM nel and the p tion Buildin and the roof n the roof, on ward location e presence were determ sual observat face contam extent possib case bound mpling appro ties required des.
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
h sample loc es for beta an deeper than WTB samp the analytica dionuclides i
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
: 90. The oth DC include; analysis of survey from le extent o f cracked dra nation of su 137 at 0.352 G-3 Crib H or unrestricte nsealed radio dministratio
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
: e. An enviro operations.
Class 2 stru resence of th ng included
: f. Direct m n floor tiles ns where phy of fixed a mined based tions of floo mination, suc ble, the loca ding radiolo ach also en d to determin cation was se nd alpha em n 1/2 inch de le locations al results fo identified by her radionuc C-14, Fe-55 the results o m the floor o of a radioa ain system p urrounding 2 pCi/g, Co-House will n ed release us oactive mate on Building.
onmental lab The LACB ucture due t he environm a scan for measurement and around ysical and/or upon or and ch as ations ogical sured ne the ent to mitting eep at  
#001 or the y the clides 5, Ni-of the of the active piping soils.
-60 at not be sing a
: erials, The b was BWR to its mental gross ts for floor


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision drain ope each dire The resu 4,915 dpm the secon imbedded gamma s was then and seco from less and dire observed Beta sc 2,261 dpm from less Direct be of 243 d measurem identified 2.3.7. S Section 8 hydrogeo was deri Haley &
License Termination Plan R
(18) supp 2.3.7.1.
Revision 0 Table 2-10      Impacted Cla ass 1 Open Land  d Survey Unitss - Characterizzation Survey SSummary S
For a di towns an river wat
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
: Lansing, water fo approxim The LAC well at th state perm LACBW Building areas are to the gr pathway se Boiling W Termination n 0 enings. A sm ect measurem ults of the m/100cm2 w nd floor ha d in a floor spectroscopy n performed ond floor lam s than MDC ct alpha re d reading of 7 cans of th m/100cm2 w s than MDC eta-gamma m dpm/100cm2 ments were d concentrati urface and 8.5 in Chap ology and hy ived directly Aldrich, Hy plements the Area Grou stance of 40 nd cities alon ter for indus Iowa, about or industria mately 40 mi CBWR site he site. Sani mitted sanit WR Adminis
Surface Soil        Co-60            Cs-137          Co-60          Cs-137        Co-60          Cs-137      Co-60            Cs-137
. Storm wa e periodically round area su after passing Water Reactor Plan mear sample ment.
# of Samples          12              12              2              2            7              7            1                1
beta scans with a scan M allway, a di tile. The c
# >CL                  2               12              0              0            0              1            0                0 M
: y. The analy involving th minated woo of 329 dpm adings rang 72 dpm/100c he roof are with a scan M C of 113 dpm measurement to a maxim all less than ions greater Groundwat pter 8 of t ydrology of y from Hal ydrogeologic e preliminary undwater Us 0 miles dow ng the Missis strial purpos t 15 miles d al purposes les downstre has its own itary wastes tary wastes h tration Buil ater runoff is y monitored urrounding t g through an r
Mean (pCi/g)          0.080          0.215          0.049          0.050          0.059          0.069        0.045            0.049 M
e for remova of the int MDC of 2,10 screte radio contaminated ysis of the ti he acquisitio od, carpet, a m/100cm2 to ged from le cm2.
Median (pCi/g)       0.058          0.100          0.049          0.050          0.050          0.054        0.045            0.049 M
ea indicate MDC of 2,26 m/100cm2 to ts taken on t mum observ n MDC of 4 than MDC b ter his LTP c ZNPS and e ey & Aldri cal Investiga y findings in se wnstream of ssippi River ses, excludin downstream o between t eam.
Max (pCi/g)          0.287          1.070          0.054          0.051          0.099          0.161        0.045            0.049 M
potable wa are collecte hauler. Thi lding and a s diverted di d for oil shee the facility v n oil separato 2-32 able contam terior surfac 00 dpm/100c oactive parti d portion of ile identified n of ten (10) and floor til a maximum ess than MD ed results 61 dpm/100c o a maximum the floor dra ved reading 42 dpm/100c by the analy ontains a s environs. T ich, Hydrog ation Report n Reference 1 the site, vir are obtained ng the adjac of the site.
Min (pCi/g)          0.048          0.032          0.044          0.050          0.048          0.048        0.045            0.049 S
the LACBW ater supply, p d in a solids is includes a a sanitary h irectly to th en and disco via downspo or located in mination was ces ranged cm2. During icle was dis f the tile wa d 0.005 uCi
SD                    0.066          0.296          0.007          0.001          0.019          0.041          N/A              N/A S
) biased dire le. Direct b m observed re DC of 39 d ranging fr cm2. Direct m observed ain openings g of 333 dp cm2. No re sis of the sm summary d The informat geological C t for the LaC
Subsurface Soil      Co-60            Cs-137          Co-60          Cs-137        Co-60          Cs-137      Co-60            Cs-137
: 17.
# of Samples          18              18            22              22            25              25          14                14
rtually all m d from groun cent G-3 pla There are n WR site an provided thr s holding tan a sanitary ho holding tank he Mississipp oloration. R outs or ente nside the LSE also taken from 1,420 g the scan of scovered. T as removed of Cs-137.
# >CL                  0                8             0               4            0              0            0                3 M
ect measurem beta-gamma eading of 5, dpm/100cm2 rom 1,872 t alpha meas reading of 1 s ranged from pm/100cm2 a emovable co mear samples description tion containe Conceptual S Crosse Boilin municipal w und water. T ant, is the co no other know nd Prairie rough a sing nk and pump olding tank k that servi pi River at o Roof drains d r the norma E.
Mean (pCi/g)          0.078          0.066          0.058          0.064          0.046          0.049        0.048            0.041 M
at the locati 0 dpm/100cm f the north e The particle and analyze An investig ments on the readings ra
Median (pCi/g)        0.052          0.054          0.058          0.065          0.046          0.049        0.048            0.042 M
,743 dpm/10 to a maxi dpm/100cm surements ra 152 dpm/100 m less than M and direct ontamination
Max (pCi/g)          0.516          0.161          0.080          0.130          0.055          0.054        0.050            0.051 M
: s.
Min (pCi/g)           0.047          0.033          0.043          0.044          0.025          0.042        0.043            0.027 S
of the geo ed in this se Site Model ng Water Re water supplie The nearest u oal-fired pla wn users of du Chien, gle ground w ped off by a that service ices the Tu outfalls. Re discharge dir al effluent re on of m2 to end of e was ed by gation e first anged 00cm2 imum m2 to anged 0cm2.
SD                    0.109          0.035          0.010          0.017          0.005          0.003        0.002            0.009 A
MDC alpha n was
Asphalt                                                                                                        Co-60            Cs-137
: ology, ection (17).
# of Samples                                                                                                      10                10
eactor es for use of ant in f river WI, water local es the urbine elease rectly elease
# >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
La Cross License T Revision 2.3.7.2.
License   Termination Plan R
Regional Mississip parallels upward; river stag demonstr river stag Groundw surface (
Revision     0 T
Groundw the Missi may turn chemical the shallo Based on of the G-located i monitorin a slightly has a do gradient towards t there are stages. G Reactor B are below During p was com permeabi buildings soils will will circ localized outside th other han or buried underlyin shallow s contamin soils with orders of se Boiling W Termination n 0 Groundw lly, groundw ppi river. C the river. U however, th ge data comp rates that the ge impacts th water beneath bgs) and the water in the s issippi Rive n and flow l constituent ow system.
Table      2-11      Class 1 Concretee, Asphalt, Sed            diment and Soill Samples - Tesst America Lab boratory Analyysis (pCi/g)
n a review of
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
-3 Ash Land in the sout ng wells (B1 y downward ownward gr at well pair the river bas e some perio Groundwater Building ba w the water t plant constru mpacted, redu ility can dec
L1010101-CJ-GS-002-SSS                                                        0.024                        0 0.020          0.233          0 0.056  0.161  00.066                              0.058 L
: s. The resul l flow at a s cumnavigate d flow regim he footprint nd, potential d piling, will ng groundw soils from p nation. The hin the supp f magnitude Water Reactor Plan ater Flow water flows i Closer to th Under typic he vertical gr pared to wa e shallow aq he water tabl h the site is e groundwat shallow depo
L1010101-CJ-GS-009-SSS                                                        0.040                        0 0.020          0.185          0 0.056  0.181  00.050                              0.042 L
: r. The deep parallel to s would occu f the ground dfill area grou th side of t 11AR/B11R vertical gra radient at w B9/B9A. T sin with a lo ods where t r flow throu sement shel table during uction, and m ucing the eff crease the h lting impact slower veloc the area, e mes on contam of these str l releases tha l likely take water. This precipitation, average sha port pilings, lower.
L1010101-CJ-GS-010-SSS                                                        0.286                        0 0.025          0.413          0 0.062  0.247  00.057                              0.051 L
r in a westerl he shore, gr al river stag radient rever ter table ele quifer is in di le elevation.
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
first encoun ter is in dire osits and fill per groundw the river.
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
ur at or near dwater elevat undwater mo the LACBW
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
) to the east adient. Durin well pairs B This is expec ocalized influ the gradients ugh the LAC l) as well as high and low more specifi fective poros hydraulic con to groundw city, and reg effectively b minant fate a ructures will at occurred w much longe is further c
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
, creating an allow aquifer the hydraul 2-33 ly direction roundwater ge, groundw rses during f evations mea irect hydrau ntered at an ect hydraulic l material flo water is also Because th r the surface tion measure onitoring we WR site, an of and up gr ng times of n B11R/B11AR cted as grou uence at B9/
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
s are revers CBWR site is s the deep p w river stage ically the ins sity and perm nductivity o water flow is gionally, a si bypassing th and transpor l likely be d within the fo er to migrate compounded n area that w r hydraulic c ic conductiv from the bl may also h water gradien flood stages.
L1010102-CJ-GS-013-SSB                                                        0.030                        0 0.016          0.021 0              0 0.044  0.170  00.041                              0.036 L
asure in LAC ulic commun n average de c communica ows towards likely to flo he potential
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
, the release ements colle ells (# B2/B3 nd associate radient of LA normal and R and B2/B undwater flo
L1010102-QJ-GS-001-SSS                                                        0.022                        0 0.015          0.018 0              0 0.036  0.113  00.042                              0.039 L
/B9A from t sed; and this s impacted b pilings that s e conditions.
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
stallation of meability of of the aquife s that ground ignificant pe these soils.
L1010103-CJ-GS-002-SSB                                                        0.011                        0 0.017          0.021 0              0 0.044  0.181  00.046                              0.044 L
rt are that po deflected and ootprint of th e both in th d as the ove will likely re conductivity vity would b luffs on the have a flow nts near the
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
. The geolog CBWR site nication with epth of 20 fe ation with th s the west an ow towards t l releases of s would like ected during 3/B9A/B9/B ed backgrou ACBWR, th low river sta B3, with an ows generally the adjacent s is likely d by deeper st support the f the support f the soils. T er within the dwater withi ercentage of The impli otential relea d flow aroun he buildings e vadose zo erlying struc etain any po y is 313 feet be expected east toward component river are sli gical and his monitoring h the river an eet below gr he adjacent nd discharges the west but f radiologic ely be confin routine sam B7/B8), whic und groundw here appears age, groundw upward ve y from the b t inlet. How due to high tructures (i.e structures, w t pilings, the This reducti e footprint o in the comp f the flow re ications of ases that occ nd them. O s, via floor d one as well a ctures isolat tentially rele per day. Fo to be one to ds the t that ightly storic wells nd the round river.
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
s into t then cal or ned to mpling ch are water to be water ertical bluffs
L1010103-QJ-GS-001-SSS                                                        0.025                        0 0.015          0.020 0              0 0.046  0.174  00.047                              0.043 L
: wever, river e., the which e soil ion in of the pacted egime these curred On the drains as the te the eased or the o two
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
La Cross License T Revision The velo gradient.
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
across th Therefor the inch Environm show sea stage. Th LACBW vicinity structure direction 2.3.7.3.
    # off Samples              13                  13                10                    10
Historica monitorin monitorin monitorin Dairylan Of the w LACBW routine b designate Environm G-3 Foss Nos. 3, 4 levels re 3.0E-08 &#xb5; During th to the s radioactiv The well suspected that samp As note Activities wells to monitorin if ground located n interval o below gr B.
    # >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
se Boiling W Termination n 0 ocity of gro The gradie he site, groun e, it is likely hes and fee mental Moni asonal varia hese wells a WR site struct of suspect s/foundation ns.
    # off Samples              16                  16                7                      7
Previous I ally, the LAC ng wells. F ng wells loc ng wells of d for radiolo wells shown WR facilities basis. The gr ed as B-2, mental Moni sil Station op 4 and 5 wer ported durin
    # >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
&#xb5;Ci/ml to 9.
    # off Samples                6                  6                6                      6
he recovery outh of the ve liquids fr l-point show d leakage. T ple are prese d in the L s Report (D support gro ng wells (10 dwater qual nominally wi of 15 to 25 f rade. These Water Reactor Plan oundwater is ent of the wa ndwater mon y that the gro et/day rang itoring Prog ation on upw are not suffic tures or area broken dra ns or variati Investigation CBWR Lice igure 2-11 i cated on th ff the LACB ogical purpo n on Figure were histor roundwater m B-3, B-7, itoring staff perational re re routinely ng this mon 0E-08 &#xb5;Ci/m of a probab e Turbine B rom suspect wn on Figure The well-po ented in Tabl LACBWR D D-Plan/PSDA oundwater e 0 wells total) ity had bee ithin five (5) feet below g wells are sh r
    # >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
s directly r ater table is i nitoring has oundwater v e). Ground gram wells a ward and do cient to char as where pote ain lines) co ions in fill m ns ensed Site ha llustrates the e LACBWR BWR site t ses.
    % Scanned S                50%                                                    50%
2-11, only P rically monit monitoring w B-8, B-9, on a routine equirements.
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
monitored f nitoring peri ml).
le spill incid Building. T broken drain 2-11 was es int was sam le 2-17. Thi Decommissio AR) (19), D evaluation.  
) were instal en impacted
) feet of one grade and on how on Figu 2-34 elated to bo nfluenced by shown that velocity acro water eleva agree with t ownward gra racterize the ential releas ould have o materials co as had sever e current loc R site. The that are or Potable Wa tored by Da wells and ba B-9A, B11A e basis for no During LA for gross be iod was less dent in 1983 This inciden n lines in th stablished do mpled once o is well-point oning Plan airyland rec In Novemb lled within t by plant o e another con ne deep well ure 2-11 as M oth the hyd y the topogr the water ta oss the site is ation data the regional adients that groundwate es associated occurred. In ould locally ral potable w cation of po ere is no po have been ater Wells N airyland for ackground gr AR, and B on-radiologi ACBWR ope eta activity.
s than or eq
, a temporar nt concerne e Turbine B own gradien on May 3, 19 t has since be and Post-S cently instal ber 2012, fi the LACBW operations.
nsist of one with a scree MW 200A an draulic cond raphy; and, w able has a v s also relativ from the groundwate are influen er flow below d with LAC n these area influence g water wells otable water otable water monitored Nos. 3 and 4 radiological roundwater B11R are m ical paramete erations, Pota Typical gr qual to MD ry well-poin ed the pote Building to su nt and below 983. The an een abandon Shutdown D lled groundw ive (5) pairs WR licensed The well p shallow wel ened interva nd B throug ductivity and with the flat ery low grad vely slow (i.
G-3 Coal er flow, and nced by the w and aroun BWR (i.e., i as, pilings, groundwater and groundw and groundw r or groundw by Solution 4 which serv l conditions monitoring monitored by ers to suppo able Water W ross beta ac DC (ranging nt was establ ential leakag ub-building w the grade o nalysis resul ned.
Decommissio water monit s of groundw site to deter pairs which ll with a scre al of 45 to 55 h MW-204A d the areas dient.
.e., in Plant d also river nd the in the deep flow water water water ns or viced on a wells y the ort the Wells ctivity from lished ge of soils.
of the ts for oning toring water rmine were eened 5 feet A and


La Crosse Boilin L                  ng Water Reacttor L
La Cross License T Revision Two (2) in June groundw 90 and C In June o through 2 and B11 several r fourth ro Potable samples transuran of the gro Addition
License   Termination Plan R
: 18.
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
2.3.7.4.
L2011101-CJ-GS-001-S SM                                    0.096                0 0.011            0.137            0 0.041  0.098  00.033                              0.031 L
The LAC twice pe groundw the MW-The colle D
L2011101-CR-PA-003--AV                                    0.023                0 0.016            0.017 0                0 0.039  0.131  00.039                              0.038 L
M p
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
R gr 2.3.7.5.
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
Groundw (5 pairs) sampling wells MW Novembe positively ranging Novembe during th During th MW-202 Sr-90 w se Boiling W Termination n 0 rounds of gr 2013 and th water samples Cs-137. Analy of 2014, a t 204 A and B AR. These radionuclide ound of gro Well #5, an were sent o nic radionucl oundwater sa nal details, in On-Going CBWR Site g er year for r water is at rel
L2011101-QJ-GS-001-S SS                                    0.012                0 0.020            0.080            0 0.060  0.188  00.091                              0.042 L
-200A/B thru ected inform Depth to grou Monitoring w otential/turb Radiological roundwater Summ water charact within the g in 2013. H W-201A and er of 2013 y detected i from 1.43 p er 2013 sam he 2013 samp he June 201 2A, MW-203 was also po Water Reactor Plan roundwater hen during s were sent ysis for H-3 third round o B; Potable W e collected g s including oundwater w nd Monitori off for radio lides. Table amples and r ncluding the g Investigatio groundwater radiological latively high u MW-204A mation during und water in well groundw bidity/dissolv sample infor sample colle mary of Grou terization eff LSE area H-3 was posi d B, MW-20 at concentra in the same pCi/L to 2.1 mpling period pling period 4 sample pe 3A and MW sitively det r
L2011101-QQ-GS-001--SB                                    0.017                0 0.012            0.013 0                0 0.040  0.127  00.037                              0.031 L
samples wer a seasonal l to an off-sit was perform of groundwa Water Wells #
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
groundwater HTD and t were collecte ing Wells B ological ana es 2-18 and 2 results.
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
e off-site ana ons r monitoring analysis pu her and lowe A/B wells as g each monit the respecti water pH/spe ved oxygen/t rmation incl ection.
L2011101-QQ-PA-001--AV                                    0.022                0 0.015            0.015 0                0 0.046  0.135  00.042                              0.040 L
undwater An fforts comme in Novemb tively detect 02-A and B, ations rangi wells durin 18 pCi/L; ho
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
: d. Co-60 an eriod, H-3 w W-203B) at c ected in w 2-35 re collected low groundw te laboratory med on site.
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
ater samples
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
#3, 4, 5, and samples w transuranic r ed from: M B11R and B alysis of sev 2-19 provide alytical labor g program co urposes only er elevations shown on F toring interv ive monitorin ecific conduc temperature.
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.
luding a com nalytical Res enced throug ber 2012 an ted at concen MW-203A ing from 15 ng the June owever, it w nd Cs-137 w was positively oncentration wells MW-20 in 2013, du water level y for radiolo s was collec 7; and Mon ere sent off radionuclide MW 200A an B11AR. T veral radion es a summar ratory repor onsists of ob y from exis
2-53
. The moni igure 2-11.
val includes:
ng well.
ctance/oxida mpleted chain sults gh the install nd the com ntration grea and B and M 50 pCi/L to 2013 sampl was not po were not po y detected in ns ranging fr 02A, MW-2 uring the sea in Novemb ogical analys cted from: M nitoring Well f for radiolo es. In Septe nd B throug These collec nuclides incl ry of the radi rts are provi btaining grou ting monito toring wells ation and red n of custody lation of 10 mmencement ater than MD MW-204A a 660 pCi/L.
ling period a ositively dete sitively dete n four (4) w from 245 pC 203A and asonal high w ber 2013. T sis for Co-60 MW-200A a ls B2, B-3, B ogical analys ember of 20 gh 204A an cted groundw luding HTD iological ana ded in Refer undwater sam oring wells w s sampled in duction y following monitoring of groundw DC in monit and B in Jun Sr-90 was at concentra ected during ected in any wells (MW-B i/L to 336 p MW-204A water These 0, Sr-and B B11R sis of 014 a nd B, water D and alysis rence mples when clude wells water toring e and s also ations g the y well
: B11R, pCi/L.
with


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision concentra Am-241 During t greater th concentra were also 2.4.
License Termination Plan R
C The surv deferred.
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
under co that will basement illustrate defer the condition ALARA data wou areas),
            # of Samples            3                3                                        5              5
Safet Histo Acce struct interf The a physi condi As acces will be co for the s radionuc and HTD events ca of a surv stored in validatin As decom surface d for open documen se Boiling W Termination n 0 ations rangin were also po he Septemb han MDC in ation of 1.14 o positively d Continuing C vey of many Examples ncrete or asp remain and t after liner s buried pip e characteriz ns:
            # >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
consideratio uld likely not ty considerat orical data sh ss for charac tures or othe fere with con ability to use ical relations itions repres ss is gained ollected, eva survey unit.
            # of Samples            3                3                                        4              4
lides present D radionuclid aused by equ vey unit(s) w n the charac g the initial mmissioning decontamina n air demolit nted survey a Water Reactor Plan ng from 1.1 ositively det ber 2014 sam n any well.
            # >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
4 pCi/L. Co detected at r Characteriz inaccessible s of areas w phalt coverin d be subjec r removal an ping systems zation of a ons (e.g., the t change the
            # of Samples            3                3                                        7              7
: tions, hows that the cterization w er obstacles w ntinued oper e engineering ship to surro sented by the to areas tha aluated and s This data t and update des. In addi uipment failu will be reco terization d classificatio g proceeds, ation (as wel tion or unre and a formal r
            # >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
12 pCi/L to ected at resi mple period, Sr-90 was o-60, Ni-63, residual conc zation e or not read where survey ngs, structur cted to FRS nd the inter s that may r soil or stru e area is eith e survey area e area could would require where the re ration of ope g judgment i ounding area e conditions at were prev stored with-o will be use e the variabil ition, as the ures or perso orded. Thes atabase. Th n and in plan areas will, ll as fixed co estricted rele l turnover w 2-36 2.01 pCi/L.
                % Scanned                  1%%                                                      1%
dual concen
Mean M    Scan (cpm)  9,000                          No Scanning Performed                  5,8900 Max M Scan (cpm)      10,000                                                                6,4000 2-54
, H-3 was n positively d
, Cs-137, Eu centrations in dily accessib ys are deferr ral wall and
, the underl riors of bur remain in th ucture was b her a radiati a or area clas be classified e significant emoval could erating system in assigning s and the lik in these adja viously inacc other radiolo ed along wi lity in the ra decommiss onnel errors, se events w his additiona nning for the as necessar ontamination ease. When will be made C-14, Tc-9 ntrations in se not positivel detected in o u-152, Eu-15 n several we ble subsurfa rred include floor surfac rlying concr ried pipe tha he end-state based on on ion or conta ssification o d without fur t deconstruct d result in an ms, or the area a cl kelihood of th acent areas.
cessible, add ogical survey ith existing adionuclide m ioning progr
, which may will be evalu al character e FRS.
ry, be decon n) to levels n a structur by the Radi 99, Eu-152, everal wells ly detected a one (1) well 54, Pu-239/2 ells.
ace soils or s soils under ces in some rete in the R at may rem condition.
ne or more amination are of the locatio rther charact tion of adjac n unsafe con lassification he area to ha ditional char y data in a s data to upd mix for both resses, data y affect the ra uated and, w rization data ntaminated that will me e is ready f ological Pro Pu-239/240 at concentra l, MW-200A 240 and Am surfaces has r structures, of the basem Reactor Bui main. Figure The decisi of the follo ea and addit on or surroun terization, cent systems ndition or n based on ave radiolog racterization urvey histor date the typ h gamma-em from operat adiological s when approp a will be us to remove eet the condi for demoliti otection grou 0 and ations A at a m-241 been soils ments ilding e 2-3 on to owing tional nding s,
gical n data ry file pes of mitting tional status
: priate, ed in loose itions ion, a up for


La Crosse Boilin L                    ng Water Reacttor L
La Cross License T Revision the comp are suitab Followin a "turnov acceptan transferre performa may inclu The "turn survey pe survey da
License   Termination Plan R
: turnover, survey p met. The Appr action Appr Appr with Appr radio Data addit Appr 2.5.
Revision    0 Table 2-155          Class 3 Asp      phalt, Sedimentt and Soil Samp  ples - Test Am merica Laboratoory Analysis (ppCi/g)
R
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
: 1.
L3012101-CR-GC-001- -CV                                                      0.028                        0 0.030        0.026 0              0 0.043  0.221  00.059                              0.053 L
U C
L3012101-CR-GC-002- -CV                                                      0.035                        0 0.026        0.033 0              0 0.062  0.271  00.056                              0.055 L
2
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
: 2.
L3012101-CR-GS-003- -SS                                                      0.025                        0 0.017        0.113          0 0.052  0.157  00.059                              0.052 L
U R
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
: 3.
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
U C
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
o
L3012104-CR-GS-002- -SM                                                      0.015                        0 0.013        0.066          0 0.035  0.128  00.047                              0.036 L
: 4.
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
E C
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
: 5.
E S
se Boiling W Termination n 0 pany preform ble.
ng the demol ver assessme ce criteria w ed to Charac ance of the F ude a "turno nover surve erformed, re ata prior to c
, and FRS), a lans will co ese objective ropriate instr n level and/o ropriate instr ropriate surv the calibrati ropriate samp nuclide ratio analysis crit ional sample ropriate class References U.S. Nuclear Content of Li 011.
U.S. Nuclear Radiation Sur U.S. Nuclear Consolidated f Radiologic EnergySoluti Crosse Boilin EnergySoluti ite Characte Water Reactor Plan ming demoli lition and/or ent" will be p will be met, cterization/L FRS. Otherw over survey,"
ey" process, epresent at le conducting t a documente ontain the ap es include:
rument selec or release cri rument quali ey technique on methodol ple collectio os, teria to ident es and, sification of Regulatory icense Termi Regulatory rvey and Site Regulatory Decommiss cal Criteria, F ons PG-EO-ng Water Rea ons GP-EO-erization Proj r
ition, validat r remediation performed. I
, then physi License Term wise, additio
" primarily fo together wi east one, but the FRS. Fo ed survey pl ppropriate da ction to ensur
: iteria, ity control m es to ensure
: logies, n and analys tify follow-u the survey a Commission ination Plan Commission e Investigati Commission sioning Guid Final Report
-313196-SV actor.  
-313196-QA ject (QAPP) 2-37 ting that the n, and when If the results ical and adm mination grou onal remedia for Class 1 an ith any addi t possibly se or each type an will be d ata assessme re the proper measures to e that the field sis to determ up actions su area.
n, Regulator s for Nuclea n, NUREG-1 ion Manual (
n, NUREG-1 dance - Char t - Septembe
-PL-001, Ch A-PL-001, Qu
).
e radiologica n an area is b s of this asse ministrative up personne ation may b nd 2 areas w itional chara everal, oppo of survey (c developed us ent to ensur r sensitivity ensure operab d measurem mine spatial v uch as remed ry Guide 1.1 ar Power Rea 1575, Revisi (MARSSIM 1757, Volum racterization er 2006.
haracterizatio uality Assur al condition believed to b essment indi control of l for prepara be required.
within the LS acterization ortunities to c characterizat ing the DQO re that sever relative to th
: bility, ent techniqu variability an diation and th 79, Standard actors, Revis ion 1, Multi-M), August 20 me 2, Revisio
, Survey, an on Survey P rance Project s in the stru be ready for icate that the the area wi ation, design This assess SE.
and remedi collect addit tion, remedia O process. T ral objective he applicabl ues are consi nd variability he collection d Format and sion 1 - June
-Agency 000.
on 1, nd Determina Plan for the L t Plan LACB ucture
: FRS, e FRS ill be n, and sment iation tional
: ation, These es are le istent y in n of d
e ation La BWR


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)
La Cross License T Revision
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)
: 6.
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
E W
: 7.
D S
: 8.
U R
D
: 9.
S C
: 10.
E 1
: 11.
U L
: 12.
U R
T
: 13.
E S
: 14.
E S
: 15.
Z F
: 16.
E C
: 17.
H 3
: 18.
H R
2
: 19.
D D
: 20.
In E
1 se Boiling W Termination n 0 EnergySoluti Water Reacto Dairyland Po AFSTOR -
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EnergySoluti urvey Repor EnergySoluti urvey Repor ZionSolution allout in Soi EnergySoluti Concern Duri Haley & Aldr 0, 2012.
Haley & Aldr Reactor, Dair 015.
Dairyland Po Decommissio nternational Emitters (max 998.
Water Reactor Plan ons Technic or Historical wer Corpora December 2 Regulatory rvey and As 006.
nal Laborato on From Dec ons Technic Sensitivity.
Regulatory Analytical Pro Regulatory Monitoring
- Effluent S ons GG-EO-rt for Octobe ons LC-RS-rt for June th s Technical ils at Zion St ons Technic ing LACBW rich, Hydrog rich Inc., Hy ryland Powe wer Coopera oning Activit Standard IS ximum beta r
cal Support D Site Assessm ation LAC-T 2009.
Commission sessment of ory, NUREG commissioni cal Support D Commission otocols Man Commission Programs (I Streams and
-313196-RS er and Novem PN-164017-hru August 2 Support Doc tation.
cal Support D WR Decomm geological C ydrogeologic r Cooperativ ative, LACB ties Report (
O 7503-1, P energy grea 2-38 Document R ment (HSA)
TR-138, Initi n NUREG-1 Materials an G/CR-5512, V ing Paramete Document R n, NUREG-1 nual (MARL n Regulatory Inception Th the Environ S-RP-001, LA mber 2014 F
-001, LACB 2015 Field W cument 13-0 Document R missioning.
onceptual Si cal Investiga ve, Genoa W BWR Decom (D-Plan/PSD Part 1, Evalua ater than 0.15 RS-TD-31319
).
ial Site Char 1575, Supple nd Equipmen Volume 3, R er Analysis -
RS-TD-31319 1576, Multi-LAP) - Augu y Guide 4.15 hrough Norm nment - July ACBWR Ra Field Work -
BWR Radiolo Work - Nove 004, Examin RS-TD-31319 ite Model, F ation Report, Wisconsin, Fi mmissioning DAR), Revis ation of Surf 5 MeV) and 96-003, La C racterization ement 1, Mu nt Manual (M Residual Rad
- October 19 96-006, Lud
-Agency Rad ust 2001.
5, Quality A mal Operatio 2007.
adiological C
- November ogical Chara ember 2015.
nation of Cs-96-001, Rad File No. 3870
, La Crosse B ile No. 3870 Plan and Po sion - March face Contam Alpha-Emit Crosse Boilin n Survey for ulti-Agency MARSAME dioactive 999.
dlum Model 4 diological ssurance or ns to Licens Characterizat r 2015.
acterization 137 Global dionuclides o 05-001 - Au Boiling Wat 05-008, Janu ost Shutdown h 2014.
mination, Bet tters - Augu ng E) -
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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/
La Cross License T Revision Survey Unit ID #
i/g)    (pCi/g)      (pCi/g))    (pCi/g)    (pCi/g)
L101010 L101010 L101010 L101010 L201110 L201110 L301210 L301210 L301210 L401210 L401210 L401210 L401210 L401210 se Boiling W Termination n 0 Survey 01 Reactor Stack G 02 Turbine Diesel G 03 LSA Bu 04 North L 01 LACBW Crib Ho 02 G-3 Cri Dischar 01 North E 02 Transm 09 Plant A 03 G-3 Co 05 Coal Pi 06 Capped 07 Ground 08 Hwy 35 Water Reactor Plan Table 2-1 y Unit Descr LA r Building, W Grounds e Building, T Generator Bu uilding, Mai LSE Grounds WR Adminis ouse, Wareh ib House, LA rge Line, Are End of Licen mission Switc Access, ISFSI al Plant Gro le Grounds d Ash Impou ds East of Hi 5/Railroad R r
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/
LACBW ription ACBWR Sit WTB, WGTV Turbine Offi uilding Grou ntenance Ea s
i/g)    (pCi/g)      (pCi/g))    (pCi/g)    (pCi/g)
LSE Buff stration Buil ouse Ground ACBWR Cir ea South of L Clas nsed Site chyard Area I Haul Road Non-Im ounds undment Gro ghway 35 Right of Way 2-39 WR Open L te Enclosure V, Ventilatio ce Building, unds at Shack Gro fer Zone Gro lding, LACB ds rc. Water LSE Fence ss 3 Grounds d Grounds mpacted Grou ounds y Grounds Land Survey Cl e Grounds on
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
, 1B ounds ounds BWR s
unds No No No No No y Units Initial lassification Class 1 Class 1 Class 1 Class 1 Class 2 Class 2 Class 3 Class 3 Class 3 on-Impacted on-Impacted on-Impacted on-Impacted on-Impacted n
Approxim Survey U Area (m 1,992 2,315 1,749 2,387 7,211 6,785 24,04 11,71 31,01 d
66,86 d
82,89 d
111,89 d
81,25 d
9,444 mate Unit m2) 2 5
9 7
1 5
2 1
2 9
4 99 4
4


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)
La Cross License T Revision Surve B101 B101 B101 B101 B101 B101 B101 B101 B101 B201 B201 B201 B201 B201 B201 B301 B301 B301 B301 se Boiling W Termination n 0 ey Unit 10001 10002 10003 10004 10005 10006 10007 10008 10009 10101 10102 10103 10104 10105 10106 12101 12102 12103 12104 Water Reactor Plan Table 2-2 Sur Wa LAC W
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)
LACBWR LACBWR M
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
L LACBW LA LA LA Ba Transmissi Barg r
LACBW rvey Area D Reactor Bu aste Treatmen CBWR Venti Waste Gas Ta R Turbine Bld Bldg 1B Diesel G LSA Buil Maintenance E Pipe Tun ACBWR Cr G-3 Crib H WR Administ ACBWR War ACBWR War ACBWR War ack-up Contr ion Sub-Stat G-1 Crib H ge Washing B 2-40 WR Structu Description uilding nt Building ilation Stack ank Vault dg./Turbine Generator Str lding Eat Shack nnel rib House House tration Build rehouse #1 rehouse #2 rehouse #3 rol Center tion Switch H House Break Room ural Survey k
Office ructure ding House m
y Units Class Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl sification lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 2 lass 2 lass 2 lass 2 lass 2 lass 2 lass 3 lass 3 lass 3 lass 3  


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)
La Cross License T Revision G-3 R G-3 S G-3 C G-3 T G-3 E G-3 C G-3 C G-4 W G-3 L G-3 L G-3 C G-3 C G-3 V G-3 T G-3 B G-3 F G-3 F G-3 W G-3 S G-3 S
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
#6 W se Boiling W Termination n 0 Table Reclaim Buil Stock Out Tr Coal Unload Transfer Tow Electrical Ro Crusher Tow Conveyor #6 Warehouse a LRAPB Buil Lime Silo El CAT Buildin Coal Plant Vehicle Stora Train Shed Bottom Ash Fly Ash Silo Fly Ash Elec Waste Silo Surge Tank Settling Tank Well House Water Reactor Plan e 2-2 (contin lding ransfer Build ing Tower wer A oom wer 6 (2) and Electrica lding ectrical Buil ng age Building Dewatering ctrical Buildi k
r nued)
Non Imp ding al Room lding g
Buildings ing 2-41 LACBWR pacted Struc G-3 An G-3 Bo G-3 Ex G-3 Ga G-3 Su G-3 Su G-3 Li G-3 W G-3 Ac G-3 As G-3 Ba G-3 Fl
#7 We G-3 Co G-3 Sa G-3 St G-3 Gr G-3 As Main P S03 Ta Structural ctures nnex Buildin oiler Fuel Oi xplosive Gas as Room ub Station Sh ub Station Sh ime Storage Weigh Station ctive Reclaim sh Coordina ag Houses (5 ammable St ll House oal Scale ample Buildi tock Out Tra rid Shed sh handling Pollution Co ank Building Survey Uni ng il Pump Bui s Storage Ro hed hed Silo n
m Buildings ators Office
: 5) torage Shed ing ansfer Buildi Blower Buil ontrol Electri g
its lding oom s/ Tunnel ing lding ical Buildingg


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
La Cross License T Revision Dete Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Gamma System a
pCi/L)
Bas Stan b
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
Fun se Boiling W Termination n 0 ector Model m 44-9 m 43-68 mo m 43-68 mo m 43-93 mo m 43-89 mo m 43-93 mo m 43-89 mo m 44-10 m 43-37 m 43-10-1 a Spectroscop ed on 1-minute ndard, ISO 750 nctional equival Water Reactor Plan Table 2-3 l b Me Ludl ode Ludl ode Ludl ode ode Ludl ode ode Ludl Ludl Ludl Ludl py e count time; a 03-1 (20).
lent instrument r
Instrume eter Model lum 3 lum 2350-1 lum 2350-1 lum 2360 lum 2360 lum 2350-1 lum 2350-1 lum 2929 N/A and default valu tation may be u 2-42 ent Types a Applica sca static &
stat static &
stat sca sca and/
smea Anal ues for surface used and Nomina ation Ty (dp an 1,0
& scan 1,8 tic
& scan 1,8 2,0 tic an 3.5 6.5 an 2,0 or ar lysis efficiencies (
al MDCs Typical Dete MDCscan pm/100cm2) 000 to 2,000 800 to 2,000 N/A 800 to 2,000 000 to 2,200 N/A 5 pCi/g 60Co 5 pCi/g 137Cs 000 to 2,200 N/A N/A s) as specified ction Sensit
)
MDCst (dpm/10 0
N/A 0
600 to 80 to 0
0 800 to 800 to 90 to 1 90 to 1 o
s N/A 0
N/A
~0.10 p for Co-6 Cs-13 in Internationa tivity tatic a
0cm2)
A 700 90 900 900 100 100 A
A
-15
-80 pCi/g 60 and 37 al


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision Analysis /
License Termination Plan R
Gamma Radionucli Isotopic N (Np-237)
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)
Isotopic Pl (Pu-238/23 Isotopic Th (Th-228/23 Isotopic Ur (U-234/235 Isotopic Cu (Cm-243/2 Isotopic Am (Am-241/2 C-14 Tritium Sr-90 Pu-241 Tc-99 Gross Alph Fe-55 Ni-63 Ni-59 se Boiling W Termination n 0 Table 2-4 Analytes ides G
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.
eptunium A
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)
lutonium 39/240)
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.
A horium 30/232)
2-61
A ranium 5/238)
A urium 244)
A mericium 243)
A LS LS G
LS LS ha / Beta G
LS LS LS Water Reactor Plan Off-Site Technique Gamma Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec SC SC GFPC SC SC GFPC SC SC SC r
e Laboratory DOE E
< 0.1pC DOE E
< 0.04 p DOE E
< 0.05 p DOE E
< 0.05 p DOE E
< 0.06 p DOE E
< 0.03 p DOE E
< 0.04 p EPA EE
< 5.0 pC EPA 90
< 10.0 p DOE E
< 1.0 pC DOE E
< 10.0 p DOE E
< 2.0 pC DOE E
< 10.0 p DOE E
< 2.0 pC DOE E
< 50.0 p 2-43 y Analytica Soils (pCi/
EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g ERF C-01 Ci/g 06.0 pCi/g EML HASL 300 Ci/
EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g al Methods a Method and
/g) 0 0
0 0
0 0
0 0
0 0
0 0 (SRW01) 0 (SRW01) and Typical d Sensitivity Wat EPA Method 10.0 pCi/L EML Pu-02 M 1.0 pCi/L ENIC Modifi 50.0 pCi/L EPA 906.0 300.0 pCi/L EICHROM M 2.0 pCi/L EML Pu-01 50.0 pCi/L EICHROM T 15.0 pCi/L EPA 900.0 5.0 pCi/L EML Fe-01 M 100.0 pCi/L EML Ni-01 M 15.0 pCi/L EML Ni-01 M 100.0 pCi/L l MDCs ter (pCi/L) 901.1 Modified ied Modified Metho Tc-01 Modified Modified Modified od


La Crosse Boilin L                  ng Water Reacttor L
La Cross License T Revision se Boiling W Termination n 0 Ta Location Area West o Area South Area North Area at G-3 Area Outsid Area at G-3 33 miles So Pedretti Far Radio Towe Junction of East of Stod Water Reactor Plan able 2-5 of #2 Wareh of Parking L of LACBW Gas Silo de G-3 Offic Outfall uth at Bad A m Substation er Northeast Hwy O and ddard at Hwy r
License   Termination Plan R
2005 Dairy (on L house Lot R Admin Bu es (off L Axe Boat Lan n East of LA of LACBW Hwy K y O Junction 2-44 yland Backg Licensed Site uilding Licensed Site nding ACBWR WR n
Revision  0 Tablle 2-19      2014 Groundwater Monitoring Reesults (pCi/L)
ground Stud Co-60 (pCi/g) e)
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
<MDC
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
<MDC
Alpha G
<MDC
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
<MDC
Beta H
<MDC
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
<MDC e) 0.023
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+
<MDC
                                                                                                                                                                  +00  4.54E+00  44.55E+00    4.66E+000  1.30E+01 F
<MDC
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+
<MDC
                                                                                                                                                                  +01  -4.95E+01  -44.96E+01  -4.03E+01 1 -3.98E+00 N
<MDC dy for Soils Cs-(pC 0.0 0.0 0.
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+
0.0 0.0 0.0 0.3 0.2 0.0 0.
                                                                                                                                                                  +01  -2.71E+01  -44.66E+00  -6.22E+00 0 -2.47E+01 C
0.0
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
-137 Ci/g) 077 026 149 038 076 017 381 227 035 188 065
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.
2-62


La Crosse Boilin L                  ng Water Reacttor L
La Cross License T Revision T
License    Termination Plan R
Conditio Undisturb Disturbed Undisturb Disturbed se Boiling W Termination n 0 Table 2-6 on and Dept bed d
Revision    0 Table 2-19 (continued)    2014 Ground    dwater Monitooring Results (p pCi/L)
bed d
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
Water Reactor Plan Investiga th D
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
Non r
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
ative Levels Meas Drainage Ar 0.
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
0.
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
n-Drainage 0.
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
0.
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
2-45 for Cs-137 sured Rang (pCi/g) eas Surface 00 to 2.80 00 to 1.67 Areas Surfa 23 to 0.66 27 to 0.34 Based on B ge R e 0-10 cm ace 0-10 cm
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


L La Crosse Boilin ng Water Reactor L
===Background===
License Termination Plan R
Range for 95 (p
Revision 0 Figuree 2-1 LACBWR Site Map - Open Land Survey Units an nd Classificatioon 2-64
0.45 0.35 m
0.15 0.23 d Studies 5% Distribu pCi/g) 5 to 3.63 5 to 2.86 5 to 0.77 to 0.42 ution


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision se Boiling W Termination n 0 Table 2
License Termination Plan R
*L Water Reactor Plan
Revision 0 Figure 2-2 LACBWR Site Map - Buiildings Identifiication 2-65
-7 Initia Radio H
C Fe N
Co N
Sr Nb Tc Cs Eu Eu Eu Np Pu Pu Pu Pu Am Cm-24 Listed half life i r
al Suite of L onuclide H-3 C-14 e-55 i-59 o-60 i-63 r-90 b-94 c-99
-137 u-152 u-154 u-155 p-237 u-238 u-239 u-240 u-241 m-241 43/244*
is the shortest h 2-46 LACBWR S Ha half life for the Site-Specific alf Life (Yea 1.24E+01 5.73E+03 2.70E+00 7.50E+04 5.27E+00 9.60E+01 2.91E+01 2.03E+04 2.13E+05 3.00E+01 1.33E+01 8.80E+00 4.76E+00 2.14E+06 8.78E+01 2.41E+04 6.60E+03 1.44E+01 4.32E+02 1.81E+01 e radionuclides c Radionucl ars) s in the pair lides


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
L L
R S
S M
M M
M S
S M
M M
M S
A M
M M
M S
M M
La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Subsurface Soil
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Asphalt
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Surface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm) ng Water React ation Plan Table 2-8 Survey Unit 66,869 m2 G-3 Coal Plan Co-60 3
0 0.070 0.075 0.078 0.057 0.011 Co-60 4
0 0.060 0.056 0.084 0.047 0.016 Co-60 None Taken 1%
5,550 6,700 or Non-Impact t L4012103 nt Grounds Cs-137 3
1 0.082 0.083 0.092 0.071 0.011 Cs-137 4
1 0.048 0.038 0.081 0.036 0.022 Cs-137 ed Open Land Survey Unit 82,894 m2 Coal Pile Grou Co-60 3
0 0.071 0.072 0.084 0.057 0.014 Co-60 3
0 0.061 0.063 0.068 0.052 0.008 Co-60 None Taken 1%
5,050 8,800 2-47 Survey Units -
L4012105 1
nds C
G Cs-137 3
1 0.061 0.060 0.068 0.055 0.006 Cs-137 3
1 0.042 0.040 0.056 0.030 0.013 Cs-137 1
8 1
- Characterizat Survey Unit L 111,899 m2 Capped Ash Im Grounds Co-60 3
0 0.082 0.084 0.090 0.072 0.009 Co-60 4
0 0.081 0.083 0.102 0.056 0.021 Co-60 2
0 0.073 0.073 0.082 0.065 0.012 1%
8,340 12,000 tion Survey Su L4012106 8
mpoundment G H
Cs-137 3
2 0.100 0.099 0.121 0.079 0.021 Cs-137 4
2 0.088 0.084 0.130 0.054 0.037 Cs-137 2
0 0.062 0.062 0.084 0.040 0.031 ummary Survey Unit L 81,254m2 Grounds East of Highway 35 Co-60 3
0 0.080 0.079 0.089 0.072 0.009 Co-60 3
0 0.081 0.069 0.106 0.068 0.022 Co-60 None Tak 1%
8,000 9,080 L4012107 f
Cs-137 3
3 0.264 0.263 0.463 0.065 0.199 Cs-137 3
2 0.068 0.057 0.091 0.056 0.020 Cs-137 ken


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
L L
R La Crosse Boilin License Termin Revision 0 Tabl ng Water React ation Plan le 2-8 (continue S
S M
M M
M SD S
M M
M M
SD A
M M
M M
SD S
M M
or ed)
Non-I urvey Unit Surface Area Description urface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D ubsurface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D Asphalt of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D urface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm)
Impacted Open Survey Unit 9,444 m2 Hwy 35/Railro Way Grounds Co-60 3
0 0.079 0.075 0.095 0.068 0.014 Co-60 3
0 0.086 0.092 0.107 0.060 0.024 Co-60 None Taken 1%
8,124 9,200 2-48 n Land Survey L4012108 1
ad Right of B A
Cs-137 3
2 0.119 0.108 0.156 0.093 0.033 Cs-137 3
2 0.189 0.091 0.409 0.067 0.191 Cs-137 Units - Chara Survey Unit L 100 m2 Background Soi Area (inside L40 Co-60 17 0
0.087 0.086 0.101 0.077 0.007 Co-60 None Ta Co-60 None Ta No Scanning P acterization Sur L4012109 ils Test 012108)
Cs-137 17 17 0.160 0.161 0.268 0.059 0.059 Cs-137 aken Cs-137 aken Performed rvey Summaryy


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
L L
R R
L L
L L
L L
L L
L L
L L
a b
La Crosse Boilin License Termin Revision 0 Radionuclide L3012103-QJ-GS-001-S L3012103-QJ-GS-001-S L3012105-Genoa Coal P L3012105-CR-GS-002-L3012105-QJ-GS-001-S L3012105-QJ-GS-001-S L3012106-QJ-GS-001-S L3012106-QJ-GS-001-S L3012107-QJ-GS-001-S L3012107-QJ-GS-001-S L3012108-QJ-GS-001-S L3012108-QJ-GS-001-S a
Bold values b
Survey units ng Water React ation Plan H-3 C
SB 4.390 1
SS 3.570 0.
Pile
-SS 0.533 0.
SB SS SB 14.600 0.
SS 0.813 0.
SB SS 1.420 0.
SB 2.350 0.
SS 6.490 0.
indicate concentration g originally classified as tor Table 2-9 C-14 Fe-55 N
.230 3.430 1
.671 2.790 1
.675 2.130 1
.713 2.300 2
.713 3.550 2
.719 3.610 2
.705 1.920 3
.728 2.260 3
greater than MDC. Itali Class 3 at time of samp Non Impa Ni-59 Co-60 N
.470 0.026 2
.870 0.027 3
0.018
.730 0.025 2
0.026 0.030
.370 0.037 3
.560 0.037 3
0.019
.800 0.025 3
.110 0.018 4
.200 0.030 4
icized values indicate M ple acted Coal Pile Ni-63 Sr-90 N
.140 0.321 0
.380 0.391 0
0
.950 0.289 0
0 0
.950 0.348 0
.580 0.338 0
0
.940 0.293 0
.440 0.278 0
.710 0.271 0
MDC value 2-49 and Soil Samp Nb-94 Tc-99 Cs 0.018 0.820 0
0.022 0.628 0
0.022 0
0.016 0.587 0
0.020 0
0.020 0
0.030 0.611 0
0.028 0.616 0
0.013 0
0.019 0.593 0
0.016 0.604 0
0.020 0.576 0
ples - Test Ame s-137 Pm-147 Eu 0.024 0.714 0
0.018 0.847 0
0.019 0
0.018 0.698 0
0.023 0
0.028 0
.319 1.500 0
.096 0.826 0
0.021 0
.018 1.450 0
.033 1.310 0
.182 0.770 0
erica Laborator u-152 Eu-154 Eu 0.071 0.190 0
0.060 0.167 0
0.052 0.152 0
0.051 0.137 0
0.049 0.166 0
0.072 0.199 0
0.115 0.223 0
0.079 0.232 0
0.045 0.115 0
0.049 0.156 0
0.041 0.128 0
0.059 0.176 0
ry Analysis (pC u-155 Np-237 Pu 0.095 0.025 0
0.096 0.024 0
0.048 0.056 0.023 0
0.055 0.074 0.080 0.035 0
0.112 0.027 0
0.038 0.048 0.040 0
0.044 0.030 0
0.060 0.020 0
Ci/g) u-238 Pu-239/240 Pu 0.046 0.015 1
0.040 0.021 1
0.036 0.029 1
0.036 0.014 2
0.044 0.026 2
0.021 0.024 2
0.026 0.021 2
0.028 0.029 2
u-241 Am-241 A
1.730 0.032 0
1.650 0.025 0
0.041 1.670 0.018 0
0.048 0.061 2.550 0.019 0
2.740 0.025 0
0.034 2.580 0.020 0
2.670 0.017 0
2.740 0.015 0
Am-243 Cm-243/244 0.022 0.010 0.024 0.019 0.025 0.006 0.034 0.006 0.013 0.019 0.035 0.006 0.036 0.017 0.024 0.015


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
L L
R S
S M
M M
M S
S M
M M
M S
A M
M M
M S
S M
M a
La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Subsurface Soil
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Asphalt
# of Samples
# >CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
SD Surface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm) a MDC va ng Water React ation Plan Table 2-10 Survey Unit 1,992 m2 Reactor Buil WGTV, Vent Grounds Co-60 12 2
0.080 0.058 0.287 0.048 0.066 Co-60 18 0
0.078 0.052 0.516 0.047 0.109 None Taken No Scanning P alue used for ana or Impacted Cla t L1010101 lding, WTB, tilation Stack Cs-137 12 12 0.215 0.100 1.070 0.032 0.296 Cs-137 18 8
0.066 0.054 0.161 0.033 0.035 Performed alytical results l ass 1 Open Land Survey Unit 2,315 m2 Turbine, Office Generator Buil Grounds Co-60 2
0 0.049 0.049 0.054 0.044 0.007 Co-60 22 0
0.058 0.058 0.080 0.043 0.010 None Taken No Scanning P less than MDC.
2-50 d Survey Units L1010102 1
e, Diesel ding L
M G
Cs-137 2
0 0.050 0.050 0.051 0.050 0.001 Cs-137 22 4
0.064 0.065 0.130 0.044 0.017 N
erformed N
s - Characteriz Survey Unit L 1,749 m2 LSA Building, Maintenance Ea Grounds Co-60 7
0 0.059 0.050 0.099 0.048 0.019 Co-60 25 0
0.046 0.046 0.055 0.025 0.005 None Taken No Scanning Pe zation Survey S L1010103 2
at Shack N
Cs-137 7
1 0.069 0.054 0.161 0.048 0.041 Cs-137 25 0
0.049 0.049 0.054 0.042 0.003 erformed Summary Survey Unit L 2,387 m2 North LSE Grou Co-60 1
0 0.045 0.045 0.045 0.045 N/A Co-60 14 0
0.048 0.048 0.050 0.043 0.002 Co-60 10 0
0.053 0.054 0.062 0.042 0.006 No Scanning Pe L1010104 unds Cs-137 1
0 0.049 0.049 0.049 0.049 N/A Cs-137 14 3
0.041 0.042 0.051 0.027 0.009 Cs-137 10 1
0.051 0.053 0.057 0.037 0.006 erformed


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
L L
R R
L L
L L
L L
L L
L L
L L
L L
L L
L L
L L
L L
L L
a La Crosse Boilin License Termin Revision 0 Radionuclide L1010101-CJ-GS-002-S L1010101-CJ-GS-009-S L1010101-CJ-GS-010-S L1010101-QJ-GS-001-S L1010101-QJ-GS-001-S L1010101-QJ-GS-002-S L1010101-QJ-GS-002-S L1010102-CJ-FC-001-C L1010102-CJ-GS-013-S L1010102-QJ-GS-001-S L1010102-QJ-GS-001-S L1010102-QJ-GS-002-S L1010103-CJ-GS-002-S L1010103-QJ-SL-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-002-S L1010103-QJ-GS-002-S L1010103-QJ-GS-003-S L1010103-QJ-GS-003-S L1010104-CJ-GS-003-S L1010104-CR-PA-007-L1010104-QQ-PA-001-L1010104-QR-GS-001-a Bold values ng Water React ation Plan T
H-3 C
SS SS SS SB 0.364 0
SS 0.441 0.
SB 0.377 0.
SS 1.380 0.
CV 1.710 0.
SB SB 8.740 0.
SS SB 24.700 0.
SB SM 0.354 0
SB 3.260 0.
SS SB 0.649 0.
SS SB 0.654 0.
SS SB
-AV
-AV
-SB indicate concentration g tor Table 2-11 C
C-14 Fe-55 N
.896 2.430 1
.676 2.190 1
.679 2.150 1
.677 4.190 2
.727 1.650 2
.726 2.120 2
.715 2.230 2
.453 0.689 0
.715 1.830 2
.702 2.100 2
.717 2.340 2
greater than MDC. Itali lass 1 Concrete Ni-59 Co-60 N
0.024 0.040 0.286
.850 0.024 3
.900 0.018 3
.750 0.017 2
.010 0.015 3
.630 0.106 3
0.030
.620 0.015 4
0.022
.760 0.021 3
0.011 0.711 0.136 1
.850 0.017 4
0.025
.620 0.014 3
0.019
.630 0.012 3
0.023 0.015 0.021 0.025 0.017 icized values indicate M e, Asphalt, Sed Ni-63 Sr-90 N
0 0
0
.040 0.335 0
.040 0.440 0
.930 0.338 0
.320 0.357 0
.920 0.292 0
0
.000 0.310 0
0
.920 0.316 0
0
.090 0.132 0
.240 0.333 0
0
.710 0.325 0
0
.660 0.300 0
0 0
0 0
0 MDC value.
2-51 diment and Soil Nb-94 Tc-99 Cs 0.020 0
0.020 0
0.025 0
0.015 0.579 0
0.012 0.587 0
0.011 0.620 0
0.010 0.521 0
0.022 0.536 0
0.016 0
0.011 0.539 0
0.015 0
0.014 0.537 0
0.017 0
0.018 0.432 0
0.011 0.606 0
0.015 0
0.012 0.645 0
0.017 0
0.009 0.557 0
0.019 0
0.008 0
0.014 0
0.025 0
0.011 0
l Samples - Tes s-137 Pm-147 Eu
.233 0
.185 0
.413 0
0.020 0.800 0
.147 3.170 0
.149 0.772 0
.059 0.978 0
.352 1.290 0
0.021 0
0.012 0.961 0
0.018 0
0.016 0.722 0
0.021 0
.136 0.360 0
0.015 0.740 0
0.020 0
0.012 0.838 0
0.017 0
0.011 0.713 0
.091 0
0.013 0
0.016 0
0.028 0
0.012 0
st America Lab u-152 Eu-154 Eu 0.056 0.161 0
0.056 0.181 0
0.062 0.247 0
0.050 0.143 0
0.034 0.112 0
0.040 0.109 0
0.033 0.096 0
0.061 0.239 0
0.044 0.170 0
0.030 0.101 0
0.036 0.113 0
0.043 0.139 0
0.044 0.181 0
0.054 0.199 0
0.036 0.117 0
0.046 0.174 0
0.029 0.103 0
0.040 0.139 0
0.029 0.092 0
0.057 0.186 0
0.032 0.078 0
0.042 0.141 0
0.058 0.218 0
0.038 0.132 0
boratory Analy u-155 Np-237 Pu 0.066 0.050 0.057 0.044 0.019 0
0.044 0.006 0
0.040 0.019 0
0.036 0.016 0
0.062 0.029 0
0.041 0.028 0.028 0
0.042 0.042 0.032 0
0.046 0.049 0.018 0
0.039 0.026 0
0.047 0.034 0.020 0
0.045 0.034 0.040 0
0.063 0.036 0.044 0.061 0.032 ysis (pCi/g) u-238 Pu-239/240 Pu 0.046 0.023 1
0.039 0.023 1
0.041 0.022 1
0.040 0.016 2
0.041 0.028 2
0.040 0.026 2
0.042 0.029 2
0.015 0.015 0
0.029 0.017 1
0.034 0.024 2
0.028 0.028 2
u-241 Am-241 A
0.058 0.042 0.051 1.970 0.015 0
1.830 0.016 0
1.950 0.017 0
2.090 0.020 0
2.490 0.018 0
0.036 2.780 0.015 0
0.039 2.660 0.015 0
0.044 0.867 0.008 0
1.430 0.009 0
0.043 2.570 0.018 0
0.024 2.470 0.018 0
0.052 0.034 0.040 0.050 0.032 Am-243 Cm-243/244 0.023 0.021 0.021 0.019 0.029 0.014 0.017 0.022 0.019 0.021 0.020 0.021 0.021 0.018 0.019 0.008 0.024 0.005 0.024 0.014 0.022 0.005


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 Cross License T Revision Tabl Sur Sur
# of
# >C Mea Med Max Min SD Sub
# of
# >C Mea Med Max Min SD Asp
# of
# >C Mea Med Max Min SD Sur
% S Mea Max se Boiling W Termination n 0 le 2-12 Im rvey Unit Surface Area Description rface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) bsurface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) phalt f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) rface Scans Scanned an Scan (cpm) x Scan (cpm)
Water Reactor Plan mpacted Cla Sur 7,211 m2 LACBWR
: Building, House, W Co-60 13 0
0.073 0.077 0.106 0.053 0.016 Co-60 16 1
0.052 0.046 0.112 0.040 0.018 Co-60 6
0 0.051 0.051 0.054 0.047 0.002 50%
7,500 to 8,0 11,500 to 12 r
ass 2 Open L S
rvey Unit L201 R
Adm LACBW Warehouse Gr 0
3 7
6 3
6 0
2 6
2 0
8 0
4 7
2 00 2,000 2-52 Land Surve Summary 11101 ministration WR Crib rounds Cs-137 13 8
0.090 0.100 0.139 0.041 0.030 Cs-137 16 2
0.049 0.048 0.088 0.034 0.012 Cs-137 6
0 0.051 0.051 0.054 0.047 0.003 ey Units - C Sur 6,785 m2 G-3 Crib Circ. Wa Area Sout Co-60 10 0
0.064 0.064 0.081 0.052 0.009 Co-60 7
0 0.049 0.048 0.055 0.042 0.004 Co-60 6
0 0.056 0.057 0.059 0.049 0.003 1
Characteriza rvey Unit L201 b House, ater Discha th of LSE Fe 0
4 4
2 9
0 9
8 5
2 4
0 6
7 9
9 3
50%
7,500 to 8,000 11,500 to 12,00 ation Surve 11102 LACBWR arge Line, ence Cs-137 10 6
0.065 0.054 0.200 0.030 0.049 Cs-137 7
2 0.038 0.033 0.052 0.029 0.009 Cs-137 6
3 0.048 0.051 0.055 0.009 0.008 0
00 ey


La Crossse Boiling Water W    Reactorr License Termination T            Plan Revision n0 Figure 2-9 9  Concreete Core Sam mpling Loccations 2-72
L L
R R
L L
L L
L L
L L
L L
L L
L a
La Crosse Boilin License Termin Revision 0 Radionuclide L2011101-CJ-GS-001-S L2011101-CR-PA-003-L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QQ-GS-001-L2011101-QQ-GS-001-L2011101-QQ-GS-002-L2011101-QQ-PA-001-L2011102-QQ-GS-001-L2011102-QQ-GS-001-L2011102-QQ-GS-002-L2011102-QQ-PA-001-a Bold val ng Water React ation Plan H-3 C
SM
-AV SB 0.518 0.
SM 2.040 0.
SS
-SB
-SS 11.810 0.
-SB 2.500 0.
-AV
-SB 1.370 1
-SS 0.533 0.
-SB 0.525 0.
-AV lues indicate con tor Table 2 C-14 Fe-55 N
.727 2.290 2
.707 2.240 2
.726 2.590 2
.731 1.940 2
.560 2.260 3
.713 2.330 2
.702 3.890 2
ncentration grea 2-13 Class 2 Ni-59 Co-60 N
0.096 0.023
.660 0.016 4
.950 0.049 4
0.012 0.017
.600 0.035 3
.680 0.017 3
0.022
.040 0.007 4
.820 0.019 4
.880 0.031 3
0.027 ater than MDC.
Asphalt, Sedim Ni-63 Sr-90 N
0 0
.030 0.273 0
.140 0.523 0
0 0
.720 0.255 0
.870 0.314 0
0
.390 0.291 0
.300 0.361 0
.950 0.327 0
0 Italicized value 2-53 ment and Soil S Nb-94 Tc-99 Cs 0.011 0
0.016 0
0.014 0.643 0
0.018 0.585 0
0.020 0
0.012 0
0.035 0.532 0
0.014 0.616 0
0.015 0
0.018 0.537 0
0.014 0.595 0
0.016 0.568 0
0.017 0
es indicate MDC Samples - Test s-137 Pm-147 Eu
.137 0
0.017 0
0.015 0.705 0
.107 0.615 0
.080 0
0.013 0
.103 0.779 0
0.016 0.697 0
0.015 0
0.021 0.672 0
0.014 0.772 0
0.018 0.717 0
0.018 0
C value.
America Labo u-152 Eu-154 Eu 0.041 0.098 0
0.039 0.131 0
0.033 0.108 0
0.048 0.178 0
0.060 0.188 0
0.040 0.127 0
0.097 0.205 0
0.037 0.119 0
0.046 0.135 0
0.044 0.173 0
0.039 0.111 0
0.052 0.183 0
0.051 0.142 0
oratory Analysi u-155 Np-237 Pu 0.033 0.039 0.040 0.022 0
0.049 0.026 0
0.091 0.037 0.102 0.023 0
0.041 0.019 0
0.042 0.055 0.031 0
0.045 0.017 0
0.051 0.022 0
0.038 is u-238 Pu-239/240 Pu 0.028 0.025 2
0.045 0.021 3
0.037 0.024 2
0.039 0.016 2
0.026 0.018 2
0.036 0.026 2
0.028 0.020 1
u-241 Am-241 A
0.031 0.038 2.470 0.015 0
3.100 0.037 0
0.042 0.031 2.800 0.019 0
2.920 0.020 0
0.040 2.680 0.029 0
2.880 0.026 0
1.710 0.010 0
0.036 Am-243 Cm-243/244 0.022 0.019 0.036 0.034 0.015 0.015 0.028 0.016 0.028 0.024 0.034 0.021 0.028 0.006


