ML16200A093

License Termination Plan - Chapter 6 - Compliance with the Radiological Criteria for License Termination, Rev. 0

ML16200A093
Person / Time
Site:	La Crosse  File:Dairyland Power Cooperative icon.png
Issue date:	06/27/2016
From:	LaCrosseSolutions
To:	Office of Nuclear Material Safety and Safeguards
References
Download: ML16200A093 (114)

Text

LA CROSSE BOILING WATER REACTOR LICENSE TERMINATION PLAN CHAPTER 6 COMPLIANCE WITH THE RADIOLOGICAL CRITERIA FOR LICENSE TERMINATION

La Cross License T Revision 6.

Com 6.1.

6.2.

6.2.

6.2.

6.2.

6.2.4 6.3.

6.4.

6.5.

6.5.

6 6

6.5.

6.5.

6.5.4 6.5.

6.5.

6.5.

6.6.

6.6.

6.6.

6.7.

6.7.

6.7.

6.8.

6.8.

6.8.

6.8.

6.9.

6.10.

6.10 6

6 6

6 se Boiling W Termination n 0 mpliance with Site Release General Site 1.

Site Ge 2.

Site Hy 3.

Area L 4.

Area G Basements, Future Land Dose Mode 1.

Backfil

.5.1.1. BFM

.5.1.2. BFM 2.

Soil....

3.

Buried 4.

Existin 5.

Remain 6.

Dose S 7.

Alterna Mixture Fra 1.

Potenti 2.

Mixtur Soil Dose A 1.

Soil So 2.

Soil Ex Soil DCGL 1.

Parame 2.

RESRA 3.

Soil DC Soil Determ Basement 0.1.

Sou

.10.1.1. Re

.10.1.2. W

.10.1.3. W

.10.1.4. Re Water Reactor Plan h the Radiol e Criteria....

e Description eology.........

ydrogeology and Use.....

Groundwater Structures a d Use Scenar l Overview lled Baseme M Insitu Sce M Excavatio Piping.......

ng Groundwa ning Above Summation fo ate Scenarios actions for In ial Radionuc e Fractions f Assessment a ource Term.

xposure Path Computatio eter Selection AD Paramete CGL Uncert ministic Anal t Fill Concep urce Term...

eactor Buildi Waste Treatm Waste Gas Tan emaining Str r

TABLE O logical Criter n.................

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

Use............

and Piping to rio and Aver nts...............

enario..........

on Scenario.

ater..............

Ground Buil for Complian s..................

nitial Suite R clides of Con for Initial Su and DCGL...

hways and Cr on Model - R n Process....

er Selection ainty Analys lysis and Soi ptual Model ing..............

ent Building nk Vault......

ructures.......

6-i OF CONTE ria for Licen o Remain aft rage Membe ldings..........

nce...............

Radionuclide ncern and Ini uite Radionu ritical Group RESRAD v7 for Uncertai sis Results...

il DCGLs....

g..................

ENTS nse Terminat fter License T er of the Crit es.................

itial Suite....

uclides.........

p..................

7.0...............

inty Analysi tion.............

Termination tical Group..

is.................

n (End State)

... 6-1

... 6-1

... 6-1

... 6-1

... 6-2

... 6-2

... 6-3

).. 6-3

... 6-6

... 6-7

... 6-7

... 6-7

... 6-8

... 6-9

... 6-9

. 6-10

. 6-10

. 6-10

. 6-10

. 6-11

. 6-11

. 6-12

. 6-13

. 6-13

. 6-14

. 6-14

. 6-14

. 6-15

. 6-17

. 6-18

. 6-19

. 6-20

. 6-20

. 6-20

. 6-21

. 6-21

La Cross License T Revision 6.10 6.11.

6.11 6

6 6

6 6.11 6.12.

6.13.

6.13 6.14.

6.15.

6.16.

6.17.

6.18.

6.18 6.18 6.18 6.18 6.18 6.19.

6.20.

6.21.

se Boiling W Termination n 0 0.2.

BFM BFM Insi 1.1.

BFM

.11.1.1. BF

.11.1.2. BF

.11.1.3. BF

.11.1.4. BF 1.2.

BFM BFM Exc Insignific 3.1.

Rad Concentra Alternate BFM Elev Soil Area Buried Pi 8.1.

Sou 8.2.

Exp 8.3.

Bur 8.4.

Bur 8.5.

Bur Existing G Demonstr Reference Water Reactor Plan M Exposure itu Scenario M Insitu Gro FM Insitugw FM Insitugw FM Insitugw FM Insitugw M Insitu Dri cavation Sce cant Dose Co dionuclides o ations in Exc Land Use S vated Area C a Factors.....

iping Dose A urce Term an posure Scena ried Piping D ried Pipe DC ried Pipe Ra Groundwate rating Comp es...............

r e Pathways...

oundwater S Computatio RESRAD U RESRAD D Dose Factor illing Spoils enario...........

ontributors a of Concern a cavated Fill Scenario Dos Consideratio Assessment a nd Radionuc ario and Crit Dose Assess CGLs Initial adionuclides er Dose.........

pliance with 6-ii Scenario.......

n Model......

Uncertainty A Deterministic rs.................

Scenario an and Radionu and Adjusted Material.....

se.................

ons...............

and DCGL..

clide Mixture tical Group.

ment...........

Suite..........

of Concern Dose Criteri Analysis for c Analysis an nd DF Calcu uclides of Co d Soil DCGL e..................

and Adjuste ion..............

Initial Suite nd DSR Res ulation..........

oncern..........

Ls and BFM ed DCGLs...

e...................

sults.............

M DFs...........

. 6-22

. 6-22

. 6-22

. 6-24

. 6-24

. 6-26

. 6-26

. 6-33

. 6-33

. 6-35

. 6-36

. 6-39

. 6-39

. 6-41

. 6-42

. 6-43

. 6-43

. 6-43

. 6-44

. 6-44

. 6-45

. 6-47

. 6-48

. 6-49

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

Baseme End St 2

Buried 3

Initial S 4

Determ used in 5

Determ Kd par 6

Soil DC for Non 7

LACBW 8

Determ Uncert 9

Results Selecte 10 BFM In for Dis 11 BFM In for Dis 12 BFM In Distrib 13 BFM In Distrib 14 BFM In for Dis 15 BFM In Remain 16 BFM In 17 BFM In 18 BFM E 19 Soil DC Dose F 20 Reactor Contrib 21 WTB B Contrib 22 WGTV Contrib Water Reactor Plan ents and Bel tate Ground Piping to re Suite of Pote ministic Valu n to calculat ministic param rameters for CGL Uncert n-Nuclide S WR Soil DC ministic Geom tainty Analy s of RESRAD ed Determini nsitugw Rx B stribution Co nsitugw Rx B stribution Co nsitugw WTB bution Coeffi nsitugw WGT bution Coeffi nsitugw Rem stribution Co nsitugw DSR ning Structu nsitugw Dose nsitu Drillin Excavation D CGLs for RO Fraction......

r Building B butor Dose F BFM DFs fo butor Dose F V BFM DFs f butor Dose F r

LIST low Ground surface elev emain in LAC ential Radion ues selected f te Soil DCGL meter values soil DCGL c ainty Result pecific Param CGLs for Init metry RESR ysis for the f D Uncertain istic Parame Building abov oefficients (K Building belo oefficients (K B Uncertaint ficients (Kd).

TV Uncertai ficients (Kd).

maining Struc oefficients (K Rs for Reacto ures..............

e Factors......

g Spoils Dos Dose Factors OC Adjusted BFM DFs for Fraction.......

r ROC Adju Fraction.......

for ROC Ad Fraction.......

6-iii OF TABLE Structures to vation is 639 CBWR End nuclides and for Sensitive Ls...............

s selected for calculation..

t and Determ meter Distri tial Suite Ra RAD Parame five BFM Ins nty Analysis eters.............

ve 619: Unc Kd)..............

ow 619 Unce Kd)..............

ty Analysis R inty Analysis ctures Uncert Kd)..............

or Building, W se Factors...

d for Insignif r ROC Adju usted for Insi djusted for In ES o Remain in 9 feet AMSL State..........

d Mixture Fr e Kd parame r non-sensiti ministic Valu ibutions.......

adionuclides eters used in situgw Config for BFM In certainty Ana ertainty Ana Results for s Results for rtainty Analy WTB, WGT ficant Contr usted for Insi ignificant nsignificant n LACBWR L..................

ractions.......

eters ive ues selected s..................

the gurations.....

situgw and alysis Result alysis Result r

ysis Results TV, and ributor ignificant ts ts

... 6-4

... 6-5

. 6-12

. 6-17

. 6-18

. 6-18

. 6-19

. 6-25

. 6-27

. 6-28

. 6-28

. 6-29

. 6-29

. 6-30

. 6-31

. 6-32

. 6-34

. 6-35

. 6-37

. 6-38

. 6-38

. 6-38

La Cross License T Revision Table 6-2 Table 6-2 Table 6-2 Table 6-2 Table 6-2 Table 6-2 Table 6-2 Table 6-3 Figure 6-Figure 6-Figure 6-Figure 6-Figure 6-Figure 6-Figure 6-6-1 RES 6-2 RES 6-3 Dos Agg se Boiling W Termination n 0 23 Remain Insigni 24 ROC an 25 Surface 26 RESRA 27 Buried 28 Buried Radion 29 Summe Insigni 30 Ground

-1 Site Re

-2 Site Ov

-3 LACBW

-4 LACBW

-5 LACBW

-6 LACBW Elevati

-7 RESRA SRAD Input SRAD Input e Contributi gregate Dose Water Reactor Plan ning Structur ificant Contr nd Insignific e Soil Area F AD Source T Piping DCG Pipe DCGL nuclide Fract ed Buried Pi ificant Radio dwater Expo egional Loca verview.......

WR Building WR End Sta WR End Sta WR End Sta ion View....

AD Paramete t Parameters t Parameters on Percentag e Percentage r

res BFM DF ributor Dose cant Radionu Factors........

Term Parame GLs..............

Ls for ROCs tions............

ipe DCGLs f onuclide Fra osure Factors LIST O ation.............

gs................

ate................

ate - Backfill ate - Backfil er Selection ATTA for LACBW for LACBW ge for Initial from Insign 6-iv Fs for ROC A e Fraction.....

uclide Mixtu eters for Bur Adjusted fo for ROCs ad actions..........

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

OF FIGURE led Structure led Reactor Flow Chart.

ACHMENT WR Soil DCG WR BRM Un l Suite Radio nificant Dose Adjusted for ture Fraction ried Piping or Insignific djusted for RES es.................

Building Ba TS GL Uncertai ncertainty A onuclides an e Contributo r

ns.................

DCGL Calc ant asement inty Analysi Analysis......

nd Determina ors................

culations......

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

ation of

.................. 6

. 6-38

. 6-39

. 6-43

. 6-45

. 6-46

. 6-47

. 6-47

. 6-48

. 6-50

. 6-51

. 6-52

. 6-53

. 6-54

. 6-55

. 6-56

. 6-57

. 6-79 6-103

La Cross License T Revision AF ALARA AMCG AMSL ANL BFM BFM Ins BFM Ins bgs DCGL DF DPC FRS G-3 GW HSA HTD ISFSI LACBW LSE LTP MARSA MARSSI MDA MDC NRC PRCC RESRAD ROC TEDE USACE WGTV WTB se Boiling W Termination n 0 Area As L Ave Abo Arg Base situgw BFM situds BFM Belo Deri Dos Dair Fina Gen Gro Hist Hard Inde WR La C LAC Lice AME Mul Man IM Mul Min Min Nuc Part D

RES Rad Tota U.S Was Was Water Reactor Plan LIST OF a Factor Low As Rea erage Membe ove Mean Se onne Nation ement Fill M M Insitu Gro M Insitu Dril ow Ground S ived Concen se Factor ryland Powe al Radiation noa-3 undwater torical Site A d-to-Detect ependent Spe Crosse Boilin CBWR Site ense Termin lti-Agency R nual lti-Agency R nimum Detec nimal Detect clear Regulat tial Rank Co Sidual RADi dionuclides o al Effective D

. Army Corp ste Gas Tank ste Treatmen r

ACRONYM asonable Ach er of the Cri ea Level nal Laborator Model oundwater lling Spoils Surface ntration Guid er Cooperativ Survey Assessment ent Fuel Stor ng Water Re Enclosure ation Plan Radiation Su Radiation Su ctable Activi able Concen tory Commi orrelation Co ioactive mat of Concern Dose Equiva ps of Engine k Vault nt Building 6-v MS AND AB hievable tical Group ry deline Level ve rage Installa eactor urvey and As urvey and Sit ity ntration ssion oefficient terials alent eers BBREVIAT l

ation ssessment of te Investigat TIONS f Materials a ion Manual and Equipme ent

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

Page Intent 6-vi tionally Leftft Blank

La Cross License T Revision

6.

C S

6.1.

The site r criteria f Regulatio Dose result group water As Lo reduc Chapter Criterion Criterion G

6.2.

This sect site. Lan descriptio Hydroge Coopera The LAC Village o to the no the west 522), fiv east shor shown in Enclosur 6.2.1. S LACBW of the C described and fluvi shales of approxim se Boiling W Termination n 0 Complianc ite Release release criter for unrestric ons (10 CFR Criterion: T ts in a Total p that does n r; and ow As Reaso ced to levels 4 describes

n. This Cha

n.

General Site tion provide nd and grou on of site ological Inv tive, Genoa CBWR facili of Genoa (po orthwest) is R shore of th e miles sout re, is an unin n Figure 6-2 re (LSE) fenc ite Geology WR is located Central Low d as approxi ial deposits.

f the Dresh mately 650 fe Water Reactor Plan ce with the Criteria ria for the L ted release R 20.1402):

The residual Effective D not exceed 25 onably Achi that are AL the method apter describ Description es a general undwater us geology a vestigation R Wisconsin (

ity is located opulation ab Reno, Minn he Mississip thwest of the ncorporated 2, with a m ce shown in y

d on the east land Physio mately 15 fe

. These unc hbach Group eet below the r

e Radiolog a Crosse Bo specified in radioactivity ose Equivale 5 mrem/yr, i ievable (ALA ARA.

ds and resul bes the met n

description e in the vi and hydrog Report, La 1).

d 17 miles so bout 800) (se esota, an un pi River. Th e plant. Vic hamlet of a more detaile Figure 6-3.

bank of the ographic Pro eet of hydrau onsolidated p and by de e ground sur 6-1 gical Crite oiling Water n Title 10, S y that is dist ent (TEDE) including tha ARA) Criter lts for demo thods for de of the geolo cinity of sit geology is Crosse Boi outh of the C ee Figure 6-nincorporated he nearest c ctory, Wiscon about 80 peo d view of t Mississippi ovince. The ulic fill over deposits are ense Precam rface (bgs).

eria for Lic Reactor (LA Section 20.14 tinguishable to an averag at from grou rion: The res onstrating co emonstrating ogy and hyd te are also provided in iling Water City of La C 1). The nea d hamlet of community i nsin, five m ople. The LA the facilities i River in the local geolo rlying 100 to e underlain mbrian cryst cense Ter ACBWR) are 402, of the from backgr ge member o undwater sou sidual radioa ompliance w g complianc drogeology described.

n Haley &

Reactor, D Crosse and a arest commu about 300 p in Iowa is N miles south o ACBWR lice s inside the e Wisconsin ogy of the o 130 feet o by flat lyin talline rocks mination e the radiolo Code of Fe round radiat of the critica urces of drin activity has b with the AL ce with the at the LACB A detailed

& Aldrich, Dairyland P mile south o unity (three m people locate New Albin f the plant o ensed site ar e LACBWR n Driftless se site is gene f glacial out ng sandstone s encounter ogical ederal tion al nking been LARA Dose BWR d site Inc.,

Power of the miles ed on (pop.

on the rea is R Site ection erally twash e and ed at

La Cross License T Revision The prim 0 to 2 bgs a 20 to thickn 30 to grave 100 t 115 t 6.2.2. S Regional it is likel the surfa groundw influence 6.2.3. A The LAC the Miss bounded Engineer The 163.

the 1 the G and i locate an are (ISFS an ap from the la oil) fu wash a parc The area and fresh to the G-se Boiling W Termination n 0 mary soil type 20 feet bgs. H and described 30 feet bgs.

ness of 7 to 100 feet bg el below the o 115 feet b o 135 feet b ite Hydroge lly, groundw ly that the gr ace water. G water flow an ed by the riv Area Land U CBWR facili sissippi Rive by the Mi rs (USACE) 5 acre site is

.5 acre LAC Genoa-3 (G-3 s owned and ed to the sou ea south of G SI) is located pproximately past operati and north of fueled power hing area (an cel of land to a of the Miss h water fishi 3 station loc Water Reactor Plan es encounter Hydraulic Fi d as light bro

. Brown to g 28 feet,

s. Brown, fin finer sands, gs. Brown fi gs. Brown fi eology water flows f roundwater f Groundwater nd also show er stage.

Use ity is located er. Althoug ssissippi Ri property to s comprised CBWR facilit

3) coal-fired d operated by uth, adjacent G-3 where th d,

y 36 acre are

ions, the LACBW r plant (remo approximat o the east of sissippi Rive ing) and com cated south o r

red at the site ill - Fill sand own to brow grey, fine to m ne to medium ine to mediu ine to mediu from the blu flow directio r elevation ws seasonal v d in the far w gh the site a ver to the w the north, an of the follow ty,

, 379 MWe e y Dairyland t to LACBW he LACBWR ea surroundin WR plant wa oved in 1989 ely 900 m2 c f Highway 35 er adjacent t mmercial bar of the LACB 6-2 e are:

ds are encou wn, fine to m medium fine m sands that um sand and um sand with ff towards th on turns do data from e variation on u western porti area is 163.

west, a rail nd a wildlife wing:

electric pow Power Coop WR, R Independe ng the ISFSI s the site of

9) which now coal ash land 5, across fro to the site is rge and ship BWR plant).

untered from medium sands e sands unde t also have z fine to medi h trace silt, o he Mississip ownstream a eight onsite upward and ion of Verno 5 acres, it i line to the e and fish ref wer station th perative (DP ent Spent Fu I containing the former G w includes th dfill is also p om LACBWR s used for re p traffic (e.g.

There is a p m approximat s with occasi erlie the fill, zones of coar ium gravels, occasional zo ppi River. Cl as groundwa e wells agre downward g on County on is relatively e east, U.S.

fuge to the s hat was comp PC). The G-uel Storage In the closed c Genoa-1 (G-he site switch present),

R.

ecreational p

. barges of c public boat l tely 0 to 20 f ional fine gr with an ave rse sand and ones of grav loser to the ater discharg ees with reg gradients tha n the east ba y isolated as Army Corp outh.

pleted in 196 3 station is nstallation coal ash land

-1) coal (and hyard and ba purposes (bo coal are deliv landing on th feet

ravel, rage d fine vel.

river, ges to gional at are ank of s it is ps of 69 dfill d later arge oating vered he

La Cross License T Revision site, loca Mississip for huntin National Lock and north of operated from daw maintain LACBW The clos no reside 6.2.4. A There are in 1963 t LSE and to the G-Highway B

6.3.

The conf buildings All but t correspon that will The belo 1 and sho basement water tab one foot As seen outside o adjacent land area Chapters areas out The struc basement will be r structure liner will se Boiling W Termination n 0 ated approxim ppi River Na ng, fishing a Fish Hatche d Dam No. 8 the site. Th by the USA wn to dusk s a highwa WR site, acros est town is G ences within Area Ground e two water to 129 feet are still in u 3 plant. Reg y 35.

Basements, S figuration o s at the time two LACBW nds to an el remain inta w ground po own in Figur t below 636 ble elevation below the av in Figure 6-of the LSE b open land a as and build 2 and 5 for tside of the L ctures to be ts, isolated s removed. T s in this LTP l remain; all Water Reactor Plan mately 4,000 ational Wildl and recreatio ery.

8, located on he dam is a ACE. This fa during the ay wayside ss from Lock Genoa, locat 2,000 feet o dwater Use supply well and 116 fee use as potabl gionally, ther Structures a f the remain of license te WR building levation of 6 act are the L ortions of the res 6-4 and 6 foot elevati

n. Note that verage water

-2, there are but within th areas were n dings outsid r additional d LSE.

backfilled w sumps and r The backfill P Chapter.

interior con r

0 feet south o life & Fish R onal activitie n the Mississ 110 feet wid acility also al months of A off State H k and Dam N ted approxim of any LACB ls on the site et bgs, respe le water for L re are five do and Piping t ning backfil ermination is gs will be d 636 foot Av LACBWR A e buildings t 6-5. Figure ion which is there are als r table eleva numerous b he LACBWR ot used to su de of the LS discussion an will be com emaining po led structure For the Rea crete and the 6-3 of the plant.

Refuge just s es. Further so sippi River a de, 600 feet llows public April throug Highway 35 No. 8.

mately 1 mil BWR structu e (Deep Wel ectively. Bot LACBWR. S omestic well to Remain a lled basemen s designated emolished t verage Mean Administratio to be demoli 6-6 provide the only ba so three very ation.

buildings ass R licensed b upport LAC SE fence are nd justificat mprised of co ortions of fo es are gener actor Buildin e steel liner There is a p south of the outh are pub at mile 679.2 long lock a c access to a gh Novembe 5 approxim le to the nor ure.

ll 3 and Dee th wells are Separate gro ls south of th after Licens nts, buried d as the End to at least th n Sea Level on Building ished and ba es a cross-sec sement with y small sum sociated wit boundary. H CBWR opera e designated tion of the no oncrete only oundations.

rally referre ng, only the will be remo portion (Poo site which h blic land are 2, is approxi and dam stru an observatio er. The Sta mately 1/2 mi rtheast of th ep Well 4) th located upg oundwater w he LACBW se Terminat piping, open d State.

hree feet bel (AMSL). T and LACB ackfilled are ction of the h a portion b mps with floo th the G-3 c However, the ations. The d as non-imp on-impacted y and includ All systems ed to as eith concrete ex oved. All re ol 9) of the U has limited a as and the G imately 0.6 m ucture owned on platform, ate of Wisc ile north o he site. Ther hat were inst gradient from wells supply w R site and ea tion (End St n land areas low grade w The two buil WR Crib H listed in Tab Reactor Bui below the av ors that exte oal plant tha ese building majority of pacted. See d classificati de full and p and compo her basemen terior to the emaining Upper access Genoa miles d and open onsin f the re are talled m the water ast of tate) s and which dings House.

ble 6-ilding erage end to at are s and f open LTP ion of partial nents nts or steel

La Cross License T Revision Table 6-Baseme Reactor Waste T Waste G Remain concrete criteria.

For the Treatmen designate assessme Remainin a unique low pote steel line In additi Reactor B and need inapprop remain is the relati WGTV w Remainin As seen relatively are very separatel se Boiling W Termination n 0 1

Basem Grou ent/Structure r Building Treatment Bu Gas Tank Va ning Structur Piping and V Tunnels Reactor/Gene Chimney Sla Turbine Sum Turbine Pit will be dec purpose of nt Building (

ed as the R ent and Fina ng Structure configuratio ential for con er is removed on, the FRS Building. T ds to be ad riately aver s not particu ively higher was evaluate ng Structure in Table 6-y low contam small in siz ly does not p Water Reactor Plan ments and B nd surface e e

uilding ault res Ventilation erator Plant ab mp contaminate dose assess (WTB), and Remaining S al Radiation es. There are on, includin ntaining sign

d. This leads S design can The WTB ha ddressed sep raged with t ularly condu contaminat ed separately s, which req

-1, the Rema mination pot ze. Treating provide a me r

Below Grou elevation is Materi remain Con Con Con Con Con Con Con Con d as necess sment, the b d Waste Gas Structures. T n Survey (F e several reas ng a portion nificant resi s to unique d n effectively as the highes parately to the other st ucive to an e ion potentia y because th quires differe aining Struc tential. Two each of the eaningful dis 6-4 nd Structur 639 feet AM ial ning Fl Su ncrete ncrete ncrete ncrete ncrete ncrete ncrete ncrete sary to meet basements o Tank Vault This creates FRS) design sons for this below the a dual radioac dose assessm y accommod st contamina ensure that tructures. Th efficient FRS al this loss o e floor is at ent modeling ctures consis of the struct e basements stinction in d res to Rema MSL loor and Wa urface Area 511.54 101.90 460.04 177.07 359.59 117.86 5.64 7.09 t the 10 CF other than th t (WGTV) ar s four separa

Reactor B s organizatio average wate ctivity after ment assump date a survey ation potenti t the source he small siz S design an of efficiency a lower elev g parameters st of a grou tures, the Tu s in the Re dose modelin ain in LACB all (m2)

Fl (f

4 0

4 7

9 6

FR 20.1402 he Reactor re grouped i ate areas to Building, W on. The Reac er table elev all interior ptions and FR y unit consi ial of all End e term in t ze of the W d implemen y is consider vation than t

s.

up of structu urbine Sump emaining Str ng due to the BWR End S loor Elevatio feet AMSL) 612 630 621 629 629 635 618 618 unrestricted Building, W into one cate consider in TB, WGTV ctor Buildin vation and a concrete an RS classifica sting of onl d State struc the WTB is WTB structu ntation but d red justified the WTB an ures that all p and Turbin ructure cate eir generally State on d use Waste egory dose V and ng has a very nd the ation.

ly the ctures s not ure to due to

. The nd the have ne Pit, egory y

La Cross License T Revision similar e would re LTP Cha The End associate Circulatin circulatin piping is that pene tunnel to penetrati End State Adminis piping, l High Pre to G-3 Well wa Storm W Remaini The pote on the fin La Cross extensive subsurfac monitorin collected plant-der be perfo exposed.

se Boiling W Termination n 0 elevations an esult in unne apter 5 for di d State will ed with conta ng Water D ng water dis defined as etrates walls o contain all ons. There i e is listed in Table De stration Build leach field lat essure Servic ater piping for Water Piping ing portion of ential for sig ndings of the se Boiling e characteriz ce soil con ng results d d under the T rived radionu rmed after Water Reactor Plan nd contamin ecessary com iscussion of also includ aminated op Discharge pip scharge. For that contain and is embe l systems pip s no embedd Table 6-2.

e 6-2 Bu escription of P ding Sanitary terals, and tan ce Water from r Well #3 f Circulating nificant surf e EnergySol Water Reac zation perfo ntamination own gradien Turbine Bui uclides abov the Turbine r

nation poten mplexity in F the FRS pro de a limited perational sy pe which w r the purpos ed in soil. T edded in con ping that ra ded piping pr uried Piping Piping System inclu nks m LACBWR C Water Discha face or subsu lutions Techn ctor Historic ormed in 20 under the nt of suspect ilding in the ve backgrou e Building 6-5 ntial. Treatin FRS design, ocess.

d number o stems. The e was used as se of this L Typical comm ncrete. The d an between b resent. The b g to remain uding drain Crib House arge Pipe urface soil c nical Suppor cal Site Ass 014 (see LT Turbine Bu ted broken d e vicinity of und. Full cha foundation ng the Rem implementa of buried p exception is for liquid e License Term mercial pow design of th buildings wh buried pipin in LACBW 104 2

7 94 70 938 3

52 contaminatio rt Document sessment (H TP Chapter 2 uilding base drain lines.

f the suspect aracterizatio is removed maining Stru ation and do ipes, with t the remaini effluent disc mination Pla wer plants als e LACBWR hich elimina ng to remain WR End Stat Quantit 4 of 4Sched 57 of 2 P 2500 gal septi 750 gal dosin 4 gal distribut 8 perforated 144 4 PV 50 of 6 222 of 8 511 of 3 95 of 2 8 of 48 conc steel grates a 100 of 10 25 of 60 ste on at LACBW t (TSD) RS-HSA) (2) an 2). There a ed on posit However, g t drain lines on of the sub d and the un uctures separ cumentation the majority ing portion o charge as we an (LTP), b so contain p R plant inclu ated the nee in the LACB te y

d. 40 PVC PVC ic tank ng tank ion tank 4 PVC VC 8

3 crete pipe at grade PVC eel pipe WR is low b

-TD-313196 nd the resul are indication tive groundw geoprobe sam s did not ide bsurface soil nderlying so rately

n. See y not of the ell as buried piping udes a ed for BWR based 6-003, lts of ns of water mples entify l will oil is

La Cross License T Revision Low con broken f located d concentra character levels tha of ground F

6.4.

The Re Consolid Radiolog the next DPC firs 1949 an were acq total area The G-1 LACBW in 1987.

operation meet cur projected Resident as it is b the north that wou the prese foreseeab property In summ plans to infrastruc 25 years Finally, t develop the DPC plausible discussio LACBW se Boiling W Termination n 0 ncentrations o floor drains down gradi ations. In la rization and an found in dwater samp Future Land easonably Fo dated Decom gical Criteria 100 years. T st acquired la additional 1 quired in 196 a owned or c plant bega WR constructi DPCs thi n as a major rent environ d remaining ial use of the ounded by t h, and a wild ld be more s ence of over ble future re to recreation mary, the DP change the l cture to supp

. Adjacent l there are larg for residenti site from in e in accord on of future WR dose asse Water Reactor Plan of groundwa under the T ent of the te 2012, five d license ter 1983, predo pling results.

d Use Scenar oreseeable S mmissioning a (NUREG-The Reasonab and at the si 8.6 acres we

62. Finally, a controlled by an operation ion began in ird plant on generation nmental stan operation lif e site over th the Mississip life and fish suitable to ad r 36 acres of sidential dev nal use at so PC site has b land use in t port the sites and, and a p ge tracts of l ial use withi ndustrial use dance with land use, ssment is the r

ater contamin Turbine Buil Turbine Bu e additional rmination. R ominantly H rio and Ave Scenario, is Guidance 1757), (3), T bly Foreseea ite in 1941to ere acquired an additiona y DPC was th n in 1941 a n 1963, was nsite, G-3, b resource to dards and is fe of G-3 is p he next 100 ppi River to refuge to th dditional res f closed coal velopment. B me point in been in cont the future. T s future use f part of the D land nearby in at least th

. Residentia NUREG-17 the Average e Industrial W 6-6 nation have lding. Grou uilding iden monitoring Results indic

-3. See LTP erage Memb s defined in

- Character Table 5.1 as able Scenario o build its fi d for G-1 coa al 26.8 acres hen, and con and was dec completed i began comm the DPC sys s currently p projected to years appea the west, a he south. The sidential dev l ash landfil Based on sur the distant fu tinuous indu The site cont for power su DPC site is c that would b he next 100 l land use is 757, Table e Member o Worker.

been identif undwater sam ntified conta well pairs w cated lower P Chapter 2, ber of the C n NUREG-1 rization, Su s a land use o for LACB irst coal-fire al ash dispo was filled b ntinues to be commissione in1967, and mercial opera stem. The G erforming a be 20-25 ye ars unlikely.

rail line to t ere are sever velopment th lls further su rrounding la future is mor ustrial use fo tains a trans upply after G currently us be preferabl year time p s therefore c 5.1 definiti of the Criti fied adjacent mpling in 1 amination a were installe groundwate section 2.3.

Critical Grou 1757, Volum urvey, and D scenario tha WR is indus ed generation osal. An addi by dredging e, 163.5 acre ed and dism was perman ation in 196 G-3 plant has a major turbi ears.

