ML16200A087: Difference between revisions

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| number = ML16200A087
| number = ML16200A087
| issue date = 06/27/2016
| issue date = 06/27/2016
| title = Boiling Water Reactor License Termination Plan - Chapter 3 - Identification of Remaining Site Dismantlement Activities, Rev. 0
| title = License Termination Plan - Chapter 3 - Identification of Remaining Site Dismantlement Activities, 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 3 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES
{{#Wiki_filter:LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 3 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES  


La Crossse Boiling Water W        Reactorr License Termination T             Plan Revisionn0 TABLE OF      O CONTE            ENTS
La Cross License T Revision 3.
: 3. Idenntification off Remaining    g Site Disman        ntlement Acctivities ................................................... 3-1 3.1. Introduction  n ........................................................................................................................ 3-1 3.2. Completed and Ongoing           g Decommisssioning Acttivities and T                      Tasks .................................. 3-3 3.2.1. Overview ..................................................................................................................... 3-3 3.2.2. Disman    ntlement of SystemsS            and d Componennts ........................................................... 3-3 3.2.2.1. Forrced Circulattion System....................
Iden 3.1.
                                                            .                   ............................................................... 3-3 3.2.2.2. Seaal Injection System S          ............................................................................................ 3-4 3.2.2.3. Deccay Heat Cooling System                m ................................................................................ 3-4 3.2.2.4. Prim  mary Purificcation System          m ................................................................................ 3-4 3.2.2.5. Alternate Core Spray Systeem ............................................................................... 3-4 3.2.2.6. Gasseous Wastee Disposal Sy                ystem ......................................................................... 3-4 3.2.2.7. Fueel Element Storage S            Well .................................................................................. 3-4 3.2.2.8. Com  mponent Cooling Water System ..................................................................... 3-5 3.2.2.9. Hyd  draulic Valv    ve Accumulaator System ................................................................ 3-5 3.2.2.10. Well W Water Sy          ystem.............................................................................................. 3-5 3.2.2.11. Deemineralized        d Water Systtem ............................................................................. 3-5 3.2.2.12. Ov  verhead Storrage Tank ....................................................................................... 3-5 3.2.2.13. Staation and Co      ontrol Air Sy      ystem ......................................................................... 3-6 3.2.2.14. Lo  ow Pressure Service Watter System ................................................................. 3-6 3.2.2.15. Hiigh Pressure Service Waater System ................................................................. 3-6 3.2.2.16. Ciirculating Water  W        System .................................................................................. 3-6 3.2.2.17. Co  ondensate Sy      ystem and Feeedwater Heeaters ...................................................... 3-6 3.2.2.18. Fu  ull-Flow Con      ndensate Dem        mineralizer System................................................... 3-6 3.2.2.19. Steeam Turbinee ..................................................................................................... 3-7 3.2.2.20. 60  0-Megawatt Generator G              ....................................................................................... 3-7 3.2.2.21. Tu  urbine Oil an    nd Hydrogen        n Seal Oil Syystem...................................................... 3-7 3.2.2.22. Heeating, Ventiilation, and Air            A Conditiooning (HVA                AC) Systems ........................ 3-7 3.2.2.23. Liquid Waste Collection Systems          S              ...................................................................... 3-8 3.2.2.24. Electrical Disttribution Sysstem ........................................................................... 3-8 3.2.3. Additio  onal Activities ................................................................................................... 3-8 3.3. Future Deco    ommissionin      ng Activitiess and Tasks ................................................................. 3-8 3.3.1. Reactorr Building ......................................................................................................... 3-9 3.3.2. Turbinee Building and      a Turbine Office    O          Buildding ...................................................... 3-11 3.3.3. Waste Treatment T              Building, B              Gass Storage Taank Vault annd LSA Storagee Building ....................................................................................................... 3-12
3.2.
: 4. LACBW 3.3.4            WR Crib Ho      ouse .............................................................................................. 3-13 3-i
3.2.
3.2.
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3.2.
3.3.
3.3.
3.3.
3.3.
3.3.4 se Boiling W Termination n 0 ntification of Introduction Completed 1.
Overvi 2.
Disman
.2.2.1. For
.2.2.2. Sea
.2.2.3. Dec
.2.2.4. Prim
.2.2.5. Alt
.2.2.6. Gas
.2.2.7. Fue
.2.2.8. Com
.2.2.9. Hyd
.2.2.10. W
.2.2.11. De
.2.2.12. Ov
.2.2.13. Sta
.2.2.14. Lo
.2.2.15. Hi
.2.2.16. Ci
.2.2.17. Co
.2.2.18. Fu
.2.2.19. Ste
.2.2.20. 60
.2.2.21. Tu
.2.2.22. He
.2.2.23. Li
.2.2.24. El 3.
Additio Future Deco 1.
Reactor 2.
Turbine 3.
Waste T Storage 4.
LACBW Water Reactor Plan f Remaining n.................
and Ongoing ew..............
ntlement of S rced Circulat al Injection S cay Heat Co mary Purific ernate Core seous Waste el Element S mponent Co draulic Valv Well Water Sy emineralized verhead Stor ation and Co ow Pressure igh Pressure irculating W ondensate Sy ull-Flow Con eam Turbine 0-Megawatt G urbine Oil an eating, Venti quid Waste ectrical Dist onal Activiti ommissionin r Building..
e Building a Treatment B e Building..
WR Crib Ho r
TABLE O g Site Disman g Decommis Systems and tion System.
System.........
oling System cation System Spray Syste e Disposal Sy Storage Well oling Water ve Accumula ystem...........
d Water Syst rage Tank....
ontrol Air Sy Service Wat Service Wa Water System ystem and Fe ndensate Dem e..................
Generator....
nd Hydrogen ilation, and A Collection S tribution Sys es................
ng Activities and Turbine O Building, Gas ouse.............
3-i OF CONTE ntlement Ac ssioning Act d Componen m.................
m.................
em................
ystem..........
System......
ator System.
tem..............
ystem..........
ter System..
ater System..
eedwater He mineralizer n Seal Oil Sy Air Conditio Systems.......
stem............
s and Tasks..
Office Build s Storage Ta ENTS ctivities........
tivities and T nts................
eaters...........
System........
ystem...........
oning (HVA ding.............
ank Vault an Tasks...........
AC) Systems.
nd LSA
... 3-1
... 3-1
... 3-3
... 3-3
... 3-3
... 3-3
... 3-4
... 3-4
... 3-4
... 3-4
... 3-4
... 3-4
... 3-5
... 3-5
... 3-5
... 3-5
... 3-5
... 3-6
... 3-6
... 3-6
... 3-6
... 3-6
... 3-6
... 3-7
... 3-7
... 3-7
... 3-7
... 3-8
... 3-8
... 3-8
... 3-8
... 3-9
. 3-11
. 3-12
. 3-13


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 3.3.5. Maintenance Eat Sh        hack and 1B      B Diesel Gennerator Buildding .................................. 3-14 3.3.6. Ventilaation Stack ....................................................................................................... 3-14 3.3.7. Legacy  y Waste ............................................................................................................ 3-15 3.4. Radiologicaal Impacts off Decommissioning Actiivities ................................................... 3-15 3.4.1. Control Mechanism        ms to Mitigatte the Reconntamination of Remediatted Areas...... 3-16 3.4.2. Occupaational Expo      osure ............................................................................................. 3-16 3.4.3. Exposu  ure to the Pu  ublic .............................................................................................. 3-16 3.4.44. Radioaactive Waste Projections ................................................................................ 3-17 3.4.5. Projectt Milestones..................................................................................................... 3-18 3.5. References ........................................................................................................................ 3-19 LIST OF TABLE              ES 1
La Cross License T Revision 3.3.
Table 3-1    Status of o Major LA    ACBWR Sysstems and Coomponents aas of June 20015 ................. 3-2 Table 3-2 2    Radiatiion Exposuree Projectionss for Decom                  mmissioning .......................................... 3-16 Table 3-3 3    Projectted Waste Qu    uantities ....................................................................................... 3-17 Table 3-4 4    Generaal Project Miilestones ....................................................................................... 3-18 3-ii
3.3.
3.3.
3.4.
3.4.
3.4.
3.4.
3.4.4 3.4.
3.5.
Table 3-1 Table 3-2 Table 3-3 Table 3-4 se Boiling W Termination n 0 5.
Mainte 6.
Ventila 7.
Legacy Radiologica 1.
Contro 2.
Occupa 3.
Exposu 4.
Radioa 5.
Project References 1
Status o 2
Radiati 3
Project 4
Genera Water Reactor Plan nance Eat Sh ation Stack..
y Waste.......
al Impacts of l Mechanism ational Expo ure to the Pu active Waste t Milestones of Major LA ion Exposure ted Waste Qu al Project Mi r
hack and 1B f Decommis ms to Mitigat osure............
ublic.............
Projections LIST ACBWR Sys e Projections uantities......
ilestones......
3-ii B Diesel Gen sioning Acti te the Recon OF TABLE stems and Co s for Decom nerator Build ivities..........
ntamination ES omponents a mmissioning.
ding.............
of Remediat as of June 20 ted Areas.....
015..............
. 3-14
. 3-14
. 3-15
. 3-15
. 3-16
. 3-16
. 3-16
. 3-17
. 3-18
. 3-19
... 3-2
. 3-16
. 3-17
. 3-18


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 LIST OF ACRONYM      MS AND AB    BBREVIATTIONS ALARA A        As Low L As Reasonably Ach    hievable ACM             Asbestos Contaiining Materiial AMSL           Aboove Mean Seea Level BSFR           Bulkk Survey Forr Release CCW             Commponent Coo  oling Water CST             Conndensate Storrage Tank D-Plan//
La Cross License T Revision ALARA ACM AMSL BSFR CCW CST D-Plan/
PSDAR R        Deccommissionin  ng Plan/Postt Shutdown Decommissioning Activvities Reportt FESW           Fuell Element Sttorage Well FRS             Finaal Radiation Survey G-3             Gennoa Fossil Staation GSTV           Gas Storage Tan nk Vault HPSW           Highh Pressure Service Wateer HVAC           Heatting Ventilattion Air Con nditioning kVA            kilo--Volt-Ampere ISFSI          Indeependent Speent Fuel Storrage Installaation LACBW  WR      La Crosse C      Boilinng Water Reeactor LPSW            Loww Pressure Seervice Waterr LSA            Loww Specific Acctivity LSE            LAC CBWR Site Enclosure E
PSDAR FESW FRS G-3 GSTV HPSW HVAC kVA ISFSI LACBW LPSW LSA LSE LTP NRC ODCM OHST REMP RPV RWP WTB se Boiling W Termination n 0 A
LTP            Liceense Terminaation Plan NRC            Nuclear Regulattory Commisssion ODCM M          Off--site Dose Caalculation Manual M
As L Asb Abo Bulk Com Con
OHST            Overhead Storag  ge Tank REMP            Radiological En nvironmentall Monitoringg Program RPV            Reacctor Pressuree Vessel RWP            Radiation Work k Permit WTB            Wasste Treatmen nt Building 3-iii
/
R Dec Fuel Fina Gen Gas High Heat kilo-Inde WR La C Low Low LAC Lice Nuc M
Off-Ove Rad Reac Rad Was Water Reactor Plan LIST OF Low As Rea estos Contai ove Mean Se k Survey For mponent Coo ndensate Stor commissionin l Element St al Radiation noa Fossil Sta Storage Tan h Pressure S ting Ventilat
-Volt-Ampe ependent Spe Crosse Boilin w Pressure Se w Specific Ac CBWR Site E ense Termina lear Regulat
-site Dose Ca rhead Storag iological En ctor Pressure iation Work ste Treatmen r
ACRONYM sonably Ach ining Materi ea Level r Release oling Water rage Tank ng Plan/Post torage Well Survey ation nk Vault ervice Wate tion Air Con re ent Fuel Stor ng Water Re ervice Water ctivity Enclosure ation Plan tory Commis alculation M ge Tank nvironmental e Vessel k Permit nt Building 3-iii MS AND AB hievable ial t Shutdown er nditioning rage Installa eactor r
ssion Manual l Monitoring BBREVIAT Decommiss ation g Program TIONS ioning Activvities Reportt


La Crossse Boiling Water W     Reactorr License Termination T            Plan Revision n0 Page Inten ntionally Lefft Blank 3-iv
La Cross License T Revision se Boiling W Termination n 0 Water Reactor Plan r
Page Inten 3-iv ntionally Lefft Blank  


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revisionn0
La Cross License T Revision
: 3.     Iddentificatiion of Rem    maining Siite Disman        ntlement A    Activities 3.1. In ntroduction n In accorddance with 10CFR50.82 1                (a)(9)(ii)(B), the Licensse Terminatiion Plan (LT  TP) must ideentify the remaaining majorr dismantlem   ment and deccontaminatioon activitiess for the deccommissioniing at the time of submittaal. The info   formation inccludes thosee areas and equipment that need fuurther remediatiion and an assessment a            of o the potenttial radiolog ical conditioons that mayy be encounttered.
: 3.
Estimates of the occcupational radiation r            do ose and the quantity off radioactive material tto be released to unrestricted areas du  uring the completion off the scheduuled tasks are provided. The projectedd volumes off radioactivee waste that will be geneerated are alsso included. These activities will be undertaken pursuant to      o the curren   nt 10 CFR 550 license, are consisttent with thhe La Crosse Boiling B        Waater Reacto  or (LACBW     WR) Decom    mmissioning Plan andd Post-Shuttdown Decommissioning Acctivities Repo    ort (D-Plan//PSDAR) (11) and do noot depend uppon LTP appproval to proceeed.
Id 3.1.
The LAC  CBWR site will be decontaminateed and dism          mantled in acccordance w    with the DE ECON alternativ ve, as desccribed in NUREG-058 N              86 Generic Environmeental Impacct Statemennt on Decommissioning off Nuclear Facilities, F              Supplement S           1, Volume 1 (2). Coompletion of the DECON alternative is  i contingen nt upon contiinued accesss to one or m  more low levvel waste dissposal sites. Cu urrently, LaCCrosseSolutiions (Solutio  ons) has acccess to low-llevel waste ddisposal faciilities located in n Andrews, Texas and att the Energy      ySolutions faacility locateed in Clive, U Utah.
In In accord the rema the time remediati Estimate released projected will be Crosse B Decomm to procee The LAC alternativ Decomm DECON sites. Cu located in Decomm regulator State and Decomm of 10 CF involve LACBW the techn approval Decomm Safety an decommi operation The rem described discussed major rem specific e compone se Boiling W Termination n 0 dentificati ntroduction dance with 1 aining major of submitta ion and an a s of the oc to unrestric d volumes of undertaken Boiling Wa issioning Ac ed.
Decomm  missioning activities a          aree being co    oordinated w  with the appplicable Feederal and State regulatorry agencies in accordan  nce with plaant administtrative proceedures. Appplicable Fedderal, State andd local regu ulatory agen ncies are listted in section 8.7.2 of L LTP Chapterr 8.
CBWR site ve, as desc issioning of alternative i urrently, LaC n Andrews, missioning a ry agencies d local regu missioning ac FR 50.82(a)(6 any un-revi WR. If an act nical specifi before impl missioning ac nd Health P issioning do ns, especially maining dec d in section d in sections maining com equipment r ents that hav Water Reactor Plan ion of Rem n
Decomm  missioning acctivities at LAACBWR wiill be conduccted in accorrdance with the requirem      ments of 10 CFFR 50.82(a)(6  6) and (a)(7)). At the tim  me of LTP ssubmittal, thhe remainingg activities ddo not involve any un-reviiewed safetty questionss or changees in the T            Technical Specificationns for LACBW  WR. If an acttivity requirees prior NRC    C approval uunder 10 CFR 50.59(c)(22), or a channge to the technnical specifiications or license, l        a su ubmittal willl be made to the NRC     C for review w and approval before impllementing th  he activity in n question.
10CFR50.82 r dismantlem al. The info assessment o ccupational r ted areas du f radioactive pursuant to ater Reacto ctivities Repo will be de cribed in N f Nuclear F is contingen CrosseSoluti Texas and at activities are in accordan ulatory agen ctivities at LA
Decomm  missioning acctivities are conducted under the S      Solutions Raadiation Prootection Proggram, Safety an nd Health Program, P          an nd Waste Management M              Program Activities cconducted dduring decommiissioning do not pose an    ny greater radiological orr safety riskk than those cconducted dduring operationns, especially y those durin ng major maaintenance annd outage evvolutions.
: 6) and (a)(7) iewed safet tivity require ications or l lementing th ctivities are Program, an not pose an y those durin ontamination 3.3. The sp s 3.3.2 throu mponents of remediation e been or are r
The rem maining decontamination    n and dism    mantlement activities th  that will bee performedd are describedd in section 3.3. The sp  pecific system  m consideraations that w will be takenn into accounnt are discussedd in sectionss 3.3.2 throuugh 3.3.7. These T      sectionns provide aan overview and describbe the major remmaining com mponents of contaminateed plant systtems and, ass appropriatee, a descriptiion of specific equipment e           remediation r              consideratio ons. Table 33-1 containss a list of m major systems and componeents that have been or aree to be remo    oved.
maining Si (a)(9)(ii)(B ment and dec formation inc of the potent radiation do uring the co e waste that o the curren or (LACBW ort (D-Plan/
3-1
contaminate NUREG-058 Facilities, S nt upon conti ions (Solutio t the Energy e being co nce with pla ncies are list ACBWR wi
). At the tim ty questions es prior NRC license, a su he activity in conducted nd Waste M ny greater ra ng major ma n and dism pecific system ugh 3.3.7. T contaminate consideratio e to be remo 3-1 ite Disman
), the Licens contaminatio cludes those tial radiolog ose and the mpletion of will be gene nt 10 CFR 5 WR) Decom
/PSDAR) (1 ed and dism 86 Generic Supplement inued access ons) has acc ySolutions fa oordinated w ant administ ted in sectio ill be conduc me of LTP s s or change C approval u ubmittal wil n question.
under the S Management diological or aintenance an mantlement m considera These section ed plant syst ons. Table 3 oved.
ntlement A se Terminati on activities e areas and ical conditio quantity of f the schedu erated are als 50 license, mmissioning
: 1) and do no mantled in ac Environme 1, Volume 1 s to one or m cess to low-l acility locate with the ap trative proce n 8.7.2 of L cted in accor submittal, th es in the T under 10 CF ll be made Solutions Ra Program r safety risk nd outage ev activities th ations that w ns provide a tems and, as 3-1 contains Activities ion Plan (LT s for the dec equipment ons that may f radioactiv uled tasks ar so included.
are consist Plan and ot depend up ccordance w ental Impac 1 (2). Co more low lev level waste d ed in Clive, U pplicable Fe edures. Ap LTP Chapter rdance with he remaining Technical S R 50.59(c)(2 to the NRC adiation Pro Activities c k than those c volutions.
that will be will be taken an overview s appropriate s a list of m TP) must ide commissioni that need fu y be encount e material t e provided.
These acti tent with th d Post-Shut pon LTP app with the DE ct Statemen ompletion o vel waste dis disposal faci Utah.
ederal and pplicable Fed r 8.
the requirem g activities d pecification 2), or a chan C for review otection Prog conducted d conducted d e performed n into accoun and describ e, a descripti major system entify ing at urther tered.
to be The vities he La tdown proval ECON nt on f the sposal ilities State
: deral, ments do not ns for nge to w and
: gram, during during d are nt are be the ion of s and


La Crossse Boiling Water W       Reactorr License Termination T              Plan Revision n0 Tablee 3-1     Sta atus of Majo or LACBW  WR Systems and Compoonents as of June 20115 System or Componen    nt                                  Staatus Forcedd Circulationn System              Partially Rem moved Reactoor Vessel Intternals                Removed R          from m site Reactoor Vessel                          Removed R          from m site Main Steam S    in Reactor Bldg.            In n place Decayy Heat Coolin  ng System            In n place- Draiined Primarry Purificatioon System            Io on Exchangeers in place; 90% removed Feedwwater in Reacctor Bldg.              In n place Seal In njection Systtem                    900% removedd Altern nate Core Sprray System              500% removedd Gaseous Waste Diisposal Systeem          All A except unnderground sstorage tank removed Fuel Element E        Storrage Well Syystem      Contents C          remmoved- Drainned Compo  onent Coolin ng Water (C CCW)        In n place- 70% % Removed Hydraulic Valve Accumulator A            r System In n place- Draiined Well Water W      Systemm                      In n Place - Isolated from T Turbine/Reacctor Bldg.
La Cross License T Revision Forced Reacto Reacto Main S Decay Primar Feedw Seal In Altern Gaseo Fuel E Compo Hydra Well W Demin Overh Station Low P High P Circul Conde Heater Steam 60-Me Main C Turbin se Boiling W Termination n 0 Table System or d Circulation or Vessel Int or Vessel Steam in Re y Heat Coolin ry Purificatio water in Reac njection Syst nate Core Spr us Waste Di Element Stor onent Coolin ulic Valve A Water System neralized Wa ead Storage n and Contro Pressure Serv Pressure Serv ating Water ensate and Fe rs Turbine egawatt Gen Condenser &
Demin neralized Waater System            In n place- Draiined- 50% reemoved Overhead Storage Tank (OHST)              In n place- Draiined Station n and Contro ol Air System m          In n place Low Pressure P        Servvice Water            300% removedd High Pressure P        Servvice Water            Operational O
ne Bldg. Mai Water Reactor Plan e 3-1 Sta as Componen n System ternals actor Bldg.
Circulating Water System                  Remains R        in pllace - pumpps de-energizzed Condeensate and Feeedwater Taanks and    Drained-D          Conndensate Storage Tank reemain in Heaterrs                                  pllace, All Feeedwater Heaaters removeed Steam Turbine                            Removed R
ng System on System ctor Bldg.
60-Meegawatt Generator                    Removed R
tem ray System isposal Syste rage Well Sy ng Water (C Accumulator m
Main Condenser C          & Accessoriees          155% Removeed Turbinne Bldg. Maiin Steam                Removed R
ater System Tank (OHS ol Air System vice Water vice Water System eedwater Ta erator
3-2
& Accessorie in Steam r
atus of Majo of June 201 nt P
R R
In In Io In 90 50 em A
ystem C
CCW)
In r System In In In T)
In m
In 30 O
R anks and D
pl R
R es 15 R
3-2 or LACBW 15 artially Rem Removed from Removed from n place n place-Drai on Exchange n place 0% removed 0% removed All except un Contents rem n place-70%
n place-Drai n Place - Iso n place-Drai n place-Drai n place 0% removed Operational Remains in pl Drained-Con lace, All Fee Removed Removed 5% Remove Removed WR Systems Sta moved m site m site ined ers in place; d
d nderground s moved-Drain
% Removed ined lated from T ined-50% re ined d
lace - pump ndensate Sto edwater Hea ed and Compo atus 90% remov storage tank ned Turbine/Reac emoved ps de-energiz rage Tank re aters remove onents ed removed ctor Bldg.
zed emain in ed