La Crossse Boiling Water W      Reactorr License Termination T            Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-73
L L
R La Crosse Boilin License Termin Revision 0 S
S M
M M
M S
S M
M M
M S
C M
M M
M S
S M
M ng Water React ation Plan Table 2-14 urvey Unit Surface Area Description urface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D ubsurface Soil of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D Concrete/Asphalt of Samples
>CL Mean (pCi/g)
Median (pCi/g)
Max (pCi/g)
Min (pCi/g)
D urface Scans
% Scanned Mean Scan (cpm)
Max Scan (cpm) or Impacted Cla Survey Unit 24,042 m2 North End of Lic Co-60 3
0 0.070 0.076 0.077 0.058 0.011 Co-60 3
0 0.051 0.053 0.054 0.046 0.004 Co-60 3
0 0.031 0.031 0.035 0.028 0.003 1%
9,000 10,000 ass 3 Open Land t L3012101 censed Site Cs-137 3
0 0.073 0.072 0.083 0.065 0.009 Cs-137 3
0 0.051 0.052 0.052 0.051 0.001 Cs-137 3
0 0.029 0.027 0.033 0.026 0.004 2-54 d Survey Units Survey Unit 11,711 m2 Transmission Swi Co-60 None T Co-60 None T Co-60 None Taken No Scanning s - Characteriz L3012102 3
tchyard Area P
G Cs-137 Taken Cs-137 Taken Cs-137 Performed zation Survey S Survey Unit L 31,012 m2 Plant Access, ISF Grounds Co-60 5
0 0.063 0.064 0.078 0.053 0.010 Co-60 4
0 0.072 0.072 0.100 0.046 0.023 Co-60 7
0 0.062 0.055 0.080 0.047 0.013 1%
5,890 6,400 Summary L3012109 SI Haul Road Cs-137 5
5 0.152 0.143 0.267 0.075 0.078 Cs-137 4
0 0.066 0.059 0.101 0.045 0.025 Cs-137 7
0 0.059 0.052 0.079 0.028 0.019 0
0


La Crossse Boiling Water W      Reactorr License Termination T            Plan Revision n0 Figurre 2-9 (contiinued) Concrete Core Sampliing Location ns 2-74
L L
R R
L L
L L
L L
L L
L L
L a
La Crosse Boilin License Termin Revision 0 Radionuclide L3012101-CR-GC-001-L3012101-CR-GC-002-L3012101-CR-GC-003-L3012101-CR-GS-003-L3012101-QQ-GS-001-L3012101-QQ-GS-001-L3012101-QQ-SL-001-L3012104-CR-GS-002-L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S a
Bold values ng Water React ation Plan H-3 C
-CV
-CV
-CV 0.
-SS
-SB 18.400 0.
-SS 15.500 0.
-SM 0.364 0.
-SM SB 2.160 0.
SM 2.890 0.
SS 2.190 0.
indicate concentration g tor Table 2-15 C-14 Fe-55 N
.669 2.180 2
.717 2.390 2
.708 2.330 2
.342 2.710 0
.670 1.950 1
.672 2.720 1
.676 4.240 1
greater than MDC. Itali 5
Class 3 Asp Ni-59 Co-60 N
0.028 0.035
.020 0.031 3
0.025
.870 0.016 5
.660 0.020 3
0.739 0.022 1
0.015
.750 0.021 3
.990 0.037 3
.880 0.029 3
icized values indicate M phalt, Sediment Ni-63 Sr-90 N
0 0
.590 0.374 0
0
.640 0.309 0
.890 0.295 0
.090 0.152 0
0
.060 0.325 0
.500 0.298 0
.300 0.329 0
MDC value 2-55 t and Soil Samp Nb-94 Tc-99 Cs 0.030 0
0.026 0
0.027 0.521 0
0.017 0
0.014 0.550 0
0.017 0.603 0
0.017 0.360 0
0.013 0
0.018 0.469 0
0.020 0.651 0
0.020 0.631 0
ples - Test Am s-137 Pm-147 Eu 0.026 0
0.033 0
0.027 1.480 0
.113 0
0.015 0.899 0
.059 1.090 0
0.020 0.333 0
.066 0
0.025 0.818 0
.094 0.818 0
.138 0.667 0
merica Laborato u-152 Eu-154 Eu 0.043 0.221 0
0.062 0.271 0
0.056 0.249 0
0.052 0.157 0
0.036 0.128 0
0.047 0.116 0
0.042 0.153 0
0.035 0.128 0
0.053 0.160 0
0.074 0.217 0
0.068 0.181 0
ory Analysis (p u-155 Np-237 Pu 0.059 0.056 0.069 0.025 0
0.059 0.036 0.039 0
0.054 0.028 0
0.034 0.009 0
0.047 0.054 0.022 0
0.071 0.006 0
0.080 0.020 0
pCi/g) u-238 Pu-239/240 Pu 0.046 0.018 1
0.035 0.022 2
0.028 0.022 2
0.016 0.013 0
0.027 0.021 1
0.031 0.017 1
0.043 0.026 1
u-241 Am-241 A
0.053 0.055 1.690 0.019 0
0.052 2.590 0.023 0
2.640 0.019 0
0.797 0.009 0
0.036 1.610 0.016 0
1.560 0.016 0
1.580 0.019 0
Am-243 Cm-243/244 0.021 0.006 0.029 0.027 0.021 0.006 0.009 0.011 0.018 0.016 0.016 0.015 0.019 0.021


L La Crosse Boilin ng Water Reactor L
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 T
License Termination Plan R
B1001101-C Result (pCi/g) 3.950
Revision 0 Figure 2-10 LACBWR Siite - Typical Geeological Crosss-Section 2-75
-0.162 9.130 0.000 11.500 39.300 6.910
-0.120 0.024 7500 2.580 0.266 0.369 0.009 0.176 0.132 0.902 0.407 0.028 0.0579 B1001101-C Result (pCi/g) 7.240
-0.492 9.450 0.000 57.700 202.000 34.500 0.191
-0.189 614.000 0.768 0.335
-0.429 0.000 0.528 0.491 7.470 1.450 0.052 0.0879 Water Reactor Plan Table 2-16 CJ-FC-001-CV 0 MDC (pCi/g)
(p 1.590 1
1.400 0
16.000 7
0.254 0
0.377 1
0.402 4
0.043 0
0.312 0
0.566 0
7.090 78 9.020 5
2.410 0
4.440 1
0.042 0
0.056 0
0.048 0
2.700 1
0.048 0
0.046 0
0.0302 0.
CJ-FC-003-CV 0 MDC (pCi/g)
(p 1.360 1
1.460 0
9.040 4
0.365 0
0.333 5
0.593 21 0.040 3
0.392 0
0.586 0
0.732 64 2.870 1
5.460 0
1.510 0
0.041 0
0.058 0
0.030 0
2.640 2
0.047 0
0.027 0
0.0408 0.
r Concrete 0-1/2 B
R pCi/g)
(p
.350 9
.793
-0
.880 10
.325 0
.250 0
.110 3
.680 0
.189 0
.330 0
1.000 9
.230
-0
.398 0
.140 0
.021
-0
.065
-0
.055
-0
.660
-1
.107 0
.030 0
0371
-0 0-1/2 B
R pCi/g)
(p
.580 12
.806
-0
.950 6
.806 0
.880 0
1.100 2
.330 0
.203
-0
.330
-0 4.000 2
.300 0
.536 0
.914
-0
.016
-0
.111
-0
.104
-0
.160
-1
.250 0
.033 0
0496 0.
2-56 Core Isotop B1001101-CJ-FC Result MD pCi/g)
(pCi/
9.720 1.56 0.346 1.44 0.400 21.3 0.000 0.26 0.082 0.16 3.850 0.42 0.162 0.05 0.001 0.13 0.076 0.52 9.660 0.15 0.039 0.51 0.025 1.26 0.071 0.37 0.002 0.04 0.017 0.06 0.006 0.04 1.510 2.50 0.011 0.03 0.014 0.03
.0081 0.04 B1001101-CJ-FC Result MD pCi/g)
(pCi/
2.600 1.57 0.566 1.39 6.160 14.3 0.000 0.25 0.435 0.05 2.990 0.40 0.304 0.05 0.001 0.15 0.129 0.59 2.450 0.11 0.045 0.34 0.179 1.02 0.007 0.28 0.010 0.05 0.005 0.06 0.004 0.04 1.320 2.66 0.018 0.03 0.009 0.03
.0000 0.01 pic Analysis C-001-CV 1/2-1 DC


L La Crosse Boilin ng Water Reactor L
/g)
License Termination Plan R
(pCi/g) 60 1.950 40 0.806 300 10.200 64 0.151 68 0.078 25 0.474 51 0.041 39 0.078 26 0.310 52 1.100 11 0.055 60 0.171 76 0.118 45 0.017 66 0.026 49 0.018 00 1.360 37 0.020 30 0.019 478 0.0094 C-003-CV 1/2-1 DC
Revision 0 Figure 2-11 1 Groundwatter Sampling Wells - LACBW WR Site 2-76}}
 
/g)
(pCi/g) 70 2.240 90 0.765 300 6.960 57 0.157 57 0.096 00 0.392 51 0.052 53 0.086 96 0.339 13 0.348 46 0.154 20 0.383 82 0.164 51 0.018 64 0.029 47 0.017 60 1.480 38 0.024 30 0.016 68 0.0047 s Results B1001 Result (pCi/g) 3.640
-0.270 0
11.300 0.000 0.800 4.860 11.600
-0.017
-0.104 450.00 0.173
-0.008 0.145
-0.010 0.575 0.715 13.200 0.550
-0.036 4
0.1540 B1001 Result (pCi/g) 4.490
-0.555 7.600 0.000 28.100 88.300 11.000
-0.016 0.153 213.00 0.162 0.557 0.108
-0.020 0.413 0.336
-7.720 0.614 0.052 7
-0.0547 101-CJ-FC-002 t
MDC (pCi/g) 1.620 0
1.410 0
9.950 0.289 0.117 0.492 0
0.046 7
0.165 4
0.564 0
0.597 2.150 8
1.460 0.837 0
0.042 0.617 0.466 0
23.500 0.401 6
0.433 0
0.4670 101-CJ-FC-004 t
MDC (pCi/g) 1.590 5
1.450 7.070 0.276 0
0.190 0
0.467 0
0.045 6
0.264 0.592 0
0.439 1.570 3.070 0.850 0
0.060 0.426 0.325 0
26.000 0.441 0.292 7
0.4320
-CV 0-1/2
 
(pCi/g) 1.330 0.794 5.540 0.183 0.172 0.581 1.130 0.095 0.322 46.900 0.924 0.820 0.503 0.009 0.436 0.413 15.100 0.419 0.140 0.2600
-CV 0-1/2
 
(pCi/g) 1.420 0.795 4.040 0.467 2.950 9.200 1.070 0.155 0.352 22.200 0.611 0.863 0.138 0.020 0.320 0.265 14.400 0.436 0.136 0.0776
 
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1001101-C Result (pCi/g) 2.960
-0.077 8.070 2.590 73.900 221.000 32.800
-0.089 0.178 65.700 0.395 0.637 0.011 0.005 0.706 0.489 9.090 1.590 0.048 0.1160 B1001101-C Result (pCi/g) 3.590
-0.246 6.030 0.000
-0.026 2.310 0.146 0.019 0.024 1.410 0.021 0.055 0.003 0.003
-0.004 0.035
-1.890 0.006
-0.002
-0.0036 Water Reactor Plan
-16 (continu CJ-FC-005-CV 0 MDC (pCi/g)
(p 1.520 1
1.410 0
9.770 5
0.267 0
0.372 7
0.427 23 0.043 3
0.531 0
0.562 0
0.569 6
1.240 0
5.650 0
0.699 0
0.015 0
0.065 0
0.035 0
2.540 2
0.045 0
0.031 0
0.0443 0.
CJ-WC-006-CV MDC (pCi/g)
(p 1.640 1
1.490 0
14.500 7
0.257 0
0.207 0
0.396 0
0.038 0
0.141 0
0.556 0
0.153 0
0.434 0
1.270 0
0.336 0
0.045 0
0.043 0
0.033 0
2.360 1
0.036 0
0.031 0
0.0287 0.
r ued)
Co 0-1/2 B
R pCi/g)
(p
.200 4
.810
-0
.230 8
.813 0
.510 0
3.000 4
.170 0
.317
-0
.336
-0
.970 0
.746 0
.831 0
.414 0
.010
-0
.134
-0
.106
-0
.270 0
.273 0
.034
-0 0590 0
1/2-1 R
pCi/g)
(p
.350 0
.836 0
.050 1
.147 0
.240 0
.335 2
.034 0
.060 0
.324
-0
.258 16
.113 0
.137 0
.196 0
.021 0
.016 0
.028
-0
.270
-1
.017 0
.005
-0 0052 0
2-57 oncrete Cor B1001101-CJ-FC Result MD pCi/g)
(pCi/
4.180 1.85 0.701 1.35 8.170 9.87 0.000 0.27 0.075 0.17 4.870 0.43 0.423 0.05 0.015 0.12 0.124 0.54 0.801 0.11 0.001 0.37 0.119 0.92 0.013 0.25 0.017 0.05 0.003 0.05 0.008 0.03 0.337 2.53 0.012 0.01 0.002 0.05
.0000 0.01 B1008101-CJ-Result MD pCi/g)
(pCi/
0.382 0.94 0.053 1.37 1.610 6.55 0.000 0.23 0.662 0.06 2.730 0.35 0.154 0.05 0.000 0.21 0.010 0.57 6.000 0.17 0.034 0.63 0.060 1.20 0.140 0.35 0.003 0.04 0.018 0.06 0.011 0.05 1.120 2.71 0.020 0.04 0.002 0.04
.0062 0.01 re Isotopic A C-005-CV 1/2-1 DC
 
i/g)
(pCi/g) 50 1.520 50 0.733 70 5.340 70 0.165 71 0.080 30 0.570 51 0.063 28 0.074 40 0.307 17 0.172 73 0.005 23 0.245 55 0.148 54 0.016 53 0.023 38 0.008 30 1.510 18 0.017 54 0.022 76 0.0049
-FC-002-CV DC
 
i/g)
(pCi/g) 40 0.559 70 0.794 50 3.370 34 0.151 65 0.131 53 0.355 53 0.041 11 0.066 79 0.335 77 1.780 33 0.056 00 0.239 57 0.215 48 0.022 60 0.033 54 0.019 10 1.480 42 0.027 44 0.017 87 0.0125 Analysis Re B1001 Result (pCi/g) 4.210 0.077 11.700 0.000 2.040 13.400 7.150 0.026 0.083 1490 0.031 0.128 0.737
-0.013 0.029 0.035
-1.380 0.048 0.003
-0.0053 B10 Result (pCi/g) 1.300
-0.296 6.460 0.000 0.974 4.400 0.235 0.016
-0.005 10.000 0.291 0.019 0.101
-0.024 0.042 0.008
-0.194 0.019
-0.001
-0.0056 esults 101-CJ-WC-006 t
MDC
)
(pCi/g) 1.700 1.440 0
9.320 0.263 0.047 0
0.420 0.034 0.154 0.580 0.721 3.660 1.190 1.470 0.044 0.037 0.025 2.650 0.052 0.029 3
0.0419 008101-CJ-FC-0 t
MDC
)
(pCi/g) 1.020 1.440 14.500 0.241 0.142 0.356 0.035 0.141 0.592 0
0.154 0.470 1.410 0.348 0.068 0.057 0.034 2.550 0.051 0.052 6
0.0444 6-CV 0-1/2
 
(pCi/g) 1.440 0.832 5.530 0.230 0.264 1.430 0.703 0.090 0.341 155.000 2.210 0.679 0.896 0.010 0.027 0.026 1.470 0.041 0.011 0.0075 003-CV
 
(pCi/g) 0.713 0.810 7.050 0.171 0.162 0.510 0.041 0.081 0.343 1.130 0.270 0.052 0.208 0.025 0.038 0.017 1.470 0.029 0.023 0.0080
 
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B100810 Result (pCi/g) 1.200 0.077 6.520 0.000 1.390 4.260 0.216 0.001 0.043 19.800
-0.119
-0.061 0.006 0.014 0.020 0.025
-1.610 0.052
-0.004 0.0100 B1002101-C Result (pCi/g) 0.763
-0.776 3.540 0.000 0.742 3.360 2.410 0.035 0.259 3.630 0.156 0.119 0.159 0.000 0.023 0.000
-0.052 0.020 0.013 0.0048 Water Reactor Plan
-16 (continu 01-CJ-FC-004-C MDC (pCi/g)
(p 0.990 0
1.430 0
11.500 5
0.229 0
0.095 0
0.339 0
0.040 0
0.143 0
0.599 0
0.166 2
0.580 0
1.370 0
0.376 0
0.065 0
0.052 0
0.042 0
2.610 1
0.034 0
0.032 0
0.0150 0.
CJ-FC-001-CV MDC (pCi/g)
(p 1.000 0
1.410 0
5.670 3
0.228 0
0.069 0
0.333 0
0.050 0
0.149 0
0.564 0
0.150 0
0.420 0
1.400 0
0.335 0
0.045 0
0.061 0
0.049 0
2.820 1
0.015 0
0.029 0
0.0143 0.
r ued)
Co CV B
R pCi/g)
(p
.685 0
.829 0
.820 15
.162 65
.255 95
.492 81
.041 99
.081 0
.350 0
.150 4
.344 0
.296 1
.220 0
.035
-0
.030 0
.028 1
.430 5
.035 3
.006 0
0142 0.
1-1.5 B
R pCi/g)
(p
.638 0
.763 0
.150 7
.159 0
.148 0
.407 5
.250 0
.066
-0
.342 0
.493 2
.236 0
.382 0
.204 0
.018
-0
.035 0
.021 0
.640
-2
.020 0
.018 0
0096 0.
2-58 oncrete Cor B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.820 0.98 0.505 1.41 5.400 13.8 5.500 0.31 5.000 0.42 7.000 0.47 9.800 0.04 0.098 0.47 0.113 0.56 4710 1.69 0.815 5.94
.250 5.46 0.073 2.12 0.012 0.06 0.920 0.62
.280 0.46 5.240 26.7 3.200 0.42 0.406 0.29
.2020 0.42 B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.094 0.91 0.372 1.38 7.770 25.0 0.000 0.25 0.872 0.13 5.730 0.38 0.106 0.04 0.034 0.14 0.032 0.52 2.440 0.14 0.125 0.38 0.271 0.95 0.099 0.32 0.007 0.05 0.004 0.06 0.009 0.04 2.090 2.70 0.017 0.04 0.029 0.02
.0059 0.03 re Isotopic A C-001-CV 0-1/2 DC
 
/g)
(pCi/g) 85 0.637 10 0.850 800 7.430 10 8.690 20 9.600 72 85.000 45 9.600 75 0.149 64 0.333 90 491.000 40 1.410 60 1.980 20 1.280 60 0.023 20 0.511 69 0.537 700 16.200 28 0.989 96 0.310 200 0.2670 C-001-CV 1.5-2 DC
 
/g)
(pCi/g) 17 0.512 80 0.819 000 11.400 59 0.188 38 0.161 88 0.646 41 0.032 42 0.083 28 0.308 46 0.343 83 0.195 56 0.406 26 0.196 52 0.019 61 0.030 41 0.021 00 1.460 41 0.025 29 0.026 331 0.0154 Analysis Re B1002 Result (pCi/g) 0.275
-0.018 0.547 0.000 1.010 0
5.640 0.253 0.029
-0.101 0
3.870 0.039
-0.260 0.077
-0.022 0.017
-0.005 0
-0.984 0.035
-0.018 0
-0.0046 B1002 Result (pCi/g) 1.710 15.400 0
8.960 423.00 300.00 2360 220.00
-0.350 0.792 25400 0.510 4.650 1.060 0.024 3.200 2.580 36.900 9.080 0.305 4
0.4280 esults 2101-CJ-FC-001 t
MDC (pCi/g) 0.931 8
1.440 5.510 0.245 0.149 0.367 0.053 0.102 1
0.507 0.137 0.444 0
1.480 0.272 2
0.064 0.059 5
0.042 4
2.680 0.037 8
0.054 6
0.0366 2101-CJ-FC-002 t
MDC (pCi/g) 1.180 0
1.510 5.860 0
0.446 0
0.762 0.661 0
0.052 0
0.935 0.562 0
4.140 13.700 7.170 7.370 0.042 0.497 0.287 0
24.000 0.682 0.388 0
0.5450
-CV 1/2-1
 
(pCi/g) 0.543 0.824 2.840 0.170 0.168 0.633 0.049 0.054 0.289 0.496 0.107 0.859 0.162 0.023 0.033 0.013 1.510 0.031 0.013 0.0066
-CV 0-1/2
 
(pCi/g) 0.846 2.310 3.640 55.200 30.200 245.000 21.100 0.567 0.373 2650 0.956 4.390 0.988 0.027 0.825 0.713 17.100 2.030 0.286 0.4200
 
La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1002101-C Result (pCi/g) 0.846 6.180 5.270 0.000 8.270 175.000 3.520
-0.041 0.165 208.000
-0.280 0.255 0.116
-0.019 0.059 0.056
-0.965 0.238 0.005 0.0018 Water Reactor Plan
-16 (continu CJ-FC-002-CV 1 MDC (pCi/g)
(p 1.120 0
1.420 1
25.300 11 0.269 0
0.114 0
0.442 18 0.047 0
0.230 0
0.522 0
0.362 21 1.580 0
1.900 0
0.864 0
0.056 0
0.064 0
0.049 0
2.970 1
0.048 0
0.060 0
0.0438 0.
r ued)
Co 1/2-1 B
R pCi/g)
(p
.716 0
.340
-0 1.400 8
.616 0
.907 8
8.300 70
.356 7
.135 0
.312 0
1.700 1
.950 0
.259 0
.205
-0
.017
-0
.046 0
.040 0
.690 1
.080 0
.028
-0 0179 0.
2-59 oncrete Cor B1002101-CJ-FC Result MD pCi/g)
(pCi/
0.836 0.96 0.405 1.44 8.430 17.0 0.000 0.33 8.570 0.14 0.600 0.54 7.000 0.05 0.038 0.21 0.062 0.54 1240 0.81 0.176 2.60 0.090 2.32 0.004 1.71 0.011 0.04 0.105 0.05 0.126 0.03
.500 2.56 0.339 0.04 0.001 0.03
.0175 0.01 re Isotopic A C-003-CV 0-1/2 DC
 
/g)
(pCi/g) 62 0.624 40 0.803 000 8.210 34 0.484 48 0.940 48 7.370 50 0.691 11 0.060 43 0.318 17 129.000 00 0.514 20 0.202 10 1.030 44 0.009 56 0.051 39 0.051 60 1.640 44 0.099 37 0.012 75 0.0203 Analysis Re 0
3 esults
 
La Cross License T Revision se Boiling W Termination n 0 Tab Water Reactor Plan ble 2-17 198 We Radion Mn-Co-Co-Nb-Cs-1 Ce-1 r
83 Groundw ell-Point So nuclide
-54
-57
-60
-95 137 141 2-60 water Analy outh of Turb A
(p ysis from Te bine Buildin Activity pCi/L) 63.4 6.4 508 21.4 21.7 18.9 emporary ng
 
L L
R La Crosse Boilin License Termin Revision 0 Jun H-3 Co-6 Sr-9 Cs-1 a
B Nov H-3 Co-6 Sr-9 Cs-1 a
B ng Water React ation Plan e 2013 MW-20 (pCi/L 572 60 4.00 90 2.05 137 3.97 Bold values indi vember 2013 MW-20 (pCi/L 235 60 4.64 90 1.18 137 4.64 Bold values indi or Table 2 01-A MW-201-B L)
(pCi/L) 2 506 0
5.01 5
2.00 7
3.84 icate concentrati 01-A MW-201-B L)
(pCi/L) 5 150 4
3.80 8
3.73 4
1.90 icate concentrati 2-18 2013 Gr B
MW-202-A (pCi/L) 660 4.76 1.82 4.05 ion greater than B
MW-202-A (pCi/L) 257 5.26 1.18 6.54 ion greater than 2-61 roundwater M MW-202-B MW (pCi/L)
(p 484 4.51 1.43 3.91 n MDC. Italicize MW-202-B MW (pCi/L)
(p 278 5.41 1.61 4.70 n MDC. Italicize onitoring Resu W-203-A MW-2 pCi/L)
(pCi N/A 42 4.95 4.1 2.06 2.0 4.52 4.3 ed values indica W-203-A MW-2 pCi/L)
(pCi 449 23 4.43 3.8 1.87 2.4 4.41 3.9 ed values indica ults 203-B MW-204-i/L)
(pCi/L) 20 397 12 4.36 06 2.18 31 4.11 ate MDC value.
203-B MW-204-i/L)
(pCi/L) 35 193 89 4.52 40 1.18 98 4.77 ate MDC value.
-A MW-204-B (pCi/L) 420 4.26 2.08 3.96
-A MW-204-B (pCi/L) 171 8.24 1.51 7.92
 
L L
R J
G A
G B
H C
F N
C N
S N
T C
E E
E P
P 2
P A
a La Crosse Boilin License Termin Revision 0 JUNE 2014 MW-DW3 Gross Alpha 1.26E-01 Gross Beta 1.48E+0 H-3 1.05E+0 C-14 2.79E+0 Fe-55
-2.00E+0 Ni-59 1.83E+0 Co-60 1.02E+0 Ni-63
-1.78E+0 Sr-90 6.09E-01 Nb-94 4.40E-01 Tc-99
-8.28E+0 Cs-137
-5.97E-0 Eu-152 9.48E+00 Eu-154
-5.24E+0 Eu-155
-2.67E+0 Pu-238 2.83E-02 Pu-239/240
-9.61E-02 Pu-241 3.51E+0 Am-241 5.39E-02 a
Bold val ng Water React ation Plan MW-DW4 M
D 1
-1.33E-01 4.44 0
3.13E+00 1.93 2
1.59E+02 1.94 0
0.00E+00
-3.9 01
-3.12E+01
-2.6 1
3.96E+01
-4.7 0
3.94E-01 2.5 00
-6.14E+00
-7.4 1
8.99E-02 8.9 1
1.43E-01
-1.2 00
-7.37E+00
-8.2 1
-3.47E-01
-7.4 0
2.34E+00
-7.4 00 3.16E+00 1.35 00 1.46E+00
-1.5 2
-4.77E-02
-2.2 2
3.36E-02 3.1 0
2.70E+00
-8.3 2
3.42E-02 4.6 lues indicate con tor MW-DW5 MW-DW7 4E+00
-3.78E-01 3E+00 0.00E+00 4E+02 1.23E+02 97E+00
-5.08E+00 66E+01
-3.86E+01 75E+01 2.60E+01 0E+00
-2.42E+00 40E+00
-4.38E+00 99E-02 1.78E-02 26E+00 7.49E-01 26E+00
-9.36E+00 45E-01
-1.83E+00 43E+00
-5.51E+00 5E+00
-4.73E+00 54E-01
-1.07E+02 22E-02 8.22E-02 13E-02 4.07E-01 39E+00 2.62E+00 65E-03
-1.01E-02 ncentration grea Tabl MW-B11R MW B11A 0.00E+00 7.33E 3.59E+00
-2.70E 2.45E+02 1.61E+
9.06E+00 6.83E+
-3.19E+01
-3.75E
-4.16E+00 2.53E+
8.76E-01
-1.94E
-3.57E+00 0.00E+
7.34E-01 6.11E
-6.99E-01 1.53E+
-5.52E+00
-8.46E 1.24E+00 1.84E+
-9.93E-01 1.48E+
1.63E+00
-2.61E 1.60E+00
-4.47E 0.00E+00 4.09E
-2.54E-02
-3.39E
-5.72E+00 8.38E 1.22E-02 8.37E ater than MDC.
le 2-19 2014 W-AR MW-B2
-01
-2.13E+00 6
E-01 1.12E+01 4
+02 1.60E+02 1
+00 1.94E+00
-2 E+01
-9.20E+00
-4
+00
-7.13E+00 3
E+00
-1.39E+00
-1
+00
-7.94E+00 1
E-01 6.52E-01 6
+00 1.77E+00 6
E+00
-7.41E+00
-8
+00 1.37E+00 2
+00 1.07E-01 1
E+00 2.36E+00 1
E+00 1.60E+00
-3 E-02 5.40E-02 8
E-02 3.40E-02 1
E-01 0.00E+00 E-02 3.98E-03 2
Italicized value 2-62 Groundwater MW-B3 MW-200-A 6.46E-01 4.04E+00 4.14E+00 8.66E+00 1.94E+02 5.23E+01 2.05E+00 9.26E+00 4.39E+01 1.93E+01 3.15E+01
-2.18E+0 1.13E+00 1.01E+00 1.50E+00
-1.97E+0 6.12E-01 9.86E-01 6.65E-01 1.08E+00 8.10E+00 3.55E+00 2.14E+00 1.77E-01 1.42E+01 9.71E+00 1.69E+00 5.77E-01 3.17E+00
-3.63E+0 8.29E-02
-1.38E-02 1.46E-01 2.68E-02
-7.39E-01 0.00E+00 2.28E-02 1.72E-01 es indicate MDC Monitoring Re MW-200-B M
20 0
-2.26E-01 3.84 0
-1.79E+00 7.26 1
1.24E+02 7.03 0
4.84E+00 4.84 1
-4.16E+01
-3.20 1
3.32E+01
-1.6 0
-1.27E+00
-6.0 0
-4.69E+00 1.82 1
9.98E-01 6.86 0
8.47E-01 3.73 0
5.08E+00 3.92 1
-3.64E-01 3.10 0
-1.16E+01 4.15 1
5.60E-01
-2.39 0
-3.44E+00
-2.92 2
1.51E-02 5.33 2
-1.57E-02
-6.8 0
4.49E+00
-4.8 1
9.71E-01 9.46 C value.
esults (pCi/L)
MW-01-A MW-201-B 4E-01
-1.04E+00 6E+00
-1.04E+00 3E+01 1.05E+02 4E+00 4.51E+00 0E+01 1.58E+01 7E+01
-7.11E+01 04E-02 1.73E+00 2E+00
-1.91E+00 6E-02 1.02E+00 3E-01 1.80E+00 2E+00 1.17E+00 0E-01
-6.21E-01 5E+00 1.12E+01 9E+00
-2.43E+00 2E+00
-2.60E+00 3E-02
-5.02E-02 86E-03 2.36E-02 85E-01
-1.42E+00 6E-02 3.99E-03 MW-202-A MW 202-1.06E+00 4.07E-4.34E+00 1.49E+
3.36E+02 1.06E+
0.00E+00 4.70E+
-3.26E+00
-4.54E+
2.49E+01
-1.05E+
-8.91E-01 1.02E+
-1.94E+00
-3.73E+
1.12E+00 6.05E-
-3.55E-01 1.04E-3.88E-01 2.73E+
-4.64E-01 2.86E+
4.11E+00 1.08E+
-1.12E+00
-1.18E+
-1.59E+00
-3.49E+
-8.46E-03 1.48E-
-2.27E-02
-4.54E 2.20E+00 2.72E+
1.16E-01 3.92E-W-
B MW-203-A
-01 1.74E+00
-2
+00 2.27E+00 5
+02 2.79E+02 2
+00 4.54E+00 4
+01
-4.95E+01
-4
+01
-2.71E+01
-4
+00 3.48E-02
-9
+00
-3.70E+00
-3
-01 1.17E+00 8
-01 1.59E+00 1
+00 4.36E+00 4
+00 1.48E+00 1
+01
-9.59E-01 4
+00 1.93E+00
-3
+00
-4.91E+00 4
-01
-5.67E-02
-5
-02
-2.27E-02
-3
+00 4.07E+00 1
-02 2.94E-02 7
MW-203-B MW-204-A 2.29E-01 7.58E-01 5.53E+00 2.69E+00 2.79E+02 1.06E+02 4.55E+00 4.66E+00 4.96E+01
-4.03E+01 4.66E+00
-6.22E+00 9.55E-01 1.91E-01 3.80E+00 0.00E+00 8.23E-01 2.01E+00
.50E+00 2.26E-01 4.17E+00 6.95E+00
.39E+00
-3.04E-01 4.99E+00 2.12E+00 3.69E+00 2.36+00 4.05E+00
-4.34E-01 5.87E-02
-5.12E-02 3.95E-02
-2.49E-02
.03E+01 4.07E+00 7.64E-02 1.56E-01 MW-204-B 1.27E+00 0
2.57E-01 2
3.49E+01 0
1.30E+01 1
-3.98E+00 0
-2.47E+01
-2.31E-01 0
-1.97E+00 0
6.11E-01 1.28E+00 0
6.31E+00 1.93E+00 0
7.68E+00 6.06E-01 1.66E+00 2
-9.28E-03 2
6.28E-02 0
-1.89E+00 8.24E-02
 
L L
R S
G G
H C
F N
C N
S N
T C
E E
E P
P P
A a
La Crosse Boilin License Termin Revision 0 September 2014 M
Gross Alpha 8
Gross Beta 2
H-3 3
C-14
-9 Fe-55 9
Ni-59 3
Co-60 2
Ni-63 2
Sr-90
-1 Nb-94
-9 Tc-99
-1 Cs-137 3
Eu-152 2
Eu-154
-3 Eu-155 2
Pu-238 1
Pu-239/240 9
Pu-241 3
Am-241 1
a Bold val ng Water React ation Plan 4
MW-DW5 MW-8.47E-01 3.09E
.96E+00 1.45E
.43E+01 0.00E 9.44E-01
-2.70E 9.39E+00
-3.10E
.13E+00 1.64E
.17E+00 1.32E
.79E+00 2.48E 1.06E+00 5.90E 9.45E-01
-1.39E 1.54E+00
-4.00
.97E+00
-7.24
.48E+00 3.00E 3.31E+00
-3.93E
.69E+00 1.95E 1.71E-02 3.69E 9.28E-02 0.00E
.18E+00
-3.68E 1.28E-01 3.69E lues indicate con tor
-B11R MW-B11A E+00 2.07E-0 E+01 3.04E-0 E+00 3.44E+0 E+00 0.00E+0 E+01
-3.49E+0 E+01
-8.49E+0 E+00 1.22E+0 E+00
-4.14E-0 E-01 2.80E-0 E+00
-1.29E-0 0E-01
-1.56E+0 4E-01 9.72E-0 E+00 6.42E+0 E+00 1.10E+0 E+00 1.69E+0 E-02
-5.50E-0 E+00
-1.10E-0 E+00
-2.29E+0 E-02
-1.69E-0 ncentration grea Table 2-19 AR MW-200-A 01 2.42E-01 01 2.41E+00 01 6.86E+01 00
-4.56E-01 01
-3.35E+01 00 7.84E+00 00 3.56E+00 01 3.62E+00 01 1.14E+00 01
-1.43E+00 00
-1.57E+00 01 2.17E+01 00
-2.39E+00 00
-6.57E-01 00
-8.16E-01 03 2.65E-02 02 5.83E-02 00
-2.23E+00 02 1.10E-01 ater than MDC.
(continued)
MW-200-B 2.01E+00 9.11E+00 5.17E+01
-4.98E+00
-4.56E+01 2.37E+01 6.20E-01
-7.87E-01 5.10E-01
-2.68E-01
-1.54E+00 1.94E+00
-1.34E+01
-1.54E+00
-1.64E+00
-6.50E-03 0.00E+00 8.49E+00 2.29E-01 Italicized value 2-63 2014 Ground MW-201-A M
1.18E+00 7.36E+00 8.67E+01 2.69E+00
-2.18E+01
-1.99E+01
-7.23E-02 5.00E+00
-1.19E-01 6.56E-01
-7.94E-01
-1.09E+00 4.79E+00
-3.09E+00
-1.48E+00
-3.59E-02 0.00E+00
-6.92E-01 1.40E-01 es indicate MDC dwater Monito MW-201-B MW 1.43E+00 1.0 3.67E+00 4.8
-3.42E+01
-5.1 9.28E-01 4.94 2.77E+01
-5.4 3.09E+01
-1.1 9.50E-01 9.7 2.15E+00 8.2
-4.99E-01 6.7 6.44E-01
-6.4
-1.95E+00 7.9 1.84E+00
-4.3 2.53E+00 9.4 1.94E+00
-3.6 4.13E+00
-2.0 8.55E-02 1.1 1.41E-01 5.8
-5.85E-01 0.0 2.80E-02 6.6 C value.
oring Results (p W-202-A MW-20 4E+00
-2.10E-86E-01 2.30E+
18E+01 1.04E+
4E+00
-2.72E+
43E+01 3.37E+
18E+01
-4.46E+
72E-01 1.18E+
25E-01
-8.30E-70E-01 5.40E-48E-02
-1.02E+
97E-01
-1.95E-34E-01 2.31E+
0E+00 6.51E+
67E-01 4.18E+
08E+00
-8.41E-13E-02 3.63E-87E-02 5.25E-0E+00
-1.76E+
62E-02 9.48E-pCi/L) 02-B MW-203-A E-01 1.37E+00
+00 1.52E+00
+02
-3.44E+01
+00
-3.95E+00
+01
-4.95E+01
+01 5.30E+01
+00 3.67E+00 E-01 1.62E+00
-01 4.80E-01
+00 8.53E-02 E-01
-1.24E+00
+00 1.56E+00
+00 4.06E+00
+00
-3.33E+00 E-01
-9.54E-02
-02 7.08E-02
-02 9.15E-02
+00 5.04E-01
-02 2.51E-01 A
MW-203-B
-6.68E-01 1.00E+00 1.21E+02 0
4.89E-01 4.32E+01
-4.34E+01 1.99E+00
-1.77E+00 8.70E-01 2.16E+00 0
-3.32E+00 6.84E-01
-1.15E+00 0
-2.31E-01
-3.66E-01 8.12E-02 5.97E-02
-3.71E+00 1.03E-01 MW-204-A 6.00E-01 5.28E+00 6.88E+01 4.73E-01 3.45E+01
-3.13E+01
-3.77E-01
-1.84E-01 9.00E-01 1.18E-01
-1.96E+00
-1.14E+00
-1.92E+01
-4.95E+00
-2.02E+00
-6.45E-04
-5.48E-03
-3.97E+00 1.06E-01 MW-204-B 3.53E+00 0.00E+00
-1.21E+02 9.46E-01
-9.25E+01
-1.87E+01 2.05E+00 3.94E-01 2.30E-01
-1.88E+00 3.89E-01 1.24E+00 2.23E+00 2.36E+00 9.46E-01
-3.26E-02 7.02E-02
-6.46E+00 2.69E-01
 
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan Figure or e 2-1 LACBWR Site Map -
2-64
- Open Land Survey Units annd Classificatioon
 
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-2 LACBWR 2-65 Site Map - Buildings Identifiication
 
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-3 r
LACBWR 2-66 R Site Drainnage and Seewer Map
 
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-4 r
LACBWR 2-67 R LCE Excllusion Area (Class 1)
 
La Cross License T Revision se Boiling W Termination n 0 Figu Water Reactor Plan ure 2-5 N
r Non Impacte 2-68 ed Open Laand Samplinng Locations
 
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-6 r
Class 1 O 2-69 Open Land SSampling LLocations
 
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-7 r
Class 2 O 2-70 Open Land SSampling LLocations
 
La Cross License T Revision se Boiling W Termination n 0 F
Water Reactor Plan Figure 2-8 r
Class 3 O 2-71 Open Land SSampling LLocations
 
La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan Figure 2-9 r
9 Concre 2-72 ete Core Sam mpling Loccations
 
La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r
inued) 2-73 Concrete CCore Sampliing Locationns
 
La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r
inued) 2-74 Concrete CCore Sampliing Locationns
 
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-10 LACBWR Si 2-75 ite - Typical Geological Crosss-Section
 
L L
R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-111 Groundwat 2-76 ter Sampling Wells - LACBW WR Site}}

Latest revision as of 21:52, 9 January 2025

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
References
Download: ML16200A086 (83)


Text

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

La Cross License T Revision 2.

Site 2.1.

2.1.

2.1.

2 2

2 2

2 2.1.

2.1.4 2

2 2.1.

2.1.

2 2

2 2

2 2

2 2

2.2.

2.2.

2.2.

2 2

2 2

2.2.

2 2

2.2.4 2.2.

2.3.

2.3.

2.3.

2.3.

2.3.4 2

2 se Boiling W Termination n 0 Characteriz Historical S 1.

Objecti 2.

Method

.1.2.1. Pre

.1.2.2. Doc

.1.2.3. Lic

.1.2.4. Per

.1.2.5. Pro 3.

Operati 4.

Inciden

.1.4.1. Rad

.1.4.2. Che 5.

Finding 6.

Initial S

.1.6.1. Sur

.1.6.2. Sur

.1.6.3. Cla

.1.6.4. Cla

.1.6.5. Cla

.1.6.6. Non

.1.6.7. Cla

.1.6.8. Cla Characteriz 1.

Data Q 2.

Survey

.2.2.1. Num

.2.2.2. Det

.2.2.3. Sca

.2.2.4. Typ 3.

Instrum Concen

.2.3.1. Cal

.2.3.2. Inst 4.

Labora 5.

Quality Summary o 1.

Backgr 2.

Potenti 3.

Non-Im 4.

Impact

.3.4.1. Cla

.3.4.2. Cla Water Reactor Plan zation..........

Site Assessm ives............

dology........

liminary Cla cument Revi enses, Perm rsonnel Inter operty Inspec ional History nts...............

diological Sp emical Spills gs and Conc Survey Area rvey Areas..

rvey Units...

ass 1 Open L ass 2 Open L ass 3 Open L n-Impacted O ass 1 Structur ass 2 and 3 S ation Appro Quality Objec y Design......

mber of Stat termination o an Coverage pes of Measu mentation Se ntrations (M libration......

trument Use atory Instrum y Assurance f Characteri round Study ial Radionuc mpacted Ope ed Open Lan ass 1 Open L ass 2 Open L r

TABLE O ment..............

assification..

iew..............

mits and Auth rviews..........

ctions...........

y..................

pills.............

s..................

lusions........

as/Units and Land Areas...

Land Areas...

Land Areas...

Open Land A res...............

Structures.....

ach..............

ctives...........

tic Measurem of Static Me urements and lection, Use MDCs)..........

e and Contro ment Method zation Surve clides of Con en Land Area nd Areas.....

Land Areas...

Land Areas...

2-i OF CONTE horizations...

Classificatio Areas..........

ments and/or easurement a d Samples...

and Minimu l..................

ds and Sensit ey Results...

ncern............

as................

ENTS on................

r Samples....

and Sample L um Detectab tivities.........

Locations....

ble

... 2-1

... 2-2

... 2-2

... 2-3

... 2-3

... 2-4

... 2-5

... 2-5

... 2-5

... 2-6

... 2-6

... 2-7

... 2-8

... 2-8

... 2-9

... 2-9

... 2-9

. 2-10

. 2-10

. 2-10

. 2-11

. 2-11

. 2-12

. 2-12

. 2-14

. 2-14

. 2-15

. 2-16

. 2-16

. 2-16

. 2-18

. 2-18

. 2-19

. 2-19

. 2-19

. 2-20

. 2-21

. 2-22

. 2-22

. 2-24

. 2-25

. 2-26

La Cross License T Revision 2

2.3.

2.3.

2 2

2 2.3.

2 2

2 2

2 2.4.

2.5.

se Boiling W Termination n 0

.3.4.3. Cla 5.

Non-Im 6.

Impact

.3.6.1. Bas

.3.6.2. Tur

.3.6.3. LA 7.

Surface

.3.7.1. Are

.3.7.2. Gro

.3.7.3. Pre

.3.7.4. On-

.3.7.5. Sum Continuing References Water Reactor Plan ass 3 Open L mpacted Stru ed Structure sement Struc rbine Buildin ACBWR Adm e and Groun ea Groundwa oundwater F vious Invest

-Going Inve mmary of Gr Characteriza r

Land Areas...

uctures.........

es and System ctures Below ng Tunnel....

ministration dwater........

ater Use......

low.............

tigations......

stigations....

roundwater A ation...........

2-ii ms...............

w 636 foot El Building.....

Analytical R levation......

Results.........

. 2-27

. 2-29

. 2-30

. 2-30

. 2-31

. 2-31

. 2-32

. 2-32

. 2-33

. 2-34

. 2-35

. 2-35

. 2-36

. 2-37

La Cross License T Revision Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-se Boiling W Termination n 0 1

LACBW 2

LACBW 3

Instrum 4

Off-Sit 5

2005 D 6

Investig 7

Initial S 8

Non-Im Survey 9

Non Im Labora 10 Impact Summa 11 Class 1 Labora 12 Impact Survey 13 Class 2 Labora 14 Impact Survey 15 Class 3 Labora 16 Concre 17 1983 G Buildin 18 2013 G 19 2014 G

-1 LACBW

-2 LACBW

-3 LACBW

-4 LACBW

-5 Non Im

-6 Class 1

-7 Class 2

-8 Class 3

-9 Concre

-10 LACB

-11 Ground Water Reactor Plan WR Open L WR Structur ment Types a te Laboratory Dairyland Ba gative Level Suite of LAC mpacted Ope y Summary.

mpacted Coa atory Analys ed Class 1 O ary.............

Concrete, A atory Analys ed Class 2 O y Summary.

2 Asphalt, Se atory Analys ed Class 3 O y Summary.

3 Asphalt, Se atory Analys ete Core Isot Groundwater ng...............

Groundwater Groundwater WR Site Ma WR Site Ma WR Site Dra WR LCE Ex mpacted Ope Open Land 2 Open Land 3 Open Land ete Core Sam WR Site - T dwater Samp r

LIST and Survey ral Survey U and Nominal y Analytical ackground St ls for Cs-137 CBWR Site-en Land Surv l Pile and So sis (pCi/g)....

Open Land S Asphalt, Sed sis (pCi/g)....

Open Land S ediment and sis................

Open Land S ediment and sis (pCi/g)....

opic Analys Analysis fro Monitoring Monitoring LIST O ap - Open La ap - Building ainage and S xclusion Are en Land Sam d Sampling L d Sampling L d Sampling L mpling Locat Typical Geolo pling Wells -

2-iii OF TABLE Units...........

Units.............

l MDCs.......

l Methods an tudy for Soil 7 Based on B

-Specific Ra vey Units - C oil Samples -

Survey Units diment and S Survey Units Soil Sample Survey Units Soil Sample is Results....

om Tempora Results......

Results (pC OF FIGURE and Survey U gs Identifica Sewer Map..

ea (Class 1)..

mpling Locati Locations.....

Locations.....

Locations.....

tions............

ogical Cross

- LACBWR ES nd Typical M ls.................

Background

dionuclides.

Characteriza

- Test Amer

- Character Soil Samples

- Character es - Test Am

- Character es - Test Am ary Well-Po Ci/L)............

RES Units and Cl ation.............

ions.............

s-Section.....

R Site...........

MDCs..........

Studies.......

ation rica rization Surv

- Test Ame rization merica rization merica oint South of lassification vey erica f Turbine

. 2-39

. 2-40

. 2-42

. 2-43

. 2-44

. 2-45

. 2-46

. 2-47

. 2-49

. 2-50

. 2-51

. 2-52

. 2-53

. 2-54

. 2-55

. 2-56

. 2-60

. 2-61

. 2-62

. 2-64

. 2-65

. 2-66

. 2-67

. 2-68

. 2-69

. 2-70

. 2-71

. 2-72

. 2-75

. 2-76

La Cross License T Revision AEC ALARA bgs CRD DCGL DQO EPA FCP FESW FRS FSS G-1 G-3 HSA HTD IR ISFSI LACBW LER LSA LSE LTP MARLA MARSA MARSSI MDC MDCR MWe NIST se Boiling W Termination n 0 United As Lo Below Contr Deriv Data Q United Force Fuel E Final Final Genoa Genoa Histor Hard-Incide Indep WR La Cr Licen Low S LACB Licen AP Multi-AME Multi-Manu IM Multi-Minim Minim Megaw Nation Water Reactor Plan LIST OF d States Ato ow As Reaso w Ground Su ol Rod Driv ed Concentr Quality Obje d States Env d Circulation Element Stor Radiation Su Status Surve a 1 Coal/Oil a 3 Fossil St rical Site As to-Detect ent Reports endent Spen rosse Boiling see Event R Specific Act BWR Site En se Terminati

-Agency Rad

-Agency Rad ual

-Agency Rad mal Detectab mum Detecta watt Electric nal Institute r

ACRONYM mic Energy onably Achie urface e

ration Guide ective vironmental P n Pump rage Well urvey ey Station tation sessment nt Fuel Stora g Water Reac eports ivity nclosure ion Plan diological L diation Surv diation Surv ble Concentr able Count R c

of Standard 2-iv MS AND AB Commission evable line Levels Protection A age Installatio ctor Laboratory A vey and Asse vey and Site rations Rate ds and Techn BBREVIAT n

Agency on Analytical Pro essment of M Investigatio nology TIONS otocols Man Materials and n Manual nual d Equipmentt

La Cross License T Revision NRC ORC PSDAR QA QAPP QC RCA REMP ROC RPV SRC STS TSD WDNR WGTV WTB ZNPS se Boiling W Termination n 0 United Opera Post-S Qualit Qualit Qualit Radio Radio Radio React Safety Sourc Techn Wisco Waste Waste Zion N Water Reactor Plan d States Nuc ational Revie Shutdown D ty Assurance ty Assurance ty Control ologically Co oactive Efflu onuclides of or Pressure V y Review Co e Term Surv nical Suppor onsin Depart e Gas Tank V e Treatment Nuclear Pow r

clear Regula ew Committ ecommissio e

e Project Pla ontrolled Are ent Monitor Concern Vessel ommittee vey rt Document tment of Nat Vault Building wer Station 2-v atory Commi ee ning Activit an ea ing Reports tural Resour ission ties Report rces

La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan r

Page Intent 2-vi tionally Leftft Blank

La Cross License T Revision

2.

S In accor Regulato Nuclear character The purp conducte remain.

License T of compl Survey (

1575, Mu Source T terminati The site quantify character site that classifica The cha NUREG-Decomm

Criteria, PG-EO-3 Reactor Characte the Data informati remediat at concen removed The deco waste of LACBW None of radiologi planned a G-3 pow minor str The majo basement se Boiling W Termination n 0 Site Chara rdance with ory Guide 1.

Power Re rization perfo pose of site ed in all are The term F Termination liance survey FSS) for op ulti-Agency Term Surve ion. See LTP characteriz the extent a rization surv will require ation and vol aracterization

-1575 (MA issioning G Final Repor 313196-SV-P (4), and GP erization Pro Quality Obj ion obtained ion planning ntrations gre and properl ommissionin f all LACB WR Administ f the buildin ically impac and these str wer operation ructures will or sub-grade ts of the Re Water Reactor Plan acterization h the requi

.179, Standa eactors (1),

formed at the characteriza eas where co Final Radiat n Plan (LTP) ys that will b pen land are Radiation S ey (STS) fo P Chapter 5 ation incorp and nature o veys and ana remediation lumes, and e n survey w ARSSIM)

Guidance - C rt, (3). In ad PL-001, Ch P-EO-31319 oject (QAPP jective (DQO d from the

g. Materials eater than th ly packaged ng approach BWR buildi tration build ngs and stru cted such th ructures, inc ns. The pub l also remain e structures t eactor Buildi r

n rements of ard Format

, this chap e La Crosse B ation is to en ontamination tion Survey

) in order to be performed eas and buri Survey and S or below gr for a descrip porates the r of contamin alyses have b n, as well as estimate cost was designed and NURE Characteriza ddition, surv haracterizatio 96-QA-PL-00 P) (5) which O) process, a characteriz which were he unrestricte for shipmen for LACBW ings, structu ding and Cri uctures asso hat they requ cluding the G blic roads an

n.

that will be ing, Waste T 2-1 f 10 CFR 50 and Conte pter provide Boiling Wat nsure that th n existed, re is from 10 acknowledg d at LACBW ed piping b Site Investig round struct ption of the results of in ation at LA been and con s to plan rem ts.

d and exec EG-1757, ation, Surve veys were de on Survey P 01, Quality describes p and measure zation provi e shown to b ed release cr nt and dispos WR requires ures and co ib House) to ociated with uire remedi G-3 Crib Hou nd railways backfilled a Treatment B 0.82 (a)(9)(ii ents for Lic es a descr ter Reactor (

he Final Rad emains, or h 0 CFR 50.82 ge the distin WR. These ased on gui gation Manu tures to be FRS.

nvestigation ACBWR. In ntinue to be mediation m cuted using Volume 2, ey, and De esigned and Plan for th Assurance policy, organ es necessary des guidanc be contamina riteria have sal.

the demolit omponents o a depth of h the Genoa al actions; use, will rem that travers and remain a Building (W i)(A) and t ense Termin ription of (LACBWR) diation Surv has the pote (9)(ii)(D) an nction betwe surveys are; idance provi al (MARSS backfilled ns and surve n addition, th e used to ide methodologie the guidan Revision 1 termination executed in e La Cross Project Pla nization, fun to achieve q ce for deco ated with rad been and wi tion, remova (with the e f at least 3 f a 3 Fossil S therefore, n main intact a se the site a at license ter WTB), Waste the guidanc nation Plan the radiolo site.

ey (FRS) w ential to exi nd is used in een the two

1) a Final S ided in NUR SIM) (2) and prior to lic eys conduct he results o ntify areas o es, develop w nce provide 1,

Consolid of Radiolo n accordance se Boiling W an LACBWR nctional activ quality data.

ontamination dioactive ma ill continue al and dispos exception o feet below g Station (G-3 no remediati and function as well as se rmination ar Gas Tank V ce of ns for ogical will be ist or n this types Status REG-d 2) a cense ed to of site of the waste ed in dated ogical e with Water R Site

vities, The n and aterial to be sal as f the grade.
3) are ion is al for everal re the Vault

La Cross License T Revision (WGTV)

(3 feet b Reactor/G sump and In the R removed removed elevation WTB, th concrete the rema cap and p following covered b remainin LTP Cha Independ shown in 2.1.

H In accor Assessm informati

reports, marine f Environm compiled 2.1.1. O The HSA LACBW surround resulted Radiolog subsurfac the 1.5 a informati may also The scop hazardou The obje Id b

se Boiling W Termination n 0

) and the re elow grade)

Generator P d the Turbin Reactor Bui

. All intern

, leaving on n (i.e., concr he only porti footers belo ining structu piles below t g the termina by at least 3 ng backfilled apter 1, sec dent Spent F n Figure 2-1)

Historical Si rdance with ent (HSA) ion, includin pre-operatio fauna and s mental Repo d for this inv Objectives A was a d WR activities dings. The in contamin gically Contr ce soils outs acre fenced ion compile o be used as pe of the us materials.

ctives of the dentify pote ased on exis Water Reactor Plan emainder of

). These re Plant, the on e pit.

lding, all in nal concrete nly the rema rete bowl on of the str ow the 636 fo ure will cons the 636 foot ation of the l feet of soil d structures to ction 1.3.1 d Fuel Storage

) is excluded te Assessme h the guida (6) was p ng any 10 C onal survey sediment su orts to the vestigation.

detailed inve related to r HSA focuse nation of pla rolled Area (

ide of the R LACBWR d by the HS input into th HSA inclu e HSA were ntial, likely sting or deriv r

f the baseme maining stru ne foot thick nternal stru will be rem aining struct below 636 ructure that oot elevation sist of the fl elevation. T license are c and physica o be plausibl describes th Installation d from the sc ent ance provid performed a CFR 50.75(g data, spill urveys), ope Nuclear Re estigation to radioactive m ed on histor ant systems, (RCA). It al RCA but with Site Enclos SA was used he developm ded potenti to:

, or known ved informat 2-2 ent structure uctures inclu k portion of uctural surfa moved to ex tural concre foot elevatio will remain

n. In the WG loors and fou The structur constructed o ally altered t ly occupied.

e site licen (ISFSI) Fac cope of the L ded in MAR and docume g) files, emp reports, spe rational sur egulatory C o collect ex materials or rical events

, buildings, lso addresse hin the owne sure (LSE) d to establis ment of reme ial contamin sources of

tion, es located b lude the Pip f the Chimn aces, system xpose the ste ete outside t on, concrete is the 630 a GTV and the undation wa ral surfaces t of steel reinf to a conditio nse boundary cility as loca LTP.

RSSIM, sec ented in Au ployee inter ecial survey rvey records Commission xisting info other conta and routin surface and d support str er controlled area share sh initial sur ediation plan nation from radioactive below the 63 ping and Ve ney Foundat ms and com eel liner, wh the liner be e pile cap an and 635 foot e other rema alls as well a that will rem forced concr on which wo

y. The fen ated in Lot 7 ction 3.0, a ugust of 19 rviews, radi ys (e.g., site s, and Ann (NRC) wer ormation (fr aminants) fo ne operationa d subsurface ructures, ope d area. The e the same rvey units.

ns and the de m radioactiv and chemi 36 foot elev entilation Tu tion, the Tu mponents wi hich will als low the 636 nd piles.) I t floor, sump aining basem as concrete p main at LACB rete which w ould not allow nced area o 7 of the site a Historical 999. Histo ological inc e aerial sur nual Radiolo re reviewed rom the sta or the site an al processes e soils withi en land area current RCA boundary.

This inform esign of the ve materials cal contami vation

unnel, urbine ill be so be 6 foot In the p and
ments, piling BWR will be w the of the e (and Site orical cident
rveys, ogical d and art of nd its s that in the as and A and The mation FRS.

s and inants

La Cross License T Revision D

n P

P P

P M

D 2.1.2. M The obje may have land area failures r material.

contamin decontam their pote Each inc was furth

analysis, sampling location.

Relevant remediat Also incl R

P p

S id Informat data, eva Units.

2.1.2.1.

The HSA classifica have a p se Boiling W Termination n 0 Distinguish p o threat to h rovide an as rovide infor rovide an in rovide a gra MARSSIM g Delineate init Methodology ective of the e significant as and struct resulting in Dependin nation varies mination acti ential for con ident identif her investiga any remed g, survey, an Historical r t informatio ion phases o luded in the Relevant exce ersonnel int lant personn ite inspectio dentify, locat ion from thi aluation of r Prelim A investiga ation of the potential for Water Reactor Plan portions of th uman health ssessment of rmation usefu nitial classific aded initial c guidance, and tial survey u y

HSA record tly impacted tures. These airborne rel ng upon pa s by area. In ivities and F ntamination.

fied that pos ated. This in dial actions nd analysis i records prov on that bec of the license research ass erpts from w terviews, inc nel to confir on, utilizing te, confirm, is research w results, docu minary Class ation was d site land are contaminati r

he site that m h,

f the likeliho ful to subsequ cation of are lassification d

unit boundari ds search and d the hazardo e included sy eases, liquid ast site ope n order to fac RS planning sed a realisti nvestigation taken to m in an attemp vided the sou comes avail e termination sociated with written report cluding the u rm documen g historic si and docume was used in umentation o sification designed to eas and struc ion (based o 2-3 may need fur od of contam uent continu eas and struc n for impacte ies and areas d interview ous material ystem, struc d spills or re erations and cilitate effec g, land areas ic potential t n focused on mitigate the s pt to identify urce of a vast lable during n plan will b h the develop ts and corres use of quest nted incident te drawings ent areas of c the HSA de of findings, o obtain su ctures as imp on historical rther action minant migra uing characte ctures as non ed soils and s s based upon process was l or radiolog cture, or area eleases, or t d processes, ctive charact s and structu to impact th n the scope o situation, an fy the as le t majority of g any addi be evaluated.

pment of the spondences, tionnaires, o ts and ident s, photograp concern.

evelopment, and the ide ufficient info pacted or no l data) or co from those

ation, erization sur n-impacted o structures in n the initial c s to identify gical status o a contamina the loss of c

, the poten terization, an ures are class he characteri of contamina nd any post eft conditio f the docume itional char e HSA were:

of current, fo tify undocum phs, prints, including th entification formation to on-impacted ontain know that pose lit

rveys, or impacted, n accordance classification those event of LACBWR ation from sy control over ntial for res nd to guide f sified based ization of th ant sampling t-remedial a n of the inc ents inspecte racterization ormer and re mented incid and diagram he compilati of initial Su o provide i

. Impacted wn contamin ttle or e with

n.

s that R site ystem solid sidual future upon e site g and action cident ed.

n and etired

dents, ms to on of urvey initial areas nation

La Cross License T Revision (based o through k is no rea impacted controlle If a land area clas was mad Initial cl historical initial cla at the tim prepared FRS desi classifica continuin surveillan classifica of comm 2.1.2.2.

Records source of for LACB include:

O S

L S

O A

E R

D H

S R

se Boiling W Termination n 0 on past or p knowledge o asonable po d from a ra d areas were area or struc ssification (e e based upon lassification l radiologica assification a me of identifi

. Final clas ign. The ch ations indica ng characteri nce, and an ations (for ex mencement of Docum maintained f documenta BWR, many Operational R afety Review Licensee Eve ite Initiated Operator Log Annual Envir Environmenta Regulatory ac Documentatio Health Physic ite inspectio Radiological Water Reactor Plan preliminary of site history ssibility for adiological p e also docum cture was cla e.g. Class 1, n the inform of LACBW al survey dat and (2) final ication of the ssification is haracterizatio ated in the H ization surve ny other ap xample, from f the FRS.

ment Review to satisfy t ation for the y record type Review Com w Committe ent Reports (

Incident Rep gs including ronmental M al investigat ctions conce on from inte cs surveys an on and survei and environ r

radiological y or previou residual ra perspective.

mented.

assified as im Class 2 or C mation obtain WR areas w ta. Classify l classificati e survey are s performed on data was HSA as descr eys, operatio pplicable sur m Class 3 to w

the requirem e HSA recor es were eval mmittee (ORC ee (SRC) Me LER) Summ ports (IR),

Reactor Ope Monitoring R tions perform erning the sit rviews cond nd sampling illance type nmental surv 2-4 l surveillanc us survey inf adioactive co Potential mpacted, the Class 3) in a ned.

was based o ying a survey ion. Initial c a using the i and verified used to val ribed in this onal surveys rvey data m o Class 2 and ments of 10 rds review p luated. A su C) Meeting M eeting Minut

maries, erator and H
Reports, med by indep te, ducted with r g results asso documents a ey documen ce). Non-im formation an ontamination chemical h en a determi accordance w on historica y area has a classification information d as a DQO lidate or upd Chapter. R s in support may cause d from Clas CFR Part 50 process. Dur ummary of t
Minutes, tes, Health Physic pendent entit retired/separ ociated with associated w
nts, mpacted are nd are those a
n. Areas w hazards incid ination of the with MARS al informatio minimum o n of most ar available wh O during cha date, as nece Radiological of decommi an increase ss 2 to Class 0.75(g)(1) p ring the con the types of cs entries,
ties, rated site per identified ev with identifie eas are iden areas where were classifie dents on ow e initial imp SSIM, sectio on and avai of two stage reas is perfo hen the HSA aracterization essary, the i survey data issioning, ro e in survey s 1) until the provided a m nduct of the records revi
rsonnel, vents, ed events, ntified there ed as wner-pacted on 2.2 ilable s: (1) ormed A was n and initial from outine area e time major HSA iewed

La Cross License T Revision Q

2.1.2.3.

LACBW permits.

allowed D the site, activities Several g licensing U

U U

W L

From Au This peri 1987, and 2.1.2.4.

Interview about the The pers the partic personne terms be site know Between individua standardi site perso the perso memorie operation 2.1.2.5.

Several Several s se Boiling W Termination n 0 Quality Contr Licen WR was opera The NRC Dairyland P to support o

s.

government g, constructio United States United States United States Wisconsin De Local/County ugust 28, 197 iod includes d ISFSI cons Person ws with curre e site and to onnel interv cipants as w el were chos ing investig wledge and e 2010 and als contacte ized personn onnel who w onnel observ s of other q nal period ex Prope on-site prop site events of Water Reactor Plan rol (QC) /Qu ses, Permits ated in accor Operating L ower Coope operations du and regulato on, operation s Atomic Ene s Nuclear Re s Environmen epartment of y Governmen 73 to the pre s power ope struction and nnel Intervie ent or previo verify or cl views includ well as indivi sen due to th ated for the experience th 2011, appr ed as part nel survey w worked at th vations docum questionnaire xperience, or rty Inspectio perty inspec f interest we r

uality Assura and Author rdance with License for erative (Dair uring its ope ory agencies ns, and decom ergy Commi egulatory Co ntal Protecti f Natural Re nts.

esent, the fac erations to 1 d spent fuel ews ous employe arify inform ded a combin idual and gro heir knowled assessment.

hat ranged fr roximately 4 of the HS which was c e LACBWR mented on th e completers r by docume ons ctions were ere identified 2-5 ance (QA) fi izations several Fed LACBWR a ryland) to us erating lifeti have provid mmissioning ission (AEC ommission (N ion Agency (

esources (WD cility has bee 1987, perma off-load whi ees were per mation gather nation of qu oup interview dge of and a

. A number rom the site c 40 recollecti SA question completed v R during its o he questionn s, current on ntation disco made over d which were finding type d deral and Sta and support se any quant ime, and to ded oversigh

g. These age C),

NRC),

(EPA),

DNR),

en operated u anent shutdo ich was com rformed to c red from the uestionnaires ws with sev association r of the pers construction ions of inte nnaire progr voluntarily b operational naire were c n-site worki overed durin r the course e subsequent documents.

ate of Wisco ting Technic tity of radioa implement d ht at LACBW encies includ under NRC own for dec mpleted in 20 collect first-h e records tha s completed veral of the p with the sys sonnel interv n period to sh erest were l ram. This by retired/sep years. With corroborated ing staff tha ng the record e of the HS tly documen onsin license cal Specifica active mater decommissio WR during s de:

License DPR commissionin 012.

hand inform at were revie by a majori participants.

stems and so viewed poss hutdown.

logged from consisted parated staf h few except d either by lo at had LACB ds search.