The site is r the east, US ral small com han the DPC upports the a and use, the c re likely than or 74 years smission stat G-3 is decom ed for recre le, and more period than t ategorized a ions. Base cal Group (

t to the susp 983 from a at relatively ed to suppor er contamin

.7 for a sum up me 2, Revisi Determinatio at is likely w strial use.

n station, G-itional 80.8 in 1962-63.

es.

mantled in nently shut d 69 and cont s been updat ine overhaul relatively iso SACE proper mmunities ne C site. In add assumption conversion o n residential and DPC ha tion and valu mmissioned i eational purp e cost-effecti the conversi as less likel ed on the a (AMCG) fo pected a well y low rt site nation mmary ion 1 on of within

-1. In acres The 1989.

down tinues ted to

l. The olated rty to earby

dition, of no of the use.

as no uable in 20-poses.

ive to on of ly but above or the

La Cross License T Revision D

6.5.

Dose mo license t 25 mrem model an There are as follow groundw very low majority concrete currently the remai remain w contamin groundw summed An overv descriptio 6.5.1. B The dose designate residual r The base altered to The BFM the concr Excavati The resu mrem/yr group. It portion r conserva 6.5.1.1.

The BFM residual material installatio Groundw Spoils (B se Boiling W Termination n 0 Dose Model odeling is pe ermination w m/yr criterion nd computati e four poten ws for the p water. The in w potential o of residual of backfille y present at t ining portion was not assoc nation. The water exposur as applicabl view of the ons and resu Backfilled Ba e model for ed as the Bas radioactivity ement End S o a condition M conceptua rete remains on geometry ults of the B per mCi tot cannot be r remain in th atively includ BFM M Insitu geom radioactivity and 2) expo on of an ons water (BFM BFM Insituds Water Reactor Plan Overview erformed to will not res

n. This sectio ional method ntial sources purpose of d ntact LACB of containin radioactivit ed basement the LACBW n of the Circ ciated with c potential fo re factors w le to demons dose assessm ults are provi asements backfilled b sement Fill M y remaining i State will be n that would al model incl s in the as-y where som BFM dose tal activity f ruled out tha he ground.

de the sum o Insitu Scena metry includ y as a result osure to dril site water su Insitugw). T

).

r demonstrate ult in a dos on provides ds for dose a of residual dose modeli BWR Admin ng significan ty to remain ts. There is WR site or wi culating Wat contaminated or significan were calculat strate compli ment method ided in sectio basements to Model (BFM in the basem e comprised d not realisti ludes two so left configu me or all of th assessments for each of at a portion o Therefore, of the BFM I ario des two expo t of leaching lling spoils upply well. T The drilling 6-7 e that residu se to the AM a general ov assessment.

radioactivity ing; backfill nistration Bu nt levels of n at the tim no indicatio ll be present ter Discharge d systems an nt groundwa ted. The dos iance with th ds for the fo ons 6.7 to 6.

o remain belo M). The BFM ments.

of backfille ically allow ource term g uration at th he concrete i s are expres the three b of the backfi the final do Insitu and BF osure scenari g from the b that are bro The well wa spoils scena ual radioactiv MCG (indus verview of th y in the End led basemen uilding will residual rad me of license on that sign t in the End e Pipe, the li nd is expecte ater contami se from each he 25 mrem/

our sources

.17.

ow 636 foot M calculates ed concrete s the remainin geometries; 1 he time of li is excavated ssed as Dos asements an filled structur ose for dem FM Excavat ios; 1) expo backfilled c ought to the ater scenario ario is design vity remaini strial worke he LACBW d State that nts, soil, bu also remain dioactivity, e terminatio nificant soil State. With imited burie ed to contain ination is al h of the fou

/yr dose crite is provided t elevation (

s the dose to structures th ng structure

1) the Insitu cense termin and brought se Factors (

nd the Rema res could be monstrating tion dose.

sure to well oncrete surf surface dur is designate nated as BFM ng at the tim er) exceedin R site conce were catego uried piping n intact but if any. The on will be in contaminati h the excepti ed piping tha n minimal, if lso very low ur sources w erion.

below. Det (see Table 6 the AMCG hat are physi s to be occu u geometry w nation and 2 t to the surfa (DF) in uni aining Struc e excavated compliance water conta faces into th ring the assu ed as BFM I M Insitu Dr me of ng the eptual orized

, and has a e vast n the ion is ion of at will f any, w but will be tailed

-1) is from ically upied.

where

2) the ace.

its of ctures and a e will aining he fill umed Insitu rilling

La Cross License T Revision The conc floors an with the radioactiv release o water sup and flow a clean c direct ex pathway The BFM are broug terminati The resi installatio brought t pathways The BFM (RESRA spreadsh assessme basement at the tim for each with the 6.5.1.2.

The BFM excavate conserva credit for assumed which is contamin Excavati mrem/yr the avera are not ex BFM Ex Remain se Boiling W Termination n 0 ceptual mod nd walls is r concrete s vity is relea occurs imme pply well is w to the well cover of at l xposure and to the indus M Insituds sce ght to the su ion, before a idual radioa on is assum to the groun s are the sam M Insitugw d AD) v7.0 m eet calculati ents are expr t (and the Re me of license Radionuclid 25 mrem/yr BFM M Excavatio d and spre atism, the exc r radioactive to inadverte consistent w nation. The on DFs that per total m age concentr xceeded.

xcavation DF ning Structur Water Reactor Plan del for the B eleased to a surfaces afte ased instantl ediately after assumed to is conservat least 3 feet i soil ingestio trial worker enario assum urface. The any leaching activity in t ed to be ina nd surface, a me as those th dose assessm model. The ions coupled ressed as DF emaining St e termination de of Concer dose criterio Excavation on scenario a ad on the cavation is a e decay. Th ently mix w with the gui e calculation are expresse Ci. The fun ration in the Fs were calc res consisten r

BFM Insitugw adjacent fill er backfill.

y into the fi r license ter be installed tively model is present ov on/inhalation AMCG is d mes that the d well installa from concre the floor co advertently m and spread o hat apply to ment is imple BFM Insitu d with RESR Fs in units o ructures) (se n, as determi rn (ROC), an on.

Scenario assumes tha ground sur assumed to o e residual ra with the mas idance in NU n is perform ed in the sam ndamental d excavated c culated sepa nt with the B 6-8 w scenario a through leac The scenar fill which is rmination tak d adjacent to led assuming ver potential n is negligib drinking wate drilling spoi ation is assu ete occurs an oncrete that mixed with t ver a 15 cm contaminate emented usin uds dose as RAD modeli of mrem/yr ee Table 6-1 ined by the F nd summed at some or a face at som occur immed adioactivity ss of structu UREG-1757 med using E me units as t driver of the concrete is li arately for th BFM Insitu D assumes that ching into w rio assumes then treated king no cred o the down g g that structu lly contamin ble or zero.

er from the o ils from the i umed to occ nd taking no t is contact the fill mate m thick layer ed surface so ng the RES sessment is ing. The res per mCi tot

). The inven FRS, will be as necessary all of the bac me time aft diately after remaining in ural concrete 7, Appendix Excel sprea the DFs for t BFM Excav imited such t he Reactor B DF calculati t the residua water that co that 100%

d as contam dit for radio gradient edg ures are not nated surfac The BFM I onsite well.

installation o cur immedia o credit for ra ted by the erial above t

r. The BFM oil.

idual RADi s implemen sults of the tal activity i ntory of resid e multiplied y, to demons ckfilled stru ter license license term n the backfi e removed d J, for addre adsheet and the BFM Ins vation DF c that the surf Building, W ions.

al radioactivi omes into co

% of the res minated soil.

oactive decay ge of the bui present. Bec ces the dose Insitugw exp of the onsite ately after lic adioactive d borehole d the floor sur Insituds exp oactive mat nted using E BFM Insitu nventory in dual radioac by the BFM strate compl ucture concre termination mination takin lled baseme during excav essing subsu results in situ scenario calculation is face soils DC WTB, WGTV ity in ontact sidual The

y. A ilding cause from osure e well cense decay.

during

rface, osure erials Excel dose each ctivity M DFs liance ete is

. For ng no nts is vation urface BFM o, i.e.,

s that CGLs V, and

La Cross License T Revision 6.5.2. S Derived C radioactiv used to p For cons contained cm woul contamin modeling Using a contamin potential a clean so In the u during F discovere Commiss Standard with guid 6.5.3. B With the piping to contamin conducte The conc two scen internal s layer of s the soil m the pipe e 2.54 cm transport Discharg assumes layer of s and Exca scenarios in units o se Boiling W Termination n 0 oil Concentratio vity in surfa perform the c servatism, a d in a 1 m de ld result in nation is ide g may be re 1 m thick nation with for subsurfa oil layer ove unlikely even FSS that ar ed geometrie sion (NRC) w d methods fo dance in NU Buried Pipin e exception o o remain a nation poten ed to develop ceptual mod narios: Insitu surfaces of t soil in an are mixing layer excavation.

layer of soi t and migrati ge Pipe whi that the pip soil on the g avated soil

s. RESRAD of dpm/100 c Water Reactor Plan on Guideline ace soils tha calculation.

and to optim epth from th lower dose entified at L quired if the kness reduc a thickness face contamin er a contamin nt that geom re not boun es will be ad will be notif or RESRAD UREG-1757.

ng of the portio at LACBWR ntial is mini p DCGLs for el for the bu u and Excav the pipe is a ea equal to th r is 15 cm d The Insitu sc l with no cr ion. This is a ch will be pe is excavat ground surfa via the sam modeling is cm2.

r e Levels (DC at correspon mize remed he surface. A (i.e., higher LACBWR w e conceptua ces the pot s somewhat nation to rem nated soil lay metries are nded by the ddressed by fied if additio parameter s The AMCG on of the Ci R was asso imal (see T r pipe.

uried piping vation. In th assumed to i he internal s due to the ex cenario assu redit taken fo a conservativ filled with ted followed ce with no c me pathways s used in con 6-9 CGLs), in un nd to the 25 diation effic A standard su r DCGL). H with a thickn al model assu tential for greater tha main in the yer at depth.

encountered e assumed additional m onal modelin selection and G for soil is th irculating W ociated with Table 6-2).

dose assessm he Insitu sc instantaneou surface area xtensive gro umes that the for the prese ve assumptio a flowable d by instant cover. The In s applicable njunction wit nits of pCi/g mrem/yr do ciency, surfa urface soil c However, in ness greater umed a 15 delays or an 15 cm is End State w d during co 1 m soil c modeling. T ng is require d uncertainty he Industrial Water Discha h contamina A buried p ment is simi cenario the r usly release a of the pipe.

ound surface e released ra ence of the p on, particula fill materia release of a ndustrial Wo to the BFM th Excel spr g, were devel ose criterion face soil is ontaminatio the unlikel than 15 cm cm contami unnecessary s encountere with a geome ontinuing ch ontaminatio The U.S. Nu ed.

y analysis ar l Worker.

arge Pipe, no ated system piping dose ilar to the B residual rad and mix wit For the Exc e disturbance dioactivity i pipe to reduc arly for the C al. The Exc all radioactiv orker is expo M and soil readsheet to loped for res

n. RESRAD defined as on thickness ly event tha m additional ination thick y remediatio ed. There is etry compris haracterizatio on thickness uclear Regul re used cons one of the b ms and ther assessment BFM and inc dioactivity on th a thin 2.5 cavation scen e associated is a below gr ce environm Circulating W cavation sce vity into a 1 osed to the I dose assess calculate DC sidual D was s that of 15 at soil dose kness.

on if s low sed of on or s, the latory istent buried refore t was cludes n the 54 cm

nario, d with round mental Water enario 5 cm Insitu sment CGLs

La Cross License T Revision 6.5.4. E Groundw license te Low leve well pair groundw contamin 6.5.5. R The LA Switchya contain r in NURE and Equi 6.5.6. D The vario exclusive BFM Ins the activ with the encounte The dos simultane demonstr following maxim maxim sum o maxim maxim maxim 6.5.7. A As discu foreseeab use scena well and A qualita lower tha se Boiling W Termination n 0 Existing Gro water monito ermination. T els of H-3 an rs were insta water concen nation presen Remaining A ACBWR Ad ard Fire Ser residual rad EG-1575, Su ipment Manu Dose Summa ous source t

e. For exam situ drilling vity released groundwate ering the we e from soi eously with rate complia g using the m mum BFM I mum BFM E of the BFM mum soil do mum buried mum existin Alternate Sc ussed in se ble scenario arios were co onsite garde ative evalua an that calcu Water Reactor Plan oundwater oring has be The final mo nd Sr-90 hav alled at the si tration are p nt at license Above Grou dministrative vice Water dioactivity. T upplement 1 ual (MARSA ation for Co terms and co mple, althoug spoils scena to groundw er activity r ll. Therefore l, buried p the BFM do ance with th mean values Insituds dose Excavation d Insitugw dos

ose, d piping dose ng groundwa enarios ection 6.4, o based on p onsidered in en.

ation of a re ulated for the r

een and wil onitoring dat ve been iden ite. Groundw provided to termination, und Building e Building, System will They will b

, Multi-Age AME) (4).

ompliance onceptual m gh a low pro ario and subs water in the released fro e, the BFM iping, and ose scenario he 25 mrem/

from FRS:

e, dose, e from all ba e,

ater dose.

the industr past and proj ncluding recr creational la e industrial u 6-10 ll continue t te will depen ntified in sam water exposu perform do

, if any.

gs LACBWR l remain int be free rele ncy Radiatio models discu obability, a sequently ex BFM Insitu om another Insitugw dos groundwate os. Therefore

/yr dose crit asements com rial use sce jected use o reational use and use scen use scenario to be condu nd on the ev mples collect ure factors in ose assessme R Crib Hou tact. The b eased in acc on Survey a ussed above given basem xcavated. An ugw scenario basement th se will be su er could als e, the final s terion will in

mbined, enario was of the LACB e, and reside nario conclu because occ ucted until valuation of ted since 20 n units of m ent for exist use and T uildings are cordance wi and Assessm are not nece ment could b nother exam for one bas hat is down ummed acro so be view site-wide do nclude the s selected a BWR site. Tw ential use wit uded that th cupancy time sometime b sampling re 12 after five mrem/yr per p ting groundw Turbine Bui e not expect ith the guid ment of Mate essarily mut be subject t mple could be sement com n gradient b oss all basem wed as occu ose assessme summation o as a reason wo alternate th a water su he dose wou e would be l before esults.

e new pCi/L water ilding ted to dance erials tually to the e that mbines before ments.

urring ent to of the nably e land upply uld be ess

La Cross License T Revision than that the recre than assu The resid scenario spreadsh states tha assurance section 6 M

6.6.

A compr present a that have character the prima The initia and BFM the soil D ROC tha described 6.6.1. P EnergySo Decomm documen Reactor M Around Decomm fuel inve 10 CFR P The list o after elim with theo Co-60 an samples) coupled several a present d

Finally, Piping an were not se Boiling W Termination n 0 t assigned to ational land umed for the dent garden as defined i eet, to calcu at if the peak e that the sc 6.15.

Mixture Fra rehensive i at the LACB e not been rization but ary radionuc al suite mixt M DF dose as DCGLs and at will be c d in section 6 Potential Ra olutions TS issioning (5 nts were rev Materials, (6 Commercia issioning As entory assess Part 61 wast of activation minating nob oretical neut nd Ni-63 (th

. The revie with review additional ra during the de the results o nd Ventilatio already acco Water Reactor Plan o an industri use scenari industrial w ner land use in NUREG-ulate the dos k dose from enario is unl ctions for In initial suite BWR site. A positively could theore clide which i ture fractions ssessments.

d BFM DFs considered d 6.5.6.

dionuclides SD RS-TD-

5) establishe viewed incl 6), and NUR al Nuclear ssessment (7 sment condu te stream ana n product ra ble gases, rad tron activati he prominen ew of Refer w of the LAC adionuclides ecommission of concrete on Tunnels ounted for b r

al worker.

o the recreat worker.

e was consid 1757, Table se from the R m a less likely likely would nitial Suite of 21 radi As discussed identified in etically be p is Cs-137.

s were used The initial s to identify during the F s of Concern

-313196-001 ed an initia luding NUR REG/CR-428 r

Power 7). The revie ucted in 1988 alyses were a adionuclides dionuclides w ion products nt activation rence 6, wh CBWR fuel s being inclu ning of LAC core sampl were review by the assessm 6-11 In addition, tional users dered to be 5-1. RESRA Resident Ga y put plausib d be necessar Radionuclid onuclides w below, the i n LACBWR present, albe in the RESR suite mixture the insignif FRS and fin n and Initial 1, Radionuc al suite of p REG/CR-347 89, Residual Plants; O

ew also inclu 8 that was d also reviewe for conside with half-liv s with abund n products id hich include inventory a uded in the BWR.

es collected wed. No radi ments descri if a water s s intake rate e a less lik AD was use ardener alter ble scenario ry. The alter des were identifi initial suite R 10 CFR it at very lo RAD uncerta e fractions w ficant dose c nal dose su l Suite clides of C potential RO 74, Long-Li l Radionuclid

Origin, Dis uded an eva decay correc ed.

eration in the ves less than dances less dentified in s both activ and 10 CFR e list of tho d from the W ionuclides w ibed above.

supply well from the w kely but pla ed, in conjun rnate scenari o is signific rnate scenari ied that cou includes ma Part 61 an ow mixture f ainty analyse were used in contributors ummation fo Concern D OC. Two in ived Activat de Concentr stribution, aluation of a cted to Janua e initial suit two years, a than 0.01 pe LACBWR vation and Part 61 ana ose that cou WTB, React were positive were install well would be ausible land nction with E io. NUREG-cant then gr io is address uld potential any radionuc nalysis or d fractions, rel es for Soil D conjunction and final l or complianc During LAC ndustry guid tion Produc ration Within Inventory, LACBWR ary 2015. Se te was devel and radionuc ercent relati 10 CFR Pa fission prod alyses result ld be poten tor Building ely identified led in e less d use Excel

-1757 reater sed in ly be clides during lative DCGL n with ist of ce as CBWR dance cts in n and and spent everal loped clides ive to art 61

ducts, ted in ntially g and d that

La Cross License T Revision The resu in Table 6.6.2. M As descr develope WTB, an 1.27 cm fractions fractions Minimum concentra provided The mixt fraction justified across co se Boiling W Termination n 0 lting list of p 6-3. The pr Mixture Fra ribed in Re ed from conc nd Piping/Ve slices from

. The use of assigned to m Detectabl ation data av d in Table 6-3 T

ture was bas for all build in Referenc ores from the Water Reactor Plan potentially p ocess for det ctions for In ference 5, t crete core da entilation Tu the cores w f cores with o low abund le Concentr vailable. Th

3.

Table 6-3 sed on a com dings. The a ce 5 by a re e different ar r

present radio termining th nitial Suite the mixture ata collected unnels. The which were th h higher con dance radion ration (MD he mixture fr Initial Su and Mix Nuclide H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 Total mpilation of 1 application o eview of Cs reas. The pot 6-12 onuclides is he mixture fr Radionuclid fractions f d during cha vast majorit herefore use ncentrations nuclides wer C) values ractions assig uite of Poten xture Fract Mixt Fract 0.000 0.000 0.002 0.010 0.012 0.080 0.009 0.000 0.000 0.877 0.000 0.000 0.000 0.000 0.000 0.003 0.000 0.000 0.000 1.0 12 cores from of the comb s-137/Sr-90 tential effect called the I ractions is de des for the Initi aracterization ty of the act ed to determ was require re not overly which were gned to the I ntial Radion tions ture tions 071 065 294 038 221 048 907 008 015 736 093 080 045 014 013 306 037 004 005 00 m all buildin bined data to ratios whic t of uncertai Initial Suite escribed belo ial Suite rad n from the R tivity was lo mine the radi ed to ensure y influenced e in many Initial Suite nuclides ngs to determ o determine ch were rela inty in the m and is prov ow.

dionuclides Reactor Buil ocated in the ionuclide mi that the mi d by the rep cases the radionuclide mine one mi the mixture atively cons mixture fracti vided were

lding, e first ixture ixture ported only es are ixture e was istent ions

La Cross License T Revision on the fin mixture i uncertain because Complian concentra emitters insignific soil DCG that is po demonstr The prim Detect (H FRS. Ho conserva fraction.

There w predomin evaluatio less than HTD rad MDC va Therefor soil and u contribut sufficient S

6.7.

Site-spec 10 CFR 2 radionuc percentag The surf uniformly expectati geometry with conc 6.7.1. S There is based on subsurfac monitorin se Boiling W Termination n 0 nal complian is comprised nty in the mi the FRS f nce with th ations for g that were cant contribu GLs and Bur ositively iden ration.

mary source o HTD) mixtu owever, the ative and pr See section were only a nantly Cs-1 on of the rela the MDC. W dionuclides t alue which c e, the radion used to deter tor dose per t margin to a oil Dose As cific DCGLs 20.1402 dos lide in order ge and the fi face soil co y contamina ions that at y consisting centrations e oil Source T limited pote n the result ce soil con ng results do Water Reactor Plan nce dose cal d of Cs-137 ixture fractio for structure e 25 mrem/y gamma-beta designated utor dose ca ried Pipe D ntified durin of potential ure fractions method use ovides suffi 6.13 for the a few posi 37, and th ative mixture When the C that are not could be ord nuclide mixtu rmine the so centage assi account for m sessment an s were devel se criterion r to provide inal list of R onceptual m ated 1 m lay the time of of a clean exceeding th Term ential for sig ts of soil c ntamination own gradient r

lculations is which is a ons for Cs-1 es and soil yr dose crit emitters. N as insignifi alculation an CGLs. The g FRS will b dose impact because the ed to calcula icient margi assessment itive soil s e concentra e fractions fo s-137 conce positively i ders of magn ure fractions oil ROC. Ho igned to soil mixture unce nd DCGL loped for res of 25 mrem/

an input to OC.

model assum yer of soil f license ter surface laye he surface so gnificant sur characterizat under the t of suspecte 6-13 s minimized beta-gamma 37, or any o l will be p terion will b Note that th cant contrib nd the corre additional d be directly c t from mixtu ere will be n ate the insig in to accoun of insignific sample resu ations were for the HTD ntrations are identified ar nitude highe s determined owever, as d l is demonst ertainty.

sidual radioa

/yr. A DCG the determi mes that the from the gr rmination re er of soil ov oil DCGL.

rface or sub ion perform Turbine Bu ed broken dr by the fact a emitter. T other beta-ga performed u be demonstr he dose con butors is al esponding ad dose from an calculated an ure uncertain no analysis o gnificant co nt for uncer cant contribu ults identifi insufficien radionuclide e low the rel re artificially er than the a d from the co described in trated to be activity in s GL was cal ination of in e soil conta round surfac esidual radio ver a contam surface soil med in 2014 uilding base rain lines. Ho that the vas There is no d amma emitti using gamm rated using ntribution fr lready accou djustments t ny beta-gam nd included i nty is limite of HTD radi ontributor do rtainty in th utor dose per ied during nt to provid es which we lative mixtur y increased actual concen oncrete core section 6.13 conservativ urface soil t culated for nsignificant c amination is ce downward oactivity wi minated subs contaminati

4. There ar ed on posit owever, geo st majority o dose impact ng radionuc ma spectrosc actual mea rom beta-ga unted for in to the BFM mma radionu in the compl ed to the Har ionuclides d ose percenta he HTD mi rcentage.

characteriza de a meani ere all report re fractions o due to usin ntrations pre es were appli 3 the insignif ve and to pro that represen each initial contributors s contained

d. There ar ill remain w surface soil ion at LACB re indication tive groundw probe sampl of the from

lides, copy.

sured amma n the

DFs, uclide liance rd-to-during age is ixture

ation, ingful ted as of the ng the esent.

ied to ficant ovide nt the suite dose in a re no with a layer BWR ns of water les

La Cross License T Revision collected plant-der continuin soil expo Soil char biased su collected 137 abov indicated samples 60 result 6.7.2. S The AM apply:

Direc Inhal Inges Inges The agri milk, gra S

6.8.

The RES for the EnergySo Factors (

6.8.1. P RESRAD belong to location site-spec character exposure Behavior for the s changed LACBW for both t se Boiling W Termination n 0 d under the T rived radion ng characteri osed.

racterization urface soil sa d inside the L ve the MDC d Co-60 abov indicated Cs s greater tha oil Exposur CG at the L ct exposure t lation of airb stion of soil stion of wate cultural and ain and veget oil DCGL C SRAD model modeling olutions TS (8).

Parameter S D parameters o more than of the sourc ific) includi ristics of atm e to, the dose ral paramete ite. For the (e.g., param WR, the beha the BFM and Water Reactor Plan Turbine Bui nuclides abo ization after n results are amples and 7 LSE fence. T C with a ma ve the MDC s-137 above an MDC. The re Pathways LACBWR s to external ra borne radioac er from onsit d gardening table ingesti Computatio l was used to discussed D RS-TD-3 Selection Pro s are classifi n one catego e term and t ng the geoh mospheric an e receptor are ers define the e same grou meters for avioral param d soil dose a r

ilding in the ove backgr the Turbine provided in 79 subsurfac Thirteen of t aximum of C with a max e MDC with e Cs-137 res s and Critic ite is the In adiation ctivity te well pathways a on pathways on Model - R o calculate D below are 313196-004, ocess fied as behav ory. Physic the geologic hydrologic, g nd biospher e also consid e receptors up of recepto industrial u meters are ba assessments.

6-14 e vicinity of round. Subs e Building fo LTP Chapte ce soil sampl the surface s 1.07 pCi/g.

ximum of 0.

a maximum sults are all i cal Group ndustrial Wo are not appli s are therefo RESRAD v7 DCGLs for s e provided LACBWR vioral, metab cal paramete al characteri geochemical ric transport dered physic behavior co ors, a param use could be ased on an i f the suspect surface soil oundation is er 2 and sum les (at varyin soil sample a Two of the 287 pCi/g. F m of 0.161 p in the range orker. The fo icable to ind ore not includ 7.0 surface soil.

d electronic Soil DCGL bolic or phy ers are deter istics of the l, and meteo up to, but cal input para onsidering th meter value c e different industrial us t drain lines l will be e s removed an mmarized he ng depths to analyses resu e surface so Fifteen of th pCi/g with n of natural ba following ex dustrial land ded.

The RESRA cally in co L and Conc sical. Some rmined by th site (i.e., so orologic cha not includin ameters.

he conceptua could chang from reside se scenario a s did not ide evaluated d nd the under ere. A total six meters) ults indicate oil sample re he subsurface no subsurface ackground.

xposure path d use. The m AD output re onjunction crete BFM e parameters he geometry urce-specifi aracteristics.

ng, uptake b al model sel ge if the sce ential use).

and are the entify during rlying of 22 were d Cs-esults e soil e Co-hways

meat, eports with Dose s may y and c and The by, or lected enario For same

La Cross License T Revision Metaboli set of me

Physical, dose mod uses sing selection Argonne Priority 1 ranking i Probabil Priority 3 from the either as paramete site-spec from the Priority 1 negativel negativel and posit to positiv than 0.25 Consisten paramete Contamin Table 6.8 Figure 6-determin to determ 6.8.2. R The unce rounded radionuc respectiv Section I for. The practical with the for select Attachme for the un se Boiling W Termination n 0 ic parameter etabolic para

, behavioral deling to cal gle values fo n process is d National L 1 parameters is document listic RESRA 3 physical p parameter d signed site-er distributio ific paramet e RESRAD 1 and 2 par ly correlated ly correlated tively correl vely correlat 5 were assign nt with the ers were assi nation Fro

87.

-7 provides nistic parame mine the fina RESRAD Pa ertainty anal mixture fra lides, and en ve mixture f I.7.5 and ens threshold o implementa objective of tion of deter ent 6-1 prov ncertainty an Water Reactor Plan rs define cer ameters appli and metabol lculate soil D or input par described bel Laboratory (

s have the h ted in Attach AD 6.0 and R parameters w distributions specific det ons defined i ter distributi uncertainty rameters. A d to dose. T d parameters ated to dose ted paramete ned the med e guidance igned the me om Decom a flow ch eters and par l determinist arameter Se lysis include actions of 0 ntered into R factions. Thi sures that the of 0.1% for ation of the R f identifying rministic par vides a table nalysis. The r

rtain physiol ies to both th lic paramete DCGLs (and ameters and low.

(ANL) rank highest pote hment B to t RESRAD-BU were assigne defined in N terministic v in NUREG/C ions. The P analysis w A PRCC va The 25th perc

s. A PRCC

e. The 75th p ers. Priority ian value of in NUREG ean values fr mmissioning hart of the rameter distr tic paramete election for U ed all of the 0.1% or gre RESRAD for is approach e sensitivitie r including RESRAD un sensitive pa ameters thro e with the de references o 6-15 logical chara he BFM and ers are treate d BFM DFs) d generates a ked physical ntial impact the ANL rep UILD 3.0 Com ed either a s NUREG/CR values, evalu CR-6697, or Partial Rank ere used to alue less th centile of the C value grea percentile of 1 and 2 para f the paramet G-1757, sec from NUREG Parameter parameter ributions is u er set used to Uncertainty e initial suite eater. The c r the uncerta is consisten es of the sign radionuclide ncertainty an arameters fo ough the unc eterministic or justificatio acteristics of d soil dose as ed as determi

). The deter a single val l parameters t on dose an port, NURE mputer Code site-specific R-6697. Prio uated by un r evaluated b Correlation evaluate th han -0.25 w e parameter ater than +0.

f the parame ameters with ter distributi ction I.6.4.2, G/CR-5512 r Analysis selection pr used in a RE o calculate so y Analysis e radionucli concentratio ainty analys nt with the nificant radio es was prim nalysis modu r significant certainty ana values and ons for the p f the potenti ssessments.

inistic param rministic mo lue for dose s by priority nd Priority 3 EG/CR-6697, es, (NUREG value or th ority 1 and 2 ncertainty an by uncertain n Coefficien he relative s was consider distribution

.25 was con eter distribut h a PRCC ab ion.

, metabolic Vol. 3, Resi (NUREG/

rocess. The ESRAD Unc oil DCGLs.

des from Ta ns assigned is, were valu guidance in onuclides ar marily applie ule but is als t radionuclid alysis is discu parameter d parameter sel ial receptor.

meters in the odule of the

. The param y as 1, 2, 3 the least.

, Developme G/CR-6697) he median v parameters nalysis usin nty analysis u nt (PRCC) v sensitivity o red sensitive n was assign nsidered sen tion was assi bsolute value and behav idual Radioa

/CR-5512) set of sel certainty Ana able 6-3 tha d to the sel ues equal to n NUREG-re fully accou ed to facilit o fully cons des. The rati ussed below distributions lections are One e final code meter or 3.

This ent of (9).

values were g the using values of the e and ned to sitive igned e less vioral active (10) lected alysis at had lected their

1757, unted tate a istent onale

w.

used listed

La Cross License T Revision in Attach and the g with the paramete The cont specific s to ensure than the from Ref Conta Soil D Soil P Soil E Satur A site-sp paramete Support Hydrolog The Inha 5512, Ta equates t Inhalatio A similar industria residentia rate for a The RES 6697 Att Assumin majority report Us and 25 (2190*.7 (2190*.2 Site-spec Pumping LACBW 129 foot The 33.1 be repres se Boiling W Termination n 0 hment 6-1. T generic para process flo er distributio taminated ar soil type is s e efficient re typical defa ference 1 we aminated Zo

Density, Porosity, Effective Po rated Zone H pecific deter er based on Document gical Param alation Rate able 5.1.1 wh to 23 m3/d.

n Rate (m3/y r process wa l worker. NU al user whic a worker as f SRAD param

t. C, Table ng 5 days a of industria sers Manua outdoo 75)/(24*365) 25)/(24*365) cific paramet g Rate Param WR. The well depth is 109 m depth is a sented by a n Water Reactor Plan The basis fo ameter distri ow chart in ons are discu rea was assu sand. The de mediation (i ault value o ere applied:

one Hydrauli rosity, Hydraulic Gr rministic val a calculatio 14-006, Co eters in Supp parameter fo hich provide The inhala yr) = 23 m3/d as followed UREG/CR-5 h correspond follows: 1.31 meters Indoo 7.6-1, whic week and al work is e al for RESRA rs.