La Crossse Boiling Water W       Reactorr License Termination T            Plan Revision n0 Tabble 3-1 (con ntinued)      Status S        of Maajor LACBW    WR System  ms and Components as a of June 20  015 System or Componen    nt                                    Staatus Turbinne Bldg. Con ndensate and d Feed      Removed R
La Cross License T Revision Tab Turbin Turbin Liquid Fuel T HVAC Electri Asbest After th demonstr reduced t will be decommi 3.2.
Turbinne Oil and Hydrogen H         Seaal Oil      Partially Remmoved Liquidd Waste Colllection Systeems          In n place - Parrtially Operaational Fuel Transfer T        Brid dge                        Removed R
C 3.2.1.
HVAC  C Systems                             In n place - Parrtially Operaational Electriical Systemss                        In n place- Discconnected Asbesttos Abatemeent                        75 5% complette After the balance of the site is remediaated and thhe levels of residual radioactivityy are demonstrrated to be below the unrestricted u              release criteeria, the 10 CFR Part 500 license will be reduced tot the area around a      the Independent I               Spent Fuel Storage Installation (IS SFSI) and the site will be transferred back to Daairyland und      der the 10 CFR Part 550 license. Spent fuell and decommiissioning acttivities comp   pleted to date are providded in sectionn 3.2.
In excess addition disposal waste.
3.2. Completed C          and a Ongoing     g Decommisssioning Acctivities and Tasks 3.2.1.       Overvieww In excesss of 2 million pounds off metallic waaste have beeen removedd, shipped, annd disposed of in addition to the Reacctor Pressurre Vessel (R    RPV) and sspent fuel sttorage rackss. Removall and disposal of the RPV  V included disposition d             of o irradiatedd hardware aand all otheer Class B aand C waste.
Waste sto Class B/C were ship rod blad Attachme removed fuel asse the storag 3.2.2.
Waste sto ored in the Fuel F    Elemen              W (FESW)) was processsed and colllected with other nt Storage Well Class B/CC waste (i.e., resins, filtters, and wasste barrel coontents) and packaged inn three liners that were ship pped for disp posal in Junee 2007. Thee RPV contaaining the reaactor internaals and 29 coontrol rod blad des was fillled with lo  ow-density cellular c         conncrete with the reactorr head instaalled.
3.2.2.1.
Attachmeents to the RPVR    were removed r          and d all other aappurtenances were cutt. The RPV    V was removed from the Reactor Build    ding and was shipped foor disposal inn June 20077. After all spent fuel assemblies and fuel f    debris were w      placed in dry cask storage in thhe ISFSI in September 22012, the storagge racks and d installed coomponents were w removedd from the F       FESW.
The Forc Circulati se Boiling W Termination n 0 ble 3-1 (con System or ne Bldg. Con ne Oil and H d Waste Coll Transfer Brid C Systems ical Systems tos Abateme e balance rated to be to the area a transferred issioning act Completed a Overview s of 2 millio to the Reac of the RPV ored in the F C waste (i.e pped for disp des was fill ents to the R from the R mblies and f ge racks and Dismantl Force ced Circula on pumps, a Water Reactor Plan ntinued)
3.2.2.       Dismantllement of Sy  ystems and Componentts 3.2.2.1.        Forced Circulation  n System The Forcced Circulaation system  m and attend    dant oil sysstems have been draineed. The Foorced Circulation pumps, auxiliary a          oil pumps, and hydraulic coupling oil ppumps have been electriically 3-3
S a
Componen ndensate and Hydrogen Sea lection Syste dge s
ent of the site below the u around the I back to Da tivities comp and Ongoing w
n pounds of ctor Pressur V included d Fuel Elemen
., resins, filt posal in June led with lo RPV were r eactor Build fuel debris w d installed co lement of Sy d Circulation ation system auxiliary oil r
Status of Ma as of June 20 nt d Feed R
al Oil P
ems In R
In In 75 is remedia unrestricted Independent airyland und pleted to dat g Decommis f metallic wa re Vessel (R disposition o nt Storage W ters, and was e 2007. The ow-density c removed and ding and wa were placed omponents w ystems and n System m and attend pumps, and 3-3 ajor LACBW 015 Removed artially Rem n place - Par Removed n place - Par n place-Disc 5% complet ated and th release crite Spent Fuel der the 10 e are provid ssioning Ac aste have be RPV) and s of irradiated Well (FESW) ste barrel co e RPV conta cellular con d all other a s shipped fo in dry cask were removed Component dant oil sys hydraulic c WR System Sta moved rtially Opera rtially Opera connected te he levels o eria, the 10 Storage Ins CFR Part 5 ded in section ctivities and een removed spent fuel st d hardware a
) was proces ontents) and aining the rea ncrete with appurtenanc or disposal in storage in th d from the F ts stems have oupling oil p ms and Com atus ational ational f residual CFR Part 50 tallation (IS 50 license.
n 3.2.
Tasks d, shipped, an torage racks and all othe ssed and col packaged in actor interna the reactor es were cut n June 2007 he ISFSI in FESW.
been draine pumps have ponents radioactivity 0 license w SFSI) and th Spent fuel nd disposed
: s. Removal er Class B a llected with n three liner als and 29 co r head insta
: t. The RPV
: 7. After all September 2 ed. The Fo been electri y are ill be e site l and of in l and and C other s that ontrol alled.
V was spent
: 2012, orced ically


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 disconnected. All 16  1 inch and 20 inch Forrced Circulaation system      m piping wass filled withh low density cellular c       conccrete. Four 16 inch Forcced Circulattion inlet nozzles and foour 16 inch ooutlet nozzles were w     cut to allow remo  oval of the reactor presssure vessel. Piping loocated within the reactor cavity c       was also a    cut at the biologiccal shield, ssegmented iinto manageeable pieces, and disposed of. Pumps and piping in the shieldeed cubicles rremain.
La Cross License T Revision disconne density c nozzles w reactor c disposed 3.2.2.2.
3.2.2.2.         Seal Injection Sysstem The Seall Injection system proviided cooling    g and sealingg water for the seals onn the two Foorced Circulation pumps an  nd the 29 coontrol rod drive units. T This system iis drained annd approxim  mately 90% rem moved.
The Seal Circulati 90% rem 3.2.2.3.
3.2.2.3.         Decayy Heat Cooliing System The Deccay Heat Co    ooling system m was a sin  ngle high prressure clossed loop conntaining a ppump, cooler, and interconn necting pipin ng used to remove r        core decay heat following rreactor shutddown.
The Dec cooler, a This syst 3.2.2.4.
This systtem is draineed and inopeerable.
The Prim regenerat resins ha coolers a 3.2.2.5.
3.2.2.4.         Primaary Purificatiion System The Prim mary Purificcation system was a high  h      pressurre, closed looop system consisting of a regenerattive cooler, purification n cooler, pum mp, two ionn exchangerrs and filterss. Ion exchhange resins haave been rem moved and the t system has h been drrained. Thee Primary Puurification ppump, coolers and a 90% of th  he piping haave been rem moved and diisposed as raadioactive w  waste. .
The Alte (HPSW) duplex st system in and 80%
3.2.2.5.        Altern nate Core Sp pray System The Alteernate Core Spray system consisted      d of two dieesel-driven H  High Pressurre Service W  Water (HPSW) pumps, whiich took sucction from th      he river and discharged to the reactoor vessel thrrough duplex sttrainers and two motor-o   operated vallves installedd in parallel. Approxim  mately 50% oof the system inn the Reacto or Building was w removed    d due to inteerference with the reactoor vessel rem  moval and 80%  % of the piiping in thee Turbine Building B          haas been rem  moved. Reemaining syystem componeents are drain ned and are ready r     for dissmantlementt.
compone 3.2.2.6.
3.2.2.6.        Gaseoous Waste Disposal Systtem This systtem routed main condeenser gassess through vaarious compponents for drying, filteering, recombin ning, monito  oring and holdup h       for decay. Thhis system hhas been reemoved withh the exception n of the und derground gaas storage tan  nks and the gas storage tank in the T    Turbine Buiilding tunnel.
This syst recombin exception tunnel.
3.2.2.7.        Fuel Element E        Storrage Well The Fuell Element Sto  orage Well (FESW)
3.2.2.7.
(        is a stainless steeel lined conncrete structuure that meaasures 11 feet by b 11 feet by  b approxim  mately 42 feeet deep. W    When full, it containeed approxim    mately 38,000 gallons of waater. The FE  ESW cooling  g system is cconnected too the well annd consists oof two pumps, one o heat excchanger, onee ion exchan    nger, piping,, valves, andd instrumenttation. All spent fuel and fuel debris, installed i        com mponents, an  nd storage raacks have beeen removedd from the stoorage well and a fixative was w applied to   o the walls. The system m has been drrained and iss inoperable.
The Fuel 11 feet b 38,000 g pumps, o fuel and well and se Boiling W Termination n 0 cted. All 1 cellular conc were cut to cavity was a of. Pumps Seal I l Injection s on pumps an moved.
3-4
Decay cay Heat Co nd interconn tem is draine Prima mary Purific tive cooler, ave been rem and 90% of th Altern ernate Core pumps, whi trainers and n the Reacto
% of the pi ents are drain Gaseo tem routed ning, monito n of the und Fuel E l Element Sto by 11 feet b allons of wa one heat exc fuel debris, i a fixative w Water Reactor Plan 16 inch and crete. Four allow remo also cut at and piping i njection Sys ystem provi nd the 29 co y Heat Cooli ooling system necting pipin ed and inope ary Purificati cation syste purification moved and t he piping ha nate Core Sp Spray syste ich took suc two motor-o or Building w iping in the ned and are r ous Waste D main conde oring and h derground ga Element Stor orage Well (
by approxim ater. The FE changer, one installed com was applied to r
20 inch For 16 inch Forc oval of the the biologic n the shielde stem ided cooling ontrol rod dr ing System m was a sin ng used to r erable.
ion System m was a h n cooler, pum the system h ave been rem pray System m consisted ction from th operated val was removed e Turbine B ready for dis isposal Syst enser gasses holdup for as storage tan rage Well (FESW) is a mately 42 fe ESW cooling e ion exchan mponents, an o the walls.
3-4 rced Circula ced Circulat reactor pres cal shield, s ed cubicles r g and sealing ive units. T ngle high pr remove core high pressur mp, two ion has been dr moved and di d of two die he river and lves installed d due to inte Building ha smantlement tem s through va decay. Th nks and the a stainless ste eet deep. W g system is c nger, piping, nd storage ra The system ation system tion inlet no ssure vessel segmented i remain.
g water for This system i ressure clos decay heat re, closed lo n exchanger rained. The isposed as ra esel-driven H discharged d in parallel erference wi as been rem
: t.
arious comp his system h gas storage eel lined con When full, connected to
, valves, and acks have be m has been dr m piping was zzles and fo
. Piping lo into manage the seals on is drained an sed loop con following r oop system rs and filters e Primary Pu adioactive w High Pressur to the reacto
. Approxim th the reacto moved. Re ponents for has been re tank in the T ncrete structu it containe o the well an d instrument een removed rained and is s filled with our 16 inch o ocated withi eable pieces n the two Fo nd approxim ntaining a p reactor shutd consisting
: s. Ion exch urification p waste..
re Service W or vessel thr mately 50% o or vessel rem emaining sy drying, filte emoved with Turbine Bui ure that mea ed approxim nd consists o tation. All d from the sto s inoperable.
h low outlet n the
, and orced mately
: pump, down.
of a hange
: pump, Water rough of the moval ystem
: ering, h the ilding asures mately of two spent orage


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 3.2.2.8.         Comp  ponent Cooliing Water Sy  ystem The Com mponent Coo  oling Water (CCW) systtem providedd controlledd quality coooling water tto the various heat h exchang    gers and pum mps in the Reactor R        Buildding during plant operattion, servingg as a barrier between b         radioactive sysstems and secondary s          c ooling systeems. The system provvided cooling water w       to Reeactor Build ding Air Con nditioner coompressors. The dismaantlement off this system iss approximattely 70% com    mplete.
La Cross License T Revision 3.2.2.8.
3.2.2.9.         Hydraaulic Valve Accumulator A          r System The funcction of the Hydraulic H          Valve V      Accum mulator system m was to suupply the neccessary hydrraulic force to operate the five piston-ttype valve actuators, a          whhich operateed the five rrotoport valvves in the Forceed Circulatio  on and Main  n Steam systtems. The hhydraulic syystem has beeen drained. The air compressors, watter pumps, an    nd other equ uipment havee also been electrically disconnectedd and drained.
The Com various h barrier b cooling w system is 3.2.2.9.
3.2.2.10.       Well Water W      Systemm Water fo or this system was supp    plied from two t    sealed ssubmersible deep well pumps that took suction through t         stainless steel strainers, annd dischargeed into inteegrated presssure tanks. The system su upplied wateer to the plaant and officee for sanitarry and drinkiing purposes. It was ussed as cooling water w      for thee two Turbine Building  g air-conditiooning units and the heatting boiler bblow-down flaash tank and   d sample co  ooler. The well water system alsoo supplied w      water for lauundry equipmen  nt and seal water w     for th he Circulatin ng Water pum  mps. The W Well Water System has been isolated from f    the Reeactor/Turbin ne building. Well waterr pump #3 ssupplies pottable water tto the Administtration Build  ding and Crib b House.
The func force to the Force air comp drained.
3.2.2.11.        Demin  neralized Water System The Dem  mineralized Water W      Systemm consists of o a lower C Condensate S Storage Tankk with a cappacity of 19,100 0 gallons and d an upper Virgin V       Waterr Tank, whicch has a capaacity of 29,7780 gallons. Both are two sections s         of an a integral aluminum tan  nk located oon the Turbinne Building office roof. The Virgin Water W      Tank provided p        watter to the Demineralizedd Water transsfer pumps, w  which distribbuted demineraalized water throughout the plant. Water W     was ddemineralizeed in batchess at Genoa F  Fossil Station (GG-3). The sy  ystem has beeen drained.
3.2.2.10.
3.2.2.12.        Overh head Storagee Tank The Oveerhead Storaage Tank (O      OHST) is a 45,000-gallo 4           on tank locaated at the ttop of, and is an integral part p of, the Reactor R        Building. The OHST serveed as a reserrvoir for waater used to flood the FESW W, cask poo  ol, and upperr cavity duriing cask loaading operatiions. Durinng operations, the OHST accted as a receiver for reejecting refu    ueling waterr using the P Primary Purrification syystem.
Water fo suction t system su cooling w down fla equipmen isolated f Administ 3.2.2.11.
The OHS  ST also supp  plied the waater for the Emergency E            C Core Spray ssystem and Reactor Buiilding Spray sy ystem, and was w a backup    p source for the Seal Inj njection systeem. The syystem is currrently drained and a inoperab    ble.
The Dem of 19,100 are two s Virgin W deminera Station (G 3.2.2.12.
3-5
The Ove integral p the FESW OHST ac The OHS Spray sy drained a se Boiling W Termination n 0 Comp mponent Coo heat exchang between rad water to Re s approximat Hydra ction of the H operate the ed Circulatio ressors, wat Well W or this syste through stai upplied wate water for the ash tank and nt and seal w from the Re tration Build Demin mineralized W 0 gallons and sections of a Water Tank p alized water G-3). The sy Overh erhead Stora part of, the R W, cask poo cted as a re ST also supp ystem, and w and inoperab Water Reactor Plan ponent Cooli oling Water gers and pum ioactive sys eactor Build tely 70% com aulic Valve A Hydraulic V five piston-t on and Main ter pumps, an Water System m was supp nless steel er to the pla e two Turbi d sample co water for th eactor/Turbin ding and Crib neralized W Water System d an upper V an integral a provided wat throughout ystem has be head Storage age Tank (O Reactor Bui ol, and upper ceiver for re plied the wa was a backup ble.
r ing Water Sy (CCW) syst mps in the R stems and s ding Air Con mplete.
Accumulator Valve Accum type valve a n Steam syst nd other equ m
plied from t strainers, an ant and office ne Building ooler. The he Circulatin ne building.
b House.
ater System m consists o Virgin Water luminum tan ter to the De the plant. W een drained.
e Tank OHST) is a 4 lding. The r cavity duri ejecting refu ater for the E p source for 3-5 ystem tem provided Reactor Build secondary c nditioner co r System mulator system actuators, wh tems. The h uipment have two sealed s nd discharge e for sanitar g air-conditio well water ng Water pum Well water of a lower C r Tank, whic nk located o mineralized Water was d 45,000-gallo OHST serve ing cask loa ueling water Emergency C the Seal Inj d controlled ding during ooling syste ompressors.
m was to su hich operate hydraulic sy e also been submersible ed into inte ry and drinki oning units system also mps. The W r pump #3 s Condensate S ch has a capa on the Turbin d Water trans demineralize on tank loca ed as a reser ading operati r using the P Core Spray s njection syste d quality coo plant operat ems. The The disma upply the nec ed the five r ystem has be electrically deep well egrated press ing purpose and the heat o supplied w Well Water supplies pot Storage Tank acity of 29,7 ne Building sfer pumps, w ed in batches ated at the t rvoir for wa ions. Durin Primary Pur system and em. The sy oling water t tion, serving system prov antlement of cessary hydr rotoport valv een drained.
disconnected pumps that sure tanks.
: s. It was us ting boiler b water for lau System has table water t k with a cap 780 gallons.
office roof.
which distrib s at Genoa F top of, and ater used to ng operation rification sy Reactor Bui ystem is curr to the g as a vided f this raulic ves in The d and took The sed as blow-undry been to the pacity Both The buted Fossil is an flood s, the ystem.
ilding rently


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 3.2.2.13.       Station and Control Air System There aree two single-stage positiive displacem    ment lubricaated type commpressors. The air receeivers act as a volume v       storaage unit for the t station. The air receeiver outlet liines join to fform a headeer for supply too the stationn and the con  ntrol air sysstems. This system is ccurrently stilll operable aand is used as needed.
La Cross License T Revision 3.2.2.13.
n 3.2.2.14.       Low Pressure P        Serv vice Water System S
There are act as a v supply to used as n 3.2.2.14.
Two verttical pumps located in th    he LACBWR Crib Houuse supplied the system through a duuplex strainer unit.
Two vert strainer u was the system is river wat to allow 3.2.2.15.
u     The Low Pressuree Service Water (LPSW        W) system sup              CCW coolers and upplied the C was the normal sup    pply to the HPSWH        system throughh the motor--driven HPS    SW pump. This system iss currently used u    as the dilution d        watter supply foor conductinng liquid waaste dischargges of river watter ingress inn the turbinee building tu  unnel area. The originaal system hass been simplified to allow dismantlemeent which is approximateely 30% com        mplete.
The purp (G-3) ma The inter (WTB) i hydrants the fire s by the rem 3.2.2.16.
3.2.2.15.       High Pressure P        Serrvice Water System The purp pose of the HPSW H        systeem is to supply fire sup pression waater. The addjacent coal plant (G-3) maaintains HPS  SW system pressure. The     T HPSW system is ddivided into two main loops.
Circulatin open suc join a co condense Water en tube side which di LACBW pumps ha 3.2.2.17.
The interrnal loop serrved the Turrbine Buildin    ng, Reactor BBuilding, annd Waste Treatment Buiilding (WTB) interior i         hosee stations an nd sprinklerr systems. The externaal loop suppplies outsidee fire hydrants and the LACBWR Crib        b House spriinklers. Thee external loop was crosss-connectedd with the fire suppression system s       for G-3.
The Cond pressure Tank (CS 3.2.2.18.
G      Currenttly, the systeem is isolateed from the TTurbine Buiilding by the remmoval of iso olation valvees and installling pipe blaanks to alloww only externnal fire loop use.
The Full removed piping ha se Boiling W Termination n 0 Statio e two single volume stora o the station needed.
3.2.2.16.       Circullating Waterr System Circulatinng water is drawn d     into the t intake flu  ume from thhe river by tw wo pumps loocated in sepparate open sucction bays in n the LACBWR Crib House. H        Eachh pump dischharges into 42 inch pipee that join a coommon 60 in   nch pipe leaading to thee main conddenser in thhe Turbine B    Building. A  At the condenseer, the 60 incch pipe bran  nches into tw wo 42 inch piipe to the toop section off the water bboxes.
Low P tical pumps unit. The L normal sup s currently u ter ingress in dismantleme High P pose of the H aintains HPS rnal loop ser interior hose and the LA uppression s moval of iso Circul ng water is d ction bays in ommon 60 in er, the 60 inc nters the top
Water en nters the top section of th he condenserr tube side aand is dischaarged from thhe bottom seection tube sidee. The 42 in  nch condensser circulatin  ng water outtlet lines tie into a comm mon 60 inchh line which discharges to the t seal well from G-3 located l       apprroximately 6600 feet dowwnstream from  m the LACBW  WR Crib Hou     use. The Circulating C              Water W      Systemm is currenttly inoperabble as the syystem pumps haave been de--energized.
: e. The 42 in scharges to t WR Crib Hou ave been de-Conde densate Syst to the suctio ST), this syst Full-F l-Flow Cond ionic impu ave been rem Water Reactor Plan n and Contr
3.2.2.17.        Condeensate System and Feedw      water Heaterrs The Cond  densate Systtem took con  ndensed steaam from the condenser hhotwell and ddelivered it uunder pressure to the suctio on of the reaactor feed pu umps. With the exceptioon of the Coondensate Stoorage Tank (CS ST), this systtem has been  n drained annd most of thhe piping hass been removved.
-stage positi age unit for t n and the con Pressure Serv located in th ow Pressure pply to the H used as the d n the turbine ent which is Pressure Ser HPSW syste SW system rved the Tur e stations an CBWR Crib system for G olation valve lating Water drawn into t n the LACB nch pipe lea ch pipe bran section of th nch condens the seal wel use. The C
3.2.2.18.        Full-F Flow Conden    nsate Demin  neralizer Systtem The Fulll-Flow Cond    densate Dem  mineralizer System connsisted of reesin-filled seervice tankss that removed ionic impurities from the     t condensate water gooing back too the reactor. All tankss and piping haave been rem moved.
-energized.
3-6
ensate Syste tem took con on of the rea tem has been Flow Conden densate Dem rities from t moved.
r ol Air Syste ive displacem the station.
ntrol air sys vice Water S he LACBW e Service W HPSW syst dilution wat e building tu approximate rvice Water em is to sup pressure. T rbine Buildin nd sprinkler b House spri G-3. Current es and install r System the intake flu WR Crib H ading to the nches into tw he condenser ser circulatin l from G-3 l Circulating W m and Feedw ndensed stea actor feed pu n drained an nsate Demin mineralizer the condens 3-6 m
ment lubrica The air rece stems. This System R Crib Hou ater (LPSW em through ter supply fo unnel area.
ely 30% com System ply fire sup The HPSW ng, Reactor B r systems.
inklers. The tly, the syste ling pipe bla ume from th House. Each e main cond wo 42 inch pi r tube side a ng water out located appr Water System water Heater am from the umps. With nd most of th neralizer Syst System con ate water go ated type com eiver outlet li system is c use supplied W) system sup h the motor-or conductin The origina mplete.
pression wa system is d Building, an The externa e external lo em is isolate anks to allow he river by tw h pump disch denser in th ipe to the to and is discha tlet lines tie roximately 6 m is current rs condenser h the exceptio he piping has tem nsisted of re oing back to mpressors.
ines join to f currently stil the system upplied the C
-driven HPS ng liquid wa al system has ater. The ad divided into nd Waste Tr al loop supp op was cros ed from the T w only extern wo pumps lo harges into he Turbine B op section of arged from th into a comm 600 feet dow tly inoperab hotwell and d on of the Co s been remov esin-filled se o the reacto The air rece form a heade ll operable a through a du CCW cooler SW pump.
aste discharg s been simp djacent coal two main l eatment Bui plies outside ss-connected Turbine Bui nal fire loop ocated in sep 42 inch pipe Building. A f the water b he bottom se mon 60 inch wnstream from ble as the sy delivered it u ondensate Sto ved.
ervice tanks
: r. All tanks eivers er for and is uplex s and This ges of lified plant oops.
ilding e fire d with ilding use.
parate e that At the boxes.
ection h line m the ystem under orage s that s and