SA developm nted in the H es and ations rial at oning

siting, R-45.

ng in mation ewed.

ity of Key ource essed m the of a ff and

tions, ogged BWR ment.

HSA.

La Cross License T Revision 2.1.3. O LACBW Dairylan Mississip bordered Mississip LSE com served as confirme road on t th fo an 1

th a

li The plan Chalmers provided LACBW 19 years defueling Operatin No. 56, d 333 irrad into five Limited d ongoing shipped internals Building removed undergro Condens Water Sy Building 2.1.4. In Based on notificati se Boiling W Termination n 0 Operational WR was a 5

d. This sing ppi River so d on the no ppi River an mprising app s the RCA b ed to be suit the south sid he land north ormer Genoa n operationa 75 feet from he fenced ISF small parce icensed site.

nt was one s Company d them with a WR achieved until it was g was compl g License D dated Augus diated fuel as (5) dry cask dismantleme at LACBW for disposal intact, and 2

, and shippe

, including t ound gas sto ate Storage ystem pump ncidents n the review ions, occurre Water Reactor Plan History 50 Megawatt gle unit, also outh of the orth by the nd Highway proximately boundary du table for unr de of the plan h of the LA a Station #1 al 350 MWe m the LSE, FSI facility t l of land to t of a series was the ori a provisional d initial criti s permanent leted on June DPR-45, pur st 4, 1987; a ssemblies, w ks and transfe ent of shutdo WR since 199 l in June 20 29 control ro ed for dispo the spent fue orage tanks)

Tank and s, heat exch w of existin ence reports r

t Electric (

o known as G Village of Mississippi

35. The lic 1.5 acres of uring operat restricted us nt. Other pro ACBWR plan (G-1) coal (

fossil gener that is locate the east of H of demonst iginal licens l operating l icality on Ju tly shut dow e 11, 1987.

rsuant to 10 and a posses which were i ferred to the own and unu

94. Waste s 007. The R ods in place osal in June el storage rac

); Condensa condenser);

angers, pipin g plant reco s, and questi 2-6 (MWe) Boil Genoa Statio f Genoa, Ve i River and ensed site c the licensed tions. Mate e before rel ominent feat nt, including (and later oil rating station ed directly so Highway 35, tration plant see; the AEC icense.

uly 11, 1967 wn by Dairy The Dairyla 0 CFR 50, w ss but not-op in Fuel Elem sites ISFSI used systems stored in the Reactor Pres was filled w e 2007. Oth cks, Gaseou ate system Turbine an ng and comp ords (e.g. an ionnaires), i ling Water on #2, is loc ernon Coun d a narrow omprises a t d site. The erial leaving ease. The s tures on the g the site sw l) fueled pow n (G-3) loca outh of G-3, across from ts funded in C later sold 7, and was yland on Ap and authority was terminat perate status ment Storage by Septemb s and waste e FESW and sure Vessel with concret her systems us Waste Dis and Feedwa nd Generato ponents that nnual and s incidents wi Reactor th cated on the nty, Wiscons strip of la total of 163 LSE bounda g the LSE w site is acces site include:

witchyard an wer plant (re ated south an

, and m LACBWR n part by A d the plant t operated fo pril 30, 198 y to operate ated by Lice s was grante e Well (FES ber 2012.

disposal op d other Clas (RPV) wit te, removed and compo sposal System ater system or; and Com t were locate semi-annual ith radiologi hat is owne east shore o sin. The s and between

.5 acres, wit ary is fenced was surveyed sed by an a nd the site o moved in 19 nd approxim that is part o AEC. The A to Dairyland or approxim

7. Final re LACBWR u ense Amend ed by NRC.

SW), were p erations has ss B/C waste th head insta from the Re onents have m (except fo m (except fo mponent Co ed in the Tu reports, lice ical or hazar ed by of the ite is n the th the d and d and access of the 989),

mately of the Allis-d and mately eactor under dment The placed been e was

alled, eactor been or the or the ooling urbine ensee rdous

La Cross License T Revision material placing t the LSE the struct LSE, wh Special Monitori reports c shutdown around th posing a of LACB contamin 2.1.4.1.

The hist involving potential chronolo T

fl In W

In su In d

st O

th 8

O th 8

O ap In O

in se Boiling W Termination n 0 implication the reactor in and, while c tures and so ich is alread emphasis w ing Reports covering the n in 1987.

he plant site significant p BWR site nation from s Radio torical revie g system lea to affect th gical order a The stainless loor. Inciden ncidents inv Water Discha n 1970, pot uppression o n

Septemb econtaminat team cleanin On Novembe he potential 0-84 Inciden On Novembe he Turbine B 7, ORC-80-9 On Decemb pproximately ncident Repo On December nto the Turbi Water Reactor Plan ns occurred n a SAFSTO contributing ils directly r dy known to was placed o (REMP), fo e periods o Available sa e were also probability o land areas system failur ological Spill ew indicated akages, radio e classificati as follows; steel liner nts involving olving leaka arge line wer tentially con on the license

ber, 1977, tion of a Fo ng tank in the er 5, 1980, p for leakage nt Report, OR er 24, 1980, Building. (D 97, LER 80-ber 6, 1980 y 1/2 gallon ort, ORC-80 r 15, 1980, t ine Building r

between th OR conditio to the radiol related to the be impacte on obtainin focusing on of SAFSTOR ampling resu reviewed. T of impacting and structu res resulting ls d that betwe ological spill ion of LACB in the FESW g leakage of age from the re noted from ntaminated ed site roads removable orced Circul e Reactor Bu artial blocka of drain wa RC-80-71, O residual rad DPC-80-93 I

-12)

, the Turb of waste w 0-71, ORC-8 the Turbine g Basement T 2-7 he commenc n in 1987.

logical conta e operation o ed.

g and revie gaseous an R and deco ults associat The objectiv g the radiolo ures. Thes g in airborne een 1967 a ls, and/or rad BWR structu W had a his f the FESW w e resin regen m 1967 to 19 Control Rod

s.

e alpha c

ation Pump uilding 701 f age of drain ater into the ORC-80-75, dioactive con Incident Rep bine Build water to the 0-75, ORC-Building Wa Tunnel. (DP cement of p All of these amination an of the reacto ewing the a nd liquid rel ommissionin ted with soi ve was the i ogical status se included releases, liq and 1987, th dioactive liq ures or soils story of leak were noted f neration was 973.

d Drive (C contaminatio (FCP) duri foot elevatio lines under soil under th ORC-80-87 ntamination port, ORC-8 ding Waste Turbine Bu 80-87, ORC aste Water T PC-80-106 In plant operati e incidents t nd potential or, were con annual Radi leases since ng activities il and groun identification or hazardou system, st quid spills or here were s quid effluent

s. The incid kage to the R from 1967 to ste system t CRD) oil wa on was d

ing mainten on. (ORC, 0 Turbine Bu he Turbine B 7, ORC-80-9 n was detect 80-71, ORC-Water T uilding floor C-80-97)

Tank overflo ncident Repo ion in 1967 took place w contaminati ntained withi ioactive Eff 1967, inclu s after the ndwater with n of those e us material s tructure, or r releases.

several inci releases wit dents are list Reactor Bui o 2012.

to the Circul as used for detected d

ance involv 09/27/77) uilding result Building. (D

97) ed in soils u 75, ORC Tank overfl
r. (DPC-80 owed waste w ort) 7 and within ion of in the fluent uding plant hin or events status area idents th the ted in ilding lating dust during ving a ted in DPC-under C owed 0-102 water

La Cross License T Revision In w

D O

un O

co in O

si co B

to O

ap b

2.1.4.2.

Between release o ranged fr and fuel impacted policies releases.

2.1.5. F LACBW within its been imp post ope Survey fo for fissio Structure Turbine Stack. In to be dire An area s support b various w se Boiling W Termination n 0 ncidents invo waste water t Discharge lin On January nspecified v On May 31, ontaminated nto the basem On July 02, 1 ight flow se ontaminated Bay door. In o an unrestri On July 16, pproximately asement floo Chem 1967 and 20 of chemicals rom spills of oil from sy d buildings.

and proced Findings and WR was desig s many syste pacted due t erational his or SAFSTOR on products t es classified Building, W n addition to ectly impacte surrounding buildings su warehouses a Water Reactor Plan olving leaka tanks throug ne were noted 30, 1981, volume of wa 1982, a lid d water and ment. (DPC 1982, approx eal rupture t d water flow n addition, a cted area. (D 1983, a leak y 15,000 gal or. (LER 83 mical Spills 014, the HSA s and/or pote f acids and c ystems and These spills dures for id d Conclusio gned with mu ems, compon to routine op tory of the R (7) identifi to enter and i as impact WTB, Low S o the structur ed by the op the LSE ha uch as the L and storage b r

age of potent gh the norma d from 1980 the Turbin ater into the seal failed o spent resin 51 Incid ximately 1,2 o the Turbin wed into the approximatel DPC-82-58 I k in the Sea llons of reac 3-07)

A document entially haza caustics used storage tank s were contr dentification ns ultiple bound nents, and st perations an plant. Dai ied historica impact react ted by the Specific Act res, the soils peration of th s also been d LACBWR C buildings.

2-8 tially contam al effluent re 0 to 1986.

e Building laundry room on a spent r onto the flo dent Report) 200 gallons o ne Building soils outsid ly 25 gallons Incident Rep al Water Inj ctor coolant ted several in ardous liquid d in the plan ks. A majo rolled and re n, control a daries to con tructures. M nd maintenan iryland LAC al failed fuel tor and supp operation o tivity (LSA) s surrounding his facility. T designated a rib House, L minated liqui elease pathw Waste W

m. (DPC-81 resin liner w oor of the S of condensat g floor, and de the Turbi s of contam port, LER 82 njection Syst to be discha ncidents inv ds to the en nts various ority of the emediated in and remedia ntrol and con Many of these nce activitie C-TR-138, I incidents at ort systems.

of the facilit

) Building, g these build This area is as impacted.

LACBWR A id from the T way to the C Water Tank 1-10 Inciden which resulte Spent Resin te water was approximate ine Building minated liquid 2-016) tem leak at arged to the volving the u nvironment.

systems to t incidents oc n accordance ation of haz ntain the rad e systems an es during the Initial Site t LACBWR ty include R WGTV, and dings have a defined by t This area i Administrati Turbine Bui Circulating W overflowed nt Report) ed in the sp Liner Room s released fr ely 20 gallo g door and T d was discha 1A FCP ca Reactor Bui unplanned sp These inci the spill of d ccurred insid e with the st zardous ma dioactive con nd structures e operationa Characteriz and the pote Reactor Buil d the Ventil also been de the LSE fenc includes anc ion Building ilding Water d and pill of m and rom a ons of Truck arged aused ilding pill or idents diesel de of tation aterial ntents have al and zation ential

lding, lation emed ce.

cillary g and

La Cross License T Revision In additi support impacted LSE whi the LSE 2.1.6. In As part o into preli and exist 2.1.6.1.

The entir larger ph classifica efficient identified were clas and are id were clas current c 2.1.6.2.

The surv or open l were deli radioactiv relatively appropria The surv Prior to accordan sizes for The deco segmenta the excep any struc survey u These ob volume c In additio the purpo se Boiling W Termination n 0 ion to the a buildings, t d to provide ich is consid areas compr nitial Surve of the HSA p iminary surv ting survey d Surve re 163.5 acr hysical sectio ation. Surv and practic d in the area ssified as n dentified in ssified as im lassification Surve vey areas wer land area tha ineated to ph vity to the e y compact sh ate for the si vey units est characteriza nce with the g survey units ommissionin ation, remov ption of stru cture will re units have be bjectives inc contained on on, the surve ose of chara Water Reactor Plan area within the open lan a buffer zon dered non-im rising approx ey Areas/Un process, the i vey areas an data.

y Areas res licensed ons of the sit vey area size cal size need

a. Survey ar on-impacted the HSA. S mpacted. F ns by area.

y Units re further di at is surveye hysical areas extent practi hapes and hi ite operation tablished by ation, survey guidance pro s for FSS.

ng approach val and dispo cture basem emain at sit een establish clude provid nsite, and dis ey units estab acterization p r

the LSE an nd immedia ne between t mpacted. Th ximately 1.5 nits and Clas impacted LA nd assigned site was div te that may e was deter ded to boun reas that hav

d. These ar Survey areas Figure 2-1 p vided into su ed and evalu s with simila cal. To the ghly irregula nal history or the HSA w y unit sizes f ovided in M that will be osal of all im ment floors an te closure a hed for struc ding survey d sposition opt blished for s planning and 2-9 nd the open ately surroun the LSE and he licensed s acres of the ssification ACBWR stru area classifi vided into su contain one rmined base nd the latera ve no reason reas have no with reason provides an i urvey units.

uated as a sin ar operationa extent prac ar shapes we r the site top were used as for Class 1 o ARSSIM, se e implement mpacted sys nd walls that and consequ ctures to fac data for rem tions for the structures tha d do not cor land areas unding the L d the G-3 lan site comprise e owner cont uctures and o ications base urvey areas.

or more sur ed upon the al and verti nable potenti o radiologica nable potenti illustration o A survey u ngle entity f al history or ctical, survey ere avoided u ography.

initial surve open land su ection 4.6 fo ted at LACB stems and ab t reside 3 fee uently, be su cilitate other mediation pla waste.

at are 3 feet rrespond to surroundin LSE fence nd and facil es a total of trolled area.

open land ar ed on the op

. Survey ar rvey units de specific ar ical extent o al for residu al impact fro ial for residu of the LACB unit is a port following FR similar pote y units were unless the un ey units for urvey units or the sugges BWR calls bove-grade et below gra ubjected to r characteriz anning, estim below grade the survey u g the LACB is designate lities south o f 163.5 acres reas were div perational hi reas are typi epending on rea and the of contamin ual contamin om site opera ual contamin BWR site an tion of a stru RS. Survey ential for res e established nusual shape characteriza were adjust sted physical for the com structures.

ade, no porti FRS. How zation objec mating the w e are intende units that w BWR ed as of the s with vided istory ically n their most nation nation ations nation nd the ucture units sidual d with e was ation.

ted in l area mplete With ion of

wever, tives.

waste ed for will be

La Cross License T Revision used for section 5 Tables 2-impacted site struc 2.1.6.3.

The follo React Turbi (L10 LSA North The basis soil by r spills of packages Based on subsurfac the unres 2.1.6.4.

The follo LACB (L20 G-3 C (L20 Based up surveys p radioactiv Class 2 o 2.1.6.5.

The follo North Trans Plant se Boiling W Termination n 0 the FRS o

.5.2 of Chap

-1 and 2-2 p d structures ctures. A sum Class owing open l tor Building ine Buildin 10102),

Building, M h LSE Area s for this cla radioactive m radioactive s and contain n an assessm ce soils in th stricted use c Class owing open l BWR Adm 11101),

Crib House, 11102).

pon a review performed in ve contamin open land sur Class owing open l h End of Lic smission Sw t Access, ISF Water Reactor Plan f remaining pter 5).

provide a de respectively mmary of th 1 Open Lan land areas ha g, WTB, WG ng, Turbine Maintenance (L1010104) assification is material in t liquids and ners.

ment of histor hese areas c criteria. Clas 2 Open Lan land areas w ministration LACBWR w of the hist n these area nation to exc rvey units ar 3 Open Lan land areas w censed Site (L witchyard Are FSI Haul Ro r

g below grad etailed list o

y. Figure 2-2 he survey uni nd Areas ave been cla GTV, Ventila Office Bu Eat Shack G s due to a se these areas d resins, radi rical inciden could possibl ss 1 open lan nd Areas were classifie
Building, Circ. Water torical inform as as docume eed the unre re shown on nd Areas were classifie L3012101),

ea (L301210 ad Grounds 2-10 de structure of the survey 2 provides a it classificati assified as im ation Stack G uilding, 1B Grounds (L10 ries of docum during facil ioactive sys nts and event ly contain re nd survey un ed as impacte LACBWR Discharge L mation and ented in the estricted rele Figure 2-1.

ed as Class 3 02),

(L3012109) es (designate y units for b a detailed in ions are pres mpacted Clas Grounds (L1 Diesel G 010103),

mented incid lity operation stem leakage ts, it was an esidual radio nits are show ed Class 2:

R Crib Ho Line, Area S operational HSA, there ease criteria.

).

ed as STS a both the ope nventory of sented as fol ss 1:

010101),

Generator Bu dents of the ns. These i e, and storag nticipated tha oactive mate wn on Figure ouse, Ware South of LSE radiation an e was a pote and discuss en land area the building llows.

uilding Gro contaminati incidents in ge of radioa at the surfac erial in exce e 2-1.

ehouse Gro E Fence Gro nd contamin ential for res ed in s and g and ounds ion of clude active e and ess of ounds ounds nation sidual

La Cross License T Revision Historica in concen Class 3 o 2.1.6.6.

Based on in the HS contamin G-3 C Coal Capp Grou Hwy The non-2.1.6.7.

The follo structure These str radioactiv radioactiv majority React Wast Venti Wast Turbi Diese LSA Main Througho spread o were rou structure structura below gr subjected se Boiling W Termination n 0 al informatio ntrations in e open land sur Non-I n a review o SA, the bala nation and ha Coal Plant G Pile Ground ped Ash Imp unds East of H 35/Railroad

-impacted op Class owing is a li

s. The com ructures con ve waste sy ve material of the curren tor Building te Treatment ilation Stack te Gas Tank ine Building el Generator Building (B ntenance Eat out facility o f loose surf utinely post s involves l material as rade, no por d to FRS. Th Water Reactor Plan on contained excess of the rvey units ar Impacted Op f the operati ance of the as been desig Grounds (L40 ds (L401210 oundment G Highway 35 d Right of W pen land surv 1 Structures ist of the m mplete list of ntain the nuc ystems, and n was routine nt radioactiv g (B1010001 t Building (B k (B1010003 Vault (B101 g (B1010005 r Building (B B1010007)

Shack (B10 operations, th face contam ted as cont the comple s waste. Wi rtion of the he Class 1 st r

d in the HSA e unrestricted re shown on pen Land Are ing history o 163.5 acre li gnated as no 012103)

5)

Grounds (L40 5 (L4012107 Way Grounds vey units are s

major buildin f all impact clear reactor nuclear fuel ely handled, ve material in

)

B1010002)

3) 10004)
5)

B1010006) 010008) hese structur ination, and taminated a ete segment ith the excep se structure tructural surv 2-11 A indicated th d release cri Figure 2-1.

eas of the facility icensed site on-impacted.

012106)

)

(L4012108) e shown on F ngs that were ted structura r, primary re l handling a

, transferred nventory at L res were sub d airborne ra areas. The tation, remo ption of stru s will rema vey units are hat the prese teria was no y and histor has no reas

)

Figure 2-1.

e initially cl al survey un eactor system and storage s d, and stored LACBWR r bjected to spi adioactive m decommis oval, and d uctural floor ain at site cl e depicted in ence of resid ot expected.

rical incident sonable pote lassified as nits is provid ms, reactor systems. D d within the resides in the ills of radioa material. St sioning app disposal of s and walls losure and a n Figure 2-1 dual radioac ts as docum ential for res impacted Cl ded in Table support sys uring operat ese building ese structure active liquid tructural sur proach for all systems that reside 3 are therefor ctivity ented sidual lass 1 e 2-2.

tems, tions,
s. A es:

ds, the rfaces these s and 3 feet re not

La Cross License T Revision 2.1.6.8.

The follo Class 2 o complete LACB G-3 C LACB LACB LACB LACB Back Trans G-1 C Barge These str structure LACBW Washing structure Administ the decom LACBW structure The LAC Switch H unrestrict Supplem Manual depicted Based on in the H section 2 residual the G-3 C 2.2.

C From Oc accordan se Boiling W Termination n 0 Class owing is a li or 3 structur e list of all im BWR Crib H Crib House (

BWR Admi BWR Wareh BWR Wareh BWR Wareh k-up Control smission Sub Crib House (

e Washing B ructures did s associated WR workers g Break Room s because th tration build mmissioning WR Class 2 or s will remain CBWR Adm House will n ted release ment 1, Multi (MARSAM in Figure 2-n a review o HSA, coup 2.3.5), the bu contaminatio Crib House, Characteriza ctober 2014 nce with th Water Reactor Plan 2 and 3 Stru ist of some res. All are mpacted stru House (B201 (B2010102) nistration Bu house #1 (B2 house #2 (B2 house #3 (B2 Center (B30 b-Station Sw (B3012103)

Break Room not routinely d with LAC and therefo m were not a hey reside i ding, the G-3 g approach c r 3 systems n at site clos ministration b not be subj using a gr i-Agency Ra E) (8). The

-1.

f the operati pled with t uildings ass on and have will remain ation Appro through Aug he Characte r

uctures of the major e located wi uctural surve 10101) uilding (B20 2010104) 2010105) 2010106) 012101) witch House (B3012104) y house radi CBWR listed re considere associated w in a Class 3 3 Crib Hous calls for the and structur sure and ther building, the ected to FR raded survey adiation Sur e Class 2 an ing history o the results sociated with e been desig intact and fu oach gust 2015, s erization Su 2-12 r buildings t ithin the lice y units is pro 010103)

(B3012102)

)

ioactive syst d above are ed Class 2 with LACBW 3 land area.

se and the T complete se ral material a refore will n e G-3 Crib H RS. Instead y approach rvey and As nd Class 3 s of the facility of charact h the G-3 s gnated as no unctional for site characte urvey Plan.

that were in ensed site b ovided in Ta

)

tems or mate outside of or 3. The WR operation With the Transmission egmentation, as waste or ot be subjec House and th d, these stru using the ssessment of structural su y and histor terization su station have on-impacted.

r G-3 power erization of L The Ch nitially classi but outside o able 2-2.

erials during the LSE bu G-1 Crib H ns but are co exception o n Sub-Statio

, removal, an salvage. No ted to FRS.

he Transmis uctures will guidance o of Materials urvey units rical incident urveys (as no reasona

. The G-3 s r operations.

LACBWR w haracterizatio ified as imp of the LSE.

g operations.

ut were use House and B onsidered Cl of the LACB on Switch H nd disposal o portion of ssion Sub-St be surveye f NUREG-s and Equip for building ts as docum summarize able potentia station, inclu was perform on Survey pacted The The ed by Barge lass 3 BWR

House, of all these tation d for
1575, pment gs are ented ed in al for uding med in Plan

La Cross License T Revision incorpora documen develope executing procedur safely an Characte objective Provi Deve Supp volum The deco buildings character subjected removed 1757, Ap The char subsurfac structura surveys w structure used to m above gr of the ex

planned, planning A signifi unit is cla design fo result in unit meet errors.

As site-s LACBW selected.

in NURE Paramete assess the se Boiling W Termination n 0 ated the pre nted in the su ed to provide g characteriz res and surv nd effectively rization data es:

ide radiologi elop the requ ort the eva mes.

ommissionin s, structures, rization effo d to FRS. E prior to the ppendix O.

racterization ce soils, pav l basements were perform

s. Upon com make determ rade or subg xpected end-executed an icant questio assified corr or FRS. A a survey des ts the release pecific Deri WR at the tim The screen EG/CR-5512 er Analysis e correct cla Water Reactor Plan evious histo urvey areas e guidance a zation survey ey unit spec y acquire the a acquired th ical inputs n uired inputs f aluation of r ng approach

, and compo orts focused Extensive ch e performanc n surveys fo ved surfaces, s that will re med in the L mpletion, the minations on w rade structu

-state structu nd documen on that must rectly. The a classificatio sign that doe e criteria. In ived Concen me the chara ning DCGLs 2 Volume 3 (9), Table 6 assification o r

orical opera from the HS and direction y activities.

cific survey e requisite ch hrough the e necessary for for LTP, and remediation for LACBW onents to a d d on open haracterizatio ce of final s ocused on g

, and concret emain in the LACBWR Ad e data was a whether add ures, surface ures at LAC nted with the be answere appropriate c on which un es not obtain n some cases ntration Guid acterization s presented i

, Residual R

.91 (Pcrit = 0 of impacted o 2-13 ational and SA and prev n to the pers The Plan w instructions haracterizati execution of r the design o d

alternatives WR calls for t depth of at l land areas on of equipm surveys is no general open te pads. Co e end-state dministration ssessed for q ditional chara and subsurf CBWR. Con e same data ed by the cha classification nderestimate n adequate in s, this can in deline Level survey was in NUREG-1 Radioactive 0.10) for soil open land or radiological vious site ch sonnel respo worked in co s (sample pl on data.

the Plan wa of FRS, s and techn the demoliti least 3 feet b and remain ment, system ot required i n land areas oncrete core condition.

n Building a quality and a acterization face soils, or ntinuing cha quality and aracterizatio n of a survey es the poten nformation to ncrease the p ls (DCGLs) performed, 1757 and th Contamina ls were used r soil survey l informatio aracterizatio onsible for im njunction w lans) that w as used to m nologies and ion and remo below grade ning structu ms or struct in accordanc s including:

samples wer In addition, and several o adequacy. T data is requ r beneath th aracterization d the results on is whethe y unit is crit ntial for con o demonstra potential for m were not ye alternate ac e concentrat ation from D d as alternat units.

on collected on efforts. I mplementing with impleme were develop meet three pri d estimate w oval of all on

e. Conseque ures that wi tures that w ce with NUR site surface re taken from

, characteriz of the G-3 st The data was uired, primar he concrete f n surveys w included in er or not a su tical to the su tamination c ate that the su making deci et establishe ction levels tion values f Decommissio e action leve d and t was g and enting ped to imary waste n-site

ently, ill be ill be REG-e and m the zation tation s then ily of floors will be n FRS urvey urvey could urvey isions ed for were found oning els to

La Cross License T Revision For struc to evalu 7,100 dpm Appendix radionuc the conse for Cs-13 2.2.1. D DQOs w FRS. Ho to determ unrestrict inspectio nature, e applicabl Characte outlined

1) State
2) Ident
3) Ident
4) Defin
5) Deve
6) Speci
7) Optim The DQO collect. N and will assessme obtaining obtained Direct m Minimal that exhi Detect (H 2.2.2. S Characte approved approach se Boiling W Termination n 0 ctures, the gr ate the clas m/100cm2 to x H. Use of lide distribu ervative appr 37 is signific Data Quality were impleme owever, the mine the rad ted use crit ons and surv xtent and ra le structures rization surv in MARSSIM the problem tify the decis tify inputs to ne the study elop a decisio ify limits on mize the des Os for site No structure therefore no ent of concre g core samp to determin measurement Detectable ibited the hi HTD) radion urvey Desig rization sur d procedures h based upon Water Reactor Plan ross screenin ssification o otal gross be f the Co-60 ution for surf roach was to cantly greate y Objectives ented for ch goal of char ionuclide m teria to dem veys of suff ange of radio

, residues, so veys were de M, Appendi m,

sion, o the decision boundaries, on rule, n decision err ign for obtai characteriza es located ab ot be subject ete in basem ples. Soils ne the mean s and scans Concentrati ighest activi nuclide(s).

gn rveys were s and the Cha n the DQOs f r

ng level that of survey u eta-gamma s screening v face contam o assume a d er.

s haracterizatio racterization mixture, wher monstrate co fficient quali oactive cont oils and surf esigned to g ix D. The se n,

rors, and ining data.

ation include bove 3 feet b ed to FRS.

ments and su were sampl and maximu s of surface ons (MDC) ity were sen designed a aracterizatio for each surv 2-14 t was used d units was th surface activ value was co mination wou distribution o on surveys in n is to quanti reas the FRS ompliance w ity and qua tamination in face water.

gather the ap even steps in ed identifyin below grade Consequent urrounding so led volumet um activity a soils were as will be e nt to an off-and perform on Survey Pl vey unit. Fo during chara he nuclide-vity based on onservative a uld be princi of 100% Co n a similar m ify and delin S goal is co with 10 CFR antity were n each appli propriate da n the DQO d ng the types will remain tly, sample c oils. Buildi trically. Su as well as th made using employed fo

-site laborat med in acco an. Survey or example, acterization a specific scr n Co-60 from as it was an ipally Co-60

-60 since the manner as an neate contam omparison of R 20.1402.

performed t icable surve ata using the development s and quanti n following d collection wa ing concrete ufficient me he sample sta g the same or FSS. Vo tory for ana ordance wit design incor an open land as an action reening valu m NUREG-nticipated tha 0 and Cs-137 e screening v nticipated fo minated area f data agains Characteriz to determin ey unit, inclu e DQO proce process are:

ities of med decommissio as focused o e was sample asurements andard devia instruments lumetric sam lysis of Har th all appli rporated a gr d survey uni level ue of

1757, at the 7 and value or the as and st the zation e the uding ess as dia to oning on the ed by were ation.

s and mples rd-to-icable raded it was

La Cross License T Revision designate the unres Class 1 s present.

to identif Class 2 o survey m select loc measurem biased su unit. A delineate warrante survey un The area character S

al su B

sy F

R ad S

A S

S ar S

C P

A L

2.2.2.1.

The num by assess se Boiling W Termination n 0 ed as Class stricted relea survey unit f The survey fy the lateral or Class 3 re measurement cations for s ment and/or urvey design A biased app e the extent o d if the char nit.

as and mater rization surv urface scans ll Class 1, 2 urvey unit L Biased subsur ystems of c igure 2-3.

Random sam ddition, soil cans and s Administratio amples were cans and sam reas.

cans and sam Concrete sam iping and V A backgroun LACBWR in Numb mber of measu sing the sam Water Reactor Plan 1 because it ase criteria.

focused on b design was l and vertica eceived surv locations an static measu sample loc n or a random proach was of an area th racterization ials surveye vey included s and random 2, 3, and no L3012102 (i.e rface soil sa oncern in C mples were ta samples we amples wer on Building e taken from mples were mples were t mples were t entillation tu nd radiation cluding: asp ber of Static urements an ple size nece r

t may conta Therefore, t bounding the based upon al extent of th veys develop nd scan area urements and cations at ran m approach warranted hat requires effort was d ed and/or sam m and biased on-impacted e., the switch amples were Class 1 and aken from a ere obtained re taken on and the G-3 m the septic ta taken on LA taken on G-3 aken in the unnels.

study was phalt, concret Measuremen nd/or sample essary to sat 2-15 ain levels of the character e contaminat n the number he contamin ped to includ

s. Biased su d/or samples ndom. The was address when the c remediation designed to v mpled in and d surface and open land a hyard).

taken along 2 areas incl asphalt and c directly belo n accessible Coal Plant.

anks.

ACBWR Ad 3 Building a basement ar performed te, and soil.

nts and/or S s that were t tisfy the DQO f radiologica rization surv tion where c r of measure nation. Area de a combin urvey design

s. Random e decision of sed by the D characterizat
n. Alternativ verify the ba d around the d subsurface area survey gside and un luding the p concrete from ow the aspha e roof surfa dministration access and he reas of the R on material amples taken in each Os.

al contamina veys that wer ontaminatio ements and as classified nation of ran ns used know survey desig f whether to DQO process tion effort w vely, a rando asis for the c e licensed ar e soils samp units with derneath und piping syste m pads and alt to a one m ace areas of n Building su eavily travel Reactor Bui ls similar to h survey uni ation greater re performed n was poten samples req as non-impa ndom and b wn informati gn selected o use primar s for each su was designe om approach classification rea as part o ples were tak the exceptio derground p ms as show paved area meter depth.

f the LACB urfaces and led surfaces.

lding, WTB o those foun it was determ r than d in a ntially quired

acted, biased ion to static rily a urvey ed to h was n of a of the ken in on of piping wn on
s. In BWR drain B, and nd at mined

La Cross License T Revision For the c that will and/or sa of residu For the sample s vertical e For non-validate measurem trivial lev generated 2.2.2.2.

For the c survey u Sample l to specifi that wer responsib survey d radioactiv potential from the 2.2.2.3.

Survey u area to b area scan Supervis was give survey un 2.2.2.4.

The char (beta and survey of FRS con and volu sampling following se Boiling W Termination n 0 characterizat be subjecte amples taken al radioactiv characteriza size was bas extent of the impacted an the basis ments and/o vels of licen d radionuclid Determ characterizat nits that wil locations we ic locations w re taken in ble Radiolog design proc vity, depres spill locatio HSA aided Scan C units were sc be scanned i nned was c or and/or th en to inform nit.

Types racterization d gamma); st f any concre nsisted of a c umetric samp g of surface g is a descrip Water Reactor Plan tion of impa ed to FSS, th n in the surve ve contamina ation of Cla sed upon the contaminati nd Class 3 op of the clas or samples w nsee-generat des are prese mination of tion of non-ll be subject ere determin within the su each surve gical Protect cess. Con sions, disco ons, or areas in the select Coverage canned to th n each surv ontingent up e Project He mation from s of Measure n survey of tatic beta me ete and/or as combination ples. The su and subsurf ption of the d r

acted Class 1 he minimum ey units wer ation in the s ss 1 structur e necessary n ion.

pen land sur ssification.

was sufficie ted radionuc ent in non-im Static Measu

-impacted an ted to FRS, ed by gener urvey unit. T y unit was tion Superv sideration w olored areas, s where the tion of biased he extent pr ey unit was pon the pro ealth Physic the initial w ements and S building sur easurements phalt-paved n of surface urvey of the face soil, sed different typ 2-16 1 and Class m number of re commensu survey unit.

res that wil number of s rvey units, th Consequen ent to ensure clides are pr mpacted area urement and nd impacted sample loca ating random The location determined visor and/or was given

, cracks, low ground has d locations.

actical in ac determined ofessional ju ist during th walk downs Samples rfaces consi s, material sa open land a scans (beta e open land diment and s pes of measu 2 open land f random or urate with th l remain an samples nee he primary c ntly, the nu e with reaso resent in Cl as.

d Sample Lo d open land ations were m pairs of c n of biased m d by the pr the Project to location w point grav s been distur ccordance w d during the udgment of he survey de and the am isted of a co amples and s areas that wi and gamma areas consis surface wate urements and d areas (pav r biased dire he probabilit nd be subjec eded to asses characterizat umber of s onable conf lass 3 areas ocations areas and C primarily ch oordinates t measurement rofessional j Health Phy ns that exh vity drain p rbed. Histo with their cla survey desi the Radiolo esign proces mbient radiat ombination smears. The ill remain an a), static bet sted of gamm er for isotop d samples tha ved and unpa ect measurem ty of the pres cted to FRS ss the latera tion DQO w systematic fidence that and no lice Class 2 struc hosen at ran hat correspo ts and/or sam judgment o ysicist durin hibit measu points, actua orical inform assification.

ign process.

ogical Prote

s. Consider tion levels i of surface e characteriz nd be subject ta measurem ma scans an pic analysis.

at were utiliz aved) ments sence S, the al and was to static only ensee-ctural ndom.

onded mples of the ng the urable al and mation The The ection ration in the scans zation ted to

ments, nd the The zed.

La Cross License T Revision 2.2.2.4.1 Gamma activity.

used for Ludlum M Ludlum M Scanning rate not t was main and, loca 2.2.2.4.2 Scanning 7,100 dpm including Hand-hel used.

Beta scan and with prevented was dete calculate of the sur If not im instrumen evaluatio investiga 2.2.2.4.3 Direct m surfaces typically detectors Direct m acquiring typically designate adjusted 2.2.2.4.4 If applic verify lo se Boiling W Termination n 0 Gamm scans were Sodium io these scans.

Model 44-10 Model 44-10 g was perfor to exceed 0.

ntained with ations of elev Beta S g was per m/100cm2 a g, but not li ld beta scin nning was p h a scanning d scanning a ermined, an d a priori to rvey.

mpacted by h nt to identi on. Any ide ation and pot Direct measurement of the build performed

s.

measurements g data over used for su ed investigat as appropria Remo able, remov oose surface Water Reactor Plan ma Surface S performed o dide (NaI) g EnergySol 0 Detector 0 NaI detecto rmed by mo

.5 m (20 in) hin 15 cm (6 vated direct l Surface Scan rformed in action level.

imited to; fl ntillation and performed w g speed of o at the specif nd the scan o ensure that high ambient fy locations entified areas tential decon t Measureme ts were per dings or on using ~10 s were condu a pre-determ urface measu tion level or ate to achiev ovable Surfac vable beta an e contamina r

Scans over open la gamma scin utions Techn Sensitivity (

ors to Co-60 oving the de per second.

in) of the s levels were f ns order to Beta scans loors, walls, d/or gas-flo with the dete one detector fied distance nning techni t the MDC f t noise level s of elevate s of elevated ntamination.

ents rformed to n concrete o 00 cm2 or l ucted by pla mined coun urements and r MDC und ve an accepta ce Contamin nd/or alpha ation is less 2-17 and surfaces ntillation det nical Suppor (10) examin 0 and Cs-137 etector in a s The distan urface if po flagged for f locate ar s were perfo

, ceilings, ro ow proportio ctor position r active win e, the detect ique adjuste for scanning s, technician d activity th d contamina detect total or asphalt pa arger sized acing the det nt time. A d generally p er considera able MDC fo nation contaminati s than the to identify tectors (typic rt Document nes the resp 7 when used serpentine p nce between ssible. Aud further inves reas of res ormed over a oofs, asphal onal detecto n maintained ndow per se tion sensitiv ed accordin g was approp ns monitored that require ation were m levels of aved areas.

scintillatio tector near t count time provided det ation. The i or direct mea on or smear applicable locations of cally 2 x 2 t (TSD) RS-onse and sc d for scanning pattern, whil n the detecto dible signals stigation and sidual activ accessible st lt and concr ors (typically d within 1 c econd. If su vity for the a ngly. Scan priate for the d the audibl further inv marked or fla contaminati These me on or gas-fl the surface to of one to t tection level instrument c asurements.

r surveys w action level f residual su

) were typi

-TD-313196 can MDC o g surface soi le advancing or and the su were monit d/or sampling vity above tructural sur rete paved a y 126 cm2) cm of the su urface condi alternate dis nning speed e stated obje e response o estigation a agged for fu ion on struc asurements low proport o be counted two minutes ls well below count times were perform

l. A smea urface ically 6-006, of the ils.

g at a urface tored;

g.

the rfaces areas.

were urface itions stance was ective of the and/or urther ctural were tional d and s was w the were med to ar for

La Cross License T Revision removab surfaces.

moderate activity a 2.2.2.4.5 Concrete contamin will rema diamond 1/2-inch w pulverize 2.2.2.4.6 Samples locations scanning defined a split spoo tools.

Subsurfa hand aug survey un 2.2.3. In The radi provide b identified action le and expe static me Concern Commer perform

3) analys Instrume in Table 2.2.3.1.

All data character se Boiling W Termination n 0 le activity w A 100 cm e pressure. S as appropriat Concr e core boring nation and th ain and be su bit core dri wide pucks ed and analy Mater of soil, sed s as well as

g. Surface so as soil below on sampling ace soil was gers. Subsur nit.

nstrumenta ation detect both reliable d for the de evels. Detec ected perform easurements (ROC) at a cially availa the three ba sis of materia ntation and 2-3.

Calibr loggers, ass rization wer Water Reactor Plan was usually m2 surface a Smears were te.

rete and Asp g and the sa he presence ubjected to F ill. The con s, represen yzed for isoto rial Sampling iment, and s other locatio oil is defined w the top 15 g system or, b sampled by rface soil sam ation Selectio tion and me e operation a ecommission ctor selectio mance in th and scanni MDC of 50%

able portable asic survey m al samples.

nominal MD ration sociated dete re calibrated r

taken at eac area was sa e then analyz phalt Core Sa ampling of of volumet FRS. Core b ncrete samp nting a certa opic content.

g sludge were ons in areas d as the top cm layer in by using han y direct push mpling was on, Use and asurement i and adequate ning of LAC on was based e field. In ng were cap

% of the app e and laborat measuremen DC values th ectors, and a d on an annu 2-18 ch direct me ampled with zed for the p ampling concrete we tric contami bore samplin le produced ain depth in obtained fr s exhibiting 15 cm (6-in n 1 m increm nd trowels, b h sampling s performed a d Minimum nstrumentat e sensitivity t CBWR at le d on detecti all cases, th pable of det plicable actio tory instrum ts: 1) surfac hat were em all other por ual basis us easurement l h a circular presence of g ere used to nation in co ng of concre d by the cori nto the surf rom designed elevated act nch) layer of ments. Surfa bucket auger systems (e.g as necessary Detectable tion for char to detect the evels suffici ion sensitivi he instrumen tecting the a on level.

ments and det ce scanning; mployed durin rtable instrum sing Nationa location on cloth or pa gross beta an assess the d oncrete wall ete was acco ing was typ face. Conc d biased and tivity that w f soil while s ace soil was rs, or other s

g. GeoProbe y to address t Concentrat racterization e initial suite iently below ity, operatin nts and detec anticipated R tectors were
2) static me ng character mentation th al Institute o non-asphalt aper filter, u nd/or gross depth of sur ls and floors omplished us pically sliced crete pucks d random sa were identifie subsurface s collected us suitable sam

) or by m the DQOs fo tions (MDC n was select e of radionuc w the establ ng characteri ctors selecte Radionuclid typically us easurements rization are hat were use of Standards t type using alpha rficial s that sing a d into were ample ed by soil is sing a mpling anual or the Cs) ted to clides lished

istics, ed for des of sed to s; and listed ed for s and

La Cross License T Revision Technolo addressed 2.2.3.2.

The recei used for portable character 2.2.4. L Gamma proportio laborator quality p preparati site labor In all ca achieved accepted analytica laborator 2.2.5. Q MARSSI used to quality fo 1576, Mu Regulato through (12). Fu may be achieved The QAP used duri functiona All chara approved audit a

Characte prescribe applied contracto se Boiling W Termination n 0 ogy (NIST) t d in the QAP Instru ipt, inspectio characteriza radiologica rization is ad Laboratory I spectroscop onal countin ry in accorda programs of ion and analy ratory under ases, analyti

d. The anal methodolog al methods ries used for Quality Assu IM, section demonstrate for sample an ulti-Agency R ory Guide 4.

Normal Op urther, MAR used in add

d.

PP was prep ing the site c al activities, acterization d procedures and surveil rization staf ed, impleme to any app ors.

Water Reactor Plan traceable sou PP.

ument Use an on, issue, co ation was p al instrumen ddressed in th Instrument py was prim ng and liquid ance with ap the contrac ysis of chara the QAPP.

ical methods lysis of rad gies or othe employed characteriza urance 2.2 discusse e that site c nalysis taken Radiologica

.15, Quality erations to RSSIM and dition to, or pared and im characterizat the DQO pr activities es

s. The effe llance activ ff and progr ented, and v plicable serv r

urces. The c nd Control ntrol, and ac performed in ntation. T he QAPP.

Methods an marily perfor d scintillatio pproved labo cted off-site acterization s s were estab diological co er comparab and the la ation.

es the need f conditions ar n to support al Laboratory y Assurance License Ter MARLAP b r in lieu of, mplemented t tion and FRS rocess, and m ssential to d ective imple

vities, incl ram self-ass verified wh vices provid 2-19 calibration o ccountability n accordance The issue a nd Sensitivi rmed by th on analysis oratory proce vendor labo samples prov blished to e ontaminants ble methodo aboratory M for a quality re acceptabl t characteriz y Analytical of Radiolo rmination) -

both indicate existing qu to ensure th S process. T measures nec data quality w mentation o luding fiel sessments, a hen deficienc ded by off-of instrument y of portable e with issue and control ities he on-site ra was perform edures. Ener oratories tha vided the sam ensure that used stand ologies. Ta MDC achiev y system to le for unres zation and F l Protocols M ogical Moni

- Effluent St e that a Qua uality system e adequacy The QAPP de cessary to ac were implem of characteri ld walk-do as appropriat cies were i

-site vendor ts used for c e radiologica e and contro l of instru adiological med by an rgySolutions at were used me level of required M dard approve able 2-4 prov ved by the ensure the a stricted rele FRS is discu Manual (MA itoring Prog treams and ality Assura ms to ensur of data bein escribes poli chieve qualit mented and ization was owns by te. Correct identified.

rs, as well characterizati al instrument ol procedure uments used laboratory.

approved ve s ensured tha d for the rec quality as th MDC values ed and gene vides the ty off-site ve adequacy of ase. Labor ssed in NUR ARLAP) (11 grams (Incep the Environ ance Project re data qual ng developed icy, organiza ty data.

performed u verified thr EnergySolu tive actions These mea as on-site ion is tation es for d for Gas endor at the

ceipt, he on-were erally ypical endor f data ratory REG-

) and eption nment Plan ity is d and

ation, using rough utions were asures sub-

La Cross License T Revision The Cha quality a and is su follows:

E op A

st D

Details o the proce data acqu requirem P

E P

S P

M pr All chara Plan, the 2.3.

S In Octob placing t October character accelerat EnergySo October 9 August 6 documen Characte PN-1640 2015 Fie Radioact character character se Boiling W Termination n 0 aracterization assurance and ubject to the Establishmen perations.

Actions to en taff.

Documentatio of the QA/QC edures and s uisition and ments. The sp ersonnel qua Execution in roper docum election of a roper instrum Management rocedures, p acterization QAPP, all a ummary of ber of 2005, the unit into of 2014, rization of L tion of de olutions in a 9, 2014. T 6, 2015. The nted in two erization Sur 017-001, LA eld Work (14 tive systems rization dat rization has Water Reactor Plan n Survey Pl d quality co QAPP. The nt/implement nsure that the on of the dat C elements s sample plan d recording pecific QA/Q alifications, accordance mentation of appropriate i ment calibra oversight of protocols, an activities w applicable im f Characteri Dairyland p o a SAFSTO Dairyland LACBWR in commission accordance w The schedule e results of th o separate rvey Report CBWR Radi 4).

s that rema a in certain been deferre r

lan was dev ontrol (QA/Q e QA/QC pr tation of plan e procedures ta collected.

specific to ch instructions was guided QC program experience, with approv survey data instruments t ation and dai f characteriz d documenta were conduct mplementing ization Surv performed a OR condition contracted n anticipation ning activiti with EnergyS ed EnergyS he site chara reports, GG for October iological Ch ain at LAC n areas du ed until such 2-20 veloped acco QC) program ogram elem ns, procedur are understo haracterizati

. The chara d and condu m component and training ved procedur and sample to perform th ily functiona zation activit ation require ted in accor g procedures vey Results limited cha

n. This sur EnergySol n of the deve ies. Char Solutions cha Solutions sit acterization s G-EO-31319 r and Novem haracterizati CBWR affec ue to ambie h time that ra ording to th m for the dec ments applica res, and prot ood and foll ion are prese acterization o ucted in com s for site cha
g.

res.

analyses.

he surveys.

al checks.

ties relative t ements.

rdance with

, and approv aracterization rvey is docu lutions to elopment of racterization aracterizatio te characteri surveys perf 96-RS-RP-0 mber 2014 F ion Survey R cted the ab ent radiatio adiological o he essential commissioni able to chara tocols for the lowed by the ented in the Q operations an mpliance wi aracterizatio to the adhere the Charact ved sample p n survey of umented in perform a f this LTP an n activities, on procedure ization effo formed by En 01, LACBW Field Work (

Report for J ility to acq on levels.

or physical c elements o ing of LACB acterization a e field e implementi QAPP, as w nd the assoc ith these QA on are as foll ence to terization Su plan instruct the LSE pri Reference 7 a more det nd the anticip

, performed es commence ort conclude nergySolutio WR Radiolo (13) and LC June thru A quire meani In these c conditions w of the BWR are as ing well as ciated A/QC ows:

urvey ions.

ior to

7. In tailed pated d by ed on ed on ons is ogical C-RS-ugust ingful
cases, would

La Cross License T Revision allow the the decom significan by revisio 2.3.1. B During t backgrou acquired backgrou As part o backgrou LACBW Normally be repres site area Supervis appropria results.

were con Concrete is located non-impa approxim unit L40 L401210 samples a The ana backgrou can be at mean Cs 0.135 pC was 0.07 Relevant Station (Z at Zion S Zion to C geograph for distu backgrou within th categorie drainage se Boiling W Termination n 0 e survey of t mmissioning nt additiona on or addend

Background

the initial ch und study fo from vario und study is of the 2014 und levels a WR fell within y, backgroun sentative. H was chosen.

or selected a ate for obtain Although th nsidered unaf e samples an d north of th acted survey mately 100 s 12108. Soil 08 were also are provided lysis of the und study fo ttributed to g

-137 concen Ci/g with a m 0 resulting i t to LACBW ZNPS) titled Station (15).

Cs-137 leve hically simila urbed soils a und Cs-137 he expected es of soil in and non-dra Water Reactor Plan hese survey g process, in l characteriz dum as a par Study haracterizati or soils at LA ous location summarized characteriza at LACBWR n nominal ex nd reference However, no

. The Energ an area outs ning backgro he selected s ffected by pa nd direct me he LSE. A y unit L4012 quare meter l samples fro evaluated f d in sections e backgroun or soils. The global fallou ntration of s maximum ob in the upper WR is a study d ZionSolutio This docum ls anticipate ar. The docu as well as u levels for th range of d the non-im ainage, distu r

units. Solu ncluding foll zation data i rt of the requ on survey p ACBWR. R ns outside o d in Table 2-ation effort, R. The pur xpected leve areas shoul suitable off gySolutions P side of the L ound measu sample locat ast LACBW asurements sphalt samp 2106. Surfa rs of undistu om non-imp for use as ba 2.3.3 and 2.

nd soil sam e results did ut. For the t surface samp bserved con r range for th y performed ons TSD 13 ment was pr ed from wor ument predic undisturbed he site speci disturbed so mpacted area urbed and un 2-21 tions intends lowing the s is obtained, uired 2 year performed in Reference 7 of the owne

5.

EnergySolu rpose of the els for soils, d be reasona f-site locatio Project Heal LSE but on rements bas tions were i WR operation were taken ples and dire ace soil samp urbed non-dr pacted survey ackground re

.3.5.3.

mples in 201 d report Cs-1 two backgrou ples taken o ncentration o his data set a for the deco

-004, Exami repared to co rldwide fall cted ranges f soils and is fic backgrou ils in non-d s at LACBW ndisturbed so s to continue submittal of this chapter update of th n October 2 states that a er controlled utions perfor e study was concrete, an ably close to on was ident lth Physicist the licensed ed upon the inside the LA ns.

in Class 3 s ect measurem ples were ac rainage soil y units L401 eference soil 14 compare 137 at levels und studies n or around of 0.268 pCi at a 95% con ommissionin ination of Cs ompare site out. The L for backgrou presented i und studies drainage are WR, the upp oil from the e characteriz this LTP. I r of the LTP he approved 005, Dairyl a series of s d area. Th rmed a limit s to assess i nd asphalt.

o the decomm tified. Cons and the Rad d LACBWR previous ra ACBWR lic survey unit L ments were cquired from within non-12107 and o ls. Analysis ed favorably s slightly ab performed a d the site pro i/g. The st nfidence leve ng of the Zio s-137 Globa soil sample LACBWR an und concentr in Table 2-6 performed a eas. As the per 95th per Zion backgr zation throug In the case w P will be up LTP.

and perform oil samples he result of ted assessme if backgroun missioning s sequently, an diation Prote site that se diological su censed area, L3012101, w also collect m a small ar

-impacted su other areas w s results for y with the bove MDC.

at LACBWR oduced a me tandard devi el of 0.275 p on Nuclear P al Fallout in Cs-137 resu nd Zion site rations of Cs

6. The obse at LACBWR ere were va centile level round study ghout where dated med a were f this ent of nd at site to n on-ection emed urvey

, they which ted in rea of urvey within these 2005 This R, the ean of iation Ci/g.

Power Soils ults at es are s-137 erved R fall arious ls for were

La Cross License T Revision considere areas, an 2.3.2. P EnergySo Decomm decommi from the some of t less than prepared 2.3.3. N Based up 163.5 acr impacted contamin operation ISFSI w operation physical for comp for the cl The non-segregate inside of Highway study for within su in coal f ISFSI fac From Oc impacted survey un and the i impacted To supp objective open land by perfor The 2015 primary surveys a se Boiling W Termination n 0 ed appropria d Class 2 an Potential Ra olutions TS issioning (

issioning of sampling o the theoretic n 2 years, an

. The list of Non-Impacte pon the infor re licensed

d. The n nation given ns. The det were not imp ns (i.e., with characterist pliance beyo lassification.

-impacted op ed into five f survey uni y 35. This s r soils. The urvey unit L4 from the G-cility, which ctober 2014 d open land nits and wer initial result d as it was d ort this con e of the add d survey uni rming additi 5 characteriz objectives and samplin Water Reactor Plan ate backgro nd 3 open lan dionuclides SD RS-TD-3 (16) establi LACBWR.

of various m cal neutron a n initial suite f potential ra ed Open La rmation com site surroun non-impacte that historic termination pacted by l hin the LSE ics. The are ond the chara pen land are survey unit it L4012108 survey unit non-impacte 4012103. A

-3 station an h has not bee to August areas of th re characteri s of the 201 determined t nclusion, ad itional chara its given an i onal soil sam zation camp of the addi ng to suppor r

ound concen nd area surve s of Concern 313196-001, shes the ba Industry gu media from p activation pro e of potentia adionuclides and Areas mpiled in the nding the L d areas ha cal informati that the con licensed ope

), site use, t eas designat acterization a is approxim ts. Non-imp 8 in a veget was formed ed survey un A majority of nd survey un en characteriz 2015, char he site. The ized as such 14 characteri that there is dditional ch acterization initial Class mpling and g aign was de tional chara rt the non-2-22 ntration leve ey units at L n

, Radionuc asis for an uidance was past plant o oducts, nobl al ROC for is listed in T e HSA, a lar LSE and IS ave no rea ion provides ntiguous ope erations was topography, ted as non-im surveys and mately 352,3 pacted open ated area w d during cha nits are show f the surface nit L401210 zed and is no racterization e survey uni h in Referenc ization, thes no reasonab haracterizatio surveys per 3 classificat gamma walk esigned in ac acterization

-impacted c els for the LACBWR.

clides of C initial suite reviewed as operations.

le gases and the decomm Table 2-7.

rge portion o SFSI receive asonable po s no indicatio en land area s based on site dischar mpacted are d sampling p 360 square m n land surve with minimal aracterizatio wn in Figure area in surv 06 complete ot addressed surveys w its were ori ce 13. Base se survey un ble potentia on was perf rformed in 2 tion for re-cl kover survey ccordance w was to per classification evaluation Concern D e of potenti s well as the Based on th radionuclide missioning o of the open ed a classif otential to on of impact as surroundi the locatio rge pathway e not require performed to meters in siz ey unit L40 l ground dis on to facilita 2-1. The G vey unit L40 ely surround d by this LTP were perform iginally clas ed upon a rev nits were rec al for residua formed in 2 2015 was to lassification ys.

with Referenc rform suffic n and to pr of non-imp uring LAC ial ROC fo analytical re he eliminatio es with a hal f LACBWR land areas o fication as contain res t from LACB ing the LSE on(s) of lice ys, and othe ed to be surv o provide a ze. This area 12109 is lo sturbance ea ate a backgr G-3 station re 012105 is cov ds the LACB P.

med in the ssified as Cl view of the classified as al contamina 2015. A m o evaluate ce n as non-imp ce 4. One o cient radiolo rovide reaso pacted CBWR or the esults on of lf-life R was on the non-sidual BWR E and ensed er site veyed basis a was ocated ast of round esides vered BWR non-lass 3 HSA non-ation.

major ertain pacted of the ogical nable

La Cross License T Revision assurance 2015 cha based on During th units L40 logger w was scan Gamma s or gravel Minimum evaluated survey un an Explo were due Thirty-tw toward d shown in instrumen positively surface s These va in section specific b in the gr were very Seventee meter.

concentra derived g average maximum backgrou 137 conc surface s the Hwy Two asp survey un were less identified A summ presented se Boiling W Termination n 0 e that the n aracterization a random d he 2015 cha 012103, L40 with a 2 by 2 nned due to surface scan

l. Alarm se m Detectabl d during the nit L401210 oranium GR-e to the prese wo surface s discolored ar n Figure 2-5 nt MDC in y identified soil samples alues are wit n 2.3.1. On background rounds east y close at 0.

en subsurfac Of the 17 ations greate gamma-emit Cs-137 conc m observed und range fo centrations th soil backgrou 35/Railroad phalt sample nits. The asp s than the M d by gamma ary of the g d in Table 2-Water Reactor Plan non-impacted n survey foc esign to ensu aracterizatio 012105, L40 2 NaI detec inaccessibili nning focused et-points for e Count Ra e performan 7 and one in

-135. The ence of natur soil samples eas or areas

5. Cs-137 26 of the 32 by gamma s was 0.131 hin the expe ly one Cs-13 data set. Th of Highway 135 pCi/g an e soil sampl 7 subsurface er than the tting radionu centration ob concentrati r Cs-137 as hat exceede und. This s d Right of W es were coll phalt surface MDC of 1,93 spectroscop gamma spect

-8.

r d survey uni cused primar ure an unbia n survey, a 012106 and ctor. In surv ity from the d on undistu r the instrum ate (MDCR) nce of the g n survey unit results of th ral backgrou s were colle where the g was positiv 2 samples.

spectroscopy pCi/g with ected backgr 37 result exc his sample w y 35. The m nd 0.131 pC les were tak e soil samp instrument uclides were bserved in t ion of 0.40 discussed in d the maxim sample was t Way Grounds lected from e was first sc 38 dpm/100c py in any of t troscopy resu 2-23 its do not c rily on soils ased survey.

minimum o L4012108 vey unit L40 e presence o urbed soils w ment were s

) of the ins gamma scan t L4012108.

he investiga und activity.

ected from ground had b vely identif No other po

y. The avera a maximum round range ceeded the m was the maxi mean of the n i/g, respectiv ken at random ples taken, MDC in ei e positively i the subsurfa 09 pCi/g. Th n section 2.3 mum Cs-137 the maximu random loc canned with cm2. No pla the asphalt s ults for each contain plant and asphalt of 1% of the was scanned 012107, less f tall, thick with minimal set at the ob strument. A n, one in su All scan al ation indicat non-impacte been disturbe fied in conc otential plan age Cs-137 c m observed c for Cs-137 maxium resu imum 0.463 non-impacte vely.

mly selected Cs-137 w ght samples identified by ace soil sam hese value 3.1. Only on 7 concentrati um 0.409 pC cations in p h a beta-gamm ant derived r samples.

h non-impac t-derived ra

t. The samp e surface so d with a Mo s than 1% of vegetation a l vegetation bserved back A total of f urvey unit L larms were in ted the elev ed areas at ed. The sam centrations nt-derived ra concentratio concentration surface sam ult of 0.268 pCi/g value ed and site-s d locations t was positive
s. No other y gamma sp mples was 0.

es are with ne subsurfac ion found in Ci/g value th paved areas mma detector radionuclide cted open la adioactivity.

ple locations oil area in su odel 2350-1 f the surface and steep te or disturbed kground plu four alarms L4012106, tw nvestigated u vated scan re locations b mple location greater than adionuclides n observed i n of 0.463 p mples as discu pCi/g in the e and was lo specific data to a depth o ely identifie r potential p pectroscopy.

087 pCi/g w hin the exp e sample ha n the site-spe at was locat in non-imp

. All scan re s were posit and survey u The were urvey data e area rrain.

d soils us the were wo in using esults biased ns are n the were in the pCi/g.

ussed e site-ocated a sets of one ed in plant-The with a pected d Cs-ecific ted in pacted esults tively unit is

La Cross License T Revision A coal as samples The resul The lab concentra also posi concentra considere of the pl radionuc positive ratios ar compared higher th operation consisten the spora derived r In survey gamma s area to d approxim uranium readings 2.3.4. Im The HSA operation been clas been iden into two north of Highway three Cla The char prepared employed radionuc of suffici surface a obtained Survey contamin se Boiling W Termination n 0 sh sample fr were sent to lts of the ana boratory an ations excee tively detect ations of the ed to very li lant-derived lide mixtur results for C re 118 and d to the site han expected nal history, t nt with natur adic positive radionuclide y unit L4012 spectroscopy determine if mately 7,000 and thorium conducted d mpacted Op A identified ns. The app ssified as C ntified as i Class 2 surv the LSE, th y 35 and the ass 3 survey racterization for each s d to determ lide concent ient quantity and subsurf from below techniques nation identi Water Reactor Plan rom survey u o Test Ame alysis are pre nalysis spor eding the MD ted but at lev e positively i ikely be the radionuclid re fractions Cs-137, Sr-16, respect e-specific mi d by factors the radionuc ral backgrou analytical r s in these su 2108, a repr

y. In additio f there is a 0 to 8,000 cp m series nuc during the w pen Land A d the open proximate are Class 1. An impacted b vey units. T he transmiss e haul road u units combin of the impac survey unit ine the later trations in th y and quality face soils in w the structur were empl ified and th r

unit L40121 erica Labora esented in T radically id DC, includin vels that are identified rad result of cou des. This c

. For exam 90 and Fe-5 tively. Wh ixture fracti s of 4,800 a lide ratios, a und and com esults are ve urvey units.

resentative s on, gamma s significant pm). The a clides with alkover surv Areas land area ea is 1.5 acr approximat y reactor op Three impact sion switchy used to tran ned is appro cted open la in accorda ral and vert he soil. Char y to quantify n each open res due to int loyed to de he radionucl 2-24 05, six surfa atories for g Table 2-9.

dentified se ng H-3, C-14 consistent w dionuclides w unting uncer conclusion w mple, samp

55. Howev hen the rati ons in Chap and 10,700, and primarily mprise 88% o ery unlikely sample of th scan reading difference analysis of t no plant de vey averaged inside the res. All ope tely 3.46 acr perations. T ted Class 3 s yard and the nsport dry fu oximately 16 and areas beg ance with R ical extent o racterization the potentia n land surve terferences a etermine th lide concent face soil sam gamma spect everal plan 4, Fe-55, Ni with natural b were close t rtainty as op was supporte le L301210 ver, the Sr-9 ios from L3 pter 6, Table respectivel y the concen of the site-sp to represent he rail road gs were take from site b the railroad erived radio d 7,000-8,50 fenced LSE en land surve re area that This open la survey units e area encom uel casks to 6.5 acres.

gan in Octob Reference 4 of any cont n inspections al volumetric ey unit. Li and inaccess he lateral a trations in t mples and fiv troscopy and nt-derived r i-63, and Sr-background to the detecti pposed to th ed by a rev 05-CR-GS-0 90/Cs-137 an 3012105-CR e 6-3, it is s ly. In conc ntrations of C pecific radio t the actual p bed gravel en of the rail background bed gravel onuclides. T 00 cpm.

E as impac ey units insi surrounds t and area has were design mpassing th the ISFSI.

ber 2014. A

4. Survey amination id s and surveys c contaminat imited soil ibility.

and vertical the soil. A ve subsurfac d HTD anal radionuclide

-90. Cs-137

. In all case ion limits an e actual pres view of exp 002-SS indi nd Fe-55/Cs R-GS-002-SS een that the clusion, base Cs-137 whic onuclide mix presence of p was analyze l road bed g (which aver indicated na The gamma cted by re ide the LSE the LSE has been segre nated for the he site acces The area o A sample plan techniques dentified an s were perfo tion of acces information l extent of A combinatio e soil lyses.

es at 7 was es, the nd are sence pected icates s-137 S are ey are ed on ch are

xture, plant-ed by gravel raged atural scan eactor have s also gated e area ss off of the n was were nd the ormed ssible n was f any on of

La Cross License T Revision random a survey p professio Protectio radioactiv spill loca survey lo not requ locations radiologi A surface surface s or surfac were take intervals Each sur site radio necessary All surfa Several s full isoto survey un 2.3.4.1.