The

) =.1875

) = 0.0625.

ter distributi meters. There l depths are 9 feet (33.1 m assumed to b nominal 20 f r

or the behav ibutions (NU n Figure 6-ussed in more umed to be th epth of soil c if necessary) of 0.15 m. T ic Conductiv radient.

lue was also on performe onestoga Ro port of Dose for the indust es an annual ation rate th d ÷ 24h/d

• 2 to determin 5512, Table ds to 1.31 L/

1 L/d

• 250 w or and Outdo ch recomme 50 weeks p expected to AD Version correspondi

5. The Ou ions were de e are two exi 116 feet an m) below th be maximum foot screen d 6-16 vioral and m UREG/CR-6

7. The basi e detail below he full 7500 contaminatio

) and FRS if The followin

vity, o selected fo ed for a san overs & As e Modeling f trial worker inhalation r e industrial 2000 h/y = 1 ne the Drink 6.87, provid

/d. This rate work days/y oor Time Fr nds a media per year, thi be indoors.

6 (12), 75%

ng RESRA utdoor Tim eveloped for isting onsite nd 129 feet b he average w m well depth depth (6.08 m metabolic par 6697) are str is for the s

w.

0 m2 area ins on was conse f contaminati ng site-speci for the Satu nd soil type ssociates (C for the Zion R AMCG wa rate of 8400/

worker was 1917 m3/yr.

king Water In des a water e was conserv yr = 327 L/yr ractions were an indoor w is equates to Consistent

% of work ti AD Indoo me Fraction r the Well P e industrial w below the g water table el

h. The minim m) starting at rameters (NU raightforwar site-specific side the LSE ervatively as ion is found ific determin urated Zone in ZionSol CRA) Repor Restoration as derived fro

/y for a resid s then calcu ntake Rate p intake rate o vatively app

r.

e derived fro work day of o 2190 hou with Table ime is assum or Fraction n is then Pump Intake water supply ground surfac levation whi mum well dep t the average UREG/CR-5 rd and cons parameters E fence. The ssumed to be d at depths gr nistic param e Field Capa lutions Tech rt, Evaluatio Project (11) om NUREG dential user.

ulated as fol parameter fo of 478 L/yr plied as the in om NUREG f 8.76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> urs per year.

2-3 of the med to be ind n

paramete n calculated e Depth and wells suppo ce (bgs) (1) ich is 20 feet pth is assum e water table 5512) istent s and e site-e 1 m reater meters acity hnical on of

).

G/CR-

. This lows:

or the for a ntake G/CR-s/day.

. The ANL doors er

=

d as Well orting

. The t bgs.

med to e

La Cross License T Revision elevation between similar t distributi NUREG/

variabilit pumping develope persons o assuming which eq actual wa to provid The rema with the p 6.8.3. S The full Referenc The unce were sen The sens distributi Four Maj provided NUREG/

determin Table 6-paramete N

se Boiling W Termination n 0

n. The mode 6.08 m and to the NUR ion.

/CR-6697 d ty. For an ind g rate is inc ed. NUREG of 328.7 m3/

g four work quates to164 ater use at a de a range th aining param process flow oil DCGL U RESRAD U ce 8. The unc ertainty anal nsitive which sitive param ions in Shep ajor Soil Typ d in Referenc

/CR-6697 d nistic values 5). The unc ers evaluated Table 6-4 Radionuclide Cs-137 Eu-152 Eu-154 Note 1: NS indic Water Reactor Plan e of the rec 33.1 m whic REG/CR-66 oes not prov dustrial use cluded in t G-6697, Tabl

/yr. This val ers. A nomi 3.5 m3/yr. T an unknown at can be use meters in At w chart in Fig Uncertainty Uncertainty R certainty ana lysis results h are listed, meter for Cs-ppard and Th pes: A Comp ce 13 and w distribution.

for sand fro certainty ana d are listed in 4

Determ used in e

Kd in Con Zone 75th NS1 75th cates non-sens r

commended ch is 19.6 m 97 distribut vide a recom scenario, the the uncertai le 3.10-1 app lue is assum inal maximu These minim future indus ed to determ ttachment 6-gure 6-7.

y Analysis R Report for So alysis results for the Kd along with

-137 was as hibault, Defa pendium, (13 was therefore All non-se om Referen alysis results n Table 6-6.

ministic Val n to calcula taminated 1460 NS 7302 itive paramete 6-17 triangular d

. Note that th tion values mmended v e pump rate inty analysi plies a sanita med to be the um rate is a mum and max strial facility mine if the do

-1 not discu Results oil DCGL pa s are provide parameters the selected ssigned the ault Soil/Soli

) which are e assigned th ensitive Kd ce 13 as lis s and the se lues selected ate Soil DCG Kd in Uns Zone NS 75th NS r

distribution he site-speci of 6, 10, alue for we depends on s a nomina ary and pota e minimum assumed bas ximum value y on the site ose is sensitiv ussed above arameters is ed in Tables indicated th d determinist 75th percent id /Liquid Pa listed in Re he 75th perc d parameters sted in NUR elected deter d for Sensit GLs saturated NS 7302 NS is assumed ific distribut and 30 fo ell pumping industry. To al uniform able water us industrial w sed on suppl es are not in after licens ve to well pu were select s provided el 6-4 to 6-6.

hat only thre tic paramete tile value fr artition Coef eference 8. E entile value s were ass REG-6697, T rministic val ive Kd para Kd in Satur Zone NS NS NS to be mid-tion is reason or the trian rate due to o ensure that distribution sage rate for well pumping ly to 20 wo ntended to pr e terminatio umping rate ed in accord lectronically ee Kd param ers, in Table rom the san efficients, Kd Europium wa from the de igned the m Table 3.9-2 lues for all ameters rated NS NS NS

-point nably ngular high t well n was r four g rate orkers redict on but dance y with meters e 6-4.

nd Kd ds, for as not efault mean (see other

La Cross License T Revision N

N T

S 6.9.

The soil paramete Contamin unsaturat electroni se Boiling W Termination n 0 Table 6-5 Radionuc H-31 C-14 Fe-55 Ni-59 Ni-63 Co-60 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Note 1: Sand Kd NUREG-6697, T Table 6-6 Contaminated Contaminated Evapotranspi Wind Speed1 Runoff coeffi Saturated zon Well pump in b Parameter o Mass loading Indoor dust fi External gam Well Pumpin Depth of Soil oil Determi DCGLs we er distributio nated Zone F ted and satur cally with R Water Reactor Plan 5

Determ Kd pa lide K

7 1

ds not listed in Table 3.9-1 wa Soil DCG for Non-N Parameter d zone erosion d zone b param ration coefficie icient ne b parameter ntake depth of Unsaturated g for inhalation iltration factor mma shielding f ng Rate l Mixing Layer inistic Analy ere calculate ons replaced Field Capac rated zone. T Reference 8. T r

ministic par arameters fo Kd (cm3/g) 0.06 5

220 400 400 60 15 160 0.1 280 825 NUREG-6607 as used.

L Uncertain Nuclide Spec rate meter ent zone n

factor r

ysis and Soi d using the by the deter ity was also The full RES The Soil DC 6-18 rameter valu or soil DCG Radi Eu Eu Np Pu Pu Pu Pu Am Am Cm Cm 7 Table 3.9-2 f nty Result a cific Param Uncertaint Result median median median median 75th median median median median median 75th median 25th il DCGLs parameter s rministic valu changed fro SRAD Summ CGLs for the ues selected GL calculatio ionuclide u-1541 u-1551 Np-237 u-238 u-239 u-240 u-241 m-241 m-241 m-243 m-244 for this radionu and Determ meter Distrib ty Selected 0.0015 0.97 0.62 6.8 0.45 0.97 19.6 0.97 2.35E-05 0.55 0.4 986.1 0.15 set provided ues listed in om 0.2 to 0.

mary Report e Initial Suite d for non-se on Kd (cm 825 825 5

550 550 550 550 1900 1900 4000 4000 uclide. The mea ministic Valu butions d Deterministi 5

d in Attachm n Tables 6-4, 066 to be co t for Soil DC e are listed in nsitive m3/g) 0 0

0 0

an value from ues selected ic Value ment 6-1 wit 6-5 and 6-6 onsistent wit CGLs is prov n Table 6-7.

th the

6. The th the vided

La Cross License T Revision B

6.10.

The BFM the backf conceptu more det pathways The BFM (639 foot 20 feet b groundw seasonal and Vent the avera assumed The seas above 61 somewha in the sat The BFM exposure drilling s se Boiling W Termination n 0 Basement Fi M is used to filled basem ual model wa tail including

s. The comp M conceptua t), i.e., to an bgs at 619 fo water is in d groundwate tilation Tunn age water ta to be instal onal water f 19 foot and at of an exce turated zone M includes tw e pathways; spoils that ar Water Reactor Plan ll Conceptu calculate do ments to rem as provided g assumed p utational mo al model assu elevation of oot elevation direct comm er fluctuation nels, the sea able level, i lled in the sa fluctuations contacting b eption in tha (see Figure Table 6-7 wo scenario ingestion o re assumed t r

ual Model ose to the ind ain after lice in section 6 physical con odel is descr umes that al f 636 foot, a n (1) which d munication w

n. Based on asonal fluctu i.e., to the 6 aturated zon result in flu backfilled st at a portion o 6-6).

7 LACB Suite R Radionuclide H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Am-243 Cm-243 Cm-244 s; Insitu and of drinking to be brough 6-19 dustrial work ense termina 6.5.1. This se nfiguration, g ibed in secti ll structures and then back defines the b with the Mi n direct obse uation can re 629 foot ele ne below the ushing of wa tructure surf of building is BWR Soil D Radionuclid e

Soil d Excavation water from ht to the sur ker AMCG f ation. A gen ection descr geohydrolog ions 6.11 and are removed kfilled. The beginning of ssissippi riv ervation of w esult in wate evation. An e 619 foot av ater into and faces. Note s below 619 DCGLs for I des DCGL (pCi/g 5.352E+06 6.768E+06 1.019E+07 2.599E+07 1.281E+01 9.495E+06 6.577E+03 2.018E+01 2.008E+03 5.811E+01 2.844E+01 2.635E+01 1.122E+03 1.693E+03 1.523E+03 1.525E+03 3.691E+04 1.105E+03 1.872E+02 2.892E+02 2.720E+03

n. The BFM an onsite w rface during from residua neral descrip ibes the con gy, source-te d 6.12.

d to a depth e average wa f the saturat ver resulting water ingres er rising up onsite wate verage wate d out of the that the Re 9 foot and is Initial g)

Insitu scena well and di the installat al radioactiv ption of the nceptual mod erm and exp of three fee ater table dep ed zone. Th g in river d ss into the P to 10 feet a er supply w er table eleva unsaturated actor Buildi assumed to ario include irect exposu tion of the o vity in BFM del in osure et bgs pth is he site driven Piping above well is ation.

zone ing is be in s two ure to onsite

La Cross License T Revision well. The the backf 6.10.1. S The sour Basemen character provided remain in 6.10.1.1.

The Reac bottom. I extends 2 upper he elevation The total foot elev 363 m2.

removed of the ste the 636 f structure reactor o no eviden liner. Th Six 1.27 laborator survey m contamin radionuc with an a There is is remov

addition, demolitio purposes activity i the liner.

6.10.1.2.

The WTB storage, a se Boiling W Termination n 0 e BFM Exca filled concre ource Term rce term fo nt End Sta rization data d in Referenc n each basem React ctor Building It has an ov 26 feet 6 inc emispherical

n.

l wall/floor vation, is 512 Remediatio exposing th eel liner will foot elevatio comprised perations by nce of conta herefore the p cm thick cor ry for analys measuremen nation. As sh lide mixture average of 1, no indicatio ved therefor general cl on and remo before the s in contamina Therefore, m Waste B contained and disposal Water Reactor Plan avation scen ete and sprea m

or the BFM ate at the a for the bas ce 8. The exp ment are sum or Building g is a right c verall intern ches below g dome, whic surface area 2 m2. The su n plans call he steel liner l be removed on will rema of a concret y the interior amination lea pile cap and re slices wer sis. The core nts and repr hown in Tab

e. The Cs-13

,903 pCi/g.

on that conta e no cores leanup of l oval of the in steel liner is ated dust fro minimal sou e Treatment facilities an l of low leve r

nario assume ading the con is the tota time of li sements that pected sourc mmarized bel circular cylin al height of grade level.

ch is 0.60 in a in the port urface area l for all bel

r. Subsequen

d. The rema ain. The rem te pile cap a r concrete, th akage beyon d piles are co re collected es were colle resent the ble 6-3, Cs-7 results fro amination is were collec loose contam nternal conc s removed. T om the steel urce term is e Building nd equipmen el solid radio 6-20 es large scal ncrete over a al inventory cense term t will remain ce term confi low.

nder with a h f 144 feet an The steel sh nch thick. T tion of the b below the 6 low grade c nt to interior aining structu maining conc and piles. Th he steel liner nd the steel l onsidered to b from the sur ected from b areas expec

-137 is the p om the six co present in th cted from th mination on crete is expe This reduces l liner to the expected in t nt for deconta oactive wast le industrial a 1 m layer o of residual mination. LT

n. The dime igurations an hemispheric nd an inside hell thicknes The lowest f building to b 619 foot ave concrete inte concrete rem ural concret crete bowl he pile cap r and the ext liner or the be non-impa rface downw biased locati cted to con predominate ores ranged f he concrete t he concrete n the steel ected for ope s the already e underlying the Reactor amination an te. The size excavation on the groun l radioactiv TP Chapter ensions and nd activity le cal dome and e diameter o ss is 1.16 inc floor elevatio be backfilled erage water t erior to the moval, the r te outside the sits on an and piles we terior concre concrete bow acted areas.

ward and ship ions as indic ntain the h e radionuclid from 66 pCi to remain af outside the liner (conc erational rad y low potenti g concrete du Building En nd the collec e of the WTB of some or nd surface.

ity remainin r 2 provides surface area evels project d semi-ellips of 60 feet, a ch, except fo on is at 612 d, i.e., below table elevati steel liner remaining po e liner and b external su ere isolated ete bowl. Th wl exterior t pped to an o cated by elev highest leve de at 88% o i/g to 7,500 p fter the steel e steel liner crete dust) diation prote ial for transf during remov nd State.

ction, proces B floor to re all of ng in s the as are ted to soidal and it or the 2 foot w 636 ion is to be ortion below upport from ere is to the offsite vated ls of of the pCi/g l liner

r. In after ection fer of val of

ssing, emain

La Cross License T Revision below 63 The WTB of 626 fe Concrete The Cs-1 offsite la Cs-137 c values th source te Decontam decontam Technica This equ 1.27 cm approxim remainin remediat 6.10.1.3.

The WG 2 feet thi system r recombin elevation Concrete of signif WGTV a levels in 0.547 µC concentra of 4% of collected is remov and FRS 6.10.1.4.

The Rem Plant/Gen slab, a sm Three co concentra The activ MDC wa se Boiling W Termination n 0 36 foot eleva B basement eet.

e cores were 137 concentr aboratory ran concentration hat were app erm is expect mination w mination thre al Support D uates to appr thick unifor mate maximu ng after rem ion is compl Waste GTV is a 29 ick floors, w routed main ning, monito

n. A small su e cores were ficant contam and WTB su the WGTV.

Ci/L and 0.0 ations in the f the contam d from the W ed to provid classificatio Rema maining Str nerator Plan mall sump in ncrete core ations in the vity was iden as found in th Water Reactor Plan ation is sma floor is at el collected at rations in the nged from 12 ns in the tw roximately ted to be on will be req eshold is th Document RS oximately 1 rm layer. A um concentr mediation to leted.

e Gas Tank V foot by 31 f walls, and cei n condense oring and ho ump is presen not collecte mination. Ho umps can be

. The most r 0215 µCi/L e sump liqui mination leve WGTV as a p de a better es on.

aining Structu ructures cat nt area, a on n the Turbine samples wer e three cores ntified in the he slice from r

ll at 36.9 m levation 630 t biased loca e first core s 240 pCi/g to wo core slic 1% of those the floor as quired to m e open air d S-TD-31319 0,000 pCi/g lthough the rations, the f o the open Vault foot undergr iling located er gases th oldup for de nt that exten d from the W owever, 10 used to prov ecent sampl for the WT d, the conta els in the WT part of conti stimate of co ures egory inclu e foot thick e Building an re collected s ranged from e core slice m 1.27-2.54 c 6-21 2 with a tota 0 feet. A sma ations as indi lices (0 - 1.2 o 25,400 pCi ces from 1.2 found in th opposed to w meet the u demolition c 96-005, La C Cs-137 assu biased chara full areal ext air demoli round concre d 3 feet bgs j hrough vario ecay in the nds to 618 fo WGTV due t CFR Part 6 vide a very r es from the B and WGT amination lev TB. Additio inuing chara ontamination udes the Pip remnant of nd a small p from the Pip m 10 pCi/g t from 0-1.27 cm.

al wall and f all sump is p icated by ele 27 cm) of th i/g with an a 27cm - 2.54 he 0 - 1.27 cm walls.

unrestricted criteria of 2 Crosse Open uming that c acterization tent and con ition criteria ete structure just outside ous compon WGTV. Th oot elevation to access res 61 samples rough estima sumps indic TV, respecti vels in the W onal surveys acterization a n levels to s ping and V f the four foo it in the Tur ping and Ven to 20 pCi/g 7 cm. Minim floor surface present with evated surve he three core average of 12 4 cm were m m slices. Th use crite mR/hr per n Air Demol contaminatio samples lik ncentrations a will not e with 14 fee of the WTB nents for d he vault floo

n.

strictions and collected fr ate of potenti cate Cs-137 ively. By sim WGTV coul s and/or core after all tank support reme Ventilation ot thick Chi rbine Buildin ntilation Tun with an ave mal activity n e area of 102 h a floor elev ey measurem s analyzed b 2,003 pCi/g.

much lower he majority o ria. The i EnergySolu lition Limits on is presen kely identifie of contamin be known et high wall B. The gas d drying, filte or is at 621 d low expect rom liquid i ial contamin concentratio mple ratio o d be in the r e samples w ks and equip ediation plan Tunnel, Re imney found ng.

nnel. The Cs rage of 15 p near or below 2 m2.

vation ments.

by the The with of the initial utions (14).

nt in a ed the nation until s and decay

ering, foot tation n the nation ons of of the range will be pment nning eactor dation s-137 pCi/g.

w the

La Cross License T Revision Cores we sump and small ar continuin The remn because i four foot potential 6.10.2. B The BFM the reas therefore The follo Direc Inhal Inges Inges Direc broug Direc surfa The agri milk, gra B

6.11.

6.11.1. B The BFM screening assumed dose mo resistanc The fill v activity m below th fill volum with wat elevation The surfa se Boiling W Termination n 0 ere not coll d pit due to t eas. Additio ng characteri nant of the it is the low t thick foun for contami BFM Exposu M includes t onably fores e the industri owing exposu ct exposure t lation of airb stion of conc stion of wate ct exposure, ght to the sur ct exposure, ce by excava cultural and ain and veget BFM Insitu S BFM Insitu G M Insitu gro g approach.

to release an deling assum e to water fl volume into moves from e average w me in the Re ter continuou ns at 618 foo face areas be Water Reactor Plan ected in the the low expe onal concret ization in the Chimney fo est one foot ndation slab ination to mi ure Pathway two exposur seeable futu ial worker.

ure pathway to external ra borne radioac crete or fill m er from onsit inhalation d rface during inhalation d ation.

d gardening table ingesti Scenario Groundwat oundwater (

One hundred nd instantly ming that th ow, i.e., are o which the m the concre water table el eactor Basem usly for the ot, the rema elow 619 foo r

e Reactor Pl ectation of si te cores an ese areas to oundation sl portion of a is expected igrate three f ys re scenarios, ure land use ys are applica adiation in ctivity in as material in te well, dose and inge g installation dose and inge pathways a on pathways ter Scenario (BFM Insitu d percent of mix with th he source te not present.

released act ete surface i levation of 6 ment below 6 full year. W aining End S ot in the thre 6-22 lant/Ventilat ignificant co nd/or dose r support FRS lab has a ve a solid four f d to contain feet into the Insitu and at the LAC able to the B as left End s left End S as left End estion dose f of the onsite estion dose f are not appli s are therefo o

ugw) concep f the invento he fill materi erm is in the tivity mixes into the fill.

619 foot. Mi 619 foot bec With the ex State baseme ee sumps ar tion Plant a ontamination rate surveys S classificati ery low pote foot slab. Th n minimal c solid concre Excavation.

BWR site is BFM scenari d State geom State geomet d State geom from contam e well into th from concret icable to ind ore not includ ptual model ory in the bac ial. RESRAD e fill and th s is proporti A portion ixing is assu cause the fil xception of t ent floors ar re insignifica area or the T n being prese s will be p ion and plann ential of bei he top surfac contaminatio ete slab is ve

. As discuss s industrial a ios:

etry (negligi try (negligib metry (negligi minated drilli he fill mater te that is bro dustrial land ded.

is based on ckfilled base D is then use hat the struc ional to the of the Reac umed to occu ll is assumed three small s re above 61 ant (less than Turbine Bui ent and their performed d ning.

ing contamin ce of the exi on levels an ery low.

sed in sectio and the AMC ible),

le),

ible),

ing spoils rial, and ought to the d use. The m n a conserv ement concr ed to perform ctures provid distance tha ctor Baseme ur over the e d to be in co sumps with 19 foot eleva n 1% of the ilding r very during nated isting d the on 6.4 CG is

meat, vative rete is m the de no at the ent is entire ontact floor ation.

e total

La Cross License T Revision backfille purpose o The mixi more unc foot, con rainwater address t BFM co dependen provided The fill m volume.

highest d resulted basement caused th from the Based on Reactor B assumed The RES importan typically and runo required Mississip unsaturat The verti rate is de the 619 f change is by forcin below fo The use periods o Full reso unsaturat not justif As listed license te was run group.

se Boiling W Termination n 0 d basement of fill mixing ing distance certain than ntact with w r infiltration this uncertai onceptual m nce of dose d in Referenc mixing dista For the Rea dose. For th in the high ts because t he RESRAD walls. This n the results Building, ab for all other SRAD non-d nt parameter determined off coefficien for LACB ppi River a ted zone.

ical water flo efined by the foot average s used to co ng the infilt r a descriptio of 3.05 m/

of increase a olution of t ted zone wou fied given th d in Table 6-ermination.

separately f Water Reactor Plan surface area g assumption e into the fil leaching int water is the n, as oppose nty in a man model, a si e on the mi ce 8.

nces evaluat actor Buildin he remaining hest dose. T the source t D Length Par reduced the s of the sen bove and be r basements/

dispersion gr r is the verti d by the infi nt parameter WR due to and the resu ow rate is co e distance th water table nservatively tration rate t on of the me

/yr is conse and decrease the actual w uld require d e bounding/

1, there are Due to diffe for the Reac r

a) and are in ns.

ll after leach to the React result of pe ed to contin nner consist imple sensit ixing distan ted ranged fr ng above 61 g basements The Reactor erm is entir rallel to Flo modeled we sitivity anal elow 619 foo

/structures.

roundwater ical flow ra iltration rate rs. A differe o the site g ulting seaso onservativel hat water rec elevation (1 y bound the to be 3.05 m ethod used to ervative bec e, as well as water flow detailed grou screening ap portions of ferences in c ctor Buildin 6-23 ncluded wit hing from flo tor Building eriodic flush nual contact ent with the tivity analy ce. The m from 2.54 cm 19 foot an as s the nomin Building a rely on the w w parameter ell water con lysis, full m ot, and a 2.5 model is us ate of water e as defined ent approach groundwater onal water y modeled i cedes from th 0 ft or 3.05 m net flow of m/y. See Eq o assign a 3.

ause the se a horizonta pattern dur undwater tra pproach used eight structu configuration ng, WTB, W th the basem oor and wal fill volume hing from s with water e screening a ysis was co mixing volum m to full mix ssumption o nal minimum above 619 f walls of a r r to be corre ncentrations.

mixing with t 54 cm mixin sed in the B through the by the prec h to definin r being hyd level fluctu in RESRAD he seasonal m). This sea water to the quation 1 an 05 m/yr infi easonal wate al componen ring the sea ansport and d d to develop ures that wil n and contam WGTV, and ments above ll surfaces a e below 619 seasonal wa r in the satu approach use onducted to me sensitivi xing through of full mixin m mixing d foot differed right circula elated to the the fill was ng distance BFM Insitugw e unsaturate cipitation, ev ng the vertic draulically c uation into D by assumin high elevati asonal 3.05 m e saturated z nd correspo iltration rate er level fluc nt, that are n asonal fluct dispersion m the BFM co ll be backfill mination po the Remai 619 foot fo above 619 fo foot. Above ater level ris urated zone.

ed to develo o determine ity calculati hout the entir ng resulted i depth of 2.54 d from the ar cylinder w e mixing dis assumed fo into the fill w assessmen ed zone whi vapotranspir cal flow rate connected to and out o ng that the an ion of 629 fo m water elev zone in RES onding discu in RESRAD ctuation inc not accounted tuations into modeling wh onceptual mo led and rema otential, the ining Struct or the oot is e 619 se, or

. To op the e the on is re fill in the 4 cm other which stance or the l was nt. An ich is ration e was o the f the nnual oot to vation RAD ussion D.

cludes d for.

o the ich is odel.

ain at BFM tures

La Cross License T Revision 6.11.1.1.

RESRAD for each concentra that a un of licens dependen can be de per mCi t the DSR BFM Ins 6.11.1.2.

An unce calculatio paramete soil DCG The para BFM Ins The affe Thicknes and Fract The unc above 6 Remainin five BFM Variable structure The selec the BFM Insitugw Mississip indicate f 619 foot

example, to be obs 10 feet (3 The seas Insitugw approach and unsa rise abov unsaturat se Boiling W Termination n 0 BFM D was used t radionuclide ations to det nit source ter se terminatio nt on the mi escribed as p total activity by the pCi/

situgw DFs as BFM ertainty anal on of DSR ers for the BF GL uncertain ameter set de situgw analys ected RESRA ss of Contam tion of Cont ertainty ana 19 foot elev ng Structure M Insitugw u e in Attach

s.

ction of the P M Insitugw RE conceptual m ppi river and fluctuations

t. However,

, it is known served in the 3.05 m) abov sonal water dose assess

h. The season aturated zone ve the 619 fo ted zone.

Water Reactor Plan Insitugw Com to develop D e in the initi termine BFM rm of 1 pCi on which w xing distanc pCi/g in fill p y in concrete

/g per mCi v s detailed in Insitugw RES lysis was pe s for the B FM Insitugw nty analysis (

eveloped to sis with chan AD geometr minated Zone aminated Zo alysis was p vation, Rea s resulting in uncertainty a hment 6-2 w Precipitation ESRAD mod model assum d fluctuates that are up the river s n that water e Piping and ve the averag table rise m sment but nal water ris e is the avera oot results in r

mputation M Dose to Sour al suite. The M Insitugw D total invento was instantly ce as discuss per total pCi e, were then value. Excel Reference 8 SRAD Unce erformed to BFM Insitug RESRAD u (see process perform the nges to acco ry paramete e, Length Pa one below th performed f actor Buildin n five separa analyses are were assigne n, Evapotran del requires a mes that the seasonally i to five feet stage does n level season d Ventilation ge water tab must be acc does not p se was addre age water tab n water perio 6-24 Model rce Ratios (D e DSRs were Fs. The fill ory was pres y released an sed above. T i in concrete calculated b l spreadshee

8.

ertainty Anal select dete gw model. T uncertainty a flowchart in soil DCGL ount for the ers are Cove arallel to Aqu he Water Tab for five stru ng below 6 ate uncertain listed in A ed the values nspiration Ra additional ex e onsite grou nto the unsa higher than not precisely nally rises to n Tunnels wi le elevation.

counted for precisely fit essed by assu ble elevation odically ente DSRs), with e used in co concentratio sent in the b nd mixed w The fill conc

e. BFM Insit by converting et calculation lysis for Init erministic R The process analysis was n Figure 6-7)

L uncertainty geometries er Depth, A uifer Flow, U ble.

ucture confi 619 foot ele nty analyses s shown in ate, and Run xplanation. A undwater is aturated zon the average y represent o an elevatio ith a floor at in the conc the RESR uming that t n of 619 foo ering backfi h units of mr njunction w ons were cal basement con with a volum centration th tugw DFs, in g pCi to mC ns were used tial Suite RESRAD pa s for determ the same as

).

y analysis is of the back Area of Con Unsaturated igurations; R evation, WT

. The param 6-2. The par Table 6-8 f noff Coeffici As discussed s in commun ne. River stag e site water t site water on sufficient at 629 foot e ceptual mod RAD ground the boundary ot. The seaso illed structur rem/yr per p with calculate culated assu ncrete at the me of fill th hen has unit units of mre i and multip d to calculat arameters fo mining the s that used fo applicable t kfilled struct ntaminated Z d Zone Thick Reactor Bui TB, WTGV, meters used fo rameters list for the respe ent paramete d above, the nication wit ge measurem table elevati table levels tly high for w levation whi del for the dwater mod y of the satu onal 3.05 m w res that are i pCi/g, ed fill uming e time hat is s that em/yr plying te the or the input or the to the tures.

Zone, kness, ilding

, and or the ed as ective ers in BFM th the ments on of

s. For water ich is BFM deling urated water in the

La Cross License T Revision Table 6-Area (m2)

Thic zone Leng Flow Unsa Thic Frac zone The effec by conse rise repre precipitat precipitat Maximiz radionuc To force represent setting th 1 in Ref paramete W

The distr value of value of Consisten the initia radionuc analysis.

se Boiling W Termination n 0 8

Deter Analy Paramete Cover Depth a of Contamina ckness of Conta e (m) gth Parallel to A w (m) aturated Zone ckness (m) tion of contam e below the wat ct of the 3.0 ervatively as esents a con tion driven i tion, evapo zing the infi lides when t e RESRAD t the infiltrat he Evapotran ference 12, i er.