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revisionn0 3.2.2.19.       Steam m Turbine The turbiine was a hiigh pressure, condensing    g, reaction, ttandem com  mpound, reheeat 3600 rpm  m unit rated at 60 6 MW. Th    he turbine co onsisted of a high pressuure and interrmediate preessure and a low-pressure element. The T Steam Turbine, T        as well w as som  me steam sysstem piping and compoonents have been removed.
La Cross License T Revision 3.2.2.19.
3.2.2.20.       60-Meegawatt Gen  nerator The 60 MW generator was a high-speed, turbine-ddriven wouund-rotor m                    machine rateed at 76,800 kV VA. The generator g           was cooled by b a hydroggen system, lubricated bby a forced-flow lubricatin ng system, and a excited by a separatte exciter atttached to thhe end of thhe generator shaft through a reduction gear.
The turbi rated at 6 pressure have bee 3.2.2.20.
g     The main m      and reseerve exciterss have been removed. T  The generatoor has been commpletely rem moved, uncon   nditionally reeleased and ddispositioneed.
The 60 76,800 kV lubricatin through a been com 3.2.2.21.
3.2.2.21.        Turbinne Oil and Hydrogen H           Seeal Oil Systemm The Turb  bine Oil Sysstem receiveed cooled oiil from the llube oil cooolers to suppply the neceessary lubricatin ng and cooliing oil to th  he turbine an nd generator bearings, exciter bearrings, and exxciter reductionn gear. Thiss system, wiith exception of the draained clean aand dirty oil tanks, has been completeely removed..
The Turb lubricatin reduction complete 3.2.2.22.
3.2.2.22.        Heatinng, Ventilatiion, and Air Conditioninng (HVAC) S      Systems The Reacctor Building Ventilatio  on System uttilized two 330 ton, 12,0000 cfm air cconditioning units for drawiing fresh airr into the bu uilding and for f circulatinng the air thrroughout thee building. Each air condiitioning unitt air inlet inccluded a filter box assemmbly, face aand bypass ddampers, andd one 337,500 Btu/hr B      capaccity steam coil c that wass used whenn heating waas required. Air entereed the building through opeenings between and around the bi-pparting doorr sections annd was exhaausted from the building ussing stack blowers throu      ugh the exhhaust stack ffor the faciliity. The staack is 350 feet high and is constructed of structuraal concrete w    with an alum minum nozzlee at the top. The exhaust system s       was equipped withw conventiional and hiigh-efficienccy filters andd monitoredd by a particulatte radiation detector. A monitoring    g system is iinstalled witth the exhauust system, w  which includes an isokinetiic nozzle, lo  ocated down nstream of tthe high-effficiency filteers. The syystem, which historically haas drawn airr from the sttack exhaustt to the monnitoring systeem, is capabble of detecting g particulate and gaseouss activity.
The Reac for drawi air condi 337,500 B building from the 350 feet exhaust s particulat includes which hi detecting Ventilati vault are the gas s vault thro Currently use of sta se Boiling W Termination n 0 Steam ine was a hi 60 MW. Th element. T n removed.
Ventilation for the WTB W      was proovided by a 2000 2    cfm exxhaust fan thhat drew air ffrom the shielded vault areas of the bu uilding and exhausted e          th he air througgh a duct ouut the floor oof the buildiing to the gas storage s        tank vault. The stack bloweers then exhhausted the aair from the gas storagee tank vault throough the connnecting tunn  nel and dischharged the aair from the bbuilding throough the stacck.
60-Me MW gener VA. The g ng system, a a reduction g mpletely rem Turbin bine Oil Sys ng and cooli n gear. This ely removed.
Currentlyy, both systeems are de-eenergized. Building B        venntilation is cuurrently suppplied througgh the use of staack fans thatt are energized by tempo  orary power.
Heatin ctor Buildin ing fresh air itioning unit Btu/hr capac through ope building us high and is system was te radiation an isokineti storically ha g particulate on for the W as of the bu storage tank ough the con y, both syste ack fans that Water Reactor Plan m Turbine igh pressure he turbine co The Steam T egawatt Gen ator was a generator w and excited gear. The m moved, uncon ne Oil and H stem receive ing oil to th s system, wi ng, Ventilati g Ventilatio r into the bu t air inlet inc city steam c enings betw sing stack b constructed equipped w detector. A ic nozzle, lo as drawn air and gaseous WTB was pro uilding and e vault. The nnecting tunn ems are de-e t are energiz r
3-7
, condensing onsisted of a Turbine, as w nerator a high-spee as cooled b by a separat main and rese nditionally re Hydrogen Se ed cooled oi he turbine an ith exceptio ion, and Air on System ut uilding and f cluded a filt coil that was een and aro lowers throu of structura with conventi A monitoring ocated down r from the st s activity.
ovided by a 2 exhausted th stack blowe nel and disch energized. B ed by tempo 3-7 g, reaction, t a high pressu well as som d, turbine-d by a hydrog te exciter at erve exciters eleased and d eal Oil System il from the l nd generato n of the dra Conditionin tilized two 3 for circulatin er box assem s used when und the bi-p ugh the exh al concrete w ional and hi g system is i nstream of t tack exhaust 2000 cfm ex he air throug ers then exh harged the a Building ven orary power.
tandem com ure and inter me steam sys driven wou gen system, ttached to th s have been dispositione m
lube oil coo r bearings, ained clean a ng (HVAC) S 30 ton, 12,00 ng the air thr mbly, face a n heating wa parting door haust stack f with an alum igh-efficienc installed wit the high-eff t to the mon xhaust fan th gh a duct ou hausted the a air from the b ntilation is cu mpound, rehe rmediate pre stem piping und-rotor m lubricated b he end of th removed. T ed.
olers to supp exciter bear and dirty oi Systems 00 cfm air c roughout the and bypass d as required.
r sections an for the facili minum nozzle cy filters and th the exhau ficiency filte nitoring syste hat drew air f ut the floor o air from the building thro urrently supp eat 3600 rpm essure and a and compo machine rate by a forced he generator The generato ply the nece rings, and ex l tanks, has conditioning e building.
dampers, and Air entere nd was exha ity. The sta e at the top.
d monitored ust system, w ers. The sy em, is capab from the shi of the buildi gas storage ough the stac plied throug m unit a low-onents ed at
-flow shaft or has essary xciter been units Each d one ed the austed ack is The d by a which
: ystem, ble of elded ing to e tank ck.
gh the


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 3.2.2.23.       Liquidd Waste Colllection Systems The Liqu uid Waste Sy  ystem colleccts the liquidd waste fromm the Turbinee Building, tthe WTB, thhe gas storage taank vault, annd the tunneel into two sttorage tanks (4500 galloons and 30000 gallons) loocated in the tunnnel between n the Reactor Building anda the Turbiine Buildingg.
La Cross License T Revision 3.2.2.23.
The Reacctor Buildin  ng Liquid Waste W     System m, which is sseparate from m the Liquid Waste Syystem, consists of two reten   ntion tanks, each with a capacity oof 6000 galllons, a liquiid waste traansfer pump, tw wo sump pu   umps, and th  he necessary y piping to route the w waste liquid to and from  m the retentionn tanks.
The Liqu storage ta in the tun The Reac consists pump, tw retention Followin liquid wa water dis Spent res quantity transferre disposal.
Followin ng processin ng and samp  pling to dem monstrate coompliance w  with the releease criteriaa, the liquid waaste from eaach system was  w then disscharged to the commoon G-3/LACBWR circullating water disscharge outfllow. This wasw the normal liquid effl  fluent releasee pathway foor LACBWR    R.
Currently discharge The air o 3.2.2.24.
Spent ressin was transsferred to thhe spent resin n receiving ttank and helld until theree was a suffi ficient quantity available for f shipmen    nt to an ap  pproved proocessing faccility. The resin was then transferreed to an ap pproved ship  pping contaiiner, dewateered, packagged and shippped for offf-site disposal.
The plan site has a buildings the stack 3.2.3.
Currently y, the liquid d waste colleection system m pumps aree not operabble. The onnly liquid efffluent dischargees at LACBW  WR are thro ough the Eastt Turbine buuilding sumpp using an aiir operated ppump.
Other com The con The Con The rack The Co The 3.3.
The air operated o          pum mp dischargees to the inlett of the liquiid waste monnitor, whichh is still operaable.
F The plan remainin se Boiling W Termination n 0 Liquid uid Waste Sy ank vault, an nnel between ctor Buildin of two reten wo sump pu n tanks.
3.2.2.24.        Electrrical Distribu ution System m The plan nt is disconneected from off-site o        poweer in supportrt of Cold annd Dark statuus. Currentlly the site has a 480 volt 50 00 kVa transsformer prov   viding poweer to multiple power carrts throughouut the buildingss. Temporarry power is tied to existing overheaad cranes annd power to exhaust fanns for the stackk.
ng processin aste from ea scharge outfl sin was trans available f ed to an ap y, the liquid es at LACBW operated pum Electr nt is disconne a 480 volt 50
3.2.3.      Additional Activitiess Other com mpleted decommissionin    ng activities include:
: s. Temporar
Thee abatement, packaging and disposaal of knownn and readilyy accessible lead and/orr lead con ntaining mateerial.
: k.
Thee abatemen  nt, packagin ng and disp   posal of knnown and rreadily acceessible Asbbestos Conntaining Maaterial (ACM  M).
Addition mpleted dec e abatement ntaining mate e abatemen ntaining Ma e placement ks from the e disconnect old and Dark e draining an Future Deco ns for the de ng site struct Water Reactor Plan d Waste Col ystem collec nd the tunne n the Reacto ng Liquid W ntion tanks, umps, and th ng and samp ach system w low. This w sferred to th for shipmen pproved ship d waste colle WR are thro mp discharge rical Distribu ected from o 00 kVa trans ry power is al Activities ommissionin
Thee placement of all spent fuel into dry y storage in tthe ISFSI faacility and thhe removal of fuel rack ks from the FESW.
, packaging erial.
Thee disconnecttion of LAC  CBWR from off-site elecctrical powerr and placinng LACBWR        R in a Coold and Dark k status.
nt, packagin aterial (ACM of all spent FESW.
Thee draining annd removal ofo other misccellaneous syystem pipingg.
tion of LAC k status.
3.3. Future F        Decommissionin    ng Activitiess and Tasks The plan ns for the decontaminatio  on, dismantllement and aanticipated eend-state condition(s) foor the remainin ng site structtures are prresented in thet followinng sections. The methoods to remeediate 3-8
nd removal o mmissionin contaminatio tures are pr r
llection Syst cts the liquid el into two st r Building a Waste System each with he necessary pling to dem was then dis was the norm he spent resin nt to an ap pping contai ection system ough the East es to the inlet ution System off-site powe sformer prov tied to exis s
ng activities and disposa ng and disp M).
fuel into dry CBWR from of other misc ng Activities on, dismantl resented in t 3-8 ems d waste from torage tanks and the Turbi m, which is s a capacity o y piping to monstrate co scharged to al liquid effl n receiving t pproved pro iner, dewate m pumps are t Turbine bu t of the liqui m
er in support viding powe ting overhea include:
al of known posal of kn y storage in t off-site elec cellaneous sy s and Tasks lement and a the followin m the Turbine (4500 gallo ine Building separate from of 6000 gall route the w ompliance w the commo fluent release tank and hel ocessing fac ered, packag e not operab uilding sump id waste mon rt of Cold an er to multipl ad cranes an n and readily nown and r the ISFSI fa ctrical power ystem piping anticipated e ng sections.
e Building, t ons and 3000
: g.
m the Liqui lons, a liqui waste liquid with the rele on G-3/LAC e pathway fo ld until there cility. The ged and ship ble. The on p using an ai nitor, which nd Dark statu e power car nd power to y accessible readily acce acility and th r and placin
: g.
end-state co The metho the WTB, th 0 gallons) lo d Waste Sy id waste tra to and from ease criteria BWR circul or LACBWR e was a suffi resin was pped for of nly liquid eff ir operated p h is still opera us. Currentl rts throughou exhaust fan lead and/or essible Asb he removal o ng LACBWR ndition(s) fo ods to reme he gas ocated
: ystem, ansfer m the a, the lating R.
ficient then ff-site fluent pump.
able.
ly the ut the ns for r lead bestos f fuel R in a or the ediate


La Crossse Boiling Water W        Reactorr License Termination T             Plan Revisionn0 contamin nated structtures, system    ms, and eq  quipment ddo not invoolve any uunique safetty or remediation issues.
La Cross License T Revision contamin remediat 3.3.1.
3.3.1.       Reactor Building B
The Reac ellipsoida and it ex for the up The build including layer of structure concrete The shel Turbine Reactor B removal closed by leaves th the north A 50 ton Reactor supported the 5-ton Hatches of the cab The rema removed and the id Systems overhead size redu the waste Water an Once the building activity w once the In prepar elevation will allow se Boiling W Termination n 0 nated struct ion issues.
The Reacctor Building is a right circular cyliinder buildinng with a heemisphericall dome and ssemi-ellipsoidaal bottom. ItI has an oveerall internall height of 1444 feet and aan inside diaameter of 600 feet, and it exxtends 26 feeet 6 inches below b       grade level. The steel shell tthickness is 1.16 inch, except for the uppper hemispherical dome, which is 0.60  0 inch thiick.
Reactor B ctor Buildin al bottom. I xtends 26 fee pper hemisp ding contain g the RPV an concrete to is supporte approximate ll includes t Building. I Building tha and dry cas y a weather he Reactor B heast quadran n traveling p Building.
The build ding containned most of the t equipmeent associateed with the nnuclear steam    m supply syystem, includingg the RPV an  nd biologicaal shielding. The interioor of the shelll is lined wiith a 9-inch--thick layer of concrete to an elevation     n of 727 feeet 10 inches Above Meaan Sea Leveel (AMSL). The structure is supporteed on a foun   ndation conssisting of cooncrete-steell piles and a pile cappinng of concrete approximateely 3 feet thiick.
d by column n hoists are a at several po bles and equ aining comp
The shelll includes two airlocks. The perso        onnel airlocck connects the Reactorr Building tto the Turbine Building. In   I addition, there is alsso an 8 feet by 10 feet freight dooor opening in the Reactor Building B        thaat is intended d to accomm modate large pieces of eqquipment. T  To facilitate RPV removal and dry cask storage, an      n opening was w created iin the Reacttor Building. The openiing is closed by y a weather tight, insulaated, roll-up,, bi-parting door. The m  majority of ppipe penetraations leaves thhe Reactor Building B          1 to o 10 feet beloow grade levvel either at the northweest quadrantt or at the northheast quadran nt and enterss the pipe tun nnel.
. Area prep dentification or compon d crane or loc uce. The sys e loading are nd sludge ar e tank has b demolition.
A 50 ton n traveling polar p      crane with w a 5 ton   n auxiliary hhoist is locaated in the uupper part oof the Reactor Building. The bridge completely spans the building annd travels on circular ttracks supported d by column ns around thee inside of th he building. The lifting cables of booth the 50-tonn and the 5-tonn hoists are also a long en    nough to reacch down thrrough hatchw  ways into thhe basement area.
will allow fo tank is prep ration for th
Hatches at several po  ositions in thhe main and intermediatte floors mayy be opened to allow passage of the cabbles and equuipment.
: n. As necess w for the per Water Reactor Plan tures, system Building g is a right It has an ove et 6 inches b herical dom ned most of t nd biologica an elevation ed on a foun ely 3 feet thi wo airlocks In addition, at is intended k storage, an tight, insula Building 1 to nt and enters polar crane w The bridge ns around the also long en ositions in th uipment.
The remaaining comp  ponents and systems s        in th he Reactor B Building willl be drainedd, dismantledd, and removed. Area prep    paration and set-up for commodity reemoval will include raddiological surrveys and the iddentificationn and mitigattion of any hazardous h           m material.
ponents and s paration and n and mitigat nents will be cal hoists. S stems will be ea in the Tur re currently been adequat Keeping as or the collect ared for dem he building sary, prior to rformance of r
Systems or compon    nents will bee removed utilizing u       meechanical m means with ssupport from  m the overhead d crane or loccal hoists. Some S      system ms or componnents might require hot w    work activitties to size reduuce. The sysstems will bee either load  ded into shippping containners or will be transportted to the wastee loading areea in the Turrbine Buildin  ng.
ms, and eq circular cyli erall internal below grade e, which is 0 the equipme al shielding.
Water an nd sludge arre currently inside the OHST.O        Thee tank will bbe dewateredd and desluddged.
n of 727 fee ndation cons ick.
Once thee tank has been b      adequattely characteerized, a fixxative will bbe applied inn preparatioon for building demolition. Keeping asssociated pip      ping and com  mponents inn place whilee performingg this activity will w allow fo  or the collecttion of any liquids.
. The perso there is als d to accomm n opening w ated, roll-up, o 10 feet belo s the pipe tun with a 5 ton completely e inside of th nough to reac he main and systems in th set-up for c tion of any h e removed u Some system e either load rbine Buildin inside the O tely characte ssociated pip tion of any l molition.
l        Thiss piping will be dismanttled and rem moved once the tank is prepared for dem    molition.
demolition, o dismantlem f hot work a 3-9 quipment d inder buildin l height of 14 level. The 0.60 inch thi ent associate The interio et 10 inches sisting of co onnel airloc so an 8 feet modate large was created i
In preparration for th he building demolition, the FESW will be dism        mantled from m the main floor elevationn. As necesssary, prior to  o dismantlem ment, the FES  SW will be ddecontaminaated to levels that will allow w for the perrformance off hot work activities a        requuired to rem move the stainnless steel F FESW 3-9
, bi-parting ow grade lev nnel.
n auxiliary h spans the he building.
ch down thr intermediat he Reactor B ommodity re hazardous m utilizing me ms or compon ded into ship ng.
OHST. The erized, a fix ping and com liquids. This the FESW ment, the FES activities requ do not invo ng with a he 44 feet and a steel shell t ick.
ed with the n or of the shel Above Mea oncrete-steel ck connects by 10 feet pieces of eq in the React door. The m vel either at hoist is loca building an The lifting rough hatchw te floors may Building wil emoval will material.
echanical m nents might pping contain e tank will b xative will b mponents in s piping wil will be dism SW will be d uired to rem olve any u emispherical an inside dia thickness is nuclear steam ll is lined wi an Sea Leve l piles and a the Reactor freight doo quipment. T tor Building majority of p the northwe ated in the u nd travels o cables of bo ways into th y be opened ll be drained include rad means with s require hot w ners or will be dewatered be applied in n place while l be dismant mantled from decontamina move the stain unique safet l dome and s ameter of 60 1.16 inch, e m supply sy ith a 9-inch-el (AMSL).
a pile cappin r Building t or opening i To facilitate
. The openi pipe penetra est quadrant upper part o n circular t oth the 50-ton he basement to allow pa d, dismantled diological sur support from work activit be transport d and deslud n preparatio e performing tled and rem m the main ated to level nless steel F ty or semi-0 feet, xcept
: ystem,
-thick The ng of to the n the RPV ing is ations t or at of the tracks n and area.
ssage d, and rveys m the ties to ted to dged.
on for g this moved floor s that FESW  


La Crossse Boiling Water W      Reactorr License Termination T               Plan Revisionn0 liner. Associated A             eqquipment (HHVAC, etc.)) and pipingg will also be removedd. Contaminnated sections of the FESW  W liner will be b size reducced using pllasma cuttingg. Sized pieeces of the FESW liner willl be lifted by y the overheead crane, packaged andd placed in tthe waste sttaging area iin the Turbine Building.
La Cross License T Revision liner. A sections liner will Turbine B will be d EnergySo Demoliti After com will be r with prop basement The r Asbe Dism Dism pipin Dism Reme The r The expo to meet t is identif method w deeper d open air process, t Once sur reach exc walls do segmente the steel sprung st Reactor B The ther packagin concrete
B          Once O      the FESW liner haas been remooved, the cooncrete underlying the F    FESW will be decontamina d            ated to the extent necessary to alllow open-airr demolitionn as specified in EnergySo  olutions Tecchnical Supp port Documeent (TSD) R    RS-TD-3131996-005, LAC    CBWR Open Air Demolitiion Limits (3  3).
: removal, loaded in the waste disposal se Boiling W Termination n 0 Associated eq of the FESW l be lifted by Building. O decontamina olutions Tec ion Limits (3 mmodity rem remediated t per contami t will includ removal of a stos Abatem mantle and re mantle and r ng as well as mantle and re ediation of th removal of a osed concret the open-air fied within t will be used depth, then a demolition.
After com mmodity rem  moval is com mplete, the basement elevvation (621 foot) of the Reactor Buiilding will be remediated r              to t levels thaat will alloww demolitionn of above gground strucctures in opeen air with prop  per contamiination contrrols per Refference 3. T    The preparattion of the R Reactor Buiilding basementt will includ  de:
then a struct rveys have cavator equi wn to grade ed and remo liner segme tructure and Building. T rmal shield ng as mixed will be rem the remain nto appropria e container site in Clive Water Reactor Plan quipment (H W liner will b y the overhe Once the FE ated to the chnical Supp 3).
The removal r         of any a identified  d Hazardouss Waste.
moval is com to levels tha ination contr de:
Asbestos Abatem  ment (to be performed by   y a qualified Subcontracttor).
any identified ment (to be p move the 6,0 emove the the auxiliary move the co he sump.
Dismmantle and remove the 6,0    000-gallon retention r         tannks.
any lead shie te will then b demolition the first coup to remove t a wire saw w If large se tural evaluat demonstrate ipped with a e level. Af ved using cu entation and d associated The remainin will be seg waste. Aft moved, comp ning portion ate container will be tran e, Utah.
Dismmantle and remove the two Forced Circulationn Pumps, inncluding thee inlet and ooutlet ng as well as the auxiliary pipin                            y oil pumps..
r HVAC, etc.)
Dismmantle and remove the co    ondensate pu urification ioon exchangerrs.
be size reduc ead crane, p SW liner ha extent nece port Docume mplete, the b at will allow rols per Ref d Hazardous erformed by 000-gallon r two Forced y oil pumps.
Remeediation of th  he sump.
ondensate pu elding.
The removal r        of any a lead shieelding.
be surveyed criteria spec ple of inche the contamin will be used ections of c tion will be c ed that the o a pneumatic fter the abo utting torche removal of ventilation ng interior c gmented usin ter the therm pletely expos of the steel rs and truck nsferred to a 3-10
The expo  osed concrette will then beb surveyed to determinne the scope of the remeddiation neceessary to meet the t open-air demolition criteria speccified in Refference 3. Iff unacceptabble contaminnation is identiffied within the t first coup  ple of inches of concrette, a scabblinng method oor air hamm mering method will w be used to remove the    t contamin  nated materiial. If the coontamination is detectedd at a deeper depth, d        then a wire saw will w be used    d to remove contaminateed areas aboove the limitts for open air demolition. If large seections of contaminatedd concrete m        must be rem moved duringg this process, then t    a structtural evaluattion will be completed.
) and piping ced using pl ackaged and as been remo ssary to all ent (TSD) R asement elev w demolition ference 3. T s Waste.
c Once surrveys have demonstrateed that the open-airo        dem molition critteria have bbeen met, a high reach exccavator equiipped with a pneumatic hammer wiill be used tto break the interior conncrete walls down to gradee level. Affter the above grade innternal steel shell is expposed, it wiill be segmenteed and removed using cu      utting torchees from the ttop down to the ground elevation. W  When the steel liner segmeentation and removal of the steel linner to the groound elevation is complete, a sprung sttructure and  d associated ventilation system willl be installeed over the remainder oof the Reactor Building.
y a qualified retention tan Circulation urification io to determin cified in Ref s of concret nated materi d to remove ontaminated completed.
B          The T remainin    ng interior concrete c        willl then be remmoved to thhe thermal shhield.
open-air dem hammer wi ve grade in es from the t the steel lin system will concrete will ng a wire s mal shield is sing the stee l liner will ed to a rail t a rail car an g will also lasma cutting d placed in t oved, the co low open-air RS-TD-31319 vation (621 n of above g The preparat Subcontract nks.
The therrmal shield will be seg    gmented usin  ng a wire ssaw into maanageable ppieces for sppecial packaginng as mixed waste. Aftter the therm      mal shield iss removed, tthe remaindder of the intterior concrete will be rem  moved, comp  pletely expossing the steeel liner. Subbsequent to interior conncrete removal, the remain    ning portion of the steell liner will be removedd. Demolitioon debris wiill be loaded innto appropriaate containerrs and trucked to a rail ttrans-load faacility in Wiinona, MN w where the wastee container will be tran    nsferred to a rail car annd then shippped to the EnergySoluutions disposal site in Clivee, Utah.
n Pumps, in on exchanger ne the scope ference 3. If te, a scabblin ial. If the co contaminate d concrete m molition crit ill be used t nternal steel top down to ner to the gro l be installe l then be rem saw into ma s removed, t el liner. Sub be removed trans-load fa nd then ship be removed
3-10
: g. Sized pie the waste st oncrete unde r demolition 96-005, LAC foot) of the ground struc tion of the R tor).
ncluding the rs.
of the remed f unacceptab ng method o ontaminatio ed areas abo must be rem teria have b to break the shell is exp the ground ound elevati ed over the moved to th anageable p the remaind bsequent to
: d. Demolitio acility in Wi pped to the
: d. Contamin eces of the F taging area i rlying the F n as specifi CBWR Ope Reactor Bui ctures in ope Reactor Bui e inlet and o diation nece ble contamin or air hamm n is detected ove the limit moved during been met, a interior con posed, it wi elevation. W on is compl remainder o he thermal sh pieces for sp der of the int interior con on debris wi inona, MN w EnergySolu nated ESW in the FESW ed in n Air ilding en air ilding outlet essary nation mering d at a ts for g this high ncrete ill be When ete, a of the hield.
pecial terior ncrete ill be where utions