There are The Clas area in th Reactor radioactiv areas, pre Twenty-t measurab locations taken in taken, C samples 13 sampl identified the surf 0.287 pC samples w Seventy-one mete se Boiling W Termination n 0 and biased s ackage. The onal judgme on Supervis vity, depres ations, or ar ocations was uired for soi s were selec ical contamin e soil sample oil samples ce scans indi en from 0.15 rface soil, co ological lab y to achieve ace and sub soil samples opic analysis nit per Refe Class e four (4) op ss 1 open lan he Class 1 op Building, th vely contam evented the a two (22) sur ble radioact s, or areas w Class 1 open Co-60 was p and Cs-137 les. No oth d by gamma face soil sa Ci/g. The a was 0.096 p nine (79) su er, two (2) lo Water Reactor Plan urvey locati e locations o ent of the E or. Consi sions, disco reas where t s also determ ils in an op cted on asp nation.

e was taken were acquir icated elevat 5 cm to dept omposite sub oratory by e an isotopic surface com were selecte s (HTD radi erence 4.

1 Open Lan pen land sur nd survey un pen land sur he Turbine minated build ability to per rface soil sam tivity, disco where the gro n land surve positively id 7 was posit her potentia spectroscop amples was verage Cs-1 Ci/g with a m ubsurface so ocations bias r

ions were es of biased me EnergySoluti deration wa lored areas, the ground h mined by are pen land are phalt in Cla at each sele red at severa ted activity.

ths ranging f bsurface soil gamma-spec c MDC equa mposite samp ed at random ionuclides).

nd Areas rvey units cl nits are show rvey units is Building, th ding and sys rform surfac mples were lored areas, ound had be ey units are s dentified in tively ident al plant-deriv py. The aver s 0.058 pCi/

137 concent maximum ob il samples w sed to areas o 2-25 stablished in easurements ions Project as given to low point g had been di ea classificat eas designat ass 1 survey cted biased a al random lo Depending from 1 to 3 m l sample or ctroscopy.

al to or less ples were an m and were s Duplicate lassified as wn in Figure obstructed b he WTB and stems, as we ce scanning d taken at loc

, buried pip een disturbed shown in Fig concentrati tified in con ved gamma rage Co-60 c

/g with a tration obser bserved conc were taken a on the south each survey s and/or sam Health Phy o locations gravity drain isturbed. Th tion. Rando ated as Clas y units whe and random cations or if on the loca m below gra asphalt sam Analysis co s than 0.10 p nalyzed afte shipped to T samples and Class 1 at L 2-1. A sign by the prese d the LSA ell as stored due to high b cations biase pe locations

d. The loca gure 2-6. O ions greater ncentrations a-emitting ra concentratio maximum rved in the centration o at 10 surface and west sid y unit in acc mples were d ysicist and that exhib n areas, actu he number m-based me ss 1. Rando ere there wa

-based surve f surface soi ation, subsur ade and com mple was ana ount times w pCi/g for Cs er drying th Test America d concrete w LACBWR to nificant porti ence of build Building.

radioactive background.

ed toward sit s, actual an ations of surf Of the 22 sur r than the M s greater th adionuclides on observed observed c analysis of f 1.07 pCi/g e soil locatio de of the WG cordance wit determined b the Radiolo bited measu ual and pote of random-b easurements om measure as no histor ey location.

l sample ana face soil sam mposited ove alyzed by th were adjuste s-137 and C he sample m a Laboratorie were collecte otaling 8,443 ion of the su dings, namel The presen material in tes that exhi nd potential face soil sam face soil sam MDC in tw han the MD s were posit in the analy concentratio f the surface

g.

ons to a dep GTV and fiv th the by the ogical urable ential based were ement ry of Sub-alysis mples r 1 m he on-ed as Co-60.

media.

es for ed by 3 m2.

urface ly the ce of these ibited spill mples mples wo (2)

DC in tively sis of on of e soil pth of ve (5)

La Cross License T Revision locations The sam evaluate Building samples 15 sampl identified of the su 0.161 pC areas is foundatio decommi Ten sam asphalt w this surv results ra measurem identified 0.057 pC A summ presented Nine sur samples gamma s In additi detected One sedi unit L10 and HTD 0.136 pC 2.3.4.2.

The imp immediat two surv LACBW these two Approxim 2350-1 d Alarm se instrumen se Boiling W Termination n 0 s that access mples at the t the subsurfa were taken taken, Cs-1 les. No oth d by gamma ubsurface so Ci/g. The ass not current ons and surr issioning pro mples were ta was taken fro vey unit. Th anging from ment of 3,09 d in concen Ci/g.

ary of the fi d in Table 2-rface soil sa taken from spectroscopy on to detect at concentra iment sampl 10103. This D analyses.

Ci/g.

Class acted Class te area surro ey units. Th WR Crib Hou o survey unit mately 1% o data logger w et-points for nt. No scan Water Reactor Plan ed the soils two WGTV ace soils alon and compo 137 was pos her potentia a spectroscop oil samples sessment of tly complete rounding bu ocess, when aken of asp om the same he asphalt s the instrume 95 dpm/100 ntrations gre indings of th

-10.

amples, 11 s Class 1 open y and HTD a ting Co-60 ations greate le was taken s sample wa Co-60 and 2 Open Lan 2 open lan ounding the hese are sho use, the G-3 ts.

of the surfac with a 2 by the instrum alarms were r

under the T V locations w ngside and u sited at dept sitively iden al plant-deriv py. The ave was 0.055 p potential su

e. Soil in uried structu access will b phalt from p e location se surface was ent MDC of cm2. Of th eater than he survey fo subsurface s n land surve analyses. Th and Cs-137 r than the in n from the s as also sent t C-137 were nd Areas nd areas tota LSE. The C own in Figur 3 Crib Hous ce soil area i y 2 NaI de ment were set e observed.

2-26 urbine Build were acquire underneath th ths of 10, 15 ntified in co ved gamma erage Cs-13 pCi/g with ubsurface soi difficult to ures and pip be more read paved areas lected for th first scanne f 2,771 dpm/

he 10 asphal MDC in on or each indiv soil samples ey units wer he results of

, H-3, C-14 nstrument MD sanitary solid to Test Amer e detected in al approxim Class 2 impa re 2-1. The se and the L in survey un etector. Thi t at the obse ding through ed to a dept he vault. Th 5 and 20 fee oncentration a-emitting ra 7 concentrat a maximum il contamina o access are ping has bee dily availabl in Class 1 s he surface an ed with beta

/100cm2 to a lt samples t nly one sam vidual Class s, one concr re sent to Te f the analysis 4, Fe-55 and DC.

ds tank that rica Laborat n this sampl mately 13,99 acted open l LACBWR LACBWR w nit L201110 is area inclu erved backgr h angled Geo th of five m he samples u et. Of the 7 ns greater th adionuclides tion observe m observed ation in the C eas such as en deferred le.

survey unit nd subsurfac a-gamma de a maximum taken, Cs-13 mple at a s 1 open land rete sample est America s are present d Ni-63 wer is located i tory for gam e, both at a 6 m2 and ar and area wa Administrat warehouses a 1 was scann uded asphalt round plus t oprobe samp meters in ord under the Tu 79 subsurface han the MD s were posit ed in the ana concentratio Class 1 open s under bui until later i L1010104.

ce soil sampl etector with of observed 37 was posit concentratio d survey un and two as a Laboratorie ted in Table re also posit in Class 1 su mma spectros concentrati re located in as segregated tion Building are all locat ned with a M t paved surf the MDCR o pling.

der to urbine e soil DC in tively alysis on of n land ilding n the The les in scan d scan tively on of nit are sphalt es for 2-11.

tively urvey scopy on of n the d into g, the ted in Model faces.

of the

La Cross License T Revision Twenty-t measurab locations taken in taken, Cs other pot The aver 0.077 pC Twenty-t and three resides in Of the 2 greater th than MD identified of 0.112 samples assessme currently surround process, w Twelve s selected results r 2,748 dpm concentra concentra observed A summ presented Three sur samples Administ HTD ana Co-60 a concentra HTD rad 2.3.4.3.

The impa land area Figure 2-site, the t se Boiling W Termination n 0 three surfac ble radioact s, or areas w Class 2 open s-137 was p tential plant rage Cs-137 Ci/g with a m three subsur e locations b n survey uni 23 subsurfac han MDC in DC in four d by gamma pCi/g. The was 0.043 ent of poten y complete.

ding buried s when access samples were randomly.

ranging fro m/100cm2.

ations great ation observ d concentrati ary of the fi d in Table 2-rface soil sa taken from tration Build alyses. The and Cs-137, ations greate dionuclides e Class acted Class 3 a was segre

-1. The Cla transmission Water Reactor Plan e soil samp tivity, disco where the gro n land surve positively ide t-derived rad 7 concentrat maximum obs face soil sam biased to are it L2011101 ce soil samp n one sample samples. N spectroscop average Cs-pCi/g with ntial subsurf Soil in dif structures an s will be mor e taken of as The asphalt om the ins Of the 12 ter than the ved in the an on of 0.055 indings of th

-12.

amples, five m an acces ding were se results of th H-3, C-14 er than MD exceeding M 3 Open Lan 3 open land egated into ass 3 impacte n switchyard r

ples were tak lored areas, ound had be ey units are s entified at co dionuclides tion observe served conce mples were t eas alongsid

1. The biase ples taken, e and Cs-13 No other po py. The sing

-137 concent h a maximu face soil con fficult to ac nd piping ha re readily av sphalt from p t surface wa strument M 2 asphalt sa e instrumen nalysis of the pCi/g.

he survey fo subsurface s ssible storm ent to Test he analysis a 4, Fe-55 an DC. As disc MDC are likel nd Areas areas total a three surve ed open land for the LAC 2-27 ken at locat

, buried pip een disturbed shown in Fig oncentration were positiv ed in the an entration of taken at 14 r de and under ed samples w Co-60 was 7 was positi otential plan gle sample w tration obser um observe ntamination cess areas s as been defe vailable.

paved areas s first scann MDC of 2, mples taken nt MDC in e asphalt sam or each indiv soil samples, m sewer ba America La are presented nd Cm-243/

cussed in se ly to be false approximatel ey units. T d survey un CBWR and G tions biased pe locations

d. The loca gure 2-7. O ns greater th vely identifi nalysis of th 0.200 pCi/g random loca rneath the S were acquire positively ively identif nt-derived ra with detectab rved in the a d concentra n in the Cla such as und erred until l in Class 2 su ned with bet

,529 dpm/10 n, Cs-137 w three samp mples was 0 vidual Class

, three aspha asin manhol aboratories f d in Table 2

/244 were ection 2.3.3 e positives.

ly 66,765m2 The Class 3 nits include t G-3 facilitie d toward sit s, actual an ations of surf Of the 23 sur han MDC in ied by gamm he surface s

g.

ations to a de Storm Sewer ed to a dept identified a fied at conce adionuclides ble Co-60 ha analysis of th ation of 0.0 ass 2 open l der building ater in the d urvey units.

ta-gamma de 00cm2 to a was positive ples. The 0.049 pCi/g s 2 open land alt samples a le located for gamma s

-13. In add also positiv for non-imp

2. The Class survey uni the north en s, the LACB es that exhi nd potential face soil sam face soil sam 14 samples ma spectrosc soil samples epth of one m r Water pipe th of five m at concentra entrations gr s were posit ad a concentr he subsurfac 088 pCi/g.

land areas i foundations decommissio The asphal etector with a maximum ely identifie average Cs with a maxi d survey un and two sedi in front of spectroscopy dition to dete vely detecte pacted areas 3 impacted its are show nd of the lice BWR plant a ibited spill mples mples

. No copy.

s was meter e that meters.

ations reater tively ration e soil The s not s and oning lt was h scan m of ed in s-137 imum nit are iment f the y and ecting ed at s, the open wn in ensed access

La Cross License T Revision and right was deem LACBW Crib Hou facility d were dee These ar Solutions A minim scanned was excl focused o points fo No scan Thirty-tw where th open lan was posi plant-der The aver 0.131 pC Seventee meter.

concentra radionuc concentra maximum Two sam selected results w were pos A summ presented As part o of concre Crib Hou Administ survey un Three co L301210 three sur Laborato se Boiling W Termination n 0 t-of-way are med impacte WR Administ use). The tr during operat emed as imp reas were c s maintains t mum of 1%

with a Mod luded from on undisturb r the instrum alarms were wo surface so he ground ha d survey un tively identi rived gamma rage Cs-137 Ci/g with a m en subsurfac Of the 17 ations grea lides were ation observ m observed c mples were t randomly.

were less tha sitively ident ary of the fi d in Table 2-of the charac ete located i use. In addi tration Build nit L301210 oncrete samp 01, the two se rface soil s ories for gam Water Reactor Plan a and the ha ed by LACB tration Build ransmission tions. The p pacted by th onservativel that classifyi of the surf el 2350-1 da gamma sur bed soils wi ment were se e observed in oil samples ad been dist nits are show ified in conc a-emitting ra 7 concentrat maximum obs e soil sampl 7 subsurface ater than M positively ved in the a concentratio aken of asph The asphalt an instrumen tified by gam indings of th

-14.

cterization of in the north ition, a sam ding and tw

9. These sam ples from su ediment sam samples and mma spectr r

aul road to th BWR due to ding and the yard was d plant access he transit of ly classified ing these are face soil are ata logger w rface scanni ith minimal et at the obse n these surve were taken turbed. The wn in Figure centrations g adionuclides tion observe served conce les were tak e soil samp MDC in ei identified analysis of th on of 0.409 p halt from pa surface wa nt MDC of 1 mma spectro he survey fo f survey unit h section of mple was take wo sediment mples were urvey unit L3 mples taken f d two subs roscopy and 2-28 he ISFSI fac o the presen presence of deemed as im area, Highw f packaged r d as impacte eas as non-im ea in survey with a 2 by ing for safe vegetation o erved backgr ey units.

at locations e locations o e 2-8. Of th greater than s were positi ed in the an entration of ken at random ples taken, ight samples by gamma he subsurfac pCi/g.

aved areas in s first scann 1,938 dpm/1 scopy in any or each indiv t L3012101, the survey u en from a sa t samples w sent off-site 3012101, th from the stor surface soil d HTD anal cility. The n nce of a sep f concrete fr mpacted as i way 35 right radioactive m ed. Howev mpacted wou y units L30 2 NaI dete ety reasons.

or disturbed round plus t biased tow of surface s he 32 surface MDC in 26 ively identif nalysis of th 0.463 pCi/g mly selected Cs-137 w

s. No oth spectrosco ce soil samp n Class 3 su ned with bet 100cm2. No y of these sam vidual Class

, samples we unit that ori anitary tank were taken fr e for isotopic he sanitary ta rm sewer ba samples w lyses. The north end of ptic system from impacte it was part o t-of way and material thro ver, it shou uld have bee 012101 and ector. Surve Gamma d soils or gra the MDCR o ard discolor oil samples e soil sampl samples. N fied by gamm he surface s

g.

d locations t was positive ther potenti opy. The ples was 0.0 urvey units.

ta-gamma de o plant deriv amples.

s 3 open land ere taken fro iginated from k that service from a storm c analysis.

ank sample asin in survey were sent t results of f the license that service ed structures of the LACB d ISFSI haul ough these a ld be noted en appropriat L3012109 ey unit L301 surface scan avel. Alarm of the instrum red areas or taken in Cl les taken, Cs No other pote ma spectrosc soil samples to a depth o ely identifie ial plant-de average Cs 087 pCi/g w The asphalt etector. All ved radionuc d survey un om several p m the LACB es the LACB m sewer bas from survey y unit L3012 to Test Am the analysi d site es the s (the BWR l road areas.

d that te.

were 12102 nning m set-ment.

areas lass 3 s-137 ential copy.

s was of one ed in erived s-137 with a t was l scan clides nit are pieces BWR BWR sin in y unit

2109, merica is are

La Cross License T Revision presented derived R and Ni-6 exceedin consisten 2.3.5. N Based up associate indicated A full lis

2.

The prim informati operation from the character The resu conducte traffic in The G-3 incidents results of A scan su gamma d using an was also gross bet MDC of identified gross alp contamin samples.

derived 0.061 pC that the material Direct an traffic ar Model 23 areas of i ranged f exceeded se Boiling W Termination n 0 d in Table 2 ROC at resid

63. As dis ng MDC are nt with natur Non-Impacte pon the inf ed with the G d that there w st of G-3 stru mary basis f ion documen ns. Additio e LACBWR rization of t ults are prov ed during the the major st station res s of radioact f the charact urvey was p detector. In alpha/beta-g taken at the ta-gamma a f 2,816 dpm/

d gross beta-pha activity nation was i The roof m ROC that w Ci/g. Based elevated dir on the roof.

nd removabl reas of the 360 instrume interest were from 2,540 d the MDC d Water Reactor Plan 2-15. The dual concent scussed in s likely to be ral backgroun ed Structur formation co G-3 Coal Pla was no reaso uctures that for the non nted in the H nally, the p R Stack du the LACBW vided in Re e 2015 chara tation buildin sides in non tive contam erization sur performed of addition, six gamma prop location of ctivity rangi

/100cm2. T

-gamma acti y ranging f dentified at material itse was positive on the fact t rect alpha m le contamin G-3 Coal P ent with 43-e scanned, in dpm/100cm during the co r

analysis of trations grea section 2.3.3 false positiv nd.

es ompiled in ant may be c onable poten have been d n-impacted HSA that the potential for uring opera WR Administ eference 13 acterization ngs were sur n-impacted s mination of s rveys perform f the mid-lev x (6) locatio portional dete each direct m ing from 2,3 The results o ivity ranging from 142 dp concentratio elf was samp ely identifie that no other measurements ation survey Plant. Scan

-93 detector.

ncluding floo m2 to 2,617 ourse of this 2-29 f these samp ater than the 3 for non-im ves. Cs-137 the HSA, S classified as ntial for resi designated as classificatio e G-3 structu windborne ations to s tration Build

. Addition campaign w rveyed.

survey unit soils, asphal med in the G vel roof of th ons were sele ector. A sm measuremen 302 dpm/10 of the direc g from 1,603 pm/100cm2 ons greater t pled on Jun ed by gamm r plant deriv s were due ys were perf n measureme

. Approxim ors and lowe 7 dpm/100cm s survey. Te ples positive e instrument mpacted are was also po Solutions co non-impac dual contam s non-impa on for the G ures were no migration o structure roo ding roof an nal surveys where the su L4012103.

lt or concre G-3 station a he G-3 Coal ected at rand mear sample nt. The resu 0cm2 to 2,8 ct beta-gamm 3 dpm/100cm to 258 dpm than MDC b ne 30, 2015.

ma spectros ved ROC wa most likely formed of re ents were p mately 5% of er wall surfa m2. No o en (10) locat ely identifie MDC, inclu eas, the HT ositively dete oncluded th cted. Histo mination from acted is prov G-3 station ot used for L of airborne ofs was ev nd the G-3 of the G-3 urfaces subje There are ete in this su are summariz l Plant build dom for dire for removab ults of the be 816 dpm/100 ma and alph m2 to 2,072 m/100cm2.

by the analy Cs-137 wa scopy at a as detected, to the pres epresentativ performed us f the concret aces. The av observed sca tions were ch ed several p uding H-3, F TD radionuc ected but at l hat the struc orical inform m site operat vided in Tab structures i LACBWR-re effluent rele valuated by Coal Plant structures ected to high e no docum urvey unit.

zed as follow ding using a ect measurem ble contamin eta scan iden 0cm2 with a ha measurem dpm/100cm No remov ysis of the s as the only concentratio it was concl sence of coa ve high perso sing the Lu te surfaces i verage scan M an measure hosen at ran plant-Fe-55 clides levels ctures mation tions.

ble 2-is the elated eased y the roof.

were h foot ented The ws:

beta-ments nation ntified scan ments m2 and vable smear plant on of luded al ash onnel udlum in the MDC ement

ndom,

La Cross License T Revision primarily measurem 875 dpm greater th 2.3.6. Im The deco impacted In additio accepted remain a Reactor B remainin and floo Reactor/G Turbine surfaces segregate radioactiv systems o Radiolog complian radiologi areas.

disassem remediat demolitio waste.

After com 3 feet be radioactiv use criter 2.3.6.1.

Characte consisted walls an (primaril taken fro 621 foot the 633 f samples w Piping Tu se Boiling W Termination n 0 y from the ments for g

/100cm2 for han MDC by mpacted Str ommissionin d buildings, s on, all system elevation fo and be subje Building tha ng reinforced ors of the Generator P sump and th above the ed by waste ve waste.

or structures gical surveys nce with 10 ical conditio The radiolo mbly and rem ion has ade on, the impa mmodity rem elow grade, vity and the ria.

Basem rization of d primarily o d floors of ly the Piping om the 615 elevation in foot elevatio were collect unnel. The l Water Reactor Plan main lobby gross activit beta-gamm y the analysi ructures an ng approach structures, sy ms and expo or grade at L ected to STS at will be exp d concrete w WGTV, an lant baseme he Turbine 636 foot ele classificatio No extensi s that will be s of the inter 0 CFR 20 re ons for the im ogical infor moval of syst equately red acted structu moval is com

, will be r e extent of a ment Structu the structur of the acquis the Reactor g Tunnels).

foot elevati n the Reactor on concrete f ted, six (6) in locations wh r

y area and y was less

a. No remov s of the sme nd Systems h for LACB ystems and c osed metal b LACBWR is S are the rem posed by the walls floors o nd the rem ent, the one pit. Conseq evation will on and dispo ive characte e removed pr riors of struc equirements mplementati rmation from tems and the duced radiol ures will be mplete, the s re-surveyed additional re ures Below 6 ral surfaces ition and rad r Building, In June and on concrete r Building, th floor of the P n the Reacto here the core 2-30 the mainte than the M vable contam ar samples.

BWR requir components below 3 feet the 639 foo maining rein e removal of of the WTB, mainder of foot thick p quently, all l be remedi osed of as c erization wa rior to the pe tures at LAC regarding on of contro m these su e demolition logical cond demolished tructures tha to determi emediation r 36 Foot Elev of basemen diological an WTB and July of 2015 floor and t he 630 foot Piping Tunn or Building, e samples we enance area.

MDC of 74 mination wa res the dem to a depth o below grad ot elevation.

nforced conc f the interior the remaini the Piping portion of th systems and iated, disass clean demoli as or will b erformance o CBWR are r the posting ols for the pr urveys will of impacted ditions to le d, packaged at will remai ine the con required, if a vation nts that wil nalysis of co the balance 5, a series o the concrete elevation co nels. A total three (3) in ere taken are

. The resu dpm/100cm as identified molition and of at least 3 de will also b The only st crete walls a r concrete an ing reinforce g and Vent he Chimney d componen sembled and ition debris, be performe of FRS.

routinely per g of areas rotection of provide th d structures a evels suitabl and properl in at license ncentrations any, to meet ll remain in oncrete core e of the bas f concrete co e floor and oncrete floor l of twelve (

the WTB an e shown in F ults of all d m2 for alpha at concentra d removal o feet below g be removed.

tructures tha and floors o nd steel line ed concrete tilation Tun y Foundation nts and struc d/or demoli clean salva ed of equipm rformed to en and to ide f workers in he basis for at the site. W le for contr ly disposed termination of the res t the unrestr n the end-s samples from sement struc ore samples east wall o r of the WTB

12) concrete nd three (3) i Figures 2-9.

direct a and ations of all grade.

The at will of the er, the walls

nnels, n, the ctural
ished, age or
ment, nsure entify these r the When rolled of as n, i.e.,

sidual ricted state m the ctures were n the B and e core in the

La Cross License T Revision The loca condition volumetr elevated wall sur discolora that exh condition there was radionuc The conc Test Ame ROC. In Reactor B and #002 concrete analysis positively 59, Tc-99 concrete 2.3.6.2.

A concre Turbine contamin in the T Analysis 0.106 pC 2.3.6.3.

As stated subjected graded su As repor radioactiv building located i Administ proximity laborator Characte beta-gam gross bet se Boiling W Termination n 0 ations selecte n or observ ric contamin observed co faces were ation or stan hibited the h n for concre s sufficient s lide fraction crete pucks r erica Labora n addition, Building sam 2 were also cores is pr of the conc y detected at 9, Pu-238, P core sample Turbin ete core was Building T nation event Turbine Buil of this sam Ci/g and H-3 LACB d previously d to FRS. In urvey approa rted in the H ve spills or has primaril in the build tration Build y to the LSE ry.

rization surv mma/alpha a ta-gamma/al Water Reactor Plan ed for concr ved radiolog ation of the ontact dose r used to id nding water.

highest pot ete in each s source term ns of gamma representing atory for gam the concrete mple locatio o sent for is resented in rete core sa t concentrati Pu-239/240, es is presente ne Building s obtained as Tunnel to cited in the lding and t mple indicate at 1.71 pCi/

BWR Admin y, the LACB nstead, these ach in accord HSA, there w radioactive ly been used ding that sup ding was in E, occupancy veys of the ctivity of in lpha activity r

rete core sam gical measu concrete. W rates or coun dentify poten The goal w ential of re survey unit.

in the cores emitters as w g the first 1/2 mma spectro e pucks rep ns #001, #0 sotopic analy Table 2-16.

amples inclu ions greater Pu-241, Am ed in Referen Tunnel s part of the attempt to HSA pertain the potential ed detectable

/g.

nistration Bu BWR Admin e two structu dance with M was no past contaminati d for office sp pported both nitially class y by LACBW LACBWR nterior floor were also p 2-31 mpling were urements in When possibl nt rates. In a ntial locatio was to ident epresenting This judg to achieve t well as HTD inch of conc oscopy and H presenting th 03, #005 an ysis. A sum Significan ude Ni-63, H than their re m-241 and A nce 16.

e 2014 chara evaluate ning to the d l radiologic e concentrat uilding nistration Bu ures will be MARSAME history of th ion in the LA pace and rec h LACBWR sified as a M WR personn Administrat rs surfaces a performed on biased tow ndicated the le, locations addition, vis ons of surf tify, to the e the worst gmental samp the sensitivit D radionuclid crete at each HTD analyse he concrete nd #006 and mmary of t nt HTD rad H-3 and Sr-9 espective MD Am-243. An acterization the possibl discovery of cal contamin tions of Cs-1 uilding and surveyed fo E guidance.

he use of un ACBWR A cords storage R and G-3 MARSSIM nel and the p tion Buildin and the roof n the roof, on ward location e presence were determ sual observat face contam extent possib case bound mpling appro ties required des.

h sample loc es for beta an deeper than WTB samp the analytica dionuclides i

90. The oth DC include; analysis of survey from le extent o f cracked dra nation of su 137 at 0.352 G-3 Crib H or unrestricte nsealed radio dministratio
e. An enviro operations.

Class 2 stru resence of th ng included

f. Direct m n floor tiles ns where phy of fixed a mined based tions of floo mination, suc ble, the loca ding radiolo ach also en d to determin cation was se nd alpha em n 1/2 inch de le locations al results fo identified by her radionuc C-14, Fe-55 the results o m the floor o of a radioa ain system p urrounding 2 pCi/g, Co-House will n ed release us oactive mate on Building.

onmental lab The LACB ucture due t he environm a scan for measurement and around ysical and/or upon or and ch as ations ogical sured ne the ent to mitting eep at

  1. 001 or the y the clides 5, Ni-of the of the active piping soils.

-60 at not be sing a

erials, The b was BWR to its mental gross ts for floor

La Cross License T Revision drain ope each dire The resu 4,915 dpm the secon imbedded gamma s was then and seco from less and dire observed Beta sc 2,261 dpm from less Direct be of 243 d measurem identified 2.3.7. S Section 8 hydrogeo was deri Haley &

(18) supp 2.3.7.1.

For a di towns an river wat

Lansing, water fo approxim The LAC well at th state perm LACBW Building areas are to the gr pathway se Boiling W Termination n 0 enings. A sm ect measurem ults of the m/100cm2 w nd floor ha d in a floor spectroscopy n performed ond floor lam s than MDC ct alpha re d reading of 7 cans of th m/100cm2 w s than MDC eta-gamma m dpm/100cm2 ments were d concentrati urface and 8.5 in Chap ology and hy ived directly Aldrich, Hy plements the Area Grou stance of 40 nd cities alon ter for indus Iowa, about or industria mately 40 mi CBWR site he site. Sani mitted sanit WR Adminis

. Storm wa e periodically round area su after passing Water Reactor Plan mear sample ment.

beta scans with a scan M allway, a di tile. The c

y. The analy involving th minated woo of 329 dpm adings rang 72 dpm/100c he roof are with a scan M C of 113 dpm measurement to a maxim all less than ions greater Groundwat pter 8 of t ydrology of y from Hal ydrogeologic e preliminary undwater Us 0 miles dow ng the Missis strial purpos t 15 miles d al purposes les downstre has its own itary wastes tary wastes h tration Buil ater runoff is y monitored urrounding t g through an r

e for remova of the int MDC of 2,10 screte radio contaminated ysis of the ti he acquisitio od, carpet, a m/100cm2 to ged from le cm2.

ea indicate MDC of 2,26 m/100cm2 to ts taken on t mum observ n MDC of 4 than MDC b ter his LTP c ZNPS and e ey & Aldri cal Investiga y findings in se wnstream of ssippi River ses, excludin downstream o between t eam.

potable wa are collecte hauler. Thi lding and a s diverted di d for oil shee the facility v n oil separato 2-32 able contam terior surfac 00 dpm/100c oactive parti d portion of ile identified n of ten (10) and floor til a maximum ess than MD ed results 61 dpm/100c o a maximum the floor dra ved reading 42 dpm/100c by the analy ontains a s environs. T ich, Hydrog ation Report n Reference 1 the site, vir are obtained ng the adjac of the site.

the LACBW ater supply, p d in a solids is includes a a sanitary h irectly to th en and disco via downspo or located in mination was ces ranged cm2. During icle was dis f the tile wa d 0.005 uCi

) biased dire le. Direct b m observed re DC of 39 d ranging fr cm2. Direct m observed ain openings g of 333 dp cm2. No re sis of the sm summary d The informat geological C t for the LaC

17.

rtually all m d from groun cent G-3 pla There are n WR site an provided thr s holding tan a sanitary ho holding tank he Mississipp oloration. R outs or ente nside the LSE also taken from 1,420 g the scan of scovered. T as removed of Cs-137.

ect measurem beta-gamma eading of 5, dpm/100cm2 rom 1,872 t alpha meas reading of 1 s ranged from pm/100cm2 a emovable co mear samples description tion containe Conceptual S Crosse Boilin municipal w und water. T ant, is the co no other know nd Prairie rough a sing nk and pump olding tank k that servi pi River at o Roof drains d r the norma E.

at the locati 0 dpm/100cm f the north e The particle and analyze An investig ments on the readings ra

,743 dpm/10 to a maxi dpm/100cm surements ra 152 dpm/100 m less than M and direct ontamination

s.

of the geo ed in this se Site Model ng Water Re water supplie The nearest u oal-fired pla wn users of du Chien, gle ground w ped off by a that service ices the Tu outfalls. Re discharge dir al effluent re on of m2 to end of e was ed by gation e first anged 00cm2 imum m2 to anged 0cm2.

MDC alpha n was

ology, ection (17).

eactor es for use of ant in f river WI, water local es the urbine elease rectly elease

La Cross License T Revision 2.3.7.2.

Regional Mississip parallels upward; river stag demonstr river stag Groundw surface (

Groundw the Missi may turn chemical the shallo Based on of the G-located i monitorin a slightly has a do gradient towards t there are stages. G Reactor B are below During p was com permeabi buildings soils will will circ localized outside th other han or buried underlyin shallow s contamin soils with orders of se Boiling W Termination n 0 Groundw lly, groundw ppi river. C the river. U however, th ge data comp rates that the ge impacts th water beneath bgs) and the water in the s issippi Rive n and flow l constituent ow system.

n a review of

-3 Ash Land in the sout ng wells (B1 y downward ownward gr at well pair the river bas e some perio Groundwater Building ba w the water t plant constru mpacted, redu ility can dec

s. The resul l flow at a s cumnavigate d flow regim he footprint nd, potential d piling, will ng groundw soils from p nation. The hin the supp f magnitude Water Reactor Plan ater Flow water flows i Closer to th Under typic he vertical gr pared to wa e shallow aq he water tabl h the site is e groundwat shallow depo
r. The deep parallel to s would occu f the ground dfill area grou th side of t 11AR/B11R vertical gra radient at w B9/B9A. T sin with a lo ods where t r flow throu sement shel table during uction, and m ucing the eff crease the h lting impact slower veloc the area, e mes on contam of these str l releases tha l likely take water. This precipitation, average sha port pilings, lower.

r in a westerl he shore, gr al river stag radient rever ter table ele quifer is in di le elevation.

first encoun ter is in dire osits and fill per groundw the river.

ur at or near dwater elevat undwater mo the LACBW

) to the east adient. Durin well pairs B This is expec ocalized influ the gradients ugh the LAC l) as well as high and low more specifi fective poros hydraulic con to groundw city, and reg effectively b minant fate a ructures will at occurred w much longe is further c

, creating an allow aquifer the hydraul 2-33 ly direction roundwater ge, groundw rses during f evations mea irect hydrau ntered at an ect hydraulic l material flo water is also Because th r the surface tion measure onitoring we WR site, an of and up gr ng times of n B11R/B11AR cted as grou uence at B9/

s are revers CBWR site is s the deep p w river stage ically the ins sity and perm nductivity o water flow is gionally, a si bypassing th and transpor l likely be d within the fo er to migrate compounded n area that w r hydraulic c ic conductiv from the bl may also h water gradien flood stages.

asure in LAC ulic commun n average de c communica ows towards likely to flo he potential

, the release ements colle ells (# B2/B3 nd associate radient of LA normal and R and B2/B undwater flo

/B9A from t sed; and this s impacted b pilings that s e conditions.

stallation of meability of of the aquife s that ground ignificant pe these soils.

rt are that po deflected and ootprint of th e both in th d as the ove will likely re conductivity vity would b luffs on the have a flow nts near the

. The geolog CBWR site nication with epth of 20 fe ation with th s the west an ow towards t l releases of s would like ected during 3/B9A/B9/B ed backgrou ACBWR, th low river sta B3, with an ows generally the adjacent s is likely d by deeper st support the f the support f the soils. T er within the dwater withi ercentage of The impli otential relea d flow aroun he buildings e vadose zo erlying struc etain any po y is 313 feet be expected east toward component river are sli gical and his monitoring h the river an eet below gr he adjacent nd discharges the west but f radiologic ely be confin routine sam B7/B8), whic und groundw here appears age, groundw upward ve y from the b t inlet. How due to high tructures (i.e structures, w t pilings, the This reducti e footprint o in the comp f the flow re ications of ases that occ nd them. O s, via floor d one as well a ctures isolat tentially rele per day. Fo to be one to ds the t that ightly storic wells nd the round river.

s into t then cal or ned to mpling ch are water to be water ertical bluffs

wever, river e., the which e soil ion in of the pacted egime these curred On the drains as the te the eased or the o two

La Cross License T Revision The velo gradient.

across th Therefor the inch Environm show sea stage. Th LACBW vicinity structure direction 2.3.7.3.

Historica monitorin monitorin monitorin Dairylan Of the w LACBW routine b designate Environm G-3 Foss Nos. 3, 4 levels re 3.0E-08 µ During th to the s radioactiv The well suspected that samp As note Activities wells to monitorin if ground located n interval o below gr B.

se Boiling W Termination n 0 ocity of gro The gradie he site, groun e, it is likely hes and fee mental Moni asonal varia hese wells a WR site struct of suspect s/foundation ns.

Previous I ally, the LAC ng wells. F ng wells loc ng wells of d for radiolo wells shown WR facilities basis. The gr ed as B-2, mental Moni sil Station op 4 and 5 wer ported durin

µCi/ml to 9.

he recovery outh of the ve liquids fr l-point show d leakage. T ple are prese d in the L s Report (D support gro ng wells (10 dwater qual nominally wi of 15 to 25 f rade. These Water Reactor Plan oundwater is ent of the wa ndwater mon y that the gro et/day rang itoring Prog ation on upw are not suffic tures or area broken dra ns or variati Investigation CBWR Lice igure 2-11 i cated on th ff the LACB ogical purpo n on Figure were histor roundwater m B-3, B-7, itoring staff perational re re routinely ng this mon 0E-08 µCi/m of a probab e Turbine B rom suspect wn on Figure The well-po ented in Tabl LACBWR D D-Plan/PSDA oundwater e 0 wells total) ity had bee ithin five (5) feet below g wells are sh r

s directly r ater table is i nitoring has oundwater v e). Ground gram wells a ward and do cient to char as where pote ain lines) co ions in fill m ns ensed Site ha llustrates the e LACBWR BWR site t ses.

2-11, only P rically monit monitoring w B-8, B-9, on a routine equirements.

monitored f nitoring peri ml).

le spill incid Building. T broken drain 2-11 was es int was sam le 2-17. Thi Decommissio AR) (19), D evaluation.

) were instal en impacted

) feet of one grade and on how on Figu 2-34 elated to bo nfluenced by shown that velocity acro water eleva agree with t ownward gra racterize the ential releas ould have o materials co as had sever e current loc R site. The that are or Potable Wa tored by Da wells and ba B-9A, B11A e basis for no During LA for gross be iod was less dent in 1983 This inciden n lines in th stablished do mpled once o is well-point oning Plan airyland rec In Novemb lled within t by plant o e another con ne deep well ure 2-11 as M oth the hyd y the topogr the water ta oss the site is ation data the regional adients that groundwate es associated occurred. In ould locally ral potable w cation of po ere is no po have been ater Wells N airyland for ackground gr AR, and B on-radiologi ACBWR ope eta activity.

s than or eq

, a temporar nt concerne e Turbine B own gradien on May 3, 19 t has since be and Post-S cently instal ber 2012, fi the LACBW operations.

nsist of one with a scree MW 200A an draulic cond raphy; and, w able has a v s also relativ from the groundwate are influen er flow below d with LAC n these area influence g water wells otable water otable water monitored Nos. 3 and 4 radiological roundwater B11R are m ical paramete erations, Pota Typical gr qual to MD ry well-poin ed the pote Building to su nt and below 983. The an een abandon Shutdown D lled groundw ive (5) pairs WR licensed The well p shallow wel ened interva nd B throug ductivity and with the flat ery low grad vely slow (i.

G-3 Coal er flow, and nced by the w and aroun BWR (i.e., i as, pilings, groundwater and groundw and groundw r or groundw by Solution 4 which serv l conditions monitoring monitored by ers to suppo able Water W ross beta ac DC (ranging nt was establ ential leakag ub-building w the grade o nalysis resul ned.

Decommissio water monit s of groundw site to deter pairs which ll with a scre al of 45 to 55 h MW-204A d the areas dient.

.e., in Plant d also river nd the in the deep flow water water water ns or viced on a wells y the ort the Wells ctivity from lished ge of soils.

of the ts for oning toring water rmine were eened 5 feet A and

La Cross License T Revision Two (2) in June groundw 90 and C In June o through 2 and B11 several r fourth ro Potable samples transuran of the gro Addition

18.

2.3.7.4.

The LAC twice pe groundw the MW-The colle D

M p

R gr 2.3.7.5.

Groundw (5 pairs) sampling wells MW Novembe positively ranging Novembe during th During th MW-202 Sr-90 w se Boiling W Termination n 0 rounds of gr 2013 and th water samples Cs-137. Analy of 2014, a t 204 A and B AR. These radionuclide ound of gro Well #5, an were sent o nic radionucl oundwater sa nal details, in On-Going CBWR Site g er year for r water is at rel

-200A/B thru ected inform Depth to grou Monitoring w otential/turb Radiological roundwater Summ water charact within the g in 2013. H W-201A and er of 2013 y detected i from 1.43 p er 2013 sam he 2013 samp he June 201 2A, MW-203 was also po Water Reactor Plan roundwater hen during s were sent ysis for H-3 third round o B; Potable W e collected g s including oundwater w nd Monitori off for radio lides. Table amples and r ncluding the g Investigatio groundwater radiological latively high u MW-204A mation during und water in well groundw bidity/dissolv sample infor sample colle mary of Grou terization eff LSE area H-3 was posi d B, MW-20 at concentra in the same pCi/L to 2.1 mpling period pling period 4 sample pe 3A and MW sitively det r

samples wer a seasonal l to an off-sit was perform of groundwa Water Wells #

groundwater HTD and t were collecte ing Wells B ological ana es 2-18 and 2 results.

e off-site ana ons r monitoring analysis pu her and lowe A/B wells as g each monit the respecti water pH/spe ved oxygen/t rmation incl ection.

undwater An fforts comme in Novemb tively detect 02-A and B, ations rangi wells durin 18 pCi/L; ho

d. Co-60 an eriod, H-3 w W-203B) at c ected in w 2-35 re collected low groundw te laboratory med on site.

ater samples

  1. 3, 4, 5, and samples w transuranic r ed from: M B11R and B alysis of sev 2-19 provide alytical labor g program co urposes only er elevations shown on F toring interv ive monitorin ecific conduc temperature.

luding a com nalytical Res enced throug ber 2012 an ted at concen MW-203A ing from 15 ng the June owever, it w nd Cs-137 w was positively oncentration wells MW-20 in 2013, du water level y for radiolo s was collec 7; and Mon ere sent off radionuclide MW 200A an B11AR. T veral radion es a summar ratory repor onsists of ob y from exis

. The moni igure 2-11.

val includes:

ng well.

ctance/oxida mpleted chain sults gh the install nd the com ntration grea and B and M 50 pCi/L to 2013 sampl was not po were not po y detected in ns ranging fr 02A, MW-2 uring the sea in Novemb ogical analys cted from: M nitoring Well f for radiolo es. In Septe nd B throug These collec nuclides incl ry of the radi rts are provi btaining grou ting monito toring wells ation and red n of custody lation of 10 mmencement ater than MD MW-204A a 660 pCi/L.

ling period a ositively dete sitively dete n four (4) w from 245 pC 203A and asonal high w ber 2013. T sis for Co-60 MW-200A a ls B2, B-3, B ogical analys ember of 20 gh 204A an cted groundw luding HTD iological ana ded in Refer undwater sam oring wells w s sampled in duction y following monitoring of groundw DC in monit and B in Jun Sr-90 was at concentra ected during ected in any wells (MW-B i/L to 336 p MW-204A water These 0, Sr-and B B11R sis of 014 a nd B, water D and alysis rence mples when clude wells water toring e and s also ations g the y well

B11R, pCi/L.

with

La Cross License T Revision concentra Am-241 During t greater th concentra were also 2.4.

C The surv deferred.

under co that will basement illustrate defer the condition ALARA data wou areas),

Safet Histo Acce struct interf The a physi condi As acces will be co for the s radionuc and HTD events ca of a surv stored in validatin As decom surface d for open documen se Boiling W Termination n 0 ations rangin were also po he Septemb han MDC in ation of 1.14 o positively d Continuing C vey of many Examples ncrete or asp remain and t after liner s buried pip e characteriz ns:

consideratio uld likely not ty considerat orical data sh ss for charac tures or othe fere with con ability to use ical relations itions repres ss is gained ollected, eva survey unit.

lides present D radionuclid aused by equ vey unit(s) w n the charac g the initial mmissioning decontamina n air demolit nted survey a Water Reactor Plan ng from 1.1 ositively det ber 2014 sam n any well.

4 pCi/L. Co detected at r Characteriz inaccessible s of areas w phalt coverin d be subjec r removal an ping systems zation of a ons (e.g., the t change the

tions, hows that the cterization w er obstacles w ntinued oper e engineering ship to surro sented by the to areas tha aluated and s This data t and update des. In addi uipment failu will be reco terization d classificatio g proceeds, ation (as wel tion or unre and a formal r

12 pCi/L to ected at resi mple period, Sr-90 was o-60, Ni-63, residual conc zation e or not read where survey ngs, structur cted to FRS nd the inter s that may r soil or stru e area is eith e survey area e area could would require where the re ration of ope g judgment i ounding area e conditions at were prev stored with-o will be use e the variabil ition, as the ures or perso orded. Thes atabase. Th n and in plan areas will, ll as fixed co estricted rele l turnover w 2-36 2.01 pCi/L.

dual concen

, H-3 was n positively d

, Cs-137, Eu centrations in dily accessib ys are deferr ral wall and

, the underl riors of bur remain in th ucture was b her a radiati a or area clas be classified e significant emoval could erating system in assigning s and the lik in these adja viously inacc other radiolo ed along wi lity in the ra decommiss onnel errors, se events w his additiona nning for the as necessar ontamination ease. When will be made C-14, Tc-9 ntrations in se not positivel detected in o u-152, Eu-15 n several we ble subsurfa rred include floor surfac rlying concr ried pipe tha he end-state based on on ion or conta ssification o d without fur t deconstruct d result in an ms, or the area a cl kelihood of th acent areas.

cessible, add ogical survey ith existing adionuclide m ioning progr

, which may will be evalu al character e FRS.

ry, be decon n) to levels n a structur by the Radi 99, Eu-152, everal wells ly detected a one (1) well 54, Pu-239/2 ells.

ace soils or s soils under ces in some rete in the R at may rem condition.

ne or more amination are of the locatio rther charact tion of adjac n unsafe con lassification he area to ha ditional char y data in a s data to upd mix for both resses, data y affect the ra uated and, w rization data ntaminated that will me e is ready f ological Pro Pu-239/240 at concentra l, MW-200A 240 and Am surfaces has r structures, of the basem Reactor Bui main. Figure The decisi of the follo ea and addit on or surroun terization, cent systems ndition or n based on ave radiolog racterization urvey histor date the typ h gamma-em from operat adiological s when approp a will be us to remove eet the condi for demoliti otection grou 0 and ations A at a m-241 been soils ments ilding e 2-3 on to owing tional nding s,

gical n data ry file pes of mitting tional status

priate, ed in loose itions ion, a up for

La Cross License T Revision the comp are suitab Followin a "turnov acceptan transferre performa may inclu The "turn survey pe survey da

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, and FRS), a lans will co ese objective ropriate instr n level and/o ropriate instr ropriate surv the calibrati ropriate samp nuclide ratio analysis crit ional sample ropriate class References U.S. Nuclear Content of Li 011.

U.S. Nuclear Radiation Sur U.S. Nuclear Consolidated f Radiologic EnergySoluti Crosse Boilin EnergySoluti ite Characte Water Reactor Plan ming demoli lition and/or ent" will be p will be met, cterization/L FRS. Otherw over survey,"

ey" process, epresent at le conducting t a documente ontain the ap es include:

rument selec or release cri rument quali ey technique on methodol ple collectio os, teria to ident es and, sification of Regulatory icense Termi Regulatory rvey and Site Regulatory Decommiss cal Criteria, F ons PG-EO-ng Water Rea ons GP-EO-erization Proj r

ition, validat r remediation performed. I

, then physi License Term wise, additio

" primarily fo together wi east one, but the FRS. Fo ed survey pl ppropriate da ction to ensur

iteria, ity control m es to ensure
logies, n and analys tify follow-u the survey a Commission ination Plan Commission e Investigati Commission sioning Guid Final Report

-313196-SV actor.

-313196-QA ject (QAPP) 2-37 ting that the n, and when If the results ical and adm mination grou onal remedia for Class 1 an ith any addi t possibly se or each type an will be d ata assessme re the proper measures to e that the field sis to determ up actions su area.

n, Regulator s for Nuclea n, NUREG-1 ion Manual (

n, NUREG-1 dance - Char t - Septembe

-PL-001, Ch A-PL-001, Qu

).

e radiologica n an area is b s of this asse ministrative up personne ation may b nd 2 areas w itional chara everal, oppo of survey (c developed us ent to ensur r sensitivity ensure operab d measurem mine spatial v uch as remed ry Guide 1.1 ar Power Rea 1575, Revisi (MARSSIM 1757, Volum racterization er 2006.

haracterizatio uality Assur al condition believed to b essment indi control of l for prepara be required.

within the LS acterization ortunities to c characterizat ing the DQO re that sever relative to th

bility, ent techniqu variability an diation and th 79, Standard actors, Revis ion 1, Multi-M), August 20 me 2, Revisio

, Survey, an on Survey P rance Project s in the stru be ready for icate that the the area wi ation, design This assess SE.

and remedi collect addit tion, remedia O process. T ral objective he applicabl ues are consi nd variability he collection d Format and sion 1 - June

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ation, These es are le istent y in n of d

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1 se Boiling W Termination n 0 EnergySoluti Water Reacto Dairyland Po AFSTOR -

U.S. Nuclear Radiation Sur December 20 andia Nation Contaminatio EnergySoluti 0 Detector S U.S. Nuclear Laboratory A U.S. Nuclear Radiological Termination)

EnergySoluti urvey Repor EnergySoluti urvey Repor ZionSolution allout in Soi EnergySoluti Concern Duri Haley & Aldr 0, 2012.

Haley & Aldr Reactor, Dair 015.

Dairyland Po Decommissio nternational Emitters (max 998.

Water Reactor Plan ons Technic or Historical wer Corpora December 2 Regulatory rvey and As 006.

nal Laborato on From Dec ons Technic Sensitivity.

Regulatory Analytical Pro Regulatory Monitoring

- Effluent S ons GG-EO-rt for Octobe ons LC-RS-rt for June th s Technical ils at Zion St ons Technic ing LACBW rich, Hydrog rich Inc., Hy ryland Powe wer Coopera oning Activit Standard IS ximum beta r

cal Support D Site Assessm ation LAC-T 2009.

Commission sessment of ory, NUREG commissioni cal Support D Commission otocols Man Commission Programs (I Streams and

-313196-RS er and Novem PN-164017-hru August 2 Support Doc tation.

cal Support D WR Decomm geological C ydrogeologic r Cooperativ ative, LACB ties Report (

O 7503-1, P energy grea 2-38 Document R ment (HSA)

TR-138, Initi n NUREG-1 Materials an G/CR-5512, V ing Paramete Document R n, NUREG-1 nual (MARL n Regulatory Inception Th the Environ S-RP-001, LA mber 2014 F

-001, LACB 2015 Field W cument 13-0 Document R missioning.

onceptual Si cal Investiga ve, Genoa W BWR Decom (D-Plan/PSD Part 1, Evalua ater than 0.15 RS-TD-31319

).

ial Site Char 1575, Supple nd Equipmen Volume 3, R er Analysis -

RS-TD-31319 1576, Multi-LAP) - Augu y Guide 4.15 hrough Norm nment - July ACBWR Ra Field Work -

BWR Radiolo Work - Nove 004, Examin RS-TD-31319 ite Model, F ation Report, Wisconsin, Fi mmissioning DAR), Revis ation of Surf 5 MeV) and 96-003, La C racterization ement 1, Mu nt Manual (M Residual Rad

- October 19 96-006, Lud

-Agency Rad ust 2001.

5, Quality A mal Operatio 2007.

adiological C

- November ogical Chara ember 2015.

nation of Cs-96-001, Rad File No. 3870

, La Crosse B ile No. 3870 Plan and Po sion - March face Contam Alpha-Emit Crosse Boilin n Survey for ulti-Agency MARSAME dioactive 999.

dlum Model 4 diological ssurance or ns to Licens Characterizat r 2015.

acterization 137 Global dionuclides o 05-001 - Au Boiling Wat 05-008, Janu ost Shutdown h 2014.

mination, Bet tters - Augu ng E) -

44-se tion of ugust ter ary n

ta-ust

La Cross License T Revision Survey Unit ID #

L101010 L101010 L101010 L101010 L201110 L201110 L301210 L301210 L301210 L401210 L401210 L401210 L401210 L401210 se Boiling W Termination n 0 Survey 01 Reactor Stack G 02 Turbine Diesel G 03 LSA Bu 04 North L 01 LACBW Crib Ho 02 G-3 Cri Dischar 01 North E 02 Transm 09 Plant A 03 G-3 Co 05 Coal Pi 06 Capped 07 Ground 08 Hwy 35 Water Reactor Plan Table 2-1 y Unit Descr LA r Building, W Grounds e Building, T Generator Bu uilding, Mai LSE Grounds WR Adminis ouse, Wareh ib House, LA rge Line, Are End of Licen mission Switc Access, ISFSI al Plant Gro le Grounds d Ash Impou ds East of Hi 5/Railroad R r

LACBW ription ACBWR Sit WTB, WGTV Turbine Offi uilding Grou ntenance Ea s

LSE Buff stration Buil ouse Ground ACBWR Cir ea South of L Clas nsed Site chyard Area I Haul Road Non-Im ounds undment Gro ghway 35 Right of Way 2-39 WR Open L te Enclosure V, Ventilatio ce Building, unds at Shack Gro fer Zone Gro lding, LACB ds rc. Water LSE Fence ss 3 Grounds d Grounds mpacted Grou ounds y Grounds Land Survey Cl e Grounds on

, 1B ounds ounds BWR s

unds No No No No No y Units Initial lassification Class 1 Class 1 Class 1 Class 1 Class 2 Class 2 Class 3 Class 3 Class 3 on-Impacted on-Impacted on-Impacted on-Impacted on-Impacted n

Approxim Survey U Area (m 1,992 2,315 1,749 2,387 7,211 6,785 24,04 11,71 31,01 d

66,86 d

82,89 d

111,89 d

81,25 d

9,444 mate Unit m2) 2 5

9 7

1 5

2 1

2 9

4 99 4

4

La Cross License T Revision Surve B101 B101 B101 B101 B101 B101 B101 B101 B101 B201 B201 B201 B201 B201 B201 B301 B301 B301 B301 se Boiling W Termination n 0 ey Unit 10001 10002 10003 10004 10005 10006 10007 10008 10009 10101 10102 10103 10104 10105 10106 12101 12102 12103 12104 Water Reactor Plan Table 2-2 Sur Wa LAC W

LACBWR LACBWR M

L LACBW LA LA LA Ba Transmissi Barg r

LACBW rvey Area D Reactor Bu aste Treatmen CBWR Venti Waste Gas Ta R Turbine Bld Bldg 1B Diesel G LSA Buil Maintenance E Pipe Tun ACBWR Cr G-3 Crib H WR Administ ACBWR War ACBWR War ACBWR War ack-up Contr ion Sub-Stat G-1 Crib H ge Washing B 2-40 WR Structu Description uilding nt Building ilation Stack ank Vault dg./Turbine Generator Str lding Eat Shack nnel rib House House tration Build rehouse #1 rehouse #2 rehouse #3 rol Center tion Switch H House Break Room ural Survey k

Office ructure ding House m

y Units Class Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl Cl sification lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 1 lass 2 lass 2 lass 2 lass 2 lass 2 lass 2 lass 3 lass 3 lass 3 lass 3

La Cross License T Revision G-3 R G-3 S G-3 C G-3 T G-3 E G-3 C G-3 C G-4 W G-3 L G-3 L G-3 C G-3 C G-3 V G-3 T G-3 B G-3 F G-3 F G-3 W G-3 S G-3 S

  1. 6 W se Boiling W Termination n 0 Table Reclaim Buil Stock Out Tr Coal Unload Transfer Tow Electrical Ro Crusher Tow Conveyor #6 Warehouse a LRAPB Buil Lime Silo El CAT Buildin Coal Plant Vehicle Stora Train Shed Bottom Ash Fly Ash Silo Fly Ash Elec Waste Silo Surge Tank Settling Tank Well House Water Reactor Plan e 2-2 (contin lding ransfer Build ing Tower wer A oom wer 6 (2) and Electrica lding ectrical Buil ng age Building Dewatering ctrical Buildi k

r nued)

Non Imp ding al Room lding g

Buildings ing 2-41 LACBWR pacted Struc G-3 An G-3 Bo G-3 Ex G-3 Ga G-3 Su G-3 Su G-3 Li G-3 W G-3 Ac G-3 As G-3 Ba G-3 Fl

  1. 7 We G-3 Co G-3 Sa G-3 St G-3 Gr G-3 As Main P S03 Ta Structural ctures nnex Buildin oiler Fuel Oi xplosive Gas as Room ub Station Sh ub Station Sh ime Storage Weigh Station ctive Reclaim sh Coordina ag Houses (5 ammable St ll House oal Scale ample Buildi tock Out Tra rid Shed sh handling Pollution Co ank Building Survey Uni ng il Pump Bui s Storage Ro hed hed Silo n

m Buildings ators Office

5) torage Shed ing ansfer Buildi Blower Buil ontrol Electri g

its lding oom s/ Tunnel ing lding ical Buildingg

La Cross License T Revision Dete Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Ludlum Gamma System a

Bas Stan b

Fun se Boiling W Termination n 0 ector Model m 44-9 m 43-68 mo m 43-68 mo m 43-93 mo m 43-89 mo m 43-93 mo m 43-89 mo m 44-10 m 43-37 m 43-10-1 a Spectroscop ed on 1-minute ndard, ISO 750 nctional equival Water Reactor Plan Table 2-3 l b Me Ludl ode Ludl ode Ludl ode ode Ludl ode ode Ludl Ludl Ludl Ludl py e count time; a 03-1 (20).

lent instrument r

Instrume eter Model lum 3 lum 2350-1 lum 2350-1 lum 2360 lum 2360 lum 2350-1 lum 2350-1 lum 2929 N/A and default valu tation may be u 2-42 ent Types a Applica sca static &

stat static &

stat sca sca and/

smea Anal ues for surface used and Nomina ation Ty (dp an 1,0

& scan 1,8 tic

& scan 1,8 2,0 tic an 3.5 6.5 an 2,0 or ar lysis efficiencies (

al MDCs Typical Dete MDCscan pm/100cm2) 000 to 2,000 800 to 2,000 N/A 800 to 2,000 000 to 2,200 N/A 5 pCi/g 60Co 5 pCi/g 137Cs 000 to 2,200 N/A N/A s) as specified ction Sensit

)

MDCst (dpm/10 0

N/A 0

600 to 80 to 0

0 800 to 800 to 90 to 1 90 to 1 o

s N/A 0

N/A

~0.10 p for Co-6 Cs-13 in Internationa tivity tatic a

0cm2)

A 700 90 900 900 100 100 A

A

-15

-80 pCi/g 60 and 37 al

La Cross License T Revision Analysis /

Gamma Radionucli Isotopic N (Np-237)

Isotopic Pl (Pu-238/23 Isotopic Th (Th-228/23 Isotopic Ur (U-234/235 Isotopic Cu (Cm-243/2 Isotopic Am (Am-241/2 C-14 Tritium Sr-90 Pu-241 Tc-99 Gross Alph Fe-55 Ni-63 Ni-59 se Boiling W Termination n 0 Table 2-4 Analytes ides G

eptunium A

lutonium 39/240)

A horium 30/232)

A ranium 5/238)

A urium 244)

A mericium 243)

A LS LS G

LS LS ha / Beta G

LS LS LS Water Reactor Plan Off-Site Technique Gamma Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec Alpha Spec SC SC GFPC SC SC GFPC SC SC SC r

e Laboratory DOE E

< 0.1pC DOE E

< 0.04 p DOE E

< 0.05 p DOE E

< 0.05 p DOE E

< 0.06 p DOE E

< 0.03 p DOE E

< 0.04 p EPA EE

< 5.0 pC EPA 90

< 10.0 p DOE E

< 1.0 pC DOE E

< 10.0 p DOE E

< 2.0 pC DOE E

< 10.0 p DOE E

< 2.0 pC DOE E

< 50.0 p 2-43 y Analytica Soils (pCi/

EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g EML HASL 300 pCi/g ERF C-01 Ci/g 06.0 pCi/g EML HASL 300 Ci/

EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g EML HASL 300 Ci/g EML HASL 300 pCi/g al Methods a Method and

/g) 0 0

0 0

0 0

0 0

0 0

0 0 (SRW01) 0 (SRW01) and Typical d Sensitivity Wat EPA Method 10.0 pCi/L EML Pu-02 M 1.0 pCi/L ENIC Modifi 50.0 pCi/L EPA 906.0 300.0 pCi/L EICHROM M 2.0 pCi/L EML Pu-01 50.0 pCi/L EICHROM T 15.0 pCi/L EPA 900.0 5.0 pCi/L EML Fe-01 M 100.0 pCi/L EML Ni-01 M 15.0 pCi/L EML Ni-01 M 100.0 pCi/L l MDCs ter (pCi/L) 901.1 Modified ied Modified Metho Tc-01 Modified Modified Modified od

La Cross License T Revision se Boiling W Termination n 0 Ta Location Area West o Area South Area North Area at G-3 Area Outsid Area at G-3 33 miles So Pedretti Far Radio Towe Junction of East of Stod Water Reactor Plan able 2-5 of #2 Wareh of Parking L of LACBW Gas Silo de G-3 Offic Outfall uth at Bad A m Substation er Northeast Hwy O and ddard at Hwy r

2005 Dairy (on L house Lot R Admin Bu es (off L Axe Boat Lan n East of LA of LACBW Hwy K y O Junction 2-44 yland Backg Licensed Site uilding Licensed Site nding ACBWR WR n

ground Stud Co-60 (pCi/g) e)

<MDC

<MDC

<MDC

<MDC

<MDC

<MDC e) 0.023

<MDC

<MDC

<MDC

<MDC dy for Soils Cs-(pC 0.0 0.0 0.

0.0 0.0 0.0 0.3 0.2 0.0 0.

0.0

-137 Ci/g) 077 026 149 038 076 017 381 227 035 188 065

La Cross License T Revision T

Conditio Undisturb Disturbed Undisturb Disturbed se Boiling W Termination n 0 Table 2-6 on and Dept bed d

bed d

Water Reactor Plan Investiga th D

Non r

ative Levels Meas Drainage Ar 0.

0.

n-Drainage 0.

0.

2-45 for Cs-137 sured Rang (pCi/g) eas Surface 00 to 2.80 00 to 1.67 Areas Surfa 23 to 0.66 27 to 0.34 Based on B ge R e 0-10 cm ace 0-10 cm

Background

Range for 95 (p

0.45 0.35 m

0.15 0.23 d Studies 5% Distribu pCi/g) 5 to 3.63 5 to 2.86 5 to 0.77 to 0.42 ution

La Cross License T Revision se Boiling W Termination n 0 Table 2

  • L Water Reactor Plan

-7 Initia Radio H

C Fe N

Co N

Sr Nb Tc Cs Eu Eu Eu Np Pu Pu Pu Pu Am Cm-24 Listed half life i r

al Suite of L onuclide H-3 C-14 e-55 i-59 o-60 i-63 r-90 b-94 c-99

-137 u-152 u-154 u-155 p-237 u-238 u-239 u-240 u-241 m-241 43/244*

is the shortest h 2-46 LACBWR S Ha half life for the Site-Specific alf Life (Yea 1.24E+01 5.73E+03 2.70E+00 7.50E+04 5.27E+00 9.60E+01 2.91E+01 2.03E+04 2.13E+05 3.00E+01 1.33E+01 8.80E+00 4.76E+00 2.14E+06 8.78E+01 2.41E+04 6.60E+03 1.44E+01 4.32E+02 1.81E+01 e radionuclides c Radionucl ars) s in the pair lides

L L

R S

S M

M M

M S

S M

M M

M S

A M

M M

M S

M M

La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Subsurface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Asphalt

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Surface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) ng Water React ation Plan Table 2-8 Survey Unit 66,869 m2 G-3 Coal Plan Co-60 3

0 0.070 0.075 0.078 0.057 0.011 Co-60 4

0 0.060 0.056 0.084 0.047 0.016 Co-60 None Taken 1%

5,550 6,700 or Non-Impact t L4012103 nt Grounds Cs-137 3

1 0.082 0.083 0.092 0.071 0.011 Cs-137 4

1 0.048 0.038 0.081 0.036 0.022 Cs-137 ed Open Land Survey Unit 82,894 m2 Coal Pile Grou Co-60 3

0 0.071 0.072 0.084 0.057 0.014 Co-60 3

0 0.061 0.063 0.068 0.052 0.008 Co-60 None Taken 1%

5,050 8,800 2-47 Survey Units -

L4012105 1

nds C

G Cs-137 3

1 0.061 0.060 0.068 0.055 0.006 Cs-137 3

1 0.042 0.040 0.056 0.030 0.013 Cs-137 1

8 1

- Characterizat Survey Unit L 111,899 m2 Capped Ash Im Grounds Co-60 3

0 0.082 0.084 0.090 0.072 0.009 Co-60 4

0 0.081 0.083 0.102 0.056 0.021 Co-60 2

0 0.073 0.073 0.082 0.065 0.012 1%

8,340 12,000 tion Survey Su L4012106 8

mpoundment G H

Cs-137 3

2 0.100 0.099 0.121 0.079 0.021 Cs-137 4

2 0.088 0.084 0.130 0.054 0.037 Cs-137 2

0 0.062 0.062 0.084 0.040 0.031 ummary Survey Unit L 81,254m2 Grounds East of Highway 35 Co-60 3

0 0.080 0.079 0.089 0.072 0.009 Co-60 3

0 0.081 0.069 0.106 0.068 0.022 Co-60 None Tak 1%

8,000 9,080 L4012107 f

Cs-137 3

3 0.264 0.263 0.463 0.065 0.199 Cs-137 3

2 0.068 0.057 0.091 0.056 0.020 Cs-137 ken

L L

R La Crosse Boilin License Termin Revision 0 Tabl ng Water React ation Plan le 2-8 (continue S

S M

M M

M SD S

M M

M M

SD A

M M

M M

SD S

M M

or ed)

Non-I urvey Unit Surface Area Description urface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D ubsurface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D Asphalt of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D urface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm)

Impacted Open Survey Unit 9,444 m2 Hwy 35/Railro Way Grounds Co-60 3

0 0.079 0.075 0.095 0.068 0.014 Co-60 3

0 0.086 0.092 0.107 0.060 0.024 Co-60 None Taken 1%

8,124 9,200 2-48 n Land Survey L4012108 1

ad Right of B A

Cs-137 3

2 0.119 0.108 0.156 0.093 0.033 Cs-137 3

2 0.189 0.091 0.409 0.067 0.191 Cs-137 Units - Chara Survey Unit L 100 m2 Background Soi Area (inside L40 Co-60 17 0

0.087 0.086 0.101 0.077 0.007 Co-60 None Ta Co-60 None Ta No Scanning P acterization Sur L4012109 ils Test 012108)

Cs-137 17 17 0.160 0.161 0.268 0.059 0.059 Cs-137 aken Cs-137 aken Performed rvey Summaryy

L L

R R

L L

L L

L L

L L

L L

L L

a b

La Crosse Boilin License Termin Revision 0 Radionuclide L3012103-QJ-GS-001-S L3012103-QJ-GS-001-S L3012105-Genoa Coal P L3012105-CR-GS-002-L3012105-QJ-GS-001-S L3012105-QJ-GS-001-S L3012106-QJ-GS-001-S L3012106-QJ-GS-001-S L3012107-QJ-GS-001-S L3012107-QJ-GS-001-S L3012108-QJ-GS-001-S L3012108-QJ-GS-001-S a

Bold values b

Survey units ng Water React ation Plan H-3 C

SB 4.390 1

SS 3.570 0.

