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# 42 ) 102RQ-RN-5- 4 44 ) 102RQ-RN-5- 6 46 ) 102RQ-RN-5- 8 48 ) 102RQ-RN-5-1 0 50 ) 102RQ-RN-5-1 2 52 ) 102RQ-RN-5-1 4 54 ) 102RQ-RN-5-3 1 56 ) 102RQ-RN-2-5- 1 58 ) 60 ) 62 ) 64 ) 66 ) 68 ) 70 ) 72 ) 74 ) 76 ) 78 ) 80 )

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_ Initials/Date : LD S / 3-8-200 7

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TECHNICA

L BACKGROUN

DDOCUMEN

T T OSUPPOR

T FINA L RULEMAKIN

GPURSUAN

T TOSECTIO

N 10 2 OF THE COMPREHENSIV

E ENVIRONMENTA

L RESPONSE , COMPENSATION , AN DLIABILIT

YACT : RADIONUCLIDE S

A Repor t to th

e
EMERGENC

YRESPONS E DIVISIO

N Offic e o f Emergenc

y an dRemedia l Respons e U.S . Environmenta l Protectio nAgenc y

Februar y 198 9

Prepare dby :
IC F INCORPORATE

Dan d C- E ENVIRONMENTA

L EP A Contrac t 68-03-345 2P. 4

TABLE OF CONTENT S Pag e CHAPTE R1 : BACKGROUN D AN D INTRODUCTIO

N1- 1 1. 1 Backgroun

d o n CERCL

Aan d R Q Notificatio n Requirement s 1- 1 1. 2 RQ Adjustment s fo r Radionuclide s 1- 2 1. 3 The Scop e o f the Radionuclid e Releas e Problem1- 5 1.3. 1 The Affecte d Communit y1- 6 1.3. 2 Radionuclid e Releas e History1- 9 1. 4 Organizatio n o f Thi s Repor t 1-1 0 CHAPTE R2 : OPTIONS FORTH E ADJUSTMEN T O F RADIONUCLID E RQ s 2- 1 2. 1 Optio n 1 : Allowing the Radionuclid e R Q t o Remai n a t One Poun

d 2 -. 1 2. 2 Optio n 2: . Considering Radionuclide s a s a Generi c Clas s o f Substances , Withou t an RQ an d No t Subjec t t o CERCL A Reporting Requirement s 2- 2 2. 3 Optio n 3 : Establishing a Dose-Equivalen t Leve l a s the Radionuclid e R Q 2- 3 2. 4 Optio n 4 : Considering Radionuclide s a s a Clas s Wit ha Singl e Activit yLeve l 2- 4 2. 5 Optio n 5 : Grouping Radionuclide s int o Categorie s Wit h an Activit yLeve l Assigne d t o Eac ho f the Separat e Categorie s 2- 4 2. 6 Optio n 6 : Establishing an Activit yLeve l R Q fo r Individua l Radionuclide s 2- 6 CHAPTE R3" : MAJORISSUE S ASSOCIATE D WIT H TH E SELECTE D RQ

ADJUSMTNE T METHODOLOG Y3- 1 3. 1 Departur e fro

mthe Methodolog

yfo r Adjusting RQ s o f Potentia l Carcinogen s 3- 2 3. 2 Incorporatio n o f Radioactive Decay3- 2 3. 3 Assume d Distanc e Betwee n the Poin t o f Releas e an d Poin t o f Exposur e 3- 3 3. 4 Assume d Configuratio n o f Radionuclid e Releas e 3- 4P. 5

TABLE OF CONTENT S (continued ) Pag e 3. 5 Modeling o f Potentia l Exposure s Throughthe Ingestio n o f Contaminate d Vegetable s 3- 5 3. 6 Additiona l Exposur e Pathwa yModel s 3- 6 CHAPTE R4 : METHODOLOG YFORRQ ADJUSTMENT S 4- 1 4. 1 Overvie wo f the Methodolog y4- 1 4. 2 Releas e Value s fo r the Inhalatio n Pathwa y4- 2 4. 3 Releas e Value s fo r the Ingestio n o f Wate r 4- 5 4. 4 Releas e Value s fo r the Ingestio n o f Foo d 4- 9 4. 5 Releas e Value s fo r the Direc t Exposur e Pathwa y4-1 2 4.5. 1 Direc t Exposur e fro ma Poin t Sourc e 4-1 2 4.5. 2 Submersio n i n a Radioactive Cloud o f Nobl e Ga s 4-1 6 4. 6 Assignment 1 o f Radionuclide s t o R Q Group s 4-1 8 4. 7 Reporting Requirement s fo r Mixture s o f Radionuclide s 4-1 9 4.7. 1 Mixture s o f Know n Compositio n 4-1 9 4.7. 2 Mixture s o f Unknow n Compositio n 4-2 0 4.7. 3 Commo n Radionuclid e Mixture s 4-2 0 4. 8 Reporting Requirement s fo r Compound s an d Mixture s o f Radionuclide s an

d Othe r Hazardou s Substance s 4-2 1 APPENDI XA : Modeling the Airborn e Releas e an d Inhalatio n o f Radionuclide s A- l APPENDI XB : Modeling the Ingestion o f Contaminate d Drinking

Wate r B- l APPENDI XC : Modeling the Ingestion o f Contaminate d Foodstuff s C- l APPENDI XD : Modeling o f Direc t Exposur e t o Radionuclide s D- l APPENDI XE : Releas e Value s an d Fina l RQ s E- lP. 6

CHAPTE R1 BACKGROUN

DAN DINTRODUCTIO

N

Thi s repor t discusse s the option s tha t wer e considere d b ythe U.S . Environmenta l Protectio n Agency(EPA ) fo r adjusting th e one-poun

d statutor

y reportabl e quantity(RQ ) fo r radionuclides , an d present s i n detai l the optio n an d metho d the Agencyha s selected . Thi s chapte r outline s the genera l reporting requirement s unde r section s 103(a ) an

d (b ) o f the Comprehensive Environmenta l Response , Compensation , an d Liabilit yAc t (CERCLA ) an d the specifi c reporting requirement s fo r radionuclides . Sectio n 1. 1 describe s CERCL Areporting requirement s an d the type s o f potentia l respons e activitie s triggere d b yCERCL Areporting ; Sectio n 1. 2 describe s the statutor yauthorityfo r an

d the intended purpos e o f the RQ adjustmen t fo r radionuclides ; Sectio n 1. 3 explain s the scop e o f the radionuclid e releas e problem ; an d Sectio n 1. 4 introduce s the remaining chapter s o f thi s report . 1. 1 BACKGROUN

DO N CERCL A AN DR Q NOTIFICATIO

N REQUIREMENT S CERCLA , a s amende d b ythe Superfun

d Amendment s an

d Reauthorizatio n Ac t o f 198 6 (SARA) , establishe s broa d federa l authorityt o respon d t o release s o r threat s o f release s o f hazardou s substance s fro mvessel s an

d facilities . The Ac t require s immediat e notificatio n t o the Nationa l Respons e Cente r whe na hazardou s substanc e designate d unde r CERCL Ai s release d int o the environmen t i n an amoun t equa l t o o r greate r than the RQ fo r tha t substance . Sectio n 101(14 ) o f CERCL Adefine s a s a CERCL Ahazardou s substanc e an y substanc e designate d under :

o Section s 30 7 an d 31 1 o f the Clean Wate r Act ; o Sectio n 300 1 o f th e Resourc e Conservatio n an d Recover yAct ; o Sectio n 11 2 o f the Clean Ai r Act ; an d
o Sectio n 7 o f the Toxi c Substance s Contro l Act . I n addition , EP

Aha s the authorityunde r sectio n 102(a ) o f CERCL At o designat e additiona l hazardou s substances . Currently , ther e ar e 72 1 CERCL Ahazardou s substances , excluding radionuclides . Radionuclide s ar e hazardou s substance s unde r CERCL

Abecaus e theywer e designate d genericall ya s a hazardou s ai r pollutan t pursuan t t o sectio n 11 2 o f the Clean Ai r Act . Sectio n 102(b ) o f CERCL Aestablishe s a one-poun d RQ fo r radionuclides , bu t sectio n 102(a ) authorize s EP

At o adjus t thi s statutor yRQ b yregulation . RQ adjustment s fo r radionuclide s wer e propose d i n a Notic e o f Propose d Rulemaking o n Marc h16 , 198 7 (5 2 FR8172) . Unde r regulation s implementing the genera l reporting requirement s o f section s 103(a ) an

d (b ) o f CERCLA , a perso n i n charg e o f a vesse l o r facility i s require d t o notif ythe Nationa l Respons e Cente r immediatel ywhe n ther e i s a releas e o f a designate d hazardou s substanc e i n an amoun t tha t equal s o rP. 7

1- 2 exceed s the RQ fo r tha t substanc e (4 0 CF R302.6(a)) . I n addition , SAR A sectio n 30 4 require s facilityowner s o r operator s t o immediatel ynotif ystat e an d loca l official s afte r the releas e o f an RQ o r more . SAR Asection 30 4 notificatio n requirement s appl yonl yt o release s tha t hav e potentia l fo r off

sit e exposur e an

d tha t ar e fro

mfacilitie s tha t produce , use , o r stor e a "hazardou s chemical, " a s define d b yregulation s unde r the Occupationa l Safety an d Healt hAc t o f 197 0 (2 9 CFR1910.1200(c) ) an d sectio n 31 1 o f SARA . Thos e person s require d t o notif ybu t wh o knowingl yfai l t o repor t immediatel ythe releas e o f an R Q ar e subjec t t o crimina l penaltie s unde r CERCL Asectio n 103(b) . Release s tha t ar e federall ypermitted , a s define d b ysectio n 101(10) , ar e exemp t fro

mthe Sectio n 10 3 notificatio n requirements . I t i s importan t t o clarif ytha t the immediat e reporting requirement s o f CERCL Asectio n 10 3 appl yt o release s o f an RQ o r mor e withi n a 24-hour period . Person s wh o frequentl yreleas e a n RQ o r mor e i n 2 4 hour s mayqualif yfo r reduce d reporting . Specifically , sectio n 103(f)(2 ) o f CERCL Aprovide s a reduce d reporting provisio n fo r release s o f an RQ o r mor e tha t ar e "continuous " an

d "stabl e i n quantityan d rate. " Suchrelease s onl ynee d t o be reporte d annuall yan d whe n ther e i s a statisticall ysignifican t increas e i n the quantit yo f the hazardou s substanc e released . Person s who do no t releas e an RQ i n 2 4 hour s do no t hav e t o repor t a t all . The purpos e o f R Q notificatio n i s t o aler t appropriat e governmen t agencie s t o release s o f hazardou s substance s tha t mayrequir e rapi d respons e t o protec t publi c healt ho r welfar e o r the environment . Fo r example , unde r sectio n 10 4 o f CERCLA , the federa l governmen t ma ytake respons e actio n wheneve r ther e i s a releas e o r a substantia l threa t o f a releas e o f a hazardou s substanc e o r o f an ypollutan t o r contaminan t tha t ma ypresen t an imminen t an

d substantia l dange r t o publi c healt ho r welfare . Notificatio n base d o n RQ s serve s t o infor mthe governmen t o f a release , thereb yenabling an evaluatio n o f the situatio n an d a timel yfiel d respons e shoul d one be deemed necessary . Th e releas e o f an RQ doe s no t necessaril ymea n tha t ther e wil l b e a hazard . Similarly , notificatio n doe s no t necessaril ymea n tha t a federa l fiel d respons e wil l occur , no r doe s i t eliminat e liabilityor responsibility fo r respons e cost s o r natura l resourc e damage s associate d wit hth e release . 1. 2 RQ ADJUSTMENT S FO RRADIONUCLIDE S Ther e ar e approximatel y1,50 0 know n radionuclides . Aradionuclid e i s an isotop e wit han unstabl e combinatio n o f proton s an d neutron s i n it s nucleus . Instabilit yi s the resul t o f an imbalanc e i n repulsive an d attractive force s betwee n thes e two type s o f nuclea r particles . T o achieve a mor e stabl e configuration , the nucleu s release s energ yi n the for

mo f particle s o r rays b y a proces s o f decaycalle d radioactivity . Eachradionuclid e decay s b ya specifi c mechanis man d a t a specifi c rat e and , a s a result , a poun d o f tw o differen t radionuclide s coul d represen t significantl ydifferen t type s an d level s o f radioactivity . ^Notificatio n t o the Nationa l Respons e Cente r pursuan t t o CERCL Asectio n 10 3 i s limite d t o release s o f designate d hazardou s substance s i n amount s tha t equa l o r excee d the applicabl e RQ . Release s consisting solel yo f pollutant s o r contaminant s tha t ar e no t designate d a s hazardou s substance s unde r CERCL A nee d no t b e reporte d t o the Nationa l Respons e Center .P. 8

1- 3 Ther e ar e four type s o f emission s fro mradionuclide s durin g th e deca y proces s tha t ma

yhave a significan t impac t o n huma n healt ho r welfar e o r the environment : alpha particles , bet a particles , gamm a rays , an

d neutron s (which ar e als o particles) . The particle s an d ray s diffe r i n thei r mass , charge , energ ycontent , an

d rang e o f penetratio n an d potentia l damag e i n surrounding media . Alpha particle s consis t o f tw o proton s an

d tw o neutron s an

d have a positive charg e o f 2 . Alpha particle s posses s energie s i n th e rang e o f 2 t o 1 2 millio n electro n volt s (MeV) , wit htypica l value s falling betwee n 4 an d 9 MeV . Alpha particle s trave l onl yshor t distance s i n matte r an d ar e highl y disruptive i n tissu e becaus e o f thei r larg e mass , relativel yhighspeed , an d larg e charge . I n general , alpha particle s presen t n o externa l hazard becaus e o f thei r shor t range , bu t do presen t a significan t interna l hazard whe n take n int o the body . Bet a particle s ar e eithe r electron s o r positron s (positivel ycharged electrons) . The energ yrang e o f bet a particle s i s 0.0 2 Me V t o 1 4 MeV , wit h typica l value s falling betwee n 0.0 4 an d 6 MeV . Bet a particle s ar e mor e penetrating (i.e. , hav e a longe r rang e i n matter ) than alpha particles , an d ar e mor e easil yscattere d an d ar e les s disruptive than alpha particles . Bet a particle s ar e primaril yinterna l hazards , althoughcertai n highenerg ybeta , particle s als o ma

ypresen t an externa l hazar d a t relativel yclos e range . Gamm a ray s ar e photon s tha t hav e n o mas s an d no charge , an

d posses s energie s i n the rang e o f 0.0 1 t o 1 0 MeV . Gamm a ray s ar e no t scattere d easily , can b e verypenetrating , an d ar e o f mos t concer n a s potentia l externa l hazards . Neutron s hav e no ne t charg e an d a mas s tha t i s slightl ylarge r than tha t o f a proton . Theyar e emitte d fro ma variet yo f sources , mos t o f whic har e man-mad e (e.g. , mixture s o f certai n radioactive source s an d targe t substances , collision s o f high-spee d particle s i n accelerators , an d fission s i n a nuclea r reactor) . However , neutron s als o mayb e emitte d naturall yfro ma handfu l o f transurani c element s an d uraniu

misotope s tha t underg o spontaneou s fission . Along wit hgamm

a rays , neutron s ar e o f mos t concern a s potentia l externa l hazards . A s note d previously , radionuclide s wer e designate d genericall ya s hazardou s ai r pollutant s unde r sectio n 11 2 o f the Clean Ai r Ac t an d are , therefore' , designate d CERCL Ahazardou s substances . Sectio n 10 2 o f CERCL A establishe s a one-poun d reportabl e quantityfo r radionuclides , a s a generi c clas s o f substances , bu t authorize s EP At o adjus t thi s RQ b yregulation . EP

A recognize s tha t an RQ o f one poun d fo r radionuclide s i s no t an appropriat e leve l i n mos t case s becaus e release s o f les s than one poun d o f a radionuclide maypresen t a substantia l dange r t o publi c healt ho r welfar e o r t o the environment . I n addition , "pound " unit s ar e no t commonl yuse d for measuring quantitie s o f radionuclides . CERCL Ahazardou s substance s othe r than radionuclide s hav e reportabl e quantitie s ranging fro mone poun

d t o 500 0 pounds . Fo r thes e substances , the principa l healt hconcern s ar e chemica l toxicity , ignitability , reactivity , or potentia l carcinogenicity . Thes e criteri a mayb e relate d t o a specifi c numbe r o f pound s o f the hazardou s substanc e released . Radionuclide s ar e veryP. 9

1- 4 differen t fro

mothe r CERCL

Ahazardou s substance s becaus e the principa l healt h hazar d associate d wit hmos t radionuclide s i s the potentia l for cance r cause d b yexposur e t o radioactivity . Althoughthe leve l o f radioactivit yfo r a give n radionuclid e i s directl yproportiona l t o it s mass , equa l masse s o f differen t radionuclide s wil l no t produc e equa l advers e healt han d environmenta l effects . Fo r thi s reason , activitylevel s ar e use d mos t generall ya s indicator s o f radiatio n intensityan d potentia l hazard . The quantit yo f radioactivityi s measure d i n unit s o f curies ^ (Ci ) and , fo r differen t radionuclides , th e sam e numbe r o f pound s translate s int o a differen t numbe r o f curies . Thus , the statutoryone-poun

d RQ translate s int o a wid e rang e o f curie s fo r differen t radionuclides , covering a t leas t twentyorder s o f magnitude . I n additio n t o curies , anothe r widel yuse d uni t fo r measuremen t o f radiatio n hazar d i s the re m(originall yRoentge n Equivalen t Man) . The re mi s a uni t o f measur e fo r radiatio n dose-equivalen t an d i s ofte n expresse d a s som e numbe r o f re

mdelivere d t o a specifi c organ suc ha s the lungs , thyroid , o r whol e body . Wherea s the curi e i s a measur e o f the quantit yo f radiatio n emitted , the dose-equivalen t directl yreflect s the leve l o f tissue damage . Curie s can b e converte d int o re mb yconsidering an exposur e scenari o define d b ysuc hfactor s a s the radionuclid e identity , rout e an d duratio n o f exposure , quantit yo f intake , tissue s mos t affected , typ e o f radiation , an d othe r factor s tha t determin e the hazardou s effect s o f the radiation . Th e nuclea r industr yi n the Unite d State s generall yuse s unit s o f curie s an d re mand , i n fact , mos t existing reporting trigger s fo r radionuclid e release s ar e expresse d i n terms o f one o r the other , o r both , o f thes e tw o units . I n addition , essentiall yal l existing regulation s an d control s establishe d b

yth e Nuclea r RegulatoryCommissio n an d the Departmen t o f Energy , whic hgovern a majo r portio n o f the nuclea r industry , ar e base d on unit s o f curie s o r rem . Therefore , fo r the RQ unde r CERCL At o b e consisten t an d meaningful , an

d t o ensur e tha t the radionuclid e R Q allow s fo r timel yreporting an d timel yfiel d response , i f necessary , the statutor yone-poun

d RQ i s being adjuste d b

yregulation . The RQ adjustment s ar e i n unit s o f curies . Th e Agencyi s adjusting the RQ fo r 75 7 specifi c radionuclide s fo r whic h the Internationa l Commissio n o n Radiologica l Protectio n (ICRP ) ha s provide d metaboli c dat a an

d recommende d intak e limit s i n ICRP Publicatio n 30. 4 Al l radionuclide s no t listed b ythe ICRP ar e groupe d int o a generi c clas s o f "radionuclides, " wit hone RQ fo r the entir e class . Chapter s 3 an d 4 o f thi s repor t discus s the RQ adjustmen t proces s i n mor e detail .

^The curi e i s a measur e o f the rat e o f radioactive decay , wit hon e curi e equa l t o 3. 7 x10- 1

- 0 disintegration s pe r second . J Radiatio n measurement s can als o b e expresse d i n internationa l metri c unit s o f becquerel s o r sieverts ; however , thes e terms ar e les s commo n i n the Unite d States . ^Internationa l Commissio n o n Radiologica l Protection , Annal s o f the ICRP : Limit s fo r Intake s o f Radionuclide s b vWorkers . ICRP Publicatio n 30 , Par t 2 , 1980 .P.1 0

1- 5 The harmfu l effect s o f radiatio n o n human s ha s bee n the focu s o f mos t o f the researc heffort s concerning radiatio n exposur e i n th e past . EPA' s mandat e unde r CERCL

Ais , o f course , concerne d wit hthe broade r problemo f potentiall y deleteriou s effect s t o the environmen t a s wel l a s t o humans . I n adjusting the radionuclid e RQ , the Agency' s goa l i s t o ensure , t o the exten t possible , ampl e protectio n fo r the mos t sensitive specie s o f flor a an d fauna . The Agency reviewe d the existing literatur e an d determine d tha t presen t information indicate s tha t protectio n o f huma n healt hwoul d b e sufficientl yprotective o f the environmen t a s well . Th e Nationa l Academ yo f Scienc e states : The principa l potentia l impac t o f radioactive effluent s o n the biospher e i s the induction o f deleteriou s healt h effect s i n man . Comparabl e level s o f impac t undoubtedl y exis t i n othe r biota , bu t ther e i s n o presen t evidenc e tha t ther e i s an

ybiologica l specie s whos e sensitivityi s sufficientl yhight o warran t a greate r leve l o f protectio n than tha t adequat e fo r man . I n addition , the ICRP ha s state d a s par t o f it s recommende d objective s that :

Althoughthe principa l objective o f radiatio n protectio n i s the achievemen t an d maintenanc e o f appropriatel ysaf e condition s fo r activitie s involving huma n exposure , th e leve l o f safetyrequire d fo r the protectio n o f al l human individual s i s though t likel yt o b e adequat e t o protec t othe r species , althoughno t necessaril yindividua l member s o f thos e species . The Commissio n therefpr e believe s tha t i f ma n i s adequatel yprotecte d the n othe r livin g thing s ar e als o likel yt o b e sufficientl yprotected . The Agencyha s determined , therefore , tha t RQ adjustment s fo r radionuclide s develope d wit hthe goa l o f protecting publi c healt hwil l protec t th e environmen t a s well . 1. 3 THE SCOP E OF THE RADIONUCLIDE RELEAS E PROBLE M Radionuclid e emission s ar e mos t closel yidentifie d wit hth e nuclea r powe r industry , bu t ar e commonl yrelease d fro mothe r activitie s a s well . The

Nationa l Academ

yo f Sciences , The Effect s o n Populatio n o f Exposur e t o LowLevel s o f Ionizin g Radiation . Repor t o f the AdvisoryCommitte e o n the Biologica l Effect s o f Ionizing Radiation , Nationa l Researc hCouncil , Novembe r 1972 , p.11 . "Internationa l Commissio n on Radiologica l Protection , Recommendation s o f the Internationa l Commissio n o n Radiologica l Protectio n (ICRP) . Publicatio n 26 , January1977 , p . 3 .P.1 1

1- 6 Nuclea r RegulatoryCommission , Agreemen t States , an d the Departmen t o f Energ y (DOE ) al l licens e o r overse e a variet yo f industria l facilitie s an d non-industria l operation s tha t emi t radionuclides . I n addition , severa l industria l categorie s no t license d b ythe Commissi6 n o r an Agreemen t Stat e potentiall ycoul d releas e radionuclides . Coal-fire d utilitie s an d industria l boilers , an

d minera l extractio n industrie s sucha s uranium , aluminum , zinc , copper , lead , an

d phosphorou s mining al l releas e certai n amount s o f naturall y occurring radionuclide s during thei r operations . Thi s sectio n summarize s the type s o f facilitie s mos t likel yt o b e affecte d b ythe RQ adjustment s an d review s briefl ythe availabl e dat a o n pas t radionuclid e releases . 1.3. 1 Th

e AffectedCommunit y Th e Nuclea r RegulatoryCommissio n ha s authorit yunde r the Atomi c Energ y Ac t o f 195 4 t o licens e source , byproduct , an d specia l nuclea r materials . Agreemen t State s als o hav e authorit yunde r the Atomi c Energ yAc t t o licens e source , byproduct , an d specia l nuclea r material s a t facilitie s withi n thei r boundaries . A s o f 1984 , ther e wer e approximatel y8,90 0 Commissio n licensee s an d 13,00 0 Agreemen t Stat e licensees . Federa l licensee s ar e subjec t t o the radioactive materia l releas e limit s specifie d i n 1 0 CFRPar t 20 , a s wel l a s othe r control s specifie d b ythe licens e an

d othe r regulations . Agreemen t Stat e licensee s ar e subjec t t o releas e limit s an d reporting requirement s specifie d i n relevan t stat e regulations , whic hgenerall yar e a t leas t a s restrictive a s thos e i n 1 0 CFRPar t 20 . Source , byproduct , an d specia l nuclea r materia l licensee s can b e divide d int o the following si xgenera l categories :

o powe r reactors ; o researchan

d tes t reactors ; o nuclea r fue l cycl e facilitie s (othe r than reactors) ; 'Agreemen t State s ar e state s tha t hav e entere d int o an agreemen t wit hthe Atomi c Energ

yCommissio n o r the Nuclea r RegulatoryCommissio n pursuan t t o sectio n 27 4 o f the Atomi c Energ yAc t o f 1954 , a s amended , unde r whic hthe Commissio n ha s relinquishe d t o suchstate s the majorit yo f it s regulator y authorit yove r source , byproduct , an d specia l nuclea r materia l i n quantitie s no t sufficien t t o for ma critica l mass . Q °Thes e terms ar e define d i n Sectio n 1 1 o f the Atomi c Energ yAct . Sourc e

oo o materia l i s define d a s (1 ) natura l uraniu m(comprise d o f 99.2 7 percen t U " , 0.7 2 percen t U 235 , an d 0.005 7 percen t U 234 ) , natura l thoriu m(Th 232 ) , o r an

y combinatio n thereof ; o r (2 ) ore s tha t contai n 0.0 5 percen t (b yweight ) o f uraniu mo r thorium . Specia l nuclea r materia l i s define d a s plutoniu mo r uraniu menriche d i n the U^ J J o r U^ J J isotop e (i.e. , U" J make s u p mor e than 0.7 2 percen t b

yweight) . Byproduc t materia l i s define d a s (1 ) an ymateria l mad e radioactive b

yexposur e t o radiatio n inciden t t o the proces s o f producing o r utilizing specia l nuclea r material ; o r (2 ) th e waste s produce d b ythe extractio n o r concentratio n o f uraniu mo r thoriu

mfro mor e (e.g. , Uraniu mMil l Tailings) . y U.S . Nuclea r RegulatoryCommission , 198 4 Annua l Report , p . 73 .P.1 2

1- 7

o radiopharmaceutica l industr yan d medica l facilities ; o radiatio n sourc e manufacturers ; an d
o othe r licensees , includin g laboratories , low-leve l wast e disposa l sites , certai n minera l an d meta l processing facilities , an d certai n Departmen t o f Defens e facilities , includin g th e Arme d Force s Radiobiolog

yResearc hInstitut e an d nin e nava l shipyards . Agreemen t State s mayals o licens e and/o r regulat e a fourt hclas s o f radioactive materia l calle d naturall yoccurring o r accelerator-produce d radioactive materia l (NARM) . The States ' authorit yt o contro l NARM , however , i s no t federall yderive d becaus e the onl yauthorit ytha t can b e relinquishe d t o state s b

ythe Nuclea r RegulatoryCommissio n i s the authorityunde r the Atomi c Energ

yAc t t o licens e source , byproduct , an d specia l nuclea r material . On e larg e categor

yo f NAR

Muser s licensed b

yAgreemen t State s i s lowenerg y accelerators . Suchaccelerator s ar e use d fo r a wid e variet yo f applications , including radiography , activatio n analysis , food sterilizatio n an d preservation , radiatio n therapy , an d research . A s o f 1984 , ther e wer e an estimate d 1,50 0 lowenerg yaccelerator s i n us e i n the U.S. , no t includin g accelerator s owne d b yDOE . ° Th e Atomi c Energ

yAc t authorize s DO E "t o protec t th e publi c healt han

d safety " wit hrespec t t o the operatio n o f so-calle d "GOCO " facilitie s - - facilitie s tha t ar e "governmen t owned , contracto r operated. " Thi s authority applie s t o activitie s involving NARM , a s wel l a s activitie s involvin g source , byproduct , an

d specia l nuclea r material . A s o f 1980 , 7 8 GOC O facilitie s i n 2 4 state s wer e subjec t t o DO E healt han d safetyrequirements . Currently , ther e ar e approximatel y4 7 DO E facilitie s tha t activel yus e radionuclides ; som e o f thes e facilities , sucha s the Hanford Installation , actuall yar e comprise d o f numerou s separat e facilitie s tha t carr you t differen t operations . Majo r DO E facilitie s include nationa l laboratories , uraniu menrichmen t faciliites , an d facilitie s associate d with : nuclea r weapon s research , development , an d production ; medica l an d biologica l research ; an d industria l application s an d development . DO E als o i s responsibl e for managing severa l site s tha t ar e no t active bu t contai n radioactive contamination , sucha s site s associate d wit h th e Formerl yUtilize d Site s Remedia l Actio n Progra m(FUSRAP) , th

e Uraniu

mMil l Tailing s Remedia l Actio n Progra m(UMTRAP) , the Gran d Junctio n Remedia l Actio n Progra m(GJRAP) , an

d the Surplu s Facilitie s Managemen t Progra m(SFMP) . Radionuclid e releas e limit s an d reporting requirement s applicabl e t o DO E facilitie s ar e se t fort hi na serie s o f interna l DO E order s issued unde r the authorit yo f the Atomi c Energ yAct .

•"•^U.S . Environmenta l Protectio n Agency , Radionuclide s Backgroun d Informatio n Documen t fo r Fina l Rules . Volume II , Octobe r 1984 , p . 3.2-6 .

• L] -IC Festimate
.P.1 3

1- 8 Ove r 7 0 percen t o f the facilitie s tha t us e material s containing radionuclide s ar e no t license d b ythe Nuclea r RegulatoryCommission , an Agreemen t State , o r b yDOE . Thes e facilitie s ar e discusse d briefl ybelow . Larg e coal-fire d boiler s ar e use d t o generat e electricit yfo r publi c an d industria l us e an

d t o provid e proces s steam , proces s ho t water , an d spac e heat . Mor e than 60 0 millio n ton s o f coa l ar e burne d eac hyea r i n utilit yan d industria l boilers . Coa l contain s minera l matte r including trac e quantitie s o f naturall yoccurring radionuclides . Uranium-23 8 an d thorium-23 2 an

d thei r deca yproduct s ar e foun d i n coal,-'- 2 however , base d o n sampl e result s fo r five utilit yboilers , 3 les s than thre e percen t o f the tota l quantit yo f radionuclide s inpu t fro mcoa l i s usuall yrelease d t o the air . Soli d waste s fro mcoal-fire d boiler s (e.g. , flyash , bottomash , slag , an d scrubbe r sludges ) ar e stockpile d commonl yi n larg e quantitie s on-site , an d thes e waste s maycontai n lowconcentration s o f naturall yoccurring radionuclides . I n earl y1985 , ther e wer e 1,28 1 coal-fire d unit s operating i n the utilit y industry , wit ha tota l generating capacit yo f 28 1 gigawatts . ^ Majo r user s o f coal-fire d industria l boiler s (producing proces s stea man d ho t water , generating electricit yfo r the producers ' ow n use , an

d providing spac e heat ) include the steel , aluminum , chemical , an d pape r industries . Ther e ar e an estimate d 51,18 7 coal-fire d industria l boiler s operating i n the Unite d States . Radionuclid e emissio n level s fro mlarg e utilit yboiler s ar e generall yi n the rang e o f 0.0 1 curie s pe r day ; radionuclid e emissio n level s fro mthe smalle r industria l boiler s ar e generall yi n the rang e o f 0.00 1 curie s pe r day . 5 Almos t al l minera l extractio n industrie s tha t involve the remova l an d processing o f ore s t o recove r meta l releas e som e radionuclides . The Agency ha s identifie d the following minera l extractio n industrie s a s having th e greates t potentia l t o releas e radionuclide s t o the air : the uraniu mmining industry , the aluminu mindustry , th

e coppe r industry , the zin c industry , the lead industry , an

d the phosphat e industry . Thes e industrie s wer e identified becaus e o f th

e larg e quantityo f or e mine d domesticall yan d becaus e th

e mining an d processing operation s conducte d creat e a likelihoo d o f radionuclid e emissions . Excep t for the uraniu mmining industry , individua l radionuclid e emissio n level s t o the ai r ar e generall yi n the rang e o f 0.00 1 curie s t o 0.00000 1 curie s pe r da yfro mthes e facilities ; uraniu mmine s mayemi t mor e
•^U.S . Environmenta l Protectio n Agency , Radionuclide s Backgroun d Informatio n Documen t fo r Fina l Rules . Volume II , Octobe r 1984 , p . 4.0-1 .