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 The remaaining structural concreete outside th      he liner beloow the 636 foot elevation (i.e., conncrete bowl below b       636 fooot elevationn, concrete pile p cap and piles) will rremain and be subjectedd to a Final Rad diation Survvey (FRS) in accordance with LTP C        Chapter 5.
La Cross License T Revision The rema bowl b Final Rad 3.3.2.
3.3.2.       Turbine Building B          annd Turbine Office O      Build  ding The Turrbine Buildiing housed the steam turbine andd generator, main conddenser, elecctrical switchgear, and otheer pneumaticc, mechanicaal and hydraaulic system        ms and equippment. A 30-ton travelingg bridge cran ne with a 5 ton auxiliarry hoist cappacity spans the Turbinee Building. The crane hass access to major m       equipm ment items located l       below w the floor tthrough nummerous hatchhes in the main floor. The Turbine T        Building is 105 feet by 79 ffeet and 60 ffeet tall.
The Tur switchge traveling crane has the main The Tur laborator ventilatin services.
The Turrbine Officee Building contained c            offices, o        the Control Rooom, lockerr room facillities, laboratorry, shops, co ounting room  m, personneel change rooom, decontamination fa      facilities, heaating, ventilatin ng and air conditioning c            g equipment, rest roomss, storeroom      m, and spacee for other plant services. In generaal, these areeas were sep       parated from m power plaant equipmeent spaces. The Turbine Office O      Build ding is 110 feeet by 50 feeet and 45 feeet tall.
Turbine O Commod and mec reciproca meet pac loading a is proper After rad
Commod  dity removall has begun and will con     ntinue in thee Turbine Buuilding utilizzing cutting tools and mecchanical meeans to dism      mantle radio oactive pipinng and com    mponents. Band sawss and reciprocaating saws will w be the prrimary meth      hods used. S  System piecees and wastee will be sizzed to meet pacckaging and waste dispo      osal criteriaa. Waste wiill be packaaged and stoored in the w        waste loading area a    located on the grou  und floor in thet northwesst corner of the Turbinee Building unntil it is properrly shipped and a disposed  d of at an off-f-site facility.
: systems, specified criteria w with the of inches contamin be used t an accept Utah. A Radiation When al building and struc sequence to allow requirem The majo to be trea disposal facility i shipped se Boiling W Termination n 0 aining struc below 636 fo diation Surv Turbine B rbine Buildi ar, and othe g bridge cran s access to m floor. The T rbine Office ry, shops, co ng and air c In genera Office Build dity removal chanical me ating saws w ckaging and area located rly shipped a dioactive com component d in Referen will be remov Reactor Con s of concrete nated materi to remove c table radioac All structural n Work Perm l structural will be dem ctural concr e within the T open acces ments. Misti ority of the c ated as low l facility. Wa n Winona, to the Ene Water Reactor Plan tural concre oot elevation vey (FRS) in Building an ing housed er pneumatic ne with a 5 major equipm Turbine Bui e Building c ounting room conditioning al, these are ding is 110 fe l has begun eans to dism will be the pr waste dispo on the grou and disposed mmodity rem ts and struc ce 3 is met.
After raddioactive com mmodity rem  moval is complete, survveys will bee performed of all remaaining systems, componentts and strucctural surfacces to ensurre that the open-air deemolition crriteria specifiedd in Reference 3 is met.. Structural materials thhat do not m        meet the opeen-air demolition criteria will w be remov    ved, segregaated, properly  y packaged aand disposedd of as radiooactive wastee. As with the Reactor Con  ntainment, iff unacceptab  ble contaminnation is idenntified withiin the first coouple of inchess of concretee, a scabblin ng method or air hammeering methodd will be used to removve the contamin nated material. If the co  ontamination  n is detectedd at a deeperr depth, thenn a wire saw  w will be used tot remove contaminated    d areas. All radioactive waste will be loaded annd transportted to an accepttable radioacctive waste disposal facility, primarrily the EnerrgySolutions facility in C        Clive, Utah. All A structural decontamin    nation activitties will be performed iin accordancce with apprroved Radiation n Work Perm  mits (RWP) and under th    he oversight of Radiationn Protection personnel.
ved, segrega ntainment, if e, a scabblin al. If the co ontaminated ctive waste decontamin mits (RWP) surfaces ha molished. Al ete will be Turbine Bui ss to load o ing methods construction level radioac aste will be l MN where ergySolutions r
When all structural surfaces have been deccontaminatedd to the open-air demoolition limitss, the building will be dem molished. All remaining systems andd componentts, interior sttructural surrfaces and strucctural concrete will be demolished to the grouund level slab. The geeneral demolition sequencee within the Turbine T        Building will bee performed from the topp down and from west too east to allow open accesss to load out    o areas. Concrete w        will be proccessed to m  meet disposal site requiremments. Mistiing methodss will be utiilized duringg building ddemolition too minimize dust.
ete outside th n, concrete p accordance nd Turbine O the steam c, mechanica ton auxiliar ment items l lding is 105 contained o m, personne g equipment eas were sep eet by 50 fee and will con mantle radio rimary meth osal criteria und floor in t d of at an off-moval is co ctural surfac
The majo  ority of the construction c              debris resullting from thhe demolition of the struucture is exppected to be treaated as low level l      radioacctive waste and a will be sshipped to thhe licensed rradioactive w     waste disposal facility. Waaste will be loaded l      into appropriate a             ccontainers annd trucked too a rail transs-load facility in Winona, MN where the waste container  c          wiill be transfferred to a rrail car andd then shipped to the EneergySolutionss disposal site     s   in Clivve, Utah. If possible, some materials 3-11
. Structural ated, properly f unacceptab ng method o ontamination d areas. All disposal fac nation activit and under th ve been dec l remaining demolished lding will be out areas.
s will be uti debris resul ctive waste a loaded into a the waste c s disposal s 3-11 he liner belo pile cap and with LTP C Office Build turbine and al and hydra ry hoist cap located below feet by 79 f offices, the el change ro
, rest rooms parated from et and 45 fee ntinue in the oactive pipin hods used. S
: a. Waste wi the northwes f-site facility mplete, surv ces to ensur materials th y packaged a ble contamin r air hamme n is detected radioactive ility, primar ties will be he oversight contaminated systems and to the grou e performed Concrete w ilized during lting from th and will be s appropriate c container wi site in Cliv ow the 636 piles) will r Chapter 5.
ding d generator, aulic system pacity spans w the floor t feet and 60 f Control Ro oom, decont s, storeroom m power pla et tall.
e Turbine Bu ng and com System piece ill be packa st corner of veys will be re that the hat do not m and disposed nation is iden ering method d at a deeper waste will rily the Ener performed i of Radiation d to the op d component und level sl from the top will be proc g building d he demolitio shipped to th containers an ill be transf ve, Utah.
foot elevati remain and main cond ms and equip the Turbine through num feet tall.
oom, locker amination fa m, and space ant equipme uilding utiliz mponents.
es and waste aged and sto the Turbine e performed open-air de meet the ope d of as radio ntified withi d will be us r depth, then be loaded an rgySolutions in accordanc n Protection en-air demo ts, interior st ab. The ge p down and cessed to m demolition to n of the stru he licensed r nd trucked to ferred to a r If possible, on (i.e., con be subjected denser, elec pment. A 3 e Building.
merous hatch r room facil facilities, hea e for other ent spaces.
zing cutting Band saws e will be siz ored in the w e Building un of all rema emolition cr en-air demo oactive waste in the first co ed to remov n a wire saw nd transport facility in C ce with appr personnel.
olition limits tructural sur eneral demo from west to meet disposa o minimize ucture is exp radioactive w o a rail trans rail car and some mat ncrete d to a ctrical 0-ton The hes in
: lities, ating, plant The tools s and zed to waste ntil it aining riteria lition
: e. As ouple ve the w will ted to
: Clive, roved s, the rfaces lition o east l site dust.
pected waste s-load d then erials


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 including g structural concrete c         willl be radiologgically surveeyed and relleased for unnrestricted uuse in accordan nce with NU UREG-1575, Supplementt 1, Multi-Aggency Radiaation Surveyy and Assesssment of Materrials and Equipment Ma      anual (MAR    RSAME) (4).. Materials released forr unrestricted use can be reecycled or reeleased for disposal d          at a non-radioloogical landfill. All bulk material sennt for recycle oro disposal ata a non-radiioactive disp    posal site wiill be subjeccted to a finaal assessmennt for the preseence of any residual r         radio oactive conttamination b y undergoinng an aggregate survey bby use of a 193--6 Micro R in nstrument orr similar.
La Cross License T Revision including accordan of Mater can be re recycle o the prese of a 193-When th excavato building
When th  he Turbine Building B           hass been dem molished, thee foundationn slab will bbe exposed. An excavator with apprropriate toolls (pneumattic hammer, loading buucket, etc.) will remove the building slab and fo   oundation to meet dispo                  quirements. During slabb and founddation osal site requ removal, undergroun   nd utilities will w also be removed, r          surrveyed, packkaged and prroperly dispposed.
: removal, Some ex discharge below gr 3.3.3.
Some ex  xamples of undergroun      nd utilities might be ggas, water, miscellaneeous piping,, and dischargee line. The slab and fo    oundation walls will be removed too a minimum        m depth of 3 feet below grrade (636 foo ot elevation).
The WTB and equip level sol basement bottom w The grad steel spen the shiel piping, c facility, c condition The base gained b drums.
3.3.3.        Waste Trreatment Bu    uilding, Gass Storage Taank Vault aand LSA Stoorage Build        ding The WTB  B is locatedd to the north  heast of the Reactor Buiilding. Thee building coontained faciilities and equip  pment for decontaminat d               tion and the collection, processing, storage, andd disposal of low level sollid radioactiive waste. The WTB is 34 feet bby 42 feet aand 20 feet tall. The W                WTB basementt floor is at elevation 63  30 feet and hash a 3 foot deep sump w   with 8 inch thick walls aand a bottom which w       extendd to a depth ofo 626 feet.
exchange The Gas 14 feet h the WTB elevation compone cubic fee until such some ass The Low It was us se Boiling W Termination n 0 g structural c nce with NU rials and Eq ecycled or re or disposal a ence of any r
The grad de floor of th he WTB con     ntains a shieelded compaartment whiich houses a 320 ft3 staiinless steel spen nt resin receeiving tank and a resin receiving and transfer equuipment. Loocated outsiide of the shiellded cubiclee were two back-washab          ble radioacttive liquid wwaste filterss and dewattering piping, containers, c            and a pumps. The main floor of the WTB alsoo housed a decontaminnation facility, consisting c          off a steam cleeaning booth  h, a decontammination sinnk, and heating/ventilatioon/air condition ning units.
-6 Micro R in he Turbine B r with appr slab and fo undergroun xamples of e line. The rade (636 foo Waste Tr B is located pment for d lid radioacti t floor is at which extend de floor of th nt resin rece lded cubicle containers, a consisting of ning units.
The baseement of thee WTB conssists of two shielded cuubicles. Onee cubicle, too which acceess is gained by removal of  o floor shieeld plugs, was w used for the storage of high acttivity solid w     waste drums. The other area, a      to whicch access is gained by a stairway, contains the dewatering ion exchangeer, the WTB sump and pump,   p      and ad dditional wasste storage sspace.
ement of the y removal o The other a er, the WTB Storage Tan igh walls an B. The vaul n 617 feet.
The Gas Storage Tan    nk Vault (GS  STV) is a 29 9 foot by 31 ffoot undergrround concreete structuree with 14 feet high walls an  nd 2 feet thicck floors, waalls, and ceilling located below grounnd just outsiide of the WTB  B. The vaullt is 3 feet belowb      gradee with a sum  mp that exteends to a deepth of 22 feeet or elevationn 617 feet. The Gas Decay    D        Systeem routed m  main condeenser gases through vaarious componeents for dryiing, filtering    g, recombiniing, monitorring and hooldup for decay. Two 1,600 cubic feeet tanks are located l        in th he GSTV. Th    he tanks hadd the capabillity to store radioactive gases until suchh time that they were baatch released    d via the stacck. The tankks remain in place alongg with some asssociated pipin  ng. The rem  mainder of th he Gas Decayy system hass been removed.
ents for dryi et tanks are l h time that t sociated pipin w Specific Ac sed to store Water Reactor Plan concrete wil UREG-1575, uipment Ma eleased for d at a non-radi residual radio nstrument or Building has ropriate tool oundation to nd utilities w undergroun slab and fo ot elevation) reatment Bu d to the north decontaminat ive waste.
The Low w Specific Acctivity (LSA    A) Storage Bu  uilding is located southw west of the TTurbine Buillding.
elevation 63 d to a depth o he WTB con eiving tank a e were two and pumps.
It was ussed to store processed, packaged an        nd sealed loow level dryy active wasste materialss, and 3-12
f a steam cle e WTB cons of floor shie area, to whic sump and p nk Vault (GS nd 2 feet thic lt is 3 feet b The Gas D ing, filtering located in th hey were ba ng. The rem ctivity (LSA processed, r
ll be radiolog Supplement anual (MAR disposal at a ioactive disp oactive cont r similar.
s been dem ls (pneumat meet dispo will also be r nd utilities oundation w uilding, Gas heast of the tion and the The WTB 30 feet and h of 626 feet.
ntains a shie and resin re back-washab The main eaning booth sists of two eld plugs, w ch access is pump, and ad STV) is a 29 ck floors, wa below grade Decay Syste g, recombini he GSTV. Th atch released mainder of th A) Storage Bu packaged an 3-12 gically surve t 1, Multi-Ag RSAME) (4).
non-radiolo posal site wi tamination b molished, the tic hammer, osal site requ removed, sur might be g alls will be s Storage Ta Reactor Bui collection, is 34 feet b has a 3 foot elded compa ceiving and ble radioact floor of th h, a decontam shielded cu was used for gained by dditional was 9 foot by 31 f alls, and ceil e with a sum em routed m ing, monitor he tanks had d via the stac he Gas Decay uilding is lo nd sealed lo eyed and rel gency Radia
. Materials ogical landfi ill be subjec y undergoin e foundation loading bu quirements.
rveyed, pack gas, water, removed to ank Vault a ilding. The processing, by 42 feet a deep sump w artment whi transfer equ tive liquid w e WTB also mination sin ubicles. One the storage a stairway, ste storage s foot undergr ling located mp that exte main conde ring and ho d the capabil ck. The tank y system has cated southw ow level dry leased for un ation Survey released for ll. All bulk cted to a fina ng an aggreg n slab will b ucket, etc.)
During slab kaged and pr miscellane o a minimum and LSA Sto e building co storage, and and 20 feet with 8 inch ich houses a uipment. Lo waste filters o housed a nk, and heati e cubicle, to of high act contains th space.
round concre below groun ends to a de enser gases oldup for de lity to store ks remain in s been remo west of the T y active was nrestricted u y and Assess r unrestricte material sen al assessmen ate survey b be exposed.
will remov b and found roperly disp eous piping, m depth of 3 orage Build ontained faci d disposal o tall. The W thick walls a a 320 ft3 stai ocated outsi s and dewat decontamin ng/ventilatio o which acce tivity solid w e dewaterin ete structure nd just outsi epth of 22 fe through va cay. Two radioactive place along ved.
Turbine Buil ste materials use in sment d use nt for nt for by use An e the dation posed.  
, and 3 feet ding ilities f low WTB and a inless ide of tering nation on/air ess is waste g ion e with ide of eet or arious 1,600 gases g with lding.
s, and  


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 sealed loow level actiivity compon  nents. No liiquid wastess were stored in this buiilding. The LSA Building is 27 feet by y 80 feet and d 15 feet talll.
La Cross License T Revision sealed lo Building Commod utilizing Band saw be cleane be sized waste loa site facili After com open air demolitio If unacc scabbling the conta contamin radioactiv When all above gr the concr GSTV lo with Cha will be u from the will be s appropria container Clive, Ut 3.3.4.
Commod  dity removal has begun      n and will continue inn the WTB,, GSTV and LSA Buiilding utilizing cutting toolls and mech  hanical mean  ns to dismanntle radioacttive piping and componnents.
The LAC plant. T cooling w diesel-dr circulatin In additio facility, a Radiolog interior a that the s se Boiling W Termination n 0 ow level acti is 27 feet by dity remova cutting tool ws and recip ed and a fixa to meet pack ading area in ity.
Band saw ws and recip procating saw ws will be th he primary m  methods usedd. The interriors of tankss will be cleaneed and a fixaative will bee applied priior to dismaantlement. S      System piecees and wastee will be sized to meet pack  kaging and waste w     dispossal criteria. W Waste will bbe packaged and stored iin the waste loaading area in n the Turbinne Building until u    it is prooperly shippped and dispoosed of at ann off-site faciliity.
mmodity rem demolition c on criteria w eptable con g method or amination is nated areas.
After com mmodity rem  moval is com   mplete, the interior conncrete surfacces will be rremediated tto the open air demolition criteria c      per Reference R           3. Structural material thaat does not m  meet the opeen-air demolitio on criteria will w be remov     ved, segregaated, packagged and dispoosed of as radioactive w  waste.
ve waste dis l structural rade portions rete floor sl ocated below apter 5. Con utilized durin demolition shipped to th ate container r will be tran tah.
If unacceptable con  ntamination is identified    d within thee first coupple of inchees of concreete, a scabbling g method or air hammeriing method will   w be usedd to remove tthe contaminnated material. If the contaamination iss detected at    a a deeper depth, thenn a wire saaw will be used to rem          move contamin nated areas. All radioaactive wastee will be looaded and ttransported to an accepptable radioactiv ve waste dissposal facilitty.
LACBWR CBWR Crib The structure water to var iven high p ng water pum on to the G-3 and consequ gical surveys and exterior structure can Water Reactor Plan ivity compon y 80 feet and l has begun ls and mech procating saw ative will be kaging and w n the Turbin moval is com criteria per R will be remov ntamination air hammeri s detected a All radioa sposal facilit surfaces hav s of each bu lab will be r w 636 foot e ncrete will be ng building of each of he licensed rs and truck nsferred to a R Crib Hou b House is lo e served as rious LACB pressure serv mps. The LA 3 Crib Hous uently, will r s, either FSS structural su n be released r
When alll structural surfaces hav    ve been decontaminatedd to the open-air demollition criteriaa, the above grrade portionss of each bu  uilding will be b demolishhed. The enntire LSA buuilding, incluuding the concrrete floor sllab will be removed.
nents. No li d 15 feet tall n and will hanical mean ws will be th e applied pri waste dispos ne Building u mplete, the Reference 3 ved, segrega is identified ing method w at a deeper active waste ty.
r          The T remaininng structuraal concrete ffor the WTB      B and GSTV lo  ocated beloww 636 foot elevation e         will remain annd be subjeccted to a FR    RS in accorddance with Chaapter 5. Con  ncrete will bee processed to t meet dispposal site reqquirements. Misting metthods will be utilized u        durinng building demolition to minimizee dust. All constructionn debris resuulting from the demolition of each of the structuree will be treeated as low        w-level radiooactive wastee and will be shipped s        to thhe licensed radioactive waste dispoosal facility.. Waste wiill be loadedd into appropriaate containerrs and truck  ked to a rail trans-load ffacility in W  Winona, MN where the w    waste containerr will be trannsferred to a rail car and d then shippeed to the EneergySolutionns disposal ssite in Clive, Uttah.
ve been dec uilding will b removed. T elevation wi e processed t demolition the structure radioactive ked to a rail a rail car and use ocated on th the intake BWR plant vice water p ACBWR Cri e, the LACB remain intac S or MARSA urface and sy d for unrestric 3-13 iquid wastes
3.3.4.        LACBWR    R Crib Hou  use The LAC  CBWR Crib  b House is lo  ocated on th he bank of tthe Mississiippi River too the west oof the plant. The T structuree served as the intake for the Circculating Waater System, which provvided cooling water w    to varrious LACB  BWR plant systems. T        The LACBW    WR Crib Hoouse containns the diesel-driven high pressure p          servvice water pumps, p         low pressure seervice waterr pumps and the circulatinng water pummps. The LA    ACBWR Criib House is 335 feet by 455 feet and 155 feet tall.
: l.
In additioon to the G-33 Crib House, the LACB    BWR Crib H    House also cuurrently servves the activee G-3 facility, and a consequ  uently, will remain r      intacct and undistturbed by thhe decommissioning proocess.
continue in ns to disman he primary m ior to disma sal criteria. W until it is pro interior con
Radiolog gical surveyss, either FSS  S or MARSA    AME free reelease surveeys will be pperformed oon the interior and a exterior structural su    urface and sy  ystems of thhe LACBWR    R Crib Housse to demonstrate that the structure s          can n be releasedd for unrestriccted use.
. Structural ated, packag d within the will be used depth, then e will be lo ontaminated be demolish The remainin ll remain an to meet disp to minimize e will be tre waste dispo trans-load f d then shippe he bank of t for the Circ systems. T pumps, low ib House is 3 BWR Crib H ct and undist AME free re ystems of th cted use.
3-13
s were store n the WTB, ntle radioact methods used antlement. S Waste will b operly shipp ncrete surfac material tha ged and dispo e first coup d to remove t n a wire sa oaded and t d to the ope hed. The en ng structura nd be subjec posal site req e dust. All eated as low osal facility.
facility in W ed to the Ene the Mississi culating Wa The LACBW pressure se 35 feet by 45 House also cu turbed by th elease surve he LACBWR d in this bui
, GSTV an tive piping
: d. The inter System piece be packaged ped and dispo ces will be r at does not m osed of as r ple of inche the contamin aw will be transported n-air demol ntire LSA bu al concrete f cted to a FR quirements.
construction w-level radio
. Waste wi Winona, MN ergySolution ippi River to ater System, WR Crib Ho ervice water 5 feet and 15 urrently serv he decommi eys will be p R Crib Hous ilding. The d LSA Bui and compon riors of tanks es and waste and stored i osed of at an remediated t meet the ope adioactive w es of concre nated materi used to rem to an accep lition criteria uilding, inclu for the WTB RS in accord Misting met n debris resu oactive waste ill be loaded where the w ns disposal s o the west o which prov ouse contain r pumps an 5 feet tall.
ves the active ssioning pro performed o se to demon LSA ilding nents.
s will e will in the n off-to the en-air waste.
ete, a al. If move ptable a, the uding B and dance thods ulting e and d into waste site in of the vided ns the d the e G-3 ocess.
on the strate