Where:

I = In E = Ev R = R P = Pr ribution eval 0.25 m/yr (

3.05 m/yr se nt with NUR al suite radion lides that w This limita Water Reactor Plan rministic Ge ysis for the f r

R A

(m) ated Zone aminated Aquifer minated ter table 05 m seasona ssuming that stant infiltra infiltration r transpiration filtration rate the non-dispe to use a 3.0 tion rate dir nspiration Ra it is seen tha nfiltration Ra vapotranspir Runoff Coeff recipitation R luated in the (the actual p elected to rep REG-1757 g nuclides are were greater ation was n r

eometry RE five BFM In Rx Building Above 619 0.91 262.68 5.18 18.29 1E-10 0

al flushing h t the distanc ation rate of rate at the LA n and runo e maximize ersion groun 05 m/yr infi rectly by ass ate and Runo at this will r 1

ate (m/yr) ration Coeffi ficient (dime Rate (m/yr) e sensitivity precipitation present the s guidance, the present at th r than 0.1%

ecessary to 6-25 ESRAD Para nsitugw Con Rx Buildin Below 619 6.10 182.41 0.75 15.24 0

1 height is acc ce that the w 3.05 m/yr. T ACBWR sit ff coefficien s the well ndwater mod iltration rate signing 3.05 off Coefficie result in an i 1

ficient (dime ensionless) analysis was driven infil seasonal wat e uncertainty heir mixture

% of the mix result in pr ameters use figurations ng 9

WTB 2.72 101.90 0.0254 6.10 3.35 0

counted for i water recedes This is conse te which is 0 nt in the S water conce del is selecte e, the precip m/yr to the ent paramete infiltration r nsionless) s a uniform ltration rate ter table fluc y analysis w e fractions as xture were ractical RES ed in the Un B

WGTV 5.46 0

460.04 4

0.0254 9.75 0.61 0

in the BFM s after the s ervative rela 0.25 m/yr (as Soil DCGL entrations fo ed in RESRA pitation para e precipitatio ers to zero. F rate equal to distribution at the site) ctuation.

was perform s listed in Ta included in SRAD run ncertainty Remaining Structures 2.4 667.26 0.0254 38.10 3.67 0

Insitugw sce seasonal (3.0 ative to the a s calculated parameter or all signif AD.

ameter is us on paramete From Equati the precipit Equation with a mini and a maxi med assuming able 6-3. Onl n the uncert times. How g

s enario 05 m) actual from set).

ficant ed to er and ion 6-tation n 6-1 imum imum g that ly the tainty

wever,

La Cross License T Revision including that all se The RES 14 provi paramete 10 to 6-1 The para generate not cont distributi The maj correlatio correlate threshold negative scenario of radioa for the n conserva assigned Figure 6 shown to The Kd v not inclu listed in R and prov attributab 6.11.1.3.

As discu the Reac Structure determin 9 to 6-14 changed The RES DSRs are 6.11.1.4.

The BFM Insitugw D and Belo Table6-1 se Boiling W Termination n 0 g all radionu ensitive para SRAD Uncer ide summar ers. Table 6-9 4 provide th ameter distrib the median, ain values ion was used jority of th on between d). The p d and each correlation is through th activity in the non-sensitive atively assign as indicated

-7 but this o be only slig values select uded in the u Reference 1 vides consiste ble to the rem BFM ssed above, ctor Buildin es. The param nistic values 4 replacing th from 0.2 to SRAD Uncer e provided in BFM M Insitugw D DFs are liste ow 619 foot 6.

Water Reactor Plan uclides with ameters will rtainty Repo ries of the 9 provides th he radionucli butions for th

, 25th and 75 for Europiu

d.

he uncertain Kd and do arameters w occurred in with Kd wa he ingestion e water phas e radionucli ned the 25th d by the PRC will have a ghtly sensitiv ted for the v uncertainty

4. Using the ency in dete moved radio Insitugw RES the BFM In ng (above meters provi in Tables 6-he parameter 0.066 to be c rtainty Repo n Table 6-15 Insitugw Dos Fs were calc ed in Table 6 t were summ r

greater than be identified rts are provi uncertainty he results fo ide specific K he site-speci 5th percentil um; the 25th nty analysis ose (i.e., 30 with positiv only one o as expected s of well wat se at equilibr ides that we percentile v CC results i very minor ve.

very low abu analysis we e 25th percen ermining the nuclides.

SRAD Deter situgw RESR and below ided in Attac 8 replacing t r distribution consistent w orts are prov

5.

se Factors culated by E 6-16. Note th med in Refe 6-26 n 0.1% of th

d.

ided electron y analysis r r the non-rad Kd results fo ific soil type e determinis h percentile results tha 0 of the 34 e correlatio of the three since the pri er and lower rium. Theref ere included values from R in order to fo r, if any, ef undance (<0 ere also assig ntiles for all insignifican rministic An RAD dose as 619 eleva chment 6-2 w the variable ns. The Con with the unsa vided electro Excel spreads hat the DFs erence 8 to he mixture nically with results with dionuclide s or each of th e of sand from stic values. N from the N at were sen 4 sensitive ons were on uncertainty imary dose p r Kd values fore, the dete d in the unc Reference 1 follow the pa ffect on dose

.1%) initial gned the 25 initial suite nt dose contr nalysis and D ssessments w ation), WTB were applied e parameter ntaminated Z aturated and onically with sheet in Ref for the Reac determine t fraction pro Reference 8 h the select specific para he basements m Reference Note that R NUREG-669 nsitive indic parameters nly slightly runs. The p pathway in t result in a g erministic K certainty an

4. The 75th arameter sel e since the suite radion 5th percentile radionuclide ributors and DSR Results were perform B, WGTV d to all five rs and the va Zone Field C saturated zo h Reference ference 8. Th ctor Building the Reactor ovides confid

. Tables 6-9 ted determin meters. Tabl s evaluated.

e 14 were us Reference 14 97 Kd param cated a neg were negat above the predominan the BFM Ins greater percen Kd values sel nalysis were h percentiles lection proce parameters nuclides that e values for es is conserv the dose fra s

med separatel and Rema analyses wit alues in Tabl Capacity was one.

8. The resu he resulting g Above 619 Building D dence 9 to 6-nistic les 6-sed to does meter gative tively 0.25 nce of situgw ntage lected e also were ess in were were sand vative action ly for aining th the les 6-s also ulting BFM 9 foot Fs in

La Cro Licens Revisi osse Boiling Wa se Termination P ion 0 Table 6-Note 1: Positive conceptual mode Note 2: Negative Note 3: Site-spec wc.usace.army.m Note 4: The prec other basements.

Para Cover Erosion R Contaminated z Contaminated z Wind Speed (N Precipitation Saturated zone b Well pump inta Well Pumping R Unsaturated zon Mass loading fo Indoor dust filtr External gamma Depth of Soil M ater Reactor Plan

-9 Results o correlation with do el.

e correlation with d cific wind speed da mil/projects/Lock4.

cipitation parameter ameter Rate zone erosion rate zone b parameter Note 3) b parameter ake depth Rate ne b parameter or inhalation ration factor a shielding factor Mixing Layer of RESRAD Un ose. Maximum site-dose. Minimum site ata used (US Army shtml) r was not sensitive Reactor Building Above 619 Percentile Va 75th 0.0 median 0.0 median 0.9 25th 3.3 Note 4 3.0 median 0.9 Note 2 6.0 median 986 median 0.9 median 2.3 median 0.5 median 0.2 median 0.2 ncertainty Ana

-specific value bas e-specific value use Corps of Engineer for the Reactor Bu 9

Rea Buil Below alue Percentile 0029 75th 0015 75th 97 median 3

median 05 Note 4 97 median 08 Note 2 6.1 median 97 median 35E-5 median 55 25th 27 median 23 median 6-27 alysis for BFM I ed on seasonal wat ed for conservatism rs, Mississippi Rive uilding Above and B actor lding w 619 e

Value Perc 0.0029 75th 0.0029 medi 0.97 medi 6.8 75th 3.05 Note 0.97 medi 6.08 Note 986.1 medi 0.97 medi 2.35E-5 medi 0.35 medi 0.27 medi 0.23 medi Insitugw and S ter rise value (3.05 m

er Lock and Damn Below 619 foot. Th WTB entile Value 0.0029 ian 0.0015 ian 0.97 10.2 1

3.05 ian 0.97 2

6.08 ian 986.1 ian 0.97 ian 2.35E-5 ian 0.55 ian 0.27 ian 0.23 Selected Determ m) used for conser 4, Alma WI, Web he 3.05 m/yr rate w WGTV Percentile Val median 0.00 median 0.00 median 0.97 median 6.8 Note 1 3.05 25th 0.84 Note 2 6.08 median 986 median 0.97 median 2.35 median 0.55 median 0.27 median 0.23 ministic Parame rvatism and linkag address http://ww was applied for con Rema Struc lue Percentile 015 75th 015 median 7

median 75th 5

Note 1 4

median 8

Note 2 6.1 75th 7

median 5E-5 median 5

median 7

median 3

median eters e to ww.mvp-nsistency with the aining ctures Value 0.0029 0.0015 0.97 10.2 3.05 0.97 6.08 1311.2 0.97 2.35E-5 0.55 0.27 0.23

La Crosse B License Ter Revision 0 Tab Rad H-3 C-1 Fe-Ni-Co-Ni-Sr-9 Cs-Eu-Eu-Pu-Tab Rad H-3 C-1 Fe-5 Ni-5 Co-Ni-6 Sr-9 Cs-Eu-Eu-Pu-2 Boiling Wate rmination Pla le 6-10 B

fo dionuclide K

3 14

-55

-59

-60

-63 90

-137

-152

-154

-241 le 6-11 B

fo dionuclide K

3 4

55 59 60 63 90 137 152 154 241 er Reactor an BFM Insitug or Distribut Kd in Contam 25th NS NS NS NS NS 25th 25th NS 75th NS BFM Insitug or Distribut Kd in Contami NS NS NS NS NS NS 25th 25th NS NS NS gw Rx Buildi tion Coeffic minated Zone 0.05 1.8 38 147 9

147 5

50 95 7302 173 gw Rx Buildi tion Coeffic inated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 6-28 ing above 61 ients (Kd)

Kd in Unsa NS 25th NS NS NS NS NS NS NS NS NS ing below 61 ients (Kd)

Kd in Unsatu NA NA NA NA NA NA NA NA NA NA NA 19: Uncerta aturated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 19 Uncertai urated Zone NA NA NA NA NA NA NA NA NA NA NA ainty Analys e

Kd in Satu NS NS NS NS NS NS 25th 25th NS NS NS inty Analysi Kd in Satu NS NS NS NS NS NS 25th 25th NS NS NS sis Results urated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 is Results urated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173

La Crosse B License Ter Revision 0 T

Rad H-3 C-14 Fe-5 Ni-5 Co-6 Ni-6 Sr-9 Cs-1 Eu-1 Eu-1 Pu-2 T

Rad H-3 C-1 Fe-Ni-Co-Ni-Sr-9 Cs-Eu-Eu-Pu-Boiling Wate rmination Pla Table 6-12 dionuclide K

4 55 59 60 63 0

137 152 154 241 Table 6-13 dionuclide K

3 14 55 59

-60 63 90 137

-152

-154 241 er Reactor an BFM Distri Kd in Contami NS NS NS NS NS NS 25th NS NS NS NS BFM Distri Kd in Contam NS NS NS NS NS 25th 25th NS NS 25th NS Insitugw W ibution Coe inated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 Insitugw W ibution Coe minated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 6-29 TB Uncerta efficients (K Kd in Unsat NS NS NS NS NS NS 25th 25th NS NS NS GTV Uncer efficients (K Kd in Unsat 75th NS 75th 75th NS NS 25th 25th NS NS NS ainty Analy Kd) turated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 rtainty Ana Kd) turated Zone 0.09 1.8 1279 1110 9

147 5

50 95 95 173 ysis Results f Kd in Satur NS NS NS 25th NS NS 25th 25th NS NS NS alysis Result Kd in Satu NS NS NS NS 25th 75th 25th 25th NS NS NS for rated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 ts for urated Zone 0.05 1.8 38 147 9

1110 5

50 95 95 173

La Crosse B License Ter Revision 0 Tab Radi H-3 C-14 Fe-55 Ni-59 Co-6 Ni-63 Sr-90 Cs-13 Eu-1 Eu-1 Pu-24 Note 1: Incons Boiling Wate rmination Pla ble 6-14 B

fo ionuclide 4

5 9

0 3

0 37 52 54 41 sistent uncertai er Reactor an BFM Insitug or Distribut Kd in Contam NS NS NS NS NS NS NS NS NS NS NS inty results wit gw Remainin tion Coeffic minated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 th PRCC value 6-30 ng Structure ients (Kd)

Kd in Unsa NS NS 75th, 25th (Note 1)

NS NS NS 25th 25th NS NS NS es only slightly es Uncertain aturated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 y above 0.25 cr nty Analysi e

Kd in Satu NS NS NS NS 25th NS 25th 25th NS NS 25th riteria. 25th per s Results urated Zone 0.05 1.8 38 147 9

147 5

50 95 95 173 rcentile value wwas used.

La Cro Licens Revisi osse Boiling Wa se Termination P ion 0 ater Reactor Plan Table 6-15 B

Radionuclide H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Am-243 Cm-243 Cm-244 BFM Insitugw D Rx Building Above 619' (mrem/yr per pCi/g) 3.51E-03 1.94E-02 6.14E-05 2.65E-05 4.15E-02 6.01E-05 5.26E-01 8.77E-02 8.22E-02 1.48E-02 5.12E-04 7.30E-06 4.35E-05 2.65E-01 3.79E-01 3.78E-01 6.33E-03 1.86E-01 2.22E-01 5.35E-03 3.02E-03 DSRs for React Rx Buildin Below 619 (mrem/yr p pCi/g) 7.13E-04 2.26E-02 5.65E-04 5.75E-05 1.10E-01 1.58E-04 1.13E+00 6.42E-03 1.64E-02 3.97E-02 2.67E-03 3.88E-03 6.03E-04 7.42E-01 8.24E-01 8.24E-01 1.59E-02 4.46E-01 4.44E-01 1.14E-01 9.08E-02 6-31 tor Building, W ng 9'

er WTB Excavation Facto (mrem/yr pCi/g 7.16E-1.99E-7.61E-2.11E-2.95E-9.26E-1.30E-2.32E-1.10E-1.84E-1.61E-1.62E-4.51E-2.33E-3.00E-2.93E-1.32E-6.34E-1.55E-9.04E-2.91E-WTB, WGTV, a B

n Dose or r per g)

WG Excava Fa (mrem pC 06 1.23 04 2.93 13 0.00 06 2.15 04 2.41 07 5.26 02 2.20 04 2.40 04 2.49 04 9.58 08 1.68 10 9.19 16 1.72 03 1.64 02 3.08 02 3.06 04 3.58 03 1.35 02 1.64 06 1.37 05 4.36 and Remaining GTV ation Dose actor m/yr per Ci/g)

R S

Exca (m

3E-05 4

3E-04 1

0E+00 1

5E-06 2

1E-03 4

6E-07 7

0E-02 3

0E-04 2

9E-04 7

8E-04 1

8E-05 7

9E-06 4

2E-07 4

4E-02 1

8E-02 3

6E-02 3

8E-04 2

5E-02 5

4E-02 1

7E-05 7

6E-05 3

g Structures Remaining Structure avation Dose Factor rem/yr per pCi/g) 4.62E-05 1.26E-03 1.53E-13 2.18E-06 4.05E-04 7.82E-07 3.47E-02 2.43E-04 7.82E-04 1.53E-04 7.17E-09 4.50E-11 4.49E-17 1.85E-03 3.09E-02 3.00E-02 2.02E-04 5.83E-03 1.57E-02 7.79E-05 3.13E-05

La Crosse B License Ter Revision 0 Ra H-3 C-1 Fe-Ni-Co-Ni-Sr-9 Nb-Tc-Cs-Eu-Eu-Eu-Pu-Pu-Pu-Pu-Am Am Cm Cm Boiling Wate rmination Pla adionuclide 3

14

-55

-59

-60

-63 90

-94

-99

-137

-152

-154

-155

-238

-239

-240

-241 m-241 m-243 m-243 m-244 er Reactor an Table Rx Buildi BFM Insitug (mrem/yr p mCi) 4.44E-03 1.02E-01 2.37E-03 2.50E-04 4.74E-01 6.80E-04 4.91E+00 6.36E-02 1.03E-01 1.71E-01 1.13E-02 1.61E-02 2.52E-03 3.20E+00 3.59E+00 3.58E+00 6.88E-02 1.93E+00 1.94E+00 4.74E-01 3.79E-01 e 6-16 BF ng gw DF per BFM Do (mr 3

1 1

4 3

1 4

4 1

6 4

2 0

2 2

5 1

2 1

4 2

3 2

3 3

9 0

5 0

6 0

6 2

2 0

1 0

3 1

1 1

6 6-32 FM Insitugw WTB M Insitugw DF ose Factor rem/yr per mCi) 1.57E-03 4.36E-02 1.67E-10 4.63E-04 6.48E-02 2.03E-04

.85E+00 5.10E-02 2.42E-02 4.05E-02 3.54E-06 3.55E-08 9.91E-14 5.10E-01

.59E+00

.44E+00 2.90E-02

.39E+00

.40E+00 1.98E-03 6.40E-03 Dose Facto WGTV BFM Insitu (mrem/yr mCi) 6.00E-0 1.43E-0 0.00E+0 1.04E-0 1.17E-0 2.56E-0 1.07E+0 1.17E-0 1.21E-0 4.66E-0 8.18E-0 4.47E-0 8.37E-0 7.97E-0 1.50E+0 1.49E+0 1.74E-0 6.57E-0 7.98E-0 6.67E-0 2.12E-0 ors V

ugw DF per R

St BFM (mr 04 1

02 4

00 5

04 7

01 1

05 2

00 1

02 8

02 2

02 5

04 2

04 1

06 1

01 6

00 1

00 1

02 6

01 1

01 5

04 2

03 1

emaining tructures M Insitugw DF rem/yr per mCi) 1.55E-03 4.21E-02 5.12E-12 7.29E-05 1.36E-02 2.62E-05 1.16E+00 8.14E-03 2.62E-02 5.14E-03 2.40E-07 1.51E-09 1.51E-15 6.21E-02 1.04E+00 1.00E+00 6.78E-03 1.95E-01 5.27E-01 2.61E-03 1.05E-03

La Cross License T Revision 6.11.2. B The BFM pathways be broug concrete.

residual which in scenario assuming mrem/yr There are of slurry would lik construct being bro The well is met an capture 1 borehole borehole depth of are unifo The dose DCGLs a DCGLs Summary The AFs RESRAD B

6.12.

The BFM and the c decay. T conceptu mixing d BFM Exc Due to d calculate same ma The BFM listed in T se Boiling W Termination n 0 BFM Insitu D M Insitu Dri s listed in se ght to the sur

. The driller radioactivity ncludes the f is the resid g no decay per total mC e a number o pits, tanks, kely involve tion. As a c ought to the l is assumed nd drilling s 100 percent area. The diameter an 3 feet in ord ormly mixed e from the ci and AFs. T and the spo y Reports ar s and BFM D results. Th BFM Excava M Excavation concrete spre The calculat ual model th during excav cavation DF differences in d separately nner as was M Excavatio Table 6-18.

Water Reactor Plan Drilling Spo illing Spoils ection 1. Th rface during r is assume y in the con fill material dual radioact or release t Ci.

of ways that and dumping additional d conservative surface.

to be drilled stopped. Th of the rema volume of s nd depth of d der to minim and spread o ircular area a The AFs wer oils spread e provided e Insituds DF he BFM Insit ation Scenar n scenario as ead on the su tion of allow at the avera vation will Fs in units of n configurati y for the Rea done for the on DFs are c r

oils Scenari s (BFM Insi he dose from the installat ed to be una ncrete surfac above the st tivity remain to the fill. T installers ha g the drilling dilution by r e assumption d into the ba he extent of aining resid spoil materi drilling whic mize the mix over a circul at the surfac re calculated area which electronically Fs were calc tuds DFs are rio ssumes that urface imme wable total age radionuc not exceed f mrem/yr pe ion and cont actor Buildin e BFM Insitu calculated by 6-33 o and DF C ituds) scenar m residual ra tion of a wel aware that t ces is brough tructure floo ning in con The BFM In andle and dis g spoils on t refilling the p n, no dilutio asement fill d drilling into dual radioact al brought t ch is conserv xing volume lar area on th ce was calcu d using the d h was determ y with Refer culated by E listed in Tab some or all o ediately after mCi is dr clide concent the surface er total mCi.

tamination p ng, WTB, W u assessment y Excel spre Calculation rio addresse adioactivity i ll that rando the backfill ht to the sur or. The sourc ncrete at the nsituds DFs spose of dril the existing s pit with the on of the spo down to the o concrete is tivity in the to the surfac vatively assu for all basem he ground su ulated by RE deterministic mined to b rence 8.

Excel spread ble 6-17.

of the backf r license ter riven by the trations in th soil DCGL potential, the WGTV, and ts.

eadsheet in s one of the in the concre omly hits bac ed structure rface with th ce term for time of lic are calculat lling spoils, surface soils material exc oil material e concrete flo s assumed to concrete su ce is calcula umed to be ments. The urface to a d ESRAD usin c parameters be 0.457 m2 dsheet in Re filled structu rmination tak e baseline l he concrete Ls. The asse e BFM Exca Remaining Reference 8 e BFM exp ete is assum ckfilled struc e is present.

he drilling s the BFM In cense termin ted with uni including th

s. The use o cavated durin is assumed oor where re o be sufficie urface withi ated based o the minimum concrete an depth of 0.15 g the surfac s applied fo

2. The RES eference 8 u ures are excav king no cred limitation in after inadve essment pro avation DFs Structures i

8. The result osure med to ctural

. The spoils nsituds nation its of he use of pits ng its after efusal ent to in the on the m fill nd fill 5 m.

e soil or soil RAD using vated dit for n the ertent ovides were in the ts are

La Cross License T Revision R

se Boiling W Termination n 0 T

Radionuclide H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Am-243 Cm-243 Cm-244 Water Reactor Plan Table 6-17 BFM Insi Reacto Buildin (mrem/yr mCi) 7.15E-0 1.26E-0 2.43E-0 1.38E-0 1.16E-0 3.50E-0 2.05E-0 7.94E-0 3.10E-0 2.83E-0 5.46E-0 5.81E-0 2.01E-0 1.08E-0 1.19E-0 1.18E-0 1.65E-0 6.94E-0 9.57E-0 5.88E-0 6.77E-0 r

BFM Insi ituds or ng r per BF (mr 09 7

08 1

09 2

09 1

01 1

09 3

04 2

02 7

07 3

02 2

02 5

02 5

03 1

04 1

04 1

04 1

05 1

04 6

03 9

03 5

05 6

6-34 itu Drilling FM Insituds WTB rem/yr per mCi) 7.03E-08 1.24E-07 2.39E-08 1.36E-08 1.14E+00 3.45E-08 2.02E-03 7.81E-01 3.05E-06 2.78E-01 5.38E-01 5.72E-01 1.97E-02 1.06E-03 1.17E-03 1.16E-03 1.62E-04 6.83E-03 9.41E-02 5.78E-02 6.66E-04 Spoils Dose BFM Ins WGTV (mrem/yr mCi) 3.64E-0 6.42E-0 1.24E-0 7.01E-0 5.91E-0 1.78E-0 1.04E-0 4.04E-0 1.58E-0 1.44E-0 2.78E-0 2.96E-0 1.02E-0 5.47E-0 6.04E-0 6.00E-0 8.39E-0 3.53E-0 4.87E-0 2.99E-0 3.44E-0 e Factors situds V

r per

)

B In Rem Str (m

pe 08 8.0 08 1.4 08 2.7 09 1.5 01 1.3 08 3.9 03 2.3 01 8.9 06 3.4 01 3.1 01 6.1 01 6.5 02 2.2 04 1.2 04 1.3 04 1.3 05 1.8 03 7.7 02 1.0 02 6.6 04 7.6 BFM nsituds maining ructures mrem/yr r mCi) 02E-09 41E-08 73E-09 55E-09 30E-01 93E-09 30E-04 91E-02 48E-07 17E-02 13E-02 52E-02 25E-03 21E-04 33E-04 32E-04 85E-05 79E-04 07E-02 60E-03 60E-05

La Cross License T Revision Rad E

E E

A A

C C

In 6.13.

NUREG-criterion applies t insignific identifies The radio the ROC DCGLs.

the soil D from fur mrem/yr se Boiling W Termination n 0 dionuclide H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Am-243 Cm-243 Cm-244 nsignificant

-1757, sectio (i.e., 2.5 mr to the sum o cant. This se s the radionu onuclides re

. The ROC The dose f DCGLs and rther detaile dose criteria Water Reactor Plan Table 6 Rx Buildin Excavation D Factor (mrem per mCi) 3.69E-06 2.92E-06 1.94E-06 7.60E-07 1.54E+00 2.08E-06 3.00E-03 9.79E-01 9.84E-03 3.40E-01 6.94E-01 7.50E-01 1.76E-02 1.17E-02 1.30E-02 1.30E-02 5.35E-04 1.79E-02 1.06E-01 6.83E-02 7.26E-03 t Dose Cont on 3.3 states rem/yr) are c of the dose ection provid uclides that c emaining aft list is determ from the rem d BFM DFs d evaluation

a.

r 6-18 BFM g

Dose m/yr W

Exca Dose (mrem m

4.8 3.8 2.5 1.0 2.0 2.7 3.9 1.2 1.3 4.5 9.1 9.9 2.3 1.5 1.7 1.7 7.0 2.3 1.4 9.0 9.6 ributors an s that radionu considered to contributio des the asses can be design ter the remo mined for co moved insign for the RO ns during F 6-35 M Excavatio WTB avation e Factor m/yr per mCi)

F 88E-05 86E-05 56E-05 01E-05 4E+01 75E-05 97E-02 9E+01 30E-01 0E+00 9E+00 2E+00 33E-01 54E-01 72E-01 71E-01 08E-03 36E-01 0E+00 03E-01 61E-02 d Radionuc uclides cont o be insign ns from the sment of dos nated as insi oval of insig oncrete using nificant cont C. The ins FRS and dem on Dose Fac WGTV Excavation D Factor (mrem per mCi) 1.63E-05 1.29E-05 8.56E-06 3.36E-06 6.81E+00 9.19E-06 1.33E-02 4.32E+00 4.35E-02 1.50E+00 3.07E+00 3.31E+00 7.78E-02 5.15E-02 5.73E-02 5.72E-02 2.36E-03 7.90E-02 4.66E-01 3.02E-01 3.21E-02 clides of Con tributing no nificant contr e aggregate se contributi ignificant do gnificant con g the BFM D tributors wa significant c monstration tors Dose m/yr Rem Stru Exca Dose (mrem m

8.18 6.47 4.30 1.69 3.42 4.6 6.66 2.17 2.18 7.54 1.54 1.66 3.90 2.59 2.88 2.87 1.19 3.96 2.34 1.5 1.6 ncern greater than ributors. T of radionuc ions from th ose contribut ntributors we DFs and for s as accounted ontributors of complia maining ucture avation Factor m/yr per mCi) 8E-06 7E-06 0E-06 9E-06 2E+00 1E-06 6E-03 7E+00 8E-02 4E-01 4E+00 6E+00 0E-02 9E-02 8E-02 7E-02 9E-03 6E-02 4E-01 1E-01 1E-02 n 10% of the The 10% crit clides consid he initial suit tors.

ere designat soil using th d for by adju will be excl ance with th e dose terion dered te and ted as he soil usting luded he 25

La Cross License T Revision Note tha low. Ass 25 mrem was used or 0.053 qualitativ represent 6.13.1. R The soil contribut final ROC contribut The dose the three insignific percentag contains the initia contribut both are in Table The Tab surface a that there to date, remainin concentra radionuc to the M contamin contamin reasonab From Att contribut and base designate The data 3 is the m calculate positively the MDC to HTD predomin se Boiling W Termination n 0 t Sr-90 was uming the ra m/yr criterion d to calculate

% percent ve reason th ted a signific Radionuclide DCGLs an tions from th Cs and adjus tor radionucl e percentage e BFM scena cant contribu ges attributa a copies of al suite and tors that wer provided in 6-3 and the le 6-3 mixtu and subsurfac e is minimal LACBWR ng subsurfac ations of r lide mixture MDC biasing nated water nation, the R ly representa tachment 6-3 te greater th ement concr ed as insigni from high a most represe d when the H y detected, t C values whi D radionucli nately Cs-13 Water Reactor Plan included in adionuclide

n. When the a e dose perce of the 25 m hat it was p cant dose fra es of Conce nd BFM D he initial suit st the ROCs lides.

es for the ini arios; BFM utors remov able to the in Tables 20 a d the dose re removed.

Attachment second appl ure was bas ce soil chara l residual ra does not an ce soil that adionuclides e fractions fo g issues dis that caused ROC and rad ative of soils 3, it is seen t an 97.28% o rete are Cs ificant contri activity cores entative data HTD radion then the mixt ich is conser ides using 37, decreases r

n the ROC l mixture in T actual soil ch entages, the mrem/yr crit positively id action.

rn and Adju Fs were us te radionucli for the dose itial suite ra Insitugw, BF ved was the nsignificant c nd 22 from percentages Two metho 6-3. The fir ied the actua sed on conc acterization i dioactivity i nticipate the t has not s identified or initial suit scussed abo concrete co dionuclide m s for FRS pl that for all s of the total d s-137, Co-6 ibutors and a s that were u a available. T uclides are p ture percent rvative. How MDC valu

s.

6-36 ist for soil a Table 6-3, th haracterizati Sr-90 dose w terion. Sr-90 dentified in usted Soil D sed in Refe ides, identify e percentage dionuclides FM Insituds, same for so contributors Reference 5 attributable ods were us rst method ap al concentrat crete cores b in the impac in soil. Bas e presence o yet been c in LACBW te radionucli ove. Based ontamination mixture deriv anning and i soil and conc dose. There 0 and Sr-9 are eliminate used to calcu The most acc positively de ages assigne wever, the ac ues will de although the he Sr-90 dos ion data for was determi 0 was inclu some conc DCGLs and erence 5 to y the insigni e attributable were calcul

, and BFM E oil and the B were differ 5 which prov e to the ag sed for the c applied the ra tions of char but was also cted area sur ed on the ch of significan characterized WR soil, t ides in soil i d on a gene n would be ved for the co implementat crete scenari efore, the fin

0. The r ed from furth ulate the radi curate radion etected. If th ed to the HT ccuracy of th ecrease as e dose contr se fraction w the initial su ined to be 2 uded as a s rete sample BFM DFs calculate t ificant contri e to the remo lated for soi Excavation.

BFM scenar rent for each vide the dos ggregate of calculation a adionuclide racterization o applied to rrounding LA haracterizati nt soil conta

d. Due to the direct d s not technic eralized assu similar to th oncrete was tion.

ios, Cs-137, nal ROCs fo remaining r her detailed ionuclide mi nuclide mix he HTD radi TD radionucl he mixture f the total ribution was was 0.009% o uite radionuc

.06E-02 mre oil ROC fo es not becau the relative ibutors, selec oved insignif il and for ea The final l rios but the

h. Attachmen e percentage the insignif and the resu mixture frac n results.

o soil. Resul ACBWR ind on survey re amination in o the very determinatio cally feasibl umption tha he source o considered Co-60 and S or LACBWR radionuclide evaluation.

ixture in Tab xture fraction ionuclides ar lides are base fractions assi sample act very of the clides em/yr or the use it dose ct the ficant ach of ist of dose nt 6-3 es for ficant ults of ctions lts of dicate esults n any low on of e due at the f soil to be Sr-90 R soil s are ble 6-ns are re not ed on igned

tivity,

La Cross License T Revision The pote the most the adjus The dose The 2.17 (0.68 mr insignific HTD rad review o concentra total sam the maxim mean act scenario contribut that the approach would ac 6-3.