Pile

-SS 0.533 0.

SB SS SB 14.600 0.

SS 0.813 0.

SB SS 1.420 0.

SB 2.350 0.

SS 6.490 0.

indicate concentration g originally classified as tor Table 2-9 C-14 Fe-55 N

.230 3.430 1

.671 2.790 1

.675 2.130 1

.713 2.300 2

.713 3.550 2

.719 3.610 2

.705 1.920 3

.728 2.260 3

greater than MDC. Itali Class 3 at time of samp Non Impa Ni-59 Co-60 N

.470 0.026 2

.870 0.027 3

0.018

.730 0.025 2

0.026 0.030

.370 0.037 3

.560 0.037 3

0.019

.800 0.025 3

.110 0.018 4

.200 0.030 4

icized values indicate M ple acted Coal Pile Ni-63 Sr-90 N

.140 0.321 0

.380 0.391 0

0

.950 0.289 0

0 0

.950 0.348 0

.580 0.338 0

0

.940 0.293 0

.440 0.278 0

.710 0.271 0

MDC value 2-49 and Soil Samp Nb-94 Tc-99 Cs 0.018 0.820 0

0.022 0.628 0

0.022 0

0.016 0.587 0

0.020 0

0.020 0

0.030 0.611 0

0.028 0.616 0

0.013 0

0.019 0.593 0

0.016 0.604 0

0.020 0.576 0

ples - Test Ame s-137 Pm-147 Eu 0.024 0.714 0

0.018 0.847 0

0.019 0

0.018 0.698 0

0.023 0

0.028 0

.319 1.500 0

.096 0.826 0

0.021 0

.018 1.450 0

.033 1.310 0

.182 0.770 0

erica Laborator u-152 Eu-154 Eu 0.071 0.190 0

0.060 0.167 0

0.052 0.152 0

0.051 0.137 0

0.049 0.166 0

0.072 0.199 0

0.115 0.223 0

0.079 0.232 0

0.045 0.115 0

0.049 0.156 0

0.041 0.128 0

0.059 0.176 0

ry Analysis (pC u-155 Np-237 Pu 0.095 0.025 0

0.096 0.024 0

0.048 0.056 0.023 0

0.055 0.074 0.080 0.035 0

0.112 0.027 0

0.038 0.048 0.040 0

0.044 0.030 0

0.060 0.020 0

Ci/g) u-238 Pu-239/240 Pu 0.046 0.015 1

0.040 0.021 1

0.036 0.029 1

0.036 0.014 2

0.044 0.026 2

0.021 0.024 2

0.026 0.021 2

0.028 0.029 2

u-241 Am-241 A

1.730 0.032 0

1.650 0.025 0

0.041 1.670 0.018 0

0.048 0.061 2.550 0.019 0

2.740 0.025 0

0.034 2.580 0.020 0

2.670 0.017 0

2.740 0.015 0

Am-243 Cm-243/244 0.022 0.010 0.024 0.019 0.025 0.006 0.034 0.006 0.013 0.019 0.035 0.006 0.036 0.017 0.024 0.015

L L

R S

S M

M M

M S

S M

M M

M S

A M

M M

M S

S M

M a

La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Subsurface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Asphalt

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Surface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) a MDC va ng Water React ation Plan Table 2-10 Survey Unit 1,992 m2 Reactor Buil WGTV, Vent Grounds Co-60 12 2

0.080 0.058 0.287 0.048 0.066 Co-60 18 0

0.078 0.052 0.516 0.047 0.109 None Taken No Scanning P alue used for ana or Impacted Cla t L1010101 lding, WTB, tilation Stack Cs-137 12 12 0.215 0.100 1.070 0.032 0.296 Cs-137 18 8

0.066 0.054 0.161 0.033 0.035 Performed alytical results l ass 1 Open Land Survey Unit 2,315 m2 Turbine, Office Generator Buil Grounds Co-60 2

0 0.049 0.049 0.054 0.044 0.007 Co-60 22 0

0.058 0.058 0.080 0.043 0.010 None Taken No Scanning P less than MDC.

2-50 d Survey Units L1010102 1

e, Diesel ding L

M G

Cs-137 2

0 0.050 0.050 0.051 0.050 0.001 Cs-137 22 4

0.064 0.065 0.130 0.044 0.017 N

erformed N

s - Characteriz Survey Unit L 1,749 m2 LSA Building, Maintenance Ea Grounds Co-60 7

0 0.059 0.050 0.099 0.048 0.019 Co-60 25 0

0.046 0.046 0.055 0.025 0.005 None Taken No Scanning Pe zation Survey S L1010103 2

at Shack N

Cs-137 7

1 0.069 0.054 0.161 0.048 0.041 Cs-137 25 0

0.049 0.049 0.054 0.042 0.003 erformed Summary Survey Unit L 2,387 m2 North LSE Grou Co-60 1

0 0.045 0.045 0.045 0.045 N/A Co-60 14 0

0.048 0.048 0.050 0.043 0.002 Co-60 10 0

0.053 0.054 0.062 0.042 0.006 No Scanning Pe L1010104 unds Cs-137 1

0 0.049 0.049 0.049 0.049 N/A Cs-137 14 3

0.041 0.042 0.051 0.027 0.009 Cs-137 10 1

0.051 0.053 0.057 0.037 0.006 erformed

L L

R R

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

a La Crosse Boilin License Termin Revision 0 Radionuclide L1010101-CJ-GS-002-S L1010101-CJ-GS-009-S L1010101-CJ-GS-010-S L1010101-QJ-GS-001-S L1010101-QJ-GS-001-S L1010101-QJ-GS-002-S L1010101-QJ-GS-002-S L1010102-CJ-FC-001-C L1010102-CJ-GS-013-S L1010102-QJ-GS-001-S L1010102-QJ-GS-001-S L1010102-QJ-GS-002-S L1010103-CJ-GS-002-S L1010103-QJ-SL-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-002-S L1010103-QJ-GS-002-S L1010103-QJ-GS-003-S L1010103-QJ-GS-003-S L1010104-CJ-GS-003-S L1010104-CR-PA-007-L1010104-QQ-PA-001-L1010104-QR-GS-001-a Bold values ng Water React ation Plan T

H-3 C

SS SS SS SB 0.364 0

SS 0.441 0.

SB 0.377 0.

SS 1.380 0.

CV 1.710 0.

SB SB 8.740 0.

SS SB 24.700 0.

SB SM 0.354 0

SB 3.260 0.

SS SB 0.649 0.

SS SB 0.654 0.

SS SB

-AV

-AV

-SB indicate concentration g tor Table 2-11 C

C-14 Fe-55 N

.896 2.430 1

.676 2.190 1

.679 2.150 1

.677 4.190 2

.727 1.650 2

.726 2.120 2

.715 2.230 2

.453 0.689 0

.715 1.830 2

.702 2.100 2

.717 2.340 2

greater than MDC. Itali lass 1 Concrete Ni-59 Co-60 N

0.024 0.040 0.286

.850 0.024 3

.900 0.018 3

.750 0.017 2

.010 0.015 3

.630 0.106 3

0.030

.620 0.015 4

0.022

.760 0.021 3

0.011 0.711 0.136 1

.850 0.017 4

0.025

.620 0.014 3

0.019

.630 0.012 3

0.023 0.015 0.021 0.025 0.017 icized values indicate M e, Asphalt, Sed Ni-63 Sr-90 N

0 0

0

.040 0.335 0

.040 0.440 0

.930 0.338 0

.320 0.357 0

.920 0.292 0

0

.000 0.310 0

0

.920 0.316 0

0

.090 0.132 0

.240 0.333 0

0

.710 0.325 0

0

.660 0.300 0

0 0

0 0

0 MDC value.

2-51 diment and Soil Nb-94 Tc-99 Cs 0.020 0

0.020 0

0.025 0

0.015 0.579 0

0.012 0.587 0

0.011 0.620 0

0.010 0.521 0

0.022 0.536 0

0.016 0

0.011 0.539 0

0.015 0

0.014 0.537 0

0.017 0

0.018 0.432 0

0.011 0.606 0

0.015 0

0.012 0.645 0

0.017 0

0.009 0.557 0

0.019 0

0.008 0

0.014 0

0.025 0

0.011 0

l Samples - Tes s-137 Pm-147 Eu

.233 0

.185 0

.413 0

0.020 0.800 0

.147 3.170 0

.149 0.772 0

.059 0.978 0

.352 1.290 0

0.021 0

0.012 0.961 0

0.018 0

0.016 0.722 0

0.021 0

.136 0.360 0

0.015 0.740 0

0.020 0

0.012 0.838 0

0.017 0

0.011 0.713 0

.091 0

0.013 0

0.016 0

0.028 0

0.012 0

st America Lab u-152 Eu-154 Eu 0.056 0.161 0

0.056 0.181 0

0.062 0.247 0

0.050 0.143 0

0.034 0.112 0

0.040 0.109 0

0.033 0.096 0

0.061 0.239 0

0.044 0.170 0

0.030 0.101 0

0.036 0.113 0

0.043 0.139 0

0.044 0.181 0

0.054 0.199 0

0.036 0.117 0

0.046 0.174 0

0.029 0.103 0

0.040 0.139 0

0.029 0.092 0

0.057 0.186 0

0.032 0.078 0

0.042 0.141 0

0.058 0.218 0

0.038 0.132 0

boratory Analy u-155 Np-237 Pu 0.066 0.050 0.057 0.044 0.019 0

0.044 0.006 0

0.040 0.019 0

0.036 0.016 0

0.062 0.029 0

0.041 0.028 0.028 0

0.042 0.042 0.032 0

0.046 0.049 0.018 0

0.039 0.026 0

0.047 0.034 0.020 0

0.045 0.034 0.040 0

0.063 0.036 0.044 0.061 0.032 ysis (pCi/g) u-238 Pu-239/240 Pu 0.046 0.023 1

0.039 0.023 1

0.041 0.022 1

0.040 0.016 2

0.041 0.028 2

0.040 0.026 2

0.042 0.029 2

0.015 0.015 0

0.029 0.017 1

0.034 0.024 2

0.028 0.028 2

u-241 Am-241 A

0.058 0.042 0.051 1.970 0.015 0

1.830 0.016 0

1.950 0.017 0

2.090 0.020 0

2.490 0.018 0

0.036 2.780 0.015 0

0.039 2.660 0.015 0

0.044 0.867 0.008 0

1.430 0.009 0

0.043 2.570 0.018 0

0.024 2.470 0.018 0

0.052 0.034 0.040 0.050 0.032 Am-243 Cm-243/244 0.023 0.021 0.021 0.019 0.029 0.014 0.017 0.022 0.019 0.021 0.020 0.021 0.021 0.018 0.019 0.008 0.024 0.005 0.024 0.014 0.022 0.005

La Cross License T Revision Tabl Sur Sur

  1. of
  1. >C Mea Med Max Min SD Sub
  1. of
  1. >C Mea Med Max Min SD Asp
  1. of
  1. >C Mea Med Max Min SD Sur

% S Mea Max se Boiling W Termination n 0 le 2-12 Im rvey Unit Surface Area Description rface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) bsurface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) phalt f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) rface Scans Scanned an Scan (cpm) x Scan (cpm)

Water Reactor Plan mpacted Cla Sur 7,211 m2 LACBWR

Building, House, W Co-60 13 0

0.073 0.077 0.106 0.053 0.016 Co-60 16 1

0.052 0.046 0.112 0.040 0.018 Co-60 6

0 0.051 0.051 0.054 0.047 0.002 50%

7,500 to 8,0 11,500 to 12 r

ass 2 Open L S

rvey Unit L201 R

Adm LACBW Warehouse Gr 0

3 7

6 3

6 0

2 6

2 0

8 0

4 7

2 00 2,000 2-52 Land Surve Summary 11101 ministration WR Crib rounds Cs-137 13 8

0.090 0.100 0.139 0.041 0.030 Cs-137 16 2

0.049 0.048 0.088 0.034 0.012 Cs-137 6

0 0.051 0.051 0.054 0.047 0.003 ey Units - C Sur 6,785 m2 G-3 Crib Circ. Wa Area Sout Co-60 10 0

0.064 0.064 0.081 0.052 0.009 Co-60 7

0 0.049 0.048 0.055 0.042 0.004 Co-60 6

0 0.056 0.057 0.059 0.049 0.003 1

Characteriza rvey Unit L201 b House, ater Discha th of LSE Fe 0

4 4

2 9

0 9

8 5

2 4

0 6

7 9

9 3

50%

7,500 to 8,000 11,500 to 12,00 ation Surve 11102 LACBWR arge Line, ence Cs-137 10 6

0.065 0.054 0.200 0.030 0.049 Cs-137 7

2 0.038 0.033 0.052 0.029 0.009 Cs-137 6

3 0.048 0.051 0.055 0.009 0.008 0

00 ey

L L

R R

L L

L L

L L

L L

L L

L L

L a

La Crosse Boilin License Termin Revision 0 Radionuclide L2011101-CJ-GS-001-S L2011101-CR-PA-003-L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QQ-GS-001-L2011101-QQ-GS-001-L2011101-QQ-GS-002-L2011101-QQ-PA-001-L2011102-QQ-GS-001-L2011102-QQ-GS-001-L2011102-QQ-GS-002-L2011102-QQ-PA-001-a Bold val ng Water React ation Plan H-3 C

SM

-AV SB 0.518 0.

SM 2.040 0.

SS

-SB

-SS 11.810 0.

-SB 2.500 0.

-AV

-SB 1.370 1

-SS 0.533 0.

-SB 0.525 0.

-AV lues indicate con tor Table 2 C-14 Fe-55 N

.727 2.290 2

.707 2.240 2

.726 2.590 2

.731 1.940 2

.560 2.260 3

.713 2.330 2

.702 3.890 2

ncentration grea 2-13 Class 2 Ni-59 Co-60 N

0.096 0.023

.660 0.016 4

.950 0.049 4

0.012 0.017

.600 0.035 3

.680 0.017 3

0.022

.040 0.007 4

.820 0.019 4

.880 0.031 3

0.027 ater than MDC.

Asphalt, Sedim Ni-63 Sr-90 N

0 0

.030 0.273 0

.140 0.523 0

0 0

.720 0.255 0

.870 0.314 0

0

.390 0.291 0

.300 0.361 0

.950 0.327 0

0 Italicized value 2-53 ment and Soil S Nb-94 Tc-99 Cs 0.011 0

0.016 0

0.014 0.643 0

0.018 0.585 0

0.020 0

0.012 0

0.035 0.532 0

0.014 0.616 0

0.015 0

0.018 0.537 0

0.014 0.595 0

0.016 0.568 0

0.017 0

es indicate MDC Samples - Test s-137 Pm-147 Eu

.137 0

0.017 0

0.015 0.705 0

.107 0.615 0

.080 0

0.013 0

.103 0.779 0

0.016 0.697 0

0.015 0

0.021 0.672 0

0.014 0.772 0

0.018 0.717 0

0.018 0

C value.

America Labo u-152 Eu-154 Eu 0.041 0.098 0

0.039 0.131 0

0.033 0.108 0

0.048 0.178 0

0.060 0.188 0

0.040 0.127 0

0.097 0.205 0

0.037 0.119 0

0.046 0.135 0

0.044 0.173 0

0.039 0.111 0

0.052 0.183 0

0.051 0.142 0

oratory Analysi u-155 Np-237 Pu 0.033 0.039 0.040 0.022 0

0.049 0.026 0

0.091 0.037 0.102 0.023 0

0.041 0.019 0

0.042 0.055 0.031 0

0.045 0.017 0

0.051 0.022 0

0.038 is u-238 Pu-239/240 Pu 0.028 0.025 2

0.045 0.021 3

0.037 0.024 2

0.039 0.016 2

0.026 0.018 2

0.036 0.026 2

0.028 0.020 1

u-241 Am-241 A

0.031 0.038 2.470 0.015 0

3.100 0.037 0

0.042 0.031 2.800 0.019 0

2.920 0.020 0

0.040 2.680 0.029 0

2.880 0.026 0

1.710 0.010 0

0.036 Am-243 Cm-243/244 0.022 0.019 0.036 0.034 0.015 0.015 0.028 0.016 0.028 0.024 0.034 0.021 0.028 0.006

L L

R La Crosse Boilin License Termin Revision 0 S

S M

M M

M S

S M

M M

M S

C M

M M

M S

S M

M ng Water React ation Plan Table 2-14 urvey Unit Surface Area Description urface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D ubsurface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D Concrete/Asphalt of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D urface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) or Impacted Cla Survey Unit 24,042 m2 North End of Lic Co-60 3

0 0.070 0.076 0.077 0.058 0.011 Co-60 3

0 0.051 0.053 0.054 0.046 0.004 Co-60 3

0 0.031 0.031 0.035 0.028 0.003 1%

9,000 10,000 ass 3 Open Land t L3012101 censed Site Cs-137 3

0 0.073 0.072 0.083 0.065 0.009 Cs-137 3

0 0.051 0.052 0.052 0.051 0.001 Cs-137 3

0 0.029 0.027 0.033 0.026 0.004 2-54 d Survey Units Survey Unit 11,711 m2 Transmission Swi Co-60 None T Co-60 None T Co-60 None Taken No Scanning s - Characteriz L3012102 3

tchyard Area P

G Cs-137 Taken Cs-137 Taken Cs-137 Performed zation Survey S Survey Unit L 31,012 m2 Plant Access, ISF Grounds Co-60 5

0 0.063 0.064 0.078 0.053 0.010 Co-60 4

0 0.072 0.072 0.100 0.046 0.023 Co-60 7

0 0.062 0.055 0.080 0.047 0.013 1%

5,890 6,400 Summary L3012109 SI Haul Road Cs-137 5

5 0.152 0.143 0.267 0.075 0.078 Cs-137 4

0 0.066 0.059 0.101 0.045 0.025 Cs-137 7

0 0.059 0.052 0.079 0.028 0.019 0

0

L L

R R

L L

L L

L L

L L

L L

L a

La Crosse Boilin License Termin Revision 0 Radionuclide L3012101-CR-GC-001-L3012101-CR-GC-002-L3012101-CR-GC-003-L3012101-CR-GS-003-L3012101-QQ-GS-001-L3012101-QQ-GS-001-L3012101-QQ-SL-001-L3012104-CR-GS-002-L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S a

Bold values ng Water React ation Plan H-3 C

-CV

-CV

-CV 0.

-SS

-SB 18.400 0.

-SS 15.500 0.

-SM 0.364 0.

-SM SB 2.160 0.

SM 2.890 0.

SS 2.190 0.

indicate concentration g tor Table 2-15 C-14 Fe-55 N

.669 2.180 2

.717 2.390 2

.708 2.330 2

.342 2.710 0

.670 1.950 1

.672 2.720 1

.676 4.240 1

greater than MDC. Itali 5

Class 3 Asp Ni-59 Co-60 N

0.028 0.035

.020 0.031 3

0.025

.870 0.016 5

.660 0.020 3

0.739 0.022 1

0.015

.750 0.021 3

.990 0.037 3

.880 0.029 3

icized values indicate M phalt, Sediment Ni-63 Sr-90 N

0 0

.590 0.374 0

0

.640 0.309 0

.890 0.295 0

.090 0.152 0

0

.060 0.325 0

.500 0.298 0

.300 0.329 0

MDC value 2-55 t and Soil Samp Nb-94 Tc-99 Cs 0.030 0

0.026 0

0.027 0.521 0

0.017 0

0.014 0.550 0

0.017 0.603 0

0.017 0.360 0

0.013 0

0.018 0.469 0

0.020 0.651 0

0.020 0.631 0

ples - Test Am s-137 Pm-147 Eu 0.026 0

0.033 0

0.027 1.480 0

.113 0

0.015 0.899 0

.059 1.090 0

0.020 0.333 0

.066 0

0.025 0.818 0

.094 0.818 0

.138 0.667 0

merica Laborato u-152 Eu-154 Eu 0.043 0.221 0

0.062 0.271 0

0.056 0.249 0

0.052 0.157 0

0.036 0.128 0

0.047 0.116 0

0.042 0.153 0

0.035 0.128 0

0.053 0.160 0

0.074 0.217 0

0.068 0.181 0

ory Analysis (p u-155 Np-237 Pu 0.059 0.056 0.069 0.025 0

0.059 0.036 0.039 0

0.054 0.028 0

0.034 0.009 0

0.047 0.054 0.022 0

0.071 0.006 0

0.080 0.020 0

pCi/g) u-238 Pu-239/240 Pu 0.046 0.018 1

0.035 0.022 2

0.028 0.022 2

0.016 0.013 0

0.027 0.021 1

0.031 0.017 1

0.043 0.026 1

u-241 Am-241 A

0.053 0.055 1.690 0.019 0

0.052 2.590 0.023 0

2.640 0.019 0

0.797 0.009 0

0.036 1.610 0.016 0

1.560 0.016 0

1.580 0.019 0

Am-243 Cm-243/244 0.021 0.006 0.029 0.027 0.021 0.006 0.009 0.011 0.018 0.016 0.016 0.015 0.019 0.021

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 T

B1001101-C Result (pCi/g) 3.950

-0.162 9.130 0.000 11.500 39.300 6.910

-0.120 0.024 7500 2.580 0.266 0.369 0.009 0.176 0.132 0.902 0.407 0.028 0.0579 B1001101-C Result (pCi/g) 7.240

-0.492 9.450 0.000 57.700 202.000 34.500 0.191

-0.189 614.000 0.768 0.335

-0.429 0.000 0.528 0.491 7.470 1.450 0.052 0.0879 Water Reactor Plan Table 2-16 CJ-FC-001-CV 0 MDC (pCi/g)

(p 1.590 1

1.400 0

16.000 7

0.254 0

0.377 1

0.402 4

0.043 0

0.312 0

0.566 0

7.090 78 9.020 5

2.410 0

4.440 1

0.042 0

0.056 0

0.048 0

2.700 1

0.048 0

0.046 0

0.0302 0.

CJ-FC-003-CV 0 MDC (pCi/g)

(p 1.360 1

1.460 0

9.040 4

0.365 0

0.333 5

0.593 21 0.040 3

0.392 0

0.586 0

0.732 64 2.870 1

5.460 0

1.510 0

0.041 0

0.058 0

0.030 0

2.640 2

0.047 0

0.027 0

0.0408 0.

r Concrete 0-1/2 B

R pCi/g)

(p

.350 9

.793

-0

.880 10

.325 0

.250 0

.110 3

.680 0

.189 0

.330 0

1.000 9

.230

-0

.398 0

.140 0

.021

-0

.065

-0

.055

-0

.660

-1

.107 0

.030 0

0371

-0 0-1/2 B

R pCi/g)

(p

.580 12

.806

-0

.950 6

.806 0

.880 0

1.100 2

.330 0

.203

-0

.330

-0 4.000 2

.300 0

.536 0

.914

-0

.016

-0

.111

-0

.104

-0

.160

-1

.250 0

.033 0

0496 0.

2-56 Core Isotop B1001101-CJ-FC Result MD pCi/g)

(pCi/

9.720 1.56 0.346 1.44 0.400 21.3 0.000 0.26 0.082 0.16 3.850 0.42 0.162 0.05 0.001 0.13 0.076 0.52 9.660 0.15 0.039 0.51 0.025 1.26 0.071 0.37 0.002 0.04 0.017 0.06 0.006 0.04 1.510 2.50 0.011 0.03 0.014 0.03

.0081 0.04 B1001101-CJ-FC Result MD pCi/g)

(pCi/

2.600 1.57 0.566 1.39 6.160 14.3 0.000 0.25 0.435 0.05 2.990 0.40 0.304 0.05 0.001 0.15 0.129 0.59 2.450 0.11 0.045 0.34 0.179 1.02 0.007 0.28 0.010 0.05 0.005 0.06 0.004 0.04 1.320 2.66 0.018 0.03 0.009 0.03

.0000 0.01 pic Analysis C-001-CV 1/2-1 DC

/g)

(pCi/g) 60 1.950 40 0.806 300 10.200 64 0.151 68 0.078 25 0.474 51 0.041 39 0.078 26 0.310 52 1.100 11 0.055 60 0.171 76 0.118 45 0.017 66 0.026 49 0.018 00 1.360 37 0.020 30 0.019 478 0.0094 C-003-CV 1/2-1 DC

/g)

(pCi/g) 70 2.240 90 0.765 300 6.960 57 0.157 57 0.096 00 0.392 51 0.052 53 0.086 96 0.339 13 0.348 46 0.154 20 0.383 82 0.164 51 0.018 64 0.029 47 0.017 60 1.480 38 0.024 30 0.016 68 0.0047 s Results B1001 Result (pCi/g) 3.640

-0.270 0

11.300 0.000 0.800 4.860 11.600

-0.017

-0.104 450.00 0.173

-0.008 0.145

-0.010 0.575 0.715 13.200 0.550

-0.036 4

0.1540 B1001 Result (pCi/g) 4.490

-0.555 7.600 0.000 28.100 88.300 11.000

-0.016 0.153 213.00 0.162 0.557 0.108

-0.020 0.413 0.336

-7.720 0.614 0.052 7

-0.0547 101-CJ-FC-002 t

MDC (pCi/g) 1.620 0

1.410 0

9.950 0.289 0.117 0.492 0

0.046 7

0.165 4

0.564 0

0.597 2.150 8

1.460 0.837 0

0.042 0.617 0.466 0

23.500 0.401 6

0.433 0

0.4670 101-CJ-FC-004 t

MDC (pCi/g) 1.590 5

1.450 7.070 0.276 0

0.190 0

0.467 0

0.045 6

0.264 0.592 0

0.439 1.570 3.070 0.850 0

0.060 0.426 0.325 0

26.000 0.441 0.292 7

0.4320

-CV 0-1/2

(pCi/g) 1.330 0.794 5.540 0.183 0.172 0.581 1.130 0.095 0.322 46.900 0.924 0.820 0.503 0.009 0.436 0.413 15.100 0.419 0.140 0.2600

-CV 0-1/2

(pCi/g) 1.420 0.795 4.040 0.467 2.950 9.200 1.070 0.155 0.352 22.200 0.611 0.863 0.138 0.020 0.320 0.265 14.400 0.436 0.136 0.0776

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1001101-C Result (pCi/g) 2.960

-0.077 8.070 2.590 73.900 221.000 32.800

-0.089 0.178 65.700 0.395 0.637 0.011 0.005 0.706 0.489 9.090 1.590 0.048 0.1160 B1001101-C Result (pCi/g) 3.590

-0.246 6.030 0.000

-0.026 2.310 0.146 0.019 0.024 1.410 0.021 0.055 0.003 0.003

-0.004 0.035

-1.890 0.006

-0.002

-0.0036 Water Reactor Plan

-16 (continu CJ-FC-005-CV 0 MDC (pCi/g)

(p 1.520 1

1.410 0

9.770 5

0.267 0

0.372 7

0.427 23 0.043 3

0.531 0

0.562 0

0.569 6

1.240 0

5.650 0

0.699 0

0.015 0

0.065 0

0.035 0

2.540 2

0.045 0

0.031 0

0.0443 0.

CJ-WC-006-CV MDC (pCi/g)

(p 1.640 1

1.490 0

14.500 7

0.257 0

0.207 0

0.396 0

0.038 0

0.141 0

0.556 0

0.153 0

0.434 0

1.270 0

0.336 0

0.045 0

0.043 0

0.033 0

2.360 1

0.036 0

0.031 0

0.0287 0.

r ued)

Co 0-1/2 B

R pCi/g)

(p

.200 4

.810

-0

.230 8

.813 0

.510 0

3.000 4

.170 0

.317

-0

.336

-0

.970 0

.746 0

.831 0

.414 0

.010

-0

.134

-0

.106

-0

.270 0

.273 0

.034

-0 0590 0

1/2-1 R

pCi/g)

(p

.350 0

.836 0

.050 1

.147 0

.240 0

.335 2

.034 0

.060 0

.324

-0

.258 16

.113 0

.137 0

.196 0

.021 0

.016 0

.028

-0

.270

-1

.017 0

.005

-0 0052 0

2-57 oncrete Cor B1001101-CJ-FC Result MD pCi/g)

(pCi/

4.180 1.85 0.701 1.35 8.170 9.87 0.000 0.27 0.075 0.17 4.870 0.43 0.423 0.05 0.015 0.12 0.124 0.54 0.801 0.11 0.001 0.37 0.119 0.92 0.013 0.25 0.017 0.05 0.003 0.05 0.008 0.03 0.337 2.53 0.012 0.01 0.002 0.05

.0000 0.01 B1008101-CJ-Result MD pCi/g)

(pCi/

0.382 0.94 0.053 1.37 1.610 6.55 0.000 0.23 0.662 0.06 2.730 0.35 0.154 0.05 0.000 0.21 0.010 0.57 6.000 0.17 0.034 0.63 0.060 1.20 0.140 0.35 0.003 0.04 0.018 0.06 0.011 0.05 1.120 2.71 0.020 0.04 0.002 0.04

.0062 0.01 re Isotopic A C-005-CV 1/2-1 DC

i/g)

(pCi/g) 50 1.520 50 0.733 70 5.340 70 0.165 71 0.080 30 0.570 51 0.063 28 0.074 40 0.307 17 0.172 73 0.005 23 0.245 55 0.148 54 0.016 53 0.023 38 0.008 30 1.510 18 0.017 54 0.022 76 0.0049

-FC-002-CV DC

i/g)

(pCi/g) 40 0.559 70 0.794 50 3.370 34 0.151 65 0.131 53 0.355 53 0.041 11 0.066 79 0.335 77 1.780 33 0.056 00 0.239 57 0.215 48 0.022 60 0.033 54 0.019 10 1.480 42 0.027 44 0.017 87 0.0125 Analysis Re B1001 Result (pCi/g) 4.210 0.077 11.700 0.000 2.040 13.400 7.150 0.026 0.083 1490 0.031 0.128 0.737

-0.013 0.029 0.035

-1.380 0.048 0.003

-0.0053 B10 Result (pCi/g) 1.300

-0.296 6.460 0.000 0.974 4.400 0.235 0.016

-0.005 10.000 0.291 0.019 0.101

-0.024 0.042 0.008

-0.194 0.019

-0.001

-0.0056 esults 101-CJ-WC-006 t

MDC

)

(pCi/g) 1.700 1.440 0

9.320 0.263 0.047 0

0.420 0.034 0.154 0.580 0.721 3.660 1.190 1.470 0.044 0.037 0.025 2.650 0.052 0.029 3

0.0419 008101-CJ-FC-0 t

MDC

)

(pCi/g) 1.020 1.440 14.500 0.241 0.142 0.356 0.035 0.141 0.592 0

0.154 0.470 1.410 0.348 0.068 0.057 0.034 2.550 0.051 0.052 6

0.0444 6-CV 0-1/2

(pCi/g) 1.440 0.832 5.530 0.230 0.264 1.430 0.703 0.090 0.341 155.000 2.210 0.679 0.896 0.010 0.027 0.026 1.470 0.041 0.011 0.0075 003-CV

(pCi/g) 0.713 0.810 7.050 0.171 0.162 0.510 0.041 0.081 0.343 1.130 0.270 0.052 0.208 0.025 0.038 0.017 1.470 0.029 0.023 0.0080

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B100810 Result (pCi/g) 1.200 0.077 6.520 0.000 1.390 4.260 0.216 0.001 0.043 19.800

-0.119

-0.061 0.006 0.014 0.020 0.025

-1.610 0.052

-0.004 0.0100 B1002101-C Result (pCi/g) 0.763

-0.776 3.540 0.000 0.742 3.360 2.410 0.035 0.259 3.630 0.156 0.119 0.159 0.000 0.023 0.000

-0.052 0.020 0.013 0.0048 Water Reactor Plan

-16 (continu 01-CJ-FC-004-C MDC (pCi/g)

(p 0.990 0

1.430 0

11.500 5

0.229 0

0.095 0

0.339 0

0.040 0

0.143 0

0.599 0

0.166 2

0.580 0

1.370 0

0.376 0

0.065 0

0.052 0

0.042 0

2.610 1

0.034 0

0.032 0

0.0150 0.

CJ-FC-001-CV MDC (pCi/g)

(p 1.000 0

1.410 0

5.670 3

0.228 0

0.069 0

0.333 0

0.050 0

0.149 0

0.564 0

0.150 0

0.420 0

1.400 0

0.335 0

0.045 0

0.061 0

0.049 0

2.820 1

0.015 0

0.029 0

0.0143 0.

r ued)

Co CV B

R pCi/g)

(p

.685 0

.829 0

.820 15

.162 65

.255 95

.492 81

.041 99

.081 0

.350 0

.150 4

.344 0

.296 1

.220 0

.035

-0

.030 0

.028 1

.430 5

.035 3

.006 0

0142 0.

1-1.5 B

R pCi/g)

(p

.638 0

.763 0

.150 7

.159 0

.148 0

.407 5

.250 0

.066

-0

.342 0

.493 2

.236 0

.382 0

.204 0

.018

-0

.035 0

.021 0

.640

-2

.020 0

.018 0

0096 0.

2-58 oncrete Cor B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.820 0.98 0.505 1.41 5.400 13.8 5.500 0.31 5.000 0.42 7.000 0.47 9.800 0.04 0.098 0.47 0.113 0.56 4710 1.69 0.815 5.94

.250 5.46 0.073 2.12 0.012 0.06 0.920 0.62

.280 0.46 5.240 26.7 3.200 0.42 0.406 0.29

.2020 0.42 B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.094 0.91 0.372 1.38 7.770 25.0 0.000 0.25 0.872 0.13 5.730 0.38 0.106 0.04 0.034 0.14 0.032 0.52 2.440 0.14 0.125 0.38 0.271 0.95 0.099 0.32 0.007 0.05 0.004 0.06 0.009 0.04 2.090 2.70 0.017 0.04 0.029 0.02

.0059 0.03 re Isotopic A C-001-CV 0-1/2 DC

/g)

(pCi/g) 85 0.637 10 0.850 800 7.430 10 8.690 20 9.600 72 85.000 45 9.600 75 0.149 64 0.333 90 491.000 40 1.410 60 1.980 20 1.280 60 0.023 20 0.511 69 0.537 700 16.200 28 0.989 96 0.310 200 0.2670 C-001-CV 1.5-2 DC

/g)

(pCi/g) 17 0.512 80 0.819 000 11.400 59 0.188 38 0.161 88 0.646 41 0.032 42 0.083 28 0.308 46 0.343 83 0.195 56 0.406 26 0.196 52 0.019 61 0.030 41 0.021 00 1.460 41 0.025 29 0.026 331 0.0154 Analysis Re B1002 Result (pCi/g) 0.275

-0.018 0.547 0.000 1.010 0

5.640 0.253 0.029

-0.101 0

3.870 0.039

-0.260 0.077

-0.022 0.017

-0.005 0

-0.984 0.035

-0.018 0

-0.0046 B1002 Result (pCi/g) 1.710 15.400 0

8.960 423.00 300.00 2360 220.00

-0.350 0.792 25400 0.510 4.650 1.060 0.024 3.200 2.580 36.900 9.080 0.305 4

0.4280 esults 2101-CJ-FC-001 t

MDC (pCi/g) 0.931 8

1.440 5.510 0.245 0.149 0.367 0.053 0.102 1

0.507 0.137 0.444 0

1.480 0.272 2

0.064 0.059 5

0.042 4

2.680 0.037 8

0.054 6

0.0366 2101-CJ-FC-002 t

MDC (pCi/g) 1.180 0

1.510 5.860 0

0.446 0

0.762 0.661 0

0.052 0

0.935 0.562 0

4.140 13.700 7.170 7.370 0.042 0.497 0.287 0

24.000 0.682 0.388 0

0.5450

-CV 1/2-1

(pCi/g) 0.543 0.824 2.840 0.170 0.168 0.633 0.049 0.054 0.289 0.496 0.107 0.859 0.162 0.023 0.033 0.013 1.510 0.031 0.013 0.0066

-CV 0-1/2

(pCi/g) 0.846 2.310 3.640 55.200 30.200 245.000 21.100 0.567 0.373 2650 0.956 4.390 0.988 0.027 0.825 0.713 17.100 2.030 0.286 0.4200

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1002101-C Result (pCi/g) 0.846 6.180 5.270 0.000 8.270 175.000 3.520

-0.041 0.165 208.000

-0.280 0.255 0.116

-0.019 0.059 0.056

-0.965 0.238 0.005 0.0018 Water Reactor Plan

-16 (continu CJ-FC-002-CV 1 MDC (pCi/g)

(p 1.120 0

1.420 1

25.300 11 0.269 0

0.114 0

0.442 18 0.047 0

0.230 0

0.522 0

0.362 21 1.580 0

1.900 0

0.864 0

0.056 0

0.064 0

0.049 0

2.970 1

0.048 0

0.060 0

0.0438 0.

r ued)

Co 1/2-1 B

R pCi/g)

(p

.716 0

.340

-0 1.400 8

.616 0

.907 8

8.300 70

.356 7

.135 0

.312 0

1.700 1

.950 0

.259 0

.205

-0

.017

-0

.046 0

.040 0

.690 1

.080 0

.028

-0 0179 0.

2-59 oncrete Cor B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.836 0.96 0.405 1.44 8.430 17.0 0.000 0.33 8.570 0.14 0.600 0.54 7.000 0.05 0.038 0.21 0.062 0.54 1240 0.81 0.176 2.60 0.090 2.32 0.004 1.71 0.011 0.04 0.105 0.05 0.126 0.03

.500 2.56 0.339 0.04 0.001 0.03

.0175 0.01 re Isotopic A C-003-CV 0-1/2 DC

/g)

(pCi/g) 62 0.624 40 0.803 000 8.210 34 0.484 48 0.940 48 7.370 50 0.691 11 0.060 43 0.318 17 129.000 00 0.514 20 0.202 10 1.030 44 0.009 56 0.051 39 0.051 60 1.640 44 0.099 37 0.012 75 0.0203 Analysis Re 0

3 esults

La Cross License T Revision se Boiling W Termination n 0 Tab Water Reactor Plan ble 2-17 198 We Radion Mn-Co-Co-Nb-Cs-1 Ce-1 r

83 Groundw ell-Point So nuclide

-54

-57

-60

-95 137 141 2-60 water Analy outh of Turb A

(p ysis from Te bine Buildin Activity pCi/L) 63.4 6.4 508 21.4 21.7 18.9 emporary ng

L L

R La Crosse Boilin License Termin Revision 0 Jun H-3 Co-6 Sr-9 Cs-1 a

B Nov H-3 Co-6 Sr-9 Cs-1 a

B ng Water React ation Plan e 2013 MW-20 (pCi/L 572 60 4.00 90 2.05 137 3.97 Bold values indi vember 2013 MW-20 (pCi/L 235 60 4.64 90 1.18 137 4.64 Bold values indi or Table 2 01-A MW-201-B L)

(pCi/L) 2 506 0

5.01 5

2.00 7

3.84 icate concentrati 01-A MW-201-B L)

(pCi/L) 5 150 4

3.80 8

3.73 4

1.90 icate concentrati 2-18 2013 Gr B

MW-202-A (pCi/L) 660 4.76 1.82 4.05 ion greater than B

MW-202-A (pCi/L) 257 5.26 1.18 6.54 ion greater than 2-61 roundwater M MW-202-B MW (pCi/L)

(p 484 4.51 1.43 3.91 n MDC. Italicize MW-202-B MW (pCi/L)

(p 278 5.41 1.61 4.70 n MDC. Italicize onitoring Resu W-203-A MW-2 pCi/L)

(pCi N/A 42 4.95 4.1 2.06 2.0 4.52 4.3 ed values indica W-203-A MW-2 pCi/L)

(pCi 449 23 4.43 3.8 1.87 2.4 4.41 3.9 ed values indica ults 203-B MW-204-i/L)

(pCi/L) 20 397 12 4.36 06 2.18 31 4.11 ate MDC value.

203-B MW-204-i/L)

(pCi/L) 35 193 89 4.52 40 1.18 98 4.77 ate MDC value.

-A MW-204-B (pCi/L) 420 4.26 2.08 3.96

-A MW-204-B (pCi/L) 171 8.24 1.51 7.92

L L

R J

G A

G B

H C

F N

C N

S N

T C

E E

E P

P 2

P A

a La Crosse Boilin License Termin Revision 0 JUNE 2014 MW-DW3 Gross Alpha 1.26E-01 Gross Beta 1.48E+0 H-3 1.05E+0 C-14 2.79E+0 Fe-55

-2.00E+0 Ni-59 1.83E+0 Co-60 1.02E+0 Ni-63

-1.78E+0 Sr-90 6.09E-01 Nb-94 4.40E-01 Tc-99

-8.28E+0 Cs-137

-5.97E-0 Eu-152 9.48E+00 Eu-154

-5.24E+0 Eu-155

-2.67E+0 Pu-238 2.83E-02 Pu-239/240

-9.61E-02 Pu-241 3.51E+0 Am-241 5.39E-02 a

Bold val ng Water React ation Plan MW-DW4 M

D 1

-1.33E-01 4.44 0

3.13E+00 1.93 2

1.59E+02 1.94 0

0.00E+00

-3.9 01

-3.12E+01

-2.6 1

3.96E+01

-4.7 0

3.94E-01 2.5 00

-6.14E+00

-7.4 1

8.99E-02 8.9 1

1.43E-01

-1.2 00

-7.37E+00

-8.2 1

-3.47E-01

-7.4 0

2.34E+00

-7.4 00 3.16E+00 1.35 00 1.46E+00

-1.5 2

-4.77E-02

-2.2 2

3.36E-02 3.1 0

2.70E+00

-8.3 2

3.42E-02 4.6 lues indicate con tor MW-DW5 MW-DW7 4E+00

-3.78E-01 3E+00 0.00E+00 4E+02 1.23E+02 97E+00

-5.08E+00 66E+01

-3.86E+01 75E+01 2.60E+01 0E+00

-2.42E+00 40E+00

-4.38E+00 99E-02 1.78E-02 26E+00 7.49E-01 26E+00

-9.36E+00 45E-01

-1.83E+00 43E+00

-5.51E+00 5E+00

-4.73E+00 54E-01

-1.07E+02 22E-02 8.22E-02 13E-02 4.07E-01 39E+00 2.62E+00 65E-03

-1.01E-02 ncentration grea Tabl MW-B11R MW B11A 0.00E+00 7.33E 3.59E+00

-2.70E 2.45E+02 1.61E+

9.06E+00 6.83E+

-3.19E+01

-3.75E

-4.16E+00 2.53E+

8.76E-01

-1.94E

-3.57E+00 0.00E+

7.34E-01 6.11E

-6.99E-01 1.53E+

-5.52E+00

-8.46E 1.24E+00 1.84E+

-9.93E-01 1.48E+

1.63E+00

-2.61E 1.60E+00

-4.47E 0.00E+00 4.09E

-2.54E-02

-3.39E

-5.72E+00 8.38E 1.22E-02 8.37E ater than MDC.

le 2-19 2014 W-AR MW-B2

-01

-2.13E+00 6

E-01 1.12E+01 4

+02 1.60E+02 1

+00 1.94E+00

-2 E+01

-9.20E+00

-4

+00

-7.13E+00 3

E+00

-1.39E+00

-1

+00

-7.94E+00 1

E-01 6.52E-01 6

+00 1.77E+00 6

E+00

-7.41E+00

-8

+00 1.37E+00 2

+00 1.07E-01 1

E+00 2.36E+00 1

E+00 1.60E+00

-3 E-02 5.40E-02 8

E-02 3.40E-02 1

E-01 0.00E+00 E-02 3.98E-03 2

Italicized value 2-62 Groundwater MW-B3 MW-200-A 6.46E-01 4.04E+00 4.14E+00 8.66E+00 1.94E+02 5.23E+01 2.05E+00 9.26E+00 4.39E+01 1.93E+01 3.15E+01

-2.18E+0 1.13E+00 1.01E+00 1.50E+00

-1.97E+0 6.12E-01 9.86E-01 6.65E-01 1.08E+00 8.10E+00 3.55E+00 2.14E+00 1.77E-01 1.42E+01 9.71E+00 1.69E+00 5.77E-01 3.17E+00

-3.63E+0 8.29E-02

-1.38E-02 1.46E-01 2.68E-02

-7.39E-01 0.00E+00 2.28E-02 1.72E-01 es indicate MDC Monitoring Re MW-200-B M

20 0

-2.26E-01 3.84 0

-1.79E+00 7.26 1

1.24E+02 7.03 0

4.84E+00 4.84 1

-4.16E+01

-3.20 1

3.32E+01

-1.6 0

-1.27E+00

-6.0 0

-4.69E+00 1.82 1

9.98E-01 6.86 0

8.47E-01 3.73 0

5.08E+00 3.92 1

-3.64E-01 3.10 0

-1.16E+01 4.15 1

5.60E-01

-2.39 0

-3.44E+00

-2.92 2

1.51E-02 5.33 2

-1.57E-02

-6.8 0

4.49E+00

-4.8 1

9.71E-01 9.46 C value.

esults (pCi/L)

MW-01-A MW-201-B 4E-01

-1.04E+00 6E+00

-1.04E+00 3E+01 1.05E+02 4E+00 4.51E+00 0E+01 1.58E+01 7E+01

-7.11E+01 04E-02 1.73E+00 2E+00

-1.91E+00 6E-02 1.02E+00 3E-01 1.80E+00 2E+00 1.17E+00 0E-01

-6.21E-01 5E+00 1.12E+01 9E+00

-2.43E+00 2E+00

-2.60E+00 3E-02

-5.02E-02 86E-03 2.36E-02 85E-01

-1.42E+00 6E-02 3.99E-03 MW-202-A MW 202-1.06E+00 4.07E-4.34E+00 1.49E+

3.36E+02 1.06E+

0.00E+00 4.70E+

-3.26E+00

-4.54E+

2.49E+01

-1.05E+

-8.91E-01 1.02E+

-1.94E+00

-3.73E+

1.12E+00 6.05E-

-3.55E-01 1.04E-3.88E-01 2.73E+

-4.64E-01 2.86E+

4.11E+00 1.08E+

-1.12E+00

-1.18E+

-1.59E+00

-3.49E+

-8.46E-03 1.48E-

-2.27E-02

-4.54E 2.20E+00 2.72E+

1.16E-01 3.92E-W-

B MW-203-A

-01 1.74E+00

-2

+00 2.27E+00 5

+02 2.79E+02 2

+00 4.54E+00 4

+01

-4.95E+01

-4

+01

-2.71E+01

-4

+00 3.48E-02

-9

+00

-3.70E+00

-3

-01 1.17E+00 8

-01 1.59E+00 1

+00 4.36E+00 4

+00 1.48E+00 1

+01

-9.59E-01 4

+00 1.93E+00

-3

+00

-4.91E+00 4

-01

-5.67E-02

-5

-02

-2.27E-02

-3

+00 4.07E+00 1

-02 2.94E-02 7

MW-203-B MW-204-A 2.29E-01 7.58E-01 5.53E+00 2.69E+00 2.79E+02 1.06E+02 4.55E+00 4.66E+00 4.96E+01

-4.03E+01 4.66E+00

-6.22E+00 9.55E-01 1.91E-01 3.80E+00 0.00E+00 8.23E-01 2.01E+00

.50E+00 2.26E-01 4.17E+00 6.95E+00

.39E+00

-3.04E-01 4.99E+00 2.12E+00 3.69E+00 2.36+00 4.05E+00

-4.34E-01 5.87E-02

-5.12E-02 3.95E-02

-2.49E-02

.03E+01 4.07E+00 7.64E-02 1.56E-01 MW-204-B 1.27E+00 0

2.57E-01 2

3.49E+01 0

1.30E+01 1

-3.98E+00 0

-2.47E+01

-2.31E-01 0

-1.97E+00 0

6.11E-01 1.28E+00 0

6.31E+00 1.93E+00 0

7.68E+00 6.06E-01 1.66E+00 2

-9.28E-03 2

6.28E-02 0

-1.89E+00 8.24E-02

L L

R S

G G

H C

F N

C N

S N

T C

E E

E P

P P

A a

La Crosse Boilin License Termin Revision 0 September 2014 M

Gross Alpha 8

Gross Beta 2

H-3 3

C-14

-9 Fe-55 9

Ni-59 3

Co-60 2

Ni-63 2

Sr-90

-1 Nb-94

-9 Tc-99

-1 Cs-137 3

Eu-152 2

Eu-154

-3 Eu-155 2

Pu-238 1

Pu-239/240 9

Pu-241 3

Am-241 1

a Bold val ng Water React ation Plan 4

MW-DW5 MW-8.47E-01 3.09E

.96E+00 1.45E

.43E+01 0.00E 9.44E-01

-2.70E 9.39E+00

-3.10E

.13E+00 1.64E

.17E+00 1.32E

.79E+00 2.48E 1.06E+00 5.90E 9.45E-01

-1.39E 1.54E+00

-4.00

.97E+00

-7.24

.48E+00 3.00E 3.31E+00

-3.93E

.69E+00 1.95E 1.71E-02 3.69E 9.28E-02 0.00E

.18E+00

-3.68E 1.28E-01 3.69E lues indicate con tor

-B11R MW-B11A E+00 2.07E-0 E+01 3.04E-0 E+00 3.44E+0 E+00 0.00E+0 E+01

-3.49E+0 E+01

-8.49E+0 E+00 1.22E+0 E+00

-4.14E-0 E-01 2.80E-0 E+00

-1.29E-0 0E-01

-1.56E+0 4E-01 9.72E-0 E+00 6.42E+0 E+00 1.10E+0 E+00 1.69E+0 E-02

-5.50E-0 E+00

-1.10E-0 E+00

-2.29E+0 E-02

-1.69E-0 ncentration grea Table 2-19 AR MW-200-A 01 2.42E-01 01 2.41E+00 01 6.86E+01 00

-4.56E-01 01

-3.35E+01 00 7.84E+00 00 3.56E+00 01 3.62E+00 01 1.14E+00 01

-1.43E+00 00

-1.57E+00 01 2.17E+01 00

-2.39E+00 00

-6.57E-01 00

-8.16E-01 03 2.65E-02 02 5.83E-02 00

-2.23E+00 02 1.10E-01 ater than MDC.

(continued)

MW-200-B 2.01E+00 9.11E+00 5.17E+01

-4.98E+00

-4.56E+01 2.37E+01 6.20E-01

-7.87E-01 5.10E-01

-2.68E-01

-1.54E+00 1.94E+00

-1.34E+01

-1.54E+00

-1.64E+00

-6.50E-03 0.00E+00 8.49E+00 2.29E-01 Italicized value 2-63 2014 Ground MW-201-A M

1.18E+00 7.36E+00 8.67E+01 2.69E+00

-2.18E+01

-1.99E+01

-7.23E-02 5.00E+00

-1.19E-01 6.56E-01

-7.94E-01

-1.09E+00 4.79E+00

-3.09E+00

-1.48E+00

-3.59E-02 0.00E+00

-6.92E-01 1.40E-01 es indicate MDC dwater Monito MW-201-B MW 1.43E+00 1.0 3.67E+00 4.8

-3.42E+01

-5.1 9.28E-01 4.94 2.77E+01

-5.4 3.09E+01

-1.1 9.50E-01 9.7 2.15E+00 8.2

-4.99E-01 6.7 6.44E-01

-6.4

-1.95E+00 7.9 1.84E+00

-4.3 2.53E+00 9.4 1.94E+00

-3.6 4.13E+00

-2.0 8.55E-02 1.1 1.41E-01 5.8

-5.85E-01 0.0 2.80E-02 6.6 C value.

oring Results (p W-202-A MW-20 4E+00

-2.10E-86E-01 2.30E+

18E+01 1.04E+

4E+00

-2.72E+

43E+01 3.37E+

18E+01

-4.46E+

72E-01 1.18E+

25E-01

-8.30E-70E-01 5.40E-48E-02

-1.02E+

97E-01

-1.95E-34E-01 2.31E+

0E+00 6.51E+

67E-01 4.18E+

08E+00

-8.41E-13E-02 3.63E-87E-02 5.25E-0E+00

-1.76E+

62E-02 9.48E-pCi/L) 02-B MW-203-A E-01 1.37E+00

+00 1.52E+00

+02

-3.44E+01

+00

-3.95E+00

+01

-4.95E+01

+01 5.30E+01

+00 3.67E+00 E-01 1.62E+00

-01 4.80E-01

+00 8.53E-02 E-01

-1.24E+00

+00 1.56E+00

+00 4.06E+00

+00

-3.33E+00 E-01

-9.54E-02

-02 7.08E-02

-02 9.15E-02

+00 5.04E-01

-02 2.51E-01 A

MW-203-B

-6.68E-01 1.00E+00 1.21E+02 0

4.89E-01 4.32E+01

-4.34E+01 1.99E+00

-1.77E+00 8.70E-01 2.16E+00 0

-3.32E+00 6.84E-01

-1.15E+00 0

-2.31E-01

-3.66E-01 8.12E-02 5.97E-02

-3.71E+00 1.03E-01 MW-204-A 6.00E-01 5.28E+00 6.88E+01 4.73E-01 3.45E+01

-3.13E+01

-3.77E-01

-1.84E-01 9.00E-01 1.18E-01

-1.96E+00

-1.14E+00

-1.92E+01

-4.95E+00

-2.02E+00

-6.45E-04

-5.48E-03

-3.97E+00 1.06E-01 MW-204-B 3.53E+00 0.00E+00

-1.21E+02 9.46E-01

-9.25E+01

-1.87E+01 2.05E+00 3.94E-01 2.30E-01

-1.88E+00 3.89E-01 1.24E+00 2.23E+00 2.36E+00 9.46E-01

-3.26E-02 7.02E-02

-6.46E+00 2.69E-01

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan Figure or e 2-1 LACBWR Site Map -

2-64

- Open Land Survey Units annd Classificatioon

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-2 LACBWR 2-65 Site Map - Buildings Identifiication

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-3 r

LACBWR 2-66 R Site Drainnage and Seewer Map

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-4 r

LACBWR 2-67 R LCE Excllusion Area (Class 1)

La Cross License T Revision se Boiling W Termination n 0 Figu Water Reactor Plan ure 2-5 N

r Non Impacte 2-68 ed Open Laand Samplinng Locations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-6 r

Class 1 O 2-69 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-7 r

Class 2 O 2-70 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-8 r

Class 3 O 2-71 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan Figure 2-9 r

9 Concre 2-72 ete Core Sam mpling Loccations

La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r

inued) 2-73 Concrete CCore Sampliing Locationns

La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r

inued) 2-74 Concrete CCore Sampliing Locationns

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-10 LACBWR Si 2-75 ite - Typical Geological Crosss-Section

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-111 Groundwat 2-76 ter Sampling Wells - LACBW WR Site

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

La Cross License T Revision 2.

Site 2.1.

2.1.

2.1.

2 2

2 2

2 2.1.

2.1.4 2

2 2.1.

2.1.

2 2

2 2

2 2

2 2

2.2.

2.2.

2.2.

2 2

2 2

2.2.

2 2

2.2.4 2.2.

2.3.

2.3.

2.3.

2.3.

2.3.4 2

2 se Boiling W Termination n 0 Characteriz Historical S 1.

Objecti 2.

Method

.1.2.1. Pre

.1.2.2. Doc

.1.2.3. Lic

.1.2.4. Per

.1.2.5. Pro 3.

Operati 4.

Inciden

.1.4.1. Rad

.1.4.2. Che 5.

Finding 6.

Initial S

.1.6.1. Sur

.1.6.2. Sur

.1.6.3. Cla

.1.6.4. Cla

.1.6.5. Cla

.1.6.6. Non

.1.6.7. Cla

.1.6.8. Cla Characteriz 1.

Data Q 2.

Survey

.2.2.1. Num

.2.2.2. Det

.2.2.3. Sca

.2.2.4. Typ 3.

Instrum Concen

.2.3.1. Cal

.2.3.2. Inst 4.

Labora 5.

Quality Summary o 1.

Backgr 2.

Potenti 3.

Non-Im 4.

Impact

.3.4.1. Cla

.3.4.2. Cla Water Reactor Plan zation..........

Site Assessm ives............

dology........

liminary Cla cument Revi enses, Perm rsonnel Inter operty Inspec ional History nts...............

diological Sp emical Spills gs and Conc Survey Area rvey Areas..

rvey Units...

ass 1 Open L ass 2 Open L ass 3 Open L n-Impacted O ass 1 Structur ass 2 and 3 S ation Appro Quality Objec y Design......

mber of Stat termination o an Coverage pes of Measu mentation Se ntrations (M libration......

trument Use atory Instrum y Assurance f Characteri round Study ial Radionuc mpacted Ope ed Open Lan ass 1 Open L ass 2 Open L r

TABLE O ment..............

assification..

iew..............

mits and Auth rviews..........

ctions...........

y..................

pills.............

s..................

lusions........

as/Units and Land Areas...

Land Areas...

Land Areas...

Open Land A res...............

Structures.....

ach..............

ctives...........

tic Measurem of Static Me urements and lection, Use MDCs)..........

e and Contro ment Method zation Surve clides of Con en Land Area nd Areas.....

Land Areas...

Land Areas...

2-i OF CONTE horizations...

Classificatio Areas..........

ments and/or easurement a d Samples...

and Minimu l..................

ds and Sensit ey Results...

ncern............

as................

ENTS on................

r Samples....

and Sample L um Detectab tivities.........

Locations....

ble

... 2-1

... 2-2

... 2-2

... 2-3

... 2-3

... 2-4

... 2-5

... 2-5

... 2-5

... 2-6

... 2-6

... 2-7

... 2-8

... 2-8

... 2-9

... 2-9

... 2-9

. 2-10

. 2-10

. 2-10

. 2-11

. 2-11

. 2-12

. 2-12

. 2-14

. 2-14

. 2-15

. 2-16

. 2-16

. 2-16

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. 2-18

. 2-19

. 2-19

. 2-19

. 2-20

. 2-21

. 2-22

. 2-22

. 2-24

. 2-25

. 2-26

La Cross License T Revision 2

2.3.

2.3.

2 2

2 2.3.

2 2

2 2

2 2.4.

2.5.

se Boiling W Termination n 0

.3.4.3. Cla 5.

Non-Im 6.

Impact

.3.6.1. Bas

.3.6.2. Tur

.3.6.3. LA 7.

Surface

.3.7.1. Are

.3.7.2. Gro

.3.7.3. Pre

.3.7.4. On-

.3.7.5. Sum Continuing References Water Reactor Plan ass 3 Open L mpacted Stru ed Structure sement Struc rbine Buildin ACBWR Adm e and Groun ea Groundwa oundwater F vious Invest

-Going Inve mmary of Gr Characteriza r

Land Areas...

uctures.........

es and System ctures Below ng Tunnel....

ministration dwater........

ater Use......

low.............

tigations......

stigations....

roundwater A ation...........

2-ii ms...............

w 636 foot El Building.....

Analytical R levation......

Results.........

. 2-27

. 2-29

. 2-30

. 2-30

. 2-31

. 2-31

. 2-32

. 2-32

. 2-33

. 2-34

. 2-35

. 2-35

. 2-36

. 2-37

La Cross License T Revision Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 2-5 Table 2-6 Table 2-7 Table 2-8 Table 2-9 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Table 2-1 Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-Figure 2-se Boiling W Termination n 0 1

LACBW 2

LACBW 3

Instrum 4

Off-Sit 5

2005 D 6

Investig 7

Initial S 8

Non-Im Survey 9

Non Im Labora 10 Impact Summa 11 Class 1 Labora 12 Impact Survey 13 Class 2 Labora 14 Impact Survey 15 Class 3 Labora 16 Concre 17 1983 G Buildin 18 2013 G 19 2014 G

-1 LACBW

-2 LACBW

-3 LACBW

-4 LACBW

-5 Non Im

-6 Class 1

-7 Class 2

-8 Class 3

-9 Concre

-10 LACB

-11 Ground Water Reactor Plan WR Open L WR Structur ment Types a te Laboratory Dairyland Ba gative Level Suite of LAC mpacted Ope y Summary.

mpacted Coa atory Analys ed Class 1 O ary.............

Concrete, A atory Analys ed Class 2 O y Summary.

2 Asphalt, Se atory Analys ed Class 3 O y Summary.

3 Asphalt, Se atory Analys ete Core Isot Groundwater ng...............

Groundwater Groundwater WR Site Ma WR Site Ma WR Site Dra WR LCE Ex mpacted Ope Open Land 2 Open Land 3 Open Land ete Core Sam WR Site - T dwater Samp r

LIST and Survey ral Survey U and Nominal y Analytical ackground St ls for Cs-137 CBWR Site-en Land Surv l Pile and So sis (pCi/g)....

Open Land S Asphalt, Sed sis (pCi/g)....

Open Land S ediment and sis................

Open Land S ediment and sis (pCi/g)....

opic Analys Analysis fro Monitoring Monitoring LIST O ap - Open La ap - Building ainage and S xclusion Are en Land Sam d Sampling L d Sampling L d Sampling L mpling Locat Typical Geolo pling Wells -

2-iii OF TABLE Units...........

Units.............

l MDCs.......

l Methods an tudy for Soil 7 Based on B

-Specific Ra vey Units - C oil Samples -

Survey Units diment and S Survey Units Soil Sample Survey Units Soil Sample is Results....

om Tempora Results......

Results (pC OF FIGURE and Survey U gs Identifica Sewer Map..

ea (Class 1)..

mpling Locati Locations.....

Locations.....

Locations.....

tions............

ogical Cross

- LACBWR ES nd Typical M ls.................

Background

dionuclides.

Characteriza

- Test Amer

- Character Soil Samples

- Character es - Test Am

- Character es - Test Am ary Well-Po Ci/L)............

RES Units and Cl ation.............

ions.............

s-Section.....

R Site...........

MDCs..........