La Crossse Boiling Water W        Reactorr License Termination T               Plan Revision n0 3.3.5.       Maintena  ance Eat Sh hack and 1B B Diesel Gen  nerator Buillding The Maiintenance Eaat Shack is a 20 feet by 40 feet annd 15 feet tall steel-sidded building with windowss constructed  d over a conccrete slab.
La Cross License T Revision 3.3.5.
The 1B Diesel D        Generrator Buildin ng is attached d to the souttheast cornerr of the Turbbine Buildingg and contains the Electrical Equipmen    nt Room, Diiesel Generaator Room, aand an emptty Battery R       Room.
The Mai windows The 1B D contains The build shaped h These tw including these stru radioactiv to a rail t car and t materials unrestrict recycled or dispos presence a 193-6 M 3.3.6.
The build  ding is consstructed of concrete c        block and steell beams andd braces. Thhe building is L-shaped having largesst dimensions of 31 feet by  b 38 feet annd 13 feet taall.
The LAC an outsid 15 inches cluster of sides on t The Ven Once ch demolitio fixative w Demoliti system w removed of the v excavato the interi the concr methods and barr resulting and will appropria se Boiling W Termination n 0 Maintena intenance Ea s constructed Diesel Gener the Electric ding is cons aving larges wo structure g the concre uctures will ve waste dis trans-load fa then shipped s, including ted use in ac or released sal at a non of any resid Micro R inst Ventilatio CBWR Vent de diameter s at the bott f 78 piles. T the southeas ntilation Sta aracterizatio on criteria p will be appli ion will be will be emp using mech ventilation s rs will saw ior of stack.
These tw wo structurees will be radiologicall r          ly characterrized and thhen completely demoliished, including g the concreete foundatio  on slabs. Construction C              debris resullting from tthe demolitioon of these struuctures will be treated ass low-level radioactive r            wwaste and wwill be shippeed to the liceensed radioactiv ve waste dissposal facilitty. Waste wiill be loadedd into approppriate contaiiners and truucked to a rail trans-load t          faacility in Winnona, MN where w      the waaste containeer will be traansferred to a rail car and then t    shipped d to the EnergySolution  ns disposal site in Clivve, Utah. IIf possible, some materialss, including  g structural concrete willw be raddiologically surveyed aand releasedd for unrestrictted use in acccordance with w MARSA     AME. Mate rials releaseed for unresttricted use caan be recycled or released for disposal at a non-rad   diological laandfill. All bbulk materiaal sent for reecycle or dispossal at a non  n-radioactivee disposal site will be subjected too a final asssessment foor the presence of any resid  dual radioacttive contamiination by unundergoing aan aggregate survey by uuse of a 193-6 Micro M      R insttrument or siimilar.
rete debris.
3.3.6.      Ventilatio on Stack The LAC  CBWR Venttilation Stack is a 350 feet  fe high, tappered, reinfoorced concreete structuree with an outsidde diameter of 7 feet at the top and 25 feet at thhe base. Thhe wall thickkness varies from 15 inchess at the botttom to 6 incches at the to  op. The 4 ffeet thick fooundation mat rests on a pile cluster off 78 piles. The T foundation mat is 40   0 foot squaree concrete baase formed w  without trianngular sides on the t southeasst and southw  west corners.
will be utili icade the fa from the de be shipped t ate container Water Reactor Plan ance Eat Sh at Shack is d over a conc rator Buildin al Equipmen structed of c st dimension es will be r ete foundatio be treated as sposal facilit acility in Win d to the En g structural ccordance w for disposal n-radioactive dual radioact trument or si on Stack tilation Stac of 7 feet at tom to 6 inc The foundati st and southw ack will be on is compl per Referenc ed to the ide performed f ployed to pr hanical hand stack will b and break th An opening The concret ized during all zones in emolition of to the licens rs and truck r
The Ven  ntilation Staack will be radiologicallly characterrized and thhen compleetely demoliished.
hack and 1B a 20 feet b crete slab.
Once characterizatio  on is complete, interiorr concrete suurfaces willl be remediiated to opeen air demolitio on criteria per p Referencce 3 and dem    molished. IIf remediatioon is not prracticable, thhen a fixative will w be applied to the ideentified surfaaces to mitiggate any loosse contaminaation.
ng is attached nt Room, Di concrete blo s of 31 feet b radiologicall on slabs. C s low-level r ty. Waste wi nona, MN w ergySolution concrete w with MARSA at a non-rad e disposal s tive contami imilar.
Demolitiion will be performed from    f     the top p down. Itt is anticipat ated that a trraveling scaaffold system will w be emp      ployed to prrovide accesss to the exxterior of thhe stack. T    The stack wiill be removed using mech    hanical hand d tools down n to the loweer 40 foot ellevation. Thhe bottom 400 feet of the ventilation v              stack s      will be b removed  d with excaavators and pneumatic breakers. The excavators will saw and break th     he concrete into manageeable sectionns and drop the sectionss into the interiior of stack. An opening  g at the botto om of the staack will be m made to alloow the removval of the concrrete debris. The concrette foundation    n mat will bee taken downn to 3 feet bbelow grade. Wet methods will be utiliized during all demolition to minim      mize dust. P  Project persoonal will moonitor and barricade the faall zones in the vicinity    y of the venntilation staack. All construction ddebris resulting from the deemolition off these strucctures will bbe treated ass low-level rradioactive w     waste and will be shipped to t the licensed radioactiv ve waste dissposal facilitty. Waste w will be loadedd into appropriaate containerrs and truck  ked to a rail trans-load ffacility in W Winona, MN where the w      waste 3-14
k is a 350 fe the top and ches at the to on mat is 40 west corners radiological ete, interior ce 3 and dem entified surfa from the top rovide acces d tools down be removed he concrete g at the botto te foundation all demoliti the vicinity f these struc ed radioactiv ked to a rail 3-14 B Diesel Gen y 40 feet an d to the sout iesel Genera ck and steel by 38 feet an ly character Construction radioactive w ill be loaded where the wa ns disposal will be rad AME. Mate diological la ite will be ination by un feet high, tap 25 feet at th op. The 4 f 0 foot square lly character r concrete su molished. I aces to mitig p down. It ss to the ex n to the lowe d with exca into manage om of the sta n mat will be on to minim y of the ven ctures will b ve waste dis trans-load f nerator Buil nd 15 feet t theast corner ator Room, a l beams and nd 13 feet ta rized and th debris resul waste and w d into approp aste containe site in Cliv diologically rials release andfill. All b subjected to undergoing a pered, reinfo he base. Th feet thick fo e concrete ba rized and th urfaces will If remediatio gate any loos t is anticipat xterior of th er 40 foot el avators and eable section ack will be m e taken down mize dust. P ntilation sta be treated as sposal facilit facility in W lding all steel-sid r of the Turb and an empt d braces. Th all.
hen comple lting from t will be shippe priate contai er will be tra ve, Utah. I surveyed a ed for unrest bulk materia o a final as an aggregate orced concre he wall thick oundation m ase formed w hen comple l be remedi on is not pr se contamina ated that a tr he stack. T levation. Th pneumatic ns and drop made to allo n to 3 feet b Project perso ack. All co s low-level r ty. Waste w Winona, MN ded building bine Building ty Battery R he building tely demoli the demolitio ed to the lice iners and tru ansferred to If possible, and released tricted use ca al sent for re ssessment fo survey by u ete structure kness varies at rests on a without trian etely demoli iated to ope racticable, th ation.
raveling sca The stack wi he bottom 40 breakers.
the sections ow the remov below grade.
onal will mo nstruction d radioactive w will be loaded where the w with g and Room.
is L-
: ished, on of ensed ucked a rail some d for an be ecycle or the use of e with from a pile ngular ished.
en air hen a affold ill be 0 feet The s into val of Wet onitor debris waste d into waste  


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 containerr will be trannsferred to a rail car andd then shippeed to the EneergySolutionns disposal ssite in Clive, Uttah.
La Cross License T Revision container Clive, Ut 3.3.7.
3.3.7.       Legacy Waste W
Approxim LACBW roads ins removal will be pr 3.4.
Approxim  mately 75 cu ubic yards of stockpileed deconstruuction debriis is stored inside the south LACBW  WR Site Encllosure (LSE    E) fence linee. The debbris consistinng of asphaalt removed from roads insside the LS  SE, the undeerlayment sand from thhe roads annd concrete debris from          m the removal of part of a wall in thee Turbine Bu      uilding. Alll of the stocckpiled decoonstruction ddebris will be prrocessed as low-level raadioactive waaste during ddecommissiooning.
R The deco Solutions programs Solutions sufficient accordan Standard Reasonab controls radioactiv written p The curr Effluent Manual the vario are routi the publi also impo waste ma and outa procedu D-Plan/P environm No alte Rad Dec a po Continue Monitori and 10 C se Boiling W Termination n 0 r will be tran tah.
3.4. Radiological R            l Impacts off Decommisssioning Act ivities The deco  ommissionin  ng activities described arre and will bbe conductedd under the provisions oof the Solutionss Radiation Protection Program P         andd Radioactivve Waste M  Management Program. T    These programss are and willw continue to be impleemented as described in the D-Plaan/PSDAR. The Solutionss Radiation Protection Program an      nd written ssite proceduures are inteended to proovide sufficientt informatio on to demon   nstrate that decommisssioning activvities will bbe performeed in accordan nce with 10  0 CFR 19, Notices, N         Insstructions A And Reportss To Workkers, 10 CFR      R 20, Standard  ds For Proteection Again   nst Radiatioon and to m maintain radiation exposuures As Low    w As Reasonab  bly Achievaable (ALAR   RA) The Solutions Raadioactive W      Waste Manaagement Proogram controls the generaation, characterization, processing,, handling, shipping, and disposaal of radioactiv ve waste in accordance with the app    proved Soluutions Radiattion Protectiion Program m, and written plant p      proceduures.
Legacy W mately 75 cu WR Site Encl side the LS of part of a rocessed as Radiological ommissionin s Radiation s are and w s Radiation t informatio nce with 10 ds For Prote bly Achieva the genera ve waste in plant procedu rent Radiati Monitoring (ODCM) (5 ous decontam inely inspec ic, and the e ortant to not anagement c ages, and de ures for wh PSDAR, the mental impac site-specifi er the conclu diation dose commission ositive envir ed applicatio ng Program CFR 50, App Water Reactor Plan nsferred to a Waste ubic yards losure (LSE SE, the unde a wall in the low-level ra l Impacts of ng activities Protection P will continue Protection on to demon 0 CFR 19, N ection Again able (ALAR ation, chara accordance ures.
The currrent Radiatiion Protection Program      m, Waste M  Management Program, aand Radioloogical Effluent Monitoring    g and Radiiological Eff  ffluent Mon itoring andd Offsite D  Dose Calcullation Manual (ODCM) (5      5) will be ussed to protect the workeers and the public, as aapplicable, dduring the varioous decontam mination and d decommisssioning activvities. These well-estabblished proggrams are routiinely inspeccted by the Nuclear Reg      gulatory Com mmission (NNRC) to enssure that worrkers, the publiic, and the environment e            t are protectted during faacility decom mmissioningg activities. It is also impo  ortant to notte that decom mmissioning  g activities innvolve the same radiatioon protectionn and waste maanagement consideratio c          ons as those encountereed during plant operatioons, maintennance and outaages, and deecommission      ning activities conducteed to date. There aree no additiional procedu  ures for wh    hich appro  oval is bein  ng sought in this L TP. As ddescribed inn the D-Plan/P PSDAR, thee decommissioning wiill be accoomplished w              with no siggnificant addverse environm mental impaccts in that:
ion Protecti g and Radi
No site-specifiic factors peertaining to the decomm      missioning of the LAC CBWR woulld alteer the concluusions presented in NUR  REG-0586 (ssee LTP Chaapter 8).
: 5) will be us mination and cted by the environment te that decom consideratio ecommission hich appro e decommi cts in that:
Rad diation dose to the public will be min nimal.
ic factors pe usions prese to the publi ing is not a ronmental im on of the cur ms at LACB pendix I. Ra r
Deccommissioning is not an  a imminentt health or ssafety conceern and willl generally have a poositive envirronmental immpact.
a rail car and of stockpile E) fence line erlayment s e Turbine Bu adioactive wa f Decommiss described ar Program and to be imple Program an nstrate that Notices, Ins nst Radiatio RA) The S cterization, with the app on Program iological Eff sed to prote d decommiss Nuclear Reg t are protect mmissioning ons as those ning activiti oval is bein ssioning wi ertaining to nted in NUR c will be min an imminent mpact.
Continueed applicatio  on of the currrent and fuuture Radiatiion Protectioon and Radiiological Efffluent Monitoring Program    ms at LACB  BWR ensures public prootection in accordance with 10 CF         FR 20 and 10 CFR C 50, App    pendix I. Raadiological Environment E              tal Monitoriing Program m (REMP) reeports 3-15
rrent and fu BWR ensure adiological E 3-15 d then shippe ed deconstru
: e. The deb and from th uilding. All aste during d sioning Act re and will b d Radioactiv emented as nd written s decommiss structions A on and to m olutions Ra processing, proved Solu m, Waste M ffluent Mon ct the worke sioning activ gulatory Com ted during fa g activities in encountere es conducte ng sought ill be acco the decomm REG-0586 (s nimal.
t health or s uture Radiati s public pro Environment ed to the Ene uction debri bris consistin he roads an l of the stoc decommissio ivities be conducted ve Waste M described i site procedu sioning activ And Reports maintain radi adioactive W
, handling, utions Radiat Management itoring and ers and the vities. Thes mmission (N acility decom nvolve the s ed during pl ed to date.
in this L omplished w missioning see LTP Cha safety conce ion Protectio otection in tal Monitori ergySolution is is stored ng of aspha nd concrete ckpiled deco oning.
d under the Management n the D-Pla ures are inte vities will b s To Work ation exposu Waste Mana
: shipping, tion Protecti Program, a d Offsite D public, as a e well-estab NRC) to ens mmissioning ame radiatio ant operatio There are TP. As d with no sig of the LAC apter 8).
ern and wil on and Radi accordance ing Program ns disposal s inside the alt removed debris from onstruction d provisions o Program. T an/PSDAR.
ended to pro be performe kers, 10 CFR ures As Low agement Pro and disposa ion Program and Radiolo Dose Calcul applicable, d blished prog sure that wor g activities.
on protection ons, mainten e no additi described in gnificant ad CBWR woul ll generally iological Eff with 10 CF m (REMP) re site in south from m the debris of the These The ovide ed in R 20, w As ogram al of m, and ogical lation during grams
: rkers, It is n and nance ional n the dverse ld have fluent FR 20 eports


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 for LAC CBWR to date  d    concludde that the public expposure as a result of ddecommissiooning activitiess is bounded by the evalu uation in NUUREG-0586,, which conccludes the im  mpact is miniimal.
La Cross License T Revision for LAC activities 3.4.1.
3.4.1.       Control Mechanisms M             s to Mitigatte the Recon ntaminationn of Remediiated Areas Due to thet large sco ope of remaaining structtures and syystems that will be deccontaminatedd and dismantleed, FRS off areas may      y be perforrmed in parrallel with decommissiioning activvities.
Due to t dismantle Consequ remediat radiologi specified described 3.4.2.
Consequently, a sysstematic app    proach will be employyed to ensuure that areaas are adequuately remediated prior to performing p           FRS F    and on ngoing decom mmissioningg activities ddo not impacct the radiologiical conditio on of areass where compliance w      with the unrrestricted reelease criterria as specifiedd in 10 CFR R 20.1402 haas been dem    monstrated. These meeasures and mechanism      ms are described d in LTP Chapter 5.
Table 3-2 This dos Exposure informati for remai Decomm Asb Rea Wa Tur Rem Wa Tot 3.4.3.
3.4.2.        Occupatiional Exposure Table 3-2 2 provides the t cumulatiive site dosee estimates for the decoommissioninng of LACB      BWR.
Continue Effluent public pr se Boiling W Termination n 0 CBWR to d s is bounded Control M the large sco ed, FRS of ently, a sys ed prior to p ical conditio d in 10 CFR d in LTP Ch Occupati 2 provides t se estimate e Projection ion gathered ining decom Table 3-missioning A bestos and ot actor Buildin aste Treatmen rbine Buildin maining Stru aste Processin tal for Deco Exposure ed applicatio Technical S rotection in a Water Reactor Plan date conclud by the evalu Mechanisms ope of rema f areas may stematic app performing F on of areas R 20.1402 ha apter 5.
This dosse estimate is documen     nted in EneergySolutionns TSD RS    S-TD-3131966-007, Radiiation Exposuree Projection  ns for LACB  BWR Decom    mmissioning (6). This iinformation is in addition to informatiion gathered  d for reportiing of yearlly site dosee. The totall radiation eexposure estiimate for remaiining decom mmissioning activities a        is estimated e         too be approxim mately 130.33 person-remm.
ional Expos the cumulati is documen ns for LACB d for reporti mmissioning a
Table 3--2    Radiiation Expossure Projecctions for Deecommissioning Expoosure Acttivity (person n-rem)
-2 Radi Act Activity ther Hazardo ng nt Building ng uctures ng (includes ommissionin e to the Pub on of Solut Specification accordance w r
Decomm  missioning Activity A
de that the uation in NU s to Mitigat aining struct y be perfor proach will FRS and on s where co as been dem ure ive site dose nted in Ene BWR Decom ing of yearl activities is e iation Expos tivity ous Material s shipping an ng Activities blic tions Radia n and Radio with 10 CFR 3-16 public exp UREG-0586, te the Recon tures and sy rmed in par be employ ngoing decom mpliance w monstrated.
Asb bestos and otther Hazardo ous Materiall Abatementt                        188.6 Reaactor Buildin ng                                                            811.4 Waaste Treatmen  nt Building                                                  9.6 Turrbine Buildin ng                                                            1.6 Rem maining Struuctures                                                        0.8 Waaste Processin  ng (includess shipping annd prep)                            188.2 Tottal for Deco ommissionin  ng Activitiess                                  1300.3 3.4.3.       Exposuree to the Pub blic Continueed applicatio  on of Soluttions Radiaation Protecction, Radiooactive Wasste, Radioloogical Effluent Technical Specification S          n and Radio  ological Envvironmental Monitoring Program asssures public prrotection in accordance a            with w 10 CFR    R 20 and 10 C  CFR 50, Apppendix I.
e estimates ergySolution mmissioning ly site dose estimated to sure Projec l Abatement nd prep) s ation Protec ological Env R 20 and 10 C posure as a
3-16
, which conc ntamination ystems that rallel with yed to ensu mmissioning with the unr These me for the deco ns TSD RS (6). This i
: e. The total o be approxim ctions for De t
ction, Radio vironmental CFR 50, App result of d cludes the im n of Remedi will be dec decommissi ure that area g activities d restricted re easures and ommissionin S-TD-313196 information l radiation e mately 130.3 ecommissio Expo (person 18 81 9
1 0
18 130 oactive Was Monitoring pendix I.
decommissio mpact is mini iated Areas contaminated ioning activ as are adequ do not impac elease criter mechanism ng of LACB 6-007, Radi is in additi exposure esti 3 person-rem ning osure n-rem) 8.6 1.4  
.6  
.6  
.8 8.2 0.3 ste, Radiolo Program as oning imal.
d and vities.
uately ct the ria as ms are BWR.
iation on to imate
: m.
ogical ssures


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revisionn0 3.4.4.       Radioacttive Waste Projections P
La Cross License T Revision 3.4.4.
The Radiioactive Waste Managem      ment Program is used too control the characterizaation, generaation, processinng, handling  g, shipping, and dispossal of radiooactive wastte during ddecommissiooning.
The Radi processin Activated low leve of waste Con Use Exp Exp Con Con Table 3-3 the deco referred t total volu feet. Ac be shippe WA Debri Deb Deb A
Activatedd and contam  minated systtems, structu  ures, and commponents reppresent the llargest volum  me of low leveel radioactive waste exp    pected to bee generated during decoommissioninng. Other fforms of waste generated du  uring decommmissioning include:
A Dry A
Conntaminated water; w
Useed disposablle protective clothing; pended abrasive and abssorbent materials; Exp Exp pended resin ns and filterss; Conntamination control materials (e.g., strippable s        cooatings, plasttic enclosurees); and Conntaminated equipment e          used u    in the deecommissionning processs.
Table 3-33 provides projections p            of o waste classifications and quantitiies that will be generateed by the decommissioning    g of LACBWR. As Solutions S          hass elected to use an appproach comm      monly referred to t as rip & ship versees performin    ng significannt on-site deecontaminatiion activitiess, the total voluume of low w-level radio oactive wastee for dispossal has beenn estimated at 393,696 cubic feet. Acctual waste volumes v        and d classificatiions may vaary. The vasst majority oof this wastee will be shippeed to the liceensed Energy  ySolutions raadioactive wwaste disposaal facility in Clive, Utahh.
Table 3-3        Proojected Wasste Quantitiies WA ASTE              PACK  KING              WASTE WASTE  E WASTE TYPE                              WE EIGHT              DENS  SITY            VOLUME    E CLASS  S (llbs.)              (lb./fft3)                  3 (ft )
Debriis: Concrete          A              20,0026,177                855                235,603 Debbris: Rebar          A                88 89,249                  855                  10,463 Debbris: Metal          A              1,8227,476                300                  60,916 Asphalt A                    A                54 41,575                  500                  10,832 Soils              A              2,87777,268                744                  38,882 Asbestos A                     A                30 00,776                  177                  17,693 Dry Active A        Wastee A                 30 0,880                  122                  2,574 (DAW)
(
(
Mixxed Waste           A                 56 6,222                 1100                  16,733 Totall Estimated V Volume           393,696 3-17
Mix se Boiling W Termination n 0 Radioact ioactive Wa ng, handling d and contam el radioactiv generated du ntaminated w ed disposabl pended abra pended resin ntamination ntaminated e 3 provides p mmissioning to as rip &
ume of low ctual waste v ed to the lice STE TYPE is: Concrete bris: Rebar bris: Metal Asphalt Soils Asbestos Active Waste (DAW) xed Waste Water Reactor Plan tive Waste P ste Managem g, shipping, minated syst e waste exp uring decom water; le protective sive and abs ns and filters control mat equipment u projections o g of LACB
& ship verse w-level radio volumes and ensed Energy Table WASTE CLASS A
A A
A A
A e
A A
r Projections ment Progra and dispos tems, structu pected to be mmissioning clothing; sorbent mate s;
erials (e.g., s used in the de of waste cla WR. As S es performin oactive waste d classificati ySolutions ra 3-3 Pro E
S WA WE (l
20,0 88 1,82 54 2,87 30 30 56 3-17 m is used to sal of radio ures, and com e generated include:
rials; strippable co ecommission ssifications Solutions has ng significan e for dispos ions may va adioactive w ojected Was ASTE EIGHT lbs.)
026,177 89,249 27,476 41,575 777,268 00,776 0,880 6,222 Total o control the oactive wast mponents rep during deco oatings, plast ning process and quantiti s elected to nt on-site de sal has been ary. The vas waste disposa ste Quantiti PACK DENS (lb./f 85 85 30 50 74 17 12 110 l Estimated V characteriza te during d present the l ommissionin tic enclosure
: s.
ies that will use an app econtaminati n estimated st majority o al facility in ies KING SITY ft3) 5 5
0 0
4 7
2 0
Volume ation, genera decommissio largest volum ng. Other f es); and be generate proach comm ion activities at 393,696 of this waste Clive, Utah WASTE VOLUME (ft3) 235,603 10,463 60,916 10,832 38,882 17,693 2,574 16,733 393,696
: ation, oning.
me of forms ed by monly s, the cubic e will
: h.
E