As anoth worst cas core sam homogen 1/2 inch, t (see Atta is that ev WTB res case valu As a co 2.179%

DCGLs a See Tabl of insign se Boiling W Termination n 0 ential effect limiting ins stment of so e percentage 9% value re rem/yr) at th cant contribu dionuclide co f the charact ations of ins mple activity mum 2.179%

tivity of the is 0.787 mr tors of only insignifican h values corr ctually be clo her example, se dose con mples taken neously distr the worst ca achment 6-3) ven in this w sults in an in ue of 2.179%

onservative (calculated and BFM D es 6-19 to 6 ificant contr T

Water Reactor Plan of mixture v significant co il DCGLs an ranged from epresents the he dose lim utors remain oncentration terization da significant c up to and e

% value was selected cor rem/yr with 0.086% (0.0 nt radionucl responding t oser to 0.086

, the concret sequences a in the WT ributed over ase dose con

). This resul worst case s nsignificant c measure, th for the Gro Dose Factors

-23 for the a ributor dose able 6-19 S C

r variability o ontributor do nd BFM Do m 0.403% to e hypothetica mit of 25 mr n constant as ns will increa ata over a ran contributor r xceeding a t s calculated f re samples is a correspon 021 mrem/yr lides would o 25 mrem/y 6% than the te core samp are from the TB is 1.2E+

the entire su nsequence w lt obviously scenario, the contributor d he most lim oundwater sc to account adjusted soil percent was Soil DCGLs Contributor ROC Co-60 Sr-90 Cs-137 6-37 on dose is co ose percenta ose Factors (

2.179%.

al dose contr rem/yr, assu s activity inc ase linearly w nge of total a radionuclides total activity for the WTB s used the do nding dose p r) (see Attac d remain at yr and that th 2.179% val ples taken d WTB basem

+04 pCi/g.

urface of the was 155 mre indicates th e dose based dose percent miting insign cenario for for the insig DCGLs and performed f s for ROC A r Dose Fract Adjusted S (pC 1.25E 6.40E 5.65E onservativel age from all (i.e. 2.179%

ribution of th uming that t creases. Ho with dose up activity in th s are below y representin B Groundwat ose calculate percentage a chment 6-3).

t their MD he insignific lue calculate during chara ment. The Assuming e WTB basem em/yr for the hat remediati d on actual c tage of 1.587 nificant dos the WTB) gnificant con d BFM Dose for Buried P Adjusted for tion Soil DCGLs Ci/g)

E+01 E+03 E+01 ly accounted of the scena

% as seen in he insignific the mixture owever, it is p to 25 mrem he samples, i MDC over ng 25 mrem/

ter scenario.

ed for the W attributed to

. The realis C values a cant contribu ed using the acterization t average tota that the av ment (101.9 e WTB Exc ion is necess core concen 7% which is se contributo was used t ntributor dos e Factors. A Pipe. See sec r Insignifica d for by app arios evaluat Attachment cant radionuc fractions o unlikely tha m/yr. Based it is clear tha r a wide ran

/yr. For exam

. When the a WTB Groundw the insignif tic expectati as concentra utor dose fra mixture in T that represen al activity fo verage activi m2) to a dep avation scen sary but the ntrations from s below the w or percentag o adjust the se (Referenc separate ana ction 6-18.

ant plying ted to 6-3).

clides of the at the d on a at the nge of

mple, actual water ficant ion is ations action Table nt the or the ity is pth of nario.

point m the worst ge of e soil ce 5).

alysis

La Cross License T Revision C

C C

C The mix contribut insignific dose imp se Boiling W Termination n 0 Table ROC Co-60 Sr-90 Cs-137 Table ROC Co-60 Sr-90 Cs-137 Table ROC Co-60 Sr-90 Cs-137 Table ROC Co-60 Sr-90 Cs-137 ture fraction tors is listed cant contribu pact and was Water Reactor Plan e 6-20 Re Ins I

e 6-21 WT Co In 6

2 4

e 6-22 WG Co In 1

1 4

e 6-23 Re Ins In 1

1 5

n for the RO in Table 6-2 utors is attrib therefore in r

eactor Build significant C Insitu GW 4.87E-01 5.05E+00 1.76E-01 TB BFM DF ontributor D nsitu GW 6.66E-02 2.93E+00 4.16E-02 GTV BFM ontributor D nsitu GW 1.20E-01 1.10E+00 4.79E-02 emaining St significant C Re nsitu GW 1.40E-02 1.19E+00 5.28E-03 OC and the

24. Note tha butable to N ncluded in th 6-38 ding BFM D Contributor Reactor Build (mre Insit Fs for ROC Dose Fractio WTB A (mre Insitu DFs for RO Dose Fractio WGTV A (mre Insitu ructures BF Contributor emaining Stru (mre Insitu mixture fra at the majori Ni-63 (with a he group of in DFs for ROC r Dose Frac ding Adjusted em/yr per mC tu Drilling Spo 1.19E-01 2.11E-04 2.91E-02 C Adjusted f on Adjusted BFM em/yr per mC u Drilling Spo 1.17E+00 2.08E-03 2.86E-01 OC Adjusted on Adjusted BFM em/yr per mC u Drilling Spo 6.08E-01 1.07E-03 1.48E-01 FM DFs for r Dose Frac uctures Adjust em/yr per mC u Drilling Spo 1.34E-01 2.36E-04 3.26E-02 action for th ity of the 0.1 a fraction of nsignificant C Adjusted ction d BFM DFs Ci) oils for Insignifi M DFs Ci) oils d for Insign M DFs Ci) oils r ROC Adju ction ted BFM DFs Ci) oils he aggregate 1013 mixtur f 0.08) whic contributors for Excavation 1.58E+00 3.08E-03 3.50E-01 icant Excavation 2.10E+01 4.08E-02 4.63E+00 nificant Excavation 7.00E+00 1.37E-02 1.54E+00 usted for Excavation 3.52E+00 6.85E-03 7.75E-01 e of insignif re fraction fo ch has a very

s.

ficant or the y low

La Cross License T Revision C

6.14.

A check concentra the residu the fill du not in the Insitugw +

complian concentra A

6.15.

As discu considere accordan complian foreseeab scenario A quanti simple qu less than intake rat A dose a irrigation ingestion livestock scenario assessme The Resi used for contamin opposed root dept se Boiling W Termination n 0 T

Concentratio calculation ations of RO ual radioacti uring basem e concrete.

+ BFM Insit nce (see LTP ations were Alternate La ussed in sect ed, Residen nce with NU nce, but wer ble land use is significa itative evalu ualitative ev n the dose fr te would be assessment o n) was perfor n and fruit an k would be ra dose assessm ents included ident Garde the Industri nated zone t to the 1 m d th paramete Water Reactor Plan Table 6-24 I

C ons in Excav n was perfor OC in fill m ivity in the c ment concrete The calcula tuds + BFM P Chapter 5) less than the and Use Sce tion 6.4, tw t Gardener UREG-1757, re used to r

e. NUREG-ant then gre uation of the valuation con om the Indu less.

of the Resid rmed. The R nd vegetable aised on the ment was pe d the ROC at ener soil dos ial Use soil thickness wa depth assume er was adde r

ROC an Mixture ROC Co-60 Sr-90 Cs-137 Insignificant Contributors Total vated Fill M rmed in Re material after concrete was e excavation ation was ba Excavation.

). For all RO e surface soil nario Dose wo alternate with onsite these less l risk-inform 1757 states t eater assuran e dose from ncluded that ustrial Use s dent Gardene Resident Gar es from an o site so the m erformed for t their respec se was calcu dose assess as changed ed in the scr d since the 6-39 nd Insignific e Fractions Mixture F 0.0 0.00 0.87 0.10 1.0 Material ference 8 to excavation.

s instantly re

n. Therefore, ased on BFM

. The summa OC and all ba l DCGLs.

less likely e well and R likely but pl the decisio that if the p nce that the s the Recreat t the dose th scenario beca er scenario (

rdener pathw onsite garden meat and mi r backfilled c ctive mixtur ulated with ment with t to more clo reening appr plant pathw cant Radion Fractions 122 091 774 013 00 o determine The calcul eleased to th

, the source M DFs that w ation DF wi asements, th but plausib Recreational lausible scen n of Indust eak dose fro cenario is un tional Use s han the Recre ause the occ (with onsite ways include

n. It was con ilk pathways concrete and e fractions a the RESRA the paramete osely repres roach used in way is activ nuclide e the maxim lation assum e fill and un term would were the sum ill be applied he hypothetic ble land us l Use with narios were trial Use as om a less lik nlikely woul scenario was eational Use cupancy tim well for dr ed direct dos nsidered hig s were inacti d soil source as listed in T AD determin er changes l ent actual s n the Industr ve in the Re mum hypoth med that 100 niformly mix be in the fil mmation of d during FR cal maximum e scenarios onsite well not analyze the reason kely put plau ld be necessa s not require e scenario w me and well w inking wate e, inhalation ghly unlikely ive. The alte e terms. The Table 6-24.

nistic param listed below site conditio rial scenario esident Gard etical 0% of xed in ll and BFM RS for m fill were

l. In ed for nably usible ary.

ed. A will be water r and n, soil y that ernate dose meters

. The ns as

o. The dener

La Cross License T Revision scenario.

5512). T C

In F

F F

L D

D The asse two ways provide t the altern equal to concentra could not decommi section 6 The soil identified was the Scenario hypothet excavate section 6 The dose Scenario determin above to it is proje The resu as-left co Gardener complian Excavati low dose for the comparis se Boiling W Termination n 0 The remain The paramete Contaminated nhalation Ra raction of T raction of T ruit, Vegetab Leafy Vegeta Drinking Wat Depth of Roo ssment of th

s. First, the m the most acc nate scenario o the maxi ations that r t plausibly o issioned whi 6.4). The dos dose from t d during cha hypothetica DCGLs, th ical maximu d and sprea 6.14). The re e from back assuming nistic parame represent th ected to cont ulting Reside ondition at t r dose from nce during F on (see LTP e from the B WTB in th son, when th Water Reactor Plan ning parame ers changes a d Zone Thick ate - 8400 m3 ime Spent In ime Spent O ble and Grai able Consum ter Intake - 4 ots - 1.22 m.

he soil dose maximum so curate estima o dose was imum allow result in 25 occupy the L ich was cons se calculation he Resident aracterization al maximum e dose was um radionuc ad on the gr esulting dose kfilled conc the BFM I eters used f he Resident G tain the majo ent Gardener the time of m the BFM FRS will be P Chapter 5)

BFM Insitu s he Industria he 30 year de r

eter changes are:

kness - 0.15m 3/yr, ndoors - 0.64 Outdoors - 0.

in Consumpt mption - 21.4 478 L/yr, from the Re oil concentra ate of dose f calculated a wable soil mrem/yr). T LACBWR si servatively a ns are docum Gardener a n as the sou m soil conc 31.4 mrem/y clide concen round surfac e from the R crete was al Insitu geom for the BFM Gardener sc ority of resid r dose from license term M Insitu sce e the summa which is do scenario. Fo al Use scen ecay period i 6-40 s are metabo m,

49,

124, tion - 112 kg esident Gard ations identi from soil in assuming the concentrati The doses w ite until after assumed to b mented in Re lternate scen urce term wa centrations t yr. A dose a ntrations in ce during th Resident Gard lso calculate metry descri M Insitugw do enario. The dual radioact backfilled c mination) wa nario is low ation of the ominated by or example, t nario, assum is included th olic and beh g/yr, ener alternat fied during c the Residen e ROC conc ions in the were calcula r the G-3 pla be 30 years eference 8.

nario using t as 0.66 mre that could r assessment w fill materia he excavatio dener was 26 ed for the R ibed in sec ose assessm WTB was u tivity at licen concrete in as 0.94 mrem w because BFM Insit the Excava the dose fro ming no de he dose is 0.

havioral (fro te scenario w characteriza nt Gardener s centrations w e Industrial ated assumin ant ceased o after license the maximum em/yr. When remain give was also per al. The fill i on of structu 6.9 mrem/yr Resident Ga ction 6.11.1 ment were m used for the nse terminat the insitu ge m/yr. Note t the BFM D tugw + BFM ation Scenari om the BFM ecay, is 1.7

.84 mrem/yr om NUREG was perform ation were us scenario. Sec were theoreti l Scenario ng that a res operation and e termination m concentra n the source en the Indu rformed usin is assumed ure concrete

r.

ardener Alte

. The RES modified as assessment tion.

eometry (i.e that the Res DFs applied M Insituds +

io. This resu M Insitu geom 77 mrem/yr.

r.

G/CR-med in sed to

cond, ically (i.e.,

sident d was n (see ations term ustrial ng the to be e (see ernate RAD listed since e., the sident d for BFM ults in metry

. For

La Cross License T Revision The fina BFM Ex limitation alternate soil. How In conclu not signif B

6.16.

The BFM the conc calculatin acceptab Although the Basem Referenc demolitio L

co L

These lim rate) and ensure th acceptab complian To comp demolitio measurem air demo contamin open air identified The dose open air assessme of potent plausible Table 5.1 but is u concentra limit are demonstr se Boiling W Termination n 0 l considerat xcavation Sc n that the ex scenario do wever, the do usion, the do ficant and th BFM Elevate M is a mixing centration an ng Area Fac ility of eleva h AFs are no ments are li ce 14. The on of structu Less than 2 m oncrete.

Less than 1,0 mits define t d removable hat the dose le. The op nce calculatio ply with the on. These s ment modes.

olition could nation potent r demolition d and remed e from a hyp demolition ent was to fu tial dose. Th e scenario (

1, the scenar sed to help ation that co acceptable, ration using Water Reactor Plan ion is the d cenario. Bec xcavated con ose from exc ose from con ose from the herefore grea ed Area Con g model that nd distributi tors (AFs) in ated areas of ot applicable mited by th Basements ures above 63 mR/hr beta-g 00 dpm/100 the acceptab e contaminat to the publ pen air demo ons for 10 C open air de surveys will

. Scanning c d include u tial. The pre n will prov iated.

pothetical ma limits was e urther risk-i he Worst-Ca (as defined rio is not an p risk infor ould remain assuming a the BFM DF r

dose from th cause the B ncrete would cavated conc ncrete would e Recreation ater assuranc nsideration t uses the tot ion of the r n conjunctio f activity doe e to the BFM e implement will be rem 36 foot eleva gamma total cm2 beta-ga ble operation tion that can lic from airb olition limit CFR 20.1402 emolition lim l use conven coverage for up to 100%

e-remediatio ide confide aximum con evaluated us inform the a ase Drilling in NUREG-nalyzed for c rm and ju in elevated ll activity is Fs.

6-41 he Resident FM Excava d not exceed crete would d be less sinc nal Use and ce that these s

tal inventory residual rad on with conc es not apply.

M, the maxim tation of the mediated to ation. The o surface cont amma loose s nal levels of n remain pr borne contam ts are opera

2.

mits, radiolog ntional gam r pre-remedi of the acc on surveys pe ence that co ncentration th sing the dril acceptability g Spoils asse

-1757, Tabl compliance w stify the de d areas after s accounted Gardener al ation concep d the surface be essential ce plants can Resident Ga scenarios w y as the sourc dioactivity.

centration-ba mum concen e open air de the open ai open air dem tamination o surface cont f fixed (as m rior to open mination gen ational level gical survey mma instrume iation survey cessible surf erformed to ontamination hat could rem lling spoils s y of a worst-essment is c le 5.1). Con with the 10 ecision that remediation for and incl lternative sc ptual model e soil DCGL ly the same nnot be grow ardener alter will not occur ce term and The standa ased DCGLs ntrations that emolition lim ir demolitio molition limit on contact wi tamination.

measured by n air demolit nerated duri ls and are n ys will be pe ents in typic ys on structu face area d prepare buil n above the main after re scenario. Th

-case conditi considered a nsistent with CFR 20.140 the hypoth n to the 2 m luded in the cenario give is based on Ls, the maxi as calculate wn in concret rnate scenar r is unnecess is independe ard approach s to determin t could rema mits describ on limits pri ts are:

ith structura contact exp tion. The l ing demoliti not a part o erformed pri cal scanning ures prior to epending on lding surface e limits wi emediation t he purpose o ion in the co a less likely h NUREG 02 dose crite hetical maxi mR/hr demo final compl en the n the imum ed for te.

ios is sary.

ent of h for ne the ain in bed in ior to al osure limits ion is of the ior to g and open n the es for ill be to the of the ontext y but

1757, erion, imum olition liance

La Cross License T Revision The Wor into a s hypothet terminati to be exc very unli immediat hitting an From Re contamin in 2 mR/

have esse of loose correspon area con pCi/g.

Also from Spoils sc Cs-137.

approxim hypothet meet the Demonst sufficient maximum S

6.17.

The RES contamin dose for from a sm Referenc used to c 1.0 m2 to The AFs smaller a The full R AFs are p se Boiling W Termination n 0 rst-Case Dri pot of resid ical Cs-137 ion taking no cavated and ikely for two tely after lic n area contai eference 8, nation throug

/hr at contac entially no e dust is tr nds to appro ntaining unif m Reference cenario, assu Therefore, mately 10,00 ical maximu e 2 mR/hr trating comp t to account m concentrat oil Area Fa SRAD mode nated. Isolat a given con maller area i ce 8 calculat calculate soi o 100 m2. Th s were calcu area by the so RESRAD Su provided in T Water Reactor Plan illing Spoils dual radioac concentrati o credit for d brought to o reasons. F cense termin ining the ma assuming an gh the first h ct is approxi effect on the rivial. For e oximately 45 form radioac e 8, the Cs-1 uming one-h the dose 0/80,000*25 um area of open air d pliance with t for the ac tions.

actors eling for so ted areas of ncentration.

s defined as tes AFs for e il DCGLs. T he need to a ulated by div oil DCGLs i ummary Rep Table 6-25.

r scenario as ctivity in b ion. The dri decay. The the surface First, the sc ation. Secon aximum hypo n arbitrary c half inch of mately 10,0 e dose rate b example, a 5 pCi/cm2 co ctivity throu 37 concentr half inch con from this 5 = 3.1 mrem residual rad demolition h the dose c ctivity, and a oil assumes f contaminati The ratio of the Area Fa each ROC u The Area o apply AFs to viding the pC in Table 6-7 ports are pro 6-42 ssumes that basement flo lling I assum entire inven while mixin enario assum nd, the proba othetical con circular area concrete, the 00 pCi/g Cs because the a loose contam ompared to 2 ugh a half i ration that w ntamination less likel m/yr and is dioactivity, b limit, is n criterion usin assess the d that the en ion that are f the dose fr actor (AF).

using RESRA of Contamin o contaminat Ci/g per 25 ovided electr the water su oor concret umed to occu ntory within ng with over mes that a w ability of an ntamination a with a 36 e Cs-137 co s-137. The l activity asso mination lev 29,000 pCi/c inch layer a would result i depth, was ly but plau not significa beyond that ot justified ng the total dose, in the ntire area w smaller than rom the full AD with the nated Zone ted areas gre mrem/yr va ronically wit upply well i e that cont ur immediat the drill diam rburden fill water supply assumed eig level during 6 inch diame oncentration evels of loo ociated with vel of 10,00 cm2 total inv at a concent in 25 mrem/

approximat usible scen ant. Further required fo on a risk inventory a areas with within the L n 7500 m2 w source term e determinis parameter eater than 10 alue from RE th Reference is drilled dir tains the hi tely after lic meter is assu and soil. Th y well is inst ght inch bor g drilling is l eter and uni that would r se contamin a very thin 00 dpm/100 ventory in a 1 tration of 10

/yr in the Dr ely 80,000 p nario would r reduction o or remediatio k-informed b and BFM D the hypoth SE, 7500 m will have a l m area to the stic paramete was varied 00 m2 is unli ESRAD for e 8. The resu rectly ighest cense umed his is talled ehole ow.

iform result nation layer 0 cm2 1 cm2 0,000 rilling pCi/g d be of the on to basis.

DFs is etical m2, is lower dose er set from ikely.

each ulting

La Cross License T Revision Radionu Cs-137 Co-60 Sr-90 B

6.18.

Buried p section d The calcu 6.18.1. S With the to remain potential Water fro impacted contamin required DCGLs character potential discussed results in then sam 6.18.2. E Consisten

material, buried pi from bur NUREG-the radio piping at conceptu that no m between The conc develope of the pip se Boiling W Termination n 0 uclide Buried Pipin iping is defi describes the ulations are ource Term exception o n at LACBW is minimal.

om LACBW d because th nation and w for non-imp for buried rization has

. The radio d in LTP Ch ndicate that t mples will be Exposure Sc nt with the two exposu ipe being ex ied pipe rem

-1757, Appe nuclide conc t LACBWR ual model is mixing is ass pipes during ceptual mod ed for the BF pe is assume Water Reactor Plan Table 1m2 9.44 9.11 11.22 ng Dose Asse ned as below e buried pip performed b m and Radio of a portion o WR was asso See Table 6 WR Crib Hou hey only con will continu pacted areas.

pipe were been perfo onuclide mix hapter 5, if c the buried p analyzed fo enario and guidance i ure scenarios xcavated and maining in sit endix J state centration in is a minimu more conser sumed to occ g excavation dels for the b FM. In the I ed to instant r

e 6-25 Su 2m2 5.56 5.42 6.66 essment and w ground pip e dose asses by RESRAD onuclide Mi of the Circu ociated with 6-2 for list o use to G-3 an ntacted clean ue operation calculated ormed in b xture is ass continuing c piping dose c r HTD radio Critical Gr n NUREG-s were cons d spread acr tu (Insitu sce es that it sho n the analysi um of 1 m b rvative than cur with the

n.

buried pipe I Insitu scenar taneously rel 6-43 urface Soil A Area F 5

3 3

3 d DCGL pe located o ssment meth D and Excel s xture ulating Water h contaminat of buried pip nd Well wate n river wate n after licen for the in buried pipin sumed to be haracterizati could exceed onuclides and roup 1757, Appe idered; 1) in ross the surf enario).

ould be appr s, including below grade.

the NUREG e soil in the Insitu and E rio the residu lease and mi Area Factor Factors m2

.07

.01

.69 outside of str hods and pro spreadsheet a r System Pip ted systems pe to remain er piping for er or ground nse terminat nitial suite ng due to th e the same ion is perfor d 50% of th d additional endix J rega nadvertent in face (Excav ropriate to u any interspe

. The LACB G-1757, App 1 m cover o Excavation s ual radioact ix with a thi rs 10m2 2.04 2.00 2.45 ructures and ovides the r as detailed in pe, none of and therefo

n. The High r Well #3 are dwater with tion. No DC radionuclide the very low as listed in rmed for bu he 25 mrem/y assessments arding asses ntrusion wh vation scenar use the arith ersing clean BWR buried pendix J con or the intersp scenarios are tivity on the in 2.54 cm l 100m2 1.19 1.18 1.41 basements.

resulting DC n Reference the buried p ore contamin Pressure Se e considered h no potentia CGLs or FS es. To date w contamin n Table 6-3 ried pipe an yr dose crite s performed ssment of b hich results i rio), and 2) hmetic avera n soil. The b d pipe excav nceptual mod persing clean e similar to internal sur ayer of soil This CGLs.

8.

piping nation ervice d non-al for SS is e, no nation

3. As nd the

erion, buried in the dose age of buried vation del in n soil those rfaces in an

La Cross License T Revision area equa released presence assumpti flowable to be con scenario ground s surface d Worker i and soil m 6.18.3. B RESRAD DCGLs f The burie and grou is design Pipe only significan the site.

The Insi include t input par term geo than one the thin basement insitu do table. Th Flow w area equa The insit Insitu Gr elevation internal s the Exca Circulatin calculate 6.18.4. B The RES Referenc se Boiling W Termination n 0 al to the int radioactivity of the pipe on, particul fill material nservative on model assum urface after disturbance c is exposed to models.

Buried Pipin D modeling for the intern ed piping w uping of all i nated as the

y. The separ ntly differen tu dose calc the Circulati rameters app ometry (see T meter below layer (2.54 t floor, i.e..,

se, which is he assumed ere calculate al in size to t tu dose for roundwater p n of the bot surface area avation scena ng Water D surface soil Buried Pipe SRAD Summ ce 8. The full Water Reactor Plan ternal surfac y as a belo e to reduce arly for the

l. The assum n the sensiti mes that the excavation.

caused by th o the Insitu a ng Dose Asse was perfor nal surfaces as separated impacted bur Group. Th ation of the nt from the o culation for ng Water D plied to the B Table 6-26).

w the ground cm) source

, the WGTV driven by th RESRAD pa ed assuming the summed the Circulat parameters w ttom of the of the pipe.

arios (and c Discharge P l DCGLs wit DCGLs Ini mary Report l RESRAD S r

ce area of th ow ground 2 environmen Circulating mption of a t ivity analysi released rad A 15 cm m he large scale and Excavate essment rmed to cal of the pipes d into two ca ried pipe oth he second ca Circulating other pipe an r the buried Discharge pip BFM Insitu G The depth d surface in e term was V at 621 foot he groundwa arameters A g that the all internal sur ting Water D with the elev pipe (630 f

. See Table correspondin Pipe were c th source ter tial Suite file names f Summary Re 6-44 he pipe. The 2.54 cm lay ntal transpor g Water Disc thin soil mix is for the BF dioactivity is mixing layer e excavation ed soil via th lculate DSR after conver ategories. Th her than the ategory cons Water pipe w nd the pipes piping Gr pe) was perf Groundwater of the buried order to be nominally a t elevation.

ater pathway Area of Con of the pipe face area of Discharge P vation of the foot). The c 6-26 for the ng DCGLs) f alculated us rm adjustmen for the RESR eports are sto e Insitu scen yer of soil w rt and migra charge Pipe xing layer fo FM (see sect s mixed with is assumed n required to he same path Rs which ar rting units to he first categ Circulating isted of the was necessa are located i roup (whic formed by R r scenario w d piping var below the f assumed to Using a low y, by minimiz ntaminated Z in the group f all Group pi Pipe was als e thin contam contaminated e source term for both the sing the RE nts as listed RAD Buried ored electron nario model with no cred ation. This i which will or buried ma tion 6.11.1) h a 15 cm la due to the o remove pip hways applic re the basis o dpm/100 cm gory include Water Disc Circulating ary because t in distinctly ch as stated RESRAD mo with adjustme ries but is in freeze zone.

be the sam wer elevatio zing the dist Zone and L p was locate ipes.

so calculated minated laye d area was m parameter e Buried Pip ESRAD par in Table 6-2 Piping runs nically. The assumes tha dit taken fo is a conserv l be filled w aterial was sh

. The Excav ayer of soil o extensive gr pe. The Indu cable to the for determ m2.

ed the summ charge Piping Water Disch the geometry different pa d above doe odeling usin ents to the so n all cases gr The elevati me as the de on maximize tance to the w Length Paral ed in one cir d using the er being set a set equal t rs. The dose pe Group an rameters use

26.

s are listed in e detailed inp at the or the vative with a hown vation on the round ustrial BFM mining mation g and harge y was arts of s not ng the ource reater on of eepest es the water llel to rcular BFM at the o the from nd the ed to n

puts

La Cross License T Revision C

A Z

T C

L A

U T

to the DC resulting Excel spr provided 6.18.5. B The Buri contribut final RO contribut fractions The dose pipe scen all buried Sr-90 and The dose pipe DCG insignific 6-3 conta initial sui contribut se Boiling W Termination n 0 Table 6-Parame Cover Depth (m Area of Contam Zone (m2)

Thickness of Contaminated z Length Parallel Aquifer Flow (m Unsaturated Zo Thickness (m)

CGL calcula RESRAD D readsheet as d in Table 6-2 Buried Pipe ied Pipe DC tions from th Cs and adju tors. The do from Table e percentage narios; Insitu d pipe scenar d Cs-137.

e percentages GL categorie cant radionu ains a copy o ite and the d tors that wer Water Reactor Plan

-26 RESR ter m) minated zone (m) to m) ne ation, includ DSRs gener s described i

27.

Radionuclid CGLs in Tab he initial suit ust the ROC ose percent 6-3.

es for the in u and Excava rios and the s for the insi es. Therefore uclide fractio of Table 24 f dose percenta re removed.

r RAD Sourc DCGL Buried Pipe Group Insitu 5.465 1349.71 0.0254 41.45 0.61 ding RESRA rated by mo in Reference des of Conc ble 6-27 wer te radionucli Cs for the do tages for th nitial suite ra ation. The fi same as ide ignificant co e, adjustmen ons were calc from Referen ages attribut 6-45 ce Term Par L Calculatio Buried P Group Excavati 0

1349.7 0.15 41.45 6.0706 AD source te odeling and e 8. The bur cern and Ad re used in R ides, identify ose fraction a he initial su adionuclides inal list of in ntified for so ontributors w nts to the Bu culated separ nce 5 which able to the a rameters for ons Pipe p

ion Circu Wa Disch Pi In 2.

1 766 0.0 160 6

3.

erm parame all unit con ried pipe DC djusted DCG Reference 5 t y the insigni attributable uite were ca s were calcu nsignificant c oil and base were differen uried Pipe DC rately for ea h provides th aggregate of r Buried Pip ulating ater harge ipe nsitu Ci D

Ex 74 6.14 0254 0.02 33 eter calculati nversions ar CGLs for th GLs to calculate ificant contri to the remo alculated us ulated for ea contributors ments. The R nt for each of CGLs to acc ach of the fou e dose perce the insignifi ping irculating Water Discharge Pipe xcavation 0

766.14 0.15 160.02 6.0706 ions, a list o e provided he initial suit the relative ibutors, selec oved insignif sing the mi ach of the b was the sam ROCs are C f the four bu count for the ur. Attachme entages for th ficant of the in an te are dose ct the ficant ixture buried me for Co-60, uried ent he

La Cross License T Revision Rad C

E E

E P

P P

P A

A C

C The dose 1.961%.

insignific The final Excavati i.e., the i are provi se Boiling W Termination n 0 dionuclide

(

H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Am-243 Cm-243 Cm-244 e fraction o Table 6-28 p cant dose per l DCGLs to on scenarios nsitu and ex ided in Table Water Reactor Plan Tab Buried Pipe Group Insitu (dpm/100 cm2 4.69E+08 1.82E+07 0.00E+00 1.12E+10 9.12E+06 4.67E+10 5.84E+05 1.01E+08 2.33E+07 2.57E+07 1.46E+09 2.68E+09 1.43E+11 1.50E+06 7.85E+05 7.93E+05 5.14E+07 1.82E+06 1.49E+06 7.57E+08 3.03E+08 of the aggre provides the rcentage.

be used du s must be su xcavation sce e 6-29.

r ble 6-27 B

2)

Buried P Exca (dpm/1 4.65 2.43 5.95 1.52 8.43 5.55 3.99 1.27 8.79 3.60 1.82 1.70 6.62 9.90 8.91 8.92 3.04 6.52 1.11 1.71 1.59 egate of the e final Buried uring FSS ac ummed in the enarios may 6-46 Buried Pipi ipe Group vation 100 cm2) 5E+09 E+10 5E+10 2E+11 E+04 5E+10 9E+07 7E+05 9E+07 0E+05 2E+05 0E+05 2E+06 0E+06 E+06 2E+06 4E+08 2E+06 E+06 E+06 9E+07 insignifican d Pipe DCGL ccount for th e conceptual y occur in pa ing DCGLs Circulating Water Discha Pipe Insitu (dpm/100 cm 1.56E+08 1.53E+07 0.00E+00 0.00E+00 4.92E+07 1.98E+11 6.94E+05 1.01E+08 7.26E+06 1.31E+08 1.45E+12 1.40E+14 4.72E+19 1.04E+07 7.88E+05 8.11E+05 1.11E+08 3.84E+06 1.52E+06 6.63E+08 3.01E+08 nt contribut Ls for the R he fact that t l model for arallel. The s g

arge m2)

Circul Disc Ex (dpm 6

2 7

1 8

7 4

1 1

3 1

1 6

1 1

1 3

7 1

1 2

tors ranges ROC adjusted the dose fro buried pipe summed Bur lating Water charge Pipe xcavation m/100 cm2)

.23E+09

.45E+10

.77E+10

.98E+11

.58E+04

.24E+10

.23E+07

.29E+05

.19E+08

.66E+05

.86E+05

.73E+05

.71E+06

.29E+07

.16E+07

.16E+07

.68E+08

.93E+06

.16E+06

.79E+06

.07E+06 from 0.413 d for the rem om the Insitu dose assessm ried Pipe DC

% to moved u and

ment, CGLs

La Cross License T Revision Radion Co-Sr-Cs-E 6.19.