Studies.......

ation rica rization Surv

- Test Ame rization merica rization merica oint South of lassification vey erica f Turbine

. 2-39

. 2-40

. 2-42

. 2-43

. 2-44

. 2-45

. 2-46

. 2-47

. 2-49

. 2-50

. 2-51

. 2-52

. 2-53

. 2-54

. 2-55

. 2-56

. 2-60

. 2-61

. 2-62

. 2-64

. 2-65

. 2-66

. 2-67

. 2-68

. 2-69

. 2-70

. 2-71

. 2-72

. 2-75

. 2-76

La Cross License T Revision AEC ALARA bgs CRD DCGL DQO EPA FCP FESW FRS FSS G-1 G-3 HSA HTD IR ISFSI LACBW LER LSA LSE LTP MARLA MARSA MARSSI MDC MDCR MWe NIST se Boiling W Termination n 0 United As Lo Below Contr Deriv Data Q United Force Fuel E Final Final Genoa Genoa Histor Hard-Incide Indep WR La Cr Licen Low S LACB Licen AP Multi-AME Multi-Manu IM Multi-Minim Minim Megaw Nation Water Reactor Plan LIST OF d States Ato ow As Reaso w Ground Su ol Rod Driv ed Concentr Quality Obje d States Env d Circulation Element Stor Radiation Su Status Surve a 1 Coal/Oil a 3 Fossil St rical Site As to-Detect ent Reports endent Spen rosse Boiling see Event R Specific Act BWR Site En se Terminati

-Agency Rad

-Agency Rad ual

-Agency Rad mal Detectab mum Detecta watt Electric nal Institute r

ACRONYM mic Energy onably Achie urface e

ration Guide ective vironmental P n Pump rage Well urvey ey Station tation sessment nt Fuel Stora g Water Reac eports ivity nclosure ion Plan diological L diation Surv diation Surv ble Concentr able Count R c

of Standard 2-iv MS AND AB Commission evable line Levels Protection A age Installatio ctor Laboratory A vey and Asse vey and Site rations Rate ds and Techn BBREVIAT n

Agency on Analytical Pro essment of M Investigatio nology TIONS otocols Man Materials and n Manual nual d Equipmentt

La Cross License T Revision NRC ORC PSDAR QA QAPP QC RCA REMP ROC RPV SRC STS TSD WDNR WGTV WTB ZNPS se Boiling W Termination n 0 United Opera Post-S Qualit Qualit Qualit Radio Radio Radio React Safety Sourc Techn Wisco Waste Waste Zion N Water Reactor Plan d States Nuc ational Revie Shutdown D ty Assurance ty Assurance ty Control ologically Co oactive Efflu onuclides of or Pressure V y Review Co e Term Surv nical Suppor onsin Depart e Gas Tank V e Treatment Nuclear Pow r

clear Regula ew Committ ecommissio e

e Project Pla ontrolled Are ent Monitor Concern Vessel ommittee vey rt Document tment of Nat Vault Building wer Station 2-v atory Commi ee ning Activit an ea ing Reports tural Resour ission ties Report rces

La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan r

Page Intent 2-vi tionally Leftft Blank

La Cross License T Revision

2.

S In accor Regulato Nuclear character The purp conducte remain.

License T of compl Survey (

1575, Mu Source T terminati The site quantify character site that classifica The cha NUREG-Decomm

Criteria, PG-EO-3 Reactor Characte the Data informati remediat at concen removed The deco waste of LACBW None of radiologi planned a G-3 pow minor str The majo basement se Boiling W Termination n 0 Site Chara rdance with ory Guide 1.

Power Re rization perfo pose of site ed in all are The term F Termination liance survey FSS) for op ulti-Agency Term Surve ion. See LTP characteriz the extent a rization surv will require ation and vol aracterization

-1575 (MA issioning G Final Repor 313196-SV-P (4), and GP erization Pro Quality Obj ion obtained ion planning ntrations gre and properl ommissionin f all LACB WR Administ f the buildin ically impac and these str wer operation ructures will or sub-grade ts of the Re Water Reactor Plan acterization h the requi

.179, Standa eactors (1),

formed at the characteriza eas where co Final Radiat n Plan (LTP) ys that will b pen land are Radiation S ey (STS) fo P Chapter 5 ation incorp and nature o veys and ana remediation lumes, and e n survey w ARSSIM)

Guidance - C rt, (3). In ad PL-001, Ch P-EO-31319 oject (QAPP jective (DQO d from the

g. Materials eater than th ly packaged ng approach BWR buildi tration build ngs and stru cted such th ructures, inc ns. The pub l also remain e structures t eactor Buildi r

n rements of ard Format

, this chap e La Crosse B ation is to en ontamination tion Survey

) in order to be performed eas and buri Survey and S or below gr for a descrip porates the r of contamin alyses have b n, as well as estimate cost was designed and NURE Characteriza ddition, surv haracterizatio 96-QA-PL-00 P) (5) which O) process, a characteriz which were he unrestricte for shipmen for LACBW ings, structu ding and Cri uctures asso hat they requ cluding the G blic roads an

n.

that will be ing, Waste T 2-1 f 10 CFR 50 and Conte pter provide Boiling Wat nsure that th n existed, re is from 10 acknowledg d at LACBW ed piping b Site Investig round struct ption of the results of in ation at LA been and con s to plan rem ts.

d and exec EG-1757, ation, Surve veys were de on Survey P 01, Quality describes p and measure zation provi e shown to b ed release cr nt and dispos WR requires ures and co ib House) to ociated with uire remedi G-3 Crib Hou nd railways backfilled a Treatment B 0.82 (a)(9)(ii ents for Lic es a descr ter Reactor (

he Final Rad emains, or h 0 CFR 50.82 ge the distin WR. These ased on gui gation Manu tures to be FRS.

nvestigation ACBWR. In ntinue to be mediation m cuted using Volume 2, ey, and De esigned and Plan for th Assurance policy, organ es necessary des guidanc be contamina riteria have sal.

the demolit omponents o a depth of h the Genoa al actions; use, will rem that travers and remain a Building (W i)(A) and t ense Termin ription of (LACBWR) diation Surv has the pote (9)(ii)(D) an nction betwe surveys are; idance provi al (MARSS backfilled ns and surve n addition, th e used to ide methodologie the guidan Revision 1 termination executed in e La Cross Project Pla nization, fun to achieve q ce for deco ated with rad been and wi tion, remova (with the e f at least 3 f a 3 Fossil S therefore, n main intact a se the site a at license ter WTB), Waste the guidanc nation Plan the radiolo site.

ey (FRS) w ential to exi nd is used in een the two

1) a Final S ided in NUR SIM) (2) and prior to lic eys conduct he results o ntify areas o es, develop w nce provide 1,

Consolid of Radiolo n accordance se Boiling W an LACBWR nctional activ quality data.

ontamination dioactive ma ill continue al and dispos exception o feet below g Station (G-3 no remediati and function as well as se rmination ar Gas Tank V ce of ns for ogical will be ist or n this types Status REG-d 2) a cense ed to of site of the waste ed in dated ogical e with Water R Site

vities, The n and aterial to be sal as f the grade.
3) are ion is al for everal re the Vault

La Cross License T Revision (WGTV)

(3 feet b Reactor/G sump and In the R removed removed elevation WTB, th concrete the rema cap and p following covered b remainin LTP Cha Independ shown in 2.1.

H In accor Assessm informati

reports, marine f Environm compiled 2.1.1. O The HSA LACBW surround resulted Radiolog subsurfac the 1.5 a informati may also The scop hazardou The obje Id b

se Boiling W Termination n 0

) and the re elow grade)

Generator P d the Turbin Reactor Bui

. All intern

, leaving on n (i.e., concr he only porti footers belo ining structu piles below t g the termina by at least 3 ng backfilled apter 1, sec dent Spent F n Figure 2-1)

Historical Si rdance with ent (HSA) ion, includin pre-operatio fauna and s mental Repo d for this inv Objectives A was a d WR activities dings. The in contamin gically Contr ce soils outs acre fenced ion compile o be used as pe of the us materials.

ctives of the dentify pote ased on exis Water Reactor Plan emainder of

). These re Plant, the on e pit.

lding, all in nal concrete nly the rema rete bowl on of the str ow the 636 fo ure will cons the 636 foot ation of the l feet of soil d structures to ction 1.3.1 d Fuel Storage

) is excluded te Assessme h the guida (6) was p ng any 10 C onal survey sediment su orts to the vestigation.

detailed inve related to r HSA focuse nation of pla rolled Area (

ide of the R LACBWR d by the HS input into th HSA inclu e HSA were ntial, likely sting or deriv r

f the baseme maining stru ne foot thick nternal stru will be rem aining struct below 636 ructure that oot elevation sist of the fl elevation. T license are c and physica o be plausibl describes th Installation d from the sc ent ance provid performed a CFR 50.75(g data, spill urveys), ope Nuclear Re estigation to radioactive m ed on histor ant systems, (RCA). It al RCA but with Site Enclos SA was used he developm ded potenti to:

, or known ved informat 2-2 ent structure uctures inclu k portion of uctural surfa moved to ex tural concre foot elevatio will remain

n. In the WG loors and fou The structur constructed o ally altered t ly occupied.

e site licen (ISFSI) Fac cope of the L ded in MAR and docume g) files, emp reports, spe rational sur egulatory C o collect ex materials or rical events

, buildings, lso addresse hin the owne sure (LSE) d to establis ment of reme ial contamin sources of

tion, es located b lude the Pip f the Chimn aces, system xpose the ste ete outside t on, concrete is the 630 a GTV and the undation wa ral surfaces t of steel reinf to a conditio nse boundary cility as loca LTP.

RSSIM, sec ented in Au ployee inter ecial survey rvey records Commission xisting info other conta and routin surface and d support str er controlled area share sh initial sur ediation plan nation from radioactive below the 63 ping and Ve ney Foundat ms and com eel liner, wh the liner be e pile cap an and 635 foot e other rema alls as well a that will rem forced concr on which wo

y. The fen ated in Lot 7 ction 3.0, a ugust of 19 rviews, radi ys (e.g., site s, and Ann (NRC) wer ormation (fr aminants) fo ne operationa d subsurface ructures, ope d area. The e the same rvey units.

ns and the de m radioactiv and chemi 36 foot elev entilation Tu tion, the Tu mponents wi hich will als low the 636 nd piles.) I t floor, sump aining basem as concrete p main at LACB rete which w ould not allow nced area o 7 of the site a Historical 999. Histo ological inc e aerial sur nual Radiolo re reviewed rom the sta or the site an al processes e soils withi en land area current RCA boundary.

This inform esign of the ve materials cal contami vation

unnel, urbine ill be so be 6 foot In the p and
ments, piling BWR will be w the of the e (and Site orical cident
rveys, ogical d and art of nd its s that in the as and A and The mation FRS.

s and inants

La Cross License T Revision D

n P

P P

P M

D 2.1.2. M The obje may have land area failures r material.

contamin decontam their pote Each inc was furth

analysis, sampling location.

Relevant remediat Also incl R

P p

S id Informat data, eva Units.

2.1.2.1.

The HSA classifica have a p se Boiling W Termination n 0 Distinguish p o threat to h rovide an as rovide infor rovide an in rovide a gra MARSSIM g Delineate init Methodology ective of the e significant as and struct resulting in Dependin nation varies mination acti ential for con ident identif her investiga any remed g, survey, an Historical r t informatio ion phases o luded in the Relevant exce ersonnel int lant personn ite inspectio dentify, locat ion from thi aluation of r Prelim A investiga ation of the potential for Water Reactor Plan portions of th uman health ssessment of rmation usefu nitial classific aded initial c guidance, and tial survey u y

HSA record tly impacted tures. These airborne rel ng upon pa s by area. In ivities and F ntamination.

fied that pos ated. This in dial actions nd analysis i records prov on that bec of the license research ass erpts from w terviews, inc nel to confir on, utilizing te, confirm, is research w results, docu minary Class ation was d site land are contaminati r

he site that m h,

f the likeliho ful to subsequ cation of are lassification d

unit boundari ds search and d the hazardo e included sy eases, liquid ast site ope n order to fac RS planning sed a realisti nvestigation taken to m in an attemp vided the sou comes avail e termination sociated with written report cluding the u rm documen g historic si and docume was used in umentation o sification designed to eas and struc ion (based o 2-3 may need fur od of contam uent continu eas and struc n for impacte ies and areas d interview ous material ystem, struc d spills or re erations and cilitate effec g, land areas ic potential t n focused on mitigate the s pt to identify urce of a vast lable during n plan will b h the develop ts and corres use of quest nted incident te drawings ent areas of c the HSA de of findings, o obtain su ctures as imp on historical rther action minant migra uing characte ctures as non ed soils and s s based upon process was l or radiolog cture, or area eleases, or t d processes, ctive charact s and structu to impact th n the scope o situation, an fy the as le t majority of g any addi be evaluated.

pment of the spondences, tionnaires, o ts and ident s, photograp concern.

evelopment, and the ide ufficient info pacted or no l data) or co from those

ation, erization sur n-impacted o structures in n the initial c s to identify gical status o a contamina the loss of c

, the poten terization, an ures are class he characteri of contamina nd any post eft conditio f the docume itional char e HSA were:

of current, fo tify undocum phs, prints, including th entification formation to on-impacted ontain know that pose lit

rveys, or impacted, n accordance classification those event of LACBWR ation from sy control over ntial for res nd to guide f sified based ization of th ant sampling t-remedial a n of the inc ents inspecte racterization ormer and re mented incid and diagram he compilati of initial Su o provide i

. Impacted wn contamin ttle or e with

n.

s that R site ystem solid sidual future upon e site g and action cident ed.

n and etired

dents, ms to on of urvey initial areas nation

La Cross License T Revision (based o through k is no rea impacted controlle If a land area clas was mad Initial cl historical initial cla at the tim prepared FRS desi classifica continuin surveillan classifica of comm 2.1.2.2.

Records source of for LACB include:

O S

L S

O A

E R

D H

S R

se Boiling W Termination n 0 on past or p knowledge o asonable po d from a ra d areas were area or struc ssification (e e based upon lassification l radiologica assification a me of identifi

. Final clas ign. The ch ations indica ng characteri nce, and an ations (for ex mencement of Docum maintained f documenta BWR, many Operational R afety Review Licensee Eve ite Initiated Operator Log Annual Envir Environmenta Regulatory ac Documentatio Health Physic ite inspectio Radiological Water Reactor Plan preliminary of site history ssibility for adiological p e also docum cture was cla e.g. Class 1, n the inform of LACBW al survey dat and (2) final ication of the ssification is haracterizatio ated in the H ization surve ny other ap xample, from f the FRS.

ment Review to satisfy t ation for the y record type Review Com w Committe ent Reports (

Incident Rep gs including ronmental M al investigat ctions conce on from inte cs surveys an on and survei and environ r

radiological y or previou residual ra perspective.

mented.

assified as im Class 2 or C mation obtain WR areas w ta. Classify l classificati e survey are s performed on data was HSA as descr eys, operatio pplicable sur m Class 3 to w

the requirem e HSA recor es were eval mmittee (ORC ee (SRC) Me LER) Summ ports (IR),

Reactor Ope Monitoring R tions perform erning the sit rviews cond nd sampling illance type nmental surv 2-4 l surveillanc us survey inf adioactive co Potential mpacted, the Class 3) in a ned.

was based o ying a survey ion. Initial c a using the i and verified used to val ribed in this onal surveys rvey data m o Class 2 and ments of 10 rds review p luated. A su C) Meeting M eeting Minut

maries, erator and H
Reports, med by indep te, ducted with r g results asso documents a ey documen ce). Non-im formation an ontamination chemical h en a determi accordance w on historica y area has a classification information d as a DQO lidate or upd Chapter. R s in support may cause d from Clas CFR Part 50 process. Dur ummary of t
Minutes, tes, Health Physic pendent entit retired/separ ociated with associated w
nts, mpacted are nd are those a
n. Areas w hazards incid ination of the with MARS al informatio minimum o n of most ar available wh O during cha date, as nece Radiological of decommi an increase ss 2 to Class 0.75(g)(1) p ring the con the types of cs entries,
ties, rated site per identified ev with identifie eas are iden areas where were classifie dents on ow e initial imp SSIM, sectio on and avai of two stage reas is perfo hen the HSA aracterization essary, the i survey data issioning, ro e in survey s 1) until the provided a m nduct of the records revi
rsonnel, vents, ed events, ntified there ed as wner-pacted on 2.2 ilable s: (1) ormed A was n and initial from outine area e time major HSA iewed

La Cross License T Revision Q

2.1.2.3.

LACBW permits.

allowed D the site, activities Several g licensing U

U U

W L

From Au This peri 1987, and 2.1.2.4.

Interview about the The pers the partic personne terms be site know Between individua standardi site perso the perso memorie operation 2.1.2.5.

Several Several s se Boiling W Termination n 0 Quality Contr Licen WR was opera The NRC Dairyland P to support o

s.

government g, constructio United States United States United States Wisconsin De Local/County ugust 28, 197 iod includes d ISFSI cons Person ws with curre e site and to onnel interv cipants as w el were chos ing investig wledge and e 2010 and als contacte ized personn onnel who w onnel observ s of other q nal period ex Prope on-site prop site events of Water Reactor Plan rol (QC) /Qu ses, Permits ated in accor Operating L ower Coope operations du and regulato on, operation s Atomic Ene s Nuclear Re s Environmen epartment of y Governmen 73 to the pre s power ope struction and nnel Intervie ent or previo verify or cl views includ well as indivi sen due to th ated for the experience th 2011, appr ed as part nel survey w worked at th vations docum questionnaire xperience, or rty Inspectio perty inspec f interest we r

uality Assura and Author rdance with License for erative (Dair uring its ope ory agencies ns, and decom ergy Commi egulatory Co ntal Protecti f Natural Re nts.

esent, the fac erations to 1 d spent fuel ews ous employe arify inform ded a combin idual and gro heir knowled assessment.

hat ranged fr roximately 4 of the HS which was c e LACBWR mented on th e completers r by docume ons ctions were ere identified 2-5 ance (QA) fi izations several Fed LACBWR a ryland) to us erating lifeti have provid mmissioning ission (AEC ommission (N ion Agency (

esources (WD cility has bee 1987, perma off-load whi ees were per mation gather nation of qu oup interview dge of and a

. A number rom the site c 40 recollecti SA question completed v R during its o he questionn s, current on ntation disco made over d which were finding type d deral and Sta and support se any quant ime, and to ded oversigh

g. These age C),

NRC),

(EPA),

DNR),

en operated u anent shutdo ich was com rformed to c red from the uestionnaires ws with sev association r of the pers construction ions of inte nnaire progr voluntarily b operational naire were c n-site worki overed durin r the course e subsequent documents.

ate of Wisco ting Technic tity of radioa implement d ht at LACBW encies includ under NRC own for dec mpleted in 20 collect first-h e records tha s completed veral of the p with the sys sonnel interv n period to sh erest were l ram. This by retired/sep years. With corroborated ing staff tha ng the record e of the HS tly documen onsin license cal Specifica active mater decommissio WR during s de:

License DPR commissionin 012.

hand inform at were revie by a majori participants.

stems and so viewed poss hutdown.

logged from consisted parated staf h few except d either by lo at had LACB ds search.

SA developm nted in the H es and ations rial at oning

siting, R-45.

ng in mation ewed.

ity of Key ource essed m the of a ff and

tions, ogged BWR ment.

HSA.

La Cross License T Revision 2.1.3. O LACBW Dairylan Mississip bordered Mississip LSE com served as confirme road on t th fo an 1

th a

li The plan Chalmers provided LACBW 19 years defueling Operatin No. 56, d 333 irrad into five Limited d ongoing shipped internals Building removed undergro Condens Water Sy Building 2.1.4. In Based on notificati se Boiling W Termination n 0 Operational WR was a 5

d. This sing ppi River so d on the no ppi River an mprising app s the RCA b ed to be suit the south sid he land north ormer Genoa n operationa 75 feet from he fenced ISF small parce icensed site.

nt was one s Company d them with a WR achieved until it was g was compl g License D dated Augus diated fuel as (5) dry cask dismantleme at LACBW for disposal intact, and 2

, and shippe

, including t ound gas sto ate Storage ystem pump ncidents n the review ions, occurre Water Reactor Plan History 50 Megawatt gle unit, also outh of the orth by the nd Highway proximately boundary du table for unr de of the plan h of the LA a Station #1 al 350 MWe m the LSE, FSI facility t l of land to t of a series was the ori a provisional d initial criti s permanent leted on June DPR-45, pur st 4, 1987; a ssemblies, w ks and transfe ent of shutdo WR since 199 l in June 20 29 control ro ed for dispo the spent fue orage tanks)

Tank and s, heat exch w of existin ence reports r

t Electric (

o known as G Village of Mississippi

35. The lic 1.5 acres of uring operat restricted us nt. Other pro ACBWR plan (G-1) coal (

fossil gener that is locate the east of H of demonst iginal licens l operating l icality on Ju tly shut dow e 11, 1987.

rsuant to 10 and a posses which were i ferred to the own and unu

94. Waste s 007. The R ods in place osal in June el storage rac

); Condensa condenser);

angers, pipin g plant reco s, and questi 2-6 (MWe) Boil Genoa Statio f Genoa, Ve i River and ensed site c the licensed tions. Mate e before rel ominent feat nt, including (and later oil rating station ed directly so Highway 35, tration plant see; the AEC icense.

uly 11, 1967 wn by Dairy The Dairyla 0 CFR 50, w ss but not-op in Fuel Elem sites ISFSI used systems stored in the Reactor Pres was filled w e 2007. Oth cks, Gaseou ate system Turbine an ng and comp ords (e.g. an ionnaires), i ling Water on #2, is loc ernon Coun d a narrow omprises a t d site. The erial leaving ease. The s tures on the g the site sw l) fueled pow n (G-3) loca outh of G-3, across from ts funded in C later sold 7, and was yland on Ap and authority was terminat perate status ment Storage by Septemb s and waste e FESW and sure Vessel with concret her systems us Waste Dis and Feedwa nd Generato ponents that nnual and s incidents wi Reactor th cated on the nty, Wiscons strip of la total of 163 LSE bounda g the LSE w site is acces site include:

witchyard an wer plant (re ated south an

, and m LACBWR n part by A d the plant t operated fo pril 30, 198 y to operate ated by Lice s was grante e Well (FES ber 2012.

disposal op d other Clas (RPV) wit te, removed and compo sposal System ater system or; and Com t were locate semi-annual ith radiologi hat is owne east shore o sin. The s and between

.5 acres, wit ary is fenced was surveyed sed by an a nd the site o moved in 19 nd approxim that is part o AEC. The A to Dairyland or approxim

7. Final re LACBWR u ense Amend ed by NRC.

SW), were p erations has ss B/C waste th head insta from the Re onents have m (except fo m (except fo mponent Co ed in the Tu reports, lice ical or hazar ed by of the ite is n the th the d and d and access of the 989),

mately of the Allis-d and mately eactor under dment The placed been e was

alled, eactor been or the or the ooling urbine ensee rdous

La Cross License T Revision material placing t the LSE the struct LSE, wh Special Monitori reports c shutdown around th posing a of LACB contamin 2.1.4.1.

The hist involving potential chronolo T

fl In W

In su In d

st O

th 8

O th 8

O ap In O

in se Boiling W Termination n 0 implication the reactor in and, while c tures and so ich is alread emphasis w ing Reports covering the n in 1987.

he plant site significant p BWR site nation from s Radio torical revie g system lea to affect th gical order a The stainless loor. Inciden ncidents inv Water Discha n 1970, pot uppression o n

Septemb econtaminat team cleanin On Novembe he potential 0-84 Inciden On Novembe he Turbine B 7, ORC-80-9 On Decemb pproximately ncident Repo On December nto the Turbi Water Reactor Plan ns occurred n a SAFSTO contributing ils directly r dy known to was placed o (REMP), fo e periods o Available sa e were also probability o land areas system failur ological Spill ew indicated akages, radio e classificati as follows; steel liner nts involving olving leaka arge line wer tentially con on the license

ber, 1977, tion of a Fo ng tank in the er 5, 1980, p for leakage nt Report, OR er 24, 1980, Building. (D 97, LER 80-ber 6, 1980 y 1/2 gallon ort, ORC-80 r 15, 1980, t ine Building r

between th OR conditio to the radiol related to the be impacte on obtainin focusing on of SAFSTOR ampling resu reviewed. T of impacting and structu res resulting ls d that betwe ological spill ion of LACB in the FESW g leakage of age from the re noted from ntaminated ed site roads removable orced Circul e Reactor Bu artial blocka of drain wa RC-80-71, O residual rad DPC-80-93 I

-12)

, the Turb of waste w 0-71, ORC-8 the Turbine g Basement T 2-7 he commenc n in 1987.

logical conta e operation o ed.

g and revie gaseous an R and deco ults associat The objectiv g the radiolo ures. Thes g in airborne een 1967 a ls, and/or rad BWR structu W had a his f the FESW w e resin regen m 1967 to 19 Control Rod

s.

e alpha c

ation Pump uilding 701 f age of drain ater into the ORC-80-75, dioactive con Incident Rep bine Build water to the 0-75, ORC-Building Wa Tunnel. (DP cement of p All of these amination an of the reacto ewing the a nd liquid rel ommissionin ted with soi ve was the i ogical status se included releases, liq and 1987, th dioactive liq ures or soils story of leak were noted f neration was 973.

d Drive (C contaminatio (FCP) duri foot elevatio lines under soil under th ORC-80-87 ntamination port, ORC-8 ding Waste Turbine Bu 80-87, ORC aste Water T PC-80-106 In plant operati e incidents t nd potential or, were con annual Radi leases since ng activities il and groun identification or hazardou system, st quid spills or here were s quid effluent

s. The incid kage to the R from 1967 to ste system t CRD) oil wa on was d

ing mainten on. (ORC, 0 Turbine Bu he Turbine B 7, ORC-80-9 n was detect 80-71, ORC-Water T uilding floor C-80-97)

Tank overflo ncident Repo ion in 1967 took place w contaminati ntained withi ioactive Eff 1967, inclu s after the ndwater with n of those e us material s tructure, or r releases.

several inci releases wit dents are list Reactor Bui o 2012.

to the Circul as used for detected d

ance involv 09/27/77) uilding result Building. (D

97) ed in soils u 75, ORC Tank overfl
r. (DPC-80 owed waste w ort) 7 and within ion of in the fluent uding plant hin or events status area idents th the ted in ilding lating dust during ving a ted in DPC-under C owed 0-102 water

La Cross License T Revision In w

D O

un O

co in O

si co B

to O

ap b

2.1.4.2.

Between release o ranged fr and fuel impacted policies releases.

2.1.5. F LACBW within its been imp post ope Survey fo for fissio Structure Turbine Stack. In to be dire An area s support b various w se Boiling W Termination n 0 ncidents invo waste water t Discharge lin On January nspecified v On May 31, ontaminated nto the basem On July 02, 1 ight flow se ontaminated Bay door. In o an unrestri On July 16, pproximately asement floo Chem 1967 and 20 of chemicals rom spills of oil from sy d buildings.

and proced Findings and WR was desig s many syste pacted due t erational his or SAFSTOR on products t es classified Building, W n addition to ectly impacte surrounding buildings su warehouses a Water Reactor Plan olving leaka tanks throug ne were noted 30, 1981, volume of wa 1982, a lid d water and ment. (DPC 1982, approx eal rupture t d water flow n addition, a cted area. (D 1983, a leak y 15,000 gal or. (LER 83 mical Spills 014, the HSA s and/or pote f acids and c ystems and These spills dures for id d Conclusio gned with mu ems, compon to routine op tory of the R (7) identifi to enter and i as impact WTB, Low S o the structur ed by the op the LSE ha uch as the L and storage b r

age of potent gh the norma d from 1980 the Turbin ater into the seal failed o spent resin 51 Incid ximately 1,2 o the Turbin wed into the approximatel DPC-82-58 I k in the Sea llons of reac 3-07)

A document entially haza caustics used storage tank s were contr dentification ns ultiple bound nents, and st perations an plant. Dai ied historica impact react ted by the Specific Act res, the soils peration of th s also been d LACBWR C buildings.

2-8 tially contam al effluent re 0 to 1986.

e Building laundry room on a spent r onto the flo dent Report) 200 gallons o ne Building soils outsid ly 25 gallons Incident Rep al Water Inj ctor coolant ted several in ardous liquid d in the plan ks. A majo rolled and re n, control a daries to con tructures. M nd maintenan iryland LAC al failed fuel tor and supp operation o tivity (LSA) s surrounding his facility. T designated a rib House, L minated liqui elease pathw Waste W

m. (DPC-81 resin liner w oor of the S of condensat g floor, and de the Turbi s of contam port, LER 82 njection Syst to be discha ncidents inv ds to the en nts various ority of the emediated in and remedia ntrol and con Many of these nce activitie C-TR-138, I incidents at ort systems.

of the facilit

) Building, g these build This area is as impacted.

LACBWR A id from the T way to the C Water Tank 1-10 Inciden which resulte Spent Resin te water was approximate ine Building minated liquid 2-016) tem leak at arged to the volving the u nvironment.

systems to t incidents oc n accordance ation of haz ntain the rad e systems an es during the Initial Site t LACBWR ty include R WGTV, and dings have a defined by t This area i Administrati Turbine Bui Circulating W overflowed nt Report) ed in the sp Liner Room s released fr ely 20 gallo g door and T d was discha 1A FCP ca Reactor Bui unplanned sp These inci the spill of d ccurred insid e with the st zardous ma dioactive con nd structures e operationa Characteriz and the pote Reactor Buil d the Ventil also been de the LSE fenc includes anc ion Building ilding Water d and pill of m and rom a ons of Truck arged aused ilding pill or idents diesel de of tation aterial ntents have al and zation ential

lding, lation emed ce.

cillary g and

La Cross License T Revision In additi support impacted LSE whi the LSE 2.1.6. In As part o into preli and exist 2.1.6.1.

The entir larger ph classifica efficient identified were clas and are id were clas current c 2.1.6.2.

The surv or open l were deli radioactiv relatively appropria The surv Prior to accordan sizes for The deco segmenta the excep any struc survey u These ob volume c In additio the purpo se Boiling W Termination n 0 ion to the a buildings, t d to provide ich is consid areas compr nitial Surve of the HSA p iminary surv ting survey d Surve re 163.5 acr hysical sectio ation. Surv and practic d in the area ssified as n dentified in ssified as im lassification Surve vey areas wer land area tha ineated to ph vity to the e y compact sh ate for the si vey units est characteriza nce with the g survey units ommissionin ation, remov ption of stru cture will re units have be bjectives inc contained on on, the surve ose of chara Water Reactor Plan area within the open lan a buffer zon dered non-im rising approx ey Areas/Un process, the i vey areas an data.

y Areas res licensed ons of the sit vey area size cal size need

a. Survey ar on-impacted the HSA. S mpacted. F ns by area.

y Units re further di at is surveye hysical areas extent practi hapes and hi ite operation tablished by ation, survey guidance pro s for FSS.

ng approach val and dispo cture basem emain at sit een establish clude provid nsite, and dis ey units estab acterization p r

the LSE an nd immedia ne between t mpacted. Th ximately 1.5 nits and Clas impacted LA nd assigned site was div te that may e was deter ded to boun reas that hav

d. These ar Survey areas Figure 2-1 p vided into su ed and evalu s with simila cal. To the ghly irregula nal history or the HSA w y unit sizes f ovided in M that will be osal of all im ment floors an te closure a hed for struc ding survey d sposition opt blished for s planning and 2-9 nd the open ately surroun the LSE and he licensed s acres of the ssification ACBWR stru area classifi vided into su contain one rmined base nd the latera ve no reason reas have no with reason provides an i urvey units.

uated as a sin ar operationa extent prac ar shapes we r the site top were used as for Class 1 o ARSSIM, se e implement mpacted sys nd walls that and consequ ctures to fac data for rem tions for the structures tha d do not cor land areas unding the L d the G-3 lan site comprise e owner cont uctures and o ications base urvey areas.

or more sur ed upon the al and verti nable potenti o radiologica nable potenti illustration o A survey u ngle entity f al history or ctical, survey ere avoided u ography.

initial surve open land su ection 4.6 fo ted at LACB stems and ab t reside 3 fee uently, be su cilitate other mediation pla waste.

at are 3 feet rrespond to surroundin LSE fence nd and facil es a total of trolled area.

open land ar ed on the op

. Survey ar rvey units de specific ar ical extent o al for residu al impact fro ial for residu of the LACB unit is a port following FR similar pote y units were unless the un ey units for urvey units or the sugges BWR calls bove-grade et below gra ubjected to r characteriz anning, estim below grade the survey u g the LACB is designate lities south o f 163.5 acres reas were div perational hi reas are typi epending on rea and the of contamin ual contamin om site opera ual contamin BWR site an tion of a stru RS. Survey ential for res e established nusual shape characteriza were adjust sted physical for the com structures.

ade, no porti FRS. How zation objec mating the w e are intende units that w BWR ed as of the s with vided istory ically n their most nation nation ations nation nd the ucture units sidual d with e was ation.

ted in l area mplete With ion of

wever, tives.

waste ed for will be

La Cross License T Revision used for section 5 Tables 2-impacted site struc 2.1.6.3.

The follo React Turbi (L10 LSA North The basis soil by r spills of packages Based on subsurfac the unres 2.1.6.4.

The follo LACB (L20 G-3 C (L20 Based up surveys p radioactiv Class 2 o 2.1.6.5.

The follo North Trans Plant se Boiling W Termination n 0 the FRS o

.5.2 of Chap

-1 and 2-2 p d structures ctures. A sum Class owing open l tor Building ine Buildin 10102),

Building, M h LSE Area s for this cla radioactive m radioactive s and contain n an assessm ce soils in th stricted use c Class owing open l BWR Adm 11101),

Crib House, 11102).

pon a review performed in ve contamin open land sur Class owing open l h End of Lic smission Sw t Access, ISF Water Reactor Plan f remaining pter 5).

provide a de respectively mmary of th 1 Open Lan land areas ha g, WTB, WG ng, Turbine Maintenance (L1010104) assification is material in t liquids and ners.

ment of histor hese areas c criteria. Clas 2 Open Lan land areas w ministration LACBWR w of the hist n these area nation to exc rvey units ar 3 Open Lan land areas w censed Site (L witchyard Are FSI Haul Ro r

g below grad etailed list o

y. Figure 2-2 he survey uni nd Areas ave been cla GTV, Ventila Office Bu Eat Shack G s due to a se these areas d resins, radi rical inciden could possibl ss 1 open lan nd Areas were classifie
Building, Circ. Water torical inform as as docume eed the unre re shown on nd Areas were classifie L3012101),

ea (L301210 ad Grounds 2-10 de structure of the survey 2 provides a it classificati assified as im ation Stack G uilding, 1B Grounds (L10 ries of docum during facil ioactive sys nts and event ly contain re nd survey un ed as impacte LACBWR Discharge L mation and ented in the estricted rele Figure 2-1.

ed as Class 3 02),

(L3012109) es (designate y units for b a detailed in ions are pres mpacted Clas Grounds (L1 Diesel G 010103),

mented incid lity operation stem leakage ts, it was an esidual radio nits are show ed Class 2:

R Crib Ho Line, Area S operational HSA, there ease criteria.

).

ed as STS a both the ope nventory of sented as fol ss 1:

010101),

Generator Bu dents of the ns. These i e, and storag nticipated tha oactive mate wn on Figure ouse, Ware South of LSE radiation an e was a pote and discuss en land area the building llows.

uilding Gro contaminati incidents in ge of radioa at the surfac erial in exce e 2-1.

ehouse Gro E Fence Gro nd contamin ential for res ed in s and g and ounds ion of clude active e and ess of ounds ounds nation sidual

La Cross License T Revision Historica in concen Class 3 o 2.1.6.6.

Based on in the HS contamin G-3 C Coal Capp Grou Hwy The non-2.1.6.7.

The follo structure These str radioactiv radioactiv majority React Wast Venti Wast Turbi Diese LSA Main Througho spread o were rou structure structura below gr subjected se Boiling W Termination n 0 al informatio ntrations in e open land sur Non-I n a review o SA, the bala nation and ha Coal Plant G Pile Ground ped Ash Imp unds East of H 35/Railroad

-impacted op Class owing is a li

s. The com ructures con ve waste sy ve material of the curren tor Building te Treatment ilation Stack te Gas Tank ine Building el Generator Building (B ntenance Eat out facility o f loose surf utinely post s involves l material as rade, no por d to FRS. Th Water Reactor Plan on contained excess of the rvey units ar Impacted Op f the operati ance of the as been desig Grounds (L40 ds (L401210 oundment G Highway 35 d Right of W pen land surv 1 Structures ist of the m mplete list of ntain the nuc ystems, and n was routine nt radioactiv g (B1010001 t Building (B k (B1010003 Vault (B101 g (B1010005 r Building (B B1010007)

Shack (B10 operations, th face contam ted as cont the comple s waste. Wi rtion of the he Class 1 st r

d in the HSA e unrestricted re shown on pen Land Are ing history o 163.5 acre li gnated as no 012103)

5)

Grounds (L40 5 (L4012107 Way Grounds vey units are s

major buildin f all impact clear reactor nuclear fuel ely handled, ve material in

)

B1010002)

3) 10004)
5)

B1010006) 010008) hese structur ination, and taminated a ete segment ith the excep se structure tructural surv 2-11 A indicated th d release cri Figure 2-1.

eas of the facility icensed site on-impacted.

012106)

)

(L4012108) e shown on F ngs that were ted structura r, primary re l handling a

, transferred nventory at L res were sub d airborne ra areas. The tation, remo ption of stru s will rema vey units are hat the prese teria was no y and histor has no reas

)

Figure 2-1.

e initially cl al survey un eactor system and storage s d, and stored LACBWR r bjected to spi adioactive m decommis oval, and d uctural floor ain at site cl e depicted in ence of resid ot expected.

rical incident sonable pote lassified as nits is provid ms, reactor systems. D d within the resides in the ills of radioa material. St sioning app disposal of s and walls losure and a n Figure 2-1 dual radioac ts as docum ential for res impacted Cl ded in Table support sys uring operat ese building ese structure active liquid tructural sur proach for all systems that reside 3 are therefor ctivity ented sidual lass 1 e 2-2.

tems, tions,
s. A es:

ds, the rfaces these s and 3 feet re not

La Cross License T Revision 2.1.6.8.

The follo Class 2 o complete LACB G-3 C LACB LACB LACB LACB Back Trans G-1 C Barge These str structure LACBW Washing structure Administ the decom LACBW structure The LAC Switch H unrestrict Supplem Manual depicted Based on in the H section 2 residual the G-3 C 2.2.

C From Oc accordan se Boiling W Termination n 0 Class owing is a li or 3 structur e list of all im BWR Crib H Crib House (

BWR Admi BWR Wareh BWR Wareh BWR Wareh k-up Control smission Sub Crib House (

e Washing B ructures did s associated WR workers g Break Room s because th tration build mmissioning WR Class 2 or s will remain CBWR Adm House will n ted release ment 1, Multi (MARSAM in Figure 2-n a review o HSA, coup 2.3.5), the bu contaminatio Crib House, Characteriza ctober 2014 nce with th Water Reactor Plan 2 and 3 Stru ist of some res. All are mpacted stru House (B201 (B2010102) nistration Bu house #1 (B2 house #2 (B2 house #3 (B2 Center (B30 b-Station Sw (B3012103)

Break Room not routinely d with LAC and therefo m were not a hey reside i ding, the G-3 g approach c r 3 systems n at site clos ministration b not be subj using a gr i-Agency Ra E) (8). The

-1.

f the operati pled with t uildings ass on and have will remain ation Appro through Aug he Characte r

uctures of the major e located wi uctural surve 10101) uilding (B20 2010104) 2010105) 2010106) 012101) witch House (B3012104) y house radi CBWR listed re considere associated w in a Class 3 3 Crib Hous calls for the and structur sure and ther building, the ected to FR raded survey adiation Sur e Class 2 an ing history o the results sociated with e been desig intact and fu oach gust 2015, s erization Su 2-12 r buildings t ithin the lice y units is pro 010103)

(B3012102)

)

ioactive syst d above are ed Class 2 with LACBW 3 land area.

se and the T complete se ral material a refore will n e G-3 Crib H RS. Instead y approach rvey and As nd Class 3 s of the facility of charact h the G-3 s gnated as no unctional for site characte urvey Plan.

that were in ensed site b ovided in Ta

)

tems or mate outside of or 3. The WR operation With the Transmission egmentation, as waste or ot be subjec House and th d, these stru using the ssessment of structural su y and histor terization su station have on-impacted.

r G-3 power erization of L The Ch nitially classi but outside o able 2-2.

erials during the LSE bu G-1 Crib H ns but are co exception o n Sub-Statio

, removal, an salvage. No ted to FRS.

he Transmis uctures will guidance o of Materials urvey units rical incident urveys (as no reasona

. The G-3 s r operations.

LACBWR w haracterizatio ified as imp of the LSE.

g operations.

ut were use House and B onsidered Cl of the LACB on Switch H nd disposal o portion of ssion Sub-St be surveye f NUREG-s and Equip for building ts as docum summarize able potentia station, inclu was perform on Survey pacted The The ed by Barge lass 3 BWR

House, of all these tation d for
1575, pment gs are ented ed in al for uding med in Plan

La Cross License T Revision incorpora documen develope executing procedur safely an Characte objective Provi Deve Supp volum The deco buildings character subjected removed 1757, Ap The char subsurfac structura surveys w structure used to m above gr of the ex

planned, planning A signifi unit is cla design fo result in unit meet errors.

As site-s LACBW selected.

in NURE Paramete assess the se Boiling W Termination n 0 ated the pre nted in the su ed to provide g characteriz res and surv nd effectively rization data es:

ide radiologi elop the requ ort the eva mes.

ommissionin s, structures, rization effo d to FRS. E prior to the ppendix O.

racterization ce soils, pav l basements were perform

s. Upon com make determ rade or subg xpected end-executed an icant questio assified corr or FRS. A a survey des ts the release pecific Deri WR at the tim The screen EG/CR-5512 er Analysis e correct cla Water Reactor Plan evious histo urvey areas e guidance a zation survey ey unit spec y acquire the a acquired th ical inputs n uired inputs f aluation of r ng approach

, and compo orts focused Extensive ch e performanc n surveys fo ved surfaces, s that will re med in the L mpletion, the minations on w rade structu

-state structu nd documen on that must rectly. The a classificatio sign that doe e criteria. In ived Concen me the chara ning DCGLs 2 Volume 3 (9), Table 6 assification o r

orical opera from the HS and direction y activities.

cific survey e requisite ch hrough the e necessary for for LTP, and remediation for LACBW onents to a d d on open haracterizatio ce of final s ocused on g

, and concret emain in the LACBWR Ad e data was a whether add ures, surface ures at LAC nted with the be answere appropriate c on which un es not obtain n some cases ntration Guid acterization s presented i

, Residual R

.91 (Pcrit = 0 of impacted o 2-13 ational and SA and prev n to the pers The Plan w instructions haracterizati execution of r the design o d

alternatives WR calls for t depth of at l land areas on of equipm surveys is no general open te pads. Co e end-state dministration ssessed for q ditional chara and subsurf CBWR. Con e same data ed by the cha classification nderestimate n adequate in s, this can in deline Level survey was in NUREG-1 Radioactive 0.10) for soil open land or radiological vious site ch sonnel respo worked in co s (sample pl on data.

the Plan wa of FRS, s and techn the demoliti least 3 feet b and remain ment, system ot required i n land areas oncrete core condition.

n Building a quality and a acterization face soils, or ntinuing cha quality and aracterizatio n of a survey es the poten nformation to ncrease the p ls (DCGLs) performed, 1757 and th Contamina ls were used r soil survey l informatio aracterizatio onsible for im njunction w lans) that w as used to m nologies and ion and remo below grade ning structu ms or struct in accordanc s including:

samples wer In addition, and several o adequacy. T data is requ r beneath th aracterization d the results on is whethe y unit is crit ntial for con o demonstra potential for m were not ye alternate ac e concentrat ation from D d as alternat units.

on collected on efforts. I mplementing with impleme were develop meet three pri d estimate w oval of all on

e. Conseque ures that wi tures that w ce with NUR site surface re taken from

, characteriz of the G-3 st The data was uired, primar he concrete f n surveys w included in er or not a su tical to the su tamination c ate that the su making deci et establishe ction levels tion values f Decommissio e action leve d and t was g and enting ped to imary waste n-site

ently, ill be ill be REG-e and m the zation tation s then ily of floors will be n FRS urvey urvey could urvey isions ed for were found oning els to

La Cross License T Revision For struc to evalu 7,100 dpm Appendix radionuc the conse for Cs-13 2.2.1. D DQOs w FRS. Ho to determ unrestrict inspectio nature, e applicabl Characte outlined

1) State
2) Ident
3) Ident
4) Defin
5) Deve
6) Speci
7) Optim The DQO collect. N and will assessme obtaining obtained Direct m Minimal that exhi Detect (H 2.2.2. S Characte approved approach se Boiling W Termination n 0 ctures, the gr ate the clas m/100cm2 to x H. Use of lide distribu ervative appr 37 is signific Data Quality were impleme owever, the mine the rad ted use crit ons and surv xtent and ra le structures rization surv in MARSSIM the problem tify the decis tify inputs to ne the study elop a decisio ify limits on mize the des Os for site No structure therefore no ent of concre g core samp to determin measurement Detectable ibited the hi HTD) radion urvey Desig rization sur d procedures h based upon Water Reactor Plan ross screenin ssification o otal gross be f the Co-60 ution for surf roach was to cantly greate y Objectives ented for ch goal of char ionuclide m teria to dem veys of suff ange of radio

, residues, so veys were de M, Appendi m,

sion, o the decision boundaries, on rule, n decision err ign for obtai characteriza es located ab ot be subject ete in basem ples. Soils ne the mean s and scans Concentrati ighest activi nuclide(s).

gn rveys were s and the Cha n the DQOs f r

ng level that of survey u eta-gamma s screening v face contam o assume a d er.

s haracterizatio racterization mixture, wher monstrate co fficient quali oactive cont oils and surf esigned to g ix D. The se n,

rors, and ining data.

ation include bove 3 feet b ed to FRS.

ments and su were sampl and maximu s of surface ons (MDC) ity were sen designed a aracterizatio for each surv 2-14 t was used d units was th surface activ value was co mination wou distribution o on surveys in n is to quanti reas the FRS ompliance w ity and qua tamination in face water.

gather the ap even steps in ed identifyin below grade Consequent urrounding so led volumet um activity a soils were as will be e nt to an off-and perform on Survey Pl vey unit. Fo during chara he nuclide-vity based on onservative a uld be princi of 100% Co n a similar m ify and delin S goal is co with 10 CFR antity were n each appli propriate da n the DQO d ng the types will remain tly, sample c oils. Buildi trically. Su as well as th made using employed fo

-site laborat med in acco an. Survey or example, acterization a specific scr n Co-60 from as it was an ipally Co-60

-60 since the manner as an neate contam omparison of R 20.1402.

performed t icable surve ata using the development s and quanti n following d collection wa ing concrete ufficient me he sample sta g the same or FSS. Vo tory for ana ordance wit design incor an open land as an action reening valu m NUREG-nticipated tha 0 and Cs-137 e screening v nticipated fo minated area f data agains Characteriz to determin ey unit, inclu e DQO proce process are:

ities of med decommissio as focused o e was sample asurements andard devia instruments lumetric sam lysis of Har th all appli rporated a gr d survey uni level ue of

1757, at the 7 and value or the as and st the zation e the uding ess as dia to oning on the ed by were ation.

s and mples rd-to-icable raded it was

La Cross License T Revision designate the unres Class 1 s present.

to identif Class 2 o survey m select loc measurem biased su unit. A delineate warrante survey un The area character S

al su B

sy F

R ad S

A S

S ar S

C P

A L

2.2.2.1.

The num by assess se Boiling W Termination n 0 ed as Class stricted relea survey unit f The survey fy the lateral or Class 3 re measurement cations for s ment and/or urvey design A biased app e the extent o d if the char nit.

as and mater rization surv urface scans ll Class 1, 2 urvey unit L Biased subsur ystems of c igure 2-3.

Random sam ddition, soil cans and s Administratio amples were cans and sam reas.

cans and sam Concrete sam iping and V A backgroun LACBWR in Numb mber of measu sing the sam Water Reactor Plan 1 because it ase criteria.

focused on b design was l and vertica eceived surv locations an static measu sample loc n or a random proach was of an area th racterization ials surveye vey included s and random 2, 3, and no L3012102 (i.e rface soil sa oncern in C mples were ta samples we amples wer on Building e taken from mples were mples were t mples were t entillation tu nd radiation cluding: asp ber of Static urements an ple size nece r

t may conta Therefore, t bounding the based upon al extent of th veys develop nd scan area urements and cations at ran m approach warranted hat requires effort was d ed and/or sam m and biased on-impacted e., the switch amples were Class 1 and aken from a ere obtained re taken on and the G-3 m the septic ta taken on LA taken on G-3 aken in the unnels.

study was phalt, concret Measuremen nd/or sample essary to sat 2-15 ain levels of the character e contaminat n the number he contamin ped to includ

s. Biased su d/or samples ndom. The was address when the c remediation designed to v mpled in and d surface and open land a hyard).

taken along 2 areas incl asphalt and c directly belo n accessible Coal Plant.

anks.

ACBWR Ad 3 Building a basement ar performed te, and soil.

nts and/or S s that were t tisfy the DQO f radiologica rization surv tion where c r of measure nation. Area de a combin urvey design

s. Random e decision of sed by the D characterizat
n. Alternativ verify the ba d around the d subsurface area survey gside and un luding the p concrete from ow the aspha e roof surfa dministration access and he reas of the R on material amples taken in each Os.

al contamina veys that wer ontaminatio ements and as classified nation of ran ns used know survey desig f whether to DQO process tion effort w vely, a rando asis for the c e licensed ar e soils samp units with derneath und piping syste m pads and alt to a one m ace areas of n Building su eavily travel Reactor Bui ls similar to h survey uni ation greater re performed n was poten samples req as non-impa ndom and b wn informati gn selected o use primar s for each su was designe om approach classification rea as part o ples were tak the exceptio derground p ms as show paved area meter depth.

f the LACB urfaces and led surfaces.

lding, WTB o those foun it was determ r than d in a ntially quired

acted, biased ion to static rily a urvey ed to h was n of a of the ken in on of piping wn on
s. In BWR drain B, and nd at mined

La Cross License T Revision For the c that will and/or sa of residu For the sample s vertical e For non-validate measurem trivial lev generated 2.2.2.2.

For the c survey u Sample l to specifi that wer responsib survey d radioactiv potential from the 2.2.2.3.

Survey u area to b area scan Supervis was give survey un 2.2.2.4.

The char (beta and survey of FRS con and volu sampling following se Boiling W Termination n 0 characterizat be subjecte amples taken al radioactiv characteriza size was bas extent of the impacted an the basis ments and/o vels of licen d radionuclid Determ characterizat nits that wil locations we ic locations w re taken in ble Radiolog design proc vity, depres spill locatio HSA aided Scan C units were sc be scanned i nned was c or and/or th en to inform nit.

Types racterization d gamma); st f any concre nsisted of a c umetric samp g of surface g is a descrip Water Reactor Plan tion of impa ed to FSS, th n in the surve ve contamina ation of Cla sed upon the contaminati nd Class 3 op of the clas or samples w nsee-generat des are prese mination of tion of non-ll be subject ere determin within the su each surve gical Protect cess. Con sions, disco ons, or areas in the select Coverage canned to th n each surv ontingent up e Project He mation from s of Measure n survey of tatic beta me ete and/or as combination ples. The su and subsurf ption of the d r

acted Class 1 he minimum ey units wer ation in the s ss 1 structur e necessary n ion.

pen land sur ssification.

was sufficie ted radionuc ent in non-im Static Measu

-impacted an ted to FRS, ed by gener urvey unit. T y unit was tion Superv sideration w olored areas, s where the tion of biased he extent pr ey unit was pon the pro ealth Physic the initial w ements and S building sur easurements phalt-paved n of surface urvey of the face soil, sed different typ 2-16 1 and Class m number of re commensu survey unit.

res that wil number of s rvey units, th Consequen ent to ensure clides are pr mpacted area urement and nd impacted sample loca ating random The location determined visor and/or was given

, cracks, low ground has d locations.

actical in ac determined ofessional ju ist during th walk downs Samples rfaces consi s, material sa open land a scans (beta e open land diment and s pes of measu 2 open land f random or urate with th l remain an samples nee he primary c ntly, the nu e with reaso resent in Cl as.

d Sample Lo d open land ations were m pairs of c n of biased m d by the pr the Project to location w point grav s been distur ccordance w d during the udgment of he survey de and the am isted of a co amples and s areas that wi and gamma areas consis surface wate urements and d areas (pav r biased dire he probabilit nd be subjec eded to asses characterizat umber of s onable conf lass 3 areas ocations areas and C primarily ch oordinates t measurement rofessional j Health Phy ns that exh vity drain p rbed. Histo with their cla survey desi the Radiolo esign proces mbient radiat ombination smears. The ill remain an a), static bet sted of gamm er for isotop d samples tha ved and unpa ect measurem ty of the pres cted to FRS ss the latera tion DQO w systematic fidence that and no lice Class 2 struc hosen at ran hat correspo ts and/or sam judgment o ysicist durin hibit measu points, actua orical inform assification.

ign process.

ogical Prote

s. Consider tion levels i of surface e characteriz nd be subject ta measurem ma scans an pic analysis.

at were utiliz aved) ments sence S, the al and was to static only ensee-ctural ndom.

onded mples of the ng the urable al and mation The The ection ration in the scans zation ted to

ments, nd the The zed.

La Cross License T Revision 2.2.2.4.1 Gamma activity.

used for Ludlum M Ludlum M Scanning rate not t was main and, loca 2.2.2.4.2 Scanning 7,100 dpm including Hand-hel used.

Beta scan and with prevented was dete calculate of the sur If not im instrumen evaluatio investiga 2.2.2.4.3 Direct m surfaces typically detectors Direct m acquiring typically designate adjusted 2.2.2.4.4 If applic verify lo se Boiling W Termination n 0 Gamm scans were Sodium io these scans.

Model 44-10 Model 44-10 g was perfor to exceed 0.

ntained with ations of elev Beta S g was per m/100cm2 a g, but not li ld beta scin nning was p h a scanning d scanning a ermined, an d a priori to rvey.

mpacted by h nt to identi on. Any ide ation and pot Direct measurement of the build performed

s.

measurements g data over used for su ed investigat as appropria Remo able, remov oose surface Water Reactor Plan ma Surface S performed o dide (NaI) g EnergySol 0 Detector 0 NaI detecto rmed by mo

.5 m (20 in) hin 15 cm (6 vated direct l Surface Scan rformed in action level.

imited to; fl ntillation and performed w g speed of o at the specif nd the scan o ensure that high ambient fy locations entified areas tential decon t Measureme ts were per dings or on using ~10 s were condu a pre-determ urface measu tion level or ate to achiev ovable Surfac vable beta an e contamina r

Scans over open la gamma scin utions Techn Sensitivity (

ors to Co-60 oving the de per second.

in) of the s levels were f ns order to Beta scans loors, walls, d/or gas-flo with the dete one detector fied distance nning techni t the MDC f t noise level s of elevate s of elevated ntamination.

ents rformed to n concrete o 00 cm2 or l ucted by pla mined coun urements and r MDC und ve an accepta ce Contamin nd/or alpha ation is less 2-17 and surfaces ntillation det nical Suppor (10) examin 0 and Cs-137 etector in a s The distan urface if po flagged for f locate ar s were perfo

, ceilings, ro ow proportio ctor position r active win e, the detect ique adjuste for scanning s, technician d activity th d contamina detect total or asphalt pa arger sized acing the det nt time. A d generally p er considera able MDC fo nation contaminati s than the to identify tectors (typic rt Document nes the resp 7 when used serpentine p nce between ssible. Aud further inves reas of res ormed over a oofs, asphal onal detecto n maintained ndow per se tion sensitiv ed accordin g was approp ns monitored that require ation were m levels of aved areas.

scintillatio tector near t count time provided det ation. The i or direct mea on or smear applicable locations of cally 2 x 2 t (TSD) RS-onse and sc d for scanning pattern, whil n the detecto dible signals stigation and sidual activ accessible st lt and concr ors (typically d within 1 c econd. If su vity for the a ngly. Scan priate for the d the audibl further inv marked or fla contaminati These me on or gas-fl the surface to of one to t tection level instrument c asurements.

r surveys w action level f residual su

) were typi

-TD-313196 can MDC o g surface soi le advancing or and the su were monit d/or sampling vity above tructural sur rete paved a y 126 cm2) cm of the su urface condi alternate dis nning speed e stated obje e response o estigation a agged for fu ion on struc asurements low proport o be counted two minutes ls well below count times were perform

l. A smea urface ically 6-006, of the ils.

g at a urface tored;

g.

the rfaces areas.

were urface itions stance was ective of the and/or urther ctural were tional d and s was w the were med to ar for

La Cross License T Revision removab surfaces.

moderate activity a 2.2.2.4.5 Concrete contamin will rema diamond 1/2-inch w pulverize 2.2.2.4.6 Samples locations scanning defined a split spoo tools.

Subsurfa hand aug survey un 2.2.3. In The radi provide b identified action le and expe static me Concern Commer perform

3) analys Instrume in Table 2.2.3.1.

All data character se Boiling W Termination n 0 le activity w A 100 cm e pressure. S as appropriat Concr e core boring nation and th ain and be su bit core dri wide pucks ed and analy Mater of soil, sed s as well as

g. Surface so as soil below on sampling ace soil was gers. Subsur nit.

nstrumenta ation detect both reliable d for the de evels. Detec ected perform easurements (ROC) at a cially availa the three ba sis of materia ntation and 2-3.

Calibr loggers, ass rization wer Water Reactor Plan was usually m2 surface a Smears were te.

rete and Asp g and the sa he presence ubjected to F ill. The con s, represen yzed for isoto rial Sampling iment, and s other locatio oil is defined w the top 15 g system or, b sampled by rface soil sam ation Selectio tion and me e operation a ecommission ctor selectio mance in th and scanni MDC of 50%

able portable asic survey m al samples.

nominal MD ration sociated dete re calibrated r

taken at eac area was sa e then analyz phalt Core Sa ampling of of volumet FRS. Core b ncrete samp nting a certa opic content.

g sludge were ons in areas d as the top cm layer in by using han y direct push mpling was on, Use and asurement i and adequate ning of LAC on was based e field. In ng were cap

% of the app e and laborat measuremen DC values th ectors, and a d on an annu 2-18 ch direct me ampled with zed for the p ampling concrete we tric contami bore samplin le produced ain depth in obtained fr s exhibiting 15 cm (6-in n 1 m increm nd trowels, b h sampling s performed a d Minimum nstrumentat e sensitivity t CBWR at le d on detecti all cases, th pable of det plicable actio tory instrum ts: 1) surfac hat were em all other por ual basis us easurement l h a circular presence of g ere used to nation in co ng of concre d by the cori nto the surf rom designed elevated act nch) layer of ments. Surfa bucket auger systems (e.g as necessary Detectable tion for char to detect the evels suffici ion sensitivi he instrumen tecting the a on level.

ments and det ce scanning; mployed durin rtable instrum sing Nationa location on cloth or pa gross beta an assess the d oncrete wall ete was acco ing was typ face. Conc d biased and tivity that w f soil while s ace soil was rs, or other s

g. GeoProbe y to address t Concentrat racterization e initial suite iently below ity, operatin nts and detec anticipated R tectors were
2) static me ng character mentation th al Institute o non-asphalt aper filter, u nd/or gross depth of sur ls and floors omplished us pically sliced crete pucks d random sa were identifie subsurface s collected us suitable sam

) or by m the DQOs fo tions (MDC n was select e of radionuc w the establ ng characteri ctors selecte Radionuclid typically us easurements rization are hat were use of Standards t type using alpha rficial s that sing a d into were ample ed by soil is sing a mpling anual or the Cs) ted to clides lished

istics, ed for des of sed to s; and listed ed for s and

La Cross License T Revision Technolo addressed 2.2.3.2.

The recei used for portable character 2.2.4. L Gamma proportio laborator quality p preparati site labor In all ca achieved accepted analytica laborator 2.2.5. Q MARSSI used to quality fo 1576, Mu Regulato through (12). Fu may be achieved The QAP used duri functiona All chara approved audit a

Characte prescribe applied contracto se Boiling W Termination n 0 ogy (NIST) t d in the QAP Instru ipt, inspectio characteriza radiologica rization is ad Laboratory I spectroscop onal countin ry in accorda programs of ion and analy ratory under ases, analyti

d. The anal methodolog al methods ries used for Quality Assu IM, section demonstrate for sample an ulti-Agency R ory Guide 4.

Normal Op urther, MAR used in add

d.

PP was prep ing the site c al activities, acterization d procedures and surveil rization staf ed, impleme to any app ors.

Water Reactor Plan traceable sou PP.

ument Use an on, issue, co ation was p al instrumen ddressed in th Instrument py was prim ng and liquid ance with ap the contrac ysis of chara the QAPP.

ical methods lysis of rad gies or othe employed characteriza urance 2.2 discusse e that site c nalysis taken Radiologica

.15, Quality erations to RSSIM and dition to, or pared and im characterizat the DQO pr activities es

s. The effe llance activ ff and progr ented, and v plicable serv r

urces. The c nd Control ntrol, and ac performed in ntation. T he QAPP.

Methods an marily perfor d scintillatio pproved labo cted off-site acterization s s were estab diological co er comparab and the la ation.

es the need f conditions ar n to support al Laboratory y Assurance License Ter MARLAP b r in lieu of, mplemented t tion and FRS rocess, and m ssential to d ective imple

vities, incl ram self-ass verified wh vices provid 2-19 calibration o ccountability n accordance The issue a nd Sensitivi rmed by th on analysis oratory proce vendor labo samples prov blished to e ontaminants ble methodo aboratory M for a quality re acceptabl t characteriz y Analytical of Radiolo rmination) -

both indicate existing qu to ensure th S process. T measures nec data quality w mentation o luding fiel sessments, a hen deficienc ded by off-of instrument y of portable e with issue and control ities he on-site ra was perform edures. Ener oratories tha vided the sam ensure that used stand ologies. Ta MDC achiev y system to le for unres zation and F l Protocols M ogical Moni

- Effluent St e that a Qua uality system e adequacy The QAPP de cessary to ac were implem of characteri ld walk-do as appropriat cies were i

-site vendor ts used for c e radiologica e and contro l of instru adiological med by an rgySolutions at were used me level of required M dard approve able 2-4 prov ved by the ensure the a stricted rele FRS is discu Manual (MA itoring Prog treams and ality Assura ms to ensur of data bein escribes poli chieve qualit mented and ization was owns by te. Correct identified.

rs, as well characterizati al instrument ol procedure uments used laboratory.

approved ve s ensured tha d for the rec quality as th MDC values ed and gene vides the ty off-site ve adequacy of ase. Labor ssed in NUR ARLAP) (11 grams (Incep the Environ ance Project re data qual ng developed icy, organiza ty data.

performed u verified thr EnergySolu tive actions These mea as on-site ion is tation es for d for Gas endor at the

ceipt, he on-were erally ypical endor f data ratory REG-

) and eption nment Plan ity is d and

ation, using rough utions were asures sub-

La Cross License T Revision The Cha quality a and is su follows:

E op A

st D

Details o the proce data acqu requirem P

E P

S P

M pr All chara Plan, the 2.3.

S In Octob placing t October character accelerat EnergySo October 9 August 6 documen Characte PN-1640 2015 Fie Radioact character character se Boiling W Termination n 0 aracterization assurance and ubject to the Establishmen perations.

Actions to en taff.