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 Table 3-33 Continu  ued WA ASTE              PACK  KING            WASTE WASTE  E WASTE TYPE                              WE EIGHT              DENS  SITY          VOLUME  E CLASS S (llbs.)              (lb./fft3)            (ft3)
La Cross License T Revision WA Clean (Debri Clea D
Cleann Backfill -       Clean 19,7747,211                755              263,297 (Debriis to Landfilll)    Debris Cleaan Asphalt         Clean 4,874,175                  500              97,484 Disposal D                    Debris Scrap Recycle - Metals                         1,803,064                  200              90,154 Metal Scrap Recyycle - Rebar                           95 54,659                  300              31,822 Metal Totall Estimated V Volume        482,757 3.4.5.      Project Milestones M
Recy Recy 3.4.5.
Table 3-4 4 lists the cu urrent schedu ule for the reemaining deccommissioniing activitiess.
Table 3-4 Date Q2/201 Q2/201 Q2/201 Q3/201 Q3/201 Q3/201 Q4/201 Q4/201 Q4/201 Q4/201 se Boiling W Termination n 0 STE TYPE n Backfill -
Tablee 3-4       Geeneral Projeect Mileston  nes Date                  Milestonee Q2/20116              Submit LT TP to NRC Q2/20116              License Transfer Com   mplete Q2/20116              Mobilizatiion Complette Q3/20116              Stack Dem molition Com mplete Q3/20117              LTP Apprroval by NRC Q3/20117              Componen  nt Removal Complete Q4/20117              Building Demolition D            Complete C
is to Landfill an Asphalt Disposal cle - Metals ycle - Rebar Project M 4 lists the cu 16 16 16 16 17 17 17 18 18 18 Water Reactor Plan WASTE CLASS l)
Q4/20118              Transportaation and Diisposal Com mplete Q4/20118              Site Remeediation Com mplete Q4/20118              FRS Com mplete 3-18
Clean Debris Clean Debris Scrap Metal Scrap Metal Milestones urrent schedu Table Milestone Submit LT License T Mobilizati Stack Dem LTP Appr Componen Building D Transporta Site Reme FRS Com r
Table 3 E
S WA WE (l
19,7 4,8 1,8 95 ule for the re e 3-4 Ge e
TP to NRC ransfer Com ion Complet molition Com roval by NR nt Removal Demolition C ation and Di ediation Com mplete 3-18 3-3 Continu ASTE EIGHT lbs.)
747,211 74,175 03,064 54,659 Total emaining dec eneral Proje mplete te mplete C
Complete Complete isposal Com mplete ued PACK DENS (lb./f 75 50 20 30 l Estimated V commissioni ect Mileston mplete KING SITY ft3) 5 0
0 0
Volume ing activities nes WASTE VOLUME (ft3) 263,297 97,484 90,154 31,822 482,757
: s.
E


La Crossse Boiling Water W      Reactorr License Termination T             Plan Revision n0 Table 3-43 Continu    ued Date                   Milestonee Q1/20119              Site Resto oration Comp    plete Q1/20119              Submit Reemaining FR        RS Reports Q1/20119              Submit Liicense Transsfer to Dairylland Amenddment Requeest to NRC Q1/20220              License Transfer to Dairyland Appproved by N            NRC Q1/20220              LACBWR    R License Teermination A      Approval by NRC Note:   Circumstances can change during d        decomm missioning. Iff Solutions deteermines that thhe decommissiooning cannot be com mpleted as outliined in this sch hedule, Solutioons will providee an updated scchedule to the NRC.
La Cross License T Revision Date Q1/201 Q1/201 Q1/201 Q1/202 Q1/202 Note:
3.5. References R
3.5.
: 1.       Dairyland D           Power Cooperaative, LACB        BWR Decom    mmissioning Plan and Poost Shutdownn Decommissio D             oning Activitties Report (D-Plan/PSD
R
(            DAR), Revission - Marchh 2014.
: 1.
: 2.       U.S.
D D
U Nuclear Regulatory Commission              n NUREG-00586, Generiic Environm          mental Impactt Statement on Decommisssioning of Nu          uclear Faciliities, Suppleement 1, Vollume 1 -
: 2.
November N           20 002.
U S
: 3.       EnergySoluti E             ons Techniccal Support Document D           R RS-TD-3131996-005, La C        Crosse Openn Air Demolition D             Limits.
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: 3.
: 4.       U.S.
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U Nuclear Regulatory Commission              n NUREG-11575, Suppleement 1, Muulti-Agency Radiation R          Surrvey and Assessment of Materials annd Equipmennt Manual (M                MARSAME      E) -
: 4.
December D            20 006.
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: 5.      Radiological R              Effluent Mo onitoring and   d Offsite Doose Calculation Manual ((ODCM).
D
: 6.      EnergySoluti E              ons Techniccal Support Document, D            R RS-TD-313196-007, Raddiation Expoosure Projections foor LACBWR    R Decommisssioning.
: 5.
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se Boiling W Termination n 0 19 19 19 20 20 Circumstance cannot be com References Dairyland Po Decommissio U.S. Nuclear tatement on November 20 EnergySoluti Demolition L U.S. Nuclear Radiation Sur December 20 Radiological EnergySoluti rojections fo Water Reactor Plan Milestone Site Resto Submit Re Submit Li License T LACBWR s can change d mpleted as outli wer Coopera oning Activit Regulatory Decommiss 002.
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Latest revision as of 21:52, 9 January 2025

License Termination Plan - Chapter 3 - Identification of Remaining Site Dismantlement Activities, Rev. 0
ML16200A087
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: ML16200A087 (24)
v • d • e


Text

LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 3 IDENTIFICATION OF REMAINING SITE DISMANTLEMENT ACTIVITIES

La Cross License T Revision 3.

Iden 3.1.

3.2.

3.2.

3.2.

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3.2.

3.3.

3.3.

3.3.

3.3.

3.3.4 se Boiling W Termination n 0 ntification of Introduction Completed 1.

Overvi 2.

Disman

.2.2.1. For

.2.2.2. Sea

.2.2.3. Dec

.2.2.4. Prim

.2.2.5. Alt

.2.2.6. Gas

.2.2.7. Fue

.2.2.8. Com

.2.2.9. Hyd

.2.2.10. W

.2.2.11. De

.2.2.12. Ov

.2.2.13. Sta

.2.2.14. Lo

.2.2.15. Hi

.2.2.16. Ci

.2.2.17. Co

.2.2.18. Fu

.2.2.19. Ste

.2.2.20. 60

.2.2.21. Tu

.2.2.22. He

.2.2.23. Li

.2.2.24. El 3.

Additio Future Deco 1.

Reactor 2.

Turbine 3.

Waste T Storage 4.

LACBW Water Reactor Plan f Remaining n.................

and Ongoing ew..............

ntlement of S rced Circulat al Injection S cay Heat Co mary Purific ernate Core seous Waste el Element S mponent Co draulic Valv Well Water Sy emineralized verhead Stor ation and Co ow Pressure igh Pressure irculating W ondensate Sy ull-Flow Con eam Turbine 0-Megawatt G urbine Oil an eating, Venti quid Waste ectrical Dist onal Activiti ommissionin r Building..

e Building a Treatment B e Building..

WR Crib Ho r

TABLE O g Site Disman g Decommis Systems and tion System.

System.........

oling System cation System Spray Syste e Disposal Sy Storage Well oling Water ve Accumula ystem...........

d Water Syst rage Tank....

ontrol Air Sy Service Wat Service Wa Water System ystem and Fe ndensate Dem e..................

Generator....

nd Hydrogen ilation, and A Collection S tribution Sys es................

ng Activities and Turbine O Building, Gas ouse.............

3-i OF CONTE ntlement Ac ssioning Act d Componen m.................

m.................

em................

ystem..........

System......

ator System.

tem..............

ystem..........

ter System..

ater System..

eedwater He mineralizer n Seal Oil Sy Air Conditio Systems.......

stem............

s and Tasks..

Office Build s Storage Ta ENTS ctivities........

tivities and T nts................

eaters...........

System........

ystem...........

oning (HVA ding.............

ank Vault an Tasks...........

AC) Systems.

nd LSA

... 3-1

... 3-1

... 3-3

... 3-3

... 3-3

... 3-3

... 3-4

... 3-4

... 3-4

... 3-4

... 3-4

... 3-4

... 3-5

... 3-5

... 3-5

... 3-5

... 3-5

... 3-6

... 3-6

... 3-6

... 3-6

... 3-6

... 3-6

... 3-7

... 3-7

... 3-7

... 3-7

... 3-8

... 3-8

... 3-8

... 3-8

... 3-9

. 3-11

. 3-12

. 3-13

La Cross License T Revision 3.3.

3.3.

3.3.

3.4.

3.4.

3.4.

3.4.

3.4.4 3.4.

3.5.

Table 3-1 Table 3-2 Table 3-3 Table 3-4 se Boiling W Termination n 0 5.

Mainte 6.

Ventila 7.

Legacy Radiologica 1.

Contro 2.

Occupa 3.

Exposu 4.

Radioa 5.

Project References 1

Status o 2

Radiati 3

Project 4

Genera Water Reactor Plan nance Eat Sh ation Stack..

y Waste.......

al Impacts of l Mechanism ational Expo ure to the Pu active Waste t Milestones of Major LA ion Exposure ted Waste Qu al Project Mi r

hack and 1B f Decommis ms to Mitigat osure............

ublic.............

Projections LIST ACBWR Sys e Projections uantities......

ilestones......

3-ii B Diesel Gen sioning Acti te the Recon OF TABLE stems and Co s for Decom nerator Build ivities..........

ntamination ES omponents a mmissioning.

ding.............

of Remediat as of June 20 ted Areas.....

015..............

. 3-14

. 3-14

. 3-15

. 3-15

. 3-16

. 3-16

. 3-16

. 3-17

. 3-18

. 3-19

... 3-2

. 3-16

. 3-17

. 3-18

La Cross License T Revision ALARA ACM AMSL BSFR CCW CST D-Plan/

PSDAR FESW FRS G-3 GSTV HPSW HVAC kVA ISFSI LACBW LPSW LSA LSE LTP NRC ODCM OHST REMP RPV RWP WTB se Boiling W Termination n 0 A

As L Asb Abo Bulk Com Con

/

R Dec Fuel Fina Gen Gas High Heat kilo-Inde WR La C Low Low LAC Lice Nuc M

Off-Ove Rad Reac Rad Was Water Reactor Plan LIST OF Low As Rea estos Contai ove Mean Se k Survey For mponent Coo ndensate Stor commissionin l Element St al Radiation noa Fossil Sta Storage Tan h Pressure S ting Ventilat

-Volt-Ampe ependent Spe Crosse Boilin w Pressure Se w Specific Ac CBWR Site E ense Termina lear Regulat

-site Dose Ca rhead Storag iological En ctor Pressure iation Work ste Treatmen r

ACRONYM sonably Ach ining Materi ea Level r Release oling Water rage Tank ng Plan/Post torage Well Survey ation nk Vault ervice Wate tion Air Con re ent Fuel Stor ng Water Re ervice Water ctivity Enclosure ation Plan tory Commis alculation M ge Tank nvironmental e Vessel k Permit nt Building 3-iii MS AND AB hievable ial t Shutdown er nditioning rage Installa eactor r

ssion Manual l Monitoring BBREVIAT Decommiss ation g Program TIONS ioning Activvities Reportt

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

Page Inten 3-iv ntionally Lefft Blank

La Cross License T Revision

3.

Id 3.1.

In In accord the rema the time remediati Estimate released projected will be Crosse B Decomm to procee The LAC alternativ Decomm DECON sites. Cu located in Decomm regulator State and Decomm of 10 CF involve LACBW the techn approval Decomm Safety an decommi operation The rem described discussed major rem specific e compone se Boiling W Termination n 0 dentificati ntroduction dance with 1 aining major of submitta ion and an a s of the oc to unrestric d volumes of undertaken Boiling Wa issioning Ac ed.

CBWR site ve, as desc issioning of alternative i urrently, LaC n Andrews, missioning a ry agencies d local regu missioning ac FR 50.82(a)(6 any un-revi WR. If an act nical specifi before impl missioning ac nd Health P issioning do ns, especially maining dec d in section d in sections maining com equipment r ents that hav Water Reactor Plan ion of Rem n

10CFR50.82 r dismantlem al. The info assessment o ccupational r ted areas du f radioactive pursuant to ater Reacto ctivities Repo will be de cribed in N f Nuclear F is contingen CrosseSoluti Texas and at activities are in accordan ulatory agen ctivities at LA

6) and (a)(7) iewed safet tivity require ications or l lementing th ctivities are Program, an not pose an y those durin ontamination 3.3. The sp s 3.3.2 throu mponents of remediation e been or are r

maining Si (a)(9)(ii)(B ment and dec formation inc of the potent radiation do uring the co e waste that o the curren or (LACBW ort (D-Plan/

contaminate NUREG-058 Facilities, S nt upon conti ions (Solutio t the Energy e being co nce with pla ncies are list ACBWR wi

). At the tim ty questions es prior NRC license, a su he activity in conducted nd Waste M ny greater ra ng major ma n and dism pecific system ugh 3.3.7. T contaminate consideratio e to be remo 3-1 ite Disman

), the Licens contaminatio cludes those tial radiolog ose and the mpletion of will be gene nt 10 CFR 5 WR) Decom

/PSDAR) (1 ed and dism 86 Generic Supplement inued access ons) has acc ySolutions fa oordinated w ant administ ted in sectio ill be conduc me of LTP s s or change C approval u ubmittal wil n question.

under the S Management diological or aintenance an mantlement m considera These section ed plant syst ons. Table 3 oved.

ntlement A se Terminati on activities e areas and ical conditio quantity of f the schedu erated are als 50 license, mmissioning

1) and do no mantled in ac Environme 1, Volume 1 s to one or m cess to low-l acility locate with the ap trative proce n 8.7.2 of L cted in accor submittal, th es in the T under 10 CF ll be made Solutions Ra Program r safety risk nd outage ev activities th ations that w ns provide a tems and, as 3-1 contains Activities ion Plan (LT s for the dec equipment ons that may f radioactiv uled tasks ar so included.

are consist Plan and ot depend up ccordance w ental Impac 1 (2). Co more low lev level waste d ed in Clive, U pplicable Fe edures. Ap LTP Chapter rdance with he remaining Technical S R 50.59(c)(2 to the NRC adiation Pro Activities c k than those c volutions.

that will be will be taken an overview s appropriate s a list of m TP) must ide commissioni that need fu y be encount e material t e provided.

These acti tent with th d Post-Shut pon LTP app with the DE ct Statemen ompletion o vel waste dis disposal faci Utah.

ederal and pplicable Fed r 8.

the requirem g activities d pecification 2), or a chan C for review otection Prog conducted d conducted d e performed n into accoun and describ e, a descripti major system entify ing at urther tered.

to be The vities he La tdown proval ECON nt on f the sposal ilities State

deral, ments do not ns for nge to w and
gram, during during d are nt are be the ion of s and

La Cross License T Revision Forced Reacto Reacto Main S Decay Primar Feedw Seal In Altern Gaseo Fuel E Compo Hydra Well W Demin Overh Station Low P High P Circul Conde Heater Steam 60-Me Main C Turbin se Boiling W Termination n 0 Table System or d Circulation or Vessel Int or Vessel Steam in Re y Heat Coolin ry Purificatio water in Reac njection Syst nate Core Spr us Waste Di Element Stor onent Coolin ulic Valve A Water System neralized Wa ead Storage n and Contro Pressure Serv Pressure Serv ating Water ensate and Fe rs Turbine egawatt Gen Condenser &

ne Bldg. Mai Water Reactor Plan e 3-1 Sta as Componen n System ternals actor Bldg.

ng System on System ctor Bldg.

tem ray System isposal Syste rage Well Sy ng Water (C Accumulator m

ater System Tank (OHS ol Air System vice Water vice Water System eedwater Ta erator

& Accessorie in Steam r

atus of Majo of June 201 nt P

R R

In In Io In 90 50 em A

ystem C

CCW)

In r System In In In T)

In m

In 30 O

R anks and D

pl R

R es 15 R

3-2 or LACBW 15 artially Rem Removed from Removed from n place n place-Drai on Exchange n place 0% removed 0% removed All except un Contents rem n place-70%

n place-Drai n Place - Iso n place-Drai n place-Drai n place 0% removed Operational Remains in pl Drained-Con lace, All Fee Removed Removed 5% Remove Removed WR Systems Sta moved m site m site ined ers in place; d

d nderground s moved-Drain

% Removed ined lated from T ined-50% re ined d

lace - pump ndensate Sto edwater Hea ed and Compo atus 90% remov storage tank ned Turbine/Reac emoved ps de-energiz rage Tank re aters remove onents ed removed ctor Bldg.

zed emain in ed

La Cross License T Revision Tab Turbin Turbin Liquid Fuel T HVAC Electri Asbest After th demonstr reduced t will be decommi 3.2.

C 3.2.1.

In excess addition disposal waste.

Waste sto Class B/C were ship rod blad Attachme removed fuel asse the storag 3.2.2.

3.2.2.1.

The Forc Circulati se Boiling W Termination n 0 ble 3-1 (con System or ne Bldg. Con ne Oil and H d Waste Coll Transfer Brid C Systems ical Systems tos Abateme e balance rated to be to the area a transferred issioning act Completed a Overview s of 2 millio to the Reac of the RPV ored in the F C waste (i.e pped for disp des was fill ents to the R from the R mblies and f ge racks and Dismantl Force ced Circula on pumps, a Water Reactor Plan ntinued)

S a

Componen ndensate and Hydrogen Sea lection Syste dge s

ent of the site below the u around the I back to Da tivities comp and Ongoing w

n pounds of ctor Pressur V included d Fuel Elemen

., resins, filt posal in June led with lo RPV were r eactor Build fuel debris w d installed co lement of Sy d Circulation ation system auxiliary oil r

Status of Ma as of June 20 nt d Feed R

al Oil P

ems In R

In In 75 is remedia unrestricted Independent airyland und pleted to dat g Decommis f metallic wa re Vessel (R disposition o nt Storage W ters, and was e 2007. The ow-density c removed and ding and wa were placed omponents w ystems and n System m and attend pumps, and 3-3 ajor LACBW 015 Removed artially Rem n place - Par Removed n place - Par n place-Disc 5% complet ated and th release crite Spent Fuel der the 10 e are provid ssioning Ac aste have be RPV) and s of irradiated Well (FESW) ste barrel co e RPV conta cellular con d all other a s shipped fo in dry cask were removed Component dant oil sys hydraulic c WR System Sta moved rtially Opera rtially Opera connected te he levels o eria, the 10 Storage Ins CFR Part 5 ded in section ctivities and een removed spent fuel st d hardware a

) was proces ontents) and aining the rea ncrete with appurtenanc or disposal in storage in th d from the F ts stems have oupling oil p ms and Com atus ational ational f residual CFR Part 50 tallation (IS 50 license.

n 3.2.

Tasks d, shipped, an torage racks and all othe ssed and col packaged in actor interna the reactor es were cut n June 2007 he ISFSI in FESW.

been draine pumps have ponents radioactivity 0 license w SFSI) and th Spent fuel nd disposed

s. Removal er Class B a llected with n three liner als and 29 co r head insta
t. The RPV
7. After all September 2 ed. The Fo been electri y are ill be e site l and of in l and and C other s that ontrol alled.

V was spent

2012, orced ically

La Cross License T Revision disconne density c nozzles w reactor c disposed 3.2.2.2.

The Seal Circulati 90% rem 3.2.2.3.

The Dec cooler, a This syst 3.2.2.4.

The Prim regenerat resins ha coolers a 3.2.2.5.

The Alte (HPSW) duplex st system in and 80%

compone 3.2.2.6.

This syst recombin exception tunnel.

3.2.2.7.

The Fuel 11 feet b 38,000 g pumps, o fuel and well and se Boiling W Termination n 0 cted. All 1 cellular conc were cut to cavity was a of. Pumps Seal I l Injection s on pumps an moved.

Decay cay Heat Co nd interconn tem is draine Prima mary Purific tive cooler, ave been rem and 90% of th Altern ernate Core pumps, whi trainers and n the Reacto

% of the pi ents are drain Gaseo tem routed ning, monito n of the und Fuel E l Element Sto by 11 feet b allons of wa one heat exc fuel debris, i a fixative w Water Reactor Plan 16 inch and crete. Four allow remo also cut at and piping i njection Sys ystem provi nd the 29 co y Heat Cooli ooling system necting pipin ed and inope ary Purificati cation syste purification moved and t he piping ha nate Core Sp Spray syste ich took suc two motor-o or Building w iping in the ned and are r ous Waste D main conde oring and h derground ga Element Stor orage Well (

by approxim ater. The FE changer, one installed com was applied to r

20 inch For 16 inch Forc oval of the the biologic n the shielde stem ided cooling ontrol rod dr ing System m was a sin ng used to r erable.

ion System m was a h n cooler, pum the system h ave been rem pray System m consisted ction from th operated val was removed e Turbine B ready for dis isposal Syst enser gasses holdup for as storage tan rage Well (FESW) is a mately 42 fe ESW cooling e ion exchan mponents, an o the walls.

3-4 rced Circula ced Circulat reactor pres cal shield, s ed cubicles r g and sealing ive units. T ngle high pr remove core high pressur mp, two ion has been dr moved and di d of two die he river and lves installed d due to inte Building ha smantlement tem s through va decay. Th nks and the a stainless ste eet deep. W g system is c nger, piping, nd storage ra The system ation system tion inlet no ssure vessel segmented i remain.

g water for This system i ressure clos decay heat re, closed lo n exchanger rained. The isposed as ra esel-driven H discharged d in parallel erference wi as been rem

t.

arious comp his system h gas storage eel lined con When full, connected to

, valves, and acks have be m has been dr m piping was zzles and fo

. Piping lo into manage the seals on is drained an sed loop con following r oop system rs and filters e Primary Pu adioactive w High Pressur to the reacto

. Approxim th the reacto moved. Re ponents for has been re tank in the T ncrete structu it containe o the well an d instrument een removed rained and is s filled with our 16 inch o ocated withi eable pieces n the two Fo nd approxim ntaining a p reactor shutd consisting

s. Ion exch urification p waste..

re Service W or vessel thr mately 50% o or vessel rem emaining sy drying, filte emoved with Turbine Bui ure that mea ed approxim nd consists o tation. All d from the sto s inoperable.

h low outlet n the

, and orced mately

pump, down.

of a hange

pump, Water rough of the moval ystem
ering, h the ilding asures mately of two spent orage

La Cross License T Revision 3.2.2.8.