13 U.S . Environmenta l Protectio n Agency , Surveyo f Five Utilit yBoiler s fo r Radionuclid e Emissions . Fina l Report . Offic e o f Radiatio n Programs , Washington , D.C. , Decembe r 1983 , p . 3 . •^IC F Energ

yService , Summer/Fal l 198 5 Coa l an d Electri c Utilitie s Marke t Assessment , p . 1- 2 (1985) . •'•-'U.S . Environmenta l Protectio n Agency , Radionuclide s Backgroun d Informatio n Documen t for Fina l Rules . Volume II , Octobe r 1984 , p . 4.1-1 1 an d p . 4.2-7 .P.1 4

1- 9 than 3 0 curie s o f radon pe r day.-*- ° Simila r t o coal-fire d boilers , facilitie s i n thes e industrie s ma ystockpil e larg e quantitie s o f soli d wast e containing generall ylowconcentration s o f naturall yoccurring radionuclides . Ther e ar e numerou s mines , mills , smelters , an d othe r processing plant s i n eacho f thes e industries . 1.3.2 * Radionuclid

e Releas e Histor

y A s par t o f thi s regulator ydevelopmen t process , releas e dat a wer e collecte d fro

mthe majo r federa l agencie s licensing , regulating , an d controlling radionuclid e releases : the Nuclea r RegulatoryCommission , the Departmen t o f Transportation , DOE , an d EPA . The dat a wer e examine d t o understand th

e scop e o f the radionuclid e releas e problem . The following releas e dat a wer e collected :

o Report s maintaine d b ythe Nuclea r Regulatory Commission' s Offic e fo r Analysi s an d Evaluatio n o f Operationa l Dat a (AEOD) , fo r the year s 198 1 throug h 1985 ; o Report s maintaine d b ythe Transportatio n Technolog y Cente r (TTC ) o f Sandi a Nationa l Laborator yi n Albuquerque , Ne wMexico , fo r 197 1 throug h1985 ; o Dat a provide d b ythe Departmen t o f Energy' s Offic e o f Environmen t an

d Health , EmergencyOperation s Cente r (EOC) , fo r Marc h198 3 throug hApri l 1986 ; o Report s t o the Nationa l Respons e Center , fo r 198 2 throug h1985 ; o Report s t o the EPA' s Offic e o f Radiatio n Programs (ORP) , for Octobe r 198 1 throug hSeptembe r 1983 ; an d
o Report s t o th

e Nuclea r RegulatoryCommission' s Operation s Center , fo r January198 3 throug hJanuar

y 1986 . The availabilit yan d qualityo f dat a varie d fro msourc e t o source , bu t duplicatio n amon

g the si xsource s appeare d t o b e relativel ylimited . The AEOD dat a include som e 30 0 report s annually , althoughabou t tw o third s o f th

e report s ar e incident s involving monitoring complianc e o r som e othe r technica l infraction tha t doe s no t involve radionuclid e releases . The TTC dat a include betwee n 1 an d 1 2 report s annuall yo f transportatio n incident s involving radionuclid e releases . Thes e event s alread yar e require d t o b e reporte d t o the Nationa l Respons e Cente r unde r Departmen t o f Transportatio n regulation s (4 9 CFRPart s 171-177) . The Departmen t o f Energ yEOC dat a include 5 2 releas e event s ove r a 3-1/ 2 yea r perio d (between 1 1 an d 2 2 event s annually )

U.S . Environmenta l Protectio n Agency , Radionuclid e Backgroun d Informatio n Documen t fo r Fina l Rules . Volume II , Octobe r 1984 , p . 7.1-8 , 7.2-6 , 7.3-4 , 7.4-4 , 6.1-11 , 5-15 .P.1 5

1-1 0
an d include release s tha t ar e reportabl e unde r DO E Orde r 5484.1 . The Nationa l Respons e Cente r dat a include approximatel y8 0 report s (abou t 3 0 report s annually ) an

d the OR P dat a includ e approximatel y6 0 report s (about 3 0 report s annually) . Th e Nationa l Respons e Cente r dat a include littl e detai l o n the radionuclid e identityan d the quantit yreleased . The OR P dat a reflec t mostl y release s fro

mpowe r reactors . The fina l dat a source , the Nuclea r Regulatory Commissio n Operation s Center , includ e dat a o n 2 6 event s (abou t 8 event s annually) . Althoughthe si xdat a source s includ e a tota l o f abou t 40 0 event s annually , a t leas t 20 0 o f thes e annua l event s ar e no t release s t o the environment . Dat a ar e available , therefore , o n approximatel y20 0 releas e event s annually . Thes e dat a sources , however , do no t cove r release s fro mal l facilitie s tha t handl e an d tha t are , therefore , likel yt o releas e radionuclides . Fo r example , release s fro munlicense d facilitie s an d release s fro mfacilitie s i n Agreemen t State s woul d no t b e expecte d t o b e wel l represente d i n the dat a sets . I n addition , no t al l type s o f radioactive materia l i s wel l represented . On e particula r typ e o f radioactive materia l tha t i s no t wel l represente d i n the dat a set s i s NARM . AlthoughAgreemen t State s an

d DO E contro l NAR

Muse s a t facilitie s unde r thei r jurisdiction , ther e ar e n o unifor

mregulator

yo r reporting requirement s fo r NARM . Virtuall yal l states , bot hagreemen t an d non-agreement , hav e som e typ e o f NAR

Mregulatory

program , ' however , the dat a collecte d unde r thes e program s have no t bee n gathere d a s par t o f thi s analysi s becaus e the ywer e to o diffuse . The availabl e data , therefore , do no t represen t full yNAR Mreleases . 1. 4 ORGANIZATIO

N OF THI S REPORT Thi s repor t discusse s the variou s option s considere d fo r adjusting the one-poun

d R Q fo r radionuclide s an d examine s i n detai l the selected option . The remainde r o f thi s repor t i s organize d a s follows :

Chapte r 2 : Option s fo r the Adjustmen t o f Radionuclid e RO s

-- a reviewo f the regulatoryapproache s considere d an d the one selected ; Chapte r 3 : Majo r Issue s Associate d wit hthe Selecte d RQ Adjustmen t Methodolog y-- a discussio n o f majo r technica l issue s raise d i n comment s o n the propose d RQ rulemaking an d change s mad e t o the adjustmen t methodolog yi n respons e ' t o comments ; Chapte r 4 : Methodolog yfo r RQ Developmen t - - the technica l analysi s an d establishmen t o f RQ values ; Appendi xA : Modeling the Airborn e Releas e an d Inhalatio n o f Radionuclides ;

1 'U.S . Nuclea r RegulatoryCommission , Regulatio n o f Naturall yOccurring an d Accelerator-Produce d Radioactiv e Materials--A n Update . NUREG-0976 , Octobe r 1984 , p . 3 .P.1 6

1-1 1 Appendi xB : Modeling the Ingestio n o f Contaminate d Drinking Water ; Appendi xC : Modeling the Ingestio n o f Contaminate d Foodstuffs ; Appendi xD : Modeling o f Direc t Exposur e t o Radionuclides ; an d Appendi xE : Releas e Value s an d Fina l RQs .P.1 7

CHAPTE R2 OPTIONS FO

RTHE ADJUSTMEN

T O F RADIONUCLID

E RQ s

Severa l option s for adjusting radionuclide RQ s wer e carefull yexamine d during the developmen t o f the fina l regulation . Eac hoptio n presente d certai n advantage s an

d disadvantage s bu t eacho f the rejecte d option s wa s determine d t o b e inferio r t o the selecte d approach . Thi s chapte r discusse s the following regulator

yoption s an

d explain s the Agency' s positio n an d rational e fo r selecting Optio n 6 , the approac huse d t o develop the fina l RQs :

o Optio n 1 : Allowing the radionuclid e R Q t o remai n a t one pound ; o Optio n 2 : Considering radionuclide s a s a generi c clas s o f substances , withou t an R Q an d no t subjec t t o CERCL Areporting requirements ; o Optio n 3 : Establishing a dose-equivalen t leve l a s the radionuclid e RQ ; o Optio n 4 : Considering radionuclide s a s a clas s wit h a singl e activit ylevel ; o Optio n 5 : Grouping radionuclide s int o categorie s wit han activit yleve l assigne d t o eacho f the separat e categories ; an d
o Optio n 6 : Establishing an activityleve l RQ fo r individua l radionuclides . 2. 1 OPTIO

N 1 : ALLOWIN

GTHE RADIONUCLID

E R Q TOREMAIN

AT ON E POUN D Sectio n 102(b ) o f CERCL Aestablishe s th

e RQ fo r radionuclide s a t one pound . Whil e a one-poun d R Q migh t be usefu l t o ensur e reporting o f verylarg e radionuclid e releases , the Agencydoe s no t believe tha t thi s RQ leve l i s appropriat e t o trigge r timel yreporting o r timel yfiel d responses , i f necessary , fo r release s o f man yradionuclide s becaus e release s o f radionuclide s tha t ar e severa l order s o f magnitud e smalle r than one poun d may represen t a seriou s healt han d environmenta l threat . I n addition , a one-poun d RQ doe s no t confor

mt o commonl yaccepted unit s o f measuremen t fo r radionuclides . Mos t radiatio n measurement s i n the Unite d State s ar e i n terms o f curie s o r rem , no t pounds . Aone-poun d RQ leve l would , therefore , diffe r markedl yfro

mreporting requirement s unde r othe r radionuclid e regulation s develope d b

yEP Aan d othe r agencies . Aone-poun

d R Q fo r the entir e clas s o f radionuclide s woul d als o no t tak e int o accoun t the variet yo f hazard s pose d b ydifferen t radionuclides . Becaus e eachradionuclid e ha s a uniqu e specifi c activity(i.e. , a certai n numbe r o f Radiatio n measurement s can als o be expresse d i n internationa l unit s o f becquerel s o r sieverts ; however , thes e terms ar e les s commo n i n th e Unite d States .P.1 8



### 2- 2 curie s fo r one pound) , a singl e one-poun d R Q woul d relat e t o differen t number s o f curie s - - an

d differen t radiatio n level s - - for eachradionuclide . The Agency , therefore , conclude d tha t a one-poun d RQ wa s no t sufficientl y protectiv e o f publi c healt han d welfar e an

d the environment . 2. 2 OPTIO

N 2 : CONSIDERIN

GRADIONUCLIDE S A S A GENERI C CLAS S OF SUBSTANCES , WITHOUT A

N RQ AN DNOT SUBJECT TOCERCL A REPORTIN

GREQUIREMENT S I n the Apri l 4 , 198 5 fina l rul e establishing notificatio n requirement s an d adjusting RQ s fo r certai n hazardou s substance s (5 0 FR13456) , EP Adecide d no t t o establis hRQ s fo r broad generi c classe s o f organi c an d metalli c compound s eve n thoug hthe yar e designate d a s toxi c pollutant s unde r sectio n 307(a ) o f the Clean Wate r Ac t and thu s include d i n CERCLA' s hazardou s substanc e list . The reasoning fo r thi s decision , a s state d i n the preambl e t o tha t rule , was :

Man yo f the generi c classe s o f compound s encompas s hundred s o r eve n thousand s o f specifi c compounds . I t woul d b e virtuall yimpossibl e fo r the Agencyt o develop a reportabl e quantitytha t woul d take int o accoun t the varying characteristic s o f al l the specifi c compound s i n the clas s (5 0 FR13461 ) . Becaus e ther e ar e ove r 1,50 0 known radionuclides , the Agencyconsidere d using a simila r approac hfo r radionuclides ; tha t is , no t establishing an RQ fo r radionuclide s an

d no t requiring radionuclid e release s t o b e reporte d t o the Nationa l Respons e Center . I n considering thi s approach , however , the Agency determine d tha t the sam e technica l argumen t coul d no t b e use d t o suppor t a decisio n no t t o establis han R Q fo r radionuclides . Althoughthe ter m "radionuclides " encompasse s hundred s o f radioactive isotope s an d countles s chemica l compound s involving thes e isotopes , i t is . possibl e t o se t a singl e RQ i n terms o f dose-equivalen t (rem ) fo r the generi c clas s o f radionuclide s an d stil l tak e int o accoun t som e o f the uniqu e characteristic s o f individua l radionuclides . Using a se t o f conservative exposur e assumptions , i t i s als o possibl e t o se t an RQ i n terms o f activitylevel s (curies ) fo r radionuclide s base d o n a predetermine d acceptabl e exposur e level . The argumen t use d fo r th e generi c classe s o f organi c an d metalli c compounds , therefore , i s no t applicabl e entirel yt o radionuclides . The Agenc yals o considere d establishing no RQ fo r radionuclide s base d o n the finding tha t existing reporting mechanism s for radionuclid e release s wer e adequat e an

d tha t an

yadditiona l reporting pursuan t t o CERCL Awoul d provid e no additiona l benefit . Unde r thi s approach , eve n withou t an R Q an d therefor e withou t a requiremen t t o repor t release s o f radionuclide s unde r CERCLA , radionuclide s woul d remai n liste d a s a hazardou s substanc e an d woul d b e subjec t t o CERCL

Arespons e an

d liabilit yprovisions . Eliminatio n o f an R Q fo r radionuclide s woul d rel yo n existing reporting requirement s o f othe r agencies . Thi s approac hwoul d minimiz e duplicatio n o f an d conflict s wit hothe r federa l an d stat e reporting requirements . The Agenc ydetermined , however , tha t thi s optio n woul d no t b e sufficientl yprotective o f publi c healt han d welfar e an

d the environment . Les s than on e third o f facilitie s tha t handl e o r produc e radionuclide s ar eP.1 9

2- 3 license d b

ythe Nuclea r Regulator yCommission , an Agreemen t State , o r the Departmen t o f Energy . The regulatio n o f NAR Mi s fragmented , non-uniform , an d incomplete . Release s o f NAR Mgenerall yar e no t subjec t t o federa l contro l an d licensing , an

d stat e control s ove r NAR Mrang e fro

mcomplet e licensing program s t o initia l registratio n requirements . Release s fro mthes e facilitie s coul d go unreporte d i f no RQ wer e t o b e established . The Agencyconcluded , therefore , tha t i t woul d no t b e fulfilling it s mandat e unde r CERCL Ai f no R Q wa s establishe d fo r radionuclides . 2. 3 OPTIO

N 3 : ESTABLISHIN

GA DOSE-EQUIVALEN

T LEVEL A S THE RADIONUCLID E R Q Adose-equivalen t leve l i s a direc t measuremen t o f the amoun t o f biologica l damag e resulting fro mexposur e t o ionizing radiation . Dose-equivalen t i s measure d i n terms o f re mo r sievert s an

d i s equa l t o the produc t o f the absorbe d dose , i n unit s o f rad s o r grays , an d a qualityfacto r assigne d t o the typ e o f radiatio n being emitted . Dose-equivalent , unlik e activity , i s no t a measur e o f the emitte d radiation , bu t i s a metho d o f normalizing th e effectivenes s o f an absorbe d dos e o f radiation i n damaging tissue , regardles s o f the typ e o f radiation . I t als o mus t be understoo d tha t activit yi s a physica l phenomenon , wherea s dose

equivalen t i s a descriptio n o f the biologica l effectivenes s o f a give n exposur e circumstance . Nevertheless , using standard assumption s regarding suchfactor s a s rout e an d duratio n o f exposure , quantit yo f intake , an d determinatio n o f the tissue s mos t affected , a dose-equivalen t leve l ma yb e relate d directl yt o a leve l o f activityfo r particula r radionuclides . The Agencyconsidere d establishing an RQ fo r radionuclide s i n terms o f dose-equivalen t (rem ) becaus e re mi s an acceptabl e uni t o f measuremen t for radionuclid e release s and , i n fact , mos t existing reporting requirement s ar e i n unit s o f rem . The principa l advantag e t o thi s optio n i s tha t differen t exposur e scenario s (e.g. , differen t radionuclid e forms , route s o f exposure , an d ag e an

d location s o f receptors ) wil l yiel d a differen t numbe r o f rem . Therefore , an RQ i n terms o f a re mleve l tha t i s deeme d t o b e acceptabl e coul d b e independen t o f th e exposur e scenari o --i t woul d appl yt o an yreleas e which , unde r existing circumstance s (whateve r theyma ybe) , coul d resul t i n the specifie d numbe r o f rem . ^U.S. " Nuclea r Regulator yCommission , Regulatio n o f Naturall yOccurring an d Accelerator-Produce d Radioactive Materials--A n Update . NUREG-0976 , Octobe r 1984 , p . 1-3 .

3 Th e gra

yi s a uni t o f absorbe d dose . On e gra yi s equa l t o an absorbe d dos e o f 1 joule/kilogra mo r 10 0 rads . The ra d i s a uni t o f absorbe d dose . One rad i s equa l t o an absorbe d dos e o f 10 0 ergs/gra mo r 0.0 1 joule/kilogram . The siever t i s a uni t o f dose-equivalent . One siever t i s equa l t o a dose

equivalen t o f 10 0 rem . Originall y"Roentgen Equivalen t Man, " the re mi s als o a uni t o f dose-equivalent . The dose-equivalen t i n re mi s numericall yequa l t o the absorbe d dos e i n rad s multiplie d b ythe qualityfacto r (Q) . Q i s equa l t o 1 fo r X-rays , gamm

a rays , an

d bet a particles ; Q i s equa l t o 1 0 fo r fas t neutron s fro m fission , fo r example , an d fo r protons ; an

d Q i s equa l t o 2 0 for alpha particle s an d fissio n fragments .P.2 0

2- 4
Ther e ar e severa l importan t disadvantage s t o thi s option , however . First , an RQ i n terms o f dose-equivalen t (rem ) woul d leave a significan t amoun t o f judgmen t t o the perso n i n charg e o f the facilityo r vessel . Thi s perso n woul d hav e bee n require d t o estimat e o r judg e th e quantit yreleased , the potentia l route s o f exposure , the perio d o f exposure , an d th e mos t vulnerabl e organ o f the bod ypotentiall yaffecte d b ythe release . I n essence , i f the R Q wer e t o b e establishe d i n unit s o f rem , the perso n i n charg e o f the vesse l o r facilitywoul d b e place d i n a positio n o f determining whethe r th e releas e pose d a threa t t o publi c healt ho r welfar e o r the environment . CERCL A establishe s tha t rol e fo r the federa l government , no t fo r the perso n i n charg e o f the vesse l o r facility . I n addition , the calculatio n (or estimation ) o f dose-equivalen t i s no t straightforward . I t coul d preclud e a timel yrepor t and , therefore , a timel y respons e shoul d on e b e deeme d appropriate . Finally , becaus e o f al l the judgment s an

d assumption s require d t o estimat e dose-equivalent , the estimate d dose-equivalen t fo r tw o differen t release s wit hth e sam e leve l o f activityo f th e sam e radionuclid e ma

yvarydrasticall yunde r differen t assumptions . Thi s potentia l variability , eve n wit ha standardize d calculatio n methodology , make s i t difficul t t o (1 ) assur e tha t the governmen t wil l b e notifie d o f al l radionuclid e release s tha t i t deems necessary ; an d (2 ) enforc e an R Q i n dose

equivalen t units . 2. 4 OPTIO

N 4 : CONSIDERIN

GRADIONUCLIDE S A S A CLAS S WITHA

SINGLE ACTIVITY LEVEL Becaus e activit ylevel s ar e relativel yeasy(compared t o the estimatio n o f dose-equivalents ) t o estimat e o r measur e quickl yduring a releas e even t throug hthe us e o f availabl e surveyinstruments , the Agencyconsidere d establishing an R Q fo r radionuclides , a s a generi c class , i n unit s o f curies . Aleve l o f activity , i n unit s o f curie s (or becquerels) , i s a measur e o f th e rat e o f radioactive deca yan d thu s the amoun t o f radiatio n give n of f b ya substance . However , a singl e R Q i n unit s o f curie s applicabl e to al l radionuclide s woul d no t accoun t fo r varying degree s o f hazard pose d b y differen t radionuclides . Exhibi t 2- 1 show s the rang e o f differen t dose-equivalen t level s (reflectin g relative level s o f damag e t o the body ) whic hma

yresul t fro

mthe inhalatio n o f one microcuri e o f differen t radionuclides . Whil e simplicit yi n reporting mus t b e sought , th e Agencydoe s no t believe tha t i t shoul d b e accomplishe d b yignorin

g substantia l difference s among individua l radionuclides . I t woul d b e extremel ydifficul t t o derive an RQ i n terms o f a singl e leve l o f activit ytha t woul d provid e timel yreporting o f the mos t hazardou s radionuclide s whil e no t being overl yprotective fo r others . 2. 5 OPTIO

N 5 : GROUPIN

GRADIONUCLIDE S INT OCATEGORIE S WITHA N ACTIVITYLEVEL ASSIGNEDTOEACHO F THE SEPARATE CATEGORIE S Radionuclide s mayb e segregate d int o variou s group s i n sucha waytha t a singl e leve l o f activit ymaybe an appropriat e RQ fo r al l the radionuclide s withi n a give n group . On e RQ , whic hwoul d assur e timel yreporting fo r release s o f the mos t hazardou s radionuclides , coul d b e assigne d t o eac hgroup . Fo r example , the Agenc yconsidere d grouping radionuclide s int o "half-lif eP.2 1

2- 5

EXHIBI T 2- 1 EFFECTIV

E DOSE-EQUIVALENTS-* / RESULTIN GFRO M THE INHALATIO

N O F ON E MICROCURI E O

F DIFFEREN

T RADIONUCLIDE S

Radionuclid e Effective dose-equivalen t i f one microcuri e i s inhale d (rem)--* /

Tritiu m(H3 ) Technetium-9 9 Radium-22 6 Uranium-23 8 Plutonium-23 8 .000 1 .0 7 8 6 50 0

--/ The effective dose-equivalen t i s a weighte d averag e o f committe d dose

equivalent s fo r specifi c organs . I t provide s a measur e o f the overal l (i.e. , whol e body ) carcinogeni c an d geneti c effect s resulting fro ma radionuclide exposure .

— / The numbe r o f remt o the whol e bod yresulting fro

mthe intak e o f a radionuclid e depend s on , among othe r factors , th e particl e siz e an

d solubility o f th e radionuclid e involved . T o facilitat e compariso n o f the hazard level s associate d wit heacho f the above radionuclides , the dose-equivalen t level s ar e base d o n eac hradionuclid e having roughl yth e sam e solubility( a "W " compoun d or , i n the cas e o f tritium , highl ysoluble ) an d particl e siz e (a

n activitymedian aerodynami c diamete r o f 1 fim). Source : Dunning , et.al. , Estimate s o f Interna l Dose-Equivalent s t o 2 2 Targe t Organ s fo r Radionuclide s Occurring i n Routin e Release s Fro mNuclea r Fuel-Cycl e Facilities . Vol . Ill , NUREG-0150 , 1981 .P.2 2

2- 6 categories " wit hprogressivel yhighe r RQ s fo r thos e categorie s having shorte r hal f lives . Anothe r optio n considere d wa s t o separat e radionuclide s int o group s o f alpha , beta , an d gamm a emitter s wit hprogressivel yhighe r RQ s fo r eac ho f thes e categories . The RQ s fo r non-radioactive substance s hav e bee n establishe d i n thi s fashion , wit hdifferen t RQ s fo r differen t group s o f chemical s having simila r chemica l an d toxicologica l properties . Th e Agenc ychos e no t t o adop t the tw o method s o f categorizing radionuclide s mentione d above . The Agencybelieve s tha t radionuclide s groupe d int o half-lif e categorie s wit hprogressivel yhighe r RQ s fo r thos e categorie s having shorte r hal f live s ma yno t b e protective o f publi c healt han d th e environmen t becaus e radionuclide s wit hrelativel yshor t hal f live s (e.g. , ten days ) coul d emi t highenerg yradiatio n a t a highrat e fo r whic hthe federa l governmen t maywis ht o receive notificatio n t o determin e whethe r a respons e actio n i s necessary . Wit hregard t o categorizing radionuclide s o n the basi s o f whethe r theyar e primaril yalpha , beta , o r gamm a emitters , the actua l threa t t o publi c healt ho r welfar e o r the environmen t i s ofte n les s dependen t o n the typ e o f emissio n than o n the energ yo f the radiatio n (i.e. , a high energ ybet a particl e migh t be mor e harmfu l than a lowenerg yalpha particle) . The Agencydi d no t selec t thi s optio n becaus e i t coul d no t determin e appropriat e group s o r categorie s fo r radionuclide s prio r t o examining each individua l radionuclid e an d estimating the potentia l effec t o f a releas e o f each . 2. 6 OPTIO

N 6 : ESTABLISHIN

GA N ACTIVITYLEVEL RQ FO RINDIVIDUA

L RADIONUCLIDE S Th e Agenc yultimatel ydecide d t o issu e R Q adjustment s fo r individua l radionuclide s base d o n level s o f activity . Ther e ar e severa l advantage s t o basing radionuclid e RQ s o n activitylevels . Fo r example , a leve l o f radioactivit yi s muc heasie r t o estimat e than a dose-equivalent . The Agency believe s tha t setting RQ s i n terms o f activity , therefore , woul d provid e mor e timel yreporting than an RQ expresse d i n terms o f dose-equivalent . Asecon d advantag e o f using activit ylevel s i s tha t establishing RQ s fo r radionuclide s individuall ywoul d allowconsideratio n o f individua l radionuclid e characteristic s including th e typ e an

d strengt ho f ionizin g radiatio n produce d during a release . A n R Q i n terms o f dose-equivalen t (rem ) als o woul d (b

ydefinition ) have considere d typ e an d strengt ho f ionizing radiation" , bu t woul d hav e lef t muc hgreate r judgmen t t o the perso n i ncharg e o f the vesse l o r facility . Activit yleve l RQ s (curies ) als o conside r each radionuclid e individually , bu t minimiz e judgment s b ythe perso n i n charg e o f the vesse l o r facility . The optio n t o establis hRQ s i n terms o f curies , therefore , wa s considere d advantageous . Th e Agencyrecognize s tha t the nuclide-specifi c R Q approac hals o ha s disadvantages . Primarily , unlik e a dose-equivalen t value , a leve l o f activit y b yitsel f doe s no t necessaril yreflec t a leve l o f dange r t o huma n health . A releas e o f an RQ , therefore , doe s no t necessaril ymea n tha t ther e ha s bee n o r wil l b e an

yharm . A s i s presentl ythe cas e fo r RQ s fo r non-radioactive substances , a case-by-cas e evaluatio n wil l b e necessaryt o estimat e the huma n healt han

d welfar e an

d environmenta l hazard s associate d wit ha radionuclid e release , an

d t o determin e i f a federa l respons e i s warranted .P.2 3

CHAPTE R3 MAJO RISSUE S ASSOCIATEDWIT HTHE SELECTE DRQ ADJUSTMEN

T METHODOLOG

Y

Base d o n the advantage s an d disadvantage s o f the variou s RQ adjustmen t option s discusse d i n Chapte r 2 o f thi s report , EP Achos e t o establis ha specifi c curi e leve l fo r individua l radionuclide s a s the adjusted radionuclid e RQs . T o determin e the appropriat e R Q fo r eac hradionuclide , EP Aestimate d th

e quantityo f radionuclide s that , i f release d unde r a conservative se t o f exposur e conditions , coul d resul t i n an individua l receiving an effective dose-equivalent 1 o f 50 0 millirem . The specifi c methodolog yuse d t o estimat e thi s quantit yfo r eac hradionuclid e i s describe d i n detai l i n Chapte r 4 o f thi s report . EP Apublishe d a Notic e o f Propose d Rulemaking (NPRM ) t o adjus t the statutor

yR Q fo r radionuclide s o n Marc h16 , 198 7 (5 2 F R8172) . The methodolog

yuse d t o determine the R Q adjustment s propose d i n th e NPR Mwa s documente d i n detai l i n a supporting Technica l Backgroun d Documen t (TBD). 2 EP Areceive d numerou s comment s o n the NPR Mconcerning the technica l approach use d t o calculat e th e propose d RQs . Man yo f the comment s questione d specifi c assumption s mad e i n the exposur e scenario s use d t o calculat e RQ s and , i n respons e t o thes e comments , the Agencyanalyze d howthe propose d RQ s woul d chang e unde r varying set s o f assumptions . The method s an d result s o f thi s additiona l analysi s ar e documente d i n a Supplementar yTechnica l Backgroun d Document . Base d o n the comment s receive d an d furthe r analysis , severa l change s i n the propose d RQ adjustmen t methodolog ywer e mad e i n orde r t o calculat e fina l RQs . Thi s chapte r summarize s the majo r technica l issue s raise d i n comments.on the NPR Man d TBD , an

d highlight s change s mad e i n the RQ adjustmen t methodolog y i n respons e t o thes e comments . Wher e applicable , the Agency' s rational e for no t changing th

e methodolog

yi n respons e t o comment s als o i s summarized . The chapte r i s divide d int o si xsections , wit heachsection describing a separat e issue an

d what , i f any , change s hav e bee n mad e i n th e R Q adjustmen t methodolog

yi n orde r t o resolve the issue .

•'-Th e effective dose-equivalen t i s a weighte d averag e o f committe d dose

equivalent s fo r specifi c organs , wit hth e weight s determine d fro mris k factor s associated " wit hthe respective organs . I t provide s a measur e o f th e overal l (i.e. , tota l body ) carcinogeni c an d geneti c ris k resulting fro ma radionuclide exposure . ^U.S . Environmenta l Protectio n Agency , Technica l Backgroun d Documen t t o Suppor t Propose d Rulemaking Pursuan t t o Sectio n 10 2 o f the Comprehensive Environmenta l Response . Compensation , an d LiabilityAct : Radionuclides . Offic e o f Emergencyan

d Remedia l Response , EmergencyRespons e Division , Decembe r 1986 . J U.S . Environmenta l Protectio n Agency , Method s an d Result s for Calculation s o f Radionuclid e Reportabl e Quantitie s Unde r Varying Set s o f Conditions . Offic e o f Emergencyan d Remedia l Response , EmergencyRespons e Division , Jun e 18 , 1987 .P.2 4

3- 2
3. 1 DEPARTURE FRO

M THE METHODOLOG

YFO RADJUSTIN

GRQ s O F POTENTIA

L CARCINOGENS Althoughradionuclide s ar e recognize d a s potentia l carcinogens , EP Achos e no t t o us e the existing RQ adjustmen t methodolog yfo r potentia l carcinogen s t o determin e propose d RQ s fo r radionuclides . Thi s choic e ha s bee n affirme d i n the determinatio n o f fina l radionuclide s RQs . The reason s fo r thi s departur e ar e outline d below , following a brie f descriptio n o f the potentia l carcinoge n methodology . EPA' s methodolog

yfo r adjusting the RQ s o f potentia l carcinogen s wa s publishe d i n the Federa l Registe r o n Marc h16 , 198 7 (5 2 FR8140) . Briefly , thi s methodolog

yconsist s o f tw

o genera l steps . First , potentia l carcinogen s ar e assigne d t o "high, " "medium, " o r "low " hazar d categorie s base d o n thei r carcinogeni c potencyan d the weight-of-evidenc e indicating tha t the yar e i n fac t human carcinogens . I n the nex t step , RQ s ar e assigne d t o eachpotentia l carcinoge n base d o n thei r relative ranking . Potentia l carcinogen s i n the high categor yar e assigne d an R Q o f one pound , thos e i n the mediu mcategor

yar e assigne d a 10-poun

d RQ , an

d thos e i n the lowcategor yar e assigne d an RQ o f 10 0 pounds . Direc t applicatio n o f the potentia l carcinoge n methodolog yfo r the adjustmen t o f radionuclid e RQ s woul d no t b e appropriat e fo r severa l reasons . First , becaus e al l radionuclide s produc e ionizing radiatio n an d ionizing radiatio n i s know

n t o b e carcinogeni c t o humans , radionuclide s woul d b e assigne d eithe r a one - o r 10-poun d R Q base d o n th

e potentia l carcinoge n ranking system . Neithe r o f thes e level s ar e appropriat e fo r radionuclid e RQ s becaus e a s littl e a s one-billiont ho f a pound o f certai n radionuclide s migh t pos e a hazar d worth yo f a report . Second , the RQ s tha t woul d b e establishe d i f the potentia l carcinoge nmethodolog ywa s use d (i.e. , one o r 1 0 pounds ) woul d varyb

yonl yone orde r o f magnitude , whil e the hazard s associate d wit h radionuclide s ca n diffe r b yman yorder s o f magnitude . Finally , establishing RQ s i n mas s unit s sucha s pound s i s inappropriat e becaus e mos t radiation measurement s an

d standard s i n the U.S . ar e establishe d i n terms o f curie s o r rem , no t pounds . Eve n modificatio n o f the potentia l carcinoge n methodolog ywoul d no t addres s the crucia l questio n o f the appropriat e scale s fo r radionuclid e RQs . The potentia l carcinoge n methodolog ywoul d b e usefu l t o rank radionuclide s relative t o eac hother , bu t no t t o assign a specifi c R Q t o eac hradionuclide . Therefore" , EP

Aha s develope d an entirel ydifferen t methodolog yfor adjusting radionuclid e RQs , one tha t model s a serie s o f exposur e scenario s tha t lin k a quantityo f radionuclid e release d wit han internationall yaccepte d dose

equivalen t limi t o f 50 0 milliremfo r the genera l public . 3. 2 INCORPORATIO

N OF RADIOACTIV

E DECA Y I n the exposur e pathwa ymodeling don e t o calculat e propose d radionuclid e RQs , EP Apurposefull yignored the effect s o f radioactive deca yfo r the sak e o f conservatisman

d simplicity . Man

ycommenter s expresse d concer n tha t thi s approac hled t o RQ s fo r certai n short-live d radionuclide s tha t wer e unnecessaril ylow . Base d o n thes e comment s an d recognizing tha t radioactive deca yi s an intrinsi c propert yo f al l radionuclides , EP Aha s decide d t o incorporat e the effect s o f radioactive deca yi n the exposur e pathwa ymodel s3- 3

use d t o develop fina l RQs . A s woul d b e expected , thi s chang e resulte d i n a genera l shif t toward highe r RQs . Fo r the purpos e o f thi s analysis , the tota l perio d o f tim e i n the hypothetica l releas e an d exposur e scenario s can b e divide d int o thre e segments : (1 ) the tim e perio d ove r whic hth e releas e occurs ; (2 ) th e tim e i t take s fo r the radionuclid e t o trave l fro mth e poin t o f releas e t o the poin t o f exposure ; an

d (3 ) the perio d o f exposure . Radioactive deca yove r thes e tim

e period s i s take n int o accoun t differentl yi n the differen t exposur e pathwa y models , a s describe d i n Chapte r 4 an d Appendice s Athroug hD o f thi s report . 3. 3 ASSUMEDDISTANCE BETWEE N TH E POIN

T OF RELEAS E AN

DTHE POIN

T OF EXPOSUR

E A s describe d i n detai l i n Chapte r 4 , the radionuclid e RQ s wer e determine d b yexamining a hypothetica l releas e an d exposur e scenari o i n whic ha radionuclid e i s release d int o the environmen t an d migrate s t o an exposur e point . I n determining propose d RQs , the assume d distanc e betwee n th e poin t o f releas e an

d poin t o f exposur e i n al l scenario s wa s 3 0 meters . EP Areceive d conflicting comment s o n thi s assume d distance ; som e arguing tha t i t i s to o clos e becaus e the distanc e t o unrestricte d area s a t man yfacilitie s tha t handl e radionuclide s i s fa r greate r than 3 0 meters , an d other s arguing that , i t i s to o far becaus e i t i s possibl e fo r individual s t o com e withi n close r distance s (e.g. , 1 meter ) o f a radionuclid e release . EP Aha s retaine d the assume d distanc e o f 3 0 meter s i n al l exposur e scenario s analyze d fo r the developmen t o f fina l RQs . I t i s recognize d tha t no one , singl e distanc e woul d b e representative o f al l possibl e releas e scenario s involving radionuclides ; however , EP Aals o believe s tha t i t woul d b e unnecessaril ycomplicate d (thu s jeopordizing timel yreporting ) t o hav e multipl e RQ s fo r differen t distances , especiall ywhe n i t i s realize d tha t the actua l circumstance s o f a releas e (includin g the distanc e t o exposur e points ) wil l b e evaluate d i n deciding whethe r t o tak e a fiel d respons e onc e a repor t i s made . Therefore , recognizing it s inheren t limitations , EP Aha s decide d t o bas e al l the radionuclid e RQ calculation s o n jus t one distance . Ther e ar e severa l compelling reason s t o us e 3 0 meter s i n th e calculatio n o f RQs . First , thi s distanc e i s i n the rang e of , an d generall yi s consisten t with , recommende d isolationdistance s i n the even t o f hazardou s substanc e spills . Th e Departmen t o f Transportatio n (DOT ) EmergencyRespons e Guideboo k recommend s tha t unnecessar ypeopl e b e kep t a t leas t 4 5 meter s upwin d fro m release s o f thre e categorie s o f nuclea r material . Fo r 1 1 othe r categorie s o f nuclea r material , however , the Guideboo k doe s no t specif ya singl e evacuatio n o r isolatio n distance ; i t simpl yrecommend s tha t unnecessar ypeopl e b e kep t "away, " tha t the hazar d are a b e isolated , an d tha t entr

yt o th e are a b e denied . Furthermore , fo r smal l leak s o f hazardou s chemical s (no t radionuclides) , the recommende d initia l isolation distance s rang e fro m9 t o 18 0 meters , an

d fo r larg e spills , the recommende d isolation distance s rang e fro m2 0 t o 38 0 meters . Approximatel y4 4 percen t o f the initia l isolation distance s recommende d fo r release s o f hazardou s chemical s i s i n th e 0-3 0 mete r

U.S . Departmen t o f Transportation , 198 4 EmergencyRespons e Guidebook . Guideboo k fo r Hazardou s Material s Incidents . DOT P 5800-3 , 1984 .3- 4

range . Therefore , 3 0 meter s appear s t o b e an isolatio n distanc e tha t generall ywoul d b e familia r base d o n publishe d recommendations , an d one tha t migh t actuall ybe use d i n the even t o f a radioactive materia l release . Second , althoug

hman yfacilitie s ar e separate d fro munrestricte d area s b y mor e than 3 0 meters , certai n categorie s o f facilitie s tha t can releas e radionuclide s ofte n do no t hav e sucha larg e buffe r are a surrounding them . Fo r example , medica l facilitie s an d researchlaboratorie s mayallowmember s o f the genera l publi c withi n 3 0 meter s o f possibl e releas e points . Finally , EP

Abelieve s tha t a distanc e o f 3 0 meter s i s reasonabl y conservative an

d tha t using thi s distanc e t o determin e RQ s woul d assur e timel y reporting for mos t conceivabl e releas e situations . Using a shorte r distance , sucha s 1 meter , woul d resul t i n RQ s tha t ar e unreasonabl ylo wfo r mos t releas e situations , leading t o unnecessaryreport s an d burdens . Long-ter m exposure s a t les s than 3 0 meter s ar e believe d mostl yt o b e representative o f occupationa l exposure s withi n the workplace , whic hRQ s ar e no t intended t o address . Moreover , i t i s recognize d tha t exposur e distance s o f les s than 3 0 meter s coul d occur i n scenario s involving a los t radioactive source , bu t report s o f los t source s generall ywoul d no t initiat e a respons e actio n regardles s o f the RQ becaus e the locatio n o f the sourc e woul d b e unknown . 3. 4 ASSUME

DCONFIGURATIO

N O F RADIONUCLID

E RELEAS E A s par t o f th

e releas e an

d exposur e scenario s examine d fo r th e determinatio n o f propose d RQs , EP Aassume d tha t radionuclide s ar e release d int o th e environmen t fro

ma poin t source . Man ycommenter s pointe d ou t tha t radionuclide s frequentl yar e release d fro marea l source s (e.g. , radon release s fro mcoa l as hpile s or ope n pi t mines ) an d tha t the propose d RQ s wer e unnecessaril ylo

wfo r thi s typ e o f release . AlthoughEP

Arecognize s tha t a poin t sourc e releas e mode l i s no t applicabl e fo r area l sources , th e poin t sourc e releas e configuratio n ha s bee n retaine d in al l exposur e scenario s use d t o determin e fina l RQs . The rational e for thi s decisio n i s basicall yth e sam e a s tha t presente d above for th e selectio n o f th

e 30-mete r distanc e i n th e exposur e scenario . Namely , EP A believe s tha t i t woul d be bes t t o us e a singl e releas e configuratio n t o determin e RQ s (multipl e RQ s for differen t releas e configuration s coul d caus e confusio n an

d untimel yreporting) , an d th e singl e bes t releas e configuratio n to assume i s a poin t sourc e becaus e i t i s conservative (i.e. , i t i s mor e likel yt o yiel d RQ s tha t wil l assur e timel yreporting than an area l source) . B yassuming a poin t sourc e t o determin e RQs , however , EP Arecognize s tha t ther e ma

ybe man

yarea l source s tha t releas e mor e than an R Q o f radionuclide s eachday . I t i s possibl e tha t the governmen t woul d neve r respon d t o a repor t o f som e o f thes e releases . Therefore , i n respons e t o request s fro mthe public , EP

Aplan s t o evaluat e availabl e releas e dat a t o determine i f certai n release s can be administrativel yexempted fro mth e R Q reporting requirement s to hel p eliminat e unnecessar yreporting burdens . I n respons e t o publi c comment s on th

e NPRM , EP

Aalread

yha s examine d an

d prepare d a separat eP.2 7

3- 5
report 5 o n th e radiologica l hazard s associate d wit hcoa l an d as ha t coal-fire d boile r sites . Th e purpos e o f thi s analysi s wa s t o investigat e whethe r a sufficient technica l basi s exist s fo r administrativel yexemptin g release s o f radionuclide s i n coa l an d coa l as hfro mth e R Q reportin g requirements . 3. 5 MODELINGOF POTENTIAL EXPOSURE S THROUGHTH E INGESTION O F CONTAMINATE D VEGETABLE S I n determinin g th e propose d RQs , EP Aconsidere d a n exposur e scenari o i n whic ha n individua l ingest s vegetable s contaminate d byth e airborn e depositio n o f radionuclides . Thi s scenari o wa s no t use d a s a basi s fo r th e propose d RQs , however , becaus e i t wa s foun d t o b e generall ya les s critica l exposur e pathwa y tha n th e ingestio n o f contaminate d wate r unde r th e se t o f condition s assume d (i.e. , fo r th e majorit yo f radionuclides , lowe r RQ s wer e calculate d fo r scenario s involvin g th e consumptio n o f contaminate d wate r tha n fo r scenario s involvin g th e consumptio n o f contaminate d vegetables) . Th e ingestio n o f contaminate d vegetables , however , wa s considere d mor e full yi n th e developmen t o f fina l RQ s fo r th e reason s state d below . Decision s t o includ e th e effect s o f radioactiv e deca yi n th e exposur e pathwa ymodel s an d t o us e a different , mor e conservativ e mode l fo r calculatin g th e facto r representin g th e transfe r o f radionuclide s fro mai r t o vegetatio n ten d t o exaggerat e th e importanc e o f th e vegetabl e ingestio n pathwa yrelativ e t o othe r pathways . Appendi xC o f th e Technica l Backgroun d Documen t supportin g th e NPR Mdescribe s th e tw o model s considere d fo r estimatin g depositio n o f radionuclides . On e o f th e model s i s presente d b yth e Nuclea r Regulator y Commissio n i n Regulator yGuid e 1.109 6 an d th e othe r i s a mode l presente d b y th e Nationa l Counci l o n Radiatio n Protectio n an d Measurement s (NCRP). 7 Th e propose d RQ s wer e base d o n th e Nuclea r Regulator yCommissio n model , whic hwa s subsequentl ydetermine d t o b e inappropriat e fo r th e releas e configuration s an d distance s considere d fo r th e developmen t o f RQs . Th e NCR P model , whic hi s ver yconservativ e whe n couple d wit hth e atmospheri c dispersio n facto r considered , wa s determine d t o b e th e mos t straightforwar d metho d fo r determinin g RQ s fo r th e vegetabl e ingestio n pathway . Se e Sectio n 4. 4 an d AppendixC o f thi s repor t fo r mor e detai l o n thes e tw o model s and th e reason s fo r ultimatel yselectin g th e NCR P model .