There is concentra under the Building In late 20 and licen 1983, pr results. G groundw Groundw ROCs id irrigation GW Exp Guidance AMCG d se Boiling W Termination n 0 Tab nuclide B

(d

-60

-90 137 Table 6 Existing Gro low potent ations have e Turbine Bu indicated po 012, five add nse terminati redominantly Groundwater water contami water Exposu dentified in n the only ex posure Facto e Report 11 drinking wat Water Reactor Plan ble 6-28 Buried Pipe Group Insitu dpm/100 cm2 9.01E+06 5.77E+05 2.54E+07 6-29 Sum for Radionucli Co-60 Sr-90 Cs-137 oundwater D tial for signi been identi uilding. Sam ositive groun ditional mon ion. Results y H-3. See r Exposure ination that m ure Factors Table 6-24 xposure pathw ors were th 1 Ingestion ter intake rat r

Buried Pip Insignifica

2)

Buri G

Exc (dpm/

8.3 3.9 3.5 mmed Burie Insignifican de Buri G

(dpm 8.3 5.6 3.5 Dose ificant grou ified in grou mpling in 19 ndwater con nitoring well indicated lo LTP Chapt Factors we may be pres for existing plus H-3.

way from gr herefore calc Dose Conv te of 327 L/y 6-47 pe DCGLs f ant Radionu ied Pipe Group avation

/100 cm2) 9E+04 8E+07 9E+05 ed Pipe DCG nt Radionuc ied Pipe Group

/100 cm2) 1E+04 9E+05 4E+05 ndwater con undwater ad 983 from a w tamination a l pairs were wer groundw ter 2 for a ere calculate ent at the tim g GW conta Because th roundwater i culated in R version Fact yr. See Table for ROCs A uclide Fract Circulat Water Disc Pipe Insitu (dpm/100 4.8 6.8 1.2 GLs for RO clide Fracti Circulat Water Disc Pipe (dpm/100 8.53E+

6.70E+

3.64E+

ntamination djacent to su well located d at relatively installed to water contam summary o ed to determ me of license amination w he industria is potable wa Reference 8 tors and the e 6-30.

Adjusted for tions ting charge e

u 0 cm2)

W (d

82E+07 80E+05 28E+08 OCs adjusted ons ting charge e

0 cm2)

+04

+05

+05 to be prese uspected bro down gradie low concent support site mination lev of characteri mine the do e termination were calculat al scenario d ater from an 8 directly u e assumed i r

Circulating Water Dischar Pipe Excavation dpm/100 cm2 8.55E+04 4.22E+07 3.65E+05 d

ent although oken floor d ent of the Tu trations.

e characteriz vels than fou ization and se from exi

n.

ted for the does not in n onsite well sing the Fe industrial w rge

2) h low drains urbine zation und in HSA isting three clude

. The ederal worker

La Cross License T Revision D

6.20.

As discu be made and could After com area and calculate

where:

The dose buried pi multiplyi se Boiling W Termination n 0 Ra Demonstrati ssed in secti through the d potentially mpliance is buried pipin dose and su Complian Max BFM Max BFM Summatio and Burie Max Open Max Buri Max Exis e for baseme iping is calcu ing the ratio Water Reactor Plan Tabl adionuclide Co-60 Cs-137 Sr-90 H-3 ing Complia ion 6.5.5, th summation y occur in pa demonstrate ng, the mean ummed as sh

nce Dose M Insitu (ds)

M Excavation on BFM Insi ed Pipe Insitu n Land ied Piping Ex sting Ground nts is calcula ulated by div by 25 mrem r

le 6-30 G

Gro ance with D he final demo of dose from arallel.

ed independ n concentrati hown in Equ n

itu (gw) u xcavation dwater ated directly viding the m m/yr. Note th 6-48 Groundwate oundwater E (mrem/yr 8.80 1.64 4.64 2.09 ose Criterio onstration of m exposure dently throug ons or inven ation 6-2.

= Dose to I

= maximum (mrem/yr)

= maximum basements

= summatio basements (mrem/yr)

= maximum (mrem/yr)

= maximum (mrem/yr)

= maximum y from mean mean FSS con hat the BFM r Exposure Exposure Fac per pCi/L) 0E-03 4E-02 4E-02 9E-05 on f compliance scenarios th gh the FRS ntory values Industrial W m BFM Insit m BFM Exc (mrem/yr) on of BFM I s (mrem/yr)

) from all pip m dose from

)

m dose from

)

m dose from n STS results ncentrations Insitugw dos Factors ctors e with the d hat are not m of each stru from the FR Worker AMC tuds dose from cavation dose Insitugw dose and Buried pe m open land s buried pipin existing gro

s. The dose f by the DCG se from the b dose criterion mutually excl ucture, open RS will be us Equatio

G (mrem/yr) m basement e from e from all Pipe Insitu d survey units ng Excavatio oundwater for open land GLs and basement n will lusive n land sed to n 6-2

)

s dose on d and

La Cross License T Revision assigned Insitugw S contamin contribut groundw R

6.21.

1.

H R

2

2.

E W

3.

U C

o

4.

U R

D

5.

E C

6.

P R

7.

P W

an

8.

E D

9.

A R

10.

S C

11.

Z (C

th

12.

A 2

13.

S M

14.

E D

se Boiling W Termination n 0 the Maximu Summation nation can ei te to dose fro water summat References Haley & Aldr Reactor, Dair 015.

EnergySoluti Water Reacto U.S. Nuclear Consolidated f Radiologic U.S. Nuclear Radiation Sur December 20 EnergySoluti Concern Duri acific North Reactor Mate acific North Within and A nd Decomm EnergySoluti DCGL and C Argonne Nati RESRAD 6.0 andia Nation Contaminatio ZionSolution CRA) Repor he Zion Rest Argonne Nati 001.

heppard and Major Soil Ty EnergySoluti Demolition L Water Reactor Plan um BFM Ex term in Equ ither be retai om well wate tion because rich Inc., Hy ryland Powe ons Technic or Historical Regulatory Decommiss cal Criteria, F Regulatory rvey and As 006.

ons Technic ing LACBW hwest Labora erials, Pacific hwest Labora Around Comm missioning As ons Technic oncrete BFM ional Labora 0 and RESRA nal Laborato on From Dec s Technical rt, Evaluation toration Proj ional Labora d Thibault, D ypes: A Com ons Technic Limits.

r cavation dos uation 6-2. T ined in the co er, not both.

e it is based o ydrogeologic r Cooperativ cal Support D Site Assessm Commission sioning Guid Final Report Commission sessment of cal Support D WR Decomm atory, NURE c Northwest atory, NURE mercial Nuc ssessment -

cal Support D M Dose Fact atory, NURE AD-BUILD ory, NUREG commissioni Support Doc n of Hydrolo ect.

atory, Users Default Soil/S mpendium, H cal Support D 6-49 se in Equatio The two scen oncrete and The Buried only on the g cal Investiga ve, Genoa W Document R ment (HSA) n, NUREG-1 dance - Char t - Septembe n NUREG-1 Materials an Document R missioning.

EG/CR-3474 Laboratory EG/CR-4289 clear Power P 1985.

Document R tors.

EG/CR-6697 3.0 Comput G/CR-5512, V ing Paramete cument 14-0 ogical Param s Manual for Solid /Liquid Health Physi Document R on 6-2 will n narios are mu excavated o d Pipe Insitu groundwater ation Report, Wisconsin, Fi RS-TD-31319

).

1757, Volum racterization er 2006.

1575, Supple nd Equipmen RS-TD-31319 4, Long-Live

- 1984.

9, Residual R Plants; Origi RS-TD-31319 7, Developm ter Codes - D Volume 3, R er Analysis -

006, Conesto meters in Sup r RESRAD V d Partition C cs, Vol. 59 N RS-TD-31319 not be includ utually exclu or released to dose is inclu r pathway.

, La Crosse B ile No. 3870 96-003, La C me 2, Revisio

, Survey, an ement 1, Mu nt Manual (M 96-001, Rad ed Activation Radionuclide in, Distribut 96-004, LAC ment of Proba December 2 Residual Rad

- October 19 oga Rovers &

pport of Dos Version 6, A Coefficients, No 4, Octob 96-005, La C ded in the B usive; the o the fill and uded in Boiling Wat 05-008, Janu Crosse Boilin on 1, nd Determina ulti-Agency MARSAME dionuclides o n Products in e Concentrat ion, Invento CBWR Soil abilistic 000.

dioactive 999.

& Associates se Modeling ANL/EAD-4,

, Kds, for Fo er 1990.

Crosse Open BFM ter ary ng ation E) -

of n

tion

ory, s

for

, July our n Air

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

ure 6-1 S

6-50 Site Regionaal Location

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

Figure 6-2 6-51 2

Site Ovverview

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 6-3 6-52 LACBWR Buildings

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 6-4 6-53 LACBWR End State

L L

R La Crosse Boilin License Termin Revision 0 ng Water React ation Plan or Figure 6-55 LACBWR 6-54 R End State - Backfilled Struc ctures

La Cross License T Revision Figure 6 se Boiling W Termination n 0 6-6 LACB Water Reactor Plan BWR End S r

State - Back 6-55 kfilled Reacctor Building Basementt Elevation V View

La Cross License T Revision Input parame value Input para valu Assign defau from NUREG Vol.

Behavioral pa Assign 75% perc TEDE is positiv with the pa se Boiling W Termination n 0 Fi eter Sensitive, ameter e

ult value G/CR 5512 3

arameter centile value if vely correlated arameter Water Reactor Plan gure 6-7 Assi TED

, lPRCCl > 0.25 r

RESRAD P Input paramete value ign 25% percentile DE is negatively co with the parame Classi Sensitive Complete using Assign NUREG Prio Input Assign from NUR V

Metabo Classify Metabo Sele pa 6-56 Parameter er e value if orrelated eter fy parameter as or Non-sensitiv sensitivity analysi RESRAD v7.0 distribution from G/CR-6697, Att C ority 1 or 2 t parameter value default value REG/CR 5512 Vol. 3 lic parameter y as Behavioral, olic, or Physical ect model arameter Selection Fl A

Non-sen ve is Classify as Pri 1, 2 or 3 No low Chart Input parameter value Assign 50% value distribution nsitive, lPRCCl < 0 Inpu Assign from R P

iority Inpu S

av Physica 0.25 ut parameter value n Median value RESRAD v7.0 Priority 3 ut parameter value Site data vailable?

al parameter Yes

La Crosse B License Ter Revision 0 R

Boiling Wate rmination Pla RESRAD In er Reactor an nput Param ATTA meters for LA 6-57 CHMENT ACBWR So 6-1 oil DCGL UUncertainty Analysis

La Cro License Revisio Soil Co Basic rad Initial prin Distribu Ac-227 (d Pu-239)

Am-241 and Pu-2 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-137 Eu-152 Eu-154 Eu-155 Fe-155 Gd-152 (

H-3 Nb-94 Nd-144 (d Ni-59 Ni-63 sse Boiling Wat e Termination P on 0 Parameter (unit) ncentrations diation dose limit (mre ncipal radionuclide (p ution coefficients daughter of Cm-243 a (also daughter of Cm 241) daughter for Eu-152) daughter for Eu-152) ter Reactor Plan Type a

em/y)

Ci/g) P (contaminated, unsat and P

-245 P

P P

P P

P P

P P

P P

P P

P P

P P

SOIL DCG Priority b

Treatme 3 D 2 D turated, and saturated 1 D 1

S 1

S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 D 1 S 1 S 1 D 1 S 1 S GL: RESRAD PARA ent c

Value/Distr 25 1

d zones) (cm 3/g) 450 Not Included in Analys Not Included in Analys Lognorm Not Included in Analys Not Included in Analys Lognorm Lognorm Lognorm Lognorm Not Included in Analys Lognorm 825 Lognorm Not Included in Analys 158 Lognorm Lognorm 6-58 METERS FOR UNCE ribution 10 CFR Unit Va Mean K NUREG 3.9-2, S Thibaul Uncertainty sis

< 0.1%

mixture Uncertainty sis

< 0.1%

mixture mal-N NUREG Uncertainty sis

< 0.1%

mixture Uncertainty sis

< 0.1%

mixture mal-N NUREG mal-N NUREG mal-N NUREG mal-N NUREG Uncertainty sis

< 0.1%

mixture mal-N NUREG Median NUREG (No san Table 3 mal-N NUREG Uncertainty sis

< 0.1%

mixture RESRA Nd not l NUREG mal-N NUREG mal-N NUREG ERTAINTY ANALYSI Basis R 20.1402 lue Kd Value for sand G/CR-6697, Table Sheppard and t

of radionuclide of radionuclide G/CR-6697 Att. C of radionuclide of radionuclide G/CR-6697 Att. C G/CR-6697 Att. C G/CR-6697 Att. C G/CR-6697 Att. C of radionuclide G/CR-6697 Att. C Value G/CR-6697, Att. C nd value listed in

.9-2)

G/CR-6697 Att. C of radionuclide ADv.7.0 Default listed in G/CR-6697 G/CR-6697 Att. C G/CR-6697 Att. C IS Distribution's 1

2 NR N R

NR N R

6.72 3.2 2

NA N A

NA N A

2.4 3.2 2

NA N A

NA N A

5.46 2.5 3

6.1 2.3 3

6.72 3.2 2

6.72 3.2 2

NA N A

5.34 2.6 7

6.72 3.2 2

-2.81 0.5 NA N A

NA N A

6.05 1.4 6

6.05 1.4 6

Statistical Paramet 3

R NR R NR 2 NA A NA A NA 2 NA A NA A NA 3 NA 3 NA 2 NA 2 NA A NA 7 NA 2 NA 5 NA A NA A NA 6 NA 6 NA ers d

4 Mean/

Median NR NR NA 825 NA NA NA NA NA 11 NA NA NA NA NA 235 NA 446 NA 825 NA 825 NA NA NA 209 NA 825 NA 0.06 NA NA NA NA NA 424 NA 424

La Cro License Revisio Np-237 (

Cm-245, Pa-231 (d Pu-239)

Pb-210 (d Po-210 (d Pu-238 Pu-239 (a Pu-240 (a Pu-241 Ra-226 (d Ra-228 (d 240)

Sm-148 (

Sr-90 Tc-99 Th-228 (d 240)

Th-229 (d Np-237, a Th-230 (d 238)

Th-232 (d 240)

U-233 (da Np-237, a sse Boiling Wat e Termination P on 0 Parameter (unit) also daughter for Am and Pu-241) daughter for Cm-243 daughter for Pu-238) daughter Pu-238) also daughter for Cm also daughter for Cm daughter Pu-238) daughter Cm-244 and (daughter Eu-152) daughter Cm-244 and daughter Am-241, Cm and Pu-241) daughter Cm-246 and daughter Cm-244 and aughter Am-241, Cm and Pu-241) ter Reactor Plan Type a

-241, P

and P

P P

P

-243)

P

-244)

P P

P d Pu-P P

P P

d Pu-P m-245, P

d Pu-P d Pu-P

-245, P

SOIL DCG Priority b

Treatme 1 S 1 D 1 D 1 D 1 S 1 S 1 S 1 S 1 D 1 D 1 D 1 S 1 S 1 D 1 D 1 D 1 D 1 D GL: RESRAD PARA ent c

Value/Distr Not Included in Analys Not Included in Analys Not Included in Analys Not Included in Analys Not Included in Analys Not Included in Analys Not Included in Analys Lognorm Not Included in Analys Not Included in Analys 245 Lognorm Not Included in Analys Not Included in Analys 3200 Not Included in Analys Not Included in Analys 35 6-59 METERS FOR UNCE ribution Uncertainty sis

< 0.1%

mixture Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu Uncertainty sis

< 0.1%

mixture Uncertainty sis

< 0.1%

mixture Uncertainty sis

< 0.1%

mixture mal-N NUREG Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu Mean K NUREG 3.9-2, S Thibaul mal-N NUREG Uncertainty sis

< 0.1%

mixture Uncertainty sis parent <

radionu 0

Mean K NUREG 3.9-2, S Thibaul Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu Mean K NUREG 3.9-2, S Thibaul ERTAINTY ANALYSI Basis of radionuclide

< 0.1% of clide mixture

< 0.1% of clide mixture

< 0.1% of clide mixture of radionuclide of radionuclide of radionuclide G/CR-6697 Att. C

< 0.1% of clide mixture

< 0.1% of clide mixture Kd Value for sand G/CR-6697, Table Sheppard and t

G/CR-6697 Att. C of radionuclide

< 0.1% of clide mixture Kd Value for sand G/CR-6697, Table Sheppard and t

< 0.1% of clide mixture

< 0.1% of clide mixture Kd Value for sand G/CR-6697, Table Sheppard and t C IS Distribution's 1

2 NA N A

NA N A

NA N A

NA N A

NA N A

NA N A

NA N A

6.86 1.8 9

NA N A

NA N A

6.72 3.2 2

3.45 2.1 2

NA N A

NA N A

8.68 3.6 2

NA N A

NA N A

4.84 3.1 3

Statistical Paramet 3

A NA A NA A NA A NA A NA A NA A NA 9 NA A NA A NA 2 NA 2 NA A NA A NA 2 NA A NA A NA 3 NA ers d

4 Mean/

Median NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 953 NA NA NA NA NA 825 NA 32 NA NA NA NA NA 5884 NA NA NA NA NA 126

La Cro License Revisio U-234 (da U-235 (da 239)

U-236 (da 240)

Initial con present in Calcula Time sinc Time for Contam Area of c Thicknes Length pa Does the penetrate Contamin table Cover a Cover de Density o Cover ero Density o (g/cm

3)

Contamin m/y)

Contamin sse Boiling Wat e Termination P on 0 Parameter (unit) aughter Pu-238) aughter Cm-243 and aughter Cm-244 and ncentration of radionu n groundwater (pCi/l) ation Times ce placement of mate calculations (y) minated Zone contaminated zone (m ss of contaminated zo arallel to aquifer flow e initial contamination e the water table?

nated fraction below w and Contaminated epth (m) of cover material osion rate of contaminated zone nated zone erosion ra nated zone total poros ter Reactor Plan Type a

P Pu-P Pu-P uclides P

erial (y)

P P

m

2) P one (m)

P (m) P NA water P

d Zone Hydrologic P

P P,B P

ate P,B sity P SOIL DCG Priority b

Treatme 1 D 1 D 1 D 3 D 3 D 3 D 2 D 2 D 2 D NA NA 3 D cal Data 2 D 2 D 2 D 1 D 2 S 2 D GL: RESRAD PARA ent c

Value/Distr Not Included in Analys Not Included in Analys Not Included in Analys 0

0 0, 1, 3, 10, 30, 1000 7500 1

98 No 0

0 NA NA 1.76 Continuous Lo 0.31 6-60 METERS FOR UNCE ribution Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu Uncertainty sis parent <

radionu No exis contam Start of immedia termina

, 100, 300, 0

RESRA 0

Size of Site Exc Surface thicknes exceed Diamete contam Contam surface Contam surface No cove No cove No cove 6 Site spe ogarithmic NUREG Table 3 Site spe ERTAINTY ANALYSI Basis

< 0.1% of clide mixture

< 0.1% of clide mixture

< 0.1% of clide mixture ting groundwater ination dose calculation ately after license tion AD Default LACBWR Licensed clusion (LSE) area e Soil contamination ss not expected to 1 m.

er of 7500 m2 inated zone minated zone at minated zone at er er er ecific e

G/CR-6697 Att. C

.8-1 ecific e

IS Distribution's 1

2 NA N A

NA N A

NA N A

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NA N A

NR N R

NR N R

NR N R

NR N R

NR N R

5E-08 0.00 0

NR N R

Statistical Paramet 3

A NA A NA A NA R NR R NR R NR R NR R NR R NR A NA R NR R NR R NR R NR R NR 07 0.005 R NR ers d

4 Mean/

Median NA NA NA NA NA NA NR NR NR NR NR NR NA NR NR NR NR NR 0.2 0.0015 NR

La Cro License Revisio Contamin Contamin conductiv Contamin Humidity Evapotra Average Precipitat Irrigation Irrigation Runoff co Watershe or pond (

Accuracy computat Saturate Density o Saturated Saturated Saturated Saturated conductiv Saturated sse Boiling Wat e Termination P on 0 Parameter (unit) nated zone field capa nated zone hydraulic vity (m/y) nated zone b parame in air (g/m

3) anspiration coefficient annual wind speed (m tion (m/y)

(m/y) mode oefficient ed area for nearby str (m

2) y for water/soil tions ed Zone Hydrolog of saturated zone (g/c d zone total porosity d zone effective poros d zone field capacity d zone hydraulic vity (m/y) d zone hydraulic grad ter Reactor Plan Type a

acity P P

ter P P

P m/s) P P

B B

P ream P

gical Data cm

3) P P

sity P P

P dient P SOIL DCG Priority b

Treatme 3 D 2 D 2 S 3 D 2 S 2 S 2 D 3 D 3 D 2 S 3 D 3 D 2 D 1 D 1 D 3 D 1 D 2 D GL: RESRAD PARA ent c

Value/Distr 0.2 3482 Lognorm 7.2 Unifor Bounded Logn 0.78 NA NA Unifor 1.00E+

1.00E-1.76 0.31 0.28 0.066 3482 0.004 6-61 METERS FOR UNCE ribution RES distribu provide 2

313 fe mal-N Site sp NURE NURE rm NURE normal - N NURE 8

NURE L

Ind Ind rm NURE

+06 R

-03 R 6

8 6

Calcula 2

Sit 313 fe 45 ERTAINTY ANALYSI Basis SRAD default. No ution or median value ed in NURE/CR-6697 Att. C Site specific e

eet/day = 34822 m/y pecific soil type sand EG/CR-6697 Att. C Table 3.5-1 Median EG/CR-6697 Att. C EG/CR-6697 Att. C Figure 4.3-1 EG/CR-6697 Att. C Figure 4.5-1 EG/CR-6697 Att. C La Crosse, WI Table 4.1-2 dustrial Scenario dustrial Scenario EG/CR-6697 Att. C Figure 4.2-1 ESRAD Default ESRAD Default Site-specific e

Site-specific e

Site-specific e

ated values for sand soil type f

te-specific value e

eet/day = 34822 m/y Site-specific e

IS Distribution's 1

2 NR N R

NR N R

-.0253 0.21 1.98 0.33 0.5 0.7 5

1.445 0.24 1

NR N R

NR N R

NR N R

0.1 0.8 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR 6 N A

4 0.001 5 NR 19 1.4 R NR R NR R NR 8 NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NA 0.97 0.999 7.2 NR 0.625 13 4.2 NR NR NR NR 0.45 NR NR NR NR NR NR NR NR

La Cro License Revisio Saturated Water tab Well pum water tab Model: N Balance sse Boiling Wat e Termination P on 0 Parameter (unit) d zone b parameter ble drop rate (m/y) mp intake depth (m be ble) ondispersion (ND) or (MB) ter Reactor Plan Type a

P P

elow P

r Mass-P SOIL DCG Priority b

Treatme 2 S 3 D 2 S 3 D GL: RESRAD PARA ent c

Value/Distr Lognorm 0

Triangu ND 6-62 METERS FOR UNCE ribution mal-N Site spe NUREG Table 3 Assume hydraul Mississ ular Site-spe Existing supply w of 116 ground depth e the wate assume well dep Minimum assume by a no depth (6 the wate Mode is point be 33.1 m Note tha distribut similar t distribut and 30 distribut Applica groundw ERTAINTY ANALYSI Basis ecific soil type sand G/CR-6697 Att. C

.5-1 ed zero due to ic connectivity with ippi river.

ecific distribution g industrial water wells onsite at depth and 129 below surface (the 129 quals 33.1 m below er table). 33.1 m ed to be maximum pth.

m well depth ed to be represented minal 20 screen 6.08 m) starting at er table.

s assumed to be mid-etween 6.08 m and which is 19.6 m.

at the site-specific tion is reasonably to the NUREG-6697 tion values of 6, 10, for the triangular tion.

ble to flowing water IS Distribution's 1

2

-.0253 0.21 NR N R

6.08 19.

6 NR N R

Statistical Paramet 3

6 N A

R NR 6 33.1 R NR ers d

4 Mean/

Median NA 0.97 NR NR 19.6 NR

La Cro License Revisio Well pum Unsatur Number o Unsat. zo Unsat. zo Unsat. zo Unsat. zo Unsat. zo Unsat. zo (m/y)

Unsat. zo paramete sse Boiling Wat e Termination P on 0 Parameter (unit) mping rate (m 3/y) rated Zone Hydro of unsaturated zone s one thickness (m) one soil density (g/cm one total porosity one effective porosity one field capacity one hydraulic conduct one soil-specific b er ter Reactor Plan Type a

P logical Data strata P P

m

3) P P

P P

tivity P

P SOIL DCG Priority b

Treatme 2 S 3 D 1 D 2 D 2 D 2 D 3 D 2 D 2 S GL: RESRAD PARA ent c

Value/Distr Unifor 1

5.1 m 1.76 0.31 0.28 0.066 3482 Lognorm O

6-63 METERS FOR UNCE ribution rm NUREG provide value du Industri rate dep NUREG applies potable four per This val the min Maximu assume workers to1643.

Site-spe m Site Spe 6

Site-spe Site-sp e

8 Site-sp e

6 Calcul a

soil type 2

Site-spe mal-N Site spe NUREG Table 3 Occupancy ERTAINTY ANALYSI Basis G/CR-6697, Att. C s no recommended ue to high variability.

al Scenario pump pends on industry.

G-6697, Table 3.10-1 a sanitary and water usage rate for rsons of 328.7 m 3/yr.

lue is assumed to be imum industrial rate.

um industrial rate ed to supply 20 s which equates 5 m 3/yr.

ecific e

ecific e

ecific e

ecific e

ecific e

ated values for sand e

f ecific e

ecific soil type sand G/CR-6697 Att. C

.5-1 IS Distribution's 1

2 328.7 1643 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

-.0253 0.21 Statistical Paramet 3

.5 NR R NR R NR R NR R NR R NR R NR R NR 6 N A

ers d

4 Mean/

Median NR 986.1 NR NR NR NR NR NR NR NA 0.97

La Cro License Revisio Inhalation Mass loa Exposure Indoor du Shielding Fraction o sse Boiling Wat e Termination P on 0 Parameter (unit) n rate (m 3/y) ading for inhalation (g/

e duration ust filtration factor g factor, external gam of time spent indoors ter Reactor Plan Type a

M,B

/m

3) P,B B

P,B ma P B

SOIL DCG Priority b

Treatme 3 D 2 S 3 D 2 S 2 S 3 D GL: RESRAD PARA ent c

Value/Distr 1917 Continuous 30 Unifor Bounded Log 0.187 6-64 METERS FOR UNCE ribution 7

NUREG Table 5 8400/y w m

3/d Industri

=23 m 3/

s Linear NURE G

RESRA parame dose ca rm NUREG Figure 7 gnormal-N NUREG Table 7 75 NUREG 7.6-1 re median 8.76 ho days a w per yea 2190 ho Majority expecte Consist the Use RESRA of work 25% ou The cor RESRA parame (2190*.7 ERTAINTY ANALYSI Basis G/CR-5512, Vol. 3

.1.1 mean value is which equates to 23 al Scenario m 3/yr

/d ÷ 24h/d

• 2000 h/y)

G/CR-6697, Att. C AD Users Manual eter value not used in alculation G/CR-6697, Att. C 7.1-1 G/CR-6697, Att. C

.10-1 G-6697 Att. C, Table ecommends a indoor work day as ours/day. Assuming 5 week and 50 weeks rs this equates to ours per year.

y of industrial work is ed to be indoors.

tent with Table 2-3 of ers Manual for AD Version 6 g 75%

time is indoors and utdoors.

rresponding AD indoor Fraction eter =

75)/(24*365) =.1875 IS Distribution's 1

2

)

NR N R

See NUREG-6697 Table 4.6-1 See NURE 6697 Ta 4.6-NR N R

0.15 0.9 5

-1.3 0.5 9

5 NR N R

Statistical Paramet 3

R NR e

EG-able 1

See NUREG-6697 Table 4.6-1 N

66 R NR 5 NR 9 0.044 R NR ers d

4 Mean/

Median NR See NUREG-97 Table 4.6-1 2.35E-05 NR NR 0.55 1 0.2725 NR

La Cro License Revisio Fraction o site)

Shape fa Ingestio Fruits, no consump Leafy veg Milk cons Meat and Fish cons Other sea Soil inges Drinking sse Boiling Wat e Termination P on 0 Parameter (unit) of time spent outdoor actor flag, external gam on, Dietary on-leafy vegetables, g ption (kg/y) getable consumption sumption (L/y) d poultry consumption sumption (kg/y) afood consumption (k stion rate (g/y) water intake (L/y) ter Reactor Plan Type a

rs (on B

mma P grain M,B (kg/y) M,B M,B n (kg/y)

M,B M,B kg/y)

M,B M,B M,B SOIL DCG Priority b

Treatme 3 D 3 D 2 D 3 D 2 D 3 D 3 D 3 D 2 D 2 D GL: RESRAD PARA ent c

Value/Distr 0.062 Circul NA NA NA NA NA NA 18.3 327 6-65 METERS FOR UNCE ribution 25 As expl the Indo parame fraction outdoor 25%.