Documentatio of the QA/QC edures and s uisition and ments. The sp ersonnel qua Execution in roper docum election of a roper instrum Management rocedures, p acterization QAPP, all a ummary of ber of 2005, the unit into of 2014, rization of L tion of de olutions in a 9, 2014. T 6, 2015. The nted in two erization Sur 017-001, LA eld Work (14 tive systems rization dat rization has Water Reactor Plan n Survey Pl d quality co QAPP. The nt/implement nsure that the on of the dat C elements s sample plan d recording pecific QA/Q alifications, accordance mentation of appropriate i ment calibra oversight of protocols, an activities w applicable im f Characteri Dairyland p o a SAFSTO Dairyland LACBWR in commission accordance w The schedule e results of th o separate rvey Report CBWR Radi 4).

s that rema a in certain been deferre r

lan was dev ontrol (QA/Q e QA/QC pr tation of plan e procedures ta collected.

specific to ch instructions was guided QC program experience, with approv survey data instruments t ation and dai f characteriz d documenta were conduct mplementing ization Surv performed a OR condition contracted n anticipation ning activiti with EnergyS ed EnergyS he site chara reports, GG for October iological Ch ain at LAC n areas du ed until such 2-20 veloped acco QC) program ogram elem ns, procedur are understo haracterizati

. The chara d and condu m component and training ved procedur and sample to perform th ily functiona zation activit ation require ted in accor g procedures vey Results limited cha

n. This sur EnergySol n of the deve ies. Char Solutions cha Solutions sit acterization s G-EO-31319 r and Novem haracterizati CBWR affec ue to ambie h time that ra ording to th m for the dec ments applica res, and prot ood and foll ion are prese acterization o ucted in com s for site cha
g.

res.

analyses.

he surveys.

al checks.

ties relative t ements.

rdance with

, and approv aracterization rvey is docu lutions to elopment of racterization aracterizatio te characteri surveys perf 96-RS-RP-0 mber 2014 F ion Survey R cted the ab ent radiatio adiological o he essential commissioni able to chara tocols for the lowed by the ented in the Q operations an mpliance wi aracterizatio to the adhere the Charact ved sample p n survey of umented in perform a f this LTP an n activities, on procedure ization effo formed by En 01, LACBW Field Work (

Report for J ility to acq on levels.

or physical c elements o ing of LACB acterization a e field e implementi QAPP, as w nd the assoc ith these QA on are as foll ence to terization Su plan instruct the LSE pri Reference 7 a more det nd the anticip

, performed es commence ort conclude nergySolutio WR Radiolo (13) and LC June thru A quire meani In these c conditions w of the BWR are as ing well as ciated A/QC ows:

urvey ions.

ior to

7. In tailed pated d by ed on ed on ons is ogical C-RS-ugust ingful
cases, would

La Cross License T Revision allow the the decom significan by revisio 2.3.1. B During t backgrou acquired backgrou As part o backgrou LACBW Normally be repres site area Supervis appropria results.

were con Concrete is located non-impa approxim unit L40 L401210 samples a The ana backgrou can be at mean Cs 0.135 pC was 0.07 Relevant Station (Z at Zion S Zion to C geograph for distu backgrou within th categorie drainage se Boiling W Termination n 0 e survey of t mmissioning nt additiona on or addend

Background

the initial ch und study fo from vario und study is of the 2014 und levels a WR fell within y, backgroun sentative. H was chosen.

or selected a ate for obtain Although th nsidered unaf e samples an d north of th acted survey mately 100 s 12108. Soil 08 were also are provided lysis of the und study fo ttributed to g

-137 concen Ci/g with a m 0 resulting i t to LACBW ZNPS) titled Station (15).

Cs-137 leve hically simila urbed soils a und Cs-137 he expected es of soil in and non-dra Water Reactor Plan hese survey g process, in l characteriz dum as a par Study haracterizati or soils at LA ous location summarized characteriza at LACBWR n nominal ex nd reference However, no

. The Energ an area outs ning backgro he selected s ffected by pa nd direct me he LSE. A y unit L4012 quare meter l samples fro evaluated f d in sections e backgroun or soils. The global fallou ntration of s maximum ob in the upper WR is a study d ZionSolutio This docum ls anticipate ar. The docu as well as u levels for th range of d the non-im ainage, distu r

units. Solu ncluding foll zation data i rt of the requ on survey p ACBWR. R ns outside o d in Table 2-ation effort, R. The pur xpected leve areas shoul suitable off gySolutions P side of the L ound measu sample locat ast LACBW asurements sphalt samp 2106. Surfa rs of undistu om non-imp for use as ba 2.3.3 and 2.

nd soil sam e results did ut. For the t surface samp bserved con r range for th y performed ons TSD 13 ment was pr ed from wor ument predic undisturbed he site speci disturbed so mpacted area urbed and un 2-21 tions intends lowing the s is obtained, uired 2 year performed in Reference 7 of the owne

5.

EnergySolu rpose of the els for soils, d be reasona f-site locatio Project Heal LSE but on rements bas tions were i WR operation were taken ples and dire ace soil samp urbed non-dr pacted survey ackground re

.3.5.3.

mples in 201 d report Cs-1 two backgrou ples taken o ncentration o his data set a for the deco

-004, Exami repared to co rldwide fall cted ranges f soils and is fic backgrou ils in non-d s at LACBW ndisturbed so s to continue submittal of this chapter update of th n October 2 states that a er controlled utions perfor e study was concrete, an ably close to on was ident lth Physicist the licensed ed upon the inside the LA ns.

in Class 3 s ect measurem ples were ac rainage soil y units L401 eference soil 14 compare 137 at levels und studies n or around of 0.268 pCi at a 95% con ommissionin ination of Cs ompare site out. The L for backgrou presented i und studies drainage are WR, the upp oil from the e characteriz this LTP. I r of the LTP he approved 005, Dairyl a series of s d area. Th rmed a limit s to assess i nd asphalt.

o the decomm tified. Cons and the Rad d LACBWR previous ra ACBWR lic survey unit L ments were cquired from within non-12107 and o ls. Analysis ed favorably s slightly ab performed a d the site pro i/g. The st nfidence leve ng of the Zio s-137 Globa soil sample LACBWR an und concentr in Table 2-6 performed a eas. As the per 95th per Zion backgr zation throug In the case w P will be up LTP.

and perform oil samples he result of ted assessme if backgroun missioning s sequently, an diation Prote site that se diological su censed area, L3012101, w also collect m a small ar

-impacted su other areas w s results for y with the bove MDC.

at LACBWR oduced a me tandard devi el of 0.275 p on Nuclear P al Fallout in Cs-137 resu nd Zion site rations of Cs

6. The obse at LACBWR ere were va centile level round study ghout where dated med a were f this ent of nd at site to n on-ection emed urvey

, they which ted in rea of urvey within these 2005 This R, the ean of iation Ci/g.

Power Soils ults at es are s-137 erved R fall arious ls for were

La Cross License T Revision considere areas, an 2.3.2. P EnergySo Decomm decommi from the some of t less than prepared 2.3.3. N Based up 163.5 acr impacted contamin operation ISFSI w operation physical for comp for the cl The non-segregate inside of Highway study for within su in coal f ISFSI fac From Oc impacted survey un and the i impacted To supp objective open land by perfor The 2015 primary surveys a se Boiling W Termination n 0 ed appropria d Class 2 an Potential Ra olutions TS issioning (

issioning of sampling o the theoretic n 2 years, an

. The list of Non-Impacte pon the infor re licensed

d. The n nation given ns. The det were not imp ns (i.e., with characterist pliance beyo lassification.

-impacted op ed into five f survey uni y 35. This s r soils. The urvey unit L4 from the G-cility, which ctober 2014 d open land nits and wer initial result d as it was d ort this con e of the add d survey uni rming additi 5 characteriz objectives and samplin Water Reactor Plan ate backgro nd 3 open lan dionuclides SD RS-TD-3 (16) establi LACBWR.

of various m cal neutron a n initial suite f potential ra ed Open La rmation com site surroun non-impacte that historic termination pacted by l hin the LSE ics. The are ond the chara pen land are survey unit it L4012108 survey unit non-impacte 4012103. A

-3 station an h has not bee to August areas of th re characteri s of the 201 determined t nclusion, ad itional chara its given an i onal soil sam zation camp of the addi ng to suppor r

ound concen nd area surve s of Concern 313196-001, shes the ba Industry gu media from p activation pro e of potentia adionuclides and Areas mpiled in the nding the L d areas ha cal informati that the con licensed ope

), site use, t eas designat acterization a is approxim ts. Non-imp 8 in a veget was formed ed survey un A majority of nd survey un en characteriz 2015, char he site. The ized as such 14 characteri that there is dditional ch acterization initial Class mpling and g aign was de tional chara rt the non-2-22 ntration leve ey units at L n

, Radionuc asis for an uidance was past plant o oducts, nobl al ROC for is listed in T e HSA, a lar LSE and IS ave no rea ion provides ntiguous ope erations was topography, ted as non-im surveys and mately 352,3 pacted open ated area w d during cha nits are show f the surface nit L401210 zed and is no racterization e survey uni h in Referenc ization, thes no reasonab haracterizatio surveys per 3 classificat gamma walk esigned in ac acterization

-impacted c els for the LACBWR.

clides of C initial suite reviewed as operations.

le gases and the decomm Table 2-7.

rge portion o SFSI receive asonable po s no indicatio en land area s based on site dischar mpacted are d sampling p 360 square m n land surve with minimal aracterizatio wn in Figure area in surv 06 complete ot addressed surveys w its were ori ce 13. Base se survey un ble potentia on was perf rformed in 2 tion for re-cl kover survey ccordance w was to per classification evaluation Concern D e of potenti s well as the Based on th radionuclide missioning o of the open ed a classif otential to on of impact as surroundi the locatio rge pathway e not require performed to meters in siz ey unit L40 l ground dis on to facilita 2-1. The G vey unit L40 ely surround d by this LTP were perform iginally clas ed upon a rev nits were rec al for residua formed in 2 2015 was to lassification ys.

with Referenc rform suffic n and to pr of non-imp uring LAC ial ROC fo analytical re he eliminatio es with a hal f LACBWR land areas o fication as contain res t from LACB ing the LSE on(s) of lice ys, and othe ed to be surv o provide a ze. This area 12109 is lo sturbance ea ate a backgr G-3 station re 012105 is cov ds the LACB P.

med in the ssified as Cl view of the classified as al contamina 2015. A m o evaluate ce n as non-imp ce 4. One o cient radiolo rovide reaso pacted CBWR or the esults on of lf-life R was on the non-sidual BWR E and ensed er site veyed basis a was ocated ast of round esides vered BWR non-lass 3 HSA non-ation.

major ertain pacted of the ogical nable

La Cross License T Revision assurance 2015 cha based on During th units L40 logger w was scan Gamma s or gravel Minimum evaluated survey un an Explo were due Thirty-tw toward d shown in instrumen positively surface s These va in section specific b in the gr were very Seventee meter.

concentra derived g average maximum backgrou 137 conc surface s the Hwy Two asp survey un were less identified A summ presented se Boiling W Termination n 0 e that the n aracterization a random d he 2015 cha 012103, L40 with a 2 by 2 nned due to surface scan

l. Alarm se m Detectabl d during the nit L401210 oranium GR-e to the prese wo surface s discolored ar n Figure 2-5 nt MDC in y identified soil samples alues are wit n 2.3.1. On background rounds east y close at 0.

en subsurfac Of the 17 ations greate gamma-emit Cs-137 conc m observed und range fo centrations th soil backgrou 35/Railroad phalt sample nits. The asp s than the M d by gamma ary of the g d in Table 2-Water Reactor Plan non-impacted n survey foc esign to ensu aracterizatio 012105, L40 2 NaI detec inaccessibili nning focused et-points for e Count Ra e performan 7 and one in

-135. The ence of natur soil samples eas or areas

5. Cs-137 26 of the 32 by gamma s was 0.131 hin the expe ly one Cs-13 data set. Th of Highway 135 pCi/g an e soil sampl 7 subsurface er than the tting radionu centration ob concentrati r Cs-137 as hat exceede und. This s d Right of W es were coll phalt surface MDC of 1,93 spectroscop gamma spect

-8.

r d survey uni cused primar ure an unbia n survey, a 012106 and ctor. In surv ity from the d on undistu r the instrum ate (MDCR) nce of the g n survey unit results of th ral backgrou s were colle where the g was positiv 2 samples.

spectroscopy pCi/g with ected backgr 37 result exc his sample w y 35. The m nd 0.131 pC les were tak e soil samp instrument uclides were bserved in t ion of 0.40 discussed in d the maxim sample was t Way Grounds lected from e was first sc 38 dpm/100c py in any of t troscopy resu 2-23 its do not c rily on soils ased survey.

minimum o L4012108 vey unit L40 e presence o urbed soils w ment were s

) of the ins gamma scan t L4012108.

he investiga und activity.

ected from ground had b vely identif No other po

y. The avera a maximum round range ceeded the m was the maxi mean of the n i/g, respectiv ken at random ples taken, MDC in ei e positively i the subsurfa 09 pCi/g. Th n section 2.3 mum Cs-137 the maximu random loc canned with cm2. No pla the asphalt s ults for each contain plant and asphalt of 1% of the was scanned 012107, less f tall, thick with minimal set at the ob strument. A n, one in su All scan al ation indicat non-impacte been disturbe fied in conc otential plan age Cs-137 c m observed c for Cs-137 maxium resu imum 0.463 non-impacte vely.

mly selected Cs-137 w ght samples identified by ace soil sam hese value 3.1. Only on 7 concentrati um 0.409 pC cations in p h a beta-gamm ant derived r samples.

h non-impac t-derived ra

t. The samp e surface so d with a Mo s than 1% of vegetation a l vegetation bserved back A total of f urvey unit L larms were in ted the elev ed areas at ed. The sam centrations nt-derived ra concentratio concentration surface sam ult of 0.268 pCi/g value ed and site-s d locations t was positive
s. No other y gamma sp mples was 0.

es are with ne subsurfac ion found in Ci/g value th paved areas mma detector radionuclide cted open la adioactivity.

ple locations oil area in su odel 2350-1 f the surface and steep te or disturbed kground plu four alarms L4012106, tw nvestigated u vated scan re locations b mple location greater than adionuclides n observed i n of 0.463 p mples as discu pCi/g in the e and was lo specific data to a depth o ely identifie r potential p pectroscopy.

087 pCi/g w hin the exp e sample ha n the site-spe at was locat in non-imp

. All scan re s were posit and survey u The were urvey data e area rrain.

d soils us the were wo in using esults biased ns are n the were in the pCi/g.

ussed e site-ocated a sets of one ed in plant-The with a pected d Cs-ecific ted in pacted esults tively unit is

La Cross License T Revision A coal as samples The resul The lab concentra also posi concentra considere of the pl radionuc positive ratios ar compared higher th operation consisten the spora derived r In survey gamma s area to d approxim uranium readings 2.3.4. Im The HSA operation been clas been iden into two north of Highway three Cla The char prepared employed radionuc of suffici surface a obtained Survey contamin se Boiling W Termination n 0 sh sample fr were sent to lts of the ana boratory an ations excee tively detect ations of the ed to very li lant-derived lide mixtur results for C re 118 and d to the site han expected nal history, t nt with natur adic positive radionuclide y unit L4012 spectroscopy determine if mately 7,000 and thorium conducted d mpacted Op A identified ns. The app ssified as C ntified as i Class 2 surv the LSE, th y 35 and the ass 3 survey racterization for each s d to determ lide concent ient quantity and subsurf from below techniques nation identi Water Reactor Plan rom survey u o Test Ame alysis are pre nalysis spor eding the MD ted but at lev e positively i ikely be the radionuclid re fractions Cs-137, Sr-16, respect e-specific mi d by factors the radionuc ral backgrou analytical r s in these su 2108, a repr

y. In additio f there is a 0 to 8,000 cp m series nuc during the w pen Land A d the open proximate are Class 1. An impacted b vey units. T he transmiss e haul road u units combin of the impac survey unit ine the later trations in th y and quality face soils in w the structur were empl ified and th r

unit L40121 erica Labora esented in T radically id DC, includin vels that are identified rad result of cou des. This c

. For exam 90 and Fe-5 tively. Wh ixture fracti s of 4,800 a lide ratios, a und and com esults are ve urvey units.

resentative s on, gamma s significant pm). The a clides with alkover surv Areas land area ea is 1.5 acr approximat y reactor op Three impact sion switchy used to tran ned is appro cted open la in accorda ral and vert he soil. Char y to quantify n each open res due to int loyed to de he radionucl 2-24 05, six surfa atories for g Table 2-9.

dentified se ng H-3, C-14 consistent w dionuclides w unting uncer conclusion w mple, samp

55. Howev hen the rati ons in Chap and 10,700, and primarily mprise 88% o ery unlikely sample of th scan reading difference analysis of t no plant de vey averaged inside the res. All ope tely 3.46 acr perations. T ted Class 3 s yard and the nsport dry fu oximately 16 and areas beg ance with R ical extent o racterization the potentia n land surve terferences a etermine th lide concent face soil sam gamma spect everal plan 4, Fe-55, Ni with natural b were close t rtainty as op was supporte le L301210 ver, the Sr-9 ios from L3 pter 6, Table respectivel y the concen of the site-sp to represent he rail road gs were take from site b the railroad erived radio d 7,000-8,50 fenced LSE en land surve re area that This open la survey units e area encom uel casks to 6.5 acres.

gan in Octob Reference 4 of any cont n inspections al volumetric ey unit. Li and inaccess he lateral a trations in t mples and fiv troscopy and nt-derived r i-63, and Sr-background to the detecti pposed to th ed by a rev 05-CR-GS-0 90/Cs-137 an 3012105-CR e 6-3, it is s ly. In conc ntrations of C pecific radio t the actual p bed gravel en of the rail background bed gravel onuclides. T 00 cpm.

E as impac ey units insi surrounds t and area has were design mpassing th the ISFSI.

ber 2014. A

4. Survey amination id s and surveys c contaminat imited soil ibility.

and vertical the soil. A ve subsurfac d HTD anal radionuclide

-90. Cs-137

. In all case ion limits an e actual pres view of exp 002-SS indi nd Fe-55/Cs R-GS-002-SS een that the clusion, base Cs-137 whic onuclide mix presence of p was analyze l road bed g (which aver indicated na The gamma cted by re ide the LSE the LSE has been segre nated for the he site acces The area o A sample plan techniques dentified an s were perfo tion of acces information l extent of A combinatio e soil lyses.

es at 7 was es, the nd are sence pected icates s-137 S are ey are ed on ch are

xture, plant-ed by gravel raged atural scan eactor have s also gated e area ss off of the n was were nd the ormed ssible n was f any on of

La Cross License T Revision random a survey p professio Protectio radioactiv spill loca survey lo not requ locations radiologi A surface surface s or surfac were take intervals Each sur site radio necessary All surfa Several s full isoto survey un 2.3.4.1.

There are The Clas area in th Reactor radioactiv areas, pre Twenty-t measurab locations taken in taken, C samples 13 sampl identified the surf 0.287 pC samples w Seventy-one mete se Boiling W Termination n 0 and biased s ackage. The onal judgme on Supervis vity, depres ations, or ar ocations was uired for soi s were selec ical contamin e soil sample oil samples ce scans indi en from 0.15 rface soil, co ological lab y to achieve ace and sub soil samples opic analysis nit per Refe Class e four (4) op ss 1 open lan he Class 1 op Building, th vely contam evented the a two (22) sur ble radioact s, or areas w Class 1 open Co-60 was p and Cs-137 les. No oth d by gamma face soil sa Ci/g. The a was 0.096 p nine (79) su er, two (2) lo Water Reactor Plan urvey locati e locations o ent of the E or. Consi sions, disco reas where t s also determ ils in an op cted on asp nation.

e was taken were acquir icated elevat 5 cm to dept omposite sub oratory by e an isotopic surface com were selecte s (HTD radi erence 4.

1 Open Lan pen land sur nd survey un pen land sur he Turbine minated build ability to per rface soil sam tivity, disco where the gro n land surve positively id 7 was posit her potentia spectroscop amples was verage Cs-1 Ci/g with a m ubsurface so ocations bias r

ions were es of biased me EnergySoluti deration wa lored areas, the ground h mined by are pen land are phalt in Cla at each sele red at severa ted activity.

ths ranging f bsurface soil gamma-spec c MDC equa mposite samp ed at random ionuclides).

nd Areas rvey units cl nits are show rvey units is Building, th ding and sys rform surfac mples were lored areas, ound had be ey units are s dentified in tively ident al plant-deriv py. The aver s 0.058 pCi/

137 concent maximum ob il samples w sed to areas o 2-25 stablished in easurements ions Project as given to low point g had been di ea classificat eas designat ass 1 survey cted biased a al random lo Depending from 1 to 3 m l sample or ctroscopy.

al to or less ples were an m and were s Duplicate lassified as wn in Figure obstructed b he WTB and stems, as we ce scanning d taken at loc

, buried pip een disturbed shown in Fig concentrati tified in con ved gamma rage Co-60 c

/g with a tration obser bserved conc were taken a on the south each survey s and/or sam Health Phy o locations gravity drain isturbed. Th tion. Rando ated as Clas y units whe and random cations or if on the loca m below gra asphalt sam Analysis co s than 0.10 p nalyzed afte shipped to T samples and Class 1 at L 2-1. A sign by the prese d the LSA ell as stored due to high b cations biase pe locations

d. The loca gure 2-6. O ions greater ncentrations a-emitting ra concentratio maximum rved in the centration o at 10 surface and west sid y unit in acc mples were d ysicist and that exhib n areas, actu he number m-based me ss 1. Rando ere there wa

-based surve f surface soi ation, subsur ade and com mple was ana ount times w pCi/g for Cs er drying th Test America d concrete w LACBWR to nificant porti ence of build Building.

radioactive background.

ed toward sit s, actual an ations of surf Of the 22 sur r than the M s greater th adionuclides on observed observed c analysis of f 1.07 pCi/g e soil locatio de of the WG cordance wit determined b the Radiolo bited measu ual and pote of random-b easurements om measure as no histor ey location.

l sample ana face soil sam mposited ove alyzed by th were adjuste s-137 and C he sample m a Laboratorie were collecte otaling 8,443 ion of the su dings, namel The presen material in tes that exhi nd potential face soil sam face soil sam MDC in tw han the MD s were posit in the analy concentratio f the surface

g.

ons to a dep GTV and fiv th the by the ogical urable ential based were ement ry of Sub-alysis mples r 1 m he on-ed as Co-60.

media.

es for ed by 3 m2.

urface ly the ce of these ibited spill mples mples wo (2)

DC in tively sis of on of e soil pth of ve (5)

La Cross License T Revision locations The sam evaluate Building samples 15 sampl identified of the su 0.161 pC areas is foundatio decommi Ten sam asphalt w this surv results ra measurem identified 0.057 pC A summ presented Nine sur samples gamma s In additi detected One sedi unit L10 and HTD 0.136 pC 2.3.4.2.

The imp immediat two surv LACBW these two Approxim 2350-1 d Alarm se instrumen se Boiling W Termination n 0 s that access mples at the t the subsurfa were taken taken, Cs-1 les. No oth d by gamma ubsurface so Ci/g. The ass not current ons and surr issioning pro mples were ta was taken fro vey unit. Th anging from ment of 3,09 d in concen Ci/g.

ary of the fi d in Table 2-rface soil sa taken from spectroscopy on to detect at concentra iment sampl 10103. This D analyses.

Ci/g.

Class acted Class te area surro ey units. Th WR Crib Hou o survey unit mately 1% o data logger w et-points for nt. No scan Water Reactor Plan ed the soils two WGTV ace soils alon and compo 137 was pos her potentia a spectroscop oil samples sessment of tly complete rounding bu ocess, when aken of asp om the same he asphalt s the instrume 95 dpm/100 ntrations gre indings of th

-10.

amples, 11 s Class 1 open y and HTD a ting Co-60 ations greate le was taken s sample wa Co-60 and 2 Open Lan 2 open lan ounding the hese are sho use, the G-3 ts.

of the surfac with a 2 by the instrum alarms were r

under the T V locations w ngside and u sited at dept sitively iden al plant-deriv py. The ave was 0.055 p potential su

e. Soil in uried structu access will b phalt from p e location se surface was ent MDC of cm2. Of th eater than he survey fo subsurface s n land surve analyses. Th and Cs-137 r than the in n from the s as also sent t C-137 were nd Areas nd areas tota LSE. The C own in Figur 3 Crib Hous ce soil area i y 2 NaI de ment were set e observed.

2-26 urbine Build were acquire underneath th ths of 10, 15 ntified in co ved gamma erage Cs-13 pCi/g with ubsurface soi difficult to ures and pip be more read paved areas lected for th first scanne f 2,771 dpm/

he 10 asphal MDC in on or each indiv soil samples ey units wer he results of

, H-3, C-14 nstrument MD sanitary solid to Test Amer e detected in al approxim Class 2 impa re 2-1. The se and the L in survey un etector. Thi t at the obse ding through ed to a dept he vault. Th 5 and 20 fee oncentration a-emitting ra 7 concentrat a maximum il contamina o access are ping has bee dily availabl in Class 1 s he surface an ed with beta

/100cm2 to a lt samples t nly one sam vidual Class s, one concr re sent to Te f the analysis 4, Fe-55 and DC.

ds tank that rica Laborat n this sampl mately 13,99 acted open l LACBWR LACBWR w nit L201110 is area inclu erved backgr h angled Geo th of five m he samples u et. Of the 7 ns greater th adionuclides tion observe m observed ation in the C eas such as en deferred le.

survey unit nd subsurfac a-gamma de a maximum taken, Cs-13 mple at a s 1 open land rete sample est America s are present d Ni-63 wer is located i tory for gam e, both at a 6 m2 and ar and area wa Administrat warehouses a 1 was scann uded asphalt round plus t oprobe samp meters in ord under the Tu 79 subsurface han the MD s were posit ed in the ana concentratio Class 1 open s under bui until later i L1010104.

ce soil sampl etector with of observed 37 was posit concentratio d survey un and two as a Laboratorie ted in Table re also posit in Class 1 su mma spectros concentrati re located in as segregated tion Building are all locat ned with a M t paved surf the MDCR o pling.

der to urbine e soil DC in tively alysis on of n land ilding n the The les in scan d scan tively on of nit are sphalt es for 2-11.

tively urvey scopy on of n the d into g, the ted in Model faces.

of the

La Cross License T Revision Twenty-t measurab locations taken in taken, Cs other pot The aver 0.077 pC Twenty-t and three resides in Of the 2 greater th than MD identified of 0.112 samples assessme currently surround process, w Twelve s selected results r 2,748 dpm concentra concentra observed A summ presented Three sur samples Administ HTD ana Co-60 a concentra HTD rad 2.3.4.3.

The impa land area Figure 2-site, the t se Boiling W Termination n 0 three surfac ble radioact s, or areas w Class 2 open s-137 was p tential plant rage Cs-137 Ci/g with a m three subsur e locations b n survey uni 23 subsurfac han MDC in DC in four d by gamma pCi/g. The was 0.043 ent of poten y complete.

ding buried s when access samples were randomly.

ranging fro m/100cm2.

ations great ation observ d concentrati ary of the fi d in Table 2-rface soil sa taken from tration Build alyses. The and Cs-137, ations greate dionuclides e Class acted Class 3 a was segre

-1. The Cla transmission Water Reactor Plan e soil samp tivity, disco where the gro n land surve positively ide t-derived rad 7 concentrat maximum obs face soil sam biased to are it L2011101 ce soil samp n one sample samples. N spectroscop average Cs-pCi/g with ntial subsurf Soil in dif structures an s will be mor e taken of as The asphalt om the ins Of the 12 ter than the ved in the an on of 0.055 indings of th

-12.

amples, five m an acces ding were se results of th H-3, C-14 er than MD exceeding M 3 Open Lan 3 open land egated into ass 3 impacte n switchyard r

ples were tak lored areas, ound had be ey units are s entified at co dionuclides tion observe served conce mples were t eas alongsid

1. The biase ples taken, e and Cs-13 No other po py. The sing

-137 concent h a maximu face soil con fficult to ac nd piping ha re readily av sphalt from p t surface wa strument M 2 asphalt sa e instrumen nalysis of the pCi/g.

he survey fo subsurface s ssible storm ent to Test he analysis a 4, Fe-55 an DC. As disc MDC are likel nd Areas areas total a three surve ed open land for the LAC 2-27 ken at locat

, buried pip een disturbed shown in Fig oncentration were positiv ed in the an entration of taken at 14 r de and under ed samples w Co-60 was 7 was positi otential plan gle sample w tration obser um observe ntamination cess areas s as been defe vailable.

paved areas s first scann MDC of 2, mples taken nt MDC in e asphalt sam or each indiv soil samples, m sewer ba America La are presented nd Cm-243/

cussed in se ly to be false approximatel ey units. T d survey un CBWR and G tions biased pe locations

d. The loca gure 2-7. O ns greater th vely identifi nalysis of th 0.200 pCi/g random loca rneath the S were acquire positively ively identif nt-derived ra with detectab rved in the a d concentra n in the Cla such as und erred until l in Class 2 su ned with bet

,529 dpm/10 n, Cs-137 w three samp mples was 0 vidual Class

, three aspha asin manhol aboratories f d in Table 2

/244 were ection 2.3.3 e positives.

ly 66,765m2 The Class 3 nits include t G-3 facilitie d toward sit s, actual an ations of surf Of the 23 sur han MDC in ied by gamm he surface s

g.

ations to a de Storm Sewer ed to a dept identified a fied at conce adionuclides ble Co-60 ha analysis of th ation of 0.0 ass 2 open l der building ater in the d urvey units.

ta-gamma de 00cm2 to a was positive ples. The 0.049 pCi/g s 2 open land alt samples a le located for gamma s

-13. In add also positiv for non-imp

2. The Class survey uni the north en s, the LACB es that exhi nd potential face soil sam face soil sam 14 samples ma spectrosc soil samples epth of one m r Water pipe th of five m at concentra entrations gr s were posit ad a concentr he subsurfac 088 pCi/g.

land areas i foundations decommissio The asphal etector with a maximum ely identifie average Cs with a maxi d survey un and two sedi in front of spectroscopy dition to dete vely detecte pacted areas 3 impacted its are show nd of the lice BWR plant a ibited spill mples mples

. No copy.

s was meter e that meters.

ations reater tively ration e soil The s not s and oning lt was h scan m of ed in s-137 imum nit are iment f the y and ecting ed at s, the open wn in ensed access

La Cross License T Revision and right was deem LACBW Crib Hou facility d were dee These ar Solutions A minim scanned was excl focused o points fo No scan Thirty-tw where th open lan was posi plant-der The aver 0.131 pC Seventee meter.

concentra radionuc concentra maximum Two sam selected results w were pos A summ presented As part o of concre Crib Hou Administ survey un Three co L301210 three sur Laborato se Boiling W Termination n 0 t-of-way are med impacte WR Administ use). The tr during operat emed as imp reas were c s maintains t mum of 1%

with a Mod luded from on undisturb r the instrum alarms were wo surface so he ground ha d survey un tively identi rived gamma rage Cs-137 Ci/g with a m en subsurfac Of the 17 ations grea lides were ation observ m observed c mples were t randomly.

were less tha sitively ident ary of the fi d in Table 2-of the charac ete located i use. In addi tration Build nit L301210 oncrete samp 01, the two se rface soil s ories for gam Water Reactor Plan a and the ha ed by LACB tration Build ransmission tions. The p pacted by th onservativel that classifyi of the surf el 2350-1 da gamma sur bed soils wi ment were se e observed in oil samples ad been dist nits are show ified in conc a-emitting ra 7 concentrat maximum obs e soil sampl 7 subsurface ater than M positively ved in the a concentratio aken of asph The asphalt an instrumen tified by gam indings of th

-14.

cterization of in the north ition, a sam ding and tw

9. These sam ples from su ediment sam samples and mma spectr r

aul road to th BWR due to ding and the yard was d plant access he transit of ly classified ing these are face soil are ata logger w rface scanni ith minimal et at the obse n these surve were taken turbed. The wn in Figure centrations g adionuclides tion observe served conce les were tak e soil samp MDC in ei identified analysis of th on of 0.409 p halt from pa surface wa nt MDC of 1 mma spectro he survey fo f survey unit h section of mple was take wo sediment mples were urvey unit L3 mples taken f d two subs roscopy and 2-28 he ISFSI fac o the presen presence of deemed as im area, Highw f packaged r d as impacte eas as non-im ea in survey with a 2 by ing for safe vegetation o erved backgr ey units.

at locations e locations o e 2-8. Of th greater than s were positi ed in the an entration of ken at random ples taken, ight samples by gamma he subsurfac pCi/g.

aved areas in s first scann 1,938 dpm/1 scopy in any or each indiv t L3012101, the survey u en from a sa t samples w sent off-site 3012101, th from the stor surface soil d HTD anal cility. The n nce of a sep f concrete fr mpacted as i way 35 right radioactive m ed. Howev mpacted wou y units L30 2 NaI dete ety reasons.

or disturbed round plus t biased tow of surface s he 32 surface MDC in 26 ively identif nalysis of th 0.463 pCi/g mly selected Cs-137 w

s. No oth spectrosco ce soil samp n Class 3 su ned with bet 100cm2. No y of these sam vidual Class

, samples we unit that ori anitary tank were taken fr e for isotopic he sanitary ta rm sewer ba samples w lyses. The north end of ptic system from impacte it was part o t-of way and material thro ver, it shou uld have bee 012101 and ector. Surve Gamma d soils or gra the MDCR o ard discolor oil samples e soil sampl samples. N fied by gamm he surface s

g.

d locations t was positive ther potenti opy. The ples was 0.0 urvey units.

ta-gamma de o plant deriv amples.

s 3 open land ere taken fro iginated from k that service from a storm c analysis.

ank sample asin in survey were sent t results of f the license that service ed structures of the LACB d ISFSI haul ough these a ld be noted en appropriat L3012109 ey unit L301 surface scan avel. Alarm of the instrum red areas or taken in Cl les taken, Cs No other pote ma spectrosc soil samples to a depth o ely identifie ial plant-de average Cs 087 pCi/g w The asphalt etector. All ved radionuc d survey un om several p m the LACB es the LACB m sewer bas from survey y unit L3012 to Test Am the analysi d site es the s (the BWR l road areas.

d that te.

were 12102 nning m set-ment.

areas lass 3 s-137 ential copy.

s was of one ed in erived s-137 with a t was l scan clides nit are pieces BWR BWR sin in y unit

2109, merica is are

La Cross License T Revision presented derived R and Ni-6 exceedin consisten 2.3.5. N Based up associate indicated A full lis

2.

The prim informati operation from the character The resu conducte traffic in The G-3 incidents results of A scan su gamma d using an was also gross bet MDC of identified gross alp contamin samples.

derived 0.061 pC that the material Direct an traffic ar Model 23 areas of i ranged f exceeded se Boiling W Termination n 0 d in Table 2 ROC at resid

63. As dis ng MDC are nt with natur Non-Impacte pon the inf ed with the G d that there w st of G-3 stru mary basis f ion documen ns. Additio e LACBWR rization of t ults are prov ed during the the major st station res s of radioact f the charact urvey was p detector. In alpha/beta-g taken at the ta-gamma a f 2,816 dpm/

d gross beta-pha activity nation was i The roof m ROC that w Ci/g. Based elevated dir on the roof.

nd removabl reas of the 360 instrume interest were from 2,540 d the MDC d Water Reactor Plan 2-15. The dual concent scussed in s likely to be ral backgroun ed Structur formation co G-3 Coal Pla was no reaso uctures that for the non nted in the H nally, the p R Stack du the LACBW vided in Re e 2015 chara tation buildin sides in non tive contam erization sur performed of addition, six gamma prop location of ctivity rangi

/100cm2. T

-gamma acti y ranging f dentified at material itse was positive on the fact t rect alpha m le contamin G-3 Coal P ent with 43-e scanned, in dpm/100cm during the co r

analysis of trations grea section 2.3.3 false positiv nd.

es ompiled in ant may be c onable poten have been d n-impacted HSA that the potential for uring opera WR Administ eference 13 acterization ngs were sur n-impacted s mination of s rveys perform f the mid-lev x (6) locatio portional dete each direct m ing from 2,3 The results o ivity ranging from 142 dp concentratio elf was samp ely identifie that no other measurements ation survey Plant. Scan

-93 detector.

ncluding floo m2 to 2,617 ourse of this 2-29 f these samp ater than the 3 for non-im ves. Cs-137 the HSA, S classified as ntial for resi designated as classificatio e G-3 structu windborne ations to s tration Build

. Addition campaign w rveyed.

survey unit soils, asphal med in the G vel roof of th ons were sele ector. A sm measuremen 302 dpm/10 of the direc g from 1,603 pm/100cm2 ons greater t pled on Jun ed by gamm r plant deriv s were due ys were perf n measureme

. Approxim ors and lowe 7 dpm/100cm s survey. Te ples positive e instrument mpacted are was also po Solutions co non-impac dual contam s non-impa on for the G ures were no migration o structure roo ding roof an nal surveys where the su L4012103.

lt or concre G-3 station a he G-3 Coal ected at rand mear sample nt. The resu 0cm2 to 2,8 ct beta-gamm 3 dpm/100cm to 258 dpm than MDC b ne 30, 2015.

ma spectros ved ROC wa most likely formed of re ents were p mately 5% of er wall surfa m2. No o en (10) locat ely identifie MDC, inclu eas, the HT ositively dete oncluded th cted. Histo mination from acted is prov G-3 station ot used for L of airborne ofs was ev nd the G-3 of the G-3 urfaces subje There are ete in this su are summariz l Plant build dom for dire for removab ults of the be 816 dpm/100 ma and alph m2 to 2,072 m/100cm2.

by the analy Cs-137 wa scopy at a as detected, to the pres epresentativ performed us f the concret aces. The av observed sca tions were ch ed several p uding H-3, F TD radionuc ected but at l hat the struc orical inform m site operat vided in Tab structures i LACBWR-re effluent rele valuated by Coal Plant structures ected to high e no docum urvey unit.

zed as follow ding using a ect measurem ble contamin eta scan iden 0cm2 with a ha measurem dpm/100cm No remov ysis of the s as the only concentratio it was concl sence of coa ve high perso sing the Lu te surfaces i verage scan M an measure hosen at ran plant-Fe-55 clides levels ctures mation tions.

ble 2-is the elated eased y the roof.

were h foot ented The ws:

beta-ments nation ntified scan ments m2 and vable smear plant on of luded al ash onnel udlum in the MDC ement

ndom,

La Cross License T Revision primarily measurem 875 dpm greater th 2.3.6. Im The deco impacted In additio accepted remain a Reactor B remainin and floo Reactor/G Turbine surfaces segregate radioactiv systems o Radiolog complian radiologi areas.

disassem remediat demolitio waste.

After com 3 feet be radioactiv use criter 2.3.6.1.

Characte consisted walls an (primaril taken fro 621 foot the 633 f samples w Piping Tu se Boiling W Termination n 0 y from the ments for g

/100cm2 for han MDC by mpacted Str ommissionin d buildings, s on, all system elevation fo and be subje Building tha ng reinforced ors of the Generator P sump and th above the ed by waste ve waste.

or structures gical surveys nce with 10 ical conditio The radiolo mbly and rem ion has ade on, the impa mmodity rem elow grade, vity and the ria.

Basem rization of d primarily o d floors of ly the Piping om the 615 elevation in foot elevatio were collect unnel. The l Water Reactor Plan main lobby gross activit beta-gamm y the analysi ructures an ng approach structures, sy ms and expo or grade at L ected to STS at will be exp d concrete w WGTV, an lant baseme he Turbine 636 foot ele classificatio No extensi s that will be s of the inter 0 CFR 20 re ons for the im ogical infor moval of syst equately red acted structu moval is com

, will be r e extent of a ment Structu the structur of the acquis the Reactor g Tunnels).

foot elevati n the Reactor on concrete f ted, six (6) in locations wh r

y area and y was less

a. No remov s of the sme nd Systems h for LACB ystems and c osed metal b LACBWR is S are the rem posed by the walls floors o nd the rem ent, the one pit. Conseq evation will on and dispo ive characte e removed pr riors of struc equirements mplementati rmation from tems and the duced radiol ures will be mplete, the s re-surveyed additional re ures Below 6 ral surfaces ition and rad r Building, In June and on concrete r Building, th floor of the P n the Reacto here the core 2-30 the mainte than the M vable contam ar samples.

BWR requir components below 3 feet the 639 foo maining rein e removal of of the WTB, mainder of foot thick p quently, all l be remedi osed of as c erization wa rior to the pe tures at LAC regarding on of contro m these su e demolition logical cond demolished tructures tha to determi emediation r 36 Foot Elev of basemen diological an WTB and July of 2015 floor and t he 630 foot Piping Tunn or Building, e samples we enance area.

MDC of 74 mination wa res the dem to a depth o below grad ot elevation.

nforced conc f the interior the remaini the Piping portion of th systems and iated, disass clean demoli as or will b erformance o CBWR are r the posting ols for the pr urveys will of impacted ditions to le d, packaged at will remai ine the con required, if a vation nts that wil nalysis of co the balance 5, a series o the concrete elevation co nels. A total three (3) in ere taken are

. The resu dpm/100cm as identified molition and of at least 3 de will also b The only st crete walls a r concrete an ing reinforce g and Vent he Chimney d componen sembled and ition debris, be performe of FRS.

routinely per g of areas rotection of provide th d structures a evels suitabl and properl in at license ncentrations any, to meet ll remain in oncrete core e of the bas f concrete co e floor and oncrete floor l of twelve (

the WTB an e shown in F ults of all d m2 for alpha at concentra d removal o feet below g be removed.

tructures tha and floors o nd steel line ed concrete tilation Tun y Foundation nts and struc d/or demoli clean salva ed of equipm rformed to en and to ide f workers in he basis for at the site. W le for contr ly disposed termination of the res t the unrestr n the end-s samples from sement struc ore samples east wall o r of the WTB

12) concrete nd three (3) i Figures 2-9.

direct a and ations of all grade.

The at will of the er, the walls

nnels, n, the ctural
ished, age or
ment, nsure entify these r the When rolled of as n, i.e.,

sidual ricted state m the ctures were n the B and e core in the

La Cross License T Revision The loca condition volumetr elevated wall sur discolora that exh condition there was radionuc The conc Test Ame ROC. In Reactor B and #002 concrete analysis positively 59, Tc-99 concrete 2.3.6.2.

A concre Turbine contamin in the T Analysis 0.106 pC 2.3.6.3.

As stated subjected graded su As repor radioactiv building located i Administ proximity laborator Characte beta-gam gross bet se Boiling W Termination n 0 ations selecte n or observ ric contamin observed co faces were ation or stan hibited the h n for concre s sufficient s lide fraction crete pucks r erica Labora n addition, Building sam 2 were also cores is pr of the conc y detected at 9, Pu-238, P core sample Turbin ete core was Building T nation event Turbine Buil of this sam Ci/g and H-3 LACB d previously d to FRS. In urvey approa rted in the H ve spills or has primaril in the build tration Build y to the LSE ry.

rization surv mma/alpha a ta-gamma/al Water Reactor Plan ed for concr ved radiolog ation of the ontact dose r used to id nding water.

highest pot ete in each s source term ns of gamma representing atory for gam the concrete mple locatio o sent for is resented in rete core sa t concentrati Pu-239/240, es is presente ne Building s obtained as Tunnel to cited in the lding and t mple indicate at 1.71 pCi/

BWR Admin y, the LACB nstead, these ach in accord HSA, there w radioactive ly been used ding that sup ding was in E, occupancy veys of the ctivity of in lpha activity r

rete core sam gical measu concrete. W rates or coun dentify poten The goal w ential of re survey unit.

in the cores emitters as w g the first 1/2 mma spectro e pucks rep ns #001, #0 sotopic analy Table 2-16.

amples inclu ions greater Pu-241, Am ed in Referen Tunnel s part of the attempt to HSA pertain the potential ed detectable

/g.

nistration Bu BWR Admin e two structu dance with M was no past contaminati d for office sp pported both nitially class y by LACBW LACBWR nterior floor were also p 2-31 mpling were urements in When possibl nt rates. In a ntial locatio was to ident epresenting This judg to achieve t well as HTD inch of conc oscopy and H presenting th 03, #005 an ysis. A sum Significan ude Ni-63, H than their re m-241 and A nce 16.

e 2014 chara evaluate ning to the d l radiologic e concentrat uilding nistration Bu ures will be MARSAME history of th ion in the LA pace and rec h LACBWR sified as a M WR personn Administrat rs surfaces a performed on biased tow ndicated the le, locations addition, vis ons of surf tify, to the e the worst gmental samp the sensitivit D radionuclid crete at each HTD analyse he concrete nd #006 and mmary of t nt HTD rad H-3 and Sr-9 espective MD Am-243. An acterization the possibl discovery of cal contamin tions of Cs-1 uilding and surveyed fo E guidance.

he use of un ACBWR A cords storage R and G-3 MARSSIM nel and the p tion Buildin and the roof n the roof, on ward location e presence were determ sual observat face contam extent possib case bound mpling appro ties required des.

h sample loc es for beta an deeper than WTB samp the analytica dionuclides i

90. The oth DC include; analysis of survey from le extent o f cracked dra nation of su 137 at 0.352 G-3 Crib H or unrestricte nsealed radio dministratio
e. An enviro operations.

Class 2 stru resence of th ng included

f. Direct m n floor tiles ns where phy of fixed a mined based tions of floo mination, suc ble, the loca ding radiolo ach also en d to determin cation was se nd alpha em n 1/2 inch de le locations al results fo identified by her radionuc C-14, Fe-55 the results o m the floor o of a radioa ain system p urrounding 2 pCi/g, Co-House will n ed release us oactive mate on Building.

onmental lab The LACB ucture due t he environm a scan for measurement and around ysical and/or upon or and ch as ations ogical sured ne the ent to mitting eep at

  1. 001 or the y the clides 5, Ni-of the of the active piping soils.

-60 at not be sing a

erials, The b was BWR to its mental gross ts for floor

La Cross License T Revision drain ope each dire The resu 4,915 dpm the secon imbedded gamma s was then and seco from less and dire observed Beta sc 2,261 dpm from less Direct be of 243 d measurem identified 2.3.7. S Section 8 hydrogeo was deri Haley &

(18) supp 2.3.7.1.

For a di towns an river wat

Lansing, water fo approxim The LAC well at th state perm LACBW Building areas are to the gr pathway se Boiling W Termination n 0 enings. A sm ect measurem ults of the m/100cm2 w nd floor ha d in a floor spectroscopy n performed ond floor lam s than MDC ct alpha re d reading of 7 cans of th m/100cm2 w s than MDC eta-gamma m dpm/100cm2 ments were d concentrati urface and 8.5 in Chap ology and hy ived directly Aldrich, Hy plements the Area Grou stance of 40 nd cities alon ter for indus Iowa, about or industria mately 40 mi CBWR site he site. Sani mitted sanit WR Adminis

. Storm wa e periodically round area su after passing Water Reactor Plan mear sample ment.

beta scans with a scan M allway, a di tile. The c

y. The analy involving th minated woo of 329 dpm adings rang 72 dpm/100c he roof are with a scan M C of 113 dpm measurement to a maxim all less than ions greater Groundwat pter 8 of t ydrology of y from Hal ydrogeologic e preliminary undwater Us 0 miles dow ng the Missis strial purpos t 15 miles d al purposes les downstre has its own itary wastes tary wastes h tration Buil ater runoff is y monitored urrounding t g through an r

e for remova of the int MDC of 2,10 screte radio contaminated ysis of the ti he acquisitio od, carpet, a m/100cm2 to ged from le cm2.

ea indicate MDC of 2,26 m/100cm2 to ts taken on t mum observ n MDC of 4 than MDC b ter his LTP c ZNPS and e ey & Aldri cal Investiga y findings in se wnstream of ssippi River ses, excludin downstream o between t eam.

potable wa are collecte hauler. Thi lding and a s diverted di d for oil shee the facility v n oil separato 2-32 able contam terior surfac 00 dpm/100c oactive parti d portion of ile identified n of ten (10) and floor til a maximum ess than MD ed results 61 dpm/100c o a maximum the floor dra ved reading 42 dpm/100c by the analy ontains a s environs. T ich, Hydrog ation Report n Reference 1 the site, vir are obtained ng the adjac of the site.

the LACBW ater supply, p d in a solids is includes a a sanitary h irectly to th en and disco via downspo or located in mination was ces ranged cm2. During icle was dis f the tile wa d 0.005 uCi

) biased dire le. Direct b m observed re DC of 39 d ranging fr cm2. Direct m observed ain openings g of 333 dp cm2. No re sis of the sm summary d The informat geological C t for the LaC

17.

rtually all m d from groun cent G-3 pla There are n WR site an provided thr s holding tan a sanitary ho holding tank he Mississipp oloration. R outs or ente nside the LSE also taken from 1,420 g the scan of scovered. T as removed of Cs-137.

ect measurem beta-gamma eading of 5, dpm/100cm2 rom 1,872 t alpha meas reading of 1 s ranged from pm/100cm2 a emovable co mear samples description tion containe Conceptual S Crosse Boilin municipal w und water. T ant, is the co no other know nd Prairie rough a sing nk and pump olding tank k that servi pi River at o Roof drains d r the norma E.

at the locati 0 dpm/100cm f the north e The particle and analyze An investig ments on the readings ra

,743 dpm/10 to a maxi dpm/100cm surements ra 152 dpm/100 m less than M and direct ontamination

s.

of the geo ed in this se Site Model ng Water Re water supplie The nearest u oal-fired pla wn users of du Chien, gle ground w ped off by a that service ices the Tu outfalls. Re discharge dir al effluent re on of m2 to end of e was ed by gation e first anged 00cm2 imum m2 to anged 0cm2.

MDC alpha n was

ology, ection (17).

eactor es for use of ant in f river WI, water local es the urbine elease rectly elease

La Cross License T Revision 2.3.7.2.

Regional Mississip parallels upward; river stag demonstr river stag Groundw surface (

Groundw the Missi may turn chemical the shallo Based on of the G-located i monitorin a slightly has a do gradient towards t there are stages. G Reactor B are below During p was com permeabi buildings soils will will circ localized outside th other han or buried underlyin shallow s contamin soils with orders of se Boiling W Termination n 0 Groundw lly, groundw ppi river. C the river. U however, th ge data comp rates that the ge impacts th water beneath bgs) and the water in the s issippi Rive n and flow l constituent ow system.

n a review of

-3 Ash Land in the sout ng wells (B1 y downward ownward gr at well pair the river bas e some perio Groundwater Building ba w the water t plant constru mpacted, redu ility can dec

s. The resul l flow at a s cumnavigate d flow regim he footprint nd, potential d piling, will ng groundw soils from p nation. The hin the supp f magnitude Water Reactor Plan ater Flow water flows i Closer to th Under typic he vertical gr pared to wa e shallow aq he water tabl h the site is e groundwat shallow depo
r. The deep parallel to s would occu f the ground dfill area grou th side of t 11AR/B11R vertical gra radient at w B9/B9A. T sin with a lo ods where t r flow throu sement shel table during uction, and m ucing the eff crease the h lting impact slower veloc the area, e mes on contam of these str l releases tha l likely take water. This precipitation, average sha port pilings, lower.

r in a westerl he shore, gr al river stag radient rever ter table ele quifer is in di le elevation.

first encoun ter is in dire osits and fill per groundw the river.

ur at or near dwater elevat undwater mo the LACBW

) to the east adient. Durin well pairs B This is expec ocalized influ the gradients ugh the LAC l) as well as high and low more specifi fective poros hydraulic con to groundw city, and reg effectively b minant fate a ructures will at occurred w much longe is further c

, creating an allow aquifer the hydraul 2-33 ly direction roundwater ge, groundw rses during f evations mea irect hydrau ntered at an ect hydraulic l material flo water is also Because th r the surface tion measure onitoring we WR site, an of and up gr ng times of n B11R/B11AR cted as grou uence at B9/

s are revers CBWR site is s the deep p w river stage ically the ins sity and perm nductivity o water flow is gionally, a si bypassing th and transpor l likely be d within the fo er to migrate compounded n area that w r hydraulic c ic conductiv from the bl may also h water gradien flood stages.

asure in LAC ulic commun n average de c communica ows towards likely to flo he potential

, the release ements colle ells (# B2/B3 nd associate radient of LA normal and R and B2/B undwater flo

/B9A from t sed; and this s impacted b pilings that s e conditions.

stallation of meability of of the aquife s that ground ignificant pe these soils.

rt are that po deflected and ootprint of th e both in th d as the ove will likely re conductivity vity would b luffs on the have a flow nts near the

. The geolog CBWR site nication with epth of 20 fe ation with th s the west an ow towards t l releases of s would like ected during 3/B9A/B9/B ed backgrou ACBWR, th low river sta B3, with an ows generally the adjacent s is likely d by deeper st support the f the support f the soils. T er within the dwater withi ercentage of The impli otential relea d flow aroun he buildings e vadose zo erlying struc etain any po y is 313 feet be expected east toward component river are sli gical and his monitoring h the river an eet below gr he adjacent nd discharges the west but f radiologic ely be confin routine sam B7/B8), whic und groundw here appears age, groundw upward ve y from the b t inlet. How due to high tructures (i.e structures, w t pilings, the This reducti e footprint o in the comp f the flow re ications of ases that occ nd them. O s, via floor d one as well a ctures isolat tentially rele per day. Fo to be one to ds the t that ightly storic wells nd the round river.

s into t then cal or ned to mpling ch are water to be water ertical bluffs

wever, river e., the which e soil ion in of the pacted egime these curred On the drains as the te the eased or the o two

La Cross License T Revision The velo gradient.

across th Therefor the inch Environm show sea stage. Th LACBW vicinity structure direction 2.3.7.3.

Historica monitorin monitorin monitorin Dairylan Of the w LACBW routine b designate Environm G-3 Foss Nos. 3, 4 levels re 3.0E-08 µ During th to the s radioactiv The well suspected that samp As note Activities wells to monitorin if ground located n interval o below gr B.

se Boiling W Termination n 0 ocity of gro The gradie he site, groun e, it is likely hes and fee mental Moni asonal varia hese wells a WR site struct of suspect s/foundation ns.

Previous I ally, the LAC ng wells. F ng wells loc ng wells of d for radiolo wells shown WR facilities basis. The gr ed as B-2, mental Moni sil Station op 4 and 5 wer ported durin

µCi/ml to 9.

he recovery outh of the ve liquids fr l-point show d leakage. T ple are prese d in the L s Report (D support gro ng wells (10 dwater qual nominally wi of 15 to 25 f rade. These Water Reactor Plan oundwater is ent of the wa ndwater mon y that the gro et/day rang itoring Prog ation on upw are not suffic tures or area broken dra ns or variati Investigation CBWR Lice igure 2-11 i cated on th ff the LACB ogical purpo n on Figure were histor roundwater m B-3, B-7, itoring staff perational re re routinely ng this mon 0E-08 µCi/m of a probab e Turbine B rom suspect wn on Figure The well-po ented in Tabl LACBWR D D-Plan/PSDA oundwater e 0 wells total) ity had bee ithin five (5) feet below g wells are sh r

s directly r ater table is i nitoring has oundwater v e). Ground gram wells a ward and do cient to char as where pote ain lines) co ions in fill m ns ensed Site ha llustrates the e LACBWR BWR site t ses.

2-11, only P rically monit monitoring w B-8, B-9, on a routine equirements.

monitored f nitoring peri ml).

le spill incid Building. T broken drain 2-11 was es int was sam le 2-17. Thi Decommissio AR) (19), D evaluation.

) were instal en impacted

) feet of one grade and on how on Figu 2-34 elated to bo nfluenced by shown that velocity acro water eleva agree with t ownward gra racterize the ential releas ould have o materials co as had sever e current loc R site. The that are or Potable Wa tored by Da wells and ba B-9A, B11A e basis for no During LA for gross be iod was less dent in 1983 This inciden n lines in th stablished do mpled once o is well-point oning Plan airyland rec In Novemb lled within t by plant o e another con ne deep well ure 2-11 as M oth the hyd y the topogr the water ta oss the site is ation data the regional adients that groundwate es associated occurred. In ould locally ral potable w cation of po ere is no po have been ater Wells N airyland for ackground gr AR, and B on-radiologi ACBWR ope eta activity.

s than or eq

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G-3 Coal er flow, and nced by the w and aroun BWR (i.e., i as, pilings, groundwater and groundw and groundw r or groundw by Solution 4 which serv l conditions monitoring monitored by ers to suppo able Water W ross beta ac DC (ranging nt was establ ential leakag ub-building w the grade o nalysis resul ned.

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of the ts for oning toring water rmine were eened 5 feet A and

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18.

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samples wer a seasonal l to an off-sit was perform of groundwa Water Wells #

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e off-site ana ons r monitoring analysis pu her and lowe A/B wells as g each monit the respecti water pH/spe ved oxygen/t rmation incl ection.

undwater An fforts comme in Novemb tively detect 02-A and B, ations rangi wells durin 18 pCi/L; ho

d. Co-60 an eriod, H-3 w W-203B) at c ected in w 2-35 re collected low groundw te laboratory med on site.

ater samples

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luding a com nalytical Res enced throug ber 2012 an ted at concen MW-203A ing from 15 ng the June owever, it w nd Cs-137 w was positively oncentration wells MW-20 in 2013, du water level y for radiolo s was collec 7; and Mon ere sent off radionuclide MW 200A an B11AR. T veral radion es a summar ratory repor onsists of ob y from exis

. The moni igure 2-11.

val includes:

ng well.

ctance/oxida mpleted chain sults gh the install nd the com ntration grea and B and M 50 pCi/L to 2013 sampl was not po were not po y detected in ns ranging fr 02A, MW-2 uring the sea in Novemb ogical analys cted from: M nitoring Well f for radiolo es. In Septe nd B throug These collec nuclides incl ry of the radi rts are provi btaining grou ting monito toring wells ation and red n of custody lation of 10 mmencement ater than MD MW-204A a 660 pCi/L.

ling period a ositively dete sitively dete n four (4) w from 245 pC 203A and asonal high w ber 2013. T sis for Co-60 MW-200A a ls B2, B-3, B ogical analys ember of 20 gh 204A an cted groundw luding HTD iological ana ded in Refer undwater sam oring wells w s sampled in duction y following monitoring of groundw DC in monit and B in Jun Sr-90 was at concentra ected during ected in any wells (MW-B i/L to 336 p MW-204A water These 0, Sr-and B B11R sis of 014 a nd B, water D and alysis rence mples when clude wells water toring e and s also ations g the y well

B11R, pCi/L.

with

La Cross License T Revision concentra Am-241 During t greater th concentra were also 2.4.

C The surv deferred.

under co that will basement illustrate defer the condition ALARA data wou areas),

Safet Histo Acce struct interf The a physi condi As acces will be co for the s radionuc and HTD events ca of a surv stored in validatin As decom surface d for open documen se Boiling W Termination n 0 ations rangin were also po he Septemb han MDC in ation of 1.14 o positively d Continuing C vey of many Examples ncrete or asp remain and t after liner s buried pip e characteriz ns:

consideratio uld likely not ty considerat orical data sh ss for charac tures or othe fere with con ability to use ical relations itions repres ss is gained ollected, eva survey unit.

lides present D radionuclid aused by equ vey unit(s) w n the charac g the initial mmissioning decontamina n air demolit nted survey a Water Reactor Plan ng from 1.1 ositively det ber 2014 sam n any well.

4 pCi/L. Co detected at r Characteriz inaccessible s of areas w phalt coverin d be subjec r removal an ping systems zation of a ons (e.g., the t change the

tions, hows that the cterization w er obstacles w ntinued oper e engineering ship to surro sented by the to areas tha aluated and s This data t and update des. In addi uipment failu will be reco terization d classificatio g proceeds, ation (as wel tion or unre and a formal r

12 pCi/L to ected at resi mple period, Sr-90 was o-60, Ni-63, residual conc zation e or not read where survey ngs, structur cted to FRS nd the inter s that may r soil or stru e area is eith e survey area e area could would require where the re ration of ope g judgment i ounding area e conditions at were prev stored with-o will be use e the variabil ition, as the ures or perso orded. Thes atabase. Th n and in plan areas will, ll as fixed co estricted rele l turnover w 2-36 2.01 pCi/L.

dual concen

, H-3 was n positively d

, Cs-137, Eu centrations in dily accessib ys are deferr ral wall and

, the underl riors of bur remain in th ucture was b her a radiati a or area clas be classified e significant emoval could erating system in assigning s and the lik in these adja viously inacc other radiolo ed along wi lity in the ra decommiss onnel errors, se events w his additiona nning for the as necessar ontamination ease. When will be made C-14, Tc-9 ntrations in se not positivel detected in o u-152, Eu-15 n several we ble subsurfa rred include floor surfac rlying concr ried pipe tha he end-state based on on ion or conta ssification o d without fur t deconstruct d result in an ms, or the area a cl kelihood of th acent areas.

cessible, add ogical survey ith existing adionuclide m ioning progr

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ry, be decon n) to levels n a structur by the Radi 99, Eu-152, everal wells ly detected a one (1) well 54, Pu-239/2 ells.

ace soils or s soils under ces in some rete in the R at may rem condition.

ne or more amination are of the locatio rther charact tion of adjac n unsafe con lassification he area to ha ditional char y data in a s data to upd mix for both resses, data y affect the ra uated and, w rization data ntaminated that will me e is ready f ological Pro Pu-239/240 at concentra l, MW-200A 240 and Am surfaces has r structures, of the basem Reactor Bui main. Figure The decisi of the follo ea and addit on or surroun terization, cent systems ndition or n based on ave radiolog racterization urvey histor date the typ h gamma-em from operat adiological s when approp a will be us to remove eet the condi for demoliti otection grou 0 and ations A at a m-241 been soils ments ilding e 2-3 on to owing tional nding s,

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, and FRS), a lans will co ese objective ropriate instr n level and/o ropriate instr ropriate surv the calibrati ropriate samp nuclide ratio analysis crit ional sample ropriate class References U.S. Nuclear Content of Li 011.

U.S. Nuclear Radiation Sur U.S. Nuclear Consolidated f Radiologic EnergySoluti Crosse Boilin EnergySoluti ite Characte Water Reactor Plan ming demoli lition and/or ent" will be p will be met, cterization/L FRS. Otherw over survey,"

ey" process, epresent at le conducting t a documente ontain the ap es include:

rument selec or release cri rument quali ey technique on methodol ple collectio os, teria to ident es and, sification of Regulatory icense Termi Regulatory rvey and Site Regulatory Decommiss cal Criteria, F ons PG-EO-ng Water Rea ons GP-EO-erization Proj r

ition, validat r remediation performed. I

, then physi License Term wise, additio

" primarily fo together wi east one, but the FRS. Fo ed survey pl ppropriate da ction to ensur

iteria, ity control m es to ensure
logies, n and analys tify follow-u the survey a Commission ination Plan Commission e Investigati Commission sioning Guid Final Report

-313196-SV actor.

-313196-QA ject (QAPP) 2-37 ting that the n, and when If the results ical and adm mination grou onal remedia for Class 1 an ith any addi t possibly se or each type an will be d ata assessme re the proper measures to e that the field sis to determ up actions su area.

n, Regulator s for Nuclea n, NUREG-1 ion Manual (

n, NUREG-1 dance - Char t - Septembe

-PL-001, Ch A-PL-001, Qu

).

e radiologica n an area is b s of this asse ministrative up personne ation may b nd 2 areas w itional chara everal, oppo of survey (c developed us ent to ensur r sensitivity ensure operab d measurem mine spatial v uch as remed ry Guide 1.1 ar Power Rea 1575, Revisi (MARSSIM 1757, Volum racterization er 2006.

haracterizatio uality Assur al condition believed to b essment indi control of l for prepara be required.

within the LS acterization ortunities to c characterizat ing the DQO re that sever relative to th

bility, ent techniqu variability an diation and th 79, Standard actors, Revis ion 1, Multi-M), August 20 me 2, Revisio

, Survey, an on Survey P rance Project s in the stru be ready for icate that the the area wi ation, design This assess SE.

and remedi collect addit tion, remedia O process. T ral objective he applicabl ues are consi nd variability he collection d Format and sion 1 - June

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1 se Boiling W Termination n 0 EnergySoluti Water Reacto Dairyland Po AFSTOR -

U.S. Nuclear Radiation Sur December 20 andia Nation Contaminatio EnergySoluti 0 Detector S U.S. Nuclear Laboratory A U.S. Nuclear Radiological Termination)

EnergySoluti urvey Repor EnergySoluti urvey Repor ZionSolution allout in Soi EnergySoluti Concern Duri Haley & Aldr 0, 2012.

Haley & Aldr Reactor, Dair 015.

Dairyland Po Decommissio nternational Emitters (max 998.

Water Reactor Plan ons Technic or Historical wer Corpora December 2 Regulatory rvey and As 006.

nal Laborato on From Dec ons Technic Sensitivity.

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- Effluent S ons GG-EO-rt for Octobe ons LC-RS-rt for June th s Technical ils at Zion St ons Technic ing LACBW rich, Hydrog rich Inc., Hy ryland Powe wer Coopera oning Activit Standard IS ximum beta r

cal Support D Site Assessm ation LAC-T 2009.

Commission sessment of ory, NUREG commissioni cal Support D Commission otocols Man Commission Programs (I Streams and

-313196-RS er and Novem PN-164017-hru August 2 Support Doc tation.

cal Support D WR Decomm geological C ydrogeologic r Cooperativ ative, LACB ties Report (

O 7503-1, P energy grea 2-38 Document R ment (HSA)

TR-138, Initi n NUREG-1 Materials an G/CR-5512, V ing Paramete Document R n, NUREG-1 nual (MARL n Regulatory Inception Th the Environ S-RP-001, LA mber 2014 F

-001, LACB 2015 Field W cument 13-0 Document R missioning.

onceptual Si cal Investiga ve, Genoa W BWR Decom (D-Plan/PSD Part 1, Evalua ater than 0.15 RS-TD-31319

).

ial Site Char 1575, Supple nd Equipmen Volume 3, R er Analysis -

RS-TD-31319 1576, Multi-LAP) - Augu y Guide 4.15 hrough Norm nment - July ACBWR Ra Field Work -

BWR Radiolo Work - Nove 004, Examin RS-TD-31319 ite Model, F ation Report, Wisconsin, Fi mmissioning DAR), Revis ation of Surf 5 MeV) and 96-003, La C racterization ement 1, Mu nt Manual (M Residual Rad

- October 19 96-006, Lud

-Agency Rad ust 2001.