5 U.S . Environmenta l Protectio n Agency , Technica l Backgroun d Supplemen t i n Suppor t o f Rulemakin g Adjustmen t Activitie s fo r Reportabl e Quantitie s (RQs ) o f Radionuclides . Offic e o f Radiatio n Programs , Februar y1989 .

6 U.S . Nuclea r Regulator yCommission , Calculatio n o f Annua l Dose s t o Ma n fro m Routin e Release s o f Reacto r Effluent s fo r th e Purpos e o f Evaluatin g Complianc e wit h1 0 CF RPar t 50 . Appendi xI . Regulator yGuid e 1.109 , Revisio n 1 , Octobe r 1987 .

7 Nationa l Counci l o n Radiatio n Protectio n an d Measurements , Screenin g Technique s fo r Determinin g Complianc e wit hEnvironmenta l Standards : Release s o f Radionuclide s t o the Atmosphere . NCR P Commentar yNo . 3 , 1986 .P.2 8

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3. 6 ADDITIONA

L EXPOSUR

E PATHWA

YMODEL S I n the developmen t o f fina l RQs , the Agencyconsidere d four potentia l exposur e pathway s mor e full ythan i t di d i n the developmen t o f propose d RQs . Thes e pathway s ar e the ingestio n o f contaminate d surfac e water , th e ingestion o f vegetable s contaminate d b yradionuclide-bearing irrigation water , the ingestio n o f contaminate d milk , an d direc t exposur e t o neutrons . A s describe d i n th

e TBD supporting the NPRM , potentia l exposure s throug h the ingestio n o f contaminate d surfac e wate r wer e considere d qualitatively , bu t an equatio n fo r the calculatio n o f RQ s base d o n thi s pathwaywa s no t developed . I t wa s recognize d that , a s lon g a s radioactive deca ywa s no t taken int o accoun t (a s wa s the cas e fo r the propose d RQs) , th e ingestion o f surfac e wate r generall ywoul d b e a les s critica l exposur e pathwa ythan the ingestion o f groun

d wate r becaus e surfac e wate r generall ywoul d provid e fo r muc hgreate r dilution . B

yincorporating radioactive deca yint o the calculatio n o f fina l RQs , however , the relative importanc e o f the surfac e wate r pathwa ywa s increase d significantl ybecaus e o f the deca ytha t can occur ove r the lon g transpor t time s i n groun d water . Accordingly , the potentia l ingestion o f contaminate d surfac e wate r wa s considere d mor e rigorousl yi n the developmen t o f fina l RQ s (se e Section 4. 3 an d Appendi xB o f thi s report) . Similarly , t o determin e the propose d RQs , EP Aconsidere d potentia l exposure s vi a othe r ingestio n pathway s (e.g. , mea t an d milk ) qualitatively , suggesting that , unde r the se t o f exposur e condition s assumed , thes e othe r ingestio n pathway s woul d be les s critica l than eithe r the ingestion o f wate r o r the ingestio n o f vegetables . EP Arecognize s tha t thes e othe r ingestion route s actuall ycoul d be mor e critica l depending o n the condition s o f a releas e and , base d o n comment s receive d o n the NPRM , the ingestion o f vegetable s contaminate d b yirrigatio n an

d th e ingestion o f mea t an d mil k wa s analyze d mor e full yi n the developmen t o f fina l RQs . Se e Section 4. 4 an d Appendi xC o f thi s repor t fo r a discussio n o f the method s an d result s o f thi s analysis . Twenty-fou r radionuclide s decay , a t leas t par t o f the time , b y spontaneou s fission an d emi t neutrons . Neutron s can presen t a significan t externa l hazard and , therefore , direc t exposur e t o neutron s wa s taken int o accoun t in th

e determinatio n o f fina l RQ s (se e Sectio n 4. 5 an d Appendi xD o f thi s repor t fo r a discussio n o f th e method s an

d resul t o f thi s analysi s o f neutrons) .P.2 9

CHAPTE R4 METHODOLOG

YFO RRQ ADJUSTMENT S Thi s chapte r describe s th e Agency' s methodolog yfo r adjusting the RQ fo r radionuclides . The chapte r i s divide d int o seve n mai n sections . Sectio n 4. 1 provide s an overviewo f th e methodology , outlining the basi c rational e an d genera l step s taken . The section s tha t followdescribe the step s outline d i n Section 4. 1 i n mor e detail . Section s 4.2 , 4.3 , 4.4 , an d 4. 5 describe th

e method s use d t o determin e RQ s base d o n inhalation , ingestio n o f water , ingestion o f food , an d direc t exposure , respectively . I n Sectio n 4.6 , the assignmen t o f radionuclide s t o RQ group s i s describe d and , finally , Section 4. 7 outline s the basi s fo r reporting requirement s fo r mixtures . 4. 1 OVERVIE

W O F TH E METHODOLOG

Y I n simples t terms , the RQ s wer e determine d b yestimating the quantityo f a radionuclide that , i f release d int o the environmen t unde r an assume d se t o f conditions , coul d resul t i n an individua l receiving a specifie d effective dose-equivalent . T o estimat e thi s quantit yfo r eachradionuclide , a serie s o f hypothetica l (but conservative ) exposur e scenario s wer e analyze d t o lin k a quantityrelease d wit han accepte d dos e level . Thi s proces s begin s wit hthe Annua l Limit s o f Intak e (ALIs ) publishe d fo r 75 7 radionuclide s i n ICRP' s Publicatio n 30 . ALI s ar e the quantityo f radionuclide s (i n becquerels ) that , i f take n i n b y"Referenc e Man," ^ woul d resul t i n eithe r (1 ) a committe d effective dose-equivalent J o f 5 re mt o th e whol e bod

y(stochasti c ALI) , o r (2 ) a committe d dose-equivalent ^ o f 5 0 re mt o an yorgan o r tissue (non-stochasti c ALI) . I n the propose d revisio n t o 1 0 CF R Par t 20 , th

e Nuclea r RegulatoryCommissio n propose s the adoptio n o f ALI s because : "th

e revisio n improve s radiatio n protectio n standard s b yreflecting development s i n the principle s tha t underli e radiatio n protectio n an d advance s i n related science s tha t have occurre d sinc e the promulgatio n o f 1 0 CFRPar t Internationa l Commissio n o n Radiologica l Protection , Annal s o f th e ICRP : Limit s fo r Intake s o f Rad i onucl.id.6s b yWoirksrs , ICRP Publicatio n 30 , Pa._r t 2 , 1980 . rt ^Referenc e ma n i s a hypothetica l individua l possessing "average " characteristic s o f human s (sucha s bod yweight , dietar

yintake , an

d inhalation rate ) t o "serv

e a s a commo n biologica l basi s fo r calculating AL I an d othe r values .

• 3A n effective dose-equivalen t i s a weighte d averag e o f committe d dose

equivalent s fo r specifi c organs , wit hthe weight s determine d fro mris k factor s associate d wit hthe respective organs . I t provide s a measur e o f the overal l (i.e. , tota l body ) carcinogeni c an d geneti c ris k resulting fro ma radionuclid e exposure . The ter

m"committed dose-equivalent " mean s tha t thi s i s the dos e tha t wil l accru e fro mone yea r o f intak e o f radionuclide s during the remaining lifetim e (5 0 years ) o f the individual . ^The dose-equivalen t referre d t o her e i s the sam e a s tha t describe d i n footnot e 3 above , excep t tha t i t i s the dos e t o a singl e organ o r tissue rathe r than an "effective " dos e t o the tota l body .4- 2

2 0 nearl y3 0 year s ago " (5 0 F R1092 , January9 , 1986) . I n short , the propose d ALI s ar e intak e limit s designe d t o limi t the ris k o f healt hdamage . EP Ause d the ALI s fro mICRP 3 0 t o determin e RQ s b yestimating th

e quantit yo f radionuclide s that , i f released , coul d resul t i n the intak e o f one-tent ho f an ALI . The ALI s wer e divide d b y1 0 t o adjus t the dos e tha t the y ar e base d o n (a

n effective dose-equivalen t o f 5 re mfo r mos t radionuclide s and , fo r a minorit yo f radionuclides , a dose-equivalen t o f 5 0 re mt o the critica l organ ) t o a n effective dose-equivalen t o f 0. 5 re m(50 0 millirem) . A whole-bod

ydose-equivalen t o f 50 0 milliremi s recommende d b ythe Federa l Radiatio n Protectio n Guidanc e a s an uppe r boun d o n exposur e t o individua l member s o f the genera l public . EP Abelieve s tha t thi s dose-equivalen t leve l i s appropriat e fo r the purpos e o f calculating RQs ; RQ s base d o n 50 0 millirem shoul d b e sufficientl ylowt o assur e timel yreporting i n mos t circumstance s bu t no t s o lowa s t o creat e unnecessaryreporting . A s discusse d below , numerou s conservative assumption s wer e mad e i n the calculatio n o f RQ s s o tha t the releas e o f an RQ wil l probabl yresul t i n whol e bod ydose s les s than 50 0 millirem . Hypothetica l release s an d exposure s wer e analyze d fo r four differen t route s o f exposure : inhalation , ingestio n o f water , ingestio n o f vegetables , an d direc t exposure . Fo r eac hexposur e pathway , a "releas e value " wa s calculate d fo r the 75 7 radionuclide s fo r whic hALI s hav e bee n published . The releas e value s represen t a quantit yo f radionuclide s (i n curies ) that , i f release d unde r the condition s assumed , coul d resul t i n a whole-bod ydose

equivalen t o f 50 0 milliremvi a eacho f the exposur e pathways . Thes e releas e value s wer e calculate d using simpl e an d conservative model s tha t defin e a hypothetica l scenari o i n which : (1 ) a radionuclid e i s assume d t o be release d int o an environmenta l medium ; (2 ) the radionuclid e i s transporte d fro mthe poin t o f releas e t o the poin t o f exposur e an d dilute d along the way ; an d (3 ) a perso n i s expose d t o (i.e. , inhales , ingests , o r i s expose d t o direc t radiatio n from ) the release d radionuclid e ove r a certai n lengt ho f time . I n thes e scenarios , man ypropertie s intrinsi c t o th e radionuclide s an

d man y environmenta l variable s ar e considered , leading t o differen t releas e value s fo r the differen t exposur e pathways . Fo r eac hradionuclide , the releas e value s calculate d fo r the differen t exposur e pathway s wer e compare d t o one anothe r an d the lowes t wa s selected . Thi s lowes t releas e valu e wa s the n rounde d dow n t o the neares t decad e t o determine " the RQ fo r tha t radionuclide . Fo r al l radionuclide s tha t do no t hav e publishe d AL I values , a singl e RQ wa s selected for al l o f the mbase d o n the distributio n o f RQ s calculate d a s outline d above fo r the 75 7 radionuclide s tha t do hav e ALIs . 4. 2 RELEAS E VALUE S FO RTH E INHALATIO

N PATHWA Y Inhalatio n releas e value s ar e i n unit s o f curie s an d represen t the activit yleve l o f eachradionuclid e that , i f release d unde r a se t o f conservative circumstances , coul d resul t i n an expose d individua l inhalingP.3 1

4- 3

one-tent ho f an ALI . The Agencydevelope d the following mathematica l expressio n t o derive releas e value s base d o n exposur e throug hinhalation : (1 ) Inhalatio n Releas e Valu e = ALI/((10)*(R)*(X/Q)*(BR)*(lxl0 6 ) ) where : AL I = Annua l Limi t o f Intak e fo r inhalatio n (microcuries) ;

1 0 = Facto r t o adjus t the dose-equivalen t o n whic hthe AL I i s base d (dimensionless) ; R= Airborn e releas e fractio n (dimensionless) ; -1 3 X/ Q = Atmospheri c relative concentratio n valu e (8. 4 x1 0 day/cubi c cm) ; BR= Breathing rat e (2. 3 x1 0 cubi c cm/day) ; an d 1 x1 0 = Conversio n facto r betwee n microcurie s an d curies . The inhalatio n ALI s use d i n the calculation s ar e take n fro mth e ICRP' s Publicatio n 3 0 (afte r conversio n fro mbecquerel s t o curies) . Wher e mor e than one inhalatio n AL I wa s availabl e for a particula r radionuclide , th e lowes t valu e wa s use d fo r the calculations . Thi s approac hassure s tha t releas e o f the radionuclid e i n it s mos t hazardou s chemica l for mi s take n int o consideration . The inhalatio n ALI s ar e derive d fo r worker s i n nuclea r facilitie s an

d ar e 1 0 time s thos e recommende d fo r adul t member s o f th e genera l public . T o adjus t the Commission' s ALI s t o reflec t the mor e protective leve l o f exposur e t o the genera l public , the ALI s ar e divide d b y10 . The releas e fraction , R , reflect s the fraction o f th e radionuclide releas e tha t coul d become airborn e an d b e o f respirabl e siz e (1 0 micron s i n diamete r o r less) . The Nuclea r RegulatoryCommissio n ha s develope d method s fo r estimating releas e fraction s fo r radionuclide s unde r acciden t conditions . Asummar

yo f thes e method s an d a tabl e o f releas e fraction s fo r thos e individua l radionuclide s wit hspecifi c RQ s can b e foun d i n Appendi xAo f thi s report . The atmospheri c relative concentratio n valu e (X/Q ) use d i n the calculations , 8. 4 x1 0 day/cubi c cm , correspond s t o th e relative concentration , a t groun d level , 3 0 meter s downwin d fro ma ground-leve l point

sourc e releas e unde r neutra l (Clas s D ) meteorologica l conditions . A

-"Fo r mos t radionuclides , the intake o f one-tent ho f an AL I wil l caus e an effective dose-equivalen t o f 50 0 millirem . Fo r a fewradionuclides , the intake o f one-tent ho f a n AL I wil l resul t i n a dose-equivalen t o f 5 re mt o th e mos t expose d organ . °McGuire , S.A. , ARegulator yAnalysi s o n EmergencyPreparednes s fo r Fue l Cycl e an

d Othe r Radioactive Material s Licenses . NUREG-1140 , U.S . Nuclea r Regulator

yCommission .P.3 2

4- 4 ground-leve l releas e unde r Clas s D meteorologica l condition s lead s t o highe r ground-leve l concentration s than woul d b e th e cas e fo r a releas e unde r mor e turbulen t conditions . B yusing the ground-leve l concentration , the derive d releas e value s ar e lowe r than woul d b e the cas e i f the Agenc yhad use d an above-groun

d concentration . Similarly , releas e value s base d o n a point

sourc e releas e a t groun d leve l ar e lowe r than woul d b e calculate d i f an area l sourc e had bee n assume d o r i f an above-groun d sourc e (e.g. , a smokestack ) had bee n assumed . Thus , the propose d RQ s ar e base d o n a mor e protectiv e releas e scenario . The Agencyha s chose n 3 0 meter s a s a reasonabl yconservative distanc e betwee n the poin t o f releas e an d poin t o f exposur e (se e Sectio n 3. 3 o f thi s report) . A t fixe d facilities , the distanc e t o unrestricte d area s i s likel yt o b e greate r than 3 0 meters ; therefore , 3 0 meter s wil l resul t i n a conservative estimat e fo r exposure . The Agencyderive d the valu e o f X/ Q fo r distance s les s than 10 0 meter s base d on th e dispersivit ydat a presente d i n The Workboo k o f Atmospheri c Dispersio n Estimates. ' The X/ Q value s presente d i n the Workboo k do no t include dat a for distance s les s than 10 0 meters ; therefor e extrapolatio n i s necessary . Althoughthe extrapolatio n fro m10 0 meter s t o 3 0 meter s mayno t b e totall yaccurate , a mor e preferre d metho d o f determining a valu e fo r X/ Q a t thi s distanc e coul d no t b e identified . The Agencybelieve s it s evaluatio n o f exposur e vi a inhalatio n i s conservative , an d tha t the erro r introduce d b

ythe extrapolatio n t o 3 0 meter s i s no t detrimenta l give n the purpos e o f RQs . Afurthe r explanatio n o f atmospheri c relative concentratio n value s an

d thei r derivatio n can b e foun d i n Appendi xAo f thi s repor t an d i n the Workboo k o n Atmospheri c Dispersio n Estimates . The inhalatio n o f toxi c substance s depend s i n an obviou s manne r o n the breathing rat e o f individuals . Fo r purpose s o f the releas e valu e calculations , the breathing rat e o f "Referenc e Man " i s assume d t o be 2. 3 x1 0 cubi c centimeter s pe r day . The expressio n show n i n Equatio n (1 ) fo r determining the releas e valu e fo r the inhalatio n pathwa yca n b e simplifie d b ysubstituting the following value s int o th

e equation : o (X/Q ) = 8. 4 x10" 13 ; an d
o B R= 2. 3 x10 7

. B ymultipling the number s i n th e denominator , Equatio n (1 ) simplifie s to : (2 ) Inhalatio n Releas e Valu e = AL I (inhalation)/((193.2)*(R) ) Fo r eacho f th

e individua l radionuclide s fo r whic han AL I i s available , the releas e value s calculate d fo r the inhalatio n pathwayar e presente d i nAppendi x

'Turner , D . Bruce , Workboo k o f Atmospheri c Dispersio n Estimates . EP AOffic e o f Ai r Programs , 1970 . Till , J.E. , Meyer , H.R . (Editors) , Radiologica l Assessment . ATextboo k on Environmenta l Analysis . NUREG/CR-3332 , U.S . Nuclea r RegulatoryCommission , 1983 .P.3 3

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E o f thi s report . A s note d i n the appendix , the inhalation mode l wa s no t use d fo r nobl e gase s othe r than rado n (e.g. , argon , krypton , an d xenon) . According t o ICRP Publicatio n 30 , the effect s o f inhaling a nobl e ga s ar e negligibl e compare d t o the effect s o f externa l irradiatio n fro ma perso n being submerge d i n a clou

d o f thes e radionuclides . Thus , a separat e mode l describe d i n Sectio n 4. 5 wa s use d t o determin e the direc t exposur e releas e valu e fo r nobl e gases . Inhalatio n o f rado n wa s considere d becaus e the critica l healt heffec t associate d wit hexposur e t o radon i s cause d b yinhalation o f radon' s short

lived deca

yproducts . I t i s importan t t o clarif ytha t Equation s (1 ) an d (2 ) ignor e the effect s o f radioactive decay . Thi s i s becaus e the inhalatio n pathwa ymode l consider s exposur e t o an airborn e plume o f radionuclides . I n thi s situation , a short

live d radionuclid e coul d underg o significan t deca yi f the releas e an d exposur e period s wer e a ful l day , bu t deca ywoul d b e muc hles s i f a tim e perio d o f severa l minute s wa s considered . Becaus e i t wa s no t possibl e t o establis h exac t bound s o n the rang e o f releas e an d exposur e periods , th e Agencyassume d conservativel ytha t n o deca yoccur s ove r thes e periods . EP Aals o ignored deca yove r th

e perio d o f radionuclid e transpor t t o the poin t o f inhalation . Thi s approac hwa s adopte d becaus e deca yduring airborn e transpor t t o a recepto r jus t 3 0 meter s awa ywoul d b e negligibl e fo r mos t radionuclides . 4. 3 RELEAS E VALUE S FO RTH E INGESTIO

N O F WATE

R EP Acalculate d releas e value s fo r the ingestion o f contaminate d groun d wate r an

d the ingestio n o f contaminate d surfac e water . The model s used t o calculat e thes e releas e value s ar e summarize d i n thi s sectio n an d documente d i n detai l i n Appendi xB o f thi s report . Fo r the ingestio n o f contaminate d surfac e water , EP Acalculate d releas e value s fo r a scenari o i n which : (1 ) a radionuclid e i s release d fro ma poin t sourc e int o a smal l river ; (2 ) th e radionuclid e mixe s completel yan d instantaneousl yi n the wate r colum n bu t doe s no t settl e t o the bottomo r decay ; an

d (3 ) a perso n draw s wate r fro ma poin t 3 0 meter s downstrea man d drink s the wate r directl yove r th e perio d o f tim

e tha t i t take s th

e contaminatio n t o pass . Radioactive deca yove r the tim

e i t take s for th

e radionuclid e t o trave l t o the poin t o f exposur e wa s ignored becaus e thi s tim e perio d woul d b e shor t (probabl yaroun d a minut e o r less) , an d deca yove r thi s perio d woul d b e negligibl e fo r mos t radionuclides . Deca yove r th

e period s o f releas e an

d exposur e als o wa s ignored becaus e thes e period s coul d no t be defined ; theycoul d b e veryshort , suchtha t insignifican t deca ywoul d occur , o r the ycoul d b e verylong , a s woul d b e the cas e i f an individua l stored a larg e quantityo f wate r withdraw n fro mthe rive r an

d consume d the wate r ove r an extende d period . Althoughthe releas e value s calculate d fo r the surfac e wate r ingestion pathwa ywer e sometime s lowe r than thos e calculate d fo r the ingestion o f groun d water , the surfac e wate r releas e value s wer e neve r the lowes t whe n compare d t o the releas e value s calculate d fo r the othe r exposur e pathways . A s a result , non e o f th

e RQ s calculate d fo r th e 75 7 specifi c radionuclide s ar e base d o n th e surfac e wate r ingestio n pathway . B ycomparison , however , the releas e value s calculate d fo r the ground-wate r ingestion pathwa ywer e the lowes t one s (an d henc e serve a s the basi s fo r RQs ) for severa l radionuclides . Therefore ,P.3 4

4- 6
becaus e the ground-wate r ingestio n pathwa yaffect s some o f the RQ s whil e the surfac e wate r ingestio n pathwa ydoe s not , the Agencychos e t o us e onl ythe ground-wate r ingestio n pathwayi n the developmen t o f fina l RQs . The metho d tha t the Agencyha s adopte d fo r the calculatio n o f releas e value s base d o n consumptio n o f contaminate d groun d wate r i s presente d i n Equatio n (3 ) below : (3 ) Drinking Wate r Releas e Valu e = ALI/((10)*(DF)*(CT)*(WC)*( 1 xIO 6 ) ) where : AL I = Annua l limi t o f intak e fo r ingestio n (microcuries) ;

1 0 - = Facto r t o adjus t the dose-equivalen t o n whic hthe AL I i s base d (dimensionless) ; DF = Dilutio n facto r (lite r ) ; CT = Contac t tim

e (days) ; WC = Wate r consumptio n o f "Referenc e Man " ( 2 liters/day) ; an d 1x1 0 = Conversio n facto r betwee n microcurie s an d curies . The ingestio n ALI s use d i n the calculation s ar e taken fro mICRP' s Publicatio n 3 0 (afte r conversio n fro mbecquerel s t o curies) . Wher e mor e than one ingestio n AL I wa s availabl e fo r a particula r radionuclide , the lowes t AL I wa s use d fo r the calculations . The facto r 1 0 convert s th e 5 re mannua l occupationa l dos e limi t t o the 50 0 millirem(0. 5 rem ) annua l limi t fo r member s o f the genera l public , a s discusse d fo r the inhalatio n pathway . The dilutio n facto r (DF ) i s derive d b yconsidering the maximu m concentratio n i n a contaminan t plume 3 0 meter s downgradien t fro ma poin t sourc e release , a s calculate d b yus e o f standard equation s modeling ground-wate r transport . Th e maximu mconcentratio n i s assume d t o b e uniforml y distribute d throughou t the plume . Thirt ymeter s i s chose n fo r consistency wit hthe atmospheri c mode l an d lead s t o highe r concentration s an d lowe r releas e value s than woul d b e the cas e fo r a greate r distance . The Agencyconsidere d tw o dilutio n model s during the RQ developmen t process : a simpl e dilutio n mode l an d an advection-dispersio n model . The simpl e dilutio n mode l relie s o n the estimat e tha t the practica l nee d fo r wate r

"Thi s i s a conservative approximatio n becaus e concentration s ar e ususall y distribute d i n a gaussian fashio n withi n a plume , wit hsmalle r concentration s toward the edge s o f the plume an d highe r concentration s nea r the plume' s cente r line .P.3 5

4- 7

o f a singl e perso n livin g i n a rura l are a i s 7,70 0 cubi c meter s pe r year . Thi s represent s a dilutio n facto r o f 1. 3 x1 0 pe r liter . The mode l assume s the flowrat e o f the aquife r i s sufficientl yslowtha t th e contac t tim

e i s an entir e yea r (36 5 days ) an d the entir e quantityrelease d i s pumpe d fro mthe wel l ove r a perio d o f one year . Us e o f the advection-dispersio n mode l fo r determinatio n o f radionuclid e concentratio n i n drinking wate r relie s o n estimate s o f longitudina l an d transvers e coefficient s o f dispersion , bul k densityo f th e aquifer , sorption coefficient s fo r individua l radionuclides , an d aquife r flowrate . The Agency believe s that , fo r the purpos e o f developing RQs , the advection-dispersio n mode l i s mor e appropriat e than the simpl e dilutio n model . The simpl e dilutio n mode l assume s tha t al l o f the releas e wil l b e pumpe d fro mthe wel l an

d al l o f the contaminate d wate r wil l b e consume d b yan individual . Althoughthe simpl e dilutio n mode l appear s appropriat e fo r determining concentratio n level s fo r purpose s o f ris k assessment , the advection-dispersio n mode l i s base d o n th e somewha t les s conservative bu t mor e likel yassumptio n tha t onl ya fractio n o f the releas e wil l b e pumpe d fro mthe wel l an

d consume d b

yan individual . The Agency , therefore , base d it s drinking wate r exposur e calculation s o n the advection-dispersio n model . The Agencyals o considere d us e o f severa l othe r ground-wate r model s use d b yEPA' s Offic e o f Soli d Wast e t o suppor t analyse s unde r the Resourc e Conservatio n an

d RecoveryAc t (RCRA) . The equation s use d i n the RCR Amodel s ar e simila r t o the equation s use d i n the advection-dispersio n model ; however , certai n parameter s use d i n the equation s i n the RCR Amodel s ar e muc hmor e conservative than thos e use d fo r purpose s o f RQ adjustmen t i n the advection-dispersio n model . The Agencybelieve s tha t the value s use d a s input s t o the advection-dispersio n mode l ar e reasonabl yconservative an d appropriat e fo r the calculatio n o f RQs . Furthe r discussio n o f the advection-dispersio n model , the simpl e dilutio n model , an d the four RCR

A model s can be foun

d i n Appendi xB o f thi s report . The ground-wate r advection-dispersio n modeling equation s utiliz e a retardatio n factor , whic haccount s fo r the exten t t o whic ha radionuclid e i s retarde d relative t o the transporting wate r mass . Retardatio n factor s fo r eac hradionuclid e diffe r becaus e differen t radionuclide s ar e adsorbe d differentl yont o the san d o r soi l i n an aquifer . Becaus e o f thei r chemica l nature , som

e radionuclide s ar e adsorbe d onl yweakl yo r no t a t al l (e.g. , technetium) , whil e other s ar e adsorbe d strongl y(e.g. , cesium) . Th e retardatio n facto r use d i n the mode l take s int o accoun t the soi l bul k density ,

iU Th e Nuclea r RegulatoryCommissio n use s th e simpl e dilutio n mode l fo r the purpose s o f determining allowabl e onsit e disposa l concentration s fo r radioactive waste . Oztunali , 0.1. , Roles , G.W. , D e Minimi s Wast e Impact s Analysi s Methodology . NUREG/CR-3585 , Februar y1984 . Whil e wate r supplie s i n suburban o r urban area s ma yb e fro

mgroun d water , the groun

d wate r i s likel y t o b e pumpe d throug hsevera l high-capacit ywell s an d then distribute d throug h severa l interconnecting pipe s t o individua l homes . Thi s typ e o f syste mwil l resul t i n muc hgreate r dilutio n than a simpl e rura l syste mwher e wate r i s obtaine d fro

ma backyar d wel l an d take n directl yt o a tap .

### 4- 8

porosity , an

d the sorptio n coefficient , K . Atabl e o f sorption coefficient s use d i n the mode l can b e foun d i n Appendi xB . Whe n th e sorption coefficien t i s equa l t o zero , the retardatio n factor , R, i s equa l t o one ; tha t is , ther e i s n o retardation . Whe n the sorptio n coefficien t i s greate r than zero , the retardatio n facto r i s greate r than one an d nuclid e retardatio n ha s occurred . The dilutio n facto r use d i n Equatio n (3 ) i s relate d directl yt o the sorptio n coefficient . The greate r the sorptio n coefficient , the greate r i s the nuclid e retardatio n i n the aquifer , an d the greate r i s the dilutio n factor . The retardatio n facto r als o affect s the estimatio n o f the contac t time , the tota l tim

e a contaminan t plume wil l b e i n contac t wit han affecte d well . I f the retardatio n facto r i s equa l t o one , the advection-dispersio n mode l assume s tha t the contaminatio n i s moving a t the sam e velocit ya s the wate r i n the aquife r (i.e. , n o retardatio n occurs) , an d the wel l i s i n contac t wit hthe contaminatio n fo r nin e days . I f the retardatio n facto r i s greate r than one , the contaminatio n i s being retarde d an d i s moving a t a slowe r rat e than the wate r i n the aquifer . Th e contac t time , therefore , wil l b e longe r than nin e days . Appendi xB describe s furthe r the relationshi p betwee n th e retardatio n factors , dilutio n factors , an d contac t time s fo r differen t radionuclides . I n calculating the drinking wate r releas e values , whe n the sorptio n coefficien t i s greate r than o r equa l t o 4 fo r a particula r radionuclide , th e contac t time i s assume d t o b e 36 5 days . I n reality , i t coul d tak e significantl ylonge r than 36 5 day s fo r the contaminan t plume t o pas s the wel l head , bu t becaus e ALI s reflec t annua l intak e levels , the contac t tim e i n the advection-dispersio n mode l i s constraine d no t t o excee d 36 5 days . The dilutio n factor , however , als o wil l reflec t the sorptio n coefficient ; th e dilutio n facto r i s verylarg e whe n the sorptio n coefficien t i s significantl y above 4 . I n the mode l use d t o calculat e releas e value s fo r the ingestion o f groun d water , the releas e i s assume d conservativel yt o b e instantaneou s t o th e saturate d zon e suchtha t n o deca yove r the perio d o f releas e coul d occur . Equatio n (3) , however , doe s conside r deca yove r the perio d o f transpor t an d perio d o f ingestion . Fo r the perio d o f transport , an exponentia l deca yter m i s incorporate d i n the calculatio n o f the dilutio n facto r (se e Appendi xB) . T o conside r deca

yove r the perio d o f ingestion , i t i s recognize d tha t an individua l woul d inges t smalle r quantitie s o f radioactivit yove r time . Accordingly , deca

yove r the perio d o f exposur e i s take n int o accoun t using the following " integrate d exponentia l equatio n involving the contac t time :



### (4 ) 

### 1 - ex

p 

### (-Xd ) where : X= 0.693/t]/2 , wher e tw 2 = radionuclid e half-lif e i n days ; an d CT = contac t time , ranging anywher e fro m9 day s whe n R

d = 1 t o u

p t o 36 5 day s whe n Rd > 1 . Releas e Value s calculate d fo r the ingestio n o f wate r ar e presente d i n Appendi xE . Again , al l o f the wate r ingestio n releas e value s i n the exhibi t ar e fo r the ingestio n o f groun d water , becaus e the surfac e wate r releas eP.3 7

4- 9 value s ar e neve r the mos t limitin g (i.e. , neve r affec t the RQs ) fo r an y radionuclide . The releas e value s note d i n Appendi xE a s being "ver ylarge " ar e for radionuclide s tha t have a larg e retardatio n facto r an d relativel y shor t half-life . Fo r thes e nuclides , the tim e o f trave l t o a wel l 3 0 meter s awa yi s sufficientl ylon g tha t muc ho f the nuclid e i s los t du e t o radioactive decay . Whil e releas e value s wer e no t calculate d i n thes e cases , i t i s recognize d tha t the ywoul d b e "ver

ylarge " relative t o th e releas e value s fo r the othe r pathway s and , therefore , woul d no t serve a s the basi s fo r RQs . 4. 4 RELEAS E VALUE S FO RTHE INGESTIO

N OF FOO D EP Aconsidere d a variet yo f exposur e scenario s involving the ingestion o f contaminate d food . Th e scenario s analyze d wer e for :

o the ingestion o f vegetable s contaminate d b ythe airborn e depositio n o f radionuclides ; o the ingestion o f vegetable s irrigated wit h radionuclide-bearing groun d water ; an

d
o th e ingestion o f anima l product s (mea t an d milk ) fro

m livestoc k tha t ingested contaminate d forage . Althoughi t i s recognize d tha t an yo f thes e exposur e scenario s coul d b e the mos t critica l (i.e. , resul t i n the greates t huma n exposures ) depending o n the actua l circumstance s surrounding a release , EP Adecide d t o bas e releas e value s fo r th

e ingestion o f food solel yo n the scenari o involving the ingestion o f vegetable s contaminate d b yairborn e deposition . The irrigatio n pathwa ywa s rejecte d because , base d o n the define d exposur e scenarios , the direc t consumptio n o f contaminate d groun d wate r woul d resul t i n greate r exposure s than the ingestion o f vegetable s irrigate d wit hcontaminate d groun d water . I n othe r words , releas e value s calculate d fo r the ingestion o f groun d wate r woul d always b e lowe r (unde r th e condition s assumed ) than releas e value s fo r the ingestion o f vegetable s contaminate d throug hirrigation . Ingestion o f contaminate d mil k and/o r mea t wa s rejecte d becaus e radionuclid e concentration s foun d i n mil k o r mea t ar e highl ydependen t upo n element-specifi c transfe r factor s betwee n forag e an d anima l products . Transfe r factor s ar e availabl e fo r onl ya fe

welement s and , a s such , an acceptabl e mode l coul d no t be applie d t o mos t radionuclides . The model s use d t o evaluat e eacho f thes e pathway s an d the reason s fo r choosing the vegetabl e ingestion pathwa yar e describe d i n detai l i n Appendi xC o f thi s report . The metho d fo r calculating releas e value s fo r th

e ingestion o f vegetable s contaminate d b yairborn e depositio n i s summarize d below . Conceptually , releas e value s fo r the ingestion o f vegetable s contaminate d b yairborne depositio n ar e calculate d fo r a scenari o define d b ythe following assumptions : (1 ) radionuclide s ar e release d t o th e ai r ove r a 24-hour perio d fro ma poin t sourc e a t groun d level ; (2 ) the radionuclid e disperse s i n ai r i n a gaussian plume ; (3 ) a portio n o f the airborn e radionuclide s deposit s o n a vegetabl e cro

p locate d 3 0 meter s downwin d o n the firs t da

yo f the growing season ; (4 ) an individua l ingest s one day' s wort ho f vegetable s fro mthe contaminate d cro

p fo r a perio d o f 6 0 days , the entir e lengt ho f the growing season ; an

d (5 ) the vegetable s ar e no t washe d o r store d afte r harvest , bu tP.3 8

4-1 0
rathe r ar e ingeste d directly . EP Arecognize s tha t thi s scenari o i s ver y conservative , particularl ywit hrespec t t o the assumptio n o f a vegetabl e crop being locate d jus t 3 0 meter s downwin d fro mthe poin t o f release . Thes e conservative assumptions , a s wel l a s the equation s use d t o mode l thi s pathway , ten d t o exaggerat e the importanc e o f the vegetabl e ingestio n pathwa yrelative t o the othe r pathways . Basing the releas e value s o n thes e conservative assumptions , however , assure s tha t ther e wil l b e timel yreporting fo r mos t conceivabl e releas e situations . The vegetabl e ingestio n releas e value s represen t the quantit yo f radionuclide s that , i f release d unde r the se t o f assumption s outline d above , coul d resul t i n an expose d individua l receiving an effective dose-equivalen t o f 50 0 millirem . Th e basi c equatio n use d t o calculat e thes e releas e value s is : (5 ) Vegetabl e Ingestio n

Releas e Valu e = ALI/((10)*(DF)*(FC)*(CT)*(R)*( 1 x10 6 ) ) (i n curies ) where : AL I = Annua l Limi t o f Intak e fo r ingestion (microcuries) ;

1 0 = Facto r t o adjus t the dose-equivalen t limi t buil t int o the ALI , 5 rem , t o a limi t o f 0. 5 re m(dimensionless) ; D F = Dilutio n facto r accounting fo r the transfe r o f radionuclide s fro

mai r t o vegetatio n (curies/kg o f vegetable s a t the poin t o f exposur e pe r curi e release d to . the atmosphere) ; FC = Foo d (i.e. , leafyvegetable ) consumptio n rat e o f referenc e ma n (0.17 5 kg/day) ; C T = Contac t time , o r the numbe r o f day s ove r whic h contaminate d vegetable s ar e ingested ; R= Airborn e releas e fractio n (dimensionless) ; an d 1 x10 ° = Conversio n facto r betwee n microcurie s an d curies . The ALI s use d i n Equatio n (5 ) wer e taken fro mICRP Publicatio n 30 . Whe n mor e than one ingestio n AL I wa s reporte d fo r a singl e radionuclide , th e lowes t on e wa s used . Selecting the lowes t AL I assure s tha t the releas e value s ar e base d o n the mos t hazardou s chemica l for mo f a radionuclide . A s describe d i n detai l i n Appendi xC , the dilutio n facto r i s base d o n th e concentratio n o f radionuclide s i n ai r ove r a vegetabl e cro p an d the exten t t o whic hthe radionuclide s deposi t o n an d i n the vegetables . The atmospheri c relative concentratio n (X/Q ) valu e use d i n the inhalation pathwa yequatio n wa s use d t o estimat e the concentratio n i n ai r a t a poin t 3 0 meter s downwin d fro m the poin t o f release . Amode l presente d b ythe NCR P i n NCRP CommentaryNo .P.3 9

4-1 1
3 1 1 wa s use d t o determin e the transfe r o f radionuclide s fro mai r t o vegetation . Thi s mode l account s fo r the radionuclid e depositio n velocity , radionuclid e los s du e t o weathering , uptak e fro msoil , tim

e perio d tha t th

e crop s ar e expose d t o contamination , an d severa l othe r factors . The valu e use d fo r the food consumptio n rat e i s the rat e tha t leafy vegetable s ar e consume d b yreferenc e man . The selecte d value , 0.17 5 kg/day , i s use d commonl yi n radiologica l assessments . The airborn e releas e fraction , R , represent s the portio n o f a release d radionuclid e tha t actuall y become s airborne . The value s use d fo r Ri n Equatio n (5 ) ar e th e sam e one s tha t ar e use d i n the calculatio n o f inhalatio n releas e value s (se e Section 4.2) , an

d ar e base d o n the value s presente d i n the Nuclea r Regulator y Commission' s NUREG-114 0 fo r sever e acciden t situations . The value s use d ar e show n i n Exhibi t A- l i n Appendi xA . Althoughi t wa s assume d tha t the expose d individua l ingest s contaminate d vegetable s fo r 6 0 days , thi s tim e perio d wa s adjuste d fo r radioactive deca y an d weathering los s t o derive an equivalen t contac t tim e (CT ) for us e i n Equatio n (5) . The dilutio n facto r outline d above , whe n applie d t o th e quantityo f radionuclid e release d i n one day , yield s th e concentratio n o f radionuclid e i n an

d o n vegetatio n afte r one day . Ove r th e nex t 6 0 days tha t a perso n i s assume d t o inges t the vegetables , the radionuclid e concentratio n wil l progressivel ydecreas e a s mor e an d mor e o f the contaminatio n i s los t due t o radioactive deca yan d weathering . Therefore , the valu e use d fo r CT i n Equatio n (5 ) i s derive d using an exponentia l deca yexpressio n tha t account s fo r the amoun t o f radionuclid e los t ove r the 6 0 da yingestion period . A differen t CT valu e i s calculate d fo r eac hradionuclid e a s a function o f th e radionuclide' s half-life . The expressio n use d t o calculat e CT i s presente d i n Appendi xC . Finally , no radioactive deca yi s considere d during the perio d o f releas e an d deposition . Thi s approac hi s taken becaus e deca yduring airborne transpor t t o an

d depositio n o n vegetatio n locate d 3 0 meter s awa ywoul d be negligibl e fo r mos t radionuclides . The releas e value s calculate d using Equatio n (5 ) ar e presente d i n Appendi xE unde r the heading "Ingestion (Food). "

•'-"'-Nationa

l Counci l o n Radiatio n Protectio n an d Measurements , Screenin g Technique s fo r Determining Complianc e wit hEnvironmenta l Standards : Release s o f Radionuclide s t o the Atmosphere . NCR P Commentar yNo . 3 , 1986 .