The Com various h barrier b cooling w system is 3.2.2.9.

The func force to the Force air comp drained.

3.2.2.10.

Water fo suction t system su cooling w down fla equipmen isolated f Administ 3.2.2.11.

The Dem of 19,100 are two s Virgin W deminera Station (G 3.2.2.12.

The Ove integral p the FESW OHST ac The OHS Spray sy drained a se Boiling W Termination n 0 Comp mponent Coo heat exchang between rad water to Re s approximat Hydra ction of the H operate the ed Circulatio ressors, wat Well W or this syste through stai upplied wate water for the ash tank and nt and seal w from the Re tration Build Demin mineralized W 0 gallons and sections of a Water Tank p alized water G-3). The sy Overh erhead Stora part of, the R W, cask poo cted as a re ST also supp ystem, and w and inoperab Water Reactor Plan ponent Cooli oling Water gers and pum ioactive sys eactor Build tely 70% com aulic Valve A Hydraulic V five piston-t on and Main ter pumps, an Water System m was supp nless steel er to the pla e two Turbi d sample co water for th eactor/Turbin ding and Crib neralized W Water System d an upper V an integral a provided wat throughout ystem has be head Storage age Tank (O Reactor Bui ol, and upper ceiver for re plied the wa was a backup ble.

r ing Water Sy (CCW) syst mps in the R stems and s ding Air Con mplete.

Accumulator Valve Accum type valve a n Steam syst nd other equ m

plied from t strainers, an ant and office ne Building ooler. The he Circulatin ne building.

b House.

ater System m consists o Virgin Water luminum tan ter to the De the plant. W een drained.

e Tank OHST) is a 4 lding. The r cavity duri ejecting refu ater for the E p source for 3-5 ystem tem provided Reactor Build secondary c nditioner co r System mulator system actuators, wh tems. The h uipment have two sealed s nd discharge e for sanitar g air-conditio well water ng Water pum Well water of a lower C r Tank, whic nk located o mineralized Water was d 45,000-gallo OHST serve ing cask loa ueling water Emergency C the Seal Inj d controlled ding during ooling syste ompressors.

m was to su hich operate hydraulic sy e also been submersible ed into inte ry and drinki oning units system also mps. The W r pump #3 s Condensate S ch has a capa on the Turbin d Water trans demineralize on tank loca ed as a reser ading operati r using the P Core Spray s njection syste d quality coo plant operat ems. The The disma upply the nec ed the five r ystem has be electrically deep well egrated press ing purpose and the heat o supplied w Well Water supplies pot Storage Tank acity of 29,7 ne Building sfer pumps, w ed in batches ated at the t rvoir for wa ions. Durin Primary Pur system and em. The sy oling water t tion, serving system prov antlement of cessary hydr rotoport valv een drained.

disconnected pumps that sure tanks.

s. It was us ting boiler b water for lau System has table water t k with a cap 780 gallons.

office roof.

which distrib s at Genoa F top of, and ater used to ng operation rification sy Reactor Bui ystem is curr to the g as a vided f this raulic ves in The d and took The sed as blow-undry been to the pacity Both The buted Fossil is an flood s, the ystem.

ilding rently

La Cross License T Revision 3.2.2.13.

There are act as a v supply to used as n 3.2.2.14.

Two vert strainer u was the system is river wat to allow 3.2.2.15.

The purp (G-3) ma The inter (WTB) i hydrants the fire s by the rem 3.2.2.16.

Circulatin open suc join a co condense Water en tube side which di LACBW pumps ha 3.2.2.17.

The Cond pressure Tank (CS 3.2.2.18.

The Full removed piping ha se Boiling W Termination n 0 Statio e two single volume stora o the station needed.

Low P tical pumps unit. The L normal sup s currently u ter ingress in dismantleme High P pose of the H aintains HPS rnal loop ser interior hose and the LA uppression s moval of iso Circul ng water is d ction bays in ommon 60 in er, the 60 inc nters the top

e. The 42 in scharges to t WR Crib Hou ave been de-Conde densate Syst to the suctio ST), this syst Full-F l-Flow Cond ionic impu ave been rem Water Reactor Plan n and Contr

-stage positi age unit for t n and the con Pressure Serv located in th ow Pressure pply to the H used as the d n the turbine ent which is Pressure Ser HPSW syste SW system rved the Tur e stations an CBWR Crib system for G olation valve lating Water drawn into t n the LACB nch pipe lea ch pipe bran section of th nch condens the seal wel use. The C

-energized.

ensate Syste tem took con on of the rea tem has been Flow Conden densate Dem rities from t moved.

r ol Air Syste ive displacem the station.

ntrol air sys vice Water S he LACBW e Service W HPSW syst dilution wat e building tu approximate rvice Water em is to sup pressure. T rbine Buildin nd sprinkler b House spri G-3. Current es and install r System the intake flu WR Crib H ading to the nches into tw he condenser ser circulatin l from G-3 l Circulating W m and Feedw ndensed stea actor feed pu n drained an nsate Demin mineralizer the condens 3-6 m

ment lubrica The air rece stems. This System R Crib Hou ater (LPSW em through ter supply fo unnel area.

ely 30% com System ply fire sup The HPSW ng, Reactor B r systems.

inklers. The tly, the syste ling pipe bla ume from th House. Each e main cond wo 42 inch pi r tube side a ng water out located appr Water System water Heater am from the umps. With nd most of th neralizer Syst System con ate water go ated type com eiver outlet li system is c use supplied W) system sup h the motor-or conductin The origina mplete.

pression wa system is d Building, an The externa e external lo em is isolate anks to allow he river by tw h pump disch denser in th ipe to the to and is discha tlet lines tie roximately 6 m is current rs condenser h the exceptio he piping has tem nsisted of re oing back to mpressors.

ines join to f currently stil the system upplied the C

-driven HPS ng liquid wa al system has ater. The ad divided into nd Waste Tr al loop supp op was cros ed from the T w only extern wo pumps lo harges into he Turbine B op section of arged from th into a comm 600 feet dow tly inoperab hotwell and d on of the Co s been remov esin-filled se o the reacto The air rece form a heade ll operable a through a du CCW cooler SW pump.

aste discharg s been simp djacent coal two main l eatment Bui plies outside ss-connected Turbine Bui nal fire loop ocated in sep 42 inch pipe Building. A f the water b he bottom se mon 60 inch wnstream from ble as the sy delivered it u ondensate Sto ved.

ervice tanks

r. All tanks eivers er for and is uplex s and This ges of lified plant oops.

ilding e fire d with ilding use.

parate e that At the boxes.

ection h line m the ystem under orage s that s and

La Cross License T Revision 3.2.2.19.

The turbi rated at 6 pressure have bee 3.2.2.20.

The 60 76,800 kV lubricatin through a been com 3.2.2.21.

The Turb lubricatin reduction complete 3.2.2.22.

The Reac for drawi air condi 337,500 B building from the 350 feet exhaust s particulat includes which hi detecting Ventilati vault are the gas s vault thro Currently use of sta se Boiling W Termination n 0 Steam ine was a hi 60 MW. Th element. T n removed.

60-Me MW gener VA. The g ng system, a a reduction g mpletely rem Turbin bine Oil Sys ng and cooli n gear. This ely removed.

Heatin ctor Buildin ing fresh air itioning unit Btu/hr capac through ope building us high and is system was te radiation an isokineti storically ha g particulate on for the W as of the bu storage tank ough the con y, both syste ack fans that Water Reactor Plan m Turbine igh pressure he turbine co The Steam T egawatt Gen ator was a generator w and excited gear. The m moved, uncon ne Oil and H stem receive ing oil to th s system, wi ng, Ventilati g Ventilatio r into the bu t air inlet inc city steam c enings betw sing stack b constructed equipped w detector. A ic nozzle, lo as drawn air and gaseous WTB was pro uilding and e vault. The nnecting tunn ems are de-e t are energiz r

, condensing onsisted of a Turbine, as w nerator a high-spee as cooled b by a separat main and rese nditionally re Hydrogen Se ed cooled oi he turbine an ith exceptio ion, and Air on System ut uilding and f cluded a filt coil that was een and aro lowers throu of structura with conventi A monitoring ocated down r from the st s activity.

ovided by a 2 exhausted th stack blowe nel and disch energized. B ed by tempo 3-7 g, reaction, t a high pressu well as som d, turbine-d by a hydrog te exciter at erve exciters eleased and d eal Oil System il from the l nd generato n of the dra Conditionin tilized two 3 for circulatin er box assem s used when und the bi-p ugh the exh al concrete w ional and hi g system is i nstream of t tack exhaust 2000 cfm ex he air throug ers then exh harged the a Building ven orary power.

tandem com ure and inter me steam sys driven wou gen system, ttached to th s have been dispositione m

lube oil coo r bearings, ained clean a ng (HVAC) S 30 ton, 12,00 ng the air thr mbly, face a n heating wa parting door haust stack f with an alum igh-efficienc installed wit the high-eff t to the mon xhaust fan th gh a duct ou hausted the a air from the b ntilation is cu mpound, rehe rmediate pre stem piping und-rotor m lubricated b he end of th removed. T ed.

olers to supp exciter bear and dirty oi Systems 00 cfm air c roughout the and bypass d as required.

r sections an for the facili minum nozzle cy filters and th the exhau ficiency filte nitoring syste hat drew air f ut the floor o air from the building thro urrently supp eat 3600 rpm essure and a and compo machine rate by a forced he generator The generato ply the nece rings, and ex l tanks, has conditioning e building.

dampers, and Air entere nd was exha ity. The sta e at the top.

d monitored ust system, w ers. The sy em, is capab from the shi of the buildi gas storage ough the stac plied throug m unit a low-onents ed at

-flow shaft or has essary xciter been units Each d one ed the austed ack is The d by a which

ystem, ble of elded ing to e tank ck.

gh the

La Cross License T Revision 3.2.2.23.

The Liqu storage ta in the tun The Reac consists pump, tw retention Followin liquid wa water dis Spent res quantity transferre disposal.

Currently discharge The air o 3.2.2.24.

The plan site has a buildings the stack 3.2.3.

Other com The con The Con The rack The Co The 3.3.

F The plan remainin se Boiling W Termination n 0 Liquid uid Waste Sy ank vault, an nnel between ctor Buildin of two reten wo sump pu n tanks.

ng processin aste from ea scharge outfl sin was trans available f ed to an ap y, the liquid es at LACBW operated pum Electr nt is disconne a 480 volt 50

s. Temporar
k.

Addition mpleted dec e abatement ntaining mate e abatemen ntaining Ma e placement ks from the e disconnect old and Dark e draining an Future Deco ns for the de ng site struct Water Reactor Plan d Waste Col ystem collec nd the tunne n the Reacto ng Liquid W ntion tanks, umps, and th ng and samp ach system w low. This w sferred to th for shipmen pproved ship d waste colle WR are thro mp discharge rical Distribu ected from o 00 kVa trans ry power is al Activities ommissionin

, packaging erial.

nt, packagin aterial (ACM of all spent FESW.

tion of LAC k status.

nd removal o mmissionin contaminatio tures are pr r

llection Syst cts the liquid el into two st r Building a Waste System each with he necessary pling to dem was then dis was the norm he spent resin nt to an ap pping contai ection system ough the East es to the inlet ution System off-site powe sformer prov tied to exis s

ng activities and disposa ng and disp M).

fuel into dry CBWR from of other misc ng Activities on, dismantl resented in t 3-8 ems d waste from torage tanks and the Turbi m, which is s a capacity o y piping to monstrate co scharged to al liquid effl n receiving t pproved pro iner, dewate m pumps are t Turbine bu t of the liqui m

er in support viding powe ting overhea include:

al of known posal of kn y storage in t off-site elec cellaneous sy s and Tasks lement and a the followin m the Turbine (4500 gallo ine Building separate from of 6000 gall route the w ompliance w the commo fluent release tank and hel ocessing fac ered, packag e not operab uilding sump id waste mon rt of Cold an er to multipl ad cranes an n and readily nown and r the ISFSI fa ctrical power ystem piping anticipated e ng sections.

e Building, t ons and 3000

g.

m the Liqui lons, a liqui waste liquid with the rele on G-3/LAC e pathway fo ld until there cility. The ged and ship ble. The on p using an ai nitor, which nd Dark statu e power car nd power to y accessible readily acce acility and th r and placin

g.

end-state co The metho the WTB, th 0 gallons) lo d Waste Sy id waste tra to and from ease criteria BWR circul or LACBWR e was a suffi resin was pped for of nly liquid eff ir operated p h is still opera us. Currentl rts throughou exhaust fan lead and/or essible Asb he removal o ng LACBWR ndition(s) fo ods to reme he gas ocated

ystem, ansfer m the a, the lating R.

ficient then ff-site fluent pump.

able.

ly the ut the ns for r lead bestos f fuel R in a or the ediate

La Cross License T Revision contamin remediat 3.3.1.

The Reac ellipsoida and it ex for the up The build including layer of structure concrete The shel Turbine Reactor B removal closed by leaves th the north A 50 ton Reactor supported the 5-ton Hatches of the cab The rema removed and the id Systems overhead size redu the waste Water an Once the building activity w once the In prepar elevation will allow se Boiling W Termination n 0 nated struct ion issues.

Reactor B ctor Buildin al bottom. I xtends 26 fee pper hemisp ding contain g the RPV an concrete to is supporte approximate ll includes t Building. I Building tha and dry cas y a weather he Reactor B heast quadran n traveling p Building.

d by column n hoists are a at several po bles and equ aining comp

. Area prep dentification or compon d crane or loc uce. The sys e loading are nd sludge ar e tank has b demolition.

will allow fo tank is prep ration for th

n. As necess w for the per Water Reactor Plan tures, system Building g is a right It has an ove et 6 inches b herical dom ned most of t nd biologica an elevation ed on a foun ely 3 feet thi wo airlocks In addition, at is intended k storage, an tight, insula Building 1 to nt and enters polar crane w The bridge ns around the also long en ositions in th uipment.

ponents and s paration and n and mitigat nents will be cal hoists. S stems will be ea in the Tur re currently been adequat Keeping as or the collect ared for dem he building sary, prior to rformance of r

ms, and eq circular cyli erall internal below grade e, which is 0 the equipme al shielding.

n of 727 fee ndation cons ick.

. The perso there is als d to accomm n opening w ated, roll-up, o 10 feet belo s the pipe tun with a 5 ton completely e inside of th nough to reac he main and systems in th set-up for c tion of any h e removed u Some system e either load rbine Buildin inside the O tely characte ssociated pip tion of any l molition.

demolition, o dismantlem f hot work a 3-9 quipment d inder buildin l height of 14 level. The 0.60 inch thi ent associate The interio et 10 inches sisting of co onnel airloc so an 8 feet modate large was created i

, bi-parting ow grade lev nnel.

n auxiliary h spans the he building.

ch down thr intermediat he Reactor B ommodity re hazardous m utilizing me ms or compon ded into ship ng.

OHST. The erized, a fix ping and com liquids. This the FESW ment, the FES activities requ do not invo ng with a he 44 feet and a steel shell t ick.

ed with the n or of the shel Above Mea oncrete-steel ck connects by 10 feet pieces of eq in the React door. The m vel either at hoist is loca building an The lifting rough hatchw te floors may Building wil emoval will material.

echanical m nents might pping contain e tank will b xative will b mponents in s piping wil will be dism SW will be d uired to rem olve any u emispherical an inside dia thickness is nuclear steam ll is lined wi an Sea Leve l piles and a the Reactor freight doo quipment. T tor Building majority of p the northwe ated in the u nd travels o cables of bo ways into th y be opened ll be drained include rad means with s require hot w ners or will be dewatered be applied in n place while l be dismant mantled from decontamina move the stain unique safet l dome and s ameter of 60 1.16 inch, e m supply sy ith a 9-inch-el (AMSL).

a pile cappin r Building t or opening i To facilitate

. The openi pipe penetra est quadrant upper part o n circular t oth the 50-ton he basement to allow pa d, dismantled diological sur support from work activit be transport d and deslud n preparatio e performing tled and rem m the main ated to level nless steel F ty or semi-0 feet, xcept

ystem,

-thick The ng of to the n the RPV ing is ations t or at of the tracks n and area.

ssage d, and rveys m the ties to ted to dged.

on for g this moved floor s that FESW

La Cross License T Revision liner. A sections liner will Turbine B will be d EnergySo Demoliti After com will be r with prop basement The r Asbe Dism Dism pipin Dism Reme The r The expo to meet t is identif method w deeper d open air process, t Once sur reach exc walls do segmente the steel sprung st Reactor B The ther packagin concrete

removal, loaded in the waste disposal se Boiling W Termination n 0 Associated eq of the FESW l be lifted by Building. O decontamina olutions Tec ion Limits (3 mmodity rem remediated t per contami t will includ removal of a stos Abatem mantle and re mantle and r ng as well as mantle and re ediation of th removal of a osed concret the open-air fied within t will be used depth, then a demolition.

then a struct rveys have cavator equi wn to grade ed and remo liner segme tructure and Building. T rmal shield ng as mixed will be rem the remain nto appropria e container site in Clive Water Reactor Plan quipment (H W liner will b y the overhe Once the FE ated to the chnical Supp 3).

moval is com to levels tha ination contr de:

any identified ment (to be p move the 6,0 emove the the auxiliary move the co he sump.

any lead shie te will then b demolition the first coup to remove t a wire saw w If large se tural evaluat demonstrate ipped with a e level. Af ved using cu entation and d associated The remainin will be seg waste. Aft moved, comp ning portion ate container will be tran e, Utah.

r HVAC, etc.)

be size reduc ead crane, p SW liner ha extent nece port Docume mplete, the b at will allow rols per Ref d Hazardous erformed by 000-gallon r two Forced y oil pumps.

ondensate pu elding.

be surveyed criteria spec ple of inche the contamin will be used ections of c tion will be c ed that the o a pneumatic fter the abo utting torche removal of ventilation ng interior c gmented usin ter the therm pletely expos of the steel rs and truck nsferred to a 3-10

) and piping ced using pl ackaged and as been remo ssary to all ent (TSD) R asement elev w demolition ference 3. T s Waste.

y a qualified retention tan Circulation urification io to determin cified in Ref s of concret nated materi d to remove ontaminated completed.

open-air dem hammer wi ve grade in es from the t the steel lin system will concrete will ng a wire s mal shield is sing the stee l liner will ed to a rail t a rail car an g will also lasma cutting d placed in t oved, the co low open-air RS-TD-31319 vation (621 n of above g The preparat Subcontract nks.

n Pumps, in on exchanger ne the scope ference 3. If te, a scabblin ial. If the co contaminate d concrete m molition crit ill be used t nternal steel top down to ner to the gro l be installe l then be rem saw into ma s removed, t el liner. Sub be removed trans-load fa nd then ship be removed

g. Sized pie the waste st oncrete unde r demolition 96-005, LAC foot) of the ground struc tion of the R tor).

ncluding the rs.

of the remed f unacceptab ng method o ontaminatio ed areas abo must be rem teria have b to break the shell is exp the ground ound elevati ed over the moved to th anageable p the remaind bsequent to

d. Demolitio acility in Wi pped to the
d. Contamin eces of the F taging area i rlying the F n as specifi CBWR Ope Reactor Bui ctures in ope Reactor Bui e inlet and o diation nece ble contamin or air hamm n is detected ove the limit moved during been met, a interior con posed, it wi elevation. W on is compl remainder o he thermal sh pieces for sp der of the int interior con on debris wi inona, MN w EnergySolu nated ESW in the FESW ed in n Air ilding en air ilding outlet essary nation mering d at a ts for g this high ncrete ill be When ete, a of the hield.

pecial terior ncrete ill be where utions

La Cross License T Revision The rema bowl b Final Rad 3.3.2.

The Tur switchge traveling crane has the main The Tur laborator ventilatin services.

Turbine O Commod and mec reciproca meet pac loading a is proper After rad

systems, specified criteria w with the of inches contamin be used t an accept Utah. A Radiation When al building and struc sequence to allow requirem The majo to be trea disposal facility i shipped se Boiling W Termination n 0 aining struc below 636 fo diation Surv Turbine B rbine Buildi ar, and othe g bridge cran s access to m floor. The T rbine Office ry, shops, co ng and air c In genera Office Build dity removal chanical me ating saws w ckaging and area located rly shipped a dioactive com component d in Referen will be remov Reactor Con s of concrete nated materi to remove c table radioac All structural n Work Perm l structural will be dem ctural concr e within the T open acces ments. Misti ority of the c ated as low l facility. Wa n Winona, to the Ene Water Reactor Plan tural concre oot elevation vey (FRS) in Building an ing housed er pneumatic ne with a 5 major equipm Turbine Bui e Building c ounting room conditioning al, these are ding is 110 fe l has begun eans to dism will be the pr waste dispo on the grou and disposed mmodity rem ts and struc ce 3 is met.

ved, segrega ntainment, if e, a scabblin al. If the co ontaminated ctive waste decontamin mits (RWP) surfaces ha molished. Al ete will be Turbine Bui ss to load o ing methods construction level radioac aste will be l MN where ergySolutions r

ete outside th n, concrete p accordance nd Turbine O the steam c, mechanica ton auxiliar ment items l lding is 105 contained o m, personne g equipment eas were sep eet by 50 fee and will con mantle radio rimary meth osal criteria und floor in t d of at an off-moval is co ctural surfac

. Structural ated, properly f unacceptab ng method o ontamination d areas. All disposal fac nation activit and under th ve been dec l remaining demolished lding will be out areas.

s will be uti debris resul ctive waste a loaded into a the waste c s disposal s 3-11 he liner belo pile cap and with LTP C Office Build turbine and al and hydra ry hoist cap located below feet by 79 f offices, the el change ro

, rest rooms parated from et and 45 fee ntinue in the oactive pipin hods used. S

a. Waste wi the northwes f-site facility mplete, surv ces to ensur materials th y packaged a ble contamin r air hamme n is detected radioactive ility, primar ties will be he oversight contaminated systems and to the grou e performed Concrete w ilized during lting from th and will be s appropriate c container wi site in Cliv ow the 636 piles) will r Chapter 5.

ding d generator, aulic system pacity spans w the floor t feet and 60 f Control Ro oom, decont s, storeroom m power pla et tall.

e Turbine Bu ng and com System piece ill be packa st corner of veys will be re that the hat do not m and disposed nation is iden ering method d at a deeper waste will rily the Ener performed i of Radiation d to the op d component und level sl from the top will be proc g building d he demolitio shipped to th containers an ill be transf ve, Utah.

foot elevati remain and main cond ms and equip the Turbine through num feet tall.

oom, locker amination fa m, and space ant equipme uilding utiliz mponents.

es and waste aged and sto the Turbine e performed open-air de meet the ope d of as radio ntified withi d will be us r depth, then be loaded an rgySolutions in accordanc n Protection en-air demo ts, interior st ab. The ge p down and cessed to m demolition to n of the stru he licensed r nd trucked to ferred to a r If possible, on (i.e., con be subjected denser, elec pment. A 3 e Building.

merous hatch r room facil facilities, hea e for other ent spaces.

zing cutting Band saws e will be siz ored in the w e Building un of all rema emolition cr en-air demo oactive waste in the first co ed to remov n a wire saw nd transport facility in C ce with appr personnel.

olition limits tructural sur eneral demo from west to meet disposa o minimize ucture is exp radioactive w o a rail trans rail car and some mat ncrete d to a ctrical 0-ton The hes in

lities, ating, plant The tools s and zed to waste ntil it aining riteria lition
e. As ouple ve the w will ted to
Clive, roved s, the rfaces lition o east l site dust.

pected waste s-load d then erials

La Cross License T Revision including accordan of Mater can be re recycle o the prese of a 193-When th excavato building

removal, Some ex discharge below gr 3.3.3.