5, Quality A mal Operatio 2007.

adiological C

- November ogical Chara ember 2015.

nation of Cs-96-001, Rad File No. 3870

, La Crosse B ile No. 3870 Plan and Po sion - March face Contam Alpha-Emit Crosse Boilin n Survey for ulti-Agency MARSAME dioactive 999.

dlum Model 4 diological ssurance or ns to Licens Characterizat r 2015.

acterization 137 Global dionuclides o 05-001 - Au Boiling Wat 05-008, Janu ost Shutdown h 2014.

mination, Bet tters - Augu ng E) -

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La Cross License T Revision Survey Unit ID #

L101010 L101010 L101010 L101010 L201110 L201110 L301210 L301210 L301210 L401210 L401210 L401210 L401210 L401210 se Boiling W Termination n 0 Survey 01 Reactor Stack G 02 Turbine Diesel G 03 LSA Bu 04 North L 01 LACBW Crib Ho 02 G-3 Cri Dischar 01 North E 02 Transm 09 Plant A 03 G-3 Co 05 Coal Pi 06 Capped 07 Ground 08 Hwy 35 Water Reactor Plan Table 2-1 y Unit Descr LA r Building, W Grounds e Building, T Generator Bu uilding, Mai LSE Grounds WR Adminis ouse, Wareh ib House, LA rge Line, Are End of Licen mission Switc Access, ISFSI al Plant Gro le Grounds d Ash Impou ds East of Hi 5/Railroad R r

LACBW ription ACBWR Sit WTB, WGTV Turbine Offi uilding Grou ntenance Ea s

LSE Buff stration Buil ouse Ground ACBWR Cir ea South of L Clas nsed Site chyard Area I Haul Road Non-Im ounds undment Gro ghway 35 Right of Way 2-39 WR Open L te Enclosure V, Ventilatio ce Building, unds at Shack Gro fer Zone Gro lding, LACB ds rc. Water LSE Fence ss 3 Grounds d Grounds mpacted Grou ounds y Grounds Land Survey Cl e Grounds on

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La Cross License T Revision G-3 R G-3 S G-3 C G-3 T G-3 E G-3 C G-3 C G-4 W G-3 L G-3 L G-3 C G-3 C G-3 V G-3 T G-3 B G-3 F G-3 F G-3 W G-3 S G-3 S

  1. 6 W se Boiling W Termination n 0 Table Reclaim Buil Stock Out Tr Coal Unload Transfer Tow Electrical Ro Crusher Tow Conveyor #6 Warehouse a LRAPB Buil Lime Silo El CAT Buildin Coal Plant Vehicle Stora Train Shed Bottom Ash Fly Ash Silo Fly Ash Elec Waste Silo Surge Tank Settling Tank Well House Water Reactor Plan e 2-2 (contin lding ransfer Build ing Tower wer A oom wer 6 (2) and Electrica lding ectrical Buil ng age Building Dewatering ctrical Buildi k

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La Cross License T Revision Analysis /

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La Cross License T Revision se Boiling W Termination n 0 Ta Location Area West o Area South Area North Area at G-3 Area Outsid Area at G-3 33 miles So Pedretti Far Radio Towe Junction of East of Stod Water Reactor Plan able 2-5 of #2 Wareh of Parking L of LACBW Gas Silo de G-3 Offic Outfall uth at Bad A m Substation er Northeast Hwy O and ddard at Hwy r

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n-Drainage 0.

0.

2-45 for Cs-137 sured Rang (pCi/g) eas Surface 00 to 2.80 00 to 1.67 Areas Surfa 23 to 0.66 27 to 0.34 Based on B ge R e 0-10 cm ace 0-10 cm

Background

Range for 95 (p

0.45 0.35 m

0.15 0.23 d Studies 5% Distribu pCi/g) 5 to 3.63 5 to 2.86 5 to 0.77 to 0.42 ution

La Cross License T Revision se Boiling W Termination n 0 Table 2

  • L Water Reactor Plan

-7 Initia Radio H

C Fe N

Co N

Sr Nb Tc Cs Eu Eu Eu Np Pu Pu Pu Pu Am Cm-24 Listed half life i r

al Suite of L onuclide H-3 C-14 e-55 i-59 o-60 i-63 r-90 b-94 c-99

-137 u-152 u-154 u-155 p-237 u-238 u-239 u-240 u-241 m-241 43/244*

is the shortest h 2-46 LACBWR S Ha half life for the Site-Specific alf Life (Yea 1.24E+01 5.73E+03 2.70E+00 7.50E+04 5.27E+00 9.60E+01 2.91E+01 2.03E+04 2.13E+05 3.00E+01 1.33E+01 8.80E+00 4.76E+00 2.14E+06 8.78E+01 2.41E+04 6.60E+03 1.44E+01 4.32E+02 1.81E+01 e radionuclides c Radionucl ars) s in the pair lides

L L

R S

S M

M M

M S

S M

M M

M S

A M

M M

M S

M M

La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Subsurface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Asphalt

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Surface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) ng Water React ation Plan Table 2-8 Survey Unit 66,869 m2 G-3 Coal Plan Co-60 3

0 0.070 0.075 0.078 0.057 0.011 Co-60 4

0 0.060 0.056 0.084 0.047 0.016 Co-60 None Taken 1%

5,550 6,700 or Non-Impact t L4012103 nt Grounds Cs-137 3

1 0.082 0.083 0.092 0.071 0.011 Cs-137 4

1 0.048 0.038 0.081 0.036 0.022 Cs-137 ed Open Land Survey Unit 82,894 m2 Coal Pile Grou Co-60 3

0 0.071 0.072 0.084 0.057 0.014 Co-60 3

0 0.061 0.063 0.068 0.052 0.008 Co-60 None Taken 1%

5,050 8,800 2-47 Survey Units -

L4012105 1

nds C

G Cs-137 3

1 0.061 0.060 0.068 0.055 0.006 Cs-137 3

1 0.042 0.040 0.056 0.030 0.013 Cs-137 1

8 1

- Characterizat Survey Unit L 111,899 m2 Capped Ash Im Grounds Co-60 3

0 0.082 0.084 0.090 0.072 0.009 Co-60 4

0 0.081 0.083 0.102 0.056 0.021 Co-60 2

0 0.073 0.073 0.082 0.065 0.012 1%

8,340 12,000 tion Survey Su L4012106 8

mpoundment G H

Cs-137 3

2 0.100 0.099 0.121 0.079 0.021 Cs-137 4

2 0.088 0.084 0.130 0.054 0.037 Cs-137 2

0 0.062 0.062 0.084 0.040 0.031 ummary Survey Unit L 81,254m2 Grounds East of Highway 35 Co-60 3

0 0.080 0.079 0.089 0.072 0.009 Co-60 3

0 0.081 0.069 0.106 0.068 0.022 Co-60 None Tak 1%

8,000 9,080 L4012107 f

Cs-137 3

3 0.264 0.263 0.463 0.065 0.199 Cs-137 3

2 0.068 0.057 0.091 0.056 0.020 Cs-137 ken

L L

R La Crosse Boilin License Termin Revision 0 Tabl ng Water React ation Plan le 2-8 (continue S

S M

M M

M SD S

M M

M M

SD A

M M

M M

SD S

M M

or ed)

Non-I urvey Unit Surface Area Description urface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D ubsurface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D Asphalt of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D urface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm)

Impacted Open Survey Unit 9,444 m2 Hwy 35/Railro Way Grounds Co-60 3

0 0.079 0.075 0.095 0.068 0.014 Co-60 3

0 0.086 0.092 0.107 0.060 0.024 Co-60 None Taken 1%

8,124 9,200 2-48 n Land Survey L4012108 1

ad Right of B A

Cs-137 3

2 0.119 0.108 0.156 0.093 0.033 Cs-137 3

2 0.189 0.091 0.409 0.067 0.191 Cs-137 Units - Chara Survey Unit L 100 m2 Background Soi Area (inside L40 Co-60 17 0

0.087 0.086 0.101 0.077 0.007 Co-60 None Ta Co-60 None Ta No Scanning P acterization Sur L4012109 ils Test 012108)

Cs-137 17 17 0.160 0.161 0.268 0.059 0.059 Cs-137 aken Cs-137 aken Performed rvey Summaryy

L L

R R

L L

L L

L L

L L

L L

L L

a b

La Crosse Boilin License Termin Revision 0 Radionuclide L3012103-QJ-GS-001-S L3012103-QJ-GS-001-S L3012105-Genoa Coal P L3012105-CR-GS-002-L3012105-QJ-GS-001-S L3012105-QJ-GS-001-S L3012106-QJ-GS-001-S L3012106-QJ-GS-001-S L3012107-QJ-GS-001-S L3012107-QJ-GS-001-S L3012108-QJ-GS-001-S L3012108-QJ-GS-001-S a

Bold values b

Survey units ng Water React ation Plan H-3 C

SB 4.390 1

SS 3.570 0.

Pile

-SS 0.533 0.

SB SS SB 14.600 0.

SS 0.813 0.

SB SS 1.420 0.

SB 2.350 0.

SS 6.490 0.

indicate concentration g originally classified as tor Table 2-9 C-14 Fe-55 N

.230 3.430 1

.671 2.790 1

.675 2.130 1

.713 2.300 2

.713 3.550 2

.719 3.610 2

.705 1.920 3

.728 2.260 3

greater than MDC. Itali Class 3 at time of samp Non Impa Ni-59 Co-60 N

.470 0.026 2

.870 0.027 3

0.018

.730 0.025 2

0.026 0.030

.370 0.037 3

.560 0.037 3

0.019

.800 0.025 3

.110 0.018 4

.200 0.030 4

icized values indicate M ple acted Coal Pile Ni-63 Sr-90 N

.140 0.321 0

.380 0.391 0

0

.950 0.289 0

0 0

.950 0.348 0

.580 0.338 0

0

.940 0.293 0

.440 0.278 0

.710 0.271 0

MDC value 2-49 and Soil Samp Nb-94 Tc-99 Cs 0.018 0.820 0

0.022 0.628 0

0.022 0

0.016 0.587 0

0.020 0

0.020 0

0.030 0.611 0

0.028 0.616 0

0.013 0

0.019 0.593 0

0.016 0.604 0

0.020 0.576 0

ples - Test Ame s-137 Pm-147 Eu 0.024 0.714 0

0.018 0.847 0

0.019 0

0.018 0.698 0

0.023 0

0.028 0

.319 1.500 0

.096 0.826 0

0.021 0

.018 1.450 0

.033 1.310 0

.182 0.770 0

erica Laborator u-152 Eu-154 Eu 0.071 0.190 0

0.060 0.167 0

0.052 0.152 0

0.051 0.137 0

0.049 0.166 0

0.072 0.199 0

0.115 0.223 0

0.079 0.232 0

0.045 0.115 0

0.049 0.156 0

0.041 0.128 0

0.059 0.176 0

ry Analysis (pC u-155 Np-237 Pu 0.095 0.025 0

0.096 0.024 0

0.048 0.056 0.023 0

0.055 0.074 0.080 0.035 0

0.112 0.027 0

0.038 0.048 0.040 0

0.044 0.030 0

0.060 0.020 0

Ci/g) u-238 Pu-239/240 Pu 0.046 0.015 1

0.040 0.021 1

0.036 0.029 1

0.036 0.014 2

0.044 0.026 2

0.021 0.024 2

0.026 0.021 2

0.028 0.029 2

u-241 Am-241 A

1.730 0.032 0

1.650 0.025 0

0.041 1.670 0.018 0

0.048 0.061 2.550 0.019 0

2.740 0.025 0

0.034 2.580 0.020 0

2.670 0.017 0

2.740 0.015 0

Am-243 Cm-243/244 0.022 0.010 0.024 0.019 0.025 0.006 0.034 0.006 0.013 0.019 0.035 0.006 0.036 0.017 0.024 0.015

L L

R S

S M

M M

M S

S M

M M

M S

A M

M M

M S

S M

M a

La Crosse Boilin License Termin Revision 0 Survey Unit Surface Area Description Surface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Subsurface Soil

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Asphalt

  1. of Samples
  1. >CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

SD Surface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) a MDC va ng Water React ation Plan Table 2-10 Survey Unit 1,992 m2 Reactor Buil WGTV, Vent Grounds Co-60 12 2

0.080 0.058 0.287 0.048 0.066 Co-60 18 0

0.078 0.052 0.516 0.047 0.109 None Taken No Scanning P alue used for ana or Impacted Cla t L1010101 lding, WTB, tilation Stack Cs-137 12 12 0.215 0.100 1.070 0.032 0.296 Cs-137 18 8

0.066 0.054 0.161 0.033 0.035 Performed alytical results l ass 1 Open Land Survey Unit 2,315 m2 Turbine, Office Generator Buil Grounds Co-60 2

0 0.049 0.049 0.054 0.044 0.007 Co-60 22 0

0.058 0.058 0.080 0.043 0.010 None Taken No Scanning P less than MDC.

2-50 d Survey Units L1010102 1

e, Diesel ding L

M G

Cs-137 2

0 0.050 0.050 0.051 0.050 0.001 Cs-137 22 4

0.064 0.065 0.130 0.044 0.017 N

erformed N

s - Characteriz Survey Unit L 1,749 m2 LSA Building, Maintenance Ea Grounds Co-60 7

0 0.059 0.050 0.099 0.048 0.019 Co-60 25 0

0.046 0.046 0.055 0.025 0.005 None Taken No Scanning Pe zation Survey S L1010103 2

at Shack N

Cs-137 7

1 0.069 0.054 0.161 0.048 0.041 Cs-137 25 0

0.049 0.049 0.054 0.042 0.003 erformed Summary Survey Unit L 2,387 m2 North LSE Grou Co-60 1

0 0.045 0.045 0.045 0.045 N/A Co-60 14 0

0.048 0.048 0.050 0.043 0.002 Co-60 10 0

0.053 0.054 0.062 0.042 0.006 No Scanning Pe L1010104 unds Cs-137 1

0 0.049 0.049 0.049 0.049 N/A Cs-137 14 3

0.041 0.042 0.051 0.027 0.009 Cs-137 10 1

0.051 0.053 0.057 0.037 0.006 erformed

L L

R R

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

L L

a La Crosse Boilin License Termin Revision 0 Radionuclide L1010101-CJ-GS-002-S L1010101-CJ-GS-009-S L1010101-CJ-GS-010-S L1010101-QJ-GS-001-S L1010101-QJ-GS-001-S L1010101-QJ-GS-002-S L1010101-QJ-GS-002-S L1010102-CJ-FC-001-C L1010102-CJ-GS-013-S L1010102-QJ-GS-001-S L1010102-QJ-GS-001-S L1010102-QJ-GS-002-S L1010103-CJ-GS-002-S L1010103-QJ-SL-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-001-S L1010103-QJ-GS-002-S L1010103-QJ-GS-002-S L1010103-QJ-GS-003-S L1010103-QJ-GS-003-S L1010104-CJ-GS-003-S L1010104-CR-PA-007-L1010104-QQ-PA-001-L1010104-QR-GS-001-a Bold values ng Water React ation Plan T

H-3 C

SS SS SS SB 0.364 0

SS 0.441 0.

SB 0.377 0.

SS 1.380 0.

CV 1.710 0.

SB SB 8.740 0.

SS SB 24.700 0.

SB SM 0.354 0

SB 3.260 0.

SS SB 0.649 0.

SS SB 0.654 0.

SS SB

-AV

-AV

-SB indicate concentration g tor Table 2-11 C

C-14 Fe-55 N

.896 2.430 1

.676 2.190 1

.679 2.150 1

.677 4.190 2

.727 1.650 2

.726 2.120 2

.715 2.230 2

.453 0.689 0

.715 1.830 2

.702 2.100 2

.717 2.340 2

greater than MDC. Itali lass 1 Concrete Ni-59 Co-60 N

0.024 0.040 0.286

.850 0.024 3

.900 0.018 3

.750 0.017 2

.010 0.015 3

.630 0.106 3

0.030

.620 0.015 4

0.022

.760 0.021 3

0.011 0.711 0.136 1

.850 0.017 4

0.025

.620 0.014 3

0.019

.630 0.012 3

0.023 0.015 0.021 0.025 0.017 icized values indicate M e, Asphalt, Sed Ni-63 Sr-90 N

0 0

0

.040 0.335 0

.040 0.440 0

.930 0.338 0

.320 0.357 0

.920 0.292 0

0

.000 0.310 0

0

.920 0.316 0

0

.090 0.132 0

.240 0.333 0

0

.710 0.325 0

0

.660 0.300 0

0 0

0 0

0 MDC value.

2-51 diment and Soil Nb-94 Tc-99 Cs 0.020 0

0.020 0

0.025 0

0.015 0.579 0

0.012 0.587 0

0.011 0.620 0

0.010 0.521 0

0.022 0.536 0

0.016 0

0.011 0.539 0

0.015 0

0.014 0.537 0

0.017 0

0.018 0.432 0

0.011 0.606 0

0.015 0

0.012 0.645 0

0.017 0

0.009 0.557 0

0.019 0

0.008 0

0.014 0

0.025 0

0.011 0

l Samples - Tes s-137 Pm-147 Eu

.233 0

.185 0

.413 0

0.020 0.800 0

.147 3.170 0

.149 0.772 0

.059 0.978 0

.352 1.290 0

0.021 0

0.012 0.961 0

0.018 0

0.016 0.722 0

0.021 0

.136 0.360 0

0.015 0.740 0

0.020 0

0.012 0.838 0

0.017 0

0.011 0.713 0

.091 0

0.013 0

0.016 0

0.028 0

0.012 0

st America Lab u-152 Eu-154 Eu 0.056 0.161 0

0.056 0.181 0

0.062 0.247 0

0.050 0.143 0

0.034 0.112 0

0.040 0.109 0

0.033 0.096 0

0.061 0.239 0

0.044 0.170 0

0.030 0.101 0

0.036 0.113 0

0.043 0.139 0

0.044 0.181 0

0.054 0.199 0

0.036 0.117 0

0.046 0.174 0

0.029 0.103 0

0.040 0.139 0

0.029 0.092 0

0.057 0.186 0

0.032 0.078 0

0.042 0.141 0

0.058 0.218 0

0.038 0.132 0

boratory Analy u-155 Np-237 Pu 0.066 0.050 0.057 0.044 0.019 0

0.044 0.006 0

0.040 0.019 0

0.036 0.016 0

0.062 0.029 0

0.041 0.028 0.028 0

0.042 0.042 0.032 0

0.046 0.049 0.018 0

0.039 0.026 0

0.047 0.034 0.020 0

0.045 0.034 0.040 0

0.063 0.036 0.044 0.061 0.032 ysis (pCi/g) u-238 Pu-239/240 Pu 0.046 0.023 1

0.039 0.023 1

0.041 0.022 1

0.040 0.016 2

0.041 0.028 2

0.040 0.026 2

0.042 0.029 2

0.015 0.015 0

0.029 0.017 1

0.034 0.024 2

0.028 0.028 2

u-241 Am-241 A

0.058 0.042 0.051 1.970 0.015 0

1.830 0.016 0

1.950 0.017 0

2.090 0.020 0

2.490 0.018 0

0.036 2.780 0.015 0

0.039 2.660 0.015 0

0.044 0.867 0.008 0

1.430 0.009 0

0.043 2.570 0.018 0

0.024 2.470 0.018 0

0.052 0.034 0.040 0.050 0.032 Am-243 Cm-243/244 0.023 0.021 0.021 0.019 0.029 0.014 0.017 0.022 0.019 0.021 0.020 0.021 0.021 0.018 0.019 0.008 0.024 0.005 0.024 0.014 0.022 0.005

La Cross License T Revision Tabl Sur Sur

  1. of
  1. >C Mea Med Max Min SD Sub
  1. of
  1. >C Mea Med Max Min SD Asp
  1. of
  1. >C Mea Med Max Min SD Sur

% S Mea Max se Boiling W Termination n 0 le 2-12 Im rvey Unit Surface Area Description rface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) bsurface Soil f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) phalt f Samples CL an (pCi/g) dian (pCi/g) x (pCi/g) n (pCi/g) rface Scans Scanned an Scan (cpm) x Scan (cpm)

Water Reactor Plan mpacted Cla Sur 7,211 m2 LACBWR

Building, House, W Co-60 13 0

0.073 0.077 0.106 0.053 0.016 Co-60 16 1

0.052 0.046 0.112 0.040 0.018 Co-60 6

0 0.051 0.051 0.054 0.047 0.002 50%

7,500 to 8,0 11,500 to 12 r

ass 2 Open L S

rvey Unit L201 R

Adm LACBW Warehouse Gr 0

3 7

6 3

6 0

2 6

2 0

8 0

4 7

2 00 2,000 2-52 Land Surve Summary 11101 ministration WR Crib rounds Cs-137 13 8

0.090 0.100 0.139 0.041 0.030 Cs-137 16 2

0.049 0.048 0.088 0.034 0.012 Cs-137 6

0 0.051 0.051 0.054 0.047 0.003 ey Units - C Sur 6,785 m2 G-3 Crib Circ. Wa Area Sout Co-60 10 0

0.064 0.064 0.081 0.052 0.009 Co-60 7

0 0.049 0.048 0.055 0.042 0.004 Co-60 6

0 0.056 0.057 0.059 0.049 0.003 1

Characteriza rvey Unit L201 b House, ater Discha th of LSE Fe 0

4 4

2 9

0 9

8 5

2 4

0 6

7 9

9 3

50%

7,500 to 8,000 11,500 to 12,00 ation Surve 11102 LACBWR arge Line, ence Cs-137 10 6

0.065 0.054 0.200 0.030 0.049 Cs-137 7

2 0.038 0.033 0.052 0.029 0.009 Cs-137 6

3 0.048 0.051 0.055 0.009 0.008 0

00 ey

L L

R R

L L

L L

L L

L L

L L

L L

L a

La Crosse Boilin License Termin Revision 0 Radionuclide L2011101-CJ-GS-001-S L2011101-CR-PA-003-L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QJ-GS-001-S L2011101-QQ-GS-001-L2011101-QQ-GS-001-L2011101-QQ-GS-002-L2011101-QQ-PA-001-L2011102-QQ-GS-001-L2011102-QQ-GS-001-L2011102-QQ-GS-002-L2011102-QQ-PA-001-a Bold val ng Water React ation Plan H-3 C

SM

-AV SB 0.518 0.

SM 2.040 0.

SS

-SB

-SS 11.810 0.

-SB 2.500 0.

-AV

-SB 1.370 1

-SS 0.533 0.

-SB 0.525 0.

-AV lues indicate con tor Table 2 C-14 Fe-55 N

.727 2.290 2

.707 2.240 2

.726 2.590 2

.731 1.940 2

.560 2.260 3

.713 2.330 2

.702 3.890 2

ncentration grea 2-13 Class 2 Ni-59 Co-60 N

0.096 0.023

.660 0.016 4

.950 0.049 4

0.012 0.017

.600 0.035 3

.680 0.017 3

0.022

.040 0.007 4

.820 0.019 4

.880 0.031 3

0.027 ater than MDC.

Asphalt, Sedim Ni-63 Sr-90 N

0 0

.030 0.273 0

.140 0.523 0

0 0

.720 0.255 0

.870 0.314 0

0

.390 0.291 0

.300 0.361 0

.950 0.327 0

0 Italicized value 2-53 ment and Soil S Nb-94 Tc-99 Cs 0.011 0

0.016 0

0.014 0.643 0

0.018 0.585 0

0.020 0

0.012 0

0.035 0.532 0

0.014 0.616 0

0.015 0

0.018 0.537 0

0.014 0.595 0

0.016 0.568 0

0.017 0

es indicate MDC Samples - Test s-137 Pm-147 Eu

.137 0

0.017 0

0.015 0.705 0

.107 0.615 0

.080 0

0.013 0

.103 0.779 0

0.016 0.697 0

0.015 0

0.021 0.672 0

0.014 0.772 0

0.018 0.717 0

0.018 0

C value.

America Labo u-152 Eu-154 Eu 0.041 0.098 0

0.039 0.131 0

0.033 0.108 0

0.048 0.178 0

0.060 0.188 0

0.040 0.127 0

0.097 0.205 0

0.037 0.119 0

0.046 0.135 0

0.044 0.173 0

0.039 0.111 0

0.052 0.183 0

0.051 0.142 0

oratory Analysi u-155 Np-237 Pu 0.033 0.039 0.040 0.022 0

0.049 0.026 0

0.091 0.037 0.102 0.023 0

0.041 0.019 0

0.042 0.055 0.031 0

0.045 0.017 0

0.051 0.022 0

0.038 is u-238 Pu-239/240 Pu 0.028 0.025 2

0.045 0.021 3

0.037 0.024 2

0.039 0.016 2

0.026 0.018 2

0.036 0.026 2

0.028 0.020 1

u-241 Am-241 A

0.031 0.038 2.470 0.015 0

3.100 0.037 0

0.042 0.031 2.800 0.019 0

2.920 0.020 0

0.040 2.680 0.029 0

2.880 0.026 0

1.710 0.010 0

0.036 Am-243 Cm-243/244 0.022 0.019 0.036 0.034 0.015 0.015 0.028 0.016 0.028 0.024 0.034 0.021 0.028 0.006

L L

R La Crosse Boilin License Termin Revision 0 S

S M

M M

M S

S M

M M

M S

C M

M M

M S

S M

M ng Water React ation Plan Table 2-14 urvey Unit Surface Area Description urface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D ubsurface Soil of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D Concrete/Asphalt of Samples

>CL Mean (pCi/g)

Median (pCi/g)

Max (pCi/g)

Min (pCi/g)

D urface Scans

% Scanned Mean Scan (cpm)

Max Scan (cpm) or Impacted Cla Survey Unit 24,042 m2 North End of Lic Co-60 3

0 0.070 0.076 0.077 0.058 0.011 Co-60 3

0 0.051 0.053 0.054 0.046 0.004 Co-60 3

0 0.031 0.031 0.035 0.028 0.003 1%

9,000 10,000 ass 3 Open Land t L3012101 censed Site Cs-137 3

0 0.073 0.072 0.083 0.065 0.009 Cs-137 3

0 0.051 0.052 0.052 0.051 0.001 Cs-137 3

0 0.029 0.027 0.033 0.026 0.004 2-54 d Survey Units Survey Unit 11,711 m2 Transmission Swi Co-60 None T Co-60 None T Co-60 None Taken No Scanning s - Characteriz L3012102 3

tchyard Area P

G Cs-137 Taken Cs-137 Taken Cs-137 Performed zation Survey S Survey Unit L 31,012 m2 Plant Access, ISF Grounds Co-60 5

0 0.063 0.064 0.078 0.053 0.010 Co-60 4

0 0.072 0.072 0.100 0.046 0.023 Co-60 7

0 0.062 0.055 0.080 0.047 0.013 1%

5,890 6,400 Summary L3012109 SI Haul Road Cs-137 5

5 0.152 0.143 0.267 0.075 0.078 Cs-137 4

0 0.066 0.059 0.101 0.045 0.025 Cs-137 7

0 0.059 0.052 0.079 0.028 0.019 0

0

L L

R R

L L

L L

L L

L L

L L

L a

La Crosse Boilin License Termin Revision 0 Radionuclide L3012101-CR-GC-001-L3012101-CR-GC-002-L3012101-CR-GC-003-L3012101-CR-GS-003-L3012101-QQ-GS-001-L3012101-QQ-GS-001-L3012101-QQ-SL-001-L3012104-CR-GS-002-L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S L3012104-QJ-GS-001-S a

Bold values ng Water React ation Plan H-3 C

-CV

-CV

-CV 0.

-SS

-SB 18.400 0.

-SS 15.500 0.

-SM 0.364 0.

-SM SB 2.160 0.

SM 2.890 0.

SS 2.190 0.

indicate concentration g tor Table 2-15 C-14 Fe-55 N

.669 2.180 2

.717 2.390 2

.708 2.330 2

.342 2.710 0

.670 1.950 1

.672 2.720 1

.676 4.240 1

greater than MDC. Itali 5

Class 3 Asp Ni-59 Co-60 N

0.028 0.035

.020 0.031 3

0.025

.870 0.016 5

.660 0.020 3

0.739 0.022 1

0.015

.750 0.021 3

.990 0.037 3

.880 0.029 3

icized values indicate M phalt, Sediment Ni-63 Sr-90 N

0 0

.590 0.374 0

0

.640 0.309 0

.890 0.295 0

.090 0.152 0

0

.060 0.325 0

.500 0.298 0

.300 0.329 0

MDC value 2-55 t and Soil Samp Nb-94 Tc-99 Cs 0.030 0

0.026 0

0.027 0.521 0

0.017 0

0.014 0.550 0

0.017 0.603 0

0.017 0.360 0

0.013 0

0.018 0.469 0

0.020 0.651 0

0.020 0.631 0

ples - Test Am s-137 Pm-147 Eu 0.026 0

0.033 0

0.027 1.480 0

.113 0

0.015 0.899 0

.059 1.090 0

0.020 0.333 0

.066 0

0.025 0.818 0

.094 0.818 0

.138 0.667 0

merica Laborato u-152 Eu-154 Eu 0.043 0.221 0

0.062 0.271 0

0.056 0.249 0

0.052 0.157 0

0.036 0.128 0

0.047 0.116 0

0.042 0.153 0

0.035 0.128 0

0.053 0.160 0

0.074 0.217 0

0.068 0.181 0

ory Analysis (p u-155 Np-237 Pu 0.059 0.056 0.069 0.025 0

0.059 0.036 0.039 0

0.054 0.028 0

0.034 0.009 0

0.047 0.054 0.022 0

0.071 0.006 0

0.080 0.020 0

pCi/g) u-238 Pu-239/240 Pu 0.046 0.018 1

0.035 0.022 2

0.028 0.022 2

0.016 0.013 0

0.027 0.021 1

0.031 0.017 1

0.043 0.026 1

u-241 Am-241 A

0.053 0.055 1.690 0.019 0

0.052 2.590 0.023 0

2.640 0.019 0

0.797 0.009 0

0.036 1.610 0.016 0

1.560 0.016 0

1.580 0.019 0

Am-243 Cm-243/244 0.021 0.006 0.029 0.027 0.021 0.006 0.009 0.011 0.018 0.016 0.016 0.015 0.019 0.021

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 T

B1001101-C Result (pCi/g) 3.950

-0.162 9.130 0.000 11.500 39.300 6.910

-0.120 0.024 7500 2.580 0.266 0.369 0.009 0.176 0.132 0.902 0.407 0.028 0.0579 B1001101-C Result (pCi/g) 7.240

-0.492 9.450 0.000 57.700 202.000 34.500 0.191

-0.189 614.000 0.768 0.335

-0.429 0.000 0.528 0.491 7.470 1.450 0.052 0.0879 Water Reactor Plan Table 2-16 CJ-FC-001-CV 0 MDC (pCi/g)

(p 1.590 1

1.400 0

16.000 7

0.254 0

0.377 1

0.402 4

0.043 0

0.312 0

0.566 0

7.090 78 9.020 5

2.410 0

4.440 1

0.042 0

0.056 0

0.048 0

2.700 1

0.048 0

0.046 0

0.0302 0.

CJ-FC-003-CV 0 MDC (pCi/g)

(p 1.360 1

1.460 0

9.040 4

0.365 0

0.333 5

0.593 21 0.040 3

0.392 0

0.586 0

0.732 64 2.870 1

5.460 0

1.510 0

0.041 0

0.058 0

0.030 0

2.640 2

0.047 0

0.027 0

0.0408 0.

r Concrete 0-1/2 B

R pCi/g)

(p

.350 9

.793

-0

.880 10

.325 0

.250 0

.110 3

.680 0

.189 0

.330 0

1.000 9

.230

-0

.398 0

.140 0

.021

-0

.065

-0

.055

-0

.660

-1

.107 0

.030 0

0371

-0 0-1/2 B

R pCi/g)

(p

.580 12

.806

-0

.950 6

.806 0

.880 0

1.100 2

.330 0

.203

-0

.330

-0 4.000 2

.300 0

.536 0

.914

-0

.016

-0

.111

-0

.104

-0

.160

-1

.250 0

.033 0

0496 0.

2-56 Core Isotop B1001101-CJ-FC Result MD pCi/g)

(pCi/

9.720 1.56 0.346 1.44 0.400 21.3 0.000 0.26 0.082 0.16 3.850 0.42 0.162 0.05 0.001 0.13 0.076 0.52 9.660 0.15 0.039 0.51 0.025 1.26 0.071 0.37 0.002 0.04 0.017 0.06 0.006 0.04 1.510 2.50 0.011 0.03 0.014 0.03

.0081 0.04 B1001101-CJ-FC Result MD pCi/g)

(pCi/

2.600 1.57 0.566 1.39 6.160 14.3 0.000 0.25 0.435 0.05 2.990 0.40 0.304 0.05 0.001 0.15 0.129 0.59 2.450 0.11 0.045 0.34 0.179 1.02 0.007 0.28 0.010 0.05 0.005 0.06 0.004 0.04 1.320 2.66 0.018 0.03 0.009 0.03

.0000 0.01 pic Analysis C-001-CV 1/2-1 DC

/g)

(pCi/g) 60 1.950 40 0.806 300 10.200 64 0.151 68 0.078 25 0.474 51 0.041 39 0.078 26 0.310 52 1.100 11 0.055 60 0.171 76 0.118 45 0.017 66 0.026 49 0.018 00 1.360 37 0.020 30 0.019 478 0.0094 C-003-CV 1/2-1 DC

/g)

(pCi/g) 70 2.240 90 0.765 300 6.960 57 0.157 57 0.096 00 0.392 51 0.052 53 0.086 96 0.339 13 0.348 46 0.154 20 0.383 82 0.164 51 0.018 64 0.029 47 0.017 60 1.480 38 0.024 30 0.016 68 0.0047 s Results B1001 Result (pCi/g) 3.640

-0.270 0

11.300 0.000 0.800 4.860 11.600

-0.017

-0.104 450.00 0.173

-0.008 0.145

-0.010 0.575 0.715 13.200 0.550

-0.036 4

0.1540 B1001 Result (pCi/g) 4.490

-0.555 7.600 0.000 28.100 88.300 11.000

-0.016 0.153 213.00 0.162 0.557 0.108

-0.020 0.413 0.336

-7.720 0.614 0.052 7

-0.0547 101-CJ-FC-002 t

MDC (pCi/g) 1.620 0

1.410 0

9.950 0.289 0.117 0.492 0

0.046 7

0.165 4

0.564 0

0.597 2.150 8

1.460 0.837 0

0.042 0.617 0.466 0

23.500 0.401 6

0.433 0

0.4670 101-CJ-FC-004 t

MDC (pCi/g) 1.590 5

1.450 7.070 0.276 0

0.190 0

0.467 0

0.045 6

0.264 0.592 0

0.439 1.570 3.070 0.850 0

0.060 0.426 0.325 0

26.000 0.441 0.292 7

0.4320

-CV 0-1/2

(pCi/g) 1.330 0.794 5.540 0.183 0.172 0.581 1.130 0.095 0.322 46.900 0.924 0.820 0.503 0.009 0.436 0.413 15.100 0.419 0.140 0.2600

-CV 0-1/2

(pCi/g) 1.420 0.795 4.040 0.467 2.950 9.200 1.070 0.155 0.352 22.200 0.611 0.863 0.138 0.020 0.320 0.265 14.400 0.436 0.136 0.0776

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1001101-C Result (pCi/g) 2.960

-0.077 8.070 2.590 73.900 221.000 32.800

-0.089 0.178 65.700 0.395 0.637 0.011 0.005 0.706 0.489 9.090 1.590 0.048 0.1160 B1001101-C Result (pCi/g) 3.590

-0.246 6.030 0.000

-0.026 2.310 0.146 0.019 0.024 1.410 0.021 0.055 0.003 0.003

-0.004 0.035

-1.890 0.006

-0.002

-0.0036 Water Reactor Plan

-16 (continu CJ-FC-005-CV 0 MDC (pCi/g)

(p 1.520 1

1.410 0

9.770 5

0.267 0

0.372 7

0.427 23 0.043 3

0.531 0

0.562 0

0.569 6

1.240 0

5.650 0

0.699 0

0.015 0

0.065 0

0.035 0

2.540 2

0.045 0

0.031 0

0.0443 0.

CJ-WC-006-CV MDC (pCi/g)

(p 1.640 1

1.490 0

14.500 7

0.257 0

0.207 0

0.396 0

0.038 0

0.141 0

0.556 0

0.153 0

0.434 0

1.270 0

0.336 0

0.045 0

0.043 0

0.033 0

2.360 1

0.036 0

0.031 0

0.0287 0.

r ued)

Co 0-1/2 B

R pCi/g)

(p

.200 4

.810

-0

.230 8

.813 0

.510 0

3.000 4

.170 0

.317

-0

.336

-0

.970 0

.746 0

.831 0

.414 0

.010

-0

.134

-0

.106

-0

.270 0

.273 0

.034

-0 0590 0

1/2-1 R

pCi/g)

(p

.350 0

.836 0

.050 1

.147 0

.240 0

.335 2

.034 0

.060 0

.324

-0

.258 16

.113 0

.137 0

.196 0

.021 0

.016 0

.028

-0

.270

-1

.017 0

.005

-0 0052 0

2-57 oncrete Cor B1001101-CJ-FC Result MD pCi/g)

(pCi/

4.180 1.85 0.701 1.35 8.170 9.87 0.000 0.27 0.075 0.17 4.870 0.43 0.423 0.05 0.015 0.12 0.124 0.54 0.801 0.11 0.001 0.37 0.119 0.92 0.013 0.25 0.017 0.05 0.003 0.05 0.008 0.03 0.337 2.53 0.012 0.01 0.002 0.05

.0000 0.01 B1008101-CJ-Result MD pCi/g)

(pCi/

0.382 0.94 0.053 1.37 1.610 6.55 0.000 0.23 0.662 0.06 2.730 0.35 0.154 0.05 0.000 0.21 0.010 0.57 6.000 0.17 0.034 0.63 0.060 1.20 0.140 0.35 0.003 0.04 0.018 0.06 0.011 0.05 1.120 2.71 0.020 0.04 0.002 0.04

.0062 0.01 re Isotopic A C-005-CV 1/2-1 DC

i/g)

(pCi/g) 50 1.520 50 0.733 70 5.340 70 0.165 71 0.080 30 0.570 51 0.063 28 0.074 40 0.307 17 0.172 73 0.005 23 0.245 55 0.148 54 0.016 53 0.023 38 0.008 30 1.510 18 0.017 54 0.022 76 0.0049

-FC-002-CV DC

i/g)

(pCi/g) 40 0.559 70 0.794 50 3.370 34 0.151 65 0.131 53 0.355 53 0.041 11 0.066 79 0.335 77 1.780 33 0.056 00 0.239 57 0.215 48 0.022 60 0.033 54 0.019 10 1.480 42 0.027 44 0.017 87 0.0125 Analysis Re B1001 Result (pCi/g) 4.210 0.077 11.700 0.000 2.040 13.400 7.150 0.026 0.083 1490 0.031 0.128 0.737

-0.013 0.029 0.035

-1.380 0.048 0.003

-0.0053 B10 Result (pCi/g) 1.300

-0.296 6.460 0.000 0.974 4.400 0.235 0.016

-0.005 10.000 0.291 0.019 0.101

-0.024 0.042 0.008

-0.194 0.019

-0.001

-0.0056 esults 101-CJ-WC-006 t

MDC

)

(pCi/g) 1.700 1.440 0

9.320 0.263 0.047 0

0.420 0.034 0.154 0.580 0.721 3.660 1.190 1.470 0.044 0.037 0.025 2.650 0.052 0.029 3

0.0419 008101-CJ-FC-0 t

MDC

)

(pCi/g) 1.020 1.440 14.500 0.241 0.142 0.356 0.035 0.141 0.592 0

0.154 0.470 1.410 0.348 0.068 0.057 0.034 2.550 0.051 0.052 6

0.0444 6-CV 0-1/2

(pCi/g) 1.440 0.832 5.530 0.230 0.264 1.430 0.703 0.090 0.341 155.000 2.210 0.679 0.896 0.010 0.027 0.026 1.470 0.041 0.011 0.0075 003-CV

(pCi/g) 0.713 0.810 7.050 0.171 0.162 0.510 0.041 0.081 0.343 1.130 0.270 0.052 0.208 0.025 0.038 0.017 1.470 0.029 0.023 0.0080

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B100810 Result (pCi/g) 1.200 0.077 6.520 0.000 1.390 4.260 0.216 0.001 0.043 19.800

-0.119

-0.061 0.006 0.014 0.020 0.025

-1.610 0.052

-0.004 0.0100 B1002101-C Result (pCi/g) 0.763

-0.776 3.540 0.000 0.742 3.360 2.410 0.035 0.259 3.630 0.156 0.119 0.159 0.000 0.023 0.000

-0.052 0.020 0.013 0.0048 Water Reactor Plan

-16 (continu 01-CJ-FC-004-C MDC (pCi/g)

(p 0.990 0

1.430 0

11.500 5

0.229 0

0.095 0

0.339 0

0.040 0

0.143 0

0.599 0

0.166 2

0.580 0

1.370 0

0.376 0

0.065 0

0.052 0

0.042 0

2.610 1

0.034 0

0.032 0

0.0150 0.

CJ-FC-001-CV MDC (pCi/g)

(p 1.000 0

1.410 0

5.670 3

0.228 0

0.069 0

0.333 0

0.050 0

0.149 0

0.564 0

0.150 0

0.420 0

1.400 0

0.335 0

0.045 0

0.061 0

0.049 0

2.820 1

0.015 0

0.029 0

0.0143 0.

r ued)

Co CV B

R pCi/g)

(p

.685 0

.829 0

.820 15

.162 65

.255 95

.492 81

.041 99

.081 0

.350 0

.150 4

.344 0

.296 1

.220 0

.035

-0

.030 0

.028 1

.430 5

.035 3

.006 0

0142 0.

1-1.5 B

R pCi/g)

(p

.638 0

.763 0

.150 7

.159 0

.148 0

.407 5

.250 0

.066

-0

.342 0

.493 2

.236 0

.382 0

.204 0

.018

-0

.035 0

.021 0

.640

-2

.020 0

.018 0

0096 0.

2-58 oncrete Cor B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.820 0.98 0.505 1.41 5.400 13.8 5.500 0.31 5.000 0.42 7.000 0.47 9.800 0.04 0.098 0.47 0.113 0.56 4710 1.69 0.815 5.94

.250 5.46 0.073 2.12 0.012 0.06 0.920 0.62

.280 0.46 5.240 26.7 3.200 0.42 0.406 0.29

.2020 0.42 B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.094 0.91 0.372 1.38 7.770 25.0 0.000 0.25 0.872 0.13 5.730 0.38 0.106 0.04 0.034 0.14 0.032 0.52 2.440 0.14 0.125 0.38 0.271 0.95 0.099 0.32 0.007 0.05 0.004 0.06 0.009 0.04 2.090 2.70 0.017 0.04 0.029 0.02

.0059 0.03 re Isotopic A C-001-CV 0-1/2 DC

/g)

(pCi/g) 85 0.637 10 0.850 800 7.430 10 8.690 20 9.600 72 85.000 45 9.600 75 0.149 64 0.333 90 491.000 40 1.410 60 1.980 20 1.280 60 0.023 20 0.511 69 0.537 700 16.200 28 0.989 96 0.310 200 0.2670 C-001-CV 1.5-2 DC

/g)

(pCi/g) 17 0.512 80 0.819 000 11.400 59 0.188 38 0.161 88 0.646 41 0.032 42 0.083 28 0.308 46 0.343 83 0.195 56 0.406 26 0.196 52 0.019 61 0.030 41 0.021 00 1.460 41 0.025 29 0.026 331 0.0154 Analysis Re B1002 Result (pCi/g) 0.275

-0.018 0.547 0.000 1.010 0

5.640 0.253 0.029

-0.101 0

3.870 0.039

-0.260 0.077

-0.022 0.017

-0.005 0

-0.984 0.035

-0.018 0

-0.0046 B1002 Result (pCi/g) 1.710 15.400 0

8.960 423.00 300.00 2360 220.00

-0.350 0.792 25400 0.510 4.650 1.060 0.024 3.200 2.580 36.900 9.080 0.305 4

0.4280 esults 2101-CJ-FC-001 t

MDC (pCi/g) 0.931 8

1.440 5.510 0.245 0.149 0.367 0.053 0.102 1

0.507 0.137 0.444 0

1.480 0.272 2

0.064 0.059 5

0.042 4

2.680 0.037 8

0.054 6

0.0366 2101-CJ-FC-002 t

MDC (pCi/g) 1.180 0

1.510 5.860 0

0.446 0

0.762 0.661 0

0.052 0

0.935 0.562 0

4.140 13.700 7.170 7.370 0.042 0.497 0.287 0

24.000 0.682 0.388 0

0.5450

-CV 1/2-1

(pCi/g) 0.543 0.824 2.840 0.170 0.168 0.633 0.049 0.054 0.289 0.496 0.107 0.859 0.162 0.023 0.033 0.013 1.510 0.031 0.013 0.0066

-CV 0-1/2

(pCi/g) 0.846 2.310 3.640 55.200 30.200 245.000 21.100 0.567 0.373 2650 0.956 4.390 0.988 0.027 0.825 0.713 17.100 2.030 0.286 0.4200

La Cross License T Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Np-237 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 se Boiling W Termination n 0 Table 2-B1002101-C Result (pCi/g) 0.846 6.180 5.270 0.000 8.270 175.000 3.520

-0.041 0.165 208.000

-0.280 0.255 0.116

-0.019 0.059 0.056

-0.965 0.238 0.005 0.0018 Water Reactor Plan

-16 (continu CJ-FC-002-CV 1 MDC (pCi/g)

(p 1.120 0

1.420 1

25.300 11 0.269 0

0.114 0

0.442 18 0.047 0

0.230 0

0.522 0

0.362 21 1.580 0

1.900 0

0.864 0

0.056 0

0.064 0

0.049 0

2.970 1

0.048 0

0.060 0

0.0438 0.

r ued)

Co 1/2-1 B

R pCi/g)

(p

.716 0

.340

-0 1.400 8

.616 0

.907 8

8.300 70

.356 7

.135 0

.312 0

1.700 1

.950 0

.259 0

.205

-0

.017

-0

.046 0

.040 0

.690 1

.080 0

.028

-0 0179 0.

2-59 oncrete Cor B1002101-CJ-FC Result MD pCi/g)

(pCi/

0.836 0.96 0.405 1.44 8.430 17.0 0.000 0.33 8.570 0.14 0.600 0.54 7.000 0.05 0.038 0.21 0.062 0.54 1240 0.81 0.176 2.60 0.090 2.32 0.004 1.71 0.011 0.04 0.105 0.05 0.126 0.03

.500 2.56 0.339 0.04 0.001 0.03

.0175 0.01 re Isotopic A C-003-CV 0-1/2 DC

/g)

(pCi/g) 62 0.624 40 0.803 000 8.210 34 0.484 48 0.940 48 7.370 50 0.691 11 0.060 43 0.318 17 129.000 00 0.514 20 0.202 10 1.030 44 0.009 56 0.051 39 0.051 60 1.640 44 0.099 37 0.012 75 0.0203 Analysis Re 0

3 esults

La Cross License T Revision se Boiling W Termination n 0 Tab Water Reactor Plan ble 2-17 198 We Radion Mn-Co-Co-Nb-Cs-1 Ce-1 r

83 Groundw ell-Point So nuclide

-54

-57

-60

-95 137 141 2-60 water Analy outh of Turb A

(p ysis from Te bine Buildin Activity pCi/L) 63.4 6.4 508 21.4 21.7 18.9 emporary ng

L L

R La Crosse Boilin License Termin Revision 0 Jun H-3 Co-6 Sr-9 Cs-1 a

B Nov H-3 Co-6 Sr-9 Cs-1 a

B ng Water React ation Plan e 2013 MW-20 (pCi/L 572 60 4.00 90 2.05 137 3.97 Bold values indi vember 2013 MW-20 (pCi/L 235 60 4.64 90 1.18 137 4.64 Bold values indi or Table 2 01-A MW-201-B L)

(pCi/L) 2 506 0

5.01 5

2.00 7

3.84 icate concentrati 01-A MW-201-B L)

(pCi/L) 5 150 4

3.80 8

3.73 4

1.90 icate concentrati 2-18 2013 Gr B

MW-202-A (pCi/L) 660 4.76 1.82 4.05 ion greater than B

MW-202-A (pCi/L) 257 5.26 1.18 6.54 ion greater than 2-61 roundwater M MW-202-B MW (pCi/L)

(p 484 4.51 1.43 3.91 n MDC. Italicize MW-202-B MW (pCi/L)

(p 278 5.41 1.61 4.70 n MDC. Italicize onitoring Resu W-203-A MW-2 pCi/L)

(pCi N/A 42 4.95 4.1 2.06 2.0 4.52 4.3 ed values indica W-203-A MW-2 pCi/L)

(pCi 449 23 4.43 3.8 1.87 2.4 4.41 3.9 ed values indica ults 203-B MW-204-i/L)

(pCi/L) 20 397 12 4.36 06 2.18 31 4.11 ate MDC value.

203-B MW-204-i/L)

(pCi/L) 35 193 89 4.52 40 1.18 98 4.77 ate MDC value.

-A MW-204-B (pCi/L) 420 4.26 2.08 3.96

-A MW-204-B (pCi/L) 171 8.24 1.51 7.92

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P 2

P A

a La Crosse Boilin License Termin Revision 0 JUNE 2014 MW-DW3 Gross Alpha 1.26E-01 Gross Beta 1.48E+0 H-3 1.05E+0 C-14 2.79E+0 Fe-55

-2.00E+0 Ni-59 1.83E+0 Co-60 1.02E+0 Ni-63

-1.78E+0 Sr-90 6.09E-01 Nb-94 4.40E-01 Tc-99

-8.28E+0 Cs-137

-5.97E-0 Eu-152 9.48E+00 Eu-154

-5.24E+0 Eu-155

-2.67E+0 Pu-238 2.83E-02 Pu-239/240

-9.61E-02 Pu-241 3.51E+0 Am-241 5.39E-02 a

Bold val ng Water React ation Plan MW-DW4 M

D 1

-1.33E-01 4.44 0

3.13E+00 1.93 2

1.59E+02 1.94 0

0.00E+00

-3.9 01

-3.12E+01

-2.6 1

3.96E+01

-4.7 0

3.94E-01 2.5 00

-6.14E+00

-7.4 1

8.99E-02 8.9 1

1.43E-01

-1.2 00

-7.37E+00

-8.2 1

-3.47E-01

-7.4 0

2.34E+00

-7.4 00 3.16E+00 1.35 00 1.46E+00

-1.5 2

-4.77E-02

-2.2 2

3.36E-02 3.1 0

2.70E+00

-8.3 2

3.42E-02 4.6 lues indicate con tor MW-DW5 MW-DW7 4E+00

-3.78E-01 3E+00 0.00E+00 4E+02 1.23E+02 97E+00

-5.08E+00 66E+01

-3.86E+01 75E+01 2.60E+01 0E+00

-2.42E+00 40E+00

-4.38E+00 99E-02 1.78E-02 26E+00 7.49E-01 26E+00

-9.36E+00 45E-01

-1.83E+00 43E+00

-5.51E+00 5E+00

-4.73E+00 54E-01

-1.07E+02 22E-02 8.22E-02 13E-02 4.07E-01 39E+00 2.62E+00 65E-03

-1.01E-02 ncentration grea Tabl MW-B11R MW B11A 0.00E+00 7.33E 3.59E+00

-2.70E 2.45E+02 1.61E+

9.06E+00 6.83E+

-3.19E+01

-3.75E

-4.16E+00 2.53E+

8.76E-01

-1.94E

-3.57E+00 0.00E+

7.34E-01 6.11E

-6.99E-01 1.53E+

-5.52E+00

-8.46E 1.24E+00 1.84E+

-9.93E-01 1.48E+

1.63E+00

-2.61E 1.60E+00

-4.47E 0.00E+00 4.09E

-2.54E-02

-3.39E

-5.72E+00 8.38E 1.22E-02 8.37E ater than MDC.

le 2-19 2014 W-AR MW-B2

-01

-2.13E+00 6

E-01 1.12E+01 4

+02 1.60E+02 1

+00 1.94E+00

-2 E+01

-9.20E+00

-4

+00

-7.13E+00 3

E+00

-1.39E+00

-1

+00

-7.94E+00 1

E-01 6.52E-01 6

+00 1.77E+00 6

E+00

-7.41E+00

-8

+00 1.37E+00 2

+00 1.07E-01 1

E+00 2.36E+00 1

E+00 1.60E+00

-3 E-02 5.40E-02 8

E-02 3.40E-02 1

E-01 0.00E+00 E-02 3.98E-03 2

Italicized value 2-62 Groundwater MW-B3 MW-200-A 6.46E-01 4.04E+00 4.14E+00 8.66E+00 1.94E+02 5.23E+01 2.05E+00 9.26E+00 4.39E+01 1.93E+01 3.15E+01

-2.18E+0 1.13E+00 1.01E+00 1.50E+00

-1.97E+0 6.12E-01 9.86E-01 6.65E-01 1.08E+00 8.10E+00 3.55E+00 2.14E+00 1.77E-01 1.42E+01 9.71E+00 1.69E+00 5.77E-01 3.17E+00

-3.63E+0 8.29E-02

-1.38E-02 1.46E-01 2.68E-02

-7.39E-01 0.00E+00 2.28E-02 1.72E-01 es indicate MDC Monitoring Re MW-200-B M

20 0

-2.26E-01 3.84 0

-1.79E+00 7.26 1

1.24E+02 7.03 0

4.84E+00 4.84 1

-4.16E+01

-3.20 1

3.32E+01

-1.6 0

-1.27E+00

-6.0 0

-4.69E+00 1.82 1

9.98E-01 6.86 0

8.47E-01 3.73 0

5.08E+00 3.92 1

-3.64E-01 3.10 0

-1.16E+01 4.15 1

5.60E-01

-2.39 0

-3.44E+00

-2.92 2

1.51E-02 5.33 2

-1.57E-02

-6.8 0

4.49E+00

-4.8 1

9.71E-01 9.46 C value.

esults (pCi/L)

MW-01-A MW-201-B 4E-01

-1.04E+00 6E+00

-1.04E+00 3E+01 1.05E+02 4E+00 4.51E+00 0E+01 1.58E+01 7E+01

-7.11E+01 04E-02 1.73E+00 2E+00

-1.91E+00 6E-02 1.02E+00 3E-01 1.80E+00 2E+00 1.17E+00 0E-01

-6.21E-01 5E+00 1.12E+01 9E+00

-2.43E+00 2E+00

-2.60E+00 3E-02

-5.02E-02 86E-03 2.36E-02 85E-01

-1.42E+00 6E-02 3.99E-03 MW-202-A MW 202-1.06E+00 4.07E-4.34E+00 1.49E+

3.36E+02 1.06E+

0.00E+00 4.70E+

-3.26E+00

-4.54E+

2.49E+01

-1.05E+

-8.91E-01 1.02E+

-1.94E+00

-3.73E+

1.12E+00 6.05E-

-3.55E-01 1.04E-3.88E-01 2.73E+

-4.64E-01 2.86E+

4.11E+00 1.08E+

-1.12E+00

-1.18E+

-1.59E+00

-3.49E+

-8.46E-03 1.48E-

-2.27E-02

-4.54E 2.20E+00 2.72E+

1.16E-01 3.92E-W-

B MW-203-A

-01 1.74E+00

-2

+00 2.27E+00 5

+02 2.79E+02 2

+00 4.54E+00 4

+01

-4.95E+01

-4

+01

-2.71E+01

-4

+00 3.48E-02

-9

+00

-3.70E+00

-3

-01 1.17E+00 8

-01 1.59E+00 1

+00 4.36E+00 4

+00 1.48E+00 1

+01

-9.59E-01 4

+00 1.93E+00

-3

+00

-4.91E+00 4

-01

-5.67E-02

-5

-02

-2.27E-02

-3

+00 4.07E+00 1

-02 2.94E-02 7

MW-203-B MW-204-A 2.29E-01 7.58E-01 5.53E+00 2.69E+00 2.79E+02 1.06E+02 4.55E+00 4.66E+00 4.96E+01

-4.03E+01 4.66E+00

-6.22E+00 9.55E-01 1.91E-01 3.80E+00 0.00E+00 8.23E-01 2.01E+00

.50E+00 2.26E-01 4.17E+00 6.95E+00

.39E+00

-3.04E-01 4.99E+00 2.12E+00 3.69E+00 2.36+00 4.05E+00

-4.34E-01 5.87E-02

-5.12E-02 3.95E-02

-2.49E-02

.03E+01 4.07E+00 7.64E-02 1.56E-01 MW-204-B 1.27E+00 0

2.57E-01 2

3.49E+01 0

1.30E+01 1

-3.98E+00 0

-2.47E+01

-2.31E-01 0

-1.97E+00 0

6.11E-01 1.28E+00 0

6.31E+00 1.93E+00 0

7.68E+00 6.06E-01 1.66E+00 2

-9.28E-03 2

6.28E-02 0

-1.89E+00 8.24E-02

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A a

La Crosse Boilin License Termin Revision 0 September 2014 M

Gross Alpha 8

Gross Beta 2

H-3 3

C-14

-9 Fe-55 9

Ni-59 3

Co-60 2

Ni-63 2

Sr-90

-1 Nb-94

-9 Tc-99

-1 Cs-137 3

Eu-152 2

Eu-154

-3 Eu-155 2

Pu-238 1

Pu-239/240 9

Pu-241 3

Am-241 1

a Bold val ng Water React ation Plan 4

MW-DW5 MW-8.47E-01 3.09E

.96E+00 1.45E

.43E+01 0.00E 9.44E-01

-2.70E 9.39E+00

-3.10E

.13E+00 1.64E

.17E+00 1.32E

.79E+00 2.48E 1.06E+00 5.90E 9.45E-01

-1.39E 1.54E+00

-4.00

.97E+00

-7.24

.48E+00 3.00E 3.31E+00

-3.93E

.69E+00 1.95E 1.71E-02 3.69E 9.28E-02 0.00E

.18E+00

-3.68E 1.28E-01 3.69E lues indicate con tor

-B11R MW-B11A E+00 2.07E-0 E+01 3.04E-0 E+00 3.44E+0 E+00 0.00E+0 E+01

-3.49E+0 E+01

-8.49E+0 E+00 1.22E+0 E+00

-4.14E-0 E-01 2.80E-0 E+00

-1.29E-0 0E-01

-1.56E+0 4E-01 9.72E-0 E+00 6.42E+0 E+00 1.10E+0 E+00 1.69E+0 E-02

-5.50E-0 E+00

-1.10E-0 E+00

-2.29E+0 E-02

-1.69E-0 ncentration grea Table 2-19 AR MW-200-A 01 2.42E-01 01 2.41E+00 01 6.86E+01 00

-4.56E-01 01

-3.35E+01 00 7.84E+00 00 3.56E+00 01 3.62E+00 01 1.14E+00 01

-1.43E+00 00

-1.57E+00 01 2.17E+01 00

-2.39E+00 00

-6.57E-01 00

-8.16E-01 03 2.65E-02 02 5.83E-02 00

-2.23E+00 02 1.10E-01 ater than MDC.

(continued)

MW-200-B 2.01E+00 9.11E+00 5.17E+01

-4.98E+00

-4.56E+01 2.37E+01 6.20E-01

-7.87E-01 5.10E-01

-2.68E-01

-1.54E+00 1.94E+00

-1.34E+01

-1.54E+00

-1.64E+00

-6.50E-03 0.00E+00 8.49E+00 2.29E-01 Italicized value 2-63 2014 Ground MW-201-A M

1.18E+00 7.36E+00 8.67E+01 2.69E+00

-2.18E+01

-1.99E+01

-7.23E-02 5.00E+00

-1.19E-01 6.56E-01

-7.94E-01

-1.09E+00 4.79E+00

-3.09E+00

-1.48E+00

-3.59E-02 0.00E+00

-6.92E-01 1.40E-01 es indicate MDC dwater Monito MW-201-B MW 1.43E+00 1.0 3.67E+00 4.8

-3.42E+01

-5.1 9.28E-01 4.94 2.77E+01

-5.4 3.09E+01

-1.1 9.50E-01 9.7 2.15E+00 8.2

-4.99E-01 6.7 6.44E-01

-6.4

-1.95E+00 7.9 1.84E+00

-4.3 2.53E+00 9.4 1.94E+00

-3.6 4.13E+00

-2.0 8.55E-02 1.1 1.41E-01 5.8

-5.85E-01 0.0 2.80E-02 6.6 C value.

oring Results (p W-202-A MW-20 4E+00

-2.10E-86E-01 2.30E+

18E+01 1.04E+

4E+00

-2.72E+

43E+01 3.37E+

18E+01

-4.46E+

72E-01 1.18E+

25E-01

-8.30E-70E-01 5.40E-48E-02

-1.02E+

97E-01

-1.95E-34E-01 2.31E+

0E+00 6.51E+

67E-01 4.18E+

08E+00

-8.41E-13E-02 3.63E-87E-02 5.25E-0E+00

-1.76E+

62E-02 9.48E-pCi/L) 02-B MW-203-A E-01 1.37E+00

+00 1.52E+00

+02

-3.44E+01

+00

-3.95E+00

+01

-4.95E+01

+01 5.30E+01

+00 3.67E+00 E-01 1.62E+00

-01 4.80E-01

+00 8.53E-02 E-01

-1.24E+00

+00 1.56E+00

+00 4.06E+00

+00

-3.33E+00 E-01

-9.54E-02

-02 7.08E-02

-02 9.15E-02

+00 5.04E-01

-02 2.51E-01 A

MW-203-B

-6.68E-01 1.00E+00 1.21E+02 0

4.89E-01 4.32E+01

-4.34E+01 1.99E+00

-1.77E+00 8.70E-01 2.16E+00 0

-3.32E+00 6.84E-01

-1.15E+00 0

-2.31E-01

-3.66E-01 8.12E-02 5.97E-02

-3.71E+00 1.03E-01 MW-204-A 6.00E-01 5.28E+00 6.88E+01 4.73E-01 3.45E+01

-3.13E+01

-3.77E-01

-1.84E-01 9.00E-01 1.18E-01

-1.96E+00

-1.14E+00

-1.92E+01

-4.95E+00

-2.02E+00

-6.45E-04

-5.48E-03

-3.97E+00 1.06E-01 MW-204-B 3.53E+00 0.00E+00

-1.21E+02 9.46E-01

-9.25E+01

-1.87E+01 2.05E+00 3.94E-01 2.30E-01

-1.88E+00 3.89E-01 1.24E+00 2.23E+00 2.36E+00 9.46E-01

-3.26E-02 7.02E-02

-6.46E+00 2.69E-01

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan Figure or e 2-1 LACBWR Site Map -

2-64

- Open Land Survey Units annd Classificatioon

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-2 LACBWR 2-65 Site Map - Buildings Identifiication

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-3 r

LACBWR 2-66 R Site Drainnage and Seewer Map

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-4 r

LACBWR 2-67 R LCE Excllusion Area (Class 1)

La Cross License T Revision se Boiling W Termination n 0 Figu Water Reactor Plan ure 2-5 N

r Non Impacte 2-68 ed Open Laand Samplinng Locations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-6 r

Class 1 O 2-69 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-7 r

Class 2 O 2-70 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 F

Water Reactor Plan Figure 2-8 r

Class 3 O 2-71 Open Land SSampling LLocations

La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan Figure 2-9 r

9 Concre 2-72 ete Core Sam mpling Loccations

La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r

inued) 2-73 Concrete CCore Sampliing Locationns

La Cross License T Revision se Boiling W Termination n 0 Figur Water Reactor Plan re 2-9 (conti r

inued) 2-74 Concrete CCore Sampliing Locationns

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-10 LACBWR Si 2-75 ite - Typical Geological Crosss-Section

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 2-111 Groundwat 2-76 ter Sampling Wells - LACBW WR Site