- 1 o •""^U.S . Nuclea r Regulator yCommission , Calculatio n o f Annua l Dose s t o Ma n fro mRoutin e Release s o f Reacto r Effluent s fo r the Purpos e o f Evaluatin g Complianc e wit h1 0 CFRPar t 50 . Appendi xI . RegulatoryGuid e 1.109 , Revisio n 1 , Octobe r 1977 . Tabl e E- 5 (page 1.109-40 ) o f thi s Guid e recommends , i n lie u o f site-specifi c data , us e o f a leaf yvegetabl e consumptio n rat e o f 6 4 kg/yea r t o asses s the dose s t o maximall yexpose d adults . Fo r the purpose s o f thi s analysis , 6 4 kg/yea r wa s divide d b y36 5 t o obtai n 0.17 5 kg/day .P.4 0

4-1 2
4. 5 RELEAS E VALUE S FO RTH E DIRECT EXPOSUR E PATHWA

Y The methodolog

yfo r determining releas e value s fo r direc t exposur e t o radiatio n depend s o n the for mo f th e radionuclid e released . Fo r certai n nobl e ga s isotopes , the releas e value s ar e base d o n exposur e due t o tota l bod y submersio n i n a radioactive ga s cloud . Fo r al l othe r radionuclides , releas e value s ar e base d o n the quantityo f radioactivit yreceive d b yan individua l expose d t o a poin t sourc e o f radiation . The calculatio n o f releas e value s fo r poin t sourc e an

d nobl e ga s release s ar e summarize d belo wan d describe d i n greate r detai l i n Appendi xD o f thi s report . The releas e value s calculate d fo r direc t exposure s ar e presente d i n Appendi xE . 4.5. 1 Direc t Exposure Fro m a Point Sourc e A s i s the cas e fo r the othe r exposur e pathwa yanalyses , the calculatio n o f direc t exposur e releas e value s assume s tha t a perso n 3 0 meter s fro mth e poin t o f a radionuclid e releas e receive s an effective dose-equivalen t o f 50 0 millirem . Assuming tha t a perso n i s 3 0 meter s fro mthe poin t o f release , direc t exposur e hazard s ar e associate d almos t entirel ywit hneutron s an d gamma rays ; the rang e i n ai r o f al l alpha particle s an d mos t bet a particle s i s far les s than 3 0 meters . 3 Therefore , t o determin e releas e value s fo r direc t exposure s t o a poin t source , EP Aconsidere d bot hthe exposur e t o neutron s an d the exposur e t o gamm a rays . O f the 75 7 radionuclide s liste d i n ICRP Publicatio n 30 , 2 4 deca ya t leas t par t o f the tim

e b yspontaneou s fissio n an d emi t neutrons . A s describe d i n Sectio n D.1. 2 o f Appendi xD , the Agencycalculate d releas e value s fo r thes e nuclide s base d o n direc t exposur e t o neutrons . The exposur e scenari o assume d i n the calculatio n o f thes e releas e value s i s simila r t o tha t assume d fo r the othe r exposur e pathways , i.e. , a perso n stand s 3 0 meter s fro ma poin t sourc e fo r 2 4 hour s an

d receive s a whol e bod ydose-equivalen t o f 50 0 millirem . I n al l cases , the direc t epxosur e releas e value s fo r the neutron-emitting isotope s wer e les s than the corresponding releas e value s calculate d fo r the inhalatio n pathway . The usua l mod e o f deca yfor th

e 2 4 isotope s (certai n uraniu misotope s an

d isotope s o f som

e transurani c elements ) i s the emissio n o f alpha particles , whic hcan caus e significan t biologica l damag e whe n emitte d inside th

e body . Unde r the exposur e conditon s assumed , therefore , the RQ s fo r thes e isotope s woul d no t b e base d o n th e direc t exposur e t o neutron s an d thi s exposur e pathwa

ywa s droppe d fro

mfurthe r consideration .

J

3 Fo r example , a 1 0 MeV alpha o r bet a particl e woul d b e an extremel y energeti c particle . The mea n rang e o f a 1 0 Me V alpha particl e i n ai r i s les s than 1 5 centimeters . Bet a particle s typicall yrang e i n energ ybetwee n 0.0 4 an d 6 MeV , althoug

hther e ar e a fewradionuclide s whic hemi t bet a particle s wit hhighe r energie s (e.g. , the maximu mbet a particl e energ yfo r carbon-1 5 an

d bromine-8 7 i s abou t 1 0 an d 8 MeV , respectively) . The mea n rang e o f a 6 MeV bet a particl e i n ai r i s onl yabou t 2 0 meter s an d thes e highenerg

ybet a particle s ar e veryrare . Therefore , althoug hther e ar e a fewnuclide s fo r whic hbet a particle s can conceivabl ytrave l approximatel y3 0 meter s i n air , exposure s a t thi s distanc e ar e fo r the mos t par t onl ya concern fo r gamm a ray s an d neutrons .P.4 1

4-1 3

Th e metho d use d b yth e Agenc yfo r calculatin g direc t exposur e releas e value s fro m

a fixe d poin t sourc e o f gamm a ray s i s adapte d fro mth e Healt h Physic s an d Radiologica l Healt hHandbook 1 ^ an d include s gamm a ra yattenuatio n i n ai r betwee n th e sourc e an d th e receptor . I t reflect s th e effect s o f gamm a radiatio n an d ca n b e simplified , a s show n i n Appendi xD , t o yiel d th e followin g equation : (6 ) Direct Exposur e Releas e Valu e = ((6.41xlO- 5 )*(Dn)*(S 2 ))/((E 1 )*(u a )*(T)*(exp(-100u a S)) ) where : D n = Dose-equivalen t i n re m(0. 5 re mo r 50 0 millirem) ;

S = Distanc e fro mth e releas e (3 0 m) ; E ^ = Th e sumo f th e product s o f th e gamm a rayenergie s an d th e gamm a ra yfraction s (MeV) ;

u a = Linea r energ yabsorptio n coefficien t fo r gamm a ray s i n ai r (cm' 1 ) ; T = Duratio n o f exposur e (i n hours) ; an d exp(-100u a S ) = Attenuatio n facto r (dimensionless) . Th e direc t exposur e releas e valu e wa s calculate d usin g Equatio n (6 ) fo r ever yradionuclid e o f interes t tha t emit s a gamm a ray . Fo r manyo f thes e radionuclides , gamm a ray s ar e not emitte d ever ytim e tha t th e nuclid e decay s (i.e. , disintegrates) . I n addition , a gamm a ra ytha t i s emitte d fro ma give n radionuclid e doe s no t necessaril yalway s hav e th e sam e energ ylevel . Thi s phenomeno n i s illustrate d i n Exhibi t 4-1 . A s show n i n thi s exhibit , ever y tim e argon-4 1 disintegrates , i t emit s a gamm a ra ywit ha n energ yleve l o f 1. 3 MeV . Krypton-8 5 emit s a gamm a ra yfo r onl ya smal l fractio n o f it s disintegration s (0. 4 percent) , whil e severa l differen t gamma s wit hdifferen t energie s ar e emitte d a t differen t frequencie s b ymolybdenum-99 . T o accoun t fo r thes e variou s gamm a ra yenergie s an d fraction s whe n usin g Equatio n (6) , th e energ yleve l (E. . ) fo r a give n radionuclid e wa s derive d b y takin g th e sumo f th e product s o f th e gamm a ra yenergie s an d th e gamm a ra y fractions . Fo r example , th e E valu e use d fo r argon-4 1 wa s 1. 3 Me V an d th e E 1 valu e use d fo r molybdenum-9 9 wa s 0.14 . Thi s approac hconsider s al l o f th e gamm a ray s fo r a give n radionuclid e an d account s fo r th e fractio n o f tim e tha t suc ha gamm a ra yi s actuall yemitted . Th e linea r energ yabsorptio n coefficien t fo r gamm a ray s i n ai r ( u ) varie s wit hth e gamm a ra yenergy . Whe n th e gamm a ra yenerg yi s 1 MeV , th e

^Nucleo n Lecter n Associates , Th e Healt hPhysic s an d Radiologica l Healt h Handbook . 1984 , p.41 .P.4 2

4-1 4

EXHIBI T 4- 1 GAMM A RA YENERGIES , GAMM

A RA Y FRACTIONS , AN

DENERG YLEVEL S FO

RSELECTE

DRADIONUCLIDE S

Radionuclid e Gamm a Ra y Energy , E (MeV ) Gamm

a Ray Fractio n (percent ) Gamm

a Ray Fractio n Time s E (MeV ) Radionuclid e

Energ yLevel , E l (MeV ) Argon-4 1 Krypton-8 5 Molybdenum-9 9 1. 3 0.51 3 0.04 1 0.14 1 0.18 1 0.36 6 0.74 0 0.77 7 0.82 2 10 0

0.4 3 1 5 6 1 1 2 4 0. 1 1. 3

2.2x1 0 4.1x1 0 70.5x10 ' 108.6x10 " 36.6x10 " 88.8x1 0 310.8x1 0 8.2x1 0 - 4

- 4 1. 3

2.2x1 0

0.1 4

Source : Nationa l Counci l o n Radiatio n Protectio n an d Measurements , A Handboo k o f Radioactivit yMeasuremen t Procedures . NCR P Repor t No . 58 . Washington , D.C . Novembe r 1978 .P.4 3

4-1 5 linea r energ

yabsorptio n coefficien t i s 3. 7 x1 0 /cm. ^ Fo r gamm a rays wit h energie s betwee n 0.0 7 MeV an d 2 MeV , th

e absorptio n coefficien t wil l varyfro m 3. 7 x1 0 b

yplu s o r minu s 1 5 percent . Becaus e the variatio n i s s o slight , fo r purpose s o f calculating th e direc t exposur e releas e values , EP Aassume d tha t the absorptio n coefficien t i s 3. 7 x1 0 /cmfo r al l radionuclide s o f concern . The duratio n o f exposure , T , i s assume d t o b e 2 4 hours . Becaus e o f radioactive decay , however , i t i s recognize d tha t a perso n woul d be exposed t o successivel ysmalle r quantitie s o f radioactivit yove r thi s period o f exposure . T o determin e an individual' s cumulative exposur e ove r the 24-hour period , therefore , a differen t exposur e duratio n i s calculate d fo r eachradionuclid e using an integrated deca yexpressio n tha t account s fo r the exten t o f radioactive deca

ytha t woul d occur ove r 2 4 hours . Thi s expression i s a s follows : (7 ) T = 1

- exp(-Xt )



## X where : X = 0.693/t-]/2 , wher et]/ 2i s th eradionuclid ehalf-lif ei ndays. ;

an d t = 1 day
. Multiplying the T derive d fro mEquatio n (7 ) b

y2 4 (i.e. , 2 4 hours/day ) yield s a duratio n o f exposur e i n unit s o f hours , whic hcan b e plugge d int o Equatio n (6) . Whil e de c a

yove r the perio d o f exposur e i s take n int o accoun t throug h Equatio n (7) , the Agencydecide d t o ignor e the effect s o f radioactive deca y ove r the perio d o f releas e an d the perio d o f transpor t t o a receptor . The releas e i s assume d conservativel yt o b e instantaneous , suchtha t no deca yove r th e releas e perio d woul d occur . I t i s impossibl e t o pu t bound s on th e length o f time necessaryfo r a perso n t o come int o contac t wit hdirec t radiation fro m a release d poin t source . The Agencyconservativel yassumed , therefore , tha t no deca yoccur s ove r thi s "transpor t time. " Substituting al l o f the value s outline d above int o Equation (6) , the equatio n "simplifie s to : (8 ) Direc t Exposur e = 25. 1 Releas e Valu e (E 1 )*(t 1 / 2 " t l/ 2 exp(-0.693/tw 2 ) ) Direc t exposur e releas e value s calculate d fo r the radionuclide s tha t emi t gamm a ray s ar e presente d i n Appendi xE o f thi s report .

J

-- > Nucleo n Lectern Associates , The Healt hPhysic s an d Radiologica l Healt h Handbook . 1984 , p.41 .P.4 4

4-1 6
4.5. 2 Submersio

ni na Radioactiv

e Clou do f Nobl e Ga s Becaus e the nobl e gase s argon , krypton , an d xeno n ar e chemicall yver y stable , theyar e no t likel yt o for msoli d o r liqui d compound s tha t can be ingested . Also , becaus e theyar e relativel yinsolubl e i n bloo d an d ar e displace d easil yb

ygase s mor e commo n i n ai r suc ha s oxyge n an d nitrogen , thes e nobl e gase s ar e no t incorporate d readil yint o the bod yafte r inhalation . A s a result , ingestio n an d inhalatio n ar e no t significan t exposur e pathway s an d ALI s fo r ingestio n an d inhalatio n wer e no t develope d b yth e ICRP for mos t nobl e gases . However , submersio n i n a radioactive clou d can caus e a significan t whol e bod ydos e du e t o direc t exposure . Therefore , direc t exposur e releas e value s fo r argon , krypton , an d xeno n wer e derive d assuming tha t an expose d individua l i s submerge d i n a cloud o f the ga s 3 0 meter s fro m the releas e point . Argon , krypton , an

d xeno n ar e the onl ynobl e gase s whos e releas e value s ar e calculate d base d o n tota l submersio n i n a cloud . The nobl e gase s heliu m an d neo n do no t for

misotope s wit hhal f live s longe r than a fewseconds . ALI s fo r thes e isotope s hav e no t bee n develope d and , therefore , no releas e value s hav e bee n calculated . The nobl e ga s rado n ha s tw o isotope s (radon-22 0 an d radon-222 ) wit hinhalatio n ALIs . Inhalatio n o f radon , rathe r than submersio n i n a cloud , wa s considere d becaus e the critica l healt heffec t associate d wit h exposur e t o rado n i s cause d b yinhalatio n o f it s short-live d deca yproducts . EP Arecognize s tha t a cloud o f non-nobl e gase s can als o contribut e t o a dos e throughthe submersion-in-a-cloud pathway , i n the sam e manne r a s nobl e gases . However , i t i s generall yrecognize d that , i n thi s situation , th e inhalation pathwayi s controlling . Therefore , direc t exposur e b ysubmersio n i n a clou d wa s analyze d fo r onl yargon , krypton , an d xenon . Adifferen t equatio n fo r the calculatio n o f direc t exposur e releas e value s i s appropriat e fo r radioactive nobl e gase s becaus e submersio n i n a cloud result s i n an integrate d dos e fro mal l direction s a t varying distance s fro mthe body . The direc t exposur e releas e value s fo r submersio n i n a radioactive clou

d o f a nobl e ga s ar e derive d throug hthe followin

g equation. " (9 ) Direc t Exposur e , Releas e Valu e = ((83)*(DAC)*(T))/((10)*(X/Q)*(lxl 0 ) ) where :
o

DA C = Derive d Airborn e Concentratio n (microcuries/cm J ) ; T - = Duratio n o f Exposur e ( 1 day) ;

Thi s equatio n i s derive d fro man equatio n foun

d i n the Annal s o f the ICRP . Publicatio n No . 30 , Par t 1 , Volume 2 , No . 3/4 , 1979 , pp . 1 0 an d 47 . Se e Appendi xD fo r mor e detials .4-1 7 X/ Q - = Atmospheri c Relative Concentratio n Valu e a t 3 0 meter s (8.4x1 0 day/cm 3 ) ; an d 1x1 0 = Conversio n facto r betwee n microcurie s an d curies . The DA C valu e specifie s the airborn e concentratio n tha t woul d resul t i n a 5 re mwhol e bod

ydose-equivalen t fo r a 200 0 hour exposur e period . T o adjus t th e airborn e concentratio n fro ma 200 0 hou r t o a 2 4 hour exposur e period , the DA C valu e i n Equatio n (9 ) i s multiple d b y8 3 (i.e. , 200 0 hours/2 4 hours). 1 7 The facto r o f 1 0 i n the denominato r o f Equatio n (9 ) convert s the 5 re mwhol e bod

y limi t fo r occupationa l exposur e t o the 0. 5 re m(50 0 millirem ) limi t fo r exposur e t o the genera l public . X/ Q i s the ground-leve l concentratio n valu e 3 0 meter s fro

mthe releas e poin t (se e Sectio n 4. 2 above an d Appendi xAfo r furthe r discussio n o f X/Q) . The effect s o f radioactive dea yar e ignore d i n Equatio n (9) . Thi s pathwa ymode l consider s exposur e t o an airborn e plume o f radionuclide s jus t 3 0 meter s fro

mthe poin t o f release . The tim e o f transpor t t o th e exposur e poin t i s shor t (3 0 second s assuming a 1 meter/secon d wind) , an

d deca yove r thi s perio d woul d b e negligibl e fo r mos t radionuclides . Althoughthe perio d o f exposur e i s assume d t o b e on e day , an individua l woul d no t b e expose d t o the sam e radionuclide s ove r thi s period . A s the plume passe s the poin t o f exposure , "new " radionuclide s jus t release d woul d approac hthe individua l whil e "old " one s woul d mov e farthe r downwind . Again , becaus e the tim e o f trave l t o a poin t 3 0 meter s fro mthe poin t o f releas e i s short , the "new " radionuclide s tha t the perso n i s repeatedl yexpose d t o woul d no t hav e decaye d significantly . Fo r thi s reason , deca yove r the perio d o f exposur e wa s ignored . The expressio n fo r determining th e releas e valu e fo r th e direc t exposur e pathwa ydue t o submersio n i n a clou d o f radioactive nobl e ga s can be simplifie d b

ymultiplying the number s i n the numerato r an d denominator . Equatio n (9 ) simplifie s to :

(10 ) Direc t Exposur e Releas e Valu e = DAC/(lxl0 " ) The direc t exposur e releas e value s fo r argon , krypton , an d xeno n can b e foun d a t the en

d o f thi s repor t i n Appendi xE .

1 'I f a differen t exposur e perio d wa s assumed , th e DA C valu e i n Equatio n (9 ) woul d hav e t o b e multiplie d b ya numbe r differen t than 83 . Fo r example , i f an exposur e perio d o f 1 2 hour s wa s assumed , the DA C woul d have t o b e multiplie d b

y16 6 (2000/12) . . Thi s chang e woul d hav e t o b e accompanie d wit ha corresponding chang e i n T ; the valu e fo r T woul d b e 0. 5 da yrathe r than 1 day . Fo r thi s reason , the direc t exposur e releas e valu e woul d no t increas e wit h longe r exposur e period s a s i s implied b yEquatio n (9 ) (on

e woul d expec t intuitivel ytha t the releas e valu e an d exposur e duratio n woul d b e inversel y related) .

### 4. 6 4-1 8

ASSIGNMENT O F RADIONUCLIDE S T O R Q GROUP S P.4 6

Appendi xE a t the en d o f thi s repor t display s th e four releas e value s calculate d fo r eac hradionuclide . Th e lowes t releas e valu e fo r each radionuclid e ha s an asteris k besid e it . The lowes t releas e value s rang e fro m ove r 100,00 0 curie s t o approximatel y0.00 1 curie . Fo r administrative feasibilit yan

d simplicity , the Agencydecide d t o assign the radionuclide s t o one o f seve n distinc t group s identifie d b yspecifi c fina l RQs . Each radionuclid e i s assigne d a fina l R Q o f 0.00 1 curie , 0.0 1 curie , 0. 1 curie , 1 curie , 1 0 curies , 10 0 curies , o r 100 0 curies . Assignmen t o f an adjuste d RQ t o a particula r radionuclid e wa s mad e b yexamining the lowes t releas e valu e for eac hradionuclid e an d rounding tha t valu e dow n t o the neares t RQ group . The 75 7 radionuclide s wit hRQ s ar e represente d a s follows : o 7 radionuclide s (1% ) hav e lowes t releas e value s les s than 0.0 1 curi e and , therefore , hav e an adjuste d RQ o f 0.00 1 curie ; o 2 9 radionuclide s (4% ) hav e lowes t releas e value s greate r than o r equa l t o 0.0 1 curi e bu t les s than 0. 1 curi e and , therefore , hav e an adjuste d RQ o f 0.0 1 curie ; o 2 9 radionuclide s (4% ) hav e lowes t releas e value s greate r than o r equa l t o 0. 1 curi e bu t les s than 1 curi e and , therefore , hav e an RQ o f 0. 1 curie ; o 3 2 radionuclide s (4% ) hav e lowes t releas e value s greate r than o r equa l t o 1 curi e bu t les s than 1 0 curie s and , therefore , hav e an RQ o f 1 curie ; o 22 0 radionuclide s (29% ) hav e lowes t releas e value s greate r than o r equa l t o 1 0 curie s bu t les s than 10 0 curie s and , therefor e hav e an R Q o f 1 0 curies ; o 23 5 radionuclide s (31% ) hav e lowes t releas e value s greate r than o r equa l t o 10 0 curie s bu t les s than 100 0 curie s and , therefore , hav e an adjuste d RQ o f 10 0 curies ; an

d
o 20 5 radionuclide s (27% ) hav e lowes t releas e value s greate r than o r equa l t o 100 0 curie s and , therefore , hav e an R Q o f 100 0 curies . An R Q o f 1 curi e als o i s assigne d t o al l radionuclide s no t listed i n ICRP' s Publicatio n 30 . Th e Agencybelieves , fo r thre e reasons , tha t b y establishing an RQ fo r the broad generi c clas s "radionuclides, " i t i s fulfilling the CERCL Amandat e t o protec t publi c health , welfare , an d the environment . First , a s see n above , the 1-curi e R Q i s the middl e RQ leve l an d the majorit y(91% ) o f the radionuclide s wit hpropose d RQ s hav e minimu mreleas e value s greate r than o r equa l t o 1 curie . Therefore , the generi c R Q o f 1 curi e fo r al l othe r radionuclide s (i.e. , thos e no t include d i n the lis t o f 75 7P.4 7

4-1 9 radionuclide s wit hspecifi c RQs ) i s probabl ya conservative value . Second , mos t o f the radionuclide s tha t fal l int o thi s categor yar e rare , bot hi n terms o f frequencyo f us e an d quantitie s used . Man yo f thes e nuclide s hav e bee n produce d i n onl ya fewisolated researc hproject s an d the world' s tota l quantityo f man

yi s les s than 1 curie . Therefore , release s o f radionuclide s no t listed b

yICRP Publicatio n 3 0 ar e expecte d t o b e infrequen t and , i f the y occur , ar e expecte d t o b e release d withi n an y24-hour perio d i n quantitie s smalle r than 1 curie . Finally , man yo f th e remaining radionuclide s have shor t half-live s an

d do no t deca

yint o othe r radioactive isotopes . Unde r mos t realisti c releas e situations , thes e radionuclide s woul d b e expecte d t o deca y an d virtuall ydisappea r befor e the ycoul d reachrecepto r locations . Two o r mor e radionuclide s wit hthe sam e RQ do no t reflec t a determinatio n tha t a releas e o f one wil l b e a s hazardou s a s the releas e o f another , o r eve n tha t the releas e o f one wil l b e hazardou s a t the propose d R Q leve l an d no t hazardou s belo wtha t level . The Agencyha s foun d tha t the actua l hazar d wil l varywit hthe uniqu e circumstance s o f the release , an d extensive scientifi c dat a an d analysi s woul d b e necessaryt o determine the hazar d presente d b yeach substanc e unde r a numbe r o f possibl e circumstances . Instead , th e RQ s aredesigne d t o b e a trigge r fo r notificatio n an d reflec t the Agency' s judgmen t tha t the federa l governmen t shoul d b e notifie d o f certai n release s t o whic ha federa l respons e migh t b e necessary . The reportabl e quantitie s represen t a determinatio n onl yo f possibl e o r potentia l harm , no t tha t release s o f a particula r amoun t o f a hazardou s substanc e necessaril ywil l b e harmfu l t o publi c healt ho r welfar e o r the environment . 4. 7 REPORTIN

GREQUIREMENT S FO

RMIXTURE S OF RADIONUCLIDE S Som e release s o f radioactive substance s ar e likel yt o consis t o f mixture s o f radionuclides . Thes e release s wil l be one o f tw o genera l types : mixture s o f know n compositio n o r mixture s o f unknow n composition . The convention s adopte d b

ythe Agencyi n establishing reporting requirement s fo r mixture s an d the RQ s fo r four commo n radionuclid e mixture s ar e presente d below . 4.7. 1 Mixture s o f Know nCompositio

n Reporting requirement s fo r release s involving mixture s o f know n compositio n can b e obtaine d directl yfro mthe RQ s fo r individua l constituent s o f the mixture . I f the identityan d quantityo f eac hradionuclid e involve d i n a release " even t i s known , the decisio n t o repor t a releas e mus t be mad e i n th e following manner : for eachradionuclid e i n th e mixture , the rati o betwee n th e quantityrelease d (i n curies ) an d the RQ for the radionuclid e mus t be determined . I f the su mo f the ratio s fo r al l radionuclide s i s les s than 1 , th e releas e nee d no t b e reported . I f the su mi s equa l t o o r greate r than 1 , th e releas e mus t be reporte d t o th e Nationa l Respons e Center . Fo r example , i f radionuclide s "a, " "b, " an d "c " ar e release d i n quantitie s o f Qa , Qb , an d Q c curie s i n a mixture , an d i f the RQ s ar e RQa , RQb , an d RQc , respectively , the n the quantityreleased fo r th e mixtur e doe s no t excee d the RQ an

d the releas e nee d no t be reporte d t o the Nationa l Respons e Cente r i f (Qa/RQa + Qb/RQb+ Qc/RQc ) i s les s than 1 . Thi s conventio n for handling release s o f radionuclid e mixture s i s recommende d b ythe ICRP .P.4 8

4-2 0
4.7. 2 Mixture s o f unknow nCompositio

n Reporting requirement s fo r mixture s o f unknow n compositio n canno t b e base d o n the determinatio n o f quantitie s released . Fo r mixture s o f unknow n composition , ther e ar e thre e possibilities : (1 ) the identityo f the radionuclide s involve d i s known , bu t the amount s release d o f eachar e unknown , (2 ) the identityo f the radionuclide s (or one o f the radionuclides ) i n the mixtur e i s unknown , bu t the amoun t release d i s know n i n tota l curie s pe r uni t volume o r weight , o r (3 ) the identityo f the radionuclide s involved i s unknow n an d the amoun t o f individua l radionuclide s release d i n the mixtur e i s unknow n (bu t the tota l quantityi s known) . Fo r thes e cases , the decisio n t o repor t a releas e i s mad e a s follows :

(1 ) Identityknown , bu t amoun t unknown . I f the identityo f eachradionuclid e i n the mixtur e i s know

n bu t the concentratio n o f one o r mor e o f the radionuclide s i s unknown , the RQ fo r the mixtur e shal l b e the lowes t RQ o f an y radionuclid e i n the mixture . Thi s metho d fo r determining the R Q o f a mixtur e assure s a repor t t o the Nationa l Respons e Cente r i f the tota l numbe r o f curie s involve d i n a releas e i s equa l t o o r greate r than the R Q i n curie s o f the substanc e wit hthe lowes t R Q i n the mixture .

(2 ) an d (3 ) Identityo f radionuclide(s ) i n the releas e i s unknown . I f the identityo f a radionuclid e i n a releas e i s unknow

n o r i f the identityo f one o r mor e radionuclide s i n the releas e o f a mixtur e o f radionuclide s i s unknown , th e releas e mus t b e reporte d t o the Nationa l Respons e Cente r i f the tota l releas e i s equa l t o or greate r than 1 curie , o r i f the tota l releas e i s equa l t o o r greate r than the lowes t RQ o f an yknow n radionuclid e i n the mixture , whic heve r i s lower . Establishing an R Q o f 1 curi e fo r a releas e i n whic hthe identityo f the radionuclid e o r radionuclide s involved i s unkow n i s consisten t wit hth e 1

- curi e R Q fo r the clas s o f radionuclide s fo r whic hinsufficien t dat a exis t t o extablis hindividua l RQs . The mixtur e rul e require s reporting i f the releas e equal s o r exceed s 1 curie , or , i f some componen t o f the mixtur e i s know nan d it s R Q i s les s than 1 curie , the n the tota l releas e mus t b e reporte d i f i t equal s o r exceed s the RQ o f the know n component . 4.7. 3 Commo

nRadionuclide Mixture s RQ s hav e bee n develope d fo r four commo n radionuclid e mixtures : radium-22 6 i n equilibriu mwit hit s daughters , natura l uraniu mno t i n secula r equilibriu

mwit hit s daughters , natura l uraniu mi n secula r equilibriu m wit hP.4 9

4-2 1 it s daughters , an

d natura l thoriu

mi n secula r equilibriu mwit hit s daughters . Mixe d fissio n product s ar e als o recognize d b ythe Agencya s an importan t an d commo n radionuclid e mixture . However , the Agencyi s presenting RQ s currentl y onl yfo r the individua l radionuclid e component s withi n thi s latte r mixtur e becaus e an R Q fo r mixe d fissio n product s woul d b e tim e dependent . Tha t is , a t differen t tim

e intervals , the concentratio n o f the differen t component s o f thi s mixtur e wil l b e different . I n addition , the component s o f the mixe d fissio n produc t wil l differ , depending o n the typ e o f reacto r involved i n thei r production . Therefore , severa l differen t mixe d fissio n produc t RQ s woul d nee d t o b e presented . Radium-22 6 ha s a hal f lif e o f abou t 160 0 years , substantiall ygreate r tha n the hal f live s o f it s eleve n daughters . Afte r a sufficien t perio d o f time , however , a stat e o f equilibriu mi s establishe d i n the mixtur e (know n a s secula r equilibrium) , suc htha t the activit ypresen t for eachdaughte r produc t an d the paren t radiu

mi s equal . Fo r example , i f one curi e o f radium-22 6 i s released , whe n equilibriu mi s reached , the activityleve l o f the mixtur e wil l b e 1 2 curies . Whe n radiu man d it s daughter s reachthi s stat e o f equilibrium , it s RQ i s 0.05 3 curie. 1 8 Natura l uraniu

mi s compose d o f the isotope s U-23 8 (99.2 7 percen t b y weight) , U-23 4 (0.005 7 percen t b yweight) , an

d U-23 5 (0.7 2 percen t b yweight) . Becaus e the compositio n b yweigh t o f natura l uraniu mi s known , w e can derive the activitylevel s o f eac ho f it s components . The rul e result s i n an R Q fo r natura l uranium , derive d throug hthe mixtur e rule , o f 0. 1 curie , i f the natura l uraniu

mi s no t i n equilibriu mwit hit s daughters . I f the natura l uraniu mi s i n secula r equilibriu mwit hit s daughters , the R Q derive d throug h the mixtur e rul e i s 0.05 2 curie . Natura l thoriu

mconsist s o f 10 0 percen t Th-232 . Whe n i n secula r equilibriu

mwit hit s daughters , the RQ fo r natura l thoriu mi s calculate d using the mixtur e rul e t o b e 0.01 1 curie . 4. 8 REPORTIN

GREQUIREMENT S FO

RCOMPOUND S AN

DMIXTURE S OF RADIONUCLIDE S AN D OTHE RHAZARDOU S SUBSTANCE S The fina l RQ s ar e fo r radionuclides , whic har e specie s o f atoms define d b ythei r atomi c numbe r an d mass . Thes e RQ s ar e applicabl e t o al l chemica l an d physica l forms i n whic hthe radionuclide s mayexist . EP Arecognize s tha t becaus e the radionuclid e RQ s ar e applicabl e t o al l chemica l forms , som e

- 1 Q -"-"Kaplan , I. , Nuclea r Physics . Addison-WesleyPublishing Company , Reading , Massachusetts , 1958 , p . 202 . Using the mixtur e rule , th e RQ fo r radiu mi n equilibriu

mwit hit s daughter s wa s calculate d fro mthe following formula : 1 1 1 2 1 

## = _L RQmi x 1 2 i= 1 R Q i where : RQ i i s the reportabl e quantityo f radiu mo r the daughte r o f concern .P.5 0

4-2 2
substance s containing radionuclide s wil l hav e tw o applicabl e RQs , one base d o n radiatio n hazar d an d th e othe r base d o n chemica l toxicity . I n such situations , the lowes t applicabl e RQ fo r a substanc e govern s whe n the owne r o r operato r mus t repor t the releas e t o the Nationa l Respons e Center . I n thi s way , the RQ s reflec t the relative chemica l toxicityan d radiatio n hazar d o f a substance . Fo r example , naturall yoccurring cadmiu mconsist s o f roughl y1 2 percen t cadmium-113 , a radioactive isotope , an d severa l othe r isotope s o f cadmiu mtha t ar e no t radioactive . The RQ fo r cadmiu mha s bee n finalize d a t 1 0 pound s an d the R Q fo r cadmium-113 , jus t one componen t o f naturall yoccurring cadmium , i s 0. 1 Ci . Arelease r o f cadmiu mmeta l i s require d t o repor t i f eithe r 1 0 pound s o f the meta l (i f the diameter s o f the particle s o f the release d meta l ar e les s than o r equa l t o 10 0 micrometers ) o r 0. 1 C i o f cadmium-11 3 (regardles s o f the particl e siz e o f the cadmium-113 ) i s released . I n thi s case , the R Q base d o n chemica l toxicit yi s muc hmor e limiting than the RQ base d o n radiotoxicit y( a releas e o f 1 0 pound s o f cadmiu mmeta l o r 1 0 pound s o f cadmium-11 3 constitute s fa r les s than 0. 1 Ci) . Fo r othe r materials , however , the R Q base d o n radiotoxicit yi s mor e limiting than the on e base d o n chemica l toxicity . I n bot hsituations , the lowes t RQ applicabl e t o the substanc e release d woul d be the reporting trigger . Urany l acetat e an

d urany l nitrat e ar e additiona l example s o f substance s wit htw o applicabl e RQs , one base d o n chemica l toxicityan d the othe r base d o n radiatio n hazard . Bot hsubstance s ar e specificall yliste d a s CERCL Ahazardou s substance s becaus e theyar e included unde r sectio n 31 1 o f the CWA ; however , theybot hconsis t o f abou t 6 0 percen t uranium-238 , a radionuclide . Base d o n thei r chemica l toxicity , urany l acetat e an d urany l nitrat e hav e a fina l adjuste d RQ o f 10 0 pound s (5 1 F R34534 , Septembe r 29 , 1986) . The fina l RQ for uranium-238 , base d upo n radiologica l hazard , i s 0. 1 Ci , whic hi s equivalen t t o roughl y66 0 pound s o f uranium-238 . Bot hthe 0. 1 C i RQ fo r uranium-23 8 an d th e 10 0 poun

d RQ ar e applicabl e t o release s o f urany l acetat e an d urany l nitrate , bu t the 100-poun

d RQ wil l alway s trigge r reporting firs t becaus e i t i s th e lower , mor e protective level . The R Q o f 10 0 pound s wil l assur e timel y reporting o f release s o f urany l acetat e an d urany l nitrat e fro mbot ha radiologica l hazar d an d chemica l toxicit ystandpoint .P.5 1