(2190*.2 0.0625 ar Circular assume purpose Industri Industri Industri Industri Industri Industri 3

NUREG Table 6 NUREG Table 6 Industri supply a an onsit 478 L/y 5512 co L/d whic conserv hour wo 1.31 L/d 327 L/y ERTAINTY ANALYSI Basis ained in the basis for oor Fraction eter, the indoor time was set at 75% and r time fraction at 25)/(24*365) =

r contaminated zone ed for modeling es al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario G/CR-5512, Vol. 3

.87 G/CR-5512, Vol. 3

.87 al Scenario water assumed to be from te well.

from NUREG/CR-orresponds to 1.31 ch is considered a vative value for 8 ork day.

d

• 250 work days =

IS Distribution's 1

2 r

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Contamin water Contamin water (if u Contamin water Contamin water Contamin food Contamin Contamin Contamin Ingestio Livestock (kg/day)

Livestock (kg/day)

Livestock (L/day)

Livestock (L/day)

Livestock Mass loa (g/m

3)

Depth of Depth of Drinking water Househo ground w Livestock water Irrigation Wet weig (kg/m

2) sse Boiling Wat e Termination P on 0 Parameter (unit) nation fraction of drink nation fraction of hous used) nation fraction of lives nation fraction of irriga nation fraction of aqua nation fraction of plan nation fraction of mea nation fraction of milk on, Non-Dietary k fodder intake for me k fodder intake for mil k water intake for mea k water intake for milk k soil intake (kg/day) ading for foliar deposit soil mixing layer (m) roots (m) water fraction from gr old water fraction from water (if used) k water fraction from g fraction from ground ght crop yield for Non-ter Reactor Plan Type a

king B,P sehold B,P stock B,P ation B,P atic B,P nt food B,P at B,P B,P eat M

k M

at M

k M

M tion P

P P

round B,P m

B,P ground B,P water B,P

-Leafy P

SOIL DCG Priority b

Treatme 3 D 3

3 D 3 D 2 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 2 S 1 D 3 D 3

3 D 3 D 2 D GL: RESRAD PARA ent c

Value/Distr 1

1 NA NA NA NA NA NA NA NA NA NA NA NA Triangu NA 1

1 NA NA NA 6-66 METERS FOR UNCE ribution All wate contam All wate Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ular NUREG Figure 3 Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis er assumed inated er from well al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario G/CR-6697, Att. C 3.12-1 al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

0 0.1 5

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR 5 0.6 R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR 0.15 NR NR NR NR NR NR

La Cro License Revisio Wet weig (kg/m

2)

Wet weig (kg/m

2)

Growing Growing Growing Transloca Transloca Transloca Weatheri Vegetatio Wet Folia Non-Leaf Wet Folia Leafy Wet Folia Fodder Dry Folia Non-Leaf Dry Folia Leafy Dry Folia Fodder Storage Fruits, no grain Leafy veg Milk Meat and Fish Crustace Well wate Surface w Livestock sse Boiling Wat e Termination P on 0 Parameter (unit) ght crop yield for Leaf ght crop yield for Fodd Season for Non-Leaf Season for Leafy (

Season for Fodder ation Factor for Non-L ation Factor for Leafy ation Factor for Fodde ing Removal Constan on (1/y) ar Interception Fractio fy ar Interception Fractio ar Interception Fractio ar Interception Fractio fy ar Interception Fractio ar Interception Fractio e times of contam on-leafy vegetables, a getables d poultry ea and mollusks er water k fodder ter Reactor Plan Type a

fy P

der P

fy (y)

P (y) P (y) P Leafy P y P er P nt for P

on for P

on for P

on for P

n for P

n for P

n for P

inated foodstuffs and B

B B

B B

B B

B B

SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 2 D 3 D 2 D 3 D 3 D 3 D 3 D (days):

3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-67 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Special C-12 con C-12 con soil (g/g)

Fraction o soil Fraction o air C-14 eva (m)

C-14 eva (1/sec)

C-12 eva (1/sec)

Fraction o Fraction o Dose Co Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Gd-152 H-3 sse Boiling Wat e Termination P on 0 Parameter (unit)

Radionuclides (C ncentration in water (g ncentration in contami of vegetation carbon of vegetation carbon asion layer thickness i asion flux rate from so asion flux rate from so of grain in beef cattle of grain in milk cow fe onversion Factors ter Reactor Plan Type a

C-14) g/cm

3) P inated P

from P

from P

in soil P

oil P

oil P

feed B eed B s (Inhalation mrem/p M

M M

M M

M M

M M

M M

M M

M M

SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 2 D 3 D 3 D 3 D 3 D pCi) 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3

D 3 D 3 D 3 D 3 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA 6.70E+

4.44E-4.40E-2.09E-3.07E-2.48E-4.55E-4.51E-2.19E-4.62E-3.19E-2.21E-2.86E-2.43E-6.40E-6-68 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri

+00 FGR 11

-01 FGR 11

-01 FGR 11

-06 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-04 FGR 11

-05 FGR 11

-05 FGR11

-04 FGR 11

-04 FGR 11

-01 FGR 11

-08 FGR 11 ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio I-129 Nb-94 Nd-144 e

Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sm-148 e

Sr-90 Tc-99 Th-228 Th-229 Th-230 Th232 U-233 U-234 U-235 U-236 U-238 Dose Co Ac-227 sse Boiling Wat e Termination P on 0 Parameter (unit) onversion Factors ter Reactor Plan Type a

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

s (Ingestion mrem/p M

SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D pCi) 3 D GL: RESRAD PARA ent c

Value/Distr 1.74E-4.14E-7.04E-2.70E-6.29E-5.40E-1.28E+

1.36E-9.40E-3.92E-4.29E-4.29E-8.25E-4.11E-8.58E-4.77E-7.34E-1.30E-8.32E-3.42E-2.15E+

3.26E-1.64e+

1.35E-1.32E-1.23E-1.25E-1.18E-1.41E-6-69 METERS FOR UNCE ribution

-04 FGR 11

-04 FGR 11

-02 ICRP6 0

-06 FGR 11

-06 FGR 11

-01 FGR 11

+00 FGR 11

-02 FGR 11

-03 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-03 FGR 11

-01 FGR 11

-03 FGR 11

-03 FGR 11

-02 ICRP6 0

-03 FGR 11

-06 FGR 11

-01 FGR 11

+00 FGR 11

-01 FGR 11

+00 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-01 FGR 11

-02 FGR 11 ERTAINTY ANALYSI Basis 0

0 IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Gd-152 H-3 I-129 Nb-94 Nd-144 e

Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 sse Boiling Wat e Termination P on 0 Parameter (unit) ter Reactor Plan Type a

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D GL: RESRAD PARA ent c

Value/Distr 3.64E-3.62E-2.09E-2.51E-2.02E-3.74E-3.70E-2.69E-7.33E-5.00E-6.48E-9.55E-1.61E-6.40E-2.76E-7.14E-1.51E-2.10E-5.77E-4.44E-1.06E-5.37E-1.90E-3.20E-3.54E-3.54E-6.84E-3.36E-1.32E-1.44E-6-70 METERS FOR UNCE ribution

-03 FGR 11

-03 FGR 11

-06 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11

-05 FGR 11

-05 FGR 11

-05 FGR 11

-06 FGR 11

-06 FGR 11

-04 FGR 11

-08 FGR 11

-04 FGR 11

-06 FGR 11

-04 ICRP6 0

-07 FGR 11

-07 FGR 11

-03 FGR 11

-02 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11

-05 FGR 11

-03 FGR 11

-03 FGR 11

-03 FGR 11 ERTAINTY ANALYSI Basis 0

IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Sm-148 e

Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 U-238 Plant Tr Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 H-3 Nb-94 Nd-144 Ni-59 sse Boiling Wat e Termination P on 0 Parameter (unit) ransfer Factors (p ter Reactor Plan Type a

M M

M M

M M

M M

M M

M M

Ci/g plant)/(pCi/g so P

P P

P P

P P

P P

P P

P P

P P

P P

SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D oil) 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D GL: RESRAD PARA ent c

Value/Distr 1.58E-1.42E-1.46E-3.96E-3.53E-5.48E-2.73E-2.89E-2.83E-2.66E-2.69E-2.55E-NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-71 METERS FOR UNCE ribution

-04 ICRP6 0

-04 FGR 11

-06 FGR 11

-04 FGR 11

-03 FGR 11

-04 FGR 11

-03 FGR 11

-04 FGR 11

-04 FGR 11

-04 FGR 11

-04 FGR 11

-04 FGR 11 Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis 0

al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Ni-63 Np-237 Pa-231 Pb-210 Pm-147 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Ra-226 Ra-228 Sb-125 Sm-148 Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 Meat Tr Ac-227 Ag-108m Am-241 Am-243 C-14 sse Boiling Wat e Termination P on 0 Parameter (unit) ransfer Factors (pC m

ter Reactor Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

Ci/kg)/(pCi/d)

P P

P P

P SOIL DCG Priority b

Treatme 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 2 D 2 D 2 D 2 D 2 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-72 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 H-3 Nb-94 Nd-144 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Ra-226 Ra-228 Sb-125 Sm-148 Sr-90 Tc-99 Th-228 Th-229 sse Boiling Wat e Termination P on 0 Parameter (unit) ter Reactor Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

SOIL DCG Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 1 D 2 D 2 D 2 D 2 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-73 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Th-230 Th-232 U-233 U-234 U-235 U-236 Milk Tra Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 H-3 Nb-94 Nd-144 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 sse Boiling Wat e Termination P on 0 Parameter (unit) ansfer Factors (pC ter Reactor Plan Type a

P P

P P

P P

Ci/L)/(pCi/d)

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P SOIL DCG Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-74 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Pu-239 Pu-240 Pu-241 Ra-226 Ra-228 Sm-148 Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 Bioaccu Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-137 Eu-152 Eu-154 Gd-152 sse Boiling Wat e Termination P on 0 Parameter (unit) umulation Factors ter Reactor Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

s for Fish ((pCi/kg)/

P P

P P

P P

P P

P P

P P

P SOIL DCG Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D

/(pCi/L))

2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-75 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio H-3 I-129 Nb-94 Ni-59 Ni-63 Np-237 Pa-231 Po-210 Pb-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sr-90 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 U-238 Bioaccu Ac-227 Am-241 sse Boiling Wat e Termination P on 0 Parameter (unit) umulation Factors ter Reactor Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

s for Crustacea/ M P

P SOIL DCG Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D Mollusks ((pCi/kg)/(p 3 D 3 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA pCi/L))

NA NA 6-76 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-137 Eu-152 Eu-154 Gd-152 H-3 I-129 Nb-94 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sr-90 Th-228 sse Boiling Wat e Termination P on 0 Parameter (unit) ter Reactor Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D S D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-77 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri Industri ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro License Revisio Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 U-238 Graphic Number o Spacing Time inte Maximum Notes:

a P = phys b 1 = high-c D = deter d Distribut Lognorma Bounded lo Truncated Bounded n Beta: 1 = m Triangular Uniform: 1 e Referenc f ZionSolu g Argonne sse Boiling Wat e Termination P on 0 Parameter (unit) cs Parameters of points egration parameters m number of points fo ical, B = behavioral, M

-priority parameter, 2 =

rministic, S = stochastic tions Statistical Parame l-n: 1= mean, 2 = stand ognormal-n: 1= mean, 2 lognormal-n: 1= mean, normal: 1 = mean, 2 = st minimum, 2 = maximum r: 1 = minimum, 2 = mo 1 = minimum, 2 = maxi ce: Haley and Aldrich, I utions Technical Suppor e National Laboratory, ter Reactor Plan Type a

P P

P P

P P

P P

s r dose M = metabolic; (see NUR

= medium-priority param c

ters:

dard deviation 2 = standard deviation,

, 2 = standard deviation tandard deviation, 3 = m m, 3 = P-value, 4 = Q-v ode, 3 = maximum imum e Sm-148 an ND-Inc., "Hydrogeological I rt Document 14-003, C Users Manual for RES SOIL DCG Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D REG/CR-6697, Attachm meter, 3 = low-priority p 3 = minimum, 4 = max

, 3 = lower quantile, 4 =

minimum, 4 = maximum alue

-144 not listed in RESRA Investigation Report L onestoga Rovers & Ass SRAD Version 6, ANL GL: RESRAD PARA ent c

Value/Distr NA NA NA NA NA NA NA NA 32 log 17 ment B, Table 4.)

parameter (see NUREG imum

= upper quantile m

AD FGR 11 DCF file La Crosse Boiling Water sociates (CRA) Report, L/EAD 4, July 2001 6-78 METERS FOR UNCE ribution Industri Industri Industri Industri Industri Industri Industri Industri RESRA RESRA RESRA G/CR-6697, Attachment r Reactor, Dairyland Po Zion Hydrogeologic In ERTAINTY ANALYSI Basis al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario al Scenario AD Default AD Default AD Default B, Table 4.1) ower Cooperative, Geno nvestigation Report IS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

oa, WI January 2015 Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ers d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR

La Cross License T Revision se Boiling W Termination n 0 RESRAD Water Reactor Plan D Input Par r

ATTA rameters for 6-79 CHMENT r LACBWR 6-2 R BFM Unceertainty Annalysis

La Cro L

R Basic ra Initial pri Distribu Ac-227 (

Pu-239)

Am-241 and Pu-2 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-137 Eu-152 Eu-154 Eu-155 Fe-55 Gd-152 H-3 Nb-94 Nd-144 (

Ni-59 Ni-63 osse Boiling Wa License Termin Revision 0 Parameter (unit) diation dose limit (mre incipal radionuclide (p ution coefficients (daughter of Cm-243 (also daughter of Cm 241)

(daughter for Eu-152 (daughter for Eu-152) ater Reactor ation Plan Type a

em/y) pCi/g) P (contaminated, unsa and P

m-245 P

P P

P P

P P

P P

P P

) P P

P

) P P

P BFM INSIT Priority b

Treatme 3 D 2 D aturated, and saturate 1 D 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 S 1 D 1 S 1 S 1 D 1 S 1 S TUgw: RESRAD PAR ent c

Value/Dist Soil 25 1

ed zones) (cm 3/g) 450 Not Inclu Uncertainty Not Inclu Uncertainty Lognorm Not Inclu Uncertainty Not Included in Analy Lognorm Lognorm Lognorm Lognorm Not Inclu Uncertainty Lognorm 825 Lognorm Not Inclu Uncertainty 158 Lognorm Lognorm 6-80 RAMETERS FOR UNC tribution Concentrations 10 CFR Unit Va 0

Mean K NUREG 3.9-2, S Thibau uded in y Analysis

< 0.1%

mixture uded in y Analysis

< 0.1%

mixture mal-N NUREG uded in y Analysis

< 0.1%

mixture n Uncertainty ysis

< 0.1%

mixture mal-N NUREG mal-N NUREG mal-N NUREG mal-N NUREG uded in y Analysis

< 0.1%

mixture mal-N NUREG 5

Median NUREG (No san Table 3 mal-N NUREG uded in y Analysis

< 0.1%

mixture 8

RESRA Nd not NUREG mal-N NUREG mal-N NUREG CERTAINTY ANALY Basis R 20.1402 alue Kd Value for sand G/CR-6697, Table Sheppard and lt

% of radionuclide e

% of radionuclide e

G/CR-6697 Att. C

% of radionuclide e

% of radionuclide e

G/CR-6697 Att. C G/CR-6697 Att. C G/CR-6697 Att. C G/CR-6697 Att. C

% of radionuclide e

G/CR-6697 Att. C n Value G/CR-6697, Att. C nd value listed in 3.9-2)

G/CR-6697 Att. C

% of radionuclide e

ADv.7.0 Default listed in G/CR-6697 G/CR-6697 Att. C G/CR-6697 Att. C YSIS Distribution's 1

2 NR N R

NR N R

6.72 3.2 NA N A

NA N A

2.4 3.2 NA N A

NA N A

5.46 2.

5 6.1 2.3 6.72 3.2 6.72 3.2 NA N A

5.34 2.6 6.72 3.2

-2.81 0.

5 NA N A

NA N A

6.05 1.4 6.05 1.4 s Statistical Paramet 3

R NR R NR 22 NA A NA A NA 22 NA A NA A NA 53 NA 33 NA 22 NA 22 NA A NA 67 NA 22 NA 5 NA A NA A NA 46 NA 46 NA ters d

4 Mean/

Median NR NR NA 825 NA NA NA NA NA 11 NA NA NA NA NA 235 NA 446 NA 825 NA 825 NA NA NA 209 NA 825 NA 0.06 NA NA NA NA NA 424 NA 424

La Cro L

R Np-237 Cm-245, Pa-231 (

Pu-239)

Pb-210 (

Po-210 (

Pu-238 Pu-239 (

Pu-240 (

Pu-241 Ra-226 (

Ra-228 (

240)

Sm-148 Sr-90 Tc-99 Th-228 (

240)

Th-229 (

Np-237, Th-230 (

238)

Th-232 (

240)

U-233 (d Np-237, osse Boiling Wa License Termin Revision 0 Parameter (unit)

(also daughter for Am

, and Pu-241)

(daughter for Cm-243 (daughter for Pu-238)

(daughter Pu-238)

(also daughter for Cm (also daughter for Cm (daughter Pu-238)

(daughter Cm-244 an (daughter Eu-152)

(daughter Cm-244 an (daughter Am-241, Cm and Pu-241)

(daughter Cm-246 an (daughter Cm-244 an daughter Am-241, Cm and Pu-241) ater Reactor ation Plan Type a

m-241, P

3 and P

) P P

P m-243)

P m-244)

P P

P nd Pu-P P

P P

d Pu-P m-245, P

d Pu-P d Pu-P m-245, P

BFM INSIT Priority b

Treatme 1 S 1 D 1 D 1 D 1 S 1 S 1 S 1 S 1 D 1 D 1 D 1 S 1 S 1 D 1 D 1 D 1 D 1 D TUgw: RESRAD PAR ent c

Value/Dist Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty Lognorm Not Inclu Uncertainty Not Inclu Uncertainty 245 Lognorm Not Inclu Uncertainty Not Inclu Uncertainty 320 Not Inclu Uncertainty Not Inclu Uncertainty 35 6-81 RAMETERS FOR UNC tribution uded in y Analysis

< 0.1%

mixture uded in y Analysis parent radionu uded in y Analysis parent radionu uded in y Analysis parent radionu uded in y Analysis

< 0.1%

mixture uded in y Analysis

< 0.1%

mixture uded in y Analysis

< 0.1%

mixture mal-N NUREG uded in y Analysis parent radionu uded in y Analysis parent radionu 5

Mean K NUREG 3.9-2, S Thibau mal-N NUREG uded in y Analysis

< 0.1%

mixture uded in y Analysis parent radionu 0

Mean K NUREG 3.9-2, S Thibau uded in y Analysis parent radionu uded in y Analysis parent radionu Mean K NUREG 3.9-2, S Thibau CERTAINTY ANALY Basis

% of radionuclide e

< 0.1% of uclide mixture

< 0.1% of uclide mixture

< 0.1% of uclide mixture

% of radionuclide e

% of radionuclide e

% of radionuclide e

G/CR-6697 Att. C

< 0.1% of uclide mixture

< 0.1% of uclide mixture Kd Value for sand G/CR-6697, Table Sheppard and lt G/CR-6697 Att. C

% of radionuclide e

< 0.1% of uclide mixture Kd Value for sand G/CR-6697, Table Sheppard and lt

< 0.1% of uclide mixture

< 0.1% of uclide mixture Kd Value for sand G/CR-6697, Table Sheppard and lt C YSIS Distribution's 1

2 NA N A

NA N A

NA N A

NA N A

NA N A

NA N A

NA N A

6.86 1.

8 NA N A

NA N A

6.72 3.2 3.45 2.1 NA N A

NA N A

8.68 3.6 NA N A

NA N A

4.84 3.1 s Statistical Paramet 3

A NA A NA A NA A NA A NA A NA A NA 89 NA A NA A NA 22 NA 2 NA A NA A NA 62 NA A NA A NA 3 NA ters d

4 Mean/

Median NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 953 NA NA NA NA NA 825 NA 32 NA NA NA NA NA 5884 NA NA NA NA NA 126

La Cro L

R U-234 (d U-235 (d 239)

U-236 (d 240)

Initial co present Calcula Time sin Time for Contam Area of c Thicknes Length p Contami table osse Boiling Wa License Termin Revision 0 Parameter (unit) daughter Pu-238) daughter Cm-243 and daughter Cm-244 and oncentration of radionu in groundwater (pCi/l ation Times nce placement of mate r calculations (y) minated Zone contaminated zone (m ss of contaminated zo parallel to aquifer flow inated fraction below ater Reactor ation Plan Type a

P d Pu-P d Pu-P uclides

)

P erial (y)

P P

m

2) P one (m)

P w (m)

P water P

BFM INSIT Priority b

Treatme 1 D 1 D 1 D 3 D 3 D 3 D 2 D 2 D 2 D 3 D TUgw: RESRAD PAR ent c

Value/Dist Not Inclu Uncertainty Not Inclu Uncertainty Not Inclu Uncertainty 0

0 0, 1, 3, 10, 30 100 Varia Varia Varia Varia 6-82 RAMETERS FOR UNC tribution uded in y Analysis parent radionu uded in y Analysis parent radionu uded in y Analysis parent radionu No exis contam Start of immed termina 0, 100, 300, 0

RESRA ble Source geome structu BFM In Analys text) ble Source geome structu BFM In Analys text) ble Source geome structu BFM In Analys text) ble Source geome structu BFM In Analys text)

CERTAINTY ANALY Basis

< 0.1% of uclide mixture

< 0.1% of uclide mixture

< 0.1% of uclide mixture sting groundwater mination f dose calculation iately after license ation AD Default e term and physical tries vary for the five res evaluated for nsitugw Uncertainty es (see Table 6-8 in e term and physical tries vary for the five res evaluated for nsitugw Uncertainty es (see Table 6-8 in e term and physical tries vary for the five res evaluated for nsitugw Uncertainty es (see Table 6-8 in e term and physical tries vary for the five res evaluated for nsitugw Uncertainty es (see Table 6-8 in YSIS Distribution's 1

2 NA N A

NA N A

NA N A

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

A NA A NA A NA R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NA NA NA NA NA NA NR NR NR NR NR NR NR

La Cro L

R Cover a Cover de Density o Cover er Density o (g/cm

3)

Contami m/y)

Contami Contami Contami conducti Contami Humidity Evap Averag osse Boiling Wa License Termin Revision 0 Parameter (unit) and Contaminated epth (m) of cover material rosion rate of contaminated zone inated zone erosion ra inated zone total poro inated zone field capa inated zone hydraulic ivity (m/y) inated zone b parame y in air (g/m

3) potranspiration coeffic ge annual wind speed ater Reactor ation Plan Type a

d Zone Hydrologic P

P P,B e

P ate P,B osity P acity P c

P eter P P

cient P d (m/s)

P BFM INSIT Priority b

Treatme cal Data 2 D 2 D 2 S 1 D 2 S 2 D 3 D 2 D 2 S 3 D 2 S 2 S TUgw: RESRAD PAR ent c

Value/Dist Varia 1.76 Continuous L 1.76 Continuous L 0.3 0.2 3482 Lognorm 7.2 0

Bounded Log 6-83 RAMETERS FOR UNC tribution ble Source geome structu BFM In Analys text) 6 Site-s p

Logarithmic NUREG Table 3 6 Site-s p

Logarithmic NUREG Table 3 1 Site-s p

2 RESRA distribu provide Att. C 22 Site-sp 313 fee mal-N Site sp NUREG Table 3 2

Median NUREG Site-s the Pr to eq rate gnormal - N NUR CERTAINTY ANALY Basis e term and physical tries vary for the five res evaluated for nsitugw Uncertainty es (see Table 6-8 in pecific e

G/CR-6697 Att. C 3.8-1 pecific e

G/CR-6697 Att. C 3.8-1 pecific e

AD default. No ution or median value ed in NURE/CR-6697 pecific e

et/day = 34822 m/y pecific soil type sand G/CR-6697 Att. C 3.5-1 n

G/CR-6697 Att. C specific value to force recipitation parameter qual to the infiltration e (see text section 6.11.1.2)

REG/CR-6697 Att. C Figure 4.5-1 YSIS Distribution's 1

2 NR N R

NR N R

5E-08 0.00 NR N R

5E-08 0.00 NR N R

e 7

NR N R

NR N R

-.0253 0.2 1

1.98 0.3 3

r NR N R

1.445 0.24 s Statistical Paramet 3

R NR R NR 07 0.005 R NR 07 0.005 R NR R NR R NR 16 N A

34 0.001 R NR 19 1.4 ters d

4 Mean/

Median NR NR 0.2 0.0015 NR 0.2 0.0015 NR 0.43 NR NR NA 0.97 0.999 7.2 NR NR 13 4.2

La Cro L

R Precipita Irrigation Irrigation Runoff c Watersh or pond Accuracy computa osse Boiling Wa License Termin Revision 0 Parameter (unit) ation (m/y) n (m/y) n mode coefficient hed area for nearby st (m

2) y for water/soil ations ater Reactor ation Plan Type a

P B

B P

tream P

BFM INSIT Priority b

Treatme 2 S 3 D 3 D 2 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist Unifo NA NA 0

1.00E 1.00E 6-84 RAMETERS FOR UNC tribution orm For the Evapot coeffici coeffici to force parame infiltrati This wa incorpo season elevatio with the stage.

Minimu traditio based Evapot coeffici coeffici precipit parame parame DCGL.

The ma is the s ground site as A Indust r

A Indust r

Site-sp the Pre to equa rate. Se

+06 RESR A

E-03 RESR A

CERTAINTY ANALY Basis e BFM analysis the transpiration ient and Runoff ient were set to zero e the Precipitation eter to equal the ion rate.

as necessary to orate the effect of nal ground water on rise associated e Mississippi river um value of 0.25 is nal infiltration rate on transpiration ient, Runoff ient and site tation rate eters listed in the eter set for Soil aximum value of 3.05 seasonal high dwater elevation at the driven by river stage.

rial Scenario rial Scenario pecific value to force ecipitation parameter al to the infiltration ee section 6.11.1.2.

AD Default AD Default YSIS Distribution's 1

2 5

e 0.25 3.0 NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

05 NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR

La Cro L

R Saturat Density o Saturate Saturate Saturate Saturate conducti Saturate Saturate Water ta osse Boiling Wa License Termin Revision 0 Parameter (unit) ted Zone Hydrolog of saturated zone (g/c ed zone total porosity ed zone effective poro ed zone field capacity ed zone hydraulic ivity (m/y) ed zone hydraulic grad ed zone b parameter able drop rate (m/y) ater Reactor ation Plan Type a

gical Data cm

3) P P

osity P P

P dient P P

P BFM INSIT Priority b

Treatme 2 D 1 D 1 D 3 D 1 D 2 D 2 S 3 D TUgw: RESRAD PAR ent c

Value/Dist 1.76 0.3 0.28 0.06 3482 0.004 Lognorm 0

6-85 RAMETERS FOR UNC tribution 6 Site-s p

1 Site-s p

8 Site-s p

66 Calcula soil typ 22 Site-sp 313 fee 45 S ite-sp mal-N Site sp NUREG Table 3 Assum hydrau Mississ CERTAINTY ANALY Basis pecific e

pecific e

pecific e

ated values for sand pe f

pecific e

et/day = 34822 m/y pecific value e

pecific soil type sand G/CR-6697 Att. C 3.5-1 ed zero due to lic connectivity with sippi river.

YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

-.0253 0.2 1

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR 16 N A

R NR ters d

4 Mean/

Median NR NR NR NR NR NR NA 0.97 NR

La Cro L

R Well pum water tab Model: N Balance osse Boiling Wa License Termin Revision 0 Parameter (unit) mp intake depth (m be ble)

Nondispersion (ND) o (MB) ater Reactor ation Plan Type a

elow P

r Mass-P BFM INSIT Priority b

Treatme 2 S 3 D TUgw: RESRAD PAR ent c

Value/Dist Triang ND 6-86 RAMETERS FOR UNC tribution ular Site-sp Existing supply of 116 ground depth e the wat assume well de Minimu assume by nom (6.08 m table.

Mode i 6.08m 19.6 m Note th distribu similar distribu and 30 distribu D Applic a

ground CERTAINTY ANALY Basis pecific distribution g industrial water wells onsite at depth and 129 below d surface (the 129 equals 33.1 m below ter table). 33.1 m ed to be maximum epth.

um well depth ed to be represented minal 20 screen depth m) from top of water s mid-point between and 33.1 m which is hat the site-specific ution is reasonably to the NUREG-6697 ution values of 6, 10, for the triangular ution.

able to moving dwater YSIS Distribution's 1

2 h 6.08 19.

NR N R

s Statistical Paramet 3

6 33.1 R NR ters d

4 Mean/

Median NR 10 NR

La Cro L

R Well pum Unsatu Number Unsat. z Unsat. z Unsat. z Unsat. z Unsat. z Unsat. z (m/y)

Unsat. z paramet Occupa Inhalatio osse Boiling Wa License Termin Revision 0 Parameter (unit) mping rate (m 3/y) urated Zone Hydro of unsaturated zone zone thickness (m) zone soil density (g/cm zone total porosity zone effective porosity zone field capacity zone hydraulic conduc zone soil-specific b ter ancy on rate (m 3/y) ater Reactor ation Plan Type a

P ological Data strata P P

m

3) P P

y P P

ctivity P

P M,B BFM INSIT Priority b

Treatme 2 S 3 D 1 D 2 D 2 D 2 D 3 D 2 D 2 S 3 D TUgw: RESRAD PAR ent c

Value/Dist Unifo 1

Varia 1.76 0.3 0.28 0.06 3482 Lognorm 191 6-87 RAMETERS FOR UNC tribution orm NUREG provide value d Industr rate de Genera for four m

3/yr (N 3.10-1) be min Maximu assume worker 1643.5 Site-sp ble Struct u

6 Site sp 1 Site sp 8 Site sp 66 Calcula soil typ 22 S ite-sp mal-N Site sp NUREG Table 3 7

NUREG Table 5 8400/y m

3/d Industr

=23 m 3

CERTAINTY ANALY Basis G/CR-6697, Att. C es no recommended due to high variability.

rial Scenario pump epends on industry.

al water usage rate r persons is 328.7 NUREG-6697, Table

) which is assumed to imum industrial rate.

um industrial rate ed to supply 20 s which equals m

3/yr.

pecific ure specific pecific e

pecific e

pecific e

ated values for sand pe f

pecific value e

pecific soil type sand G/CR-6697 Att. C 3.5-1 G/CR-5512, Vol. 3 5.1.1 mean value is which equates to 23 rial Scenario m 3/yr 3/d ÷ 24h/d

• 2000 h/y YSIS Distribution's 1

2 o

328.7 164 3

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

-.0253 0.2 1

y)

NR N R

s Statistical Paramet 3

3.5 NR R NR R NR R NR R NR R NR R NR R NR 16 N A

R NR ters d

4 Mean/

Median NR 986.1 NR NR NR NR NR NR NR NA 0.97 NR

La Cro L

R Mass loa Exposur Indoor d Shielding Fraction Fraction site)

Shape fa osse Boiling Wa License Termin Revision 0 Parameter (unit) ading for inhalation (g re duration ust filtration factor g factor, external gam of time spent indoors of time spent outdoo actor flag, external ga ater Reactor ation Plan Type a

g/m

3) P,B B

P,B mma P s B ors (on B

amma P BFM INSIT Priority b

Treatme 2 S 3 D 2 S 2 S 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist Continuou 30 Unifo Bounded Log 0.187 0.062 Circu 6-88 RAMETERS FOR UNC tribution s Linear NURE G

RESRA parame dose ca orm NUREG Figure gnormal-N NUREG Table 7 75 NUREG 7.6-1 re median 8.76 ho days a per yea 2190 h Majorit expecte Consis the Us RESRA of work 25% ou The co RESRA parame (2190*

25 As exp the Ind parame fraction outdoo 25%.

(2190*

0.0625 ular Circula assume purpos CERTAINTY ANALY Basis G/CR-6697, Att. C AD Users Manual eter value not used in alculation G/CR-6697, Att. C 7.1-1 G/CR-6697, Att. C 7.10-1 G-6697 Att. C, Table ecommends a n indoor work day as ours/day. Assuming 5 week and 50 weeks ars this equates to ours per year.

y of industrial work is ed to be indoors.

stent with Table 2-3 of sers Manual for AD Version 6 g 75%

k time is indoors and utdoors.

orresponding AD indoor Fraction eter =

.75)/(24*365) =.1875 lained in the basis for oor Fraction eter, the indoor time n was set at 75% and or time fraction at

.25)/(24*365) =

ar contaminated zone ed for modeling es YSIS Distribution's 1

2 See NUREG-6697 Table 4.6-1 See NURE 6697 T 4.6-n NR NR 0.15 0.

9

-1.3 0.

5 5

s f

5 NR N R

r d

NR N R

NR N R

s Statistical Paramet 3

e EG-Table

-1 See NUREG-6697 Table 4.6-1 N

66 R NR 95 NR 59 0.044 R NR R NR R NR ters d

4 Mean/

Median See NUREG-697 Table 4.6-1 2.35E-05 NR NR 0.55 1

0.2725 NR NR NR 5

La Cro L

R Ingesti Fruits, no consump Leafy ve Milk con Meat and Fish con Other se Soil inge Drinking Contami water Contami water (if Contami water Contami water Contami food Contami Contami osse Boiling Wa License Termin Revision 0 Parameter (unit) on, Dietary on-leafy vegetables, g ption (kg/y) egetable consumption sumption (L/y) d poultry consumptio nsumption (kg/y) eafood consumption (

estion rate (g/y) water intake (L/y) ination fraction of drin ination fraction of hou used) ination fraction of live ination fraction of irrig ination fraction of aqu ination fraction of plan ination fraction of mea ater Reactor ation Plan Type a

grain M,B n (kg/y)

M,B M,B n (kg/y)

M,B M,B kg/y)

M,B M,B M,B nking B,P usehold B,P stock B,P gation B,P uatic B,P nt food B,P at B,P BFM INSIT Priority b

Treatme 2 D 3 D 2 D 3 D 3 D 3 D 2 D 2 D 3 D 3

3 D 3 D 2 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA 18.3 327 1

1 NA NA NA NA NA 6-89 RAMETERS FOR UNC tribution A Indust r

A Industr A

Industr A

Industr A

Industr A

Industr 3

NUREG Table 6 7

NUREG Table 6 Industr supply an ons 478 L/y 5512 c L/d whi conserv hour w 1.31 L/

327 L/y All wate contam All wate A

Industr A

Industr A

Industr A

Industr A

Industr CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario G/CR-5512, Vol. 3 6.87 G/CR-5512, Vol. 3 6.87 rial Scenario water assumed to be from ite well.

y from NUREG/CR-orresponds to 1.31 ich is considered a rvative value for 8 ork day.

