ML16200A087

Boiling Water Reactor 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
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Download: ML16200A087 (24)

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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

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....................

. ............................................................... 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

4. LACBW 3.3.4 WR Crib Ho ouse .............................................................................................. 3-13 3-i

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

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

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//

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

LTP Liceense Terminaation Plan NRC Nuclear Regulattory Commisssion ODCM M Off--site Dose Caalculation Manual M

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

La Crossse Boiling Water W Reactorr License Termination T Plan Revision n0 Page Inten ntionally Lefft Blank 3-iv

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0

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.

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.

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.

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.

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.

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.

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.

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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.

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

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

60-Meegawatt Generator Removed R

Main Condenser C & Accessoriees 155% Removeed Turbinne Bldg. Maiin Steam Removed R

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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

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

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.

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 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.

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.

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

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.

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.

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.

This systtem is draineed and inopeerable.

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. .

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.

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.

3.2.2.7. Fuel Element E Storrage Well The Fuell Element Sto orage Well (FESW)

( 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.

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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.

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.

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.

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.

3.2.2.12. 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.

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.

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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.

n 3.2.2.14. Low Pressure P Serv vice Water System S

Two verttical pumps located in th he LACBWR Crib Houuse supplied the system through a duuplex strainer unit.

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.

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.

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.

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.

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.

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.

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.

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.

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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.

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.

g The main m and reseerve exciterss have been removed. T The generatoor has been commpletely rem moved, uncon nditionally reeleased and ddispositioneed.

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..

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.

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.

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.

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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.

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.

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.

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.

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.

The air operated o pum mp dischargees to the inlett of the liquiid waste monnitor, whichh is still operaable.

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.

3.2.3. Additional Activitiess Other com mpleted decommissionin ng activities include:

Thee abatement, packaging and disposaal of knownn and readilyy accessible lead and/orr lead con ntaining mateerial.

Thee abatemen nt, packagin ng and disp posal of knnown and rreadily acceessible Asbbestos Conntaining Maaterial (ACM M).

Thee placement of all spent fuel into dry y storage in tthe ISFSI faacility and thhe removal of fuel rack ks from the FESW.

Thee disconnecttion of LAC CBWR from off-site elecctrical powerr and placinng LACBWR R in a Coold and Dark k status.

Thee draining annd removal ofo other misccellaneous syystem pipingg.

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

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.

3.3.1. Reactor Building B

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.

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.

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.

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.

Hatches at several po ositions in thhe main and intermediatte floors mayy be opened to allow passage of the cabbles and equuipment.

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.

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.

Water an nd sludge arre currently inside the OHST.O Thee tank will bbe dewateredd and desluddged.

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.

l Thiss piping will be dismanttled and rem moved once the tank is prepared for dem molition.

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

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.

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).

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:

The removal r of any a identified d Hazardouss Waste.

Asbestos Abatem ment (to be performed by y a qualified Subcontracttor).

Dismmantle and remove the 6,0 000-gallon retention r tannks.

Dismmantle and remove the two Forced Circulationn Pumps, inncluding thee inlet and ooutlet ng as well as the auxiliary pipin y oil pumps..

Dismmantle and remove the co ondensate pu urification ioon exchangerrs.

Remeediation of th he sump.

The removal r of any a lead shieelding.

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.

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.

B The T remainin ng interior concrete c willl then be remmoved to thhe thermal shhield.

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.

3-10

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.

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 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.

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.

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.

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.

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

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.

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.

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).

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.

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.

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.

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.

The Low w Specific Acctivity (LSA A) Storage Bu uilding is located southw west of the TTurbine Buillding.

It was ussed to store processed, packaged an nd sealed loow level dryy active wasste materialss, and 3-12

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.

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.

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.

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.

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.

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.

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.

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.

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.

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.

3-13

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.

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 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.

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.

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.

The Ven ntilation Staack will be radiologicallly characterrized and thhen compleetely demoliished.

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.

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

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.

3.3.7. Legacy Waste W

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.

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.

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:

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).

Rad diation dose to the public will be min nimal.

Deccommissioning is not an a imminentt health or ssafety conceern and willl generally have a poositive envirronmental immpact.

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

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.

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.

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.

3.4.2. Occupatiional Exposure Table 3-2 2 provides the t cumulatiive site dosee estimates for the decoommissioninng of LACB BWR.

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.

Table 3--2 Radiiation Expossure Projecctions for Deecommissioning Expoosure Acttivity (person n-rem)

Decomm missioning Activity A

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.

3-16

La Crossse Boiling Water W Reactorr License Termination T Plan Revisionn0 3.4.4. Radioacttive Waste Projections P

The Radiioactive Waste Managem ment Program is used too control the characterizaation, generaation, processinng, handling g, shipping, and dispossal of radiooactive wastte during ddecommissiooning.

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:

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

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)

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

Table 3-4 4 lists the cu urrent schedu ule for the reemaining deccommissioniing activitiess.

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

Q4/20118 Transportaation and Diisposal Com mplete Q4/20118 Site Remeediation Com mplete Q4/20118 FRS Com mplete 3-18

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.

3.5. References R

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

( DAR), Revission - Marchh 2014.

2. U.S.

U Nuclear Regulatory Commission n NUREG-00586, Generiic Environm mental Impactt Statement on Decommisssioning of Nu uclear Faciliities, Suppleement 1, Vollume 1 -

November N 20 002.

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

L

4. U.S.

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

December D 20 006.

5. Radiological R Effluent Mo onitoring and d Offsite Doose Calculation Manual ((ODCM).

6. EnergySoluti E ons Techniccal Support Document, D R RS-TD-313196-007, Raddiation Expoosure Projections foor LACBWR R Decommisssioning.

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