APPENDICE S



# IP.5 2



### APPENDI XA MODELINGTH E AIRBORNE RELEAS E AND INHALATION

O F RADIONUCLIDE S

Thi s appendi xdocument s th e mode l use d t o calculat e inhalatio n releas e value s (RVs ) whic har e a componen t i n th e adjustmen t o f radionuclid e RQs . Th e inhalatio n releas e value s represen t th e quantit yo f a-radionuclid e (inunit s o f curies ) that , i f release d int o ai r unde r a nassume d se t o f conditions , coul d resul t i n an expose d individua l receiving aneffectiv e dose-equivalen t o f 50 0 milliremthroughth e inhalatio n pathway . Th e inhalatio n RV s calculate d fo r eac hradionuclid e can b e foun d i n Appendi xE o f thi s report . Thi s appendi xi s divide d int o thre e mai nsections . Th e firs t sectio n present s th e basi c mode l use d t o calculat e inhalatio n RVs , define s th e inpu t parameters , an d discusse s th e basi c rational e underlying th e model . I nsection s A. 2 an d A.3 , th e basi s fo r tw o keyinpu t variable s use d i nth e model , th e airborn e releas e fractio nan d th e atmospheri c relativ e concentratio n value , respectively , i s presented . A. l TH E INHALATIONMODE L Radionuclide s can b e release d int o th e ai r i nsevera l differen t way s an

d a t an yrate . I n orde r t o calculat e meaningfu l releas e value s fo r th e adjustmen t o f RQs , i t i s necessaryt o us e a mode l tha t i s realisti c (i.e. , reflect s releas e an d exposur e condition s tha t mayactuall yoccur ) bu t conservativ e enought o yiel d timel yreporting fo r mos t releas e situations . Th e mode l selecte d fo r thi s purpos e assume s that : (1 ) radionuclide s ar e release d t o ai r fro ma poin t sourc e a t ground level ; (2 ) th e radionuclide s dispers e i nth e atmospher e i na gaussia nplume ; an d

A- l

### (3 ) a n individua l i s expose d a t a positio n3 0 meter s downwind

fromth e poin t o f releas e an d remain s i nth e plume centerline , th e poin t o f maximu mconcentration , fo r th e entir e releas e period . Unde r thi s se t o f conditions , th e siz e o f th e releas e i n curie s (the releas e value ) necessaryt o provid e a 50 0 millirem effectiv e dose-equivalen t t o th e expose d individua l ca nb e calculate d usin g equatio n (1) : Inhalatio n Releas e Valu e = ALI/[(10)*(R)*(X/Q)*(BR)*( 1 xIO 6 

### )] . (l ) (Ci ) where : AL I = annua l limi t o f intak e fo r inhalatio n(microcuries) ; 1 0 facto r t o conver t th e annua l limi t o f intak e whic hi s base d o n 5 remdose-equivalen t t o a worke r i n a nuclea r facilit yt o 0. 5 rem , th e Federa l Radiatio n Protectio n Guidelin e fo r exposur e t o member s o f th e genera l public ; R= airborn e releas e fraction ; X/ Q = atmospheri c relativ e concentratio nvalu e a t a positio n 3 0 meter s downwind (8. 4 x10~ 1 3 

### day/cubi c cm) ; B R= breathin g rat e fo r referenc e ma n(2. 3 xIO 7 

### cubi c cm/day) ; an

d 1 x10 s 

### conversio n facto r betwee nmicrocurie s an d curies . Th e inhalatio n ALI s use d i nth e calculation s ar e take nfro m ICRP' s Publicatio n 30 1 

### afte r bein g converte d frombecquerel s t o microcuries . Wher e mor e tha non e AL I wa s give n fo r a particula r radionuclide , th e lowes t valu e wa s use d fo r th e calculations . Thi s assure s tha t th e mos t hazardou s chemica l for mo f a radionuclid e i s use d i n th e releas e valu e calculations . internationa l Commissio no n Radiologica l Protectio n(ICRP) , "Limit s fo r Intake s o f Radionuclide s b yWorkers, " Publicatio n30 , Par t 2 , 1980 . A- 2 

# I IP.5 4



### Ther e ar e tw o importan t point s t o clarif ywit hrespec t t o equatio n (1) . First , th e mode l ignore s th e effect s o f radioactiv e decay . Thi s i s becaus e th e pathwaymode l consider s exposure s t o a n airborn e plume o f radionuclide . Ashort-live d radionuclid e coul d underg o significan t decayi f th e releas e an d exposur e period s wer e a s long a s on e day , bu t decaywoul d b e muc h les s i f a time perio d o f a fewhours , minute s o r second s wa s considered . Becaus e i t wa s no t possibl e t o establis hexac t bound s o n th e rang e o f releas e an d exposur e period s (not e tha t th e equatio n doe s no t includ e a specifi c time facto r fo r thes e periods) , th e Agenc yconservativel yassume d tha t n o decayoccur s ove r thes e periods . EPAals o ignore d decayove r th e perio d o f radionuclid e transpor t t o th e poin t o f inhalation . Thi s approac h wa s adopte d becaus e decayduring airborn e transpor t t o a recepto r 3 0 meter s downwind woul d b e negligibl e fo r mos t o f th e radionuclide s considered . Second , i t i s recognize d tha t th e poin t sourc e ground leve l releas e assume d i n th e mode l i s no t applicabl e t o al l releas e configurations . Radionuclide s ar e als o commonl yemitte d t o th e ai r fro marea l source s an d fro m raise d poin t source s suc ha s smokestacks . Example s o f area l source s includ e coa l as hpile s foun d a t coal-fire d boile r site s an d ope npi t mining operations , bot ho f whic hemi t rado nt o th e atmosphere . Apoin t sourc e releas e a t ground leve l wa s assume d i n th e mode l becaus e i t mos t closel yresemble s a n episodi c releas e fo r whic ha respons e migh t b e take n an

d becaus e i t yield s mor e conservativ e (i.e. , lower ) releas e value s tha n othe r releas e configurations . I n thi s sense , th e releas e value s calculate d unde r thes e condition s wil l assur e timel yreporting fo r mos t releas e situations . Conversely , releas e value s tha t woul d hav e bee n calculate d i f anarea l o r elevate d sourc e ha d bee n assume d woul d no t necessaril yassur e timel yreporting fo r release s fro ma poin t sourc e a t ground level . A- 3

### A . 2 EVALUATIONO F TH E RELEAS E FRACTIO N Th e releas e fraction , R , reflect s th e fractio n o f a radionuclid e releas e tha t coul d become airborn e an d b e o f respirabl e siz e (1 0 micron s i n diamete r o r less) . Th e Nuclea r RegulatoryCommissio n ha s develope d releas e fraction s fo r radionuclide s unde r acciden t conditions 2



### . Thes e releas e fraction s and th e "rational e beh-irf-them-are-summarifzectbeiow i - - Isotope s o f th e nobl e gase s argon , krypton , rado nand xeno n hav e bee n assigne d releas e fraction s o f 1. 0 becaus e the yar e alway s gase s a t roomtemperature , remai n mixe d wit hair , an d d o no t reac t chemicall yt o for mles s volatil e compounds . Th e Nuclea r RegulatoryCommissio n ha s assigne d a releas e fractio no f 0. 5 t o compound s o f hydrogen , carbon , phosphorous , sulfur , an d iodine . Compound s o f thes e element s woul d b e expecte d t o produc e les s tha n 10 0 percen t volatilize d an d respirabl e particle s o r gase s fo r th e following reasons : (1 ) some compound s o f th e element s wil l settl e ou t o n surface s an d no t b e release d t o th e atmosphere , and (2 ) som e particle s i n th e releas e ma yno t b e respirable . Compound s o f th e element s selenium , mercury , cesium , polonium , tellurium , and ruthenium , among other s ar e onl ysemi

volatil e an

d hav e bee n assigne d releas e fraction s o f 0.01 . Releas e fraction s fo r non-volatil e metal s suc ha s uranium , Plutonium , tantalum , thorium , an d americium , among others , hav e bee n se t a t 0.001 . Fo r thes e metal s o r compound s o f thes e metals , th e releas e pathwayi s no t volatilizatio nbu t entrainmen t o f particle s i n a n ai r stream . Eve nfinel yground powder s wil l 

# I 

# 1

2 

### McGuire , S.A. , " ARegulatoryAnalysi s o nEmergenc yPreparednes s fo r Fue l Cycl e and Othe r Radioactiv e Materia l Licensees, " NUREG

1140 , Jun e 1985 . A- 4P.5 6



### generall ycontai n les s tha na fewpercen t o f th e powde r i n respirabl e size . Th e fractio no f particle s o f respirabl e siz e i s kep t smal l b

yth e difficult yi nproducin g smal l particle s an d subsequentl yb

yagglomeratio n an d weathering , processe s whic h caus e micron-size d particle s t o stic k t o surfaces , t o large r particle s an

d t o themselves . Releas e fraction s fo r th e variou s element s ma yb e foun d i n Exhibi t A-l . Inhalatio n releas e fraction s wer e take n fromth e Nuclea r RegulatoryCommission' s NUREG-1140 . Wher e releas e fraction s fo r specifi c isotope s ar e show ni nNUREG-1140 , thes e wer e use d fo r al l isotope s o f th e element . Wher e NUREG-114 0 doe s no t sho wa releas e fractio nfo r a specifi c elemen t o r isotope , th e releas e fraction s wer e derive d b yreferenc e t o statement s a t th e en d o f th e tabl e recommending a releas e fractio no f 0.0 1 fo r "an yothe r beta-gamma emitter " an d a releas e fractio no f 0.00 1 fo r "an yothe r alph a emitter. "

A- 5•*) w



### a. c 

# y i- i o H -* d 

### w c r P d B wa

p - • < M 3 0 1 oi oi • o i r ti t N J (D O U l P - 0 1 •C- 3 P B P - d 

### o o

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### o c r to 3 * l i o B o ( D ca r tp - p 

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# i B P d B t d 0

0 !- < P o B p 3 (D ( 0 B d r t 3 * 0 3 fl> 

# i 0 0 a > 0 0•-< 1 ( D r o p- *

_P v o d 00 ( - l i P 

# i > i n r t ( - r t P 3 ( D > > 01 i Q a >o 3 3 p o > 3 r t P B O 3 • i p o d B p 3 > O r t p 3 P d B 

### w p a > 3 a > 3 r t

0 0 X * I r o u i o



# H M W d - i WOOOOOOOOOOOO00000 0 0000>>>CO>> >

•n^BdoiiMoi © H I » a i i H - I D ^turtcoiicrBi- o > i 

### a . W 

# 5 ! H 0 0 H l-

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O O O o o H P - * o o OOOOOOOOOOO O O U l o o o o o P - H * o o o o p - * (D

r t o ® 3 ^ 3 0 1

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P - o * H * * oooo o p > O P - O H * P - H o o OOO O O P " P " P OOOO O P - O H O P - * H P - * » * * * O O M O O

Op P i r t 3 - O 01

• d 3 * o 

# 2 0 1 P >

rP . P - o 0 1 9 p - 5 5 P - O 

### cr p m t , m- \ mm\ P - (t ) ( D o » d Wr t <t > d P *3 S

o O P * Om » < t r p . ( D 3 

### S 2S S I Dmmn i i O d 

# 3 3 3 C L i Q (D 0 ) P " 3 I D fl> P - < 01 d p - rn a

3 I D 0 1 r t ( D r t p t" 1 t" 1 I D P i p> p . 3 el s ' P > 3 

### § « H H • i i i i i

• d 3 r t O 3 n H ffi

O 3 • < p , Q, Q , p . p - p - i i P - 3 d o 

# g ( D B - 3

I D 3 O P

> P -i- b B 3 p -P O ( D

P > 3 Q C l p i P i P * P . P - O •x j hr )

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-2«TJ502a:2: !z! 3!WSl?St H ^t- , « ^ H ' - , H w w r tDiCncrp- , OP.O«-5P.3«i3dtrpiiia)i i 3 o C O X > n d ci

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o o 3 r t

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o P 1 * ooo o ooooo o o o M P- * 

### ooooooooo o

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### o a t rt»_ p i 0 1 

### ooo o HP - OH P- * OOOOO O HHOP- HH H* * * * O O O HO OO OOOO O P - P- P

- HP 1 * * *

### EXHIBI T A- l (Cont. ) P.5 9



### Elemen t Plutoniu

m Poloniu m Potassiu

m Praseodymiu

m Promethiu

m Protactiniu

m Radiu m Rado n Rheniu m Rhodiu m Rubidiu m Rutheniu

m Samariu m Scandiu m Seleniu m Silico n Silve r Sodiu m Strontiu

m Sulfu r Tantalu m Technetiu

m Telluriu

m Terbiu m Thalliu m Thoriu m Thuliu m Ti n Titaniu m Symbo l P u P o K P r P m P a R a Rn R e Rh Rb R u Sm S c S e S i Ag Na S r S T a T c T e Tb T l Th T m S n T i Releas e Fractio n (R ) 0.00 1 0.0 1 0.0 1 0.01 * 0.0 1 0.00 1 0.00 1 1. 0 0.01 * 0.01 * 0.0 1 0.0 1 0.0 1 0.0 1 0.0 1 0.01 * 0.0 1 0.0 1 0.0 1 0. 5 0.00 1 - 0.0 1 0.0 1 0.0 1 0.0 1 0.00 1 0.0 1 0.0 1 0.0 1

A- 8

### EXHIBI T A- l (Cont. ) P.6 0



### Elemen t Tungste n Uraniu m Vanadiu m Xeno n Ytterbiu

m Yttriu m Zin c Zirconiu

m Symbo l W U V

—X e - Yb Y Z n Z r Releas e

Fractio n(R ) 0.0 1 0.00 1 0.0 1 "-*

- - 1. 0
_

0.0 1 0.0 1 0.0 1 0.0 1

* Indicate s tha t th e releas e fractio ni s base d o nth e NUREG-114 0 releas e fractio nfo r "an yothe r beta-gamma emitter. "

* * Indicate s tha t th e releas e fractio ni s base d o nth e NUREG-114 0 releas e fractio nfo r "an yothe r alpha emitter. "

Source : McGuire , S.A. , " ARegulatoryAnalysi s o n Emergenc y

Preparednes s fo r Fue l Cycl e an d Othe r Radioactiv e Materia l Licensees, " NUREG-1140 .



# I I A- 9P.6 1



### A . 3 DERIVATIONO F TH E ATMOSPHERI C RELATIVE CONCENTRATIONVALU E I n calculatin g inhalatio nreleas e values , i t i s necessary t o us e atmospheri c dispersio nmodeling t o estimat e th e fractio n o f a releas e whic hmigh t b e encountere d b yan individual . Th e atmospheri c dispersio n paramete r neede d i nequatio n (1 ) i s th e atmospheri c relativ e concentratio n value , Ch i ove r Q (X/Q) . Th e valu e use d fo r X/ Q wa s take nfro m Exhibi t A-2 , whic hi s a n extrapolatio n o f th e graphi n Exhibi t A-3. 3 

### Exhibi t A- 3 plot s Xu/ Q pe r squar e mete r versu s distanc e fromth e sourc e i n kilometer s fo r release s varyin g i n heigh t fro mground leve l (th e uppermos t lin e i n th e plot ) t o a heigh t o f 30 0 meters . Th e symbo l u i n Xu/ Q stand s fo r wind spee d i n meter s pe r second . Xu/ Q i s plotte d s o tha t a valu e fo r X/ Q ca n b e derive d fo r an y- wind spee d simpl yb ydividing th e valu e foun d i n th e plo t b

yth e desire d wind speed . I n thi s analysis , a wind spee d o f 1 mete r pe r second i s used , yieldin g a X/ Q i nunit s o f second s pe r cubi c meter . Fo r th e purpos e o f calculating RQs , some conservativ e assumption s i n derivin g X/ Q hav e bee n made . Thes e assumption s include : 1 . Th e distanc e fromth e poin t sourc e releas e t o th e poin t o f exposur e i s assume d t o b e 3 0 meter s (abou t 10 0 feet) . I n addition , i t i s assume d tha t a gaussia n distributio n o f th e release d contaminan t i s establishe d almos t immediatel ywithi nth e plum e an d i s full y develope d a t 3 0 meters .

3 

### Turner , D . Bruce , "Workboo k o f Atmospheri c Dispersio n Estimates, " EPAOffic e o f Ai r Programs , 1970 . A-1 0•9. 1

—0.0 1

—•0.00 1

1. 0 0.0 1 0.000 1 Distanc eFra

nSource(fan. )



### EXHIBI T A-2 . X/ Q Vs . Distanc e fo r a Ground Leve l Release ,

Stabilit yClas s D . 

# 1 I A-l lXu/ Qa



### EXHIBI T A-3 . Xu/ Q Vs . Distanc e a t Variou s Height s (H ) o f Releas e

(meters) , Stabilit yClas s D .

A-1 2 

# 1

I

### 2 . Th e releas e occur s a t ground level . Thi s approac h give s th e highes t ground leve l concentration s an d th e lowes t inhalatio n RVs . 3 . Th e poin t o f exposur e i s directl ydownwin d fromth e releas e i n neutra l (Clas s D ) atmospheri c condition s an d th e wind spee d (u ) i s 1 mete r pe r second . 4 . Th e materia l release d i s a stabl e ga s o r aeroso l (les s tha n 2 0 micron s i ndiameter ) whic hremain s suspende d i n ai r fo r long periods_o f time . 5 . Th e ga s o r aeroso l i s continuousl yemitte d fro m th e sourc e o r th e emissio ntim e i s equa l t o o r greate r tha n th e trave l time t o th e poin t o f exposure . I nthi s case , i t i s possibl e t o omi t fromconsideratio n diffusio n i n th e directio n o f transport . Th e equation s use d t o produc e th e graph s i nExhibit s A- 2 an d A- 3 ar e vali d onl yi f diffusio ni nthi s directio n i s assume d t o b e zero . Thi s i s a reasonabl e assumptio nbecaus e th e rat e o f diffusio ni nthi s directio nwoul d b e muc h smalle r tha n th e wind spee d o f 1 mete r pe r second . 6 . Non e o f th e materia l emitte d i s remove d fro mth e plum e a s i t move s downwind and ther e i s complet e reflectio n fro mth e ground . Wit hthes e assumption s and referrin g t o Exhibi t A-2 , i t i s possibl e t o obtai n a X/ Q o f 7. 2 x10" 2 

### second s pe r cubi c meter . Becaus e a breathing rat e i nunit s o f cubi c centimeter s pe r dayi s bein g use d i n equatio n (1) , i t i s necessaryt o conver t X/ Q t o compatibl e units . Thi s lead s t o a valu e o f 8,4j^ P daype r cubi c centimeter , th e valu e use d i nthi s report . Mos t publishe d source s describin g gaussia nadvection

dispersio n equation s provid e graphica l representation s fo r X/ Q a t distance s fro

mth e sourc e a s clos e a s 10 0 meters . Th e Agenc y recognize s tha t extrapolatio no f thes e value s t o shorte r distance s mayintroduc e anerro r i n subsequen t calculations . Th e extrapolation , however , allow s th e calculatio no f conservativ e releas e value s and , fo r thi s application , th e erro r whic hmayb e introduce d i s believe d t o b e inconsequential . Moreover , i t i s A-1 3P.6 5 i



### recognize d tha t severa l othe r assumption s i nth e atmospheri c dispersio n mode l als o yiel d a conservativ e X/ Q value . Alternativ e assumption s would , o f course , yiel d differen t value s fo r X/ Q a s discusse d below . If , instead o f extrapolating dow nt o 3 0 meters , th e valu e fo r a distanc e o f on e hundre d meter s (assumin g a ground leve l release ) i s chosen , X/ Q become s 9. 5 xIO" 1 4 

### da ype r cubi c centimeter . Thi s valu e i s almos t a norde r o f magnitud e smalle r tha n th e 3 0 mete r valu e an d woul d lead t o inhalatio nRV s nearl ya facto r o f te n higher . Exhibi t A- 3 als o show s value s fo r plum e height s (H ) greate r tha nground leve l ( H = 1 0 t o H = 30 0 meters) . Plum e height s ar e no t necessaril yth e same a s th e stac k heigh t and ar e affecte d b yphenomen a suc ha s inversio nlayers , wind speeds , an

d th e velocit yo f stac k ejecta . I nan ycase , i t i s clea r fro

mExhibi t A- 3 tha t i f RV s wer e t o b e calculate d o nth e basi s o f a releas e fromabov e ground level , theywoul d b e muc h larger . Fo r example , i n th e cas e o f a releas e 2 0 meter s abov e ground , th e calculate d X/ Q i s approximatel y1 x10~ 1 7 

### daype r cubi c centimete r a t on e hundre d meters , a facto r nearl yte n thousand time s smalle r tha n tha t fo r a groun d leve l release . I f calculate d a t 35 0 meter s (the poin t o f maximu m concentratio n accordin g t o Exhibi t A-3 ) th e valu e woul d b e 3. 5 xIO" 1 5 

### daype r cubi c centimeter , a valu e mor e tha n 20 0 time s smalle r tha nth e valu e use d i n equatio n (1) . Th e graph s shown i nExhibit s A- 2 an d A- 3 an

d use d fo r th e determinatio n o f X/ Q ar e generate d fromth e equation s fo r atmospheri c modelin g and ar e intende d t o simplif yth e tas k o f determinin g X/Q . Th e generall yaccepte d expressio nfo r th e concentration , X(chi) , o f ga s o r aerosol s a t poin t x,y, z fro ma continuou s sourc e wit ha neffectiv e emissio nheight , H , i s give n i n th e equatio n below . Th e coordinat e systemreferre d t o ca nb e foun d i n Exhibi t A-4 . A-1 4P.6 6

X(x,y.z;H ) . exp

2 T a yff

x u 

# t-&)]H-e)]-K^)] } <

«

where : 

## X» chi , concentratio n(Curies/m 3 

## ) ; x,y, z = position s i nth e coordinat e system s (se e Exhibi t Q= releas e rat e (curies/sec ) ; 7 r= p i (3.14159 , approximately) ; a y = horizonta l dispersivit y (meters) ; o z

## = vertica l dispersivit y (meters ) ; u= windspee d(meter s pe r second) ; exp= exp(-a/b ) = e(~ a 

## / b 

## ) wher e e i s th e bas e o f

natura l logarithm s an di s approximatel y

equa l t o 2.7183 ; and H= th e effectiv e emissionheigh t (meters) . Severa l assumption s ar e mad e concerningth e hypothetica l releas e whic hresul t i nth e simplificationo f Equatio n(2) . Thes e simplification s ar e show nbelow . Fo r concentration s calculate da t groundleve l fo r a ground leve l releas e (i.e. , z = 0 ) th e equationsimplifie s to : 

# Xfx.y.O.H, -^^ ex

pJ - *(£-) 2 

# ]« P ["T^) 2 

# ] O )

A-1 53= >

l — » 

## t(*.-y.z )

*.y.O )

EXHIBI T A-4 . Coordinat e System fo r Atmospheri c Modelin g Showing Gaussia n Distribution s i nth e Horizonta l an d Vertical .

### Wher e th e concentratio n i s t o b e calculate d along th e

centerlin e o f th e plum e giving th e maximu mconcentratio n (i.e. , y= 0) : X(x,0,0;H ) = ^ ex p yz 

# [XI (4 )

Fo r a ground leve l sourc e wit hn o effectiv e plume ris e (i.e. , H = 0) , th e equatio n simplifie s eve nfurther : X(x,0,0;0 ) = ^ (5 )

yz Th e value s fo r dispersio ni n th e yan d z direction s (a y

### an d a z

### ) varywit hth e turbulen t structur e o f th e atmosphere , heigh t abov e th e surface , surfac e roughness , sampling time ove r whic h th e concentratio n i s t o b e estimated , wind speed , an d distanc e fromth e source . Value s fo r (7 yan d a z

### ar e estimate d fo r eac h atmospheri c stabilit yclass , whic hinclud e a n estimate d wind speed . Stabilit yclas s D , use d here , assume s a ligh t wind i n overcas t condition s during eithe r dayo r night . Usin g Stabilit y Clas s D result s i n highe r concentration s an d lowe r RQ s than woul d mor e turbulen t stabilit yclassifications . Th e estimate s fo r horizonta l an

d vertica l dispersio n coefficient s ca n b e foun d i n th e Workboo k o f Atmospheri c Dispersio n Estimates. 4 

### Rearranging Equatio n (5) , above , a s shown , an d applying value s fo r cr y

### an d a z 

### fro m th e graphi n Exhibi t A- 5 yields :

1 l



### -2- 2 Xu/ Q = = = 7. 5 x1 0 L 

### mc



### . (6 ) * O a 7T(2.6)(1.65 )

4 

### Turner , D . Bruce , "Workboo k o f Atmospheri c Dispersio n Estimates, " EPAOffic e o f Ai r Programs , 1970 . A-1 7P.6 9

10 0

100 0 10 0 Distanc eDownwind , meter s



### EXHIBI T A-5 . Horizonta l an d Vertica l Dispersio n Coefficien t a s a Functio n o f Downwind Distanc e Fromth e Source .

A-1 8P.7 0



### Divisio n o f bot hside s o f th e equatio n bya win d speed , u , o f 1 mete r pe r secon d gives :

X/ Q = 7. 5 x10~ 2 

### se c m" 3



### . (7 ) Considerin g th e possibilitie s fo r erro r introduce d i n extrapolation , thi s valu e agree s ver ywel l wit hth e valu e foun d b yreferenc e t o Exhibi t A- 2 (7. 2 x10~ 2 

### se c m~ 3 

### ) .

A-1 9P.7 1



### APPENDI XB MODELINGTH E INGESTIO NO F CONTAMINATE D DRINKIN GWATE R

Drinking wate r i n th e Unite d State s i s usuall yobtaine d fro m on e o f tw o sources : well s drille d int o subsurfac e aquifer s o r surfac e source s suc ha s reservoirs , lake s o r rivers . Anyo f thes e drinkin g wate r source s canbecom e contaminate d froma releas e o f radionuclides . Th e Agenc yha s calculate d ingestio n releas e value s fo r bot hsubsurfac e aquifer s an d fo r river s i n orde r t o determin e whic hmigh t provid e th e mor e critica l pathway fo r consumptio n o f contaminate d water . EPAbelieve s tha t reservoir s an

d lake s provid e suc hlarg e dilutio nfactor s fo r release s o f radionuclide s tha t modeling thes e potentia l source s o f contaminate d wate r wil l provid e releas e value s muc hlarge r tha n thos e produce d b ymodeling o f ground wate r o r rive r wate r and , therefore , i s no t necessary . Poin t source s o f releas e ar e assume d i n bot hth e ground

wate r mode l an

d surface-wate r model . Thi s assumptio n i s mad e becaus e suc ha sourc e bette r represent s a sudden , episodi c releas e o r spil l a s oppose d t o a chroni c releas e froma wast e sit e o r othe r impoundment . Sectio n B. l provide s th e genera l equatio n th e Agenc yuse d t o calculat e releas e value s fo r th e consumptio n o f contaminate d drinking wate r whil e sectio nB. 2 review s a numbe r o f ground-wate r model s examine d b yth e Agenc y an d describe s i n detai l th e advection-dispersio n mode l chose nfo r calculatio n o f a dilutio nfacto r t o b e use d i nth e equatio n fo r calculatio n o f releas e value s base d o n wate r consumption . Sectio n B. 3 describe s a surfac e wate r mode l fo r contaminatio no f river s frompoin t sourc e release s o f radionuclide s and explain s th e Agency' s reason s fo r no t using thi s mode l fo r determinatio n o f dilutio n factor s and calculatio no f releas e values .

B- lP.7 2



### B. l CALCULATIO

N OF RELEAS E VALUE S FO RTH E CONSUMPTIO

N OF CONTAMINATEDDRINKIN GWATE R Th e releas e valu e calculate d fo r th e consumptio no f contaminate d drinking wate r (DW ) i s directl yproportiona l t o th e ingestio n AL I an

d inversel yproportiona l t o th e dilutio nfactor , contac t time , an

d wate r consumptio n rat e o f referenc e man . Th e metho d whic hth e Agenc yha s adopte d fo r th e calculatio n o f releas e value s base d o n th e consumptio no f contaminate d drinking wate r i s summarize d i n equatio n (1) . DWReleas e Valu e = ALI/[(10)*(DF)*(CT)*(WC)*( 1 xIO 6 

### ) ] (l ) where : AL I = annua l limit s i f intak e fo r ingestio n(microcuries) ; 1 0 facto r t o conver t th e annua l limi t o f intak e whic hi s base d o n 5 remdose-equivalen t t o a worke r i na nuclea r facilit yt o th e mor e conservativ e 0. 5 remfo r exposur e t o th e genera l public ; D F = dilutio n facto r (liter" 1 

### ) ; C T = contac t tim e (days) ; W C = wate r consumptio n rat e o f referenc e ma n( 2 liter s pe r day) ; an

d 1 xIO 6 

### conversio n facto r betwee n microcurie s an d curies . Th e ingestio n ALI s use d i n th e calculatio n ar e take n fro m ICRP' s Publicatio n 30 1 

### afte r conversio nfrom becquerel s t o microcuries . Wher e mor e tha n on e AL I wa s give nfo r a particula r radionuclide , th e lowes t valu e wa s use d i n th e calculations . internationa l Commissio no nRadiologica l Protectio n (ICRP) , "Limit s fo r Intake s o f Radionuclide s b yWorker, " Publicatio n 30 , Par t 2 , 1980 . B- 2P.7 3



### Th e dilutio n facto r (DF ) and contac t tim e (CT ) term s use d i n equatio n (1 ) fo r calculatio n o f a drinking wate r releas e valu e base d o n th e consumptio n o f contaminate d ground wate r ar e derive d and mor e full yexplaine d i nsectio n B. 2 whil e sectio nB. 3 explain s th e derivatio no f a dilutio nfacto r fo r contaminate d rive r water . A s describe d i n sectio nB.2 , th e dilutio n facto r fo r ground-wate r consumptio n take s radioactiv e decayint o accoun t fo r th e perio d o f transpor t fromth e poin t o f releas e t o th e poin t o f exposur e an d th e contac t tim e termi nequatio n(1 ) i s modifie d fo r radioactiv e decayove r th e perio d o f consumption . I n determinatio n o f a dilutio n facto r fo r consumptio no f contaminate d rive r water , however , radioactiv e decayi s no t considere d becaus e th e time o f transpor t from th e poin t o f releas e t o th e poin t o f consumptio n i s ver yshort . Additionally , i n thi s case , radioactiv e decaydurin g th e perio d o f consumptio n i s ignore d becaus e thi s perio d i s no t wel l define d a s i t i s i n th e scenari o fo r consumptio no f contaminate d ground water . B. 2 GROUND-WATERTRANSPORT OF RADIONUCLIDE S Tw o ground-wate r model s fo r th e purpos e o f calculating a dilutio n facto r i n equatio n (1) , th e advection-dispersio nmode l an d th e simpl e dilutio n model , wer e examine d i nsome detai l b y th e Agency . Also , fou r othe r model s develope d fo r specialize d purpose s withi n th e Resourc e Conservatio n an d RecoveryAc t (RCRA ) programwer e reviewe d an d compare d t o th e selecte d advection

dispersio n model . Thes e model s ar e describe d below . B. 2. 1 The Advection-Dispersio nModel . Th e calculatio n o f a dilutio nfacto r fo r a radionuclid e releas e t o ground wate r ca n b e accomplishe d b yassuming a releas e scenari o tha t i s reasonabl yconservative . I nthi s calculation , i t i s assume d tha t th e releas e i s directl yt o ground water , whic h B- 3P.7 4



### i s a conservativ e assumptio nbecaus e i t neglect s migratio n throughth e unsaturate d zone . Th e following assumption s ar e als o made :

o flowi s uniforman d stead y(ground-wate r velocit y=0. 5 meter/day) ; o th e aquife r i s homogeneou s an d isotropic ; o th e releas e i s a ninstantaneou s poin t sourc e t o th e saturate d zone ; o a t tim e zero , th e concentratio n o f radionuclid e i nth e aquife r i s zero ; o th e aquife r i s o f finit e thicknes s an d infinit e exten t (ther e ar e n o boundarie s clos e enought o affec t th e transport) ; an

d o th e drinking wate r wel l i s locate d 3 0 meter s down gradien t from

th e poin t o f release . Fo r a n instantaneou s poin t sourc e locate d o n th e z axi s i n uniformstead

yflow(Exhibi t B-l) , th e analytica l solutio no f th e transpor t equatio n is 2 

### : C - 3 

### Mexp - ( 4 7Tt) J 

### /^(E x 

### E y 

### E z 

### )V^R d 

### n (x-Ut) 2 

### + _Y 2 

### + __z 2 

### + X t 4E z 

### t 4E x 

### t 4Ey t (2 ?
where : M= magnitud e o f th e instantaneou s releas e ( 1 Ci) ;

Rd n X t = retardatio nfactor ;

= effectiv e porosit y(0.1) ;

= radioactiv e decayconstan t (0.693/t 1 

### / 2 

### )

- tim e o f trave l fro msourc e t o wel l ( t - 30/(V x 

### /{riR d 

### )); t 

### l/ 2 = 

### radionuclid e half-lif e i n days ;

2 

### Carlsaw , H. , Jaeger , J. , "Conductio no f Hea t i n Solids, " Oxford Universit yPress , London , 1959 . B- 4

### EXHIBIT B- l Scenari ofo rCalculatio no f Ground-Wate rTranspor t

3IO C VIC W W«l l

30 «

PLAM VIC W

O friUiil- / / Pt-UM* « ttim e 9f»«tt rtfi M i»r « ( wel l



### B- 5P.7 6



### C = maximu

mradionuclid e concentration ;

an d E x 

### , Ey , E 2 

### , R^ , an d Uar e define d as : E x

### = Dxx/% ' E y

### - Dyy/Rd, ' E z 

### = Dz^Rd ; U= Vx/nRd ; R^ j = 1 + (P b 

### )*(K d 

### /n) ; where : D 

### x x = 

### longitudina l coefficien t o f dispersion ;

Dy y- D z z = 

### transvers e coefficient s o f dispersion ; Pj

- = bul k densit yo f th e aquife r (1. 5 gm/cm 3 

### ) ; V x

### = flowo f th e aquife r (0. 5 meter s pe r day) . Thi s valu e wa s chose na s a conservativ e flo wrat e fo r sand-containing aquifer s b ycompariso n t o Tabl e B- 2 i n th e repor t referenced 3



### . Thi s tabl e lists

4 5 differen t saturate d zon e layer s tha t contai n san d an d variou s othe r eart hmaterial s i n differen t proportions . Th e smalles t flowliste d i s 0. 7 meters/year , whil e th e larges t i s greate r tha n 10,00 0 meters/year . Th e averag e flowi s 62 5 meters/yea r o r abu t 1. 7 meter/day . Avalu e o f 0. 5 meters/dayi s conservativ e i ntha t i t prolong s contac t tim e an

d lead s t o a lowe r (mor e conservative ) Releas e Value ; an d K ^ = th e sorptio n coefficien t i n cm 3 

### / g (se e Exhibi t B- 2 fo r a compilatio n o f value s used) . Dispersio n coefficient s ar e define d byth e following equations : D 

### x x" (a_.)*(V x 

### /n) ; Dy y= D 

### z z = (a t 

### )*(V x 

### /n) ; where : a ! = longitudina l dispersivit y(2 0 meters) ;

a ^ = transvers e dispersivit y( 4 meters) .

3 

### "Line r Locatio n Ris k an d Cos t Analysi s model, " Draf t Repor t unde r Contrac t No . 68-01-6621 , Offic e o f Soli d Waste , EPA , January , 1985 . B- 6P.7 7



### EXHIBI T B- 2 SORPTIO N COEFFICIENT VALUE S SORPTION ELEMENT Actiniu m Aluminu m Americiu

m Antimon y Argo n Arseni c Astatin e Bariu m Berkeliu

m Berylliu

m Bismut h Bromin e Cadmiu m Calciu m Californiu

m Carbo n Ceriu m Cesiu m Chlorin e Chromiu m Cobal t Coppe r Curiu m Dysprosiu

m Einsteiniu

m Erbiu m A c

A l A m S b A r A s A t Ba Bk B e B i B r Cd C a C f C C e C s C l C r C o C u C m D y E s E r COEFFICIENT . _y i 100 0 0 100 0 1 0 0 0 10 0 70 0 7 5 1 0 0 50-10 0 1 5 0 0 200 0 200 0 0 0 200 0 0 50 0 0 0 0 * SOURC E

EPA520/4-79-007 C Assumption* * Haje k (1966) , Knol l (1965 ) (1969 ) EPA520/6-78-00 7 EPA520/4-79-007 C Assumption* * EPA520/4-79-007 C Analogou s t o S r (PNW L 8/2/86 ) EPA520/4-79-007 C EPA520/4-79-007 C EPA520-4-79-007 C Assumption* * Estimat e (PNWL 8/18/86 ) EPA520/4-79-007 C Assumption* * Estimat e (PNWL , 8/18/86 ) Rhode s (1957 ) Benso n(1960 ) Lette r Repor t RJS-ARCH O EPA520/4-79-007 C Assumption* * EPA520/6-78-00 7 Assumption* * EPA520/6-78-007 , Sheppar d (1976 ) Assumption* * Assumption* * Assumption* *

B- 7P.7 8



### ELEMENT Europiu m Fermiu m Fluorin e Franciu m Gadoliniu

m Galliu m Germaniu

m Gol d Hafniu m Holmiu m Hydroge n Indiu m Iodin e Iridiu m Iro n Krypto n Lanthanu

m Lead Lutetiu m Magnesiu

m Manganes e Mendeleviu

m Mercury Molybdenu

m Neodymiu

m Neptuniu

m Nicke l Niobiu m Osmiu m Palladiu

m E u Fm F F r Gd G a G e AU H f H o H I n I I r F e K r L a P b L u M g M n Md H g M o N d
N p N i N b O s Pd SORPTION COEFFICIENT . % *

50 0 0 0 20 0 500-100 0 0 0 0 0 60 0 0 0 3 0 15 0 0 0 400 0 0 0 0 0 0 5 50 0 1 0 10 0 200 0 0 50-10 0 SOURC E

Sem e & Ra i (1976 ) Assumption* * Assumption* * EP A520/4-79-007 C Chemica l Analogyt o Rar e Eart h (PNWL 8/18/86 ) Assumption* * Assumption* * Assumption* * Assumption* * EP A520/4-79-007 C EPA520/6-78-00 7 Assumption* * Shallo wLand Buria l Progra m Assumption* * EP A520/4-79-007 C Iner t Ga s (PNWL 8/18/86 ) Assumption* * EPA520/4-79-007 C Assumption* * Assumption* * Assumption* * Assumption* * Assumption* * EP A520/4-79-007 C Chemica l Analo g t o Rar e Eart h (PNWL 8/18/86 ) Routso n e t a l 1975 , 76 , Sheppar d (1976 ) Estimat e (PNWL 8/18/86 ) EPA520/4-79-007 C Assumption* * Estimat e (PNWL 8/18/86 ) B- 8_PJ 9



### SORPTION ELEMENT Phosphoru s Platinu m Plutoniu

m Poloniu m Potassiu

m Praseodymiu

m Promethiu

m Protactiniu

m Radiu m Rado n Rheniu m Rhodiu m Rubidiu m Rutheniu

m Samariu m Scandiu m Seleniu m Silico n Silve r Sodiu m Strontiu

m Sulfu r Tantalu m Technetiu

m Telluriu

m Terbiu m Thalliu m Thoriu m P

P t P u P o K P r P m P a R a Rn R e Rh Rb R u Sm S c S e S i Ag N a S r S T a T c T e Tb T l Th COEFFICI I

100

- :NT . K .