The WTB and equip level sol basement bottom w The grad steel spen the shiel piping, c facility, c condition The base gained b drums.

exchange The Gas 14 feet h the WTB elevation compone cubic fee until such some ass The Low It was us se Boiling W Termination n 0 g structural c nce with NU rials and Eq ecycled or re or disposal a ence of any r

-6 Micro R in he Turbine B r with appr slab and fo undergroun xamples of e line. The rade (636 foo Waste Tr B is located pment for d lid radioacti t floor is at which extend de floor of th nt resin rece lded cubicle containers, a consisting of ning units.

ement of the y removal o The other a er, the WTB Storage Tan igh walls an B. The vaul n 617 feet.

ents for dryi et tanks are l h time that t sociated pipin w Specific Ac sed to store Water Reactor Plan concrete wil UREG-1575, uipment Ma eleased for d at a non-radi residual radio nstrument or Building has ropriate tool oundation to nd utilities w undergroun slab and fo ot elevation) reatment Bu d to the north decontaminat ive waste.

elevation 63 d to a depth o he WTB con eiving tank a e were two and pumps.

f a steam cle e WTB cons of floor shie area, to whic sump and p nk Vault (GS nd 2 feet thic lt is 3 feet b The Gas D ing, filtering located in th hey were ba ng. The rem ctivity (LSA processed, r

ll be radiolog Supplement anual (MAR disposal at a ioactive disp oactive cont r similar.

s been dem ls (pneumat meet dispo will also be r nd utilities oundation w uilding, Gas heast of the tion and the The WTB 30 feet and h of 626 feet.

ntains a shie and resin re back-washab The main eaning booth sists of two eld plugs, w ch access is pump, and ad STV) is a 29 ck floors, wa below grade Decay Syste g, recombini he GSTV. Th atch released mainder of th A) Storage Bu packaged an 3-12 gically surve t 1, Multi-Ag RSAME) (4).

non-radiolo posal site wi tamination b molished, the tic hammer, osal site requ removed, sur might be g alls will be s Storage Ta Reactor Bui collection, is 34 feet b has a 3 foot elded compa ceiving and ble radioact floor of th h, a decontam shielded cu was used for gained by dditional was 9 foot by 31 f alls, and ceil e with a sum em routed m ing, monitor he tanks had d via the stac he Gas Decay uilding is lo nd sealed lo eyed and rel gency Radia

. Materials ogical landfi ill be subjec y undergoin e foundation loading bu quirements.

rveyed, pack gas, water, removed to ank Vault a ilding. The processing, by 42 feet a deep sump w artment whi transfer equ tive liquid w e WTB also mination sin ubicles. One the storage a stairway, ste storage s foot undergr ling located mp that exte main conde ring and ho d the capabil ck. The tank y system has cated southw ow level dry leased for un ation Survey released for ll. All bulk cted to a fina ng an aggreg n slab will b ucket, etc.)

During slab kaged and pr miscellane o a minimum and LSA Sto e building co storage, and and 20 feet with 8 inch ich houses a uipment. Lo waste filters o housed a nk, and heati e cubicle, to of high act contains th space.

round concre below groun ends to a de enser gases oldup for de lity to store ks remain in s been remo west of the T y active was nrestricted u y and Assess r unrestricte material sen al assessmen ate survey b be exposed.

will remov b and found roperly disp eous piping, m depth of 3 orage Build ontained faci d disposal o tall. The W thick walls a a 320 ft3 stai ocated outsi s and dewat decontamin ng/ventilatio o which acce tivity solid w e dewaterin ete structure nd just outsi epth of 22 fe through va cay. Two radioactive place along ved.

Turbine Buil ste materials use in sment d use nt for nt for by use An e the dation posed.

, and 3 feet ding ilities f low WTB and a inless ide of tering nation on/air ess is waste g ion e with ide of eet or arious 1,600 gases g with lding.

s, and

La Cross License T Revision sealed lo Building Commod utilizing Band saw be cleane be sized waste loa site facili After com open air demolitio If unacc scabbling the conta contamin radioactiv When all above gr the concr GSTV lo with Cha will be u from the will be s appropria container Clive, Ut 3.3.4.

The LAC plant. T cooling w diesel-dr circulatin In additio facility, a Radiolog interior a that the s se Boiling W Termination n 0 ow level acti is 27 feet by dity remova cutting tool ws and recip ed and a fixa to meet pack ading area in ity.

mmodity rem demolition c on criteria w eptable con g method or amination is nated areas.

ve waste dis l structural rade portions rete floor sl ocated below apter 5. Con utilized durin demolition shipped to th ate container r will be tran tah.

LACBWR CBWR Crib The structure water to var iven high p ng water pum on to the G-3 and consequ gical surveys and exterior structure can Water Reactor Plan ivity compon y 80 feet and l has begun ls and mech procating saw ative will be kaging and w n the Turbin moval is com criteria per R will be remov ntamination air hammeri s detected a All radioa sposal facilit surfaces hav s of each bu lab will be r w 636 foot e ncrete will be ng building of each of he licensed rs and truck nsferred to a R Crib Hou b House is lo e served as rious LACB pressure serv mps. The LA 3 Crib Hous uently, will r s, either FSS structural su n be released r

nents. No li d 15 feet tall n and will hanical mean ws will be th e applied pri waste dispos ne Building u mplete, the Reference 3 ved, segrega is identified ing method w at a deeper active waste ty.

ve been dec uilding will b removed. T elevation wi e processed t demolition the structure radioactive ked to a rail a rail car and use ocated on th the intake BWR plant vice water p ACBWR Cri e, the LACB remain intac S or MARSA urface and sy d for unrestric 3-13 iquid wastes

l.

continue in ns to disman he primary m ior to disma sal criteria. W until it is pro interior con

. Structural ated, packag d within the will be used depth, then e will be lo ontaminated be demolish The remainin ll remain an to meet disp to minimize e will be tre waste dispo trans-load f d then shippe he bank of t for the Circ systems. T pumps, low ib House is 3 BWR Crib H ct and undist AME free re ystems of th cted use.

s were store n the WTB, ntle radioact methods used antlement. S Waste will b operly shipp ncrete surfac material tha ged and dispo e first coup d to remove t n a wire sa oaded and t d to the ope hed. The en ng structura nd be subjec posal site req e dust. All eated as low osal facility.

facility in W ed to the Ene the Mississi culating Wa The LACBW pressure se 35 feet by 45 House also cu turbed by th elease surve he LACBWR d in this bui

, GSTV an tive piping

d. The inter System piece be packaged ped and dispo ces will be r at does not m osed of as r ple of inche the contamin aw will be transported n-air demol ntire LSA bu al concrete f cted to a FR quirements.

construction w-level radio

. Waste wi Winona, MN ergySolution ippi River to ater System, WR Crib Ho ervice water 5 feet and 15 urrently serv he decommi eys will be p R Crib Hous ilding. The d LSA Bui and compon riors of tanks es and waste and stored i osed of at an remediated t meet the ope adioactive w es of concre nated materi used to rem to an accep lition criteria uilding, inclu for the WTB RS in accord Misting met n debris resu oactive waste ill be loaded where the w ns disposal s o the west o which prov ouse contain r pumps an 5 feet tall.

ves the active ssioning pro performed o se to demon LSA ilding nents.

s will e will in the n off-to the en-air waste.

ete, a al. If move ptable a, the uding B and dance thods ulting e and d into waste site in of the vided ns the d the e G-3 ocess.

on the strate

La Cross License T Revision 3.3.5.

The Mai windows The 1B D contains The build shaped h These tw including these stru radioactiv to a rail t car and t materials unrestrict recycled or dispos presence a 193-6 M 3.3.6.

The LAC an outsid 15 inches cluster of sides on t The Ven Once ch demolitio fixative w Demoliti system w removed of the v excavato the interi the concr methods and barr resulting and will appropria se Boiling W Termination n 0 Maintena intenance Ea s constructed Diesel Gener the Electric ding is cons aving larges wo structure g the concre uctures will ve waste dis trans-load fa then shipped s, including ted use in ac or released sal at a non of any resid Micro R inst Ventilatio CBWR Vent de diameter s at the bott f 78 piles. T the southeas ntilation Sta aracterizatio on criteria p will be appli ion will be will be emp using mech ventilation s rs will saw ior of stack.

rete debris.

will be utili icade the fa from the de be shipped t ate container Water Reactor Plan ance Eat Sh at Shack is d over a conc rator Buildin al Equipmen structed of c st dimension es will be r ete foundatio be treated as sposal facilit acility in Win d to the En g structural ccordance w for disposal n-radioactive dual radioact trument or si on Stack tilation Stac of 7 feet at tom to 6 inc The foundati st and southw ack will be on is compl per Referenc ed to the ide performed f ployed to pr hanical hand stack will b and break th An opening The concret ized during all zones in emolition of to the licens rs and truck r

hack and 1B a 20 feet b crete slab.

ng is attached nt Room, Di concrete blo s of 31 feet b radiologicall on slabs. C s low-level r ty. Waste wi nona, MN w ergySolution concrete w with MARSA at a non-rad e disposal s tive contami imilar.

k is a 350 fe the top and ches at the to on mat is 40 west corners radiological ete, interior ce 3 and dem entified surfa from the top rovide acces d tools down be removed he concrete g at the botto te foundation all demoliti the vicinity f these struc ed radioactiv ked to a rail 3-14 B Diesel Gen y 40 feet an d to the sout iesel Genera ck and steel by 38 feet an ly character Construction radioactive w ill be loaded where the wa ns disposal will be rad AME. Mate diological la ite will be ination by un feet high, tap 25 feet at th op. The 4 f 0 foot square lly character r concrete su molished. I aces to mitig p down. It ss to the ex n to the lowe d with exca into manage om of the sta n mat will be on to minim y of the ven ctures will b ve waste dis trans-load f nerator Buil nd 15 feet t theast corner ator Room, a l beams and nd 13 feet ta rized and th debris resul waste and w d into approp aste containe site in Cliv diologically rials release andfill. All b subjected to undergoing a pered, reinfo he base. Th feet thick fo e concrete ba rized and th urfaces will If remediatio gate any loos t is anticipat xterior of th er 40 foot el avators and eable section ack will be m e taken down mize dust. P ntilation sta be treated as sposal facilit facility in W lding all steel-sid r of the Turb and an empt d braces. Th all.

hen comple lting from t will be shippe priate contai er will be tra ve, Utah. I surveyed a ed for unrest bulk materia o a final as an aggregate orced concre he wall thick oundation m ase formed w hen comple l be remedi on is not pr se contamina ated that a tr he stack. T levation. Th pneumatic ns and drop made to allo n to 3 feet b Project perso ack. All co s low-level r ty. Waste w Winona, MN ded building bine Building ty Battery R he building tely demoli the demolitio ed to the lice iners and tru ansferred to If possible, and released tricted use ca al sent for re ssessment fo survey by u ete structure kness varies at rests on a without trian etely demoli iated to ope racticable, th ation.

raveling sca The stack wi he bottom 40 breakers.

the sections ow the remov below grade.

onal will mo nstruction d radioactive w will be loaded where the w with g and Room.

is L-

ished, on of ensed ucked a rail some d for an be ecycle or the use of e with from a pile ngular ished.

en air hen a affold ill be 0 feet The s into val of Wet onitor debris waste d into waste

La Cross License T Revision container Clive, Ut 3.3.7.

Approxim LACBW roads ins removal will be pr 3.4.

R The deco Solutions programs Solutions sufficient accordan Standard Reasonab controls radioactiv written p The curr Effluent Manual the vario are routi the publi also impo waste ma and outa procedu D-Plan/P environm No alte Rad Dec a po Continue Monitori and 10 C se Boiling W Termination n 0 r will be tran tah.

Legacy W mately 75 cu WR Site Encl side the LS of part of a rocessed as Radiological ommissionin s Radiation s are and w s Radiation t informatio nce with 10 ds For Prote bly Achieva the genera ve waste in plant procedu rent Radiati Monitoring (ODCM) (5 ous decontam inely inspec ic, and the e ortant to not anagement c ages, and de ures for wh PSDAR, the mental impac site-specifi er the conclu diation dose commission ositive envir ed applicatio ng Program CFR 50, App Water Reactor Plan nsferred to a Waste ubic yards losure (LSE SE, the unde a wall in the low-level ra l Impacts of ng activities Protection P will continue Protection on to demon 0 CFR 19, N ection Again able (ALAR ation, chara accordance ures.

ion Protecti g and Radi

5) will be us mination and cted by the environment te that decom consideratio ecommission hich appro e decommi cts in that:

ic factors pe usions prese to the publi ing is not a ronmental im on of the cur ms at LACB pendix I. Ra r

a rail car and of stockpile E) fence line erlayment s e Turbine Bu adioactive wa f Decommiss described ar Program and to be imple Program an nstrate that Notices, Ins nst Radiatio RA) The S cterization, with the app on Program iological Eff sed to prote d decommiss Nuclear Reg t are protect mmissioning ons as those ning activiti oval is bein ssioning wi ertaining to nted in NUR c will be min an imminent mpact.

rrent and fu BWR ensure adiological E 3-15 d then shippe ed deconstru

e. The deb and from th uilding. All aste during d sioning Act re and will b d Radioactiv emented as nd written s decommiss structions A on and to m olutions Ra processing, proved Solu m, Waste M ffluent Mon ct the worke sioning activ gulatory Com ted during fa g activities in encountere es conducte ng sought ill be acco the decomm REG-0586 (s nimal.

t health or s uture Radiati s public pro Environment ed to the Ene uction debri bris consistin he roads an l of the stoc decommissio ivities be conducted ve Waste M described i site procedu sioning activ And Reports maintain radi adioactive W

, handling, utions Radiat Management itoring and ers and the vities. Thes mmission (N acility decom nvolve the s ed during pl ed to date.

in this L omplished w missioning see LTP Cha safety conce ion Protectio otection in tal Monitori ergySolution is is stored ng of aspha nd concrete ckpiled deco oning.

d under the Management n the D-Pla ures are inte vities will b s To Work ation exposu Waste Mana

shipping, tion Protecti Program, a d Offsite D public, as a e well-estab NRC) to ens mmissioning ame radiatio ant operatio There are TP. As d with no sig of the LAC apter 8).

ern and wil on and Radi accordance ing Program ns disposal s inside the alt removed debris from onstruction d provisions o Program. T an/PSDAR.

ended to pro be performe kers, 10 CFR ures As Low agement Pro and disposa ion Program and Radiolo Dose Calcul applicable, d blished prog sure that wor g activities.

on protection ons, mainten e no additi described in gnificant ad CBWR woul ll generally iological Eff with 10 CF m (REMP) re site in south from m the debris of the These The ovide ed in R 20, w As ogram al of m, and ogical lation during grams

rkers, It is n and nance ional n the dverse ld have fluent FR 20 eports

La Cross License T Revision for LAC activities 3.4.1.

Due to t dismantle Consequ remediat radiologi specified described 3.4.2.

Table 3-2 This dos Exposure informati for remai Decomm Asb Rea Wa Tur Rem Wa Tot 3.4.3.

Continue Effluent public pr se Boiling W Termination n 0 CBWR to d s is bounded Control M the large sco ed, FRS of ently, a sys ed prior to p ical conditio d in 10 CFR d in LTP Ch Occupati 2 provides t se estimate e Projection ion gathered ining decom Table 3-missioning A bestos and ot actor Buildin aste Treatmen rbine Buildin maining Stru aste Processin tal for Deco Exposure ed applicatio Technical S rotection in a Water Reactor Plan date conclud by the evalu Mechanisms ope of rema f areas may stematic app performing F on of areas R 20.1402 ha apter 5.

ional Expos the cumulati is documen ns for LACB d for reporti mmissioning a

-2 Radi Act Activity ther Hazardo ng nt Building ng uctures ng (includes ommissionin e to the Pub on of Solut Specification accordance w r

de that the uation in NU s to Mitigat aining struct y be perfor proach will FRS and on s where co as been dem ure ive site dose nted in Ene BWR Decom ing of yearl activities is e iation Expos tivity ous Material s shipping an ng Activities blic tions Radia n and Radio with 10 CFR 3-16 public exp UREG-0586, te the Recon tures and sy rmed in par be employ ngoing decom mpliance w monstrated.

e estimates ergySolution mmissioning ly site dose estimated to sure Projec l Abatement nd prep) s ation Protec ological Env R 20 and 10 C posure as a

, which conc ntamination ystems that rallel with yed to ensu mmissioning with the unr These me for the deco ns TSD RS (6). This i

e. The total o be approxim ctions for De t

ction, Radio vironmental CFR 50, App result of d cludes the im n of Remedi will be dec decommissi ure that area g activities d restricted re easures and ommissionin S-TD-313196 information l radiation e mately 130.3 ecommissio Expo (person 18 81 9

1 0

18 130 oactive Was Monitoring pendix I.

decommissio mpact is mini iated Areas contaminated ioning activ as are adequ do not impac elease criter mechanism ng of LACB 6-007, Radi is in additi exposure esti 3 person-rem ning osure n-rem) 8.6 1.4

.6

.6

.8 8.2 0.3 ste, Radiolo Program as oning imal.

d and vities.

uately ct the ria as ms are BWR.

iation on to imate

m.

ogical ssures

La Cross License T Revision 3.4.4.

The Radi processin Activated low leve of waste Con Use Exp Exp Con Con Table 3-3 the deco referred t total volu feet. Ac be shippe WA Debri Deb Deb A

A Dry A

(

Mix se Boiling W Termination n 0 Radioact ioactive Wa ng, handling d and contam el radioactiv generated du ntaminated w ed disposabl pended abra pended resin ntamination ntaminated e 3 provides p mmissioning to as rip &

ume of low ctual waste v ed to the lice STE TYPE is: Concrete bris: Rebar bris: Metal Asphalt Soils Asbestos Active Waste (DAW) xed Waste Water Reactor Plan tive Waste P ste Managem g, shipping, minated syst e waste exp uring decom water; le protective sive and abs ns and filters control mat equipment u projections o g of LACB

& ship verse w-level radio volumes and ensed Energy Table WASTE CLASS A

A A

A A

A e

A A

r Projections ment Progra and dispos tems, structu pected to be mmissioning clothing; sorbent mate s;

erials (e.g., s used in the de of waste cla WR. As S es performin oactive waste d classificati ySolutions ra 3-3 Pro E

S WA WE (l

20,0 88 1,82 54 2,87 30 30 56 3-17 m is used to sal of radio ures, and com e generated include:

rials; strippable co ecommission ssifications Solutions has ng significan e for dispos ions may va adioactive w ojected Was ASTE EIGHT lbs.)

026,177 89,249 27,476 41,575 777,268 00,776 0,880 6,222 Total o control the oactive wast mponents rep during deco oatings, plast ning process and quantiti s elected to nt on-site de sal has been ary. The vas waste disposa ste Quantiti PACK DENS (lb./f 85 85 30 50 74 17 12 110 l Estimated V characteriza te during d present the l ommissionin tic enclosure

s.

ies that will use an app econtaminati n estimated st majority o al facility in ies KING SITY ft3) 5 5

0 0

4 7

2 0

Volume ation, genera decommissio largest volum ng. Other f es); and be generate proach comm ion activities at 393,696 of this waste Clive, Utah WASTE VOLUME (ft3) 235,603 10,463 60,916 10,832 38,882 17,693 2,574 16,733 393,696

ation, oning.

me of forms ed by monly s, the cubic e will

h.

E

La Cross License T Revision WA Clean (Debri Clea D

Recy Recy 3.4.5.

Table 3-4 Date Q2/201 Q2/201 Q2/201 Q3/201 Q3/201 Q3/201 Q4/201 Q4/201 Q4/201 Q4/201 se Boiling W Termination n 0 STE TYPE n Backfill -

is to Landfill an Asphalt Disposal cle - Metals ycle - Rebar Project M 4 lists the cu 16 16 16 16 17 17 17 18 18 18 Water Reactor Plan WASTE CLASS l)

Clean Debris Clean Debris Scrap Metal Scrap Metal Milestones urrent schedu Table Milestone Submit LT License T Mobilizati Stack Dem LTP Appr Componen Building D Transporta Site Reme FRS Com r

Table 3 E

S WA WE (l

19,7 4,8 1,8 95 ule for the re e 3-4 Ge e

TP to NRC ransfer Com ion Complet molition Com roval by NR nt Removal Demolition C ation and Di ediation Com mplete 3-18 3-3 Continu ASTE EIGHT lbs.)

747,211 74,175 03,064 54,659 Total emaining dec eneral Proje mplete te mplete C

Complete Complete isposal Com mplete ued PACK DENS (lb./f 75 50 20 30 l Estimated V commissioni ect Mileston mplete KING SITY ft3) 5 0

0 0

Volume ing activities nes WASTE VOLUME (ft3) 263,297 97,484 90,154 31,822 482,757

s.

E

La Cross License T Revision Date Q1/201 Q1/201 Q1/201 Q1/202 Q1/202 Note:

3.5.

R

1.

D D

2.

U S

N

3.

E D

4.

U R

D

5.

R

6.

E P

se Boiling W Termination n 0 19 19 19 20 20 Circumstance cannot be com References Dairyland Po Decommissio U.S. Nuclear tatement on November 20 EnergySoluti Demolition L U.S. Nuclear Radiation Sur December 20 Radiological EnergySoluti rojections fo Water Reactor Plan Milestone Site Resto Submit Re Submit Li License T LACBWR s can change d mpleted as outli wer Coopera oning Activit Regulatory Decommiss 002.

ons Technic Limits.

Regulatory rvey and As 006.

Effluent Mo ons Technic or LACBWR r

Table 3 e

oration Comp emaining FR icense Trans ransfer to D R License Te during decomm ined in this sch ative, LACB ties Report (

Commission sioning of Nu cal Support D Commission sessment of onitoring and cal Support D R Decommis 3-19 3-4 Continu plete RS Reports sfer to Dairyl airyland Ap ermination A missioning. If hedule, Solutio BWR Decom (D-Plan/PSD n NUREG-0 uclear Facili Document R n NUREG-1 Materials an d Offsite Do Document, R ssioning.

ued land Amend pproved by N Approval by f Solutions dete ons will provide mmissioning DAR), Revis 0586, Generi ities, Supple RS-TD-31319 1575, Supple nd Equipmen ose Calculati RS-TD-3131 dment Reque NRC NRC ermines that th e an updated sc Plan and Po sion - March ic Environm ement 1, Vol 96-005, La C ement 1, Mu nt Manual (M on Manual (96-007, Rad est to NRC he decommissio chedule to the ost Shutdown h 2014.

mental Impact lume 1 -

Crosse Open ulti-Agency MARSAME (ODCM).

diation Expo oning NRC.

n t

n Air E) -

osure

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