/d

• 250 work days =

y er assumed minated er from well rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Contami Ingesti Livestoc (kg/day)

Livestoc (kg/day)

Livestoc (L/day)

Livestoc (L/day)

Livestoc Mass loa (g/m

3)

Depth of Depth of Drinking water Househo ground w Livestoc water Irrigation Wet weig (kg/m

2)

Wet weig (kg/m

2)

Wet weig (kg/m

2)

Growing Growing Growing Transloc Transloc Transloc Weather Vegetati osse Boiling Wa License Termin Revision 0 Parameter (unit) ination fraction of milk on, Non-Dietary ck fodder intake for me ck fodder intake for mi ck water intake for me ck water intake for mil ck soil intake (kg/day) ading for foliar deposi f soil mixing layer (m) f roots (m) water fraction from g old water fraction from water (if used) ck water fraction from n fraction from ground ght crop yield for Non ght crop yield for Lea ght crop yield for Fod g Season for Non-Lea g Season for Leafy g Season for Fodder cation Factor for Non-cation Factor for Leafy cation Factor for Fodd ring Removal Constan on (1/y) ater Reactor ation Plan Type a

k B,P eat M

ilk M

eat M

k M

M ition P

) P P

ground B,P m

B,P ground B,P d water B,P n-Leafy P

fy P

der P

afy (y)

P (y) P (y)

P

-Leafy P y P der P nt for P

BFM INSIT Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 2 D 1 D 3 D 3

3 D 3 D 2 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 2 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA Triang NA 1

1 NA NA NA NA NA NA NA NA NA NA NA NA 6-90 RAMETERS FOR UNC tribution A

Industr A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

ular NUREG Figure A Indust r

Industr Industr A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario G/CR-6697, Att. C 3.12-1 rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

0 0.1 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR 5 0.6 R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR 0.15 NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Wet Foli Non-Lea Wet Foli Leafy Wet Foli Fodder Dry Folia Non-Lea Dry Folia Leafy Dry Folia Fodder Storage Fruits, no grain Leafy ve Milk Meat and Fish Crustace Well wat Surface Livestoc Specia C-12 con C-12 con soil (g/g)

Fraction soil Fraction air C-14 eva (m)

C-14 eva (1/sec)

C-12 eva (1/sec) osse Boiling Wa License Termin Revision 0 Parameter (unit) ar Interception Fractio afy ar Interception Fractio ar Interception Fractio ar Interception Fractio afy ar Interception Fractio ar Interception Fractio e times of contam on-leafy vegetables, a egetables d poultry ea and mollusks ter water ck fodder l Radionuclides (C ncentration in water (g ncentration in contam

)

of vegetation carbon of vegetation carbon asion layer thickness asion flux rate from so asion flux rate from so ater Reactor ation Plan Type a

on for P

on for P

on for P

on for P

on for P

on for P

minated foodstuffs and B

B B

B B

B B

B B

C-14) g/cm

3) P minated P

from P

from P

in soil P

oil P

oil P

BFM INSIT Priority b

Treatme 3 D 2 D 3 D 3 D 3 D 3 D s (days):

3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 2 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-91 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Fraction Fraction Dose C Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Eu-155 Gd-152 H-3 I-129 Nb-94 Nd-144 e

Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 osse Boiling Wa License Termin Revision 0 Parameter (unit) of grain in beef cattle of grain in milk cow f Conversion Factor ater Reactor ation Plan Type a

e feed B

feed B rs (Inhalation mrem/

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

BFM INSIT Priority b

Treatme 3 D 3 D

/pCi) 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3

D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist NA NA 6.70E 4.44E 4.40E 2.09E 3.07E 2.48E 4.55E 4.51E 2.19E 4.62E 3.19E 2.21E 2.86E 4.14E 2.43E 6.40E 1.74E 4.14E 7.04E 2.70E 6.29E 5.40E 1.28E 1.36E 9.40E 3.92E 6-92 RAMETERS FOR UNC tribution A Indust r

A Indust r

+00 FGR 11 E-01 FGR 11 E-01 FGR 11 E-06 FGR 11 E-01 FGR 11 E-01 FGR 11 E-01 FGR 11 E-01 FGR 11 E-04 FGR 11 E-05 FGR 11 E-05 FGR11 E-04 FGR 11 E-04 FGR 11 E-05 FGR 11 E-01 FGR 11 E-08 FGR 11 E-04 FGR 11 E-04 FGR 11 E-02 ICRP6 0

E-06 FGR 11 E-06 FGR 11 E-01 FGR 11

+00 FGR 11 E-02 FGR 11 E-03 FGR 11 E-01 FGR 11 CERTAINTY ANALY Basis rial Scenario rial Scenario 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 0

1 1

1 1

1 1

1 YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sm-148 e

Sr-90 Tc-99 Th-228 Th-229 Th-230 Th232 U-233 U-234 U-235 U-236 U-238 Dose C Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-134 Cs-137 osse Boiling Wa License Termin Revision 0 Parameter (unit) e Conversion Factor ater Reactor ation Plan Type a

M M

M M

M M

M M

M M

M M

M M

M M

M M

rs (Ingestion mrem/p M

M M

M M

M M

M M

M M

BFM INSIT Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D pCi) 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist 4.29E 4.29E 8.25E 4.11E 8.58E 4.77E 7.34E 1.30E 8.32E 3.42E 2.15E 3.26E 1.64e+

1.35E 1.32E 1.23E 1.25E 1.18E 1.41E 3.64E 3.62E 2.09E 2.51E 2.02E 3.74E 3.70E 2.69E 7.33E 5.00E 6-93 RAMETERS FOR UNC tribution E-01 FGR 11 E-01 FGR 11 E-03 FGR 11 E-01 FGR 11 E-03 FGR 11 E-03 FGR 11 E-02 ICRP6 0

E-03 FGR 11 E-06 FGR 11 E-01 FGR 11

+00 FGR 11 E-01 FGR 11

+00 FGR 11 E-01 FGR 11 E-01 FGR 11 E-01 FGR 11 E-01 FGR 11 E-01 FGR 11 E-02 FGR 11 E-03 FGR 11 E-03 FGR 11 E-06 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-05 FGR 11 E-05 FGR 11 E-05 FGR 11 CERTAINTY ANALY Basis 1

1 1

1 1

1 0

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Eu-152 Eu-154 Eu-155 Gd-152 H-3 I-129 Nb-94 Nd-144 e

Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sm-148 e

Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 osse Boiling Wa License Termin Revision 0 Parameter (unit) e ater Reactor ation Plan Type a

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

BFM INSIT Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist 6.48E 9.55E 1.53E 1.61E 6.40E 2.76E 7.14E 1.51E 2.10E 5.77E 4.44E 1.06E 5.37E 1.90E 3.20E 3.54E 3.54E 6.84E 3.36E 1.32E 1.44E 1.58E 1.42E 1.46E 3.96E 3.53E 5.48E 2.73E 2.89E 2.83E 6-94 RAMETERS FOR UNC tribution E-06 FGR 11 E-06 FGR 11 E-06 FGR 11 E-04 FGR 11 E-08 FGR 11 E-04 FGR 11 E-06 FGR 11 E-04 ICRP6 0

E-07 FGR 11 E-07 FGR 11 E-03 FGR 11 E-02 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-05 FGR 11 E-03 FGR 11 E-03 FGR 11 E-03 FGR 11 E-04 ICRP6 0

E-04 FGR 11 E-06 FGR 11 E-04 FGR 11 E-03 FGR 11 E-04 FGR 11 E-03 FGR 11 E-04 FGR 11 E-04 FGR 11 CERTAINTY ANALY Basis 1

1 1

1 1

1 1

0 1

1 1

1 1

1 1

1 1

1 1

1 1

0 1

1 1

1 1

1 1

1 YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R U-235 U-236 U-238 Plant T Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 H-3 Nb-94 Nd-144 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Pm-147 Po-210 Pu-238 Pu-239 Pu-240 osse Boiling Wa License Termin Revision 0 Parameter (unit)

Transfer Factors (p ater Reactor ation Plan Type a

M M

M pCi/g plant)/(pCi/g so P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P BFM INSIT Priority b

Treatme 3 D 3 D 3 D oil) 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D TUgw: RESRAD PAR ent c

Value/Dist 2.66E 2.69E 2.55E NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-95 RAMETERS FOR UNC tribution E-04 FGR 11 E-04 FGR 11 E-04 FGR 11 A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis 1

1 1

rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Pu-241 Ra-226 Ra-228 Sb-125 Sm-148 Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 Meat Tr Ac-227 Ag-108m Am-241 Am-243 C-14 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 osse Boiling Wa License Termin Revision 0 Parameter (unit) ransfer Factors (p m

ater Reactor ation Plan Type a

P P

P P

P P

P P

P P

P P

P P

P pCi/kg)/(pCi/d)

P P

P P

P P

P P

P P

P P

P P

BFM INSIT Priority b

Treatme 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 1 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-96 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R H-3 Nb-94 Nd-144 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Ra-226 Ra-228 Sb-125 Sm-148 Sr-90 Tc-99 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 Milk Tr Ac-227 Am-241 Am-243 osse Boiling Wa License Termin Revision 0 Parameter (unit) ransfer Factors (pC ater Reactor ation Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P Ci/L)/(pCi/d)

P P

P BFM INSIT Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 1 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-97 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R C-14 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Eu-152 Eu-154 Fe-55 Gd-152 H-3 Nb-94 Nd-144 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Ra-226 Ra-228 Sm-148 Sr-90 Tc-99 Th-228 Th-229 osse Boiling Wa License Termin Revision 0 Parameter (unit) ater Reactor ation Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

BFM INSIT Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-98 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Th-230 Th-232 U-233 U-234 U-235 U-236 Bioacc Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-137 Eu-152 Eu-154 Gd-152 H-3 I-129 Nb-94 Ni-59 Ni-63 Np-237 Pa-231 Po-210 Pb-210 Pu-238 osse Boiling Wa License Termin Revision 0 Parameter (unit) cumulation Factors ater Reactor ation Plan Type a

P P

P P

P P

s for Fish ((pCi/kg)

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P BFM INSIT Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D

/(pCi/L))

2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 6-99 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sr-90 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 U-238 Bioacc Ac-227 Am-241 Am-243 C-14 Cm-243 Cm-244 Cm-245 Cm-246 Co-60 Cs-137 Eu-152 Eu-154 Gd-152 osse Boiling Wa License Termin Revision 0 Parameter (unit) cumulation Factors ater Reactor ation Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

s for Crustacea/ M P

P P

P P

P P

P P

P P

P P

BFM INSIT Priority b

Treatme 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D 2 D Mollusks ((pCi/kg)/(

3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA pCi/L))

NA NA NA NA NA NA NA NA NA NA NA NA NA 6-100 RAMETERS FOR UNC tribution A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Indust r

A Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R H-3 I-129 Nb-94 Ni-59 Ni-63 Np-237 Pa-231 Pb-210 Po-210 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Ra-228 Sr-90 Th-228 Th-229 Th-230 Th-232 U-233 U-234 U-235 U-236 U-238 Graphi Number Spacing Time int osse Boiling Wa License Termin Revision 0 Parameter (unit) cs Parameters of points tegration parameter ater Reactor ation Plan Type a

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

P P

s BFM INSIT Priority b

Treatme 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D S D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D 3 D TUgw: RESRAD PAR ent c

Value/Dist NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 32 log 6-101 RAMETERS FOR UNC tribution A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr A

Industr RESR A

g RESR A

CERTAINTY ANALY Basis rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario rial Scenario AD Default AD Default YSIS Distribution's 1

2 NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

NR N R

s Statistical Paramet 3

R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR R NR ters d

4 Mean/

Median NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR NR

La Cro L

R Maximum N

a b

c d

L B

T B

B T

U e

f g

osse Boiling Wa License Termin Revision 0 Parameter (unit) m number of points fo Notes:

a P = physical, B = beha b 1 = high-priority param c D = deterministic, S =

d Distributions Statistica Lognormal-n: 1= mean, Bounded lognormal-n: 1 Truncated lognormal-n:

Bounded normal: 1 = m Beta: 1 = minimum, 2 =

Triangular: 1 = minimum Uniform: 1 = minimum, e

Reference:

Haley and f ZionSolutions Technic g Argonne National Lab ater Reactor ation Plan Type a

or dose avioral, M = metabolic; meter, 2 = medium-prio

= stochastic al Parameters:

2 = standard deviation 1= mean, 2 = standard d 1= mean, 2 = standard mean, 2 = standard devia

= maximum, 3 = P-value m, 2 = mode, 3 = maxim

, 2 = maximum e Sm-14 Aldrich, Inc., "Hydroge cal Support Document boratory, Users Manu BFM INSIT Priority b

Treatme (see NUREG/CR-6697 ority parameter, 3 = low deviation, 3 = minimum deviation, 3 = lower qu ation, 3 = minimum, 4 =

e, 4 = Q-value mum 48 an ND-144 not listed eological Investigation 14-003, Conestoga Rov ual for RESRAD Versio TUgw: RESRAD PAR ent c

Value/Dist 17 7, Attachment B, Table w-priority parameter (see m, 4 = maximum uantile, 4 = upper quant

= maximum d in RESRAD FGR 11 D Report La Crosse Boil vers & Associates (CRA n 6, ANL/EAD 4, July 6-102 RAMETERS FOR UNC tribution RESR A

4.)

e NUREG/CR-6697, At tile DCF file ling Water Reactor, Da A) Report, Zion Hydrog y 2001 CERTAINTY ANALY Basis AD Default ttachment B, Table 4.1) iryland Power Coopera geologic Investigation R YSIS Distribution's 1

2 NR N R

)

ative, Genoa, WI Janua Report s Statistical Paramet 3

R NR ary 2015 ters d

4 Mean/

Median NR

La Cross License T Revision Dose se Boiling W Termination n 0 e Contribut Aggreg Water Reactor Plant tion Percent gate Dose P r

ATTA tage for Init Percentage f 6-103 CHMENT tial Suite Ra from Insigni 6-3 adionuclide ificant Dose es and Deter e Contribut rmination o ors f

La Cros License Revision H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 Insignifican contributor d percentage b on mixture Insignifican contributor d percentage b on actual da Insignifican contributor d based on act data (mrem/

se Boiling Wate Termination Pl n 0 So mrem/yr 3.30E-09 2.41E-09 7.21E-09 9.98E-09 2.38E-02 2.12E-07 3.45E-05 1.02E-04 1.86E-06 3.77E-01 8.21E-04 7.61E-04 1.01E-05 2.14E-06 2.18E-06 2.07E-06 8.29E-06 5.21E-06 4*

4.11E-06 nt dose based nt dose based ata 2.60E-02 nt dose tual

/yr) er Reactor lant oil DCGLs Dose Fraction 0.000%

0.000%

0.000%

0.000%

5.911%

0.000%

0.009%

0.025%

0.000%

93.653%

0.204%

0.189%

0.003%

0.001%

0.001%

0.001%

0.002%

0.001%

0.001%

0.427%

0.0004%

Table 20 Rx Bldg Grou mrem/yr 3.14E-06 6.66E-05 6.96E-06 2.59E-06 5.79E-03 5.47E-05 4.45E-02 5.26E-06 1.54E-05 1.50E-01 1.06E-05 1.29E-05 1.14E-06 4.63E-04 4.77E-04 2.10E-04 7.07E-04 7.58E-05 2.26E-05 1.25E+01 0 from Referen undwater Dose Fraction m

0.002%

5 0.033%

8 0.003%

7 0.001%

1 2.858%

1 0.027%

2 21.993%

1 0.003%

6 0.008%

4 74.095%

2 0.005%

5 0.006%

4 0.001%

9 0.229%

1 0.235%

1 0.104%

5 0.349%

2 0.037%

3 0.011%

2 1.054%

1 0.528%

nce 5 ( TSD RS-Rx Bldg Drilling Spo mrem/yr Dose F 5.05E-12 0.00 8.23E-12 0.00 7.14E-12 0.00 1.43E-11 0.00 1.42E-03 5.37 2.82E-10 0.00 1.86E-06 0.00 6.57E-06 0.02 4.64E-11 0.00 2.48E-02 94.2 5.10E-05 0.19 4.66E-05 0.17 9.11E-07 0.00 1.56E-08 0.00 1.58E-08 0.00 5.05E-08 0.00 2.54E-07 0.00 3.74E-07 0.00 2.80E-07 0.00 0.40 1.63E+00 0.02 6-104

-TD-313196-00 oils Rx Fraction mrem/y 00%

2.61E-0 00%

1.91E-0 00%

5.70E-0 00%

7.89E-0 74%

1.88E-0 00%

1.67E-0 07%

2.72E-0 25%

8.10E-0 00%

1.47E-0 217%

2.98E-0 94%

6.48E-0 77%

6.02E-0 03%

7.97E-0 00%

1.69E-0 00%

1.73E-0 00%

1.64E-0 01%

6.56E-0 01%

4.14E-0 01%

3.25E-0 03%

1.97E+0 26%

01) - Dose Cont Bldg Excavation yr Dose Fraction 09 0.000%

09 0.000%

09 0.000%

09 0.000%

02 5.903%

07 0.000%

05 0.009%

05 0.025%

06 0.000%

01 93.661%

04 0.204%

04 0.189%

06 0.003%

06 0.001%

06 0.001%

06 0.001%

06 0.002%

06 0.001%

06 0.001%

0.427%

01 0.336%

ribution per R WTB Grou n

mrem/yr 1.11E-06 2.85E-05 4.91E-13 4.80E-06 7.91E-04 1.63E-05 2.58E-02 4.22E-06 3.62E-06 3.55E-02 3.31E-09 2.85E-11 4.49E-17 7.38E-05 8.75E-04 8.87E-05 5.09E-04 1.33E-04 9.42E-08 7.87E-01 ROC per Scenar undwater Dose Fraction 0.002%

0.045%

0.000%

0.008%

1.238%

0.026%

40.445%

0.007%

0.006%

55.598%

0.000%

0.000%

0.000%

0.115%

1.369%

0.139%

0.797%

0.208%

0.000%

2.179%

0.086%

rio WTB Drilling Spo mrem/yr Dose 4.96E-11 0.

8.10E-11 0.

7.02E-11 0.

1.41E-10 0.

1.39E-02 5.

2.78E-09 0.

1.83E-05 0.

6.46E-05 0.

4.57E-10 0.

2.44E-01 94 5.03E-04 0.

4.59E-04 0.

8.92E-06 0.

1.53E-07 0.

1.55E-07 0.

4.95E-07 0.

2.50E-06 0.

3.67E-06 0.

2.75E-06 0.

0.

3.19E+00 0.

oils W

e Fraction mrem

.000%

3.45E

.000%

2.52E

.000%

7.52E

.000%

1.05E 376%

2.49E

.000%

2.21E 007%

3.60E

.025%

1.07E

.000%

1.95E

.213%

3.95E+

.194%

8.59E

.177%

7.96E

.003%

1.06E

.000%

2.23E

.000%

2.28E

.000%

2.17E

.001%

8.65E

.001%

5.47E

.001%

4.30E

.404%

5.19E+

.051%

WTB Excavation m/yr Dose Fractio

-08 0.000%

-08 0.000%

-08 0.000%

-07 0.000%

-01 5.908%

-06 0.000%

-04 0.009%

-03 0.025%

-05 0.000%

+00 93.657%

-03 0.204%

-03 0.189%

-04 0.003%

-05 0.001%

-05 0.001%

-05 0.001%

-05 0.002%

-05 0.001%

-05 0.001%

0.427%

+01 0.886%

on

La Cros License Revision se Boiling Wate Termination Pl n 0 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239/240*

Pu-241 Am-241 Am-243 Cm-243/244*

Insignificant contributor dose percentage base on mixture Insignificant contributor dose based on actual data (mrem/yr)

Insignificant contributor dose percentage base on actual data er Reactor lant WGTV G mrem/yr 4.24E-07 9.34E-06 0.00E+00 1.08E-06 1.43E-03 2.06E-06 9.70E-03 9.68E-07 1.81E-06 4.09E-02 7.64E-07 3.59E-07 3.79E-09 1.15E-04 1.99E-04 5.32E-05 2.41E-04 3.12E-05 3.17E-08 e

ed e

l 2.93E+00 e

ed Table 20 fr Groundwater Dose Fraction 0.001%

0.018%

0.000%

0.002%

2.712%

0.004%

18.424%

0.002%

0.003%

77.619%

0.001%

0.001%

0.000%

0.219%

0.378%

0.101%

0.457%

0.059%

0.000%

1.246%

7 0.146%

om Reference 5 WGTV Drilling S mrem/yr Do 2.57E-11 4.19E-11 3.64E-11 7.27E-11 7.21E-03 1.43E-09 9.43E-06 3.34E-05 2.36E-10 1.26E-01 9

2.60E-04 2.38E-04 4.62E-06 7.92E-08 8.02E-08 2.57E-07 1.29E-06 1.90E-06 1.42E-06 7.45E+00 5 (TSD RS-TD Spoils ose Fraction mre 0.000%

1.15 0.000%

8.42 0.000%

2.51 0.000%

3.49 5.380%

8.31 0.000%

7.40 0.007%

1.21 0.025%

3.57 0.000%

6.51 94.210%

1.32 0.194%

2.87 0.177%

2.66 0.003%

3.52 0.000%

7.45 0.000%

7.61 0.000%

7.22 0.001%

2.89 0.001%

1.82 0.001%

1.44 0.403%

7.81E+

0.120%

6-105

-313196-001) (c WGTV Excavation em/yr Dose Frac 5E-08 0.000%

2E-09 0.000%

1E-08 0.000%

9E-08 0.000%

1E-02 5.916%

0E-07 0.000%

1E-04 0.009%

7E-04 0.025%

1E-06 0.000%

E+00 93.648%

7E-03 0.204%

6E-03 0.189%

2E-05 0.003%

5E-06 0.001%

1E-06 0.001%

2E-06 0.001%

9E-05 0.002%

2E-05 0.001%

4E-05 0.001%

0.428%

01 1.336%

cont.) - Dose C Remaini Gro ction mrem/yr 1.09E-06 2.75E-05 1.50E-14 7.57E-07 1.66E-04 2.11E-06 1.05E-02 6.73E-07 3.92E-06 4.51E-03 2.24E-10 1.21E-12 6.84E-19 8.99E-06 1.38E-04 2.07E-05 7.14E-05 2.06E-05 1.24E-07 1.25E+00 ontribution pe ing Basements oundwater Dose Fraction 0.007%

0.177%

0.000%

0.005%

1.072%

0.014%

67.909%

0.004%

0.025%

29.109%

0.000%

0.000%

0.000%

0.058%

0.891%

0.134%

0.461%

0.133%

0.001%

1.910%

0.095%

er ROC per Sce Remaining Baseme Spoils mrem/yr D

5.66E-12 9.21E-12 8.02E-12 1.61E-11 1.59E-03 3.16E-10 2.09E-06 7.37E-06 5.21E-11 2.78E-02 5.73E-05 5.23E-05 1.02E-06 1.75E-08 1.77E-08 5.66E-08 2.85E-07 4.18E-07 3.14E-07 2.38E+00 enario nts Drilling Rema Dose Fraction mr 0.000%

5.7 0.000%

4.2 0.000%

1.2 0.000%

1.7 5.376%

4.1 0.000%

3.7 0.007%

6.0 0.025%

1.7 0.000%

3.2 94.213%

6.6 0.194%

1.4 0.177%

1.3 0.003%

1.7 0.000%

3.7 0.000%

3.8 0.000%

3.6 0.001%

1.4 0.001%

9.1 0.001%

7.1 0.403%

5.69E 0.038%

aining Basements Excav rem/yr Dose Fra 78E-09 0.000 23E-09 0.000 26E-08 0.000 75E-08 0.000 18E-02 5.911 71E-07 0.000 04E-05 0.009 79E-04 0.025 26E-06 0.000 62E-01 93.654 44E-03 0.204 33E-03 0.189 77E-05 0.003 75E-06 0.001 82E-06 0.001 64E-06 0.001 45E-05 0.002 14E-06 0.001 19E-06 0.001 0.427 E+01 0.972 vation action 0%

0%

0%

0%

1%

0%

9%

5%

0%

4%

4%

9%

3%

1%

1%

1%

2%

1%

1%

7%

2%

La Cross License T Revision Table 22 Percent H-3 C-14 Fe-55 Ni-59 Co-6 Ni-63 Sr-90 Nb-9 Tc-99 Cs-13 Eu-15 Eu-15 Eu-15 Pu-23 Pu-239/

Pu-24 Am-24 Am-24 Cm-243 se Boiling W Termination n 0 2 from Refer Using the H W

mr 1.5 4

2.2 5

1.9 9

6.2 0

7.2 3

1.8 0

2.5 4

2.3 9

1.2 37 3.5 52 2.1 54 1.4 55 2.9 38 5.9

/240 7.2 41 5.3 41 4.8 43 7.8

/244 5.4 Dose B Conce (mr 2.3 Water Reactor Plant rence 5 (TS Highest Acti WTB Groundw rem/yr F

9E-07 21E-05 92E-13 28E-06 6E-04 83E-05 59E-02 4

0E-06 28E-06 52E-02 5

9E-09 47E-11 93E-17 98E-05 29E-04 3E-05 87E-04 84E-05 40E-08 Based on entrations Ins Co rem/yr) 6E+00 r

SD RS-TD-3 ivity Cores water Dose Fraction 0.000%

0.035%

0.000%

0.010%

1.147%

0.029%

40.855%

0.004%

0.002%

55.694%

0.000%

0.000%

0.000%

0.095%

1.152%

0.084%

0.769%

0.124%

0.000%

2.304%

significant ontributor Based on Dose D

C 0.218%

6-106 313196-001)

WTB Drill mrem/yr 7.14E-12 6.28E-11 2.74E-11 1.85E-10 1.28E-02 3.11E-09 1.83E-05 3.51E-05 1.61E-10 2.42E-01 3.32E-04 2.37E-04 5.83E-06 1.24E-07 1.29E-07 2.98E-07 2.39E-06 2.17E-06 1.58E-06 Dose Based on Concentrations (mrem/yr) 9.52E+00

- Insignific ling Spoils Dose Fraction 0.000%

0.000%

0.000%

0.000%

5.002%

0.000%

0.007%

0.014%

0.000%

94.749%

0.130%

0.093%

0.002%

0.000%

0.000%

0.000%

0.001%

0.001%

0.001%

0.242%

Insignificant Contributor

% Based on Dose 0.092%

cant Contrib WTB mrem/y 4.95E-0 1.96E-0 2.94E-0 1.37E-0 2.29E-0 2.48E-0 3.60E-0 5.81E-0 6.85E-0 3.92E+0 5.67E-0 4.12E-0 6.90E-0 1.81E-0 1.90E-0 1.30E-0 8.27E-0 3.23E-0 2.46E-0 t

r n

Dose Based Concentrat (mrem/y 1.55E+0 butor Dose B Excavation yr Dos Fract 9

0.000 8

0.000 8

0.000 7

0.000 01 5.499 6

0.000 04 0.009 4

0.014 6

0.000 00 94.236 3

0.137 3

0.099 5

0.002 5

0.000 5

0.000 5

0.000 5

0.002 5

0.001 5

0.001 0.256 d on tions Insignif Contrib

% Base Dos yr) 02 1.587 se ion 0%

0%

0%

0%

9%

0%

9%

4%

0%

6%

7%

9%

2%

0%

0%

0%

2%

1%

1%

6%

ficant butor ed on se 7%

L L

R La Crosse Boilin License Termin Revision 0 Table 2 H-3 C-14 Fe-55 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Cs-137 Eu-152 Eu-154 Eu-155 Pu-238 Pu-239/240 Pu-241 Am-241 Am-243 Cm-243/244 Insignificant Radionuclide Dose Percent ng Water React ation Plant 24 from Refere Buried Pipe Group mrem/yr D

1.52E-13 2.68E-14 4.93E-14 6.83E-14 1.45E-07 1.45E-12 2.27E-10 6.52E-10 1.70E-12 2.44E-06 5.12E-09 4.73E-09 6.84E-11 1.46E-11 1.49E-11 1.01E-11 5.62E-11 3.52E-11 2.78E-11 or ence 5 ( TSD RS p Excavation Dose Fraction 0.000006%

0.000001%

0.000002%

0.000003%

5.588696%

0.000056%

0.008762%

0.025163%

0.000066%

93.988458%

0.197504%

0.182523%

0.002638%

0.000564%

0.000575%

0.000388%

0.002168%

0.001357%

0.001071%

0.414%

S-TD-313196-0 Buried Pipe Gro mrem/yr D

1.51E-12 3.59E-11 0.00E+00 9.23E-13 1.34E-09 1.72E-12 1.55E-08 8.23E-13 6.43E-12 3.42E-08 6.39E-13 3.00E-13 3.17E-15 9.65E-11 1.69E-10 5.95E-11 2.01E-10 2.62E-11 1.57E-13 6-107 001) Buried Pip oup InSitu Dose Fraction 0.002918%

0.069510%

0.000000%

0.001788%

2.592108%

0.003333%

30.046145%

0.001593%

0.012456%

66.198432%

0.001238%

0.000581%

0.000006%

0.186737%

0.327211%

0.115147%

0.389710%

0.050785%

0.000304%

1.163%

ping Dose Contr Circ Water Pipe E mrem/yr D

1.13E-13 2.67E-14 3.78E-14 5.24E-14 1.42E-07 1.11E-12 2.14E-10 6.41E-10 1.26E-12 2.40E-06 9

5.03E-09 4.65E-09 6.75E-11 1.12E-11 1.14E-11 8.31E-12 4.62E-11 3.38E-11 2.66E-11 ribution per R Excavation Dose Fraction 0.000004%

0.000001%

0.000001%

0.000002%

5.580068%

0.000044%

0.008401%

0.025160%

0.000049%

93.998448%

0.197405%

0.182371%

0.002648%

0.000440%

0.000449%

0.000326%

0.001813%

0.001324%

0.001043%

0.413%

ROC per Scenar Circ Water Pip mrem/yr D

4.53E-12 4.28E-11 0.00E+00 0.00E+00 2.48E-10 4.07E-13 1.31E-08 6

8.18E-13 2.06E-11 6.70E-09 3

6.45E-16 5.72E-18 9.61E-24 1.39E-11 1.69E-10 2.77E-11 9.53E-11 2.57E-11 1.58E-13 rio pe InSitu Dose Fraction 0.022182%

0.209552%

0.000000%

0.000000%

1.215574%

0.001991%

64.004473%

0.004008%

0.101008%

32.818795%

0.000003%

0.000000%

0.000000%

0.067971%

0.825476%

0.135521%

0.466862%

0.125811%

0.000774%

1.961%