### 0 0 -1000 0 2 5 3 5 500-100 0 1000

- 100

- -1000 0 400 0 -1000 0 0 0 0 50 0 0-50 0 500-100 0 0 1 0 0 50-10 0 1 0 10 0 0 0 0 50-10 0 500-100 0

100 0 2 -1000 0 SOURC E

Assumption* * Assumption* * EPA520/6-78-007 , AShallow Lan d Buria l Program EPA520/4-79-007 C EPA520/4-79-007 C Chemica l Analogyt o Rar e Eart h (PNW L 8/18/86 ) Benso n(1960 ) Rar e Eart h EPA520/4-79-007 C EPA520/6-78-00 7 EPA520/4-79-007 C Assumption* * Assumption* * Chemica l Analogyt o C s (PNW L 8/18/86 ) Rhode s (1957 ) Chemica l Analogyt o Rar e Eart h (PNW L 8/18/86 ) Assumption* * Shallo wLand Buria l Progra m Assumption* * Estimat e (PNWL 8/18/86 ) EPA520/4-79-007 C Shallo wLand Buria l Progra m Lette r Repor t RJS-ARCH O Assumption* * Assumption* * Shal l Lan

d Buria l Progra

m Estimat e (PNWL 8/18/86 ) Chemica l Analogyt o Rar e Eart h (PNW L 8/18/86 ) EPA520/4-79-007 C EPA5520-6-78-00 7
B- 9P.8 0



### SORPTION ELEMENT Thuliu m Ti n Titaniu m Tungste n Uraniu m Vanadiu m Xeno n Ytterbiu

m Yttriu m Zin c Zirconiu

m Tm

S n T i W U V X e Yb Y Z n Z r COEFFICIENT . K$* 0 50-10 0 0 0 1-5 0 0 0 0 50 0 0 200 0 SOURC E

Assumption* * Estimat e (PNWL 8/18/86 ) Assumption* * Assumption* * Estimat e (PNWL 8/18/86 ) Assumption* * Iner t Ga s (PNWL 8/18/86 ) Assumption* * Estimat e (PNWL 8/18/86 ) Assumption* * Rhode s (1957 ) Fo r sorptio n coefficien t value s tha t ar e give n i nranges , th e lowes t sorptio ncoefficien t wa s chose n fo r th e ingestio n Releas e Valu e calculation .

* * 

### Fo r thes e element s n o K< j valu e ha s bee n obtaine d and a sorptio n coefficien t o f zer o (Kd=0 ) wa s assume d (n o retardation) . SOURCE S Bensen , D.W . 1960 . Revie wo f Soi l ChemistryResearc ha t Hanford . HW-67201 . Environmenta l Protectio n Agenc yRep . EPA520/6-78-007 . Ames , L . L . an

d Dhanpa t Rai , "Radionuclid e Interaction s wit h Soi l and Roc k Media. " Environmenta l Protectio nAgenc yRep . EP A520/4-79-007C . "Technica l Suppor t o f Standard s fo r HighLeve l Radioactiv e Wast e Management, " Vol . C , Migratio nPathways , 1979 . Hajek , B . F . 1966 . "Plutoniu man d Americiu

mMobilit yi n Soils. " BNWL-CC-925 . Knoll , K . C . 1965 . "Reactio n o f Hig hSal t Aqueou s Plu s Organi c Wast e wit hSoil. " BNWL-CC-313 . B-1 0P.8 1



### Knoll , K . C . 1969 . "Reaction s o f Organi c Waste s i nSoils . BNWL-860. " Lette r Repor t R . J . Sem e - ARCH O 6/5/75 , a lette r writte n t o Atlanti c Richfiel d Hanfor d Compan yb yw . Marti nreporting some , a t tha t time , ne wlaboratorydata . PNW L 8/18/86 , Lette r fromMartin , W . t o EMS I 8/18/86 , reportin g estimate s o f K ^ fo r a Generi c Sand ySediment . Rhodes , D . W . 1957 . "Th e Effec t o f p H o nth e Uptak e o f Radioactiv e Isotope s fromSolutio n bya Soil. " Soi l Scienc e Societ yo f Americ a Proceedings , 21:389-392 . Routson , R . C , G . Jansen , an d A . V . Robinson . 1976 . "99T C 

### N

p an d 241 

### A mSorptio no nTw o Subsoil s from Differing Weathering Intensit yAreas. " BNWL-2000 . Pt . 2 , pp . 50-52 . Seme , R . J . an

d Dhanpa t Rai . 1976 . "Adsorption

Precipitatio n Behavio r o f E u i nSoil s an d Standar d Clays. " Agronom yAbstracts , p . 132 . Shallo wLand Buria l Program- a s ye t unpublishe d result s obtaine d o n a n ongoing DO E sponsore d program . Sheppard , J . C. , J . A . Kittrick , T . L . Hart . 1976 . "Determinatio n o f Distributio nRatio s an d Diffusio n Coefficient s o f Neptunium , Americium , and Curiu m i n Soil

Aquati c Environments, " RLO-221-T-12-2 .

B-l lP.8 2



### Fo r thi s calculation , th e aquife r i s assumedt o be thic k enoug hs o tha t the uppe r an dlower boundarie s do no t significantl y

affec t the vertica l component o f transvers e dispersiona s the contaminant migrate s t o the well . I nvie w o f the rang e o f value s presentedb y Codel l an

dDuguid 4 

### , EP

A belive s thes e value s for transvers e an dlongitudina l dispersivit y ar e reasonabl y

conservative an

dappropriat e for the adjustmen t o f RQs. 5 

### The wel l i s assumedt o li e o nthe centerline o f the plum e ( y = z = 0 ) an

dthe maximu

m concentrationa t the wel l i s given by : C - ____ ___ _exp(-Xt) . (3 ) ( 4TrtJ-V-fExEyEgjV^Rd n Substitutin gth erelationship s fo rE x 

### , Ey , E z 

### , an dtint o Equatio n(3 ) gives : C = _exp[(-0.693/t, / ? 

### )(6) ]

R d n 

### Simplificatio nyields : C = M (1207 T ) V - a t 1 / 2

### a

_nR d exp(-4. 2 Rd/ti /2 

### ) (5 )

4 

### Till , J.E . Meyer , H.R . (Editors) , "Radiologica l Assessment . TextbookonEnvironmenta l Analysis, " NUREG/CR-3332 , U.S . Nuclea r Regulatory

Commission , 1983 . 5 

### Value s for longitudina l an dtransvers e dispersivit y usedfor ground-wate r model s developedfor Resourc e Conservationan d Recovery

Ac t (RCRA ) purpose s are generall y smalle r becaus e the equation s wer e developedt o evaluat e ris kwhil e equation s for R Q purpose s ar e no t directl y ris krelated . Furthe r discussiono f thes e RCR

A model s canbe foun di nthi s appendix . B-1 2P.8 3



### Fo r a ^ = 2 0 meters , a.^= 4 meters , n = 0.1 , M= 1 curie , an d introducing a conversio n fracto r fro mcubi c meter s t o liter s ( l x 10 3 

### ) , th e maximu

m concentratio n a t th e wel l i s calculate d as : C - ,-r, _- ! _exp(-4. 2 RdAi/2 ) (6 ) (1207T )•*/ *(20) *-/*(*) (0.1 ) (Rd ) (1X10 J 

### ) '

C = 7. 6 xIO" 8 

### exp(-4. 2 Rd/ti/2 ) liters" 1



### . (7 ) Equatio n (7 ) give s th e amoun t o f dilutio nfo r a on e curi e releas e int o a n aquifer . Th e dilutio n facto r (DF ) fo r th e aquife r is , therefore , define d as :

D F - 7. 6 x10" 8 

### exp(-4. 2 Rd/ti/2 ) liters" 1



### . (8 ) Th e valu e o f th e retardatio nfacto r wil l affec t no t onl yth e maximu mconcentratio n o f th e radionuclide s foun d i nth e plum e develope d b

yth e releas e bu t als o th e tim e require d fo r th e plume t o reac han

d pas s th e well . Whe nth e sorptio ncoefficient , Kd / i s equa l t o zero , th e retardatio n facto r i s equa l t o one . Whe n th e sorptio n coefficien t become s larger , however , th e retardatio n facto r increase s rapidl y(e.g. , whe nK d = 1 / Rd ~ 16 

### ) • A s K d increases , then , a longe r perio d o f tim e i s require d fo r th e radionuclid e t o reac han d pas s th e well . Whe nradioactiv e decay i s considere d i n thi s equatio nan d th e retardatio nfacto r i s greate r tha n one , i t ha s th e effec t o f "removing " a larg e portio n o f th e radionuclide s befor e theycanb e ingested . A s a result , th e calculate d releas e value , whe nth e retardatio n facto r i s greate r tha n one , i s significantl ylarge r tha nth e releas e valu e whe n th e retardatio n facto r i s equa l t o on e and , i nfact , become s muc hlarge r i n compariso nwit hth e othe r releas e value s calculate d fo r th e othe r exposur e pathways . I t i s recognized , therefore , tha t th e ground-wate r ingestio nreleas e valu e B-1 3C d l is) oc n ^ 3 * ( D 

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### n to r t p O 0 > 01 el - 

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### s ' ro • i 0 \ * ro P - P * p - 01 r t

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### c C ro r t 3 * 0 > r t • d p C B ro * d o > 01 01 ro 01 •

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• d P « d B ro • I- 3 3 * ro r t tr ro

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- 3 • i ro o > r t ro • i r t tr to 3 O 3 ro • 01 ro m o > • i o > r t ro

- 3 • i o d 3 p - i • C 0 * r t ro i i p 3 i Q ro C O r t p o 3 ro 

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• i ro r t 0 * • i p . 0) r t p O 3 M l t u O r t O " i p - 01 i Q i i ro 0 * r t ro • i rt tr to ti O 3 ro

- S p - P - P -

### a/ b= a/ c = a]/a- t = 20/ 4 = 5 .

Therefore ,

b= a/5 , c = a/5 ,

and 1 = (4/3 ) *(7T )*(a 3 

### /25)*(7. 6 XIO" 5 

### ) . (10 ) Solving fo r a gives :

a - 4 3 meters , and th e time require d fo r th e ellipsoida l plume t o pas s th e wel l i s give n by :

Contac t Tim e (CT ) = a/(V x 

### /n ) = 9 days . (ll ) Becaus e th e time availabl e fo r consumptio n o f contaminate d wate r i s th e same a s th e perio d o f tim e th e contaminatio ni s i n contac t wit hth e well , th e contac t tim e (CT ) i s 9 days . I n orde r t o conside r decayove r th e perio d o f ingestion , i t i s recognize d tha t a n individua l wil l inges t smalle r quantitie s o f radioactivit ya t time s tha t ar e succesivel ymor e distan t from th e tim e tha t th e radionuclid e firs t arrive s a t th e poin t o f exposure , th e drinking wate r well . Accordingly , radioactiv e decayove r th e perio d o f exposur e wa s take nint o accoun t b y modifyin g th e contac t tim e a s follows :

1 - expf

- XCT) . X

B-1 5

### Th e Ground-Wate r Ingestio nReleas e Valu e i s calculate d b y us e o f equatio n (1 ) an d substituting i nth e modifie d expressio n fo r contac t tim e a s summarize d i n equatio n (12 ) below : Ground-wate r Ingestio n = AL I . (12 ^ Releas e Valu e [lO]*[DF]*[WC]*[l-exp(

- XCT)/ X]*[ 1 xIO 6 

### ] Where : AL I = Annua l Limit s o f Intak e fo r ingestio n

(microcuries) ; 1 0 convert s th e 5 remoccupationa l exposur e limi t t o

th e mor e conservativ e 0. 5 remexposur e limi t fo r th e genera l public ;

x

### = 0.693/t 1 

### / 2 

### ; tl/ 2 = 

### radionuclid e half-lif e (days) ; D F = dilutio n facto r [7. 6 x10~ 8 

### exp(-4. 2 Rd/ t 

### l/2 )

liters" 1 

### ] ; Rd = retardatio n facto r (1) ; W C = wate r consumptio n rat e o f "Referenc e Man " ( 2

liters/day) ; C T = contac t time ( 9 days) ; an d 1 xIO 6 

### convert s microcurie s t o curies . Substitutin g th e value s fo r DF , WC , R d 

### , an d C T give s th e followin g expressio n fo r th e ground-wate r ingestio n Releas e Value : Ground-wate r Ingestio n = AL I . (13 ; Releas e Valu e [2.2]*[exp(-4.2/t 1/2 

### )]*[t 1/2 

### -t 1/2 

### exp(-6.2/t 1/ 

### 2) ]

B-1 6P.8 7



### B.2. 2 Th e Simpl e Dilutio nModel . Th e Nuclea r RegulatoryCommissio n suggeste d a simpl e dilutio n mode l fo r th e calculatio no f Releas e Value s base d o n ground-wate r transport . Thi s mode l wa s develope d i n orde r t o determin e th e maximu mconcentration s fo r on-sit e disposa l o f low leve l nuclea r wast e an d t o identif ysite s suitabl e fo r th e disposa l o f suc hwaste . Th e Commission' s goa l i nbot hthes e case s i s t o minimiz e th e ris k t o th e publi c fo r exposur e vi a th e ground wate r t o release s o f radioactiv e material . Althoughthi s approac hma yb e appropriat e fo r th e minimizatio n o f risk , i t appear s inappropriat e fo r th e determinatio no f RQ s whic hsimpl y ac t a s trigger s fo r notificatio no f a releas e o f a hazardou s substance . Som e o f th e assumption s mad e b yth e Nuclea r RegulatoryCommissio n fo r thei r calculation s using th e simpl e - dilutio n mode l ar e show n below. 7



### o Ground-wate r flowrate s ar e betwee n0.000 5 an d 0.0 3 meters/day . o Longitudina l dispersivitie s ar e betwee n 0.0 5 and 0. 1 meter . o Transvers e dispersivitie s ar e zero . o Pumping rate s ca n varybetwee n770 0 cubi c meters/yea r and 2,000,00 0 cubi c meters/year . o Wate r consumptio ni s 2 liters/dayfo r a n individual . Usin g thes e assumptions , th e aquife r resemble s a veryslo w flowing pipelin e betwee n th e poin t o f releas e an d th e well . Th e flowoccur s a t suc ha rat e tha t th e entiret yo f th e releas e i s pumpe d from

th e wel l ove r a perio d o f on e year . Th e contac t time (CT ) is , therefore , 36 5 days . Ignoring radioactiv e decayand

7 

### Oztunali , O.I. , Roles , C.W. , "DeMinimi s Wast e Impact s Analysi s Methodology, " NUREG/CR-3 5 85 , February , 1984 . B-1 7P.8 8



### usin g a pumpin g rat e o f 770 0 cubi c meter s pe r yea r a s suggeste d b yth e Nuclea r RegulatoryCommission , a dilutio n facto r (DF ) ca n b e calculated : D F = 1/770 0 m 3 

### - 1. 3 xIO" 4 

### m" 3 

### - 1. 3 xIO" 7 

### liter" 1



### . Usin g thes e figure s an d onc e agai nignoring radioactiv e decay , a Releas e Valu e (RV ) i n curie s ca nb e calculate d fro man AL I i n microcurie s byus e o f equatio n(1) . R V o ALI/[(10)*(1. 3 x10" 7 

### /liter)*( 2 liter/day)*(36 5 day) *

( 1 xIO 6 

### uCi/Ci)] ; R V = ALI/949 . Releas e Value s fo r ingestio ncalculate d i nthi s wa ywoul d b e abou t 7 0 time s smalle r tha nthos e calculate d b yth e advection

dispersio n mode l ignoring radioactiv e decayan d similarl ysmalle r including factor s fo r radioactiv e decay . B.2. 3 Othe r Ground-Wate r Model s Th e EPA' s Offic e o f Soli d Wast e use s severa l ground-wate r model s i n implementin g th e Resourc e Conservatio nand RecoveryAc t (RCRA) . Althoug hothe r model s ar e use d withi n th e RCR Aprogram , th e following fou r hav e bee nanalyze d an d compare d t o th e ground

wate r ingestio n model :
o Th e Comparativ e Ris k Assessmen t Mode l (CRAM ) use d t o compar e th e huma nhealt hrisk s an d cost s o f variou s combination s o f hazardou s wast e streams , environmenta l settings , and wast e treatmen t technologies ; o Th e Liner-Locatio n Ris k an d Cos t Analysi s Mode l use d t o estimat e th e huma nhealt hrisk s o f land disposa l facilitie s o f differen t design s i n differen t environmenta l settings ;

B-1 8

### o Th e Threshol d Mode l use d i ndetermining th e nee d t o ba n o r restric t hazardou s wast e fromlan d disposal ; and o Th e Vertica l an d Horizonta l Sprea d (VHS ) Mode l use d i n analyzing ground-wate r transpor t issue s associate d wit h delisting petition s (i.e. , petition s t o remov e a substanc e fro

mRCRA' s hazardou s substanc e list) . Th e following discussio n compare s thos e four RCR Amodel s t o th e R Q ground-wate r mode l i nterm s of : (1 ) th e basi c equation s use d i n eac hmodel ; an d (2 ) value s fo r th e inpu t variable s use d i n th e equations . Compariso n o f Mode l Ecruations Al l simpl e ground-wate r transpor t model s —including th e transpor t model s use d i nth e R Q adjustmen t methodology / th e CRAM , th e Line r Locatio n Model , th e Threshol d Model , an d th e VH S Mode l

—ar e base d o n th e same law s o f physic s and , a s such , ar e base d o n th e same basi c transpor t equation . Th e onl ydifferenc e i n th e models ' equation s i s th e releas e scenari o use d i ndevelopin g th e analytica l solutio n t o th e transpor t equation . Thes e releas e scenario s var yi n tw o respects . First , th e configuratio no f th e contaminan t sourc e ca n vary ; i t ca nb e a poin t source , a lin e source , o r a plan e source . Second , th e contaminan t tha t i s being modele d ca n b e release d i n differen t tim e frames ; i t ca nb e release d instantaneously , continuously , o r a t a variabl e rate . Everythin g els e being equal , al l o f th e ground-wate r model s considere d her e wil l giv e differen t result s onl ybecaus e thei r equation s ar e base d o n differen t sourc e configuration s and differen t contaminan t releas e rates . Th e sourc e configuratio n and contaminan t releas e rate s assume d i n eac ho f th e model s ar e shown i n Exhibi t B-3 .

B-1 9P.9 0



### EXHIBI T B- 3 SOURC E CONFIGURATION S AND CONTAMINANT RELEAS E RATE S ASSUME D I NTH E RCR AAND R Q MODE L EQUATION S

Mode l Contaminan t Sourc e Configuratio n Contaminan t Releas e Rate s R Q Mode l CRA M Liner-Locatio n Mode l Threshol d Mode l VH S Mode l poin t sourc e poin t sourc e plan e sourc e plan e sourc e plan e sourc e instantaneou s releas e continuou s releas e tim e variabl e releas e tim e variabl e releas e (Gaussian ) continuou s releas e Source : IC F Analysi s Th e selectio n o f instantaneou s releas e fo r th e R Q mode l wa s base d o n th e consideratio n tha t th e highes t ground-wate r concentratio n wil l b e achieve d whe n th e sourc e i s release d instantaneousl yrathe r tha n continuousl yo r a t some variabl e rate . Fo r example , a wel l 3 0 meter s downgradien t fromth e poin t o f releas e woul d experienc e a highe r concentratio n o f radio

activit yi f 1 curi e wa s release d al l a t onc e rathe r tha n a littl e bi t a t a tim e ove r a prolonge d period . O nth e othe r hand , a n instantaneou s releas e versu s a prolonge d releas e wil l resul t i n ground-wate r contaminatio n tha t wil l pas s beyond a wel l mor e quickl y(i.e. . th e contac t tim e i s shorte r fo r a ninstantaneou s release) . Fo r a prolonge d release , th e contaminatio nwil l b e found i n smalle r concentration s bu t wil l persis t around a nearb y wel l fo r a longe r perio d o f time .

B-2 0P.9 1



### I n comparing th e differen t contaminan t sourc e configura

tions , neithe r a poin t no r a plan e sourc e i s necessaril yalway s mor e conservativ e tha n th e other . Apoin t sourc e assume s tha t th e entir e release , assume d t o b e 1 cur_.' a i n th e R Q ground

wate r model , i s a t th e outse t concentrate d int o a singl e poin t an d the n allowe d t o dispers e a s i t flow s downgradien t t o th e poin t o f exposure . I n contrast , a plan e sourc e assume s tha t th e tota l releas e i s distribute d throughou t a plan e o f a specifie d lengt han

d width . Whethe r on e i s mor e conservativ e tha n th e othe r depend s o n th e dimension s o f th e plan e i nrelatio nt o th e dimension s o f th e aquifer , an d o n th e distanc e from th e poin t o f releas e t o th e poin t o f exposure . Apoin t sourc e i s though t t o b e mor e appropriat e fo r th e purpos e o f developing a nR Q becaus e i t bes t represent s a sudden , episodi c releas e o r spill . Aplan e sourc e i s mor e appropriat e fo r modeling chroni c release s froma surfac e impoundmen t o r landfill . Compariso n o f Value s fo r Inpu t Variable s Th e primaryinpu t variable s i n th e R Q ground-wate r mode l are : o a retardatio nfactor , whic htake s int o accoun t ho wmuc h

a contaminan t i s retarde d (throug hsorptio nb

ysoi l an

d othe r mechanisms ) relativ e t o th e transporting wate r mass ; o ground-wate r velocity ; o saturate d zon e thickness ; o porosity , whic hrefer s t o th e amoun t o f opening s o r hole s i n a soi l o r rock ; o longitudina l dispersivity , whic hreflect s th e exten t o f dispersio n o f a contaminan t a t righ t angle s t o th e directio n o f ground-wate r flow ; an d o th e distanc e t o th e neares t wate r suppl ywell .
B-2 1P.9 2



### Th e value s use d fo r th e variable s i n th e R Q ground-wate r model , a s wel l a s th e value s use d i nth e RCR Aground-wate r models , ar e presente d i nExhibi t B-4 . A s show n i n thi s exhibit , al l bu t on e mode l (the VH S model ) tak e int o accoun t contaminan t retardation . A s als o shown i n Exhibi t B-4 , th e value s use d fo r velocity , aquife r thickness , an d porosit yi nth e R Q ground-wate r mode l ar e i n th e rang e o f thos e commonl yuse d b yth e RCR

Amodels . However , th e value s fo r dispersivit y(bothlongitudina l an d transverse ) use d i n th e R Q mode l ar e significantl yhighe r tha nthos e use d i n th e RCR Amodels . Th e value s o f longitudina l an d transvers e dispersivit y reporte d i n th e literatur e varywidely . Dispersivit yvalue s hav e bee n obtaine d fo r differen t soi l type s throughfiel d measurements , laboratoryexperiments , an d from th e calibratio no f numerica l model s (i.e. , calibratio no f model s t o matc hobserve d fiel d data) . I n general , ou t o f thes e thre e way s t o determin e value s fo r dispersivity , value s measure d i n th e laboratoryar e th e lowest , fiel d measure d value s ar e generall yintermediat e i n size , and th e mode l derive d value s ar e usuall yth e highest . Laboratorymeasure d value s o f dispersivit yar e ofte n s o lowtha t the yar e frequentl yconsidere d unrealistic ; mode l derive d value s ar e considere d mor e realisti c tha nthos e measure d i n th e laboratory , bu t no t a s realisti c a s thos e measure d i nth e field . Exhibi t B- 5 present s field s measure d value s and mode l derive d value s o f dispersivit yfo r alluvia l aquifer s (i.e. , deposit s compose d o f particle s o f gravel , sand , silt , o r clay tha t ar e no t bound o r hardened) .

B-2 2EXHIBI T B- 4 VALUE S OF INPUT VARIABLE S USE DI M TH E RCR

A AH D RQGROUND-WATERNOOEL S

Mode l Retardatio na / Ground-Wate r Velocit y (m/day ) Aquife r

Thicknes s (m ) Porosit y

(dimensionless ) Longitudina l

Dispersivit y (m ) Transvers e

Dispersivit y (m ) Distanc e

t o Wel l (m )

RQ Mode l CRA M ye s

ye s Liner-Locatio nye s Threshol dMode l ye s VH S Mode l n o 0. 5 <2 5 0.003-2 8 <2 5 N/ Ad / 2 0

5 3 b / 0. 1

0.35-0.5 6 3 0 3-56 0 thic k enough s o a s t o no t imped e dispersio n 0.01-0. 3

0.3-0. 6 N/ Ad / 2 0

1.8-2. 8 0.6- 1 0. 6 1. 7 0. 2 3 0

5 0 c / 6 0 c / 5 0 cl 30 5

a / Value s fo r retardatio nfactor s ar e no t given ; instea dth e tabl e indicate s whethe r th e mode l consider s retardation . b / I nCRAM , saturate daquife r thicknes s ha s a nexponentia l probabilit ydistributio nwit ha mea no f 53 . c / Thes e ar e th e shortes t distance s t o well s use db yth e models : th e dispersivit yvalue s reported , whic har e dependen t o ndistance , ar e base do nthes e minimumdistances , d / No t applicable ; velocit yandporosivit yar e no t use di nth e VH S model .

B-2 3P.9 4



### EXHIBI T B- 5 FIEL DMEASUREMEN T AN DMODE L CALIBRATION VALUE S FO RDISPERSIVIT YFO RALLUVIA L AQUIFER S Fiel d Measurement s ~ Mode l Calibratio n Value s

Transvers e Longitudina l Transvers e Dispersivit yDispersivit yDispersivit y (m ) (m ) (m ) Settin g Chal k River , Ontari o Lyons , Franc e Alsace , Franc e Barstow , C A Rock yMountai n Arsena l Arkansa s Rive r Valle y Californi a Sutte r Basin , < Longitudina l

Dispersivit y (m ) 0.034-0. 1 0.1-0. 5 

### 1 2 15. 2



### C A 1 5 6 1 30. 5r-l



### 1 8 30. 5 30. 5 30. 5 80-20 0 9. 1

9. 1 8-2 0

Source : Table s 4. 1 an d 4. 2 i n Codell , R . an d Duigid , J. , "Transpor t

o f Radionuclide s i n Groundwater, " Chapte r 4 , Radiologica l Assessment . Till , J. , an d Meyer , H. , eds. , U.S . Nuclea r Regulator yCommission , Septembe r 1983 .

B-2 4

### I n comparing th e dispersivit yvalue s use d i n th e R Q mode l t o

th e value s i n Exhibi t B-5 , th e R Q model' s value s ar e o n th e high sid e fo r fiel d measure d value s an d o n th e lowsid e fo r mode l calibratio n values . EPAconsider s th e dispersivit yvalue s use d i n th e R Q mode l t o b e realisti c fo r a nalluvia l aquifer . Th e dispersivit yvalue s use d i nth e RCR Amodel s ar e generall yo nth e lo wsid e o f th e fiel d measure d values , and significantl ylowe r tha n th e value s obtaine d fro mth e mode l calibrations . Th e model s develope d b yth e EPAOffic e o f Soli d Wast e fo r applicatio n t o RCR

Aar e ris k base d an d a s suc har e believe d t o b e mor e conservativ e tha n necessaryfo r developmen t o f reportabl e quantitie s whic hac t a s a trigge r fo r notificatio n o f a releas e o f a hazardou s substance . Fo r thi s reason , th e Agenc yha s decide d t o us e th e advection-dispersio nmode l fo r determinatio n o f Releas e Value s base d o n a ground-wate r ingestio nscenario . B. 3 SURFAC E WATE RTRANSPORT O F RADIONUCLIDE S Surfac e wate r use d fo r drinking purpose s i nth e Unite d State s generall ycome s fromlakes , reservoirs , o r rivers . Lake s an d reservoir s ar e simila r i n tha t the yar e generall ylarg e bodie s o f wate r wit hrelativel ylo wflowrate s whe ncompare d t o rivers . Becaus e o f thei r size , dilutio nfactor s fo r radionuclide s i n lake s an d reservoir s ar e expecte d t o b e muc h large r tha n thos e fo r rivers , an d th e Agenc yha s chose nt o mode l consumptio n o f contaminate d surfac e wate r wit hreferenc e t o smal l river s i n preferenc e t o lake s o r reservoirs . B.3. 1 Calculatio n o f a Dilutio n Facto r fo r Rive r Wate r Equatio n (1 ) ca n b e use d t o calculat e a drinking wate r Releas e Valu e fo r rive r wate r i f a dilutio nfacto r fo r thi s sourc e o f wate r ca n b e determined . Equatio n (14 ) ha s previousl y B-2 5P.9 6



### bee n recommende d b yth e Agency 8 

### fo r th e calculatio no f downstream concentration s o f pollutant s afte r releas e fro ma poin t source . C x

### = {[Q]*[exp(

- Xx/u)]}/ F (14 )

where : C x

### = maximu

mcontaminan t concentratio n3 0 meter s downstream(Ci/liter) ; Q = contaminan t releas e rat e (Ci/day) ; F = surfac e wate r flowrat e (liter/day) ; X= radioactiv e decayconstan t (0.693/two , sec -1



### . Fo r th e reason s discusse d above , radioactiv e decayi s ignore d i n thi s calculatio nan d th e radioactiv e half

life , tw2 ' i s 

### considere d t o b e infinite) ; x= distanc e fro mpoin t o f releas e t o poin t o f exposur e (3 0 meters) ; an

d u = mea n strea

mvelocit y(0.6 4 meter/sec) . I n applying thi s equatio nth e following assumption s ar e made : o th e releas e i s a ninstantaneou s poin t sourc e and th e rive r i s homogeneou s an d isotropic ; o prio r t o th e momen t o f release , th e concentratio no f radionuclid e i n th e rive r i s zero ; o contaminan t an d rive r wate r mi xcompletel yan d instantaneousl yan

d ther e i s n o longitudina l dispersion ; o exposur e occur s 3 0 meter s downgradien t from th e poin t o f release ;

8 

### U.S . Environmenta l Protectio n Agency , Offic e o f Emergenc yan d Remedia l Response , "Superfund Exposur e Assessmen t Manual, " Fina l Draft , prepare d b

yVersar , Inc. , Septembe r 22 , 1987 .

B-2 6P.9 7



### o a smal l rive r i s assume d wit ha flowrat e o f 1 xIO 9 

### liter s pe r day(abou t 40 0 cubi c fee t pe r second ) an d a velocit yo f abou t 0.6 4 meter s pe r second 9 

### ; o remova l o f th e release d radionuclid e b yothe r processe s (e.g. , settling , vaporization ) i s ignored ; an d o radioactiv e decayduring transpor t i s neglecte d becaus e th e transpor t time t o a poin t 3 0 meter s downstreami s shor t an

d decayove r thi s shor t perio d o f tim e i s negligibl e fo r al l bu t a handfu l o f radionuclides . Wit hth e radioactiv e decayconstan t se t t o zer o (i.e. , n o decayi s considered ) equatio n(14 ) simplifie s to : C x

### = Q/F . (15 ) Usin g a valu e o f 1 xIO 9 

### liter s pe r dayfo r F i nequatio n (15 ) i s reasonabl yconservativ e becaus e onl yabou t 1 5 percen t o f surfac e wate r i n th e Unite d State s flow s a t a rat e slowe r tha n thi s value 10



### . Becaus e concentratio n an d surfac e wate r flo wrat e ar e inversel yproportional , a highe r flowrat e woul d lead t o a lower , les s conservativ e concentration . Substituting th e sourc e term , l curie , fo r Q i n equatio n(15 ) gives : C x

### = ( 1 Ci/day)/( l xIO 9 

### liter/day ) (16 ) C x

### - 1 x10~ 9 

### Ci/liter . (17 ) Equatio n (17 ) give s th e amoun t o f dilutio nfo r a on e curi e releas e int o a smal l river . Th e dilutio nfacto r (DF ) fo r us e i n

9 

### U.S . Environmenta l Protectio n Agency , Offic e o f Soli d Waste , "Th e RCR

ARisk-Cos t Analysi s Mode l Phas e II I Report, " prepare d b y ICF , Inc. , Marc h1 , 1984 .

10 

### "Determinatio n o f Harmfu l Quantitie s an d Rate s o f Penalt yfo r Hazardou s Substances, " EPA-440/9-75-005 , Volume s a-d , January , 1975 . B-2 73 .9 8



### calculatin g surfac e wate r releas e value s is , therefore , define d as : D F = 1 xIO" 9 

### liter" 1



### . (18 ) Radioactiv e decayove r th e perio d o f ingestio ni s ignore d and a 1 daycontac t tim e (CT ) i s use d i nequatio n(1) . Th e Agenc ybelieve s tha t i t i s appropriat e t o ignor e radioactiv e decayunde r thes e circumstance s because , a s i s th e cas e fo r radionuclid e inhalation , i t i s no t possibl e t o establis hexac t bound s o n th e rang e o f exposur e periods . Anindividua l coul d consum e a dail yquantit yo f wate r ove r a fewminutes , allowing littl e decayfo r a short-live d radionuclide , o r ove r th e perio d o f a n entir e day . Substituting value s fo r DF , CT , an d W C int o equatio n (1 ) an d solving fo r th e drinkin g wate r releas e valu e base d o nconsumptio n o f contaminate d rive r wate r give s equatio n(19) : River-wate r Ingestio n = AL I . (19 ) Releas e Valu e 0.0 2 Compariso n o f releas e value s calculate d b yus e o f equatio n(19 ) an d thos e releas e value s calculate d fo r ground wate r ingestion , inhalation , consumptio n o f contaminate d vegetables , and direc t exposur e show s tha t i n n o cas e i s th e river-wate r ingestio n releas e valu e th e lowes t o f th e calculate d releas e value s an d n o RQ s ar e determine d byus e o f equatio n(19) . Fo r thi s reason , th e Agenc yuse d th e equatio n calculating ground-wate r ingestio n releas e valu e [equatio n (13) ] t o mode l ingestio no f contaminate d drinkin g water .

B-2 8P.9 9



### APPENDI XC MODELINGTH E INGESTIONO F CONTAMINATE D

FOODSTUFF S Anumbe r o f model s hav e bee n develope d t o describ e th e transfe r o f radionuclide s t o variou s foodstuff s an d the nt o ma n afte r a n atmospheri c radioactiv e release. 1 

### Thes e model s typicall ybegi n wit han estimat e o f th e radionuclid e ai r concentratio n abov e th e food crop o r pastur e an d subsequentl y calculat e th e radionuclid e concentratio n i nan d o nth e foo d crop o r forage . Th e leve l o f contaminatio ndepend s upo nman yfactor s including th e rat e a t whic hth e radionuclid e i s deposited , th e fractio n retaine d b yth e plan t leaf , th e area l densit yo f th e crop , an

d th e transfe r rat e betwee n soi l an d crop . Equation s relating thes e variable s generall yinclud e compartment s describing mechanism s fo r remova l o f radionuclide s fro mcrop s throughweathering an d radioactiv e decay . I naddition , model s hav e bee n develope d whic hdescrib e th e transpor t o f radionuclide s t o ma n throughmil k (th e so-calle d air-grass-cow-milk-ma n pathway) , meat , an d vegetabl e crop s o r forag e contaminate d b y contac t wit hcontaminate d irrigatio n water . Th e Agenc yha s analyze d thes e pathway s fo r th e purpos e o f calculating RQ s an d describe s th e result s o f thes e analyse s i n thi s Appendix . EPAha s decide d t o us e releas e value s calculate d a s a resul t o f airborn e contaminatio no f leaf yvegetable s a s a componen t i n th e determinatio n o f reportabl e quantitie s fo r radionuclides . Thi s rout e wa s chose n i npreferenc e t o th e irrigatio npathway because , a s i s show n i nth e discussio no f thi s pathway , th e amoun t o f radionuclid e provide d t o ma nvi a irrigatio no f vegetable s wit hground wate r will , unde r th e modeling condition s ^-Nair , S. , "Model s fo r th e Evaluatio no f Ingestio nDose s Fromth e Consumptio n o f Terrestria l Food s Following an Atmospheri c Radioactiv e Release. " Centra l Electricit yGenerating Board , BerkeleyNuclea r Laboratories , England , April , 1984 . C- lP.10 0



### analyzed , alway s b e les s tha n tha t provide d b ydirec t consumptio n o f th e contaminate d ground water . Mil k and/o r mea t contaminatio n ca n b e a n importan t pathwayfo r radionuclid e consumptio nb yma n afte r a n airborn e o r waterborn e releas e o f radionuclides . Thes e pathways , however , wer e no t chose nfo r th e calculatio no f releas e value s becaus e radionuclid e concentration s foun d i nmea t an

d mil k ar e highl ydependen t upo n elemen t specifi c transfe r factor s betwee n th e forag e o r wate r an d th e anima l products . Thes e transfe r factor s ar e availabl e fo r onl ya fewelement s and th e equations , therefore , ca n onl yb e use d fo r a fractio no f radionuclides . Sectio n C l document s th e equatio n use d b yth e Agenc yt o calculat e releas e value s fo r food ingestion . Sectio nC. 2 present s i n detai l th e applicatio n o f thi s mode l t o airborn e depositio n o f radionuclide s o nvegetabl e crop s an d discusse s th e irrigatio n mode l investigate d b yth e Agency . Sectio nC. 3 briefl y describe s th e approache s considere d b yth e Agenc yfo r evaluatio n o f contaminate d mea t an d milk . C l TH E FOO D INGESTIONMODE L Th e siz e o f th e releas e i ncurie s necessaryt o provid e a 50 0 millire mexposur e t o a membe r o f th e genera l publi c throughth e consumptio n o f contaminate d vegetable s i s th e Vegetabl e Ingestio n Releas e Value . Thi s quantit yi s directl yproportiona l t o th e annua l limi t o f intak e fo r ingestio n an d inversel yproportiona l t o th e concentratio n o nan d i n th e vegetables , th e dail yrat e o f foo d consumption , th e contac t time an d th e releas e fractio nfo r th e radionuclide . Thi s relationshi p i s summarize d i nequatio n (1) . Vegetabl e Ingestio n Releas e Valu e = ALI/[(10)*(DF)*(FC)*(CT)*(R)*( 1 xIO 6 

### ) ] (1 ) (curies ) C- 2_p, 1



### where : AL I = annua l limi t o f intak e fo r ingestio n(microcuries) ; 1 0 facto r t o conver t th e annua l limi t o f intak e whic hi s base d o n 5 remdose-equivalen t t o a worke r i na nuclea r facilit yt o th e mor e conservativ e 0. 5 remfo r exposur e t o th e genera l public ; D F = dilutio n facto r - th e concentratio no f radionuclid e i n an d o n th e vegetatio npe r curi e o f radionuclid e release d t o th e atmospher e (Ci/k g pe r C i release d o r 1/k g - derivatio n o f thi s termi s describe d i nSectio n C. 2 below) ; F C = food consumptio n(i.e. , leaf yvegetable ) o f referenc e ma n (0.17 5 kg/day- U.S . Nuclea r Regulatory Commission , RegulatoryGuid e 1.109 , October , 1977 . Pag e 40.) ; C T - contac t time , o r th e numbe r o f day s ove r whic hth e contaminate d vegetable s ar e ingeste d (derivatio no f thi s termi s describe d below) ; R= airborn e releas e fractio n (se e Appendi xAfo r a discussio n o f releas e fractions) ; an d 1 xIO 6 

### conversio n facto r betwee n microcurie s an d curies . Th e ingestio n ALI s use d i n th e calculation s ar e take nfro m ICRP' s Publicatio n 30 2 

### afte r conversio nfro mbecquerel s t o microcuries . Wher e mor e tha n on e ingestio nAL I wa s give n fo r a particula r radionuclide , th e lowes t valu e wa s use d i nth e calculations . C. 2 DETERMINATIONO F TH E DILUTIONFACTOR Tw o approache s fo r modeling th e concentratio n o f radionuclide s i n an d o n vegetabl e crop s afte r anairborn e releas e wer e evaluated . Th e firs t use d anequatio npublishe d b yth e Nuclea r RegulatoryCommissio nan d th e secon

d a simila r equatio n internationa l Commissio no n Radiologica l Protectio n(ICRP) , "Limit s fo r Intake s o f Radionuclide s b yWorkers, " Publicatio n30 , Par t 2 , 1980 . C- 3P. 2



### develope d b

yth e Nationa l Counci l o nRadiatio nProtectio n an d Measurement s (NCRP ) an d recommende d b

ythemt o mode l th e effect s o f continuou s o r intermitten t release s o f radioactiv e materia l t o th e environment . C.2. 1 The Nuclea r Regulator y Commissio

nModel 3 

### Th e Nuclea r RegulatoryCommissio n mode l estimate s th e concentratio n o f radionuclide s o n an d i n vegetatio nproduce d b y depositio n ont o th e plan t foliag e fro mai r an

d b yuptak e fro

m activit yinitiall ydeposite d o nth e ground . Th e mode l i s vali d fo r particulat e radionuclide s excep t tritiu man d carbon-14 . Th e Commissio n provide s value s fo r th e model' s variou s inpu t parameter s t o allo wth e us e o f th e equatio nfo r differen t purpose s suc ha s estimating concentration s i n produc e consume d b y man ; i n leaf yvegetable s consume d b yman ; o r i n forag e consume d b yanimal s an

d converte d t o mea t o r mil k consume d b yman . Th e equatio n contain s a termfo r th e depositio nrat e o f a radionuclid e (d^) , whic hi s calculate d b yreferenc e t o a secon d RegulatoryGuide 4 

### an d whic huse s atmospheri c dispersio n estimate s t o deriv e th e ai r concentratio na t variou s distance s downwind fro ma release . EPAuse d th e Nuclea r RegulatoryCommission' s mode l fo r th e developmen t o f propose d RQ s fo r radionuclides ; however , afte r a re-evaluatio n o f th e Nuclea r RegulatoryCommissio nan d NCR P models , EPAdecide d t o us e th e NCR P mode l fo r developmen t o f th e fina l RQs . Thi s chang e wa s mad e mainl ybecaus e i t wa s determine d

3 

### Nuclea r RegulatoryCommission , "Calculatio n o f Annua l Dose s t o Ma n FromRoutin e Release s o f Reactio nEffluen t fo r th e Purpos e o f Evaluatin g Complianc e wit h1 0 CF RPar t 50 , Appendi xI. " RegulatoryGuid e 1.109 , October , 1977 .

4 

### Nuclea r RegulatoryCommission , "Method s fo r Estimating Atmospheri c Transpor t an d Dispersio no f Gaseou s Effluent s i n Routin e Release s from Light-Water-Coole d Reactors. " Regulatory Guid e 1.111 , July , 1977 . C- 4P. 3



### tha t th e assumption s an d calculationa l technique s use d t o develop th e Commission' s methodologymak e i t unsuitabl e fo r applicatio n t o a distanc e o f 3 0 meter s fro ma nassume d poin t source . Th e Commission' s approac hwa s develope d specificall yfo r consideratio n a t nuclea r powe r plant s wit hparticula r releas e characteristic s an

d relativel ylarg e distance s (i.e. , severa l hundre d meter s an

d beyond ) t o a potentia l recepto r o f interest . Accordingly , EPAconclude d tha t extrapolatio no f relativ e depositio n rate s presente d i nRegulatoryGuid e 1.11 1 t o a distnc e o f 3 0 meter s woul d no t b e accurate . C.2. 2 Th e NCRP Model 5 

### Th e NCR P mode l wa s designe d t o addres s continuou s o r intermitten t release s o f radioactiv e materia l t o th e environmen t an d ai d i n th e design o r redesigno f facilitie s handling radionuclide s s o tha t thei r projecte d emission s ca n b e compare d wit henvironmenta l standards . Th e mode l i s verysimila r t o th e Nuclea r RegulatoryCommissio nmodel , bu t incorporate s a termfo r th e depositio n rat e o f radionuclide s fro mai r t o crop s tha t i s generall ybelieve d t o b e mor e suitabl e tha n th e Commission' s mode l fo r th e 30-mete r distanc e use d i n thi s analysis . Th e equatio n allow s fo r th e time perio d tha t crop s ar e expose d t o contaminatio n during th e growing seaso nan d therefor e ca n b e applie d t o episodi c releases . Severa l assumption s ar e mad e i n applying thi s mode l t o th e specifi c circumstance s o f releas e considere d here , an d include :

o th e releas e i s a nepisodi c releas e an d al l radio

nuclide s whic har e going t o become airborn e an d b e subjec t t o depositio no no r nea r a crop ar e release d i n on e dayo r less ;

5 

### "Screenin g Technique s fo r Determining Complianc e wit h Environmenta l Standards : Release s o f Radionuclide s t o th e Atmosphere. " NCR P CommentaryNo . 3 , Nationa l Counci l o n Radiatio n Protectio n an d Measurement , Marc h31 , 1986 .

C- 5P. 4



### o th e expose d vegetabl e cro p i s locate d 3 0 meter s downwind fro

mth e poin t o f releas e an d th e contaminate d foo d i s consume d o na dail ybasi s b ya n individua l fo r 6 0 day s (th

e lengt ho f th e growin g season) ; an d o radioactiv e decaywhic hmayoccu r betwee n th e tim e o f releas e an

d th e time o f depositio n o nth e vegetable s i s conservativel yassume d t o b e zer o (i.e. , X ^ = 0 ) becaus e th e time perio d o f releas e coul d b e a s shor t a s a fe wsecond s o r a s long a s on e day , and i s undefined . Th e NCR P equatio n along wit ha n explanatio n o f th e term s i s shown below :

C

## = V



## C•- " l 

## exp( 

## " X 

## E t 

## e ) 

## • B



## v 1"«P(- W ii r \t~~~ 

### 'vd air | YA

- P A

- 

## (2 ) where : C v

### = concentratio n o f radionuclid e i nand o nvegetatio n

(Ci/kg) ;

c 

### ai r = 

### concentratio n o f radionuclide s i n ai r a t th e locatio n o f growing vegetable s (8. 4 xIO" 7 

### Ci/meter 3 

### ) , wher e C a 

### i r 

### = (radionuclid e releas e rate)*(X/Q) ; X/ Q = atmospheri c relativ e concentratio n(8. 4 x10~ 7 

### day/meter 3 

### , se e Appendi xA) ; V< j = depositio n velocit yfo r we t and drydepositio n

(100 0 meter/day) ; f R

### = intercep t fraction , th e fractio no f deposite d activit yintercepte d an d retaine d b

yedibl e portion s o f th e crop (0.25 , dimensionless) ; X E 

### . = effectiv e decayconstan t fo r remova l o f th e

radionuclid e deposite d o n vegetatio n (1/day) , wher e 

## X E

## = X i + X w 

## ; X i = radioactiv e decayconstan t (1/day ) = 0.693/tw 2 = 

### ° ' X w

### = weatherin g decayconstan t (1/day ) = 0.693/t w 

### ; t 

### l/ 2 = 

### radioactiv e decayhalf-lif e fo r th e individua l

radionuclid e (day , radioactiv e decayoccurring durin g th e perio d o f releas e an d transpor t t o th e cro p i s ignored) ; C- 6P. 5



### t w

### = weathering half-lif e (1 4 days) ; t e 

### = tim e perio d o f above-ground crop exposur e t o

contaminatio n during th e growing seaso n( 1 day) ; Y- standing crop biomas s o f edibl e portio no f crop a t

harves t ( 2 kg/meter 2 

### ) ; By= concentratio n rati o fo r th e transfe r o f th e elemen t

t o th e edibl e portio no f a crop fromdrysoi l (dimensionles s an

d radionuclid e specific , se e Exhibi t C- l fo r a compilatio no f thes e values) ; X B 

### = th e effectiv e rat e constan t fo r remova l o f

radionuclid e fromsoi l (1/day) , wher e 

## X B

## = X i + X H L

## ; X H L 

### = rat e constan t fo r remova l o f radioelemen t fromsoi l

b yharvesting an

d leaching (2. 7 x10~ 5 

### day" 1 

### ) ; t D

### = perio d o f depositio n i n soi l ( 1 day) ; an d P = area l densit yfo r th e effectiv e roo t zon e i n soi l

(24 0 kg/meter 2 

### ) . Substituting th e appropriat e value s int o equatio n(2 ) an d solving gives : C v

### = = ( 1 xIO" 4 

### + 3. 5 xIO" 6 

### By ) Ci/kg . (3 ) Thi s become s a dilutio n facto r (DF ) throughdivisio nb yth e sourc e term , 1 curie : D F = ( 1 XIO" 4 

### + 3. 5 XIO" 6 

### By ) kg" 1



### . (4 ) Th e dilutio n factor , use d i n equatio n (1 ) fo r th e calcualtio n o f vegetabl e ingestio nreleas e values , represent s th e concentratio n o f radionuclid e i n an d o n vegetatio n pe r curi e o f radionuclid e releas e t o th e atmosphere ; i t i s i nunit s o f Ci/kg pe r Ci , o r kg" 1



### .

C- 7P. 6



### Th e Agenc yassume s tha t th e contaminate d vegetable s ar e consume d o n a dail ybasi s durin g th e growin g seaso n an d ar e no t stored . Th e growin g seaso n i s nominall yconsidere d t o b e 6 0 day s (t ) an d thu s woul d becom e th e contac t tim e (CT ) i n equatio n (1 ) i f on e wer e t o ignor e radioactiv e deca yan d remova l o f radionuclid e fro m th e vegetatio n byweatherin g processes . I n fact , becaus e radionuclide s ar e remove d b ybot hdeca yan d weatherin g i n a n exponentia l fashion , ther e i s a n "equivalent " contac t tim e tha t depend s upo n th e lengt ho f th e growin g an d consumin g seaso n (t ) an d th e rat e o f los s du e t o deca yan d weathering . Thi s equivalen t contac t tim e i s calculate d i n th e followin g way :

1 - exp (

- X E 

### t ) C T = . (5 )

X E
Substitutio n fo r X E 

### gives :

1 - exp [- ( X i + X w 

### )*t ] C T - . (6 )



## X i + 

## X

w Substitutio n fo r X i an d X w

### yields :

1 - exp{-[(0.693/t 1/2 

### ) + (0.693/t w 

### )]*[t] } C T = . _. (7 )

(0.693/t 1/2 

### ) + (0.693/t w 

### )

Usin g a valu e o f 6 0 day s fo r t an d a valu e o f 1 4 day s fo r th e weatherin g hal f lif e (t w 

### ) , equatio n (7 ) simplifie s to :

1 - exp-[(41.6/t 1/2 

### ) + 3 ] C T - = _. (8 ) (0.693/t 1 

### / 2 

### ) + 0.049 5 C- 8P. 7



### Substitutin g appropriat e value s fo r D F an d F C int o equatio n (1 ) gives : Vegetabl e Ingestio n AL I (ingestion ) Releas e Valu e = , (9 ) (curies ) (17 5 + 6. 1 _v)*(R)*(CT ) wher e C T i s calculate d usin g equatio n (8) . Applicatio n o f thi s equatio n t o thos e radionuclide s fo r whic hALI s ar e availabl e produce s th e foo d ingestio n releas e value s show n i n Appendi xE .



### C- 9P. 8



### EXHIBI T C- l SOI L T O PLAN T CONCENTRATIO NFACTOR S (Bv )

B v 0.003 5 0.004 0 0.005 5 0.2 0 0 0.04 0 1. 0 0.1 5 0.00 1 0.01 0 0.03 5 1. 5 0.5 5 3 . 5 0.00 1 0.01 0 0.08 0 7 0 0.007 5 0.02 0 0.4 0 0.0008 5 0.01 0 0.00 1 0.01 0 0.01 0 0.00 1 0.06 0 0.03 0 

### ELEMENT Actiniu m Aluminu m Americiu

m Antimon y Argon * Arseni c Astatin e Bariu m Berkelium* * Berylliu

m Bismut h Bromin e Cadmiu m Calciu m Californium* * Ceriu m Cesiu m Chlorin e Chromiu m Cobal t Coppe r Curiu m Dysprosiu

m Einsteinium* * Erbiu m Europiu m Fermium* * Fluorin e Franciu m SYMBO L

AC A l A m S b A r A s A t B a Bk B e B i B r Cd C a C f C e C s C l C r C o C u C m D y E s E r E u F m F F r

C-1 0P. 9



### EXHIBI T C- l SOI L T O PLAN T CONCENTRATIO NFACTOR S (Bv )



## Sv 0.01 0 0.004 0 0.4 0 0.4 0 0.003 5 0.01 0 0.01 0 0.004 0 0.1 5 0.05 5 0.004 0 0 0.01 0 0.04 5 0.01 0 1. 0 0.2 5 0.001 0 0.9 0 0.2 5 0.01 0 0.1 0 0.06 0 0.02 0 0.01 5 0.1 5 3. 5 0.09 5 0.0004 5 

### ELEMENT Gadoliniu

m Galliu m Germaniu

m Gol d Hafniu m Heliu m Holmiu m Indiu m Iodin e Iridiu m Iro n Krypton * Lanthanu

m Lead Lutetiu m Magnesiu

m Manganes e Mendelevium* * Mercury Molybdenu

m Neodymiu

m Neptuniu

m Nicke l Niobiu m Osmiu m Palladiu

m Phosphoru s Platinu m Plutoniu

m SYMBO L

G d Ga G e A U H f H e H o I n I I r F e K r L a Pb Lu Mg M n Md H g M o N d N p N i N b O S Pd P P t P u C-l lP.1 0



### EXHIBI T C- l SOI L TO PLAN

T CONCENTRATIONFACTOR S (Bv )

ELEMENT SYMBO L B v Poloniu mP o 0.002 5 Potassiu

mK l. o Praseodymiu

mP r 0.01 0 Promethiu

mP

m0.01 0 Protactiniu

m P a 0.002 5 Radiu m R a 0.01 5 Radon * Rn o Rheniu mR e 1. 5 Rhodiu mRh0.1 5 Rubidiu mR b0.1 5 Rutheniu

mR u 0.07 5 Samariu mSm0.01 0 Scandiu mS c 0.006 0 Seleniu mS e 0.02 5 Silico n s i 0.3 5 Silve r Ag 0.4 0 Sodiu m Na 0.07 5 Strontiu

mS r 2. 5 Sulfu r S 1. 5 Tantalu mT a 0.01 0 Technetiu

m T c 9. 5 Telluriu

mT e 0.02 5 Terbiu mTb0.01 0 Thalliu mT l 0.004 0 Thoriu mTh0.0008 5 Thuliu mT m0.01 0 Ti n S n 0.03 0

C-1 2P.1 1 

# I I I i i i i i i i 

# I i i i i 

# l i 

# I i EXHIBI T C- l SOI L T O PLAN

T CONCENTRATIONFACTOR S (Bv )

ELEMENT Titaniu m Tungste n Uraniu m Vanadiu m Xenon * Ytterbiu

m Yttriu m Zin c Zirconiu

m SYMBO L

T i W U V X e Y b Y Z n Z r 

### -i v 0.005 5 0.04 5 0.008 5 0.005 5 0 0.01 0 0.01 5 1. 5 0.002 0



### * Assumptio n fo r nobl e gases . * * EMS I Estimat e Source : CF . Bae s III , R.D . Sharp , A.L . Sjoreen , R.W . Shor , " A

Revie wan

d Analysi s o f Parameter s fo r Assessin g Transpor t o f Environmentall yRelease d Radionuclide s ThroughAgriculture, " ORNL-5786 , September , 1984 .

C-1 3

### C2. 3 Th e Irrigatio n Mode l

I n additio n t o th e contaminatio no f vegetabl e crop s through airborn e depositio n o f radionuclides , crop s ca nb e contaminate d throughirrigatio n wit hcontaminate d water . Th e mode l presente d i n Sectio n C l ca n b e use d t o calculat e a releas e valu e fo r contaminatio n throughirrigatio ni f th e releas e fractio n (R) , develope d fo r airborn e releas e o f radionuclide , i s se t equa l t o one . Al l othe r variable s i n th e equatio n hav e th e same definitio n an

d th e equatio nbecomes : Irrigatio n Releas e Valu e = ALI/[(10)*(DF)*(FC)*(CT)*( 1 xIO 6 

### ) ] . (10 ) (curies ) Th e radionuclid e tha t contact s th e vegetabl e cro p i s containe d i n th e irrigatio n wate r rathe r tha n i na nairborn e plume , an

d th e following assumption s ar e made :

o th e contaminate d wate r i s pumpe d fro ma wel l 3 0 meter s downgradien t fro

mth e radionuclid e releas e an d th e concentratio n i nth e contaminate d wate r i s th e same a s tha t calculate d i nth e ground-wate r ingestio nmode l foun d i n Appendi xB ; o th e cro p i s watere d dail yduring th e 6 0 daygrowing season , 5 1 day s wit huncontaminate d wate r an d 9 day s wit hcontaminate d wate r (se e Appendi xB) ; an d o th e leaf yvegetable s ar e eate n a s harveste d an d no t stored . Th e Nuclea r RegulatoryCommissio nprovide s equatio n(11) 6 

### fo r calculatio n o f radionuclid e concentratio ni nvegetatio ndu e t o irrigatio n wit hcontaminate d water .

6 

### U.S . Nuclea r RegulatoryCommission , "Calculatio n o f Annua l Dose s t o Ma n FromRoutin e Release s o f Reactio nEffluen t fo r th e purpos e o f Evaluating Complianc e wit h1 0 CFRPar t 50 , Appendi x I. " RegulatoryGuid e 1.109 , October , 1977 . C-1 4 

# I

1 1 i I i t f I i i f 1 i I i I iP.1 3



### C = C I vw r[l-exp(

- X E 

### t e 

### ) ] f.B v 

### [l-exp(

- X._

b 

### ) ] Y 

### v X 

### E PX 

### i exp(

- x^ ) (11 ) 

### where : C v

### = = concentratio n o f radionuclid e i nth e edibl e portio no f th e cro p (Ci/kg) ; C w

### - concentratio n o f radionuclid e i nirrigatio nwate r (7. 6 x10~ 8 

### /R d Ci/liter , se e Appendi xB) ; I = averag e irrigatio nrat e during th e growin g seaso n(2. 5 liter s pe r squar e meter-day , liter/m 2 

### -day) ; r - fractio n o f deposite d activit yretaine d o ncrop s (0.25 ) ; 

## X E

## = X i + X w 

## ; Xi- 0.693/t 1 

## / 2 

## ; Xw

## = 0.693/t w 

## ; t_/ 2 ~ radionuclid e hal f life ; t w

### = weatherin g hal f lif e (1 4 day) ; t e 

### = tim e perio d crop s ar e expose d t o contaminatio nduring th e growin g seaso n( 9 day) ; Y v

### = agricultura l yiel d ( 2 kg/m 2 

### ) ; f j = fractio n o f yea r crop s ar e irrigate d wit hcontaminate d wate r (9/365) ; Bv= concentratio n facto r fo r soi l uptake ; t ^ - perio d o f tim e soi l i s expose d t o contaminate d wate r ( 9 day ) ; P = effectiv e surfac e densit yo f soi l (24 0 kg/m 2 

### ) ; an d t n

### = tim e betwee n harves t an d consumptio n( 0 day) . Substituting th e appropriat e value s int o th e irrigatio n mode l (ignoring radioactiv e deca yan d setting R ^ equa l t o one) , C-1 5P.1 4



### an d dividing b

yth e sourc e term , 1 curie , t o yiel d a dilutio n facto r (DF ) gives : D F = [1. 7 XIO" 7 

### + (1. 9 X10~ i:L 

### )*(Bv ) ]/kg . (12 ) Th e second termi n equatio n(12 ) i s approximatel yon e ten
thousandt h(1/10,000 ) o f th e firs t ter man d canb e ignore d o n substitutio n int o equatio n(10 ) t o yiel d equatio n(13) . Irrigatio n Releas e Valu e = ALI/[(0.3)*(CT) ] (13 ) (curies ) Unde r th e same conditions , th e drinking wate r releas e valu e obtaine d i n Appendi xB is : DWReleas e Valu e = ALI/[(1.5)*(CT)] . (14 ) Equatio n (14 ) wil l alway s yiel d a releas e valu e abou t 5 time s smalle r tha n tha t give n b yequatio n(13) . Fo r thi s reason , i t i s no t necessaryt o furthe r conside r th e irrigatio nrout e fo r calculatio n o f releas e values . C 3 INGESTIO

N OF CONTAMINATEDMEA T O RMILK Radionuclide s whe n release d t o ai r ca ncontaminat e anima l forag e or , i f release d t o water , ca ncontaminat e anima l drinking water . I n eithe r case , radionuclide s ca nb e consume d b yanimals . Afte r consumptio n b ydomesti c animal s suc ha s mil k producin g cow s o r bee f cattle , radionuclide s ca n b e foun d i n th e mil k an

d mea t an d provid e a rout e fo r th e exposur e o f man . Th e ingestio nmode l foun d i n Sectio n C l [equatio n(1) ] ca nb e use d t o calculat e a releas e valu e fo r th e mea t o r mil k rout e afte r a nairborn e radionuclid e releas e i f th e appropriat e dilutio nfacto r (DF ) can b e derived . Similarly , equatio n (1 ) i n sectio nB. l ca nb e use d C-1 6P.1 5



### t o calculat e a releas e valu e fo r th e mea t o r mil k rout e afte r a releas e t o drinking water . Th e Nuclea r RegulatoryCommissio n provide s equatio n(15 ) fo r calculating th e concentratio n o f radionuclid e i n mea t o r milk. 7 

### Thi s equatio n contain s compartment s fo r calculating th e concentratio n i n forag e an d th e concentratio ni nwate r an d can b e spli t t o provid e tw o equations , (16 ) an d (17) , separating airborn e fro

mwaterborn e releases .

c 

### i A= F 

### iA( c 

### iFQ F + c 

### iAwQAw ) (15 )
c 

### i A(airborne ) = Fi A 

### Ci F 

### Q F 

### (16 ) C i A

### (waterborne ) = F i A 

### C iAw 

### Q A w

### (17 ) where : Ci A

### = concentratio no f radionuclid e i nanima l produc t

(Ci/lite r fo r mil k o r Ci/kg fo r meat) ; Fi A

### = transfe r coefficien t o f radionuclide , th e fractio n

o f th e dail yintak e tha t i s transferre d t o mil k (day/liter ) o r mea t (day/kg ) - thi s valu e i s elemen t dependent ; Ci E 

### = concentratio n o f radionuclid e i n forag e (Ci/kg) ; Qp = feed consume d dail yb yanima l (kg/day) ;

c 

### iA w~ concentratio no f radionuclid e i n wate r (Ci/liter) ;

an d QA W= 

### wate r consume d dail yb yanima l (liter/day) . Equation s (15) , (16 ) an d (17 ) canb e divide d b yth e sourc e term , 1 curie , t o produc e a dilutio n facto r (DF ) i nliters" 1 

### o r kg" 1



### . Avalu e fo r Ci F 

### ca n b e foun d throughapplicatio no f equatio n(2 )

7 

### U.S . Nuclea r RegulatoryCommission , "Calculatio no f Annua l Dose s t o Ma n FromRoutin e Release s o f Reacto r Effluent s fo r th e Purpos e o f Evaluating Complianc e Wit h1 0 CF RPar t 50 , Appendi x I. " RegulatoryGuid e 1.109 , October , 1977 . C-1 7P.1 6



### i n thi s Appendi xan d a valu e fo r Ci A w

### ca n b e foun d through applicatio n o f equatio n (7 ) i nAppendi xB . Thes e equation s ar e vali d fo r al l radionuclide s excep t tritiu m an d carbon-14 . Value s fo r Fi A 

### , th e radionuclid e transfe r coefficient , ar e compile d b yth e Nuclea r RegulatoryCommissio n i n RegulatoryGuid e 1.10 9 (referenc e 7) . Value s fo r thi s variabl e ar e experimentall yderive d an d availabl e fo r onl ya fewelements . Fo r thi s reason , i f ingestio nreleas e value s fo r radionuclide s wer e base d o n th e mea t o r mil k ingestio nroute , the ycoul d no t b e calculate d fo r man

yo f th e 75 7 radionuclide s withou t estimating transfe r coefficients . Th e Agenc ybelieve s tha t i t i s bette r t o mode l ingestio n o f radionuclide s base d o nconsumptio no f leaf y vegetable s wher e soi l t o vegetabl e matte r transfe r coefficient s (Bv ) ar e bette r understoo d an d ar e a mino r componen t i n th e calculation .

C-1 8P.1 7



### APPENDI XD MODELIN GOF DIREC T EXPOSUR E T O RADIONUCLIDE S

I n orde r fo r a n exposur e t o anindividua l t o occu r afte r a releas e o f radionuclide , i t i s no t necessaryfo r tha t individua l t o inges t o r inhal e th e radionuclide . Becaus e radionuclide s produc e radiatio n tha t ca n b e propagate d throughair , i t i s possibl e fo r a n exposur e t o occu r i f a nindividua l i s physicall yi n th e vicinit yo f th e release d radionuclide . Thi s typ e o f exposur e i s terme d direc t exposure . Becaus e alpha particles , eve nver yenergeti c alpha particles , hav e a ver yshor t rang e i nair , i t i s unnecessaryt o includ e exposur e t o alpha particle s i nth e model . Bet a particle s hav e a longe r rang e i n ai r than alpha particles , bu t onl yveryhigh energ ybet a particle s whic har e produce d onl yb ya veryfew radionuclide s hav e range s i n ai r approaching 3 0 meters , th e distanc e assume d i n th e model . Fo r thi s reason , th e Agenc yha s chose n t o mode l onl ydirec t exposur e t o gamma rays . Some uraniu

misotope s an

d a fewisotope s o f some transurani c element s decayb

yspontaneou s fissio n producin g neutron s whic hhav e range s i n ai r exceeding 3 0 meters . Becaus e direc t exposur e t o neutron s i n thes e fewcase s coul d delive r significan t radiatio n doses , th e Agenc yals o modele d thi s rout e an d foun d that , i never

y cas e o f spontaneou s fission , releas e value s calculate d fo r inhalatio n wer e considerabl ylowe r tha n thos e calculate d fo r direc t exposur e t o gamma ray s o r neutrons . Sectio n D. l discusse s exposur e t o fixe d poin t source s o f radiatio n whil e sectio nD. 2 develop s th e equatio n use d b yth e Agenc yfo r calculatio n o f direc t exposur e releas e value s fo r argon , krypto n an

d xeno n base d onsubmersio n i n a nairborn e cloud o f thes e nobl e gases .

D- lP.1 8



### D. l FIXE D POINT SOURCE S Th e Agenc ybelieve s tha t developmen t o f a direc t exposur e mode l base d o n exposur e t o a poin t sourc e o f soli d o r liqui d radionuclide , a s oppose d t o a lin e o r area l source , bes t represent s a sudden , episodi c releas e o f radionuclide . A s i s th e cas e wit h th e inhalatio n mode l an d th e ingestio n mode l use d t o calculat e releas e value s fo r radionuclides , th e exposur e i s assume d t o occu r a t a distanc e o f 3 0 meter s fromth e poin t o f release . Th e equatio n develope d i n sectio n D.l. l i s tha t use d t o calculat e th e releas e value s base d o n direc t exposur e t o suc ha poin t sourc e o f gamm a radiation , whil e th e equatio n develope d i n sectio nD.l. 2 wa s use d b yth e Agenc yfo r evaluatio n o f exposur e t o neutron s fro m spontaneou s fission . D.l. l Radionuclide s WhichEmi t Gamm a Rays Th e Radiologica l Healt hHandbook 1 

### provide s th e following equation s fo r determining gamma ra yexposur e an

d gamma ra

y absorptio n froma fixed poin t sourc e o f radiation .

I 0 

### = 0.15 6 n x

### E (IO 5 

### u a 

### ) (1 ) I = I o 

### e" 100u 

### a s 

### (2 ) R/hr = (n 2 

### I)/S 2 

### (3 ) where : I 0 

### = unshielde d exposur e rat e a t 1 mete r fro ma on e curi e poin t sourc e (R/hr-C i a t 1 meter) ; I = attenuate d radiatio nexposur e rat e (R/hr) ; n ^ - gamma quant a pe r disintegration ; ln 

### Th e Healt hPhysic s an d Radiologica l Healt hHandbook, " Nucleo n Lecter n Associates , Olney , MD , 1984 , page s 4 1 an d 45 . D- 2P.1 9



### E = energ yo f gamma quant a i nMeV ; u a 

### = linea r energ yabsorptio n coefficien t fo r gamm a ray s i nai r (a t standar d temperatur e (23°C ) an d pressur e ( 1 atm) ) i ncm" 1 

### ; n 2 = numbe r o f curies ; S = distanc e i nmeters ; an d R/hr-C i = exposur e rat e i nRoentge npe r hou r pe r curi e

o f release . Whe n combined , thes e thre e equation s become : R/hr-C i = [(1.5 6 x10 4 

### )*(n 1 

### )*(E)*(u a 

### )*(n 2 

### )*(e" 100u 

### a s 

### )]/S 2 

### (4 ) Th e valu e fo r u a 

### i s foun d i nth e Radiologica l Healt hHandboo k t o b e 3. 7 x10~ 5 

### cm" 1 

### fo r gamma ray s wit ha nenerg yo f 1 MeV . Th e valu e varie s wit hth e energ yo f th e gamma ra

yinvolve d bu t i s approximatel ycorrec t (±15% ) fo r gamma ray s wit henergie s ranging fro mabou t 0.0 7 MeV

t o abou t 2 MeV . Therefore , recognizing th e relativel ysmal l error , thi s singl e valu e fo r u a 

### i s use d fo r al l radionuclide s fo r th e sak e o f simplicity . The distance , S , use d fo r othe r exposur e route s i s 3 0 meter s an d i s use d here . Photo n attenuatio n i n ai r betwee n th e sourc e an d recepto r i s represente d b ye~ 100u 

### a s 

### . Incorporatio n o f a termfo r photo n attenuatio ni nth e equatio n result s i n a sligh t increas e i n th e direc t exposur e Releas e Valu e sinc e approximatel y1 0 percen t o f th e photon s emitte d fro mth e sourc e wil l b e absorbe d i n3 0 meter s o f ai r betwee nth e sourc e an

d th e receptor . A2 4 hou r exposur e duratio n(T ) wa s chose n becaus e RQ s ar e applicabl e fo r release s tha t occu r ove r a maximu m o f 2 4 hours . Althoughi t i s recognize d tha t i t i s unlikel y tha t an individua l actuall ywoul d remai n3 0 meter s awayfo r a ful l 2 4 hours , EPAcoul d no t conclud e tha t i t i s impossibl e and , therefore , use d a 24-hou r exposur e perio d t o assur e timel y reporting i n sucha n event . Ashorte r time period migh t rais e th e D- 3P.2 0



### releas e valu e t o suc ha nexten t tha t notificatio n migh t no t b e give n o f a releas e tha t woul d b e harmfu l i f anindividua l wer e t o b e expose d fo r 2 4 hour s o r othe r extende d period s clos e t o 2 4 hours . Multiplyin g b yT t o conver t Roentge n pe r hou r pe r curi e t o Roentge n pe r curie , th e equatio nbecomes : R/C i = [(1.5 6 x10 4 

### )*( ni 

### )*(E)*(u a 

### )*(n2)*(T)*(e- u a s 

### )]/S 2



### . (5 ) Roentge n i s approximatel yequa l t o remfo r gamma rays : 1 Roentge n = 9 5 ergs/gramo f sof t tissue ; 1 rad = 10 0 ergs/gram ; an d 1 rem= 1 rad (fo r gamma rays) . Therefore , 1 remi s approximatel yequa l t o 1 Roentge n fo r gamma rays . Substituting rempe r curi e o f releas e (Dn ) fo r Roentge npe r curi e (R/Ci ) an

d rearranging equatio n (4 ) t o solv e fo r n 2 

### gives :

n 2 

### = [(6.4 1 x10" 5 

### )*(Dn)*(S 2 

### )]/[(n 1 

### )*(E)*(u a 

### )*(T)*(e" 100u 

### a s 

### )] . (6 ) I n thi s application , th e valu e fo r n 2 

### i s th e direc t exposur e releas e value , representing th e numbe r o f curie s i n a poin t sourc e yieldin g a specifie d dose-equivalen t (Dn) . A s note d previously , th e term s n± an d E ar e th e gamma ra y fractio n an

d th e gamma rayenergy , respectively . Man y radionuclide s emi t mor e tha non e gamma ra ype r disintegratio no r the yemi t gamma ray s o f varyin g energies . Ofte neac ho f thes e gamma ray s ar e emitte d onl yfo r a specifi c fractio n o f disintegratio n events . I norde r t o accoun t fo r this , th e produc t o f th e energ

yo f eac hgamma ra yemitte d (Ei ) an

d th e fractio no f tim e i t i s emitte d (ni ) i s summe d t o produc e a value , E^ , whic h reflect s th e tota l gamma rayenerg yproduce d b

yeac hradionuclide . Th e metho d use d fo r thi s calculatio ni s show ni nequatio n (7) . D- 4P.2 1



### E1 

### = _ _[(ni)*(Ei) ] (7 ) i Some radionuclide s emi t positivel ycharge d electron s (positrons ) which , whe n theystrik e negativel ycharge d electrons , annihilat e on e anothe r an d produc e tw o gamma ray s wit ha nenerg yo f 0.51 1 Me V

each . Bot hannihilatio ngamma ray s ar e considere d i nthe calculation s fo r thos e radionuclide s whic hdecayb ypositro n emission . Substituting E ^ fo r th e produc t o f n^an d E an d using "Direc t Exposur e (DE ) Releas e Valu e (RV) " fo r n 2 

### yields : D E R V = [(6.4 1 X10" 5 

### )*(Dn)*(S 2 

### )]/[(E 1 

### )*(U a 

### )*(T)*(e" 100u 

### a S 

### ) ] (8 ) Equatio n (8 ) ca n b e use d fo r th e calculatio n o f direc t exposur e releas e value s whe nradioactiv e decayi s no t considered . I n orde r t o accoun t fo r radioactiv e decayduring th e perio d o f exposure 2 

### , thi s perio d [ T i nequatio n(8)] , mus t b e modifie d t o reflec t decreasing exposur e a t time s tha t ar e successivel ymor e distan t fro

m th e tim e tha t th e radionuclid e wa s release d (a n instantaneou s releas e i s assumed) . Th e equatio nuse d fo r thi s purpos e i s show

n below : 

## T= r24i*n-expf - xtn . (9 )

X

2 

### Radioactiv e decayoccurring during th e perio d o f releas e i s ignore d becaus e thi s perio d coul d b e a s shor t a s a fewsecond s o r a s long a s on e dayan d i s undefined . Similarly , becaus e i t i s impossibl e t o defin e th e time necessaryfo r anindividua l t o come int o contac t wit hth e release d radioactiv e material , th e Agenc y conservativel yassume d tha t n o decayoccur s ove r thi s "transpor t time" .

D- 5P.2 2



### where : t = perio d o f exposur e i ndays.( 1 day) ; X= radioactiv e decayconstan t (0.693/ti /2)

- ti/ 2 = radioactiv e half-lif e i n days ; and 2 4 conversio n facto r betwee nday s an d hours . Combining equatio n (8 ) wit hequatio n(9 ) yield s equatio n(10) . D E R V = (6.4 1 X10" 5 

### )*(Dn)*(S 2 

### ) (10 ) [E 1 

### ]*[u a 

### ]*[exp-(100u a 

### S)]*[24]*{[l-exp(

- Xt)]/ x} Substitutin g value s i n fo r Dn (0. 5 rem) , S (3 0 meters) , t ( 1 day) , u a 

### (3. 7 x10~ 5 

### centimeters) , an d X(0.693/t 1 

### / 2 

### ) ' th e 

### equatio n reduce s to : D E R V = 25. 1 . (11 ) [E 1 

### ]*[t 1/2 

### -t 1/ 2 

### exp(-0.693/t 1/2 

### ) ] Thi s equatio n i s identica l t o tha t showni nth e bod yo f thi s repor t and , excep t fo r thos e case s calculate d o n th e basi s o f submersio n i n a cloud o f radioactiv e nobl e gas , wa s use d t o calculat e th e direc t exposur e releas e value s shown i n Appendi xE . D.l. 2 Radionuclide s WhichDeca y b y Spontaneou s Fissionan dEmi t Neutron s Include d i n th e ICR P Publicatio n3 0 lis t o f 75 7 radionuclide s ar e 2 4 radionuclide s whic hdecay , a t leas t par t o f th e time , b y spontaneou s fission . Thes e radionuclide s ar e al l eithe r uraniu m

D- 6P.2 3



### isotope s o r isotope s o f transurani c elements 3



### . Th e usua l mod e o f decayfo r thes e isotope s i s throughth e emissio no f alpha particles . Thoughalpha particle s ar e no t penetrating , theyhav e a highqualit yfactor 4 

### an d whe nradionuclide s emitting alpha particle s ar e ingeste d o r inhale d an d deposite d i n tissues , th e damag e don e ca n b e enormous . I t i s no t surprising , then , tha t fo r thes e alpha emitting uraniu misotope s an

d transuranics , th e exposur e pathwayamong th e four evaluate d (inhalation , ingestio no f contaminate d drinking water , ingestio no f contaminate d foodstuffs , an d direc t exposure ) tha t give s th e lowes t calculate d releas e valu e i s inhalation . Exhibi t D- l present s a lis t o f radionuclide s whic hdecayb

yspontaneou s fissio nan d appea r i n th e ICR P Publicatio n 3 0 list . Exhibi t D- l als o provide s th e fractio no f decay s tha t occu r b yspontaneou s fission , th e inhalatio nreleas e valu e an

d th e calculate d neutro nexposur e releas e valu e fo r eac h radionuclide . Th e metho d use d b yth e Agenc yfo r determining a releas e valu e base d o n exposur e t o neutron s fo r isotope s whic h underg o spontaneou s fissio n i s describe d below . Equatio n (12 ) i s commonl yuse d fo r calculatio no f th e neutro n dos e rat e fro

ma n isotropi c poin t source 5



### . I » Q/[(4)*(pi)*(r 2 

### )*(8000) ] (12 )

3 

### Transurani c element s ar e thos e wit hhighe r atomi c number s tha n uraniu man d appea r beyond uraniu mi nth e periodi c char t o f th e elements . 4 

### Th e qualit yfacto r i s a measur e o f th e relativ e amoun t o f damag e don e t o tissue s b

ydifferen t type s o f radiation . Alph a particle s hav e bee n assigne d a qualit yfacto r o f 2 0 a s compare d t o 1 0 fo r neutron s an

d ar e believe d t o b e twic e a s damaging t o tissue s tha n neutrons . 5 

### "Th e Healt hPhysic s an d Radiologica l Healt hHandbook, " Nucleo n Lecter n Associates , pag e 38 , 1984 .

D- 7P.2 4



### EXHIBI T E -1 RADIONUCLIDE S INCLUDE DI N ICR P PUBLICATIO N WHIC HDECA

YBYSPONTANEOU S FISSION

Radionuclid e

Uranium-23 2 Uranium-23 5 Uranium-2 3 6 Uranium-23 8 Plutonium-2 3 6 Plutonium-23 8 Plutonium-23 9 Plutonium-24 0 Plutonium-24 4 Curium-23 8 Curium-24 2 Curium-24 4 Curium-24 6 Curium-24 8 Berkelium-24 9 Californium-24 6 Californium-24 8 Californium-24 9 Californium-25 0 Californium-25 2 Californium-25 4 Spontaneou s Fissio n Fraction * (SFF )

9 X 4. 2 1 0 X 

### -1 3 IO" 1 0 

### < 3 XIO" 1 

### 5. 4 8. 1 1. 8 4. 4 4. 9 1. 2 <1.5 6. 8 1. 3 2. 6 8. 3 4. 7 >0. ( 2. 9 5. 2 7. 7 3. 1 9. 9 X X X X X X X X X X X X 

### IO" 7 

### lo-i o IO" 9 

### IO" 1 2 

### IO" 8 

### IO" 3 

### IO" 4 

### 10~ 8 

### IO" 6 

### IO" 4 

### IO" 2 

### lo-i o 30 1 X X X X X 

### IO" 5 

### IO" 9 

### IO" 4 

### 1Q~ 2 

### IO" 1



### D- 8 Inhalatio n Releas e Valu e (Ci )

0.0 1 0. 1 0. 1 0. 1 0. 1 0.0 1 0.0 1 0.0 1 0.0 1 100 0 1 0.0 1 0.0 1 0.00 1 1 1 0 0. 1 0.0 1 0.0 1 0. 1 0. 1 

# m

3 0

Neutro n Exposur e ^ Releas e Value* * •

(Ci ) •

2. 8 X10 1 1 

### 5. 9 XIO 8 

### | | >0.8 3 • 4. 6 xio 5 

### m 3. 1 XIO 8 

### P 1. 4 XIO 8 

### ^ 5. 7 XIO 1 0 

### | 5. 1 XIO 6 

### 20 0 • >170 0 3. 7 xIO 6 

### • 1. 8 XIO 5 

### W 96 0 £ 

# 1 5. 3 XIO 8 ^ 

### <25 0 1 860 0 4. 8 XIO 7 

### • 32 0 8. 0 g 0.2 5 •P.2 5



### EXHIBI T D- l - (Continued ) RADIONUCLIDE S INCLUDEDIN ICRP PUBLICATIO

N 3 0 WHICHDECA

YB YSPONTANEOUS FISSIO N

Radionuclid e

Einsteinium-25 3 Einsteinium-254 m Fermium-25 4 Spontaneou s Fissio n Fraction * (SFF )

8. 7 xIO" 8 

### <0.00 1 5. 9 XIO" 4 

### Inhalatio n

Releas e Valu e (Ci )

1 0 1 10 0 Neutro n Exposur e

Releas e Value* *

(Ci )

2. 9 XIO 6 

### >25 0 42 0

* * 

### "Handboo k o f Chemistryan d Physics, " 63rd Edition , CRC Press , 198 2 Kocher , Davi d C "Radioactiv e Deca yDat a Tables, " Technica l Informatio n Center , U.S . Departmen t o f Energy , 1981 . Th e phenomeno n o f "inscattering " migh t reduc e thes e value s b ya s muc ha s 3 0 percent . Th e conclusions , however , remai n unchanged .

D- 9P.2 6



### where : I = dos e rat e i n rems/hou r (for purpose s o f calculatin g RQs , a dose-equivalen t o f 0. 5 re man d anexposur e perio d o f 2 4 hour s i s assume d leading t o an allowabl e averag e dos e rat e pe r hou r o f 0.5/24) ; Q = numbe r o f neutron s emitte d pe r secon d froma poin t source ; p i = approximatel y3.14159 ; an d r - distanc e fro

m sourc e t o recepto r i ncentimeter s (3 0 meter s o r 3 00 0 centimeter s fo r consistenc ywit hothe r models) . Rearrangin g equatio n (12 ) t o solv e fo r Q gives : Q = (I)*(4)*(pi)*(r 2 

### )*(8000) . (13 ) Substitutin g i n value s fo r I , pi , an d r yields : Q = 1.8 8 x10 1 0 

### neutrons/second . O n th e average , eac hfissio n yield s tw o neutrons , therefor e th e tota l numbe r o f fission s pe r secon d (F ) is : F = 9. 4 xIO 9 

### fissions/sec . (14 ) On e curi e i s equivalen t t o 3. 7 x10 1 0 

### disintegration s pe r second bu t onl ya fractio n o f th e tota l disintegrations , th e spontaneou s fissio n fractio n (SFF ) show ni n Exhibi t D-l , occu r b yspontaneou s fission . Divisio n o f equatio n(14 ) b yth e numbe r o f disintegration s pe r secon d equa l t o on e curi e an d th e spontaneou s fissio n fractio n fo r eac hradionuclid e give s equatio n (15 ) whic h provide s a releas e valu e base d o ndirec t exposur e t o neutrons .

D-1 0P.2 7



### Neutro n Exposur e = 0.25/SFF . (15 ) Releas e Valu e (Ci )
I n thi s calculation , radioactiv e decayove r th e perio d o f exposur e i s ignored . Inclusio no f thi s facto r would , fo r relativel yshort-live d radionuclides , increas e th e releas e value s calculate d o n th e basi s o f exposur e t o neutrons . Withou t consideratio n o f thi s factor , releas e value s calculate d i nthi s way ar e th e lowes t theycoul d b e bu t ar e stil l uniforml yhighe r tha n releas e value s calculate d o n th e basi s o f inhalatio n a s show ni n th e fina l tw o column s o f Exhibi t D-l . Fo r thi s reason , th e Agenc y chos e t o calculat e direc t exposur e releas e value s fo r al l radionuclide s o n th e basi s o f gamm a ra yexposur e a s describe d i n sectio n D.l.l , o r i f th e radionuclide s exis t a s a nobl e gas , o n th e basi s o f submersio n i n an airborn e clou d a s describe d i nsectio n D.2 . D. 2 SUBMERSIONI NACLOUD O F NOBL E GAS. 6 

### Th e nobl e gase s argon , krypton , an d xeno nar e veryresistan t t o combinatio n wit hothe r element s t o for msoli d o r liqui d derivatives . Th e radioactiv e form s o f thes e element s ar e no t

6 

### Th e nobl e gase s heliu man d neo nd o no t for

m isotope s wit hhalf

live s longe r tha n a fewseconds . Non e o f thes e isotope s ar e liste d i n ICR P Publicatio n 3 0 an d n o releas e value s o r propose d RQ s hav e bee n calculate d fo r them . Th e nobl e ga s rado nha s tw o isotope s (radon-22 0 and radon-222 ) liste d i n ICR P Publicatio n 3 0 wit h inhalatio n ALI s calculate d wit han d withou t daughter s present . Du e t o th e fac t tha t Radon-22 0 an d Radon-22 2 emi t alpha particle s an d some o f th e daughter s produce d b ythei r decayemi t alpha particles , inhalatio n become s th e critica l exposur e pathway , an d submersio n i n a n airborn e cloud i s no t addresse d b yth e ICR P fo r eithe r isotope . Th e lowes t o f th e ALI s i n eac hcas e wa s use d i nth e usua l manne r t o calculat e inhalatio n releas e value s and , sinc e submersio n i na n airborn e cloud i s no t addresse d b yth e ICR P fo r eithe r rado n isotope , direc t exposur e releas e value s wer e calculate d b yus e o f equatio n (11) . D-l lP.2 8



### likel yt o b e foun

d i n compound s o r i nsoli d o r liqui d ingestibl e form . I n addition , thes e gase s hav e verylowsolubilit yi nbloo d an d ar e easil ydisplace d fro mbloo d b

yth e mor e commo ngase s foun d i n ai r suc ha s oxyge n an d nitrogen . Fo r thes e reasons , neithe r ingestio n no r inhalatio n compris e a rout e o f significan t exposur e fo r argon , krypto n o r xeno nan d ALI s fo r isotope s o f thes e element s ar e no t found i n ICR P Publicatio n30 . Th e on e rout e o f potentia l exposur e considere d significan t fo r radioactiv e form s o f thes e element s i s throughdirec t exposur e fromsubmersio n i n a nairborn e cloud (know

n a s "cloudshine") . Th e equatio nuse d fo r calculatio n o f th e Direc t Exposur e (DE ) Releas e Valu e (RV ) base d o nsubmersio n i n suc ha n airborn e clou d i s show

n below 7 

### :
D E R V = [(83)*(DAC)*(T)]/[(10)*(X/Q)*( 1 XIO 6 

### )] . (16 ) Where : DAC = derive d ai r concentratio n (uCi/cubi c centimeter )

fro mICR P Publicatio n 30 ; T = time o f exposur e ( 1 day) ; X/ Q = atmospheri c relativ e concentratio nvalu e (8. 4 x

10" 1 3 

### day/cubi c centimeter) ; 8 3 conversio nfacto r t o adjus t airborn e concentration s

fro ma 200 0 hou r wor k yea r (5 0 week s time s 4 0 hour s pe r week ) t o a 2 4 hou r exposur e perio d ( 2 000/24) ; an d 1 xIO 6 

### conversio n facto r fro mmicrocuri e (uCi ) t o curie . The-DAC i s th e airborn e concentratio nt o whic ha n individua l mus t b e expose d fo r on e wor k yea r ( 2 00 0 hours ) i norde r t o receive a n occupationa l dose-equivalen t o f 5 rem . Th e facto r o f 1 0 convert s thi s occupationa l dose-equivalen t t o th e 0. 5 rem/yr limi t applicabl e t o th e genera l public . Fo r consistenc ywit hothe r

7 

### Annal s o f th e ICRP , Publicatio n 30 , Par t 1 , Vol . 2 , No . 3/4 , 1979 , Pergammo n Press , page s 1 0 an d 47 . D-1 2P.2 9



### exposur e pathway s the atmospheri c relativ e concentratio nvalu e (X/Q ) i s derive d fo r exposur e 3 0 meter s fro mth e releas e unde r stabilit yclas s D condition s (se e Appendi xA) . I norde r t o conver t th e duratio n o f exposur e fro ma 200 0 hou r wor k yea r t o 2 4 hour s ( l day) , th e DAC mus t b e multiplie d b ya facto r o f 8 3 (200 0 hours/2 4 hours) . Thi s i s th e airborn e concentratio n tha t wil l delive r a 5 rem dose-equivalen t i n 2 4 hours . Th e exposur e time , T ( 1 day) , i s include d i n th e equatio nbecaus e RQ s ar e applicabl e t o release s tha t occu r ove r a maximu mexposur e tim e o f 2 4 hours . EPA recognize s tha t i t i s unlikel ytha t a nindividua l woul d actuall yb e expose d t o a n airborn e clou d fo r a ful l day3 0 meter s fro mth e release , bu t ca n no t conclud e tha t i t i s impossibl e and , therefore , use s a 24-hou r exposur e perio d i nth e model . Additionally , becaus e th e facto r 8 3 is , a s describe d above , derive d b ydivisio n o f th e 200 0 hou r wor k yea r b yth e exposur e time , i nthi s cas e 2 4 hours , an ychang e i n exposur e time , T , wil l b e exactl ycompensate d b ya chang e i n th e facto r o f 83 . Fo r example , i f a one-hal f day exposur e tim e wer e chosen , T i n equatio n (16 ) woul d become on e half , whil e th e numerica l facto r 8 3 woul d become 16 6 (2000/12) . Substitutio n o f time (T) 8 

### an d th e atmospheri c relativ e concentratio n valu e (X/Q ) int o equatio n(16 ) lead s t o equatio n(17 ) whic hwa s use d fo r calculatio n o f th e direc t exposur e releas e value s fo r isotope s o f th e nobl e gases , wher e appropriate .

D E Releas e Valu e = (DAC)/(1. 0 XIO" 7 

### ) . (17 )

8 

### Thi s pathwayassume s an exposur e t o a n airborn e plume o f radionuclide . Becaus e i t i s no t possibl e t o establis hexac t bound s o n th e rang e o f releas e an d exposur e periods , th e Agencyassume s conservativel ytha t n o decayoccur s ove r thes e period s an d th e time perio d (T ) i s no t adjuste d fo r decayi n thi s scenario .

D-1 3P.3 0

Atom . No . Radionuclid e RADIONUCLIDE S Actinium-22 4 8 9 Actinium-22 5 8 9 Actinium-22 6 8 9 Actinium-22 7 8 9 Actinium-22 8 8 9 Aluminum-2 6 1 3 Americium-23 7 9 5 Americium-23 8 9 5 Americium-23 9 9 5 Americium-24 0 9 5 Americium-24 1 9 5 Americium-242 m9 5 Americium-24 2 9 5 Americium-24 3 9 5 Americium-244 m9 5 Americium-24 4 9 5 Americium-24 5 9 5 Americium-246 m9 5 Americium-24 6 9 5 Antimony-11 5 5 1 Antimony-116 m5 1 Antimony-11 6 5 1 Antimony-11 7 5 1 Antimony-118 m5 1 Ingestio n (food )

6.6 E 4 3.4 E 1 3.6 E 2 .:&.-.QE- 2 3.2 E 4 1.2 E 1 * 6.3 E 6 2.3 E 6 4.I E 4 4.3 E 3 3.0E- 1 3.0E- 1 3.I E 4 3.0E- 1 1.3 E 7 2.9 E 4 1.4 E 6 LI E 7 4.4 E 6 1.4 E 6 1.9 E 5 2.8 E 6 2.4 E 5 9.6 E 3 APPENDI XE

Releas e Value s (Ci ) Ingestio n Inha

- (water ) lation Direc t Exposur e

v.lg . v.lg . v.lg . v.lg . v.lg . 2.9 E 1 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 1.6 E 2 *

1.6 E 0 * 1.6 E 1 * 2.1E-3 * 4.7 E 1 * 3.I E 1 1.6 E 6 1.6 E 4 5.2 E 4 1.6 E 4 2.6E-2 * 2.6E-2 * 4.I E 2 * 2.6E-2 * 2.I E 4 * 1.0 E 3 4.I E 5 1.0 E 6 5.2 E 5 1.0 E 5 3.6 E 4 1.6 E 5 1.0 E 5 1.0 E 4 1.7 E 3

1.3 E 3 3.4 E 2 5.4 E 5 1.4 E 2 2.0 E 1 2.I E 3 * 5.3 E 2 * 8.0 E 2 * 4.5 E 1 *

3.2 E 5

7.9 E 2

9.5 E 1 * 1.7 E 4 * 1.7 E 3 * 1.5 E 3 * 2.2 E 3 * 2.I E 2 * 1.3 E 3 * 1.5 E 3 * 4.9 E 1 * Fina l

R Q (Ci ) 1 & 10 0 1 1 0 0.00 1 1 0 1 0 100 0 10 0 10 0 1 0 0.0 1 0.0 1 10 0 0.0 1 100 0 1 0 100 0 100 0 100 0 100 0 10 0 100 0 100 0 1 0


### E- lP.3 1

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestio n Ingestio n Inha

- (food ) (water ) lation Direc t Exposur e Fina l

R Q (Ci )
Antimony-11 9 Antimony-12 0 (1 6 min ) Antimony-12 0 (5.7 6 day ) Antimony-12 2 Antimony-124 m Antimony-12 4 Antimony-12 5 Antimony-126 m Antimony-12 6 Antimony-12 7 Antimony-12 8 (10. 4 min ) Antimony-12 8 (9.0 1 hr ) Antimony-12 9 Antimony-13 0 Antimony-13 1 Argon-3 9 Argon-4 1 Arsenic-6 9 Arsenic-7 0 Arsenic-7 1 Arsenic-7 2 Arsenic-7 3 5 1 5 1

5 1 2.9 E 3 *

3.6 E 6
8.7 E 1 v.lg .

v.lg . v.lg . 1.6 E 4

2.I E 5
5.2 E 2 L I E 5 *

1.6 E 1 * 100 0

100 0

1 0 

### 5 1 5 1 5 1 5 1 5 1 5 1 5 1 5 1 5 1 5 1 5 1 5 1 1 8 1 8 3 3 3 3 3 3 3 3 3 3 1.2 E

5.6 E 1.8 E 6.0 E 1.5 E 3.0 E 9.I E 4.5 E
1.1 E
6.5 E 3.0 E 2.5 E 

### n a n a LI E 1.1 E 7.3 E 3.5 E 2.7 E 

### 2 6 1 * 1 * 

### 6 1 1 6 3 3 5 5

6 5 2 2 2 * v.lg .

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 

### n a n a
> E 9

> E 9 3.9 E 3 1.8 E 4 6.4 E 2 5.2 E

3.I E 1.0 E 2.6 E 1.0 E 2.6 E 4.7 E 2.I E
1.6 E
4.7 E 3.I E 1.0 E 

### n a n a 5.2 E 2.6 E 2.6 E 5.2 E 1.0 E 

### 2 5 * 

### 2 2 5 2 2 5 3 3 4 4

4 * 

### 4 3 2 3 _. 9.3 E

- - 2.0 E 8.9 E 1.2 E 1.4 E 6.6 E 1.9 E
2.8 E

LI E 3.4 E 1.2 E 2.0 E 3.0 E 1.0 E 2.9 E 1.9 E 5.6 E 

### 1 *



### 1 1 3 * 1 * 1 * 3 * 1 * 2 * 2 * 3 * 

### 3* + 1* + 

### 5 2 * 2 * 1 * 1 0

100 0 

### 1 0 1 0 100 0 

### 1 0 1 0 100 0 

### 1 0 

### 10 0 10 0 100 0 100 0 

### 1 0 100 0 

### 10 0 10 0 1 0 

### 10 0

E- 2APPENDI XE(Continued )

Radionuclid e

Arsenic-7 4 Arsenic-7 6 Arsenic-7 7 Arsenic-7 8 Astatine-20 7 Astatine-21 1 Barium-12 6 Barium-12 8 Barium-131 m Barium-13 1 Barium-133 m Barium-13 3 Barium-135 m Barium-13 9 Barium-14 0 Barium-14 1 Barium-14 2 Berkelium-24 5 Berkelium-24 6 Berkelium-24 7 Berkelium-24 9 Berkelium-25 0 Beryllium- 7 Beryllium-1 0 Atom . No .



### 3 3 3 3 3 3 3 3 — 

### 8 5 8 5 5 6 5 6 5 6 5 6 5 6 5 6 5 6 5 6 5 6 5 6 5 6 9 7 9 7 9 7 9 7 9 7 

### 4 4 Ingestio n (food )

5.I E 1 * 3.9 E 2 1.1 E 3 * 5.0 E 4 3.I E 5 1.3 E 3 3.5 E 4 9.5 E 1 * 1.6 E 7 1.8 E 2 5.4 E 2 * 5.9 E 1 * LI E 3 * 6.8 E 4 3.0 E 1 * 6.2 E 5 2.7 E 6 2.2 E 3 7.5 E 3 3.0E- 1 1.5 E 1 3.0 E 4 1.5 E 3 3.0 E 1 Releas e Value s

Ingestio n (water )

L I E 2 1.9 E 4 1.5 E 4

> E 9

> E 9 / / 1.6 E 8 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci ) —

Inha

lation

4.I E 2 5.2 E 2 2.6 E 3 1.0 E 4 1.0 E 4 2.6 E 2 * 1.0 E 4 1.0 E 3 5.2 E 5 4.I E 3 4.7 E 3 3.6 E 2 5.2 E 3 1.6 E 4 5.2 E 2 3.6 E 4 5.2 E 4 5.2 E 3 1.6 E 4 2.6E-2 * 1.0 E 0 * 2.I E 2 * 1.0 E 4 5.2 E 0 * Direc t

Exposur e

8.I E 1.3 E 6.I E 3.9 E 3.7 E 5.3 E 1.0 E LI E 4.I E 9.3 E 9.5 E 1.0 E 1.1 E 9.9 E 2.I E 3.6 E 3.4 E 4.6 E 6.0 E 3.2 E

- - 2.I E 7.4 E

- - 

### 1 2 * 

### 3 2 * 2 * 

### 4 3 * 

### 3 4 * 1 * 

### 2 2 3 3 * 

### 2 3 * 3 * 2 * 1 * 

### 2

2 2 * Fina l

RQ (Ci )



### 1 0 

### 10 0 100 0 

### 10 0 10 0 10 0 100 0 

### 1 0 100 0 

### 1 0 

### 10 0 1 0 100 0 100 0 

### 1 0 100 0 100 0 

### 10 0 1 0 0.0 1 

### 1 10 0 10 0 

### 1
E- 3P.3 3

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestio n Ingestion Inha

- (food ) (water ) lation Direc t Exposur e Fina l

RQ (Ci )

Bismuth-20 0 Bismuth-20 1 Bismuth-20 2 Bismuth-20 3 Bismuth-20 5 Bismuth-20 6 Bismuth-20 7 Bismuth-210 m Bismuth-21 0 Bismuth-21 2 Bismuth-21 3 Bismuth-21 4 Bromine-74 m Bromine-7 4 Bromine-7 5 Bromine-7 6 Bromine-7 7 Bromine-80 m Bromine-8 0 Bromine-8 2 Bromine-8 3 Bromine-8 4 Cadmium-10 4 Cadmium-10 7 8 3 8 3 8 3 8 3 — 8 3 8 3 8 3 8 3 8 3 8 3 8 3 8 3 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 4 8 4 8 4.8 E 5

5.3 E 4 5.5 E 4 

### 1-.-7-B

- 3 5.4 E 1 5.5 E 1 3.0 E 1 1.2 E 0 8.6 E 1 4.7 E 4 8.8 E 4 5.7 E 5 1.3 E 5 4.3 E 5 1.6 E 5 2.3 E 3 3.7 E 3 4.I E 4 1.5 E 6 8.5 E 2 1.9 E 5 3.4 E 5 1.9 E 5 2.9 E 4 v.lg .

v.lg . v.lg . v . lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 

### > E 9 / /
> E 9 / /
> E 9 / / 1.3 E 6 / / 2.4 E 4 if > E 9 / /
> E 9 / / 1.6 E 4 / /
> E 9 / /

> E 9 / / v.lg . v.lg . 4 . I E 4

1.6 E 4 2.I E 4 3.I E 3 5.2 E 2 4.7 E 2 2.I E 2 3.6E-1 * 1.6 E 1 * 1.0 E 2 * 1.6 E 2 * 4.I E 2 * 2.0 E 4 3.6 E 4 2.6 E 4 2.0 E 3 1.0 E 4 5.0 E 3 * 1.0 E 5 2.0 E 3 3.I E 4 * 3.I E 4 3.6 E 4 2.6 E 4 4.7 E 2 *

4.7 E 2 * 1.0 E 3 * 4-.2 E 1 * 4.4 E 1 * 1.2 E 1 * 2.5 E 1 * 1.5 E 2 1.3 E 8 5.8 E 3

1.4 E 3 3.2 E 2 * 9.7 E 2 * 3.3 E 2 * 2.8 E 1 * 1.5 E 2 *

4.0 E 4 * 1.7 E 1 * 3.5 E 4 6.9 E 2 * 2.7 E 3 * 1.6 E 4 * 10 0

10 0 100 0 1 0 1 0 1 0 1 0 0. 1 1 0 10 0 10 0 10 0 10 0 10 0 10 0 1 0 10 0 100 0 100 0 1 0 100 0 10 0 100 0 100 0


### E- 4APPENDI XE(Continued ) P.3 4

Radionuclid e

Cadmium-10 9 Cadmium-113 m Cadmium-11 3 Cadmium-115 m Cadmium-11 5 Cadmium-117 m Cadmium-11 7 Calcium-4 1 Calcium-4 5 Calcium-4 7 Californium-24 4 Californium-24 6 Californium-24 8 Californium-24 9 Californium-25 0 Californium-25 1 Californium-25 2 Californium-25 3 Californium-25 4 Carbon-1 1 Carbon-1 4 Cerium-13 4 Cerium-13 5 Cerium-137 m Atom . No .



### 4 8 4 8 4 8 4 8 4 8 4 8 4 8 2 0 2 0 2 0 9 8 9 8 9 8 9 8 9 8 9 8 9 8 9 8 9 8 

### 6 6 5 8 5 8 5 8 Ingestio n (food )

9.0 E 0 * 5.9E-1 * 5.8E-1 * 1.1 E 1 * 1.8 E 2 1.4 E 4 1.9 E 4 8.0 E 1 * 5.7 E 1 * 8.2 E 1 8.8 E 6 1.2 E 3 6.2 E 0 3.0E- 1 9.0E- 1 3.0E- 1 1.8 E 0 3.0 E 2 LI E 0

- -

- - 7.7 E 1 * 1.1 E 3 6.I E 2 * Releas e Value s

Ingestion (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9 2.0 E 3 1.5 E 0 7.3E- 2 2.2E- 1 7.3E- 2 4.4E- 1 6.6 E 1 2.5E- 1

> E 9 1.5 E 2 v.lg . v.lg . v.lg . / / / / / / / / / / 

### it it it it (Ci ) — Inha

lation

2.I E 1 1.0 E 0 1.0 E 0 2.6 E 1 5.2 E 2 5.2 E 3 5.2 E 3 2.I E 3 4.I E 2 4.7 E 2 3.I E 3 * 4.7 E 1 * 4.7E-1 * 2.6E-2 * 5.2E-2 * 2.6E-2 * 1.6E-1 * 1.0 E 1 * 1.0E-1 * 4.I E 3 2.I E 1 * 3.6 E 2 2.I E 3 2.I E 3 Direc t

Exposur e

1.1 E 4 6.9 E 5

- -

. LI E 3 1.1 E 2 * 7.0 E 1 * 2.8 E 2 *

- -

- - 3.5 E 1 *

- - 3.4 E 6

- - 1.2 E 2

—

— 3.6 E 6

- -

— 1.8 E 3 *

- - 1.3 E 3 7.9 E 1 * 1.4 E 3 Fina l

RQ (Ci )



### 1 0. 1 0. 1

,. - 1 0 

### 10 0 1 0 

### 10 0 1 0 1 0 1 0 100 0 

### 1 0 

### 0. 1 0.0 1 0.0 1 0.0 1 

### 0. 1 1 0 

### 0. 1 100 0 

### 1 0 1 0 1 0 

### 10 0
E- 5APPENDI XE(Continued ) P.3 5

Radionuclid e

Cerium-13 7 Cerium-13 9 Cerium-14 1 Cerium-14 3 Cerium-14 4 Cesium-12 5 Cesium-12 7 Cesium-12 9 Cesium-13 0 Cesium-13 1 Cesium-13 2 Cesium-134 m Cesium-13 4 Cesium-135 m Cesium-13 5 Cesium-13 6 Cesium-13 7 Cesium-13 8 Chlorine-3 6 Chlorine-3 8 Chlorine-3 9 Chromium-4 8 Chromium-4 9 Chromium-5 1 Atom . 

### No .

5 8 5 8 5 8

5 8 •••••• 

### 5 8 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 

### 55 . 1 7 1 7 1 7 2 4 2 4 2 4 Inges t 

### io

n (food )

5.4 E 1.6 E 8.2 E 3;:2 E 6.2 E 6.3 E 9.3 E 6.4 E 1.2 E 1.4 E 2.7 E 3.3 E 2.I E LI E 2.I E 2.3 E 3.0 E 3.5 E 1.7 E 9.0 E 6.0 E 2.8 E 4.I E 1.7 E 

### 4 2 * 

### 1 2 0 5 4 3 6 3 * 

### 2 5 0 * 

### 6 1 * 

### 1 0 * 

### 5 1 * 

### 4 4 3 5 3 Releas e Value s Ingestio n (wate r

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 1.5 E 2

> E 9

> E 9 3.I E 5

> E 9 3.8 E 3 )

- • _

/ / / / / / (Ci ) Inh a lation

5.2 E 3.6 E 3.I E V. O E 5.2 E 5.2 E 4.7 E 1.6 E 1.0 E 1.6 E 2.I E 5.2 E 5.2 E 1.0 E 5.2 E 3.6 E 1.0 E 3.I E 1.0 E 2.0 E 2.6 E 3.6 E 4.I E 1.0 E 

### 4 2 2 3 0 * 

### 4 4 4 5 4 3 4 1 5 2 2 2 4 2 4 4 3 4 4 Direct Exposur e

6.9 E 2.7 E 5.2 E

• 1 . 9 E 2.3 E 3.I E 3.3 E 1.9 E 3.0 E

- - 5.7 E 1.3 E 2.4 E 4.3 E

- - 2.0 E 6.5 E 5.0 E

- - 6.9 E 4.5 E 1.3 E 9.9 E 1.1 E 

### 3 * 

### 2 1 * 2 * 

### 3 3 * 2 * 2 * 4 *

1 * 4 * 

### 1 2 *

1 * 

### 1 2 *

2 * 2 * 2 * 3 * 3 * Fina l

R Q (Ci )

100 0 

### 10 0 1 0

' " 10 0 

### 1 100 0 

### 10 0 10 0 100 0 100 0 

### 1 0 100 0 

### 1 10 0 1 0 1 0 

### 1 10 0 1 0 

### 10 0 10 0 10 0 100 0 100 0 E- 6APPENDI XE (Continued ) P.3 6

Radionuclid e

Cobalt-5 5 Cobalt-5 6 Cobalt-5 7 Cobalt-58 m Cobalt-5 8 Cobalt-60 m Cobalt-6 0 Cobalt-6 1 Cobalt-62 m Copper-6 0 Copper-6 1 Copper-6 4 Copper-6 7 Curium-23 8 Curium-24 0 Curium-24 1 Curium-24 2 Curium-24 3 Curium-24 4 Curium-24 5 Curium-24 6 Curium-24 7 Curium-24 8 Curium-24 9 Atom . No .



### 2 7 2 7 2 7 27--. . 

### 2 7 2 7 2 7 2 7 2 7 2 9 2 9 2 9 2 9 9 6 9 6 9 6 9 6 9 6 9 6 9 6 9 6 9 6 9 6 9 6 Ingestio n

(food )

5.7 E 3 1.4 E 2 1.2 E 3

-•..-. 6..4E.. 5 3.5 E 2 5.4 E 8 6.0 E 1 1.2 E 6 1.6 E 7 7.3 E 5 2.8 E 4 7.7 E 3 * 9.0 E 2 8.0 E 5 4.3 E 1 4.I E 2 1.9 E 1 6.0E- 1 6.0E- 1 3.0E- 1 3.0E- 1 3.0E- 1 1.2E- 1 4.5 E 6 Releas e Value s

Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9

> E 9 2.2 E 7 4.9 E 3 v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . / / / / / / / / (Ci ) — Inha

lation

1.6 E 4 1.0 E 3 3.6 E 3 3.I E 5 * 3.6 E 3 1.6 E 7 1.6 E 2 3.I E 5 1.0 E 6 4.7 E 4 1.6 E 4 1.0 E 4 2.6 E 3 5.2 E 3 * 2.6 E 0 * 1 . O E 2 1.6 E 0 * 4.1E-2 * 5.2E-2 * 2.6E-2 * 2.6E-2 * 3.1E-2 * 5.2E-3 * 1.0 E 5 Direc t

Exposur e

4.9 E 1 * 1.1 E 1 * 3.0 E 2 * 9.I E 6 4.5 E 1 * 3.0 E 6 * 1.5 E 1 * 4.0 E 3 * 1.0 E 3 * 9.9 E 2 * 8.2 E 2 * 8.I E 3 3.7 E 2 *

- -

- - 9.6 E 1 * 1.0 E 7 5.0 E 2 1.4 E 7 1.7 E 3

- - 1.2 E 2

- - 3.I E 4 * Fin a RQ ( C



### 1 0 1 0 

### 10 0 100 0 

### 1 0 100 0 

### 1 0 100 0 100 0 

### 10 0 10 0 100 0 

### 10 0 100 0 

### 1 1 0 

### 1 0 . 0 . 0 . 0 . 0 . 0 . 100 0 

### 1 i )

- • -



### 0 1 0 1 I 

### 0 1 0 1 0 1 

### 00 1

E- 7P.3 7



### Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Values (Ci ) Ingestio nIngestio nInha

- (food ) (water ) latio n Direc t Exposur e Fina l

R Q (Ci ) Dysprosium-15 5 6 6 8.8 E 3 Dysprosium-15 7 6 6 2.4 E 4 Dysprosium-15 9 6 6 3.2 E 2 Dysprosium-16 5 6 6 - ••• • -4 . IE' 4 Dysprosium-16 6 6 6 8.7 E 1 * Einsteiniura-25 0 9 9 5.7E 5 Einsteinium-25 1 9 9 2.2 E 4 Einsteinium-25 3 9 9 9.6 E 1 Einsteinium-254 m9 9 8.I E 1 Einsteinium-25 4 9 9 6.2 E 0 Erbium-16 1 6 8 5.9 E 4 Erbium-16 5 6 8 5.7 E 4 * Erbium-16 9 6 8 2.I E 2 * Erbium-17 1 6 8 5.2 E 3 Erbium-17 2 6 8 2.2 E 2 Europium-14 5 6 3 1.9 E 2 Europium-14 6 6 3 1.1 E 2 Europium-14 7 6 3 1.3 E 2 Europium-14 8 6 3 3.6 E 1 Europium-14 9 6 3 3.4 E 2 * Europium-15 0 6 3 2.3 E 3 (12. 6 hr ) Europium-15 0 6 3 2.4 E 1 (34. 2 yr ) Europium-152 m6 3 3.2 E 3 2
. I E8 / / 6
. I E9 /

/ 7.7 E2/

/ > E9 / / 3.3 E2/

/ 7.0 E9 /

/ 4.8 E4/

/ 2
. I E1 /

/ L I E3 / / 1.5 E0/ /


### > E 9 / / 9.7 E 8 / / 4.7 E 2 / / 3.4 E 9 / / 1.8 E 3 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 1.6 E 4

3.I E 4 1.0 E 3 2.6 E 4 3.6 E 2 3.6 E 3 5.2 E 3 * 1.0 E 1 * 5.2 E 0 * 5.2E-1 * 3.I E 4 1.0 E 5 1.6 E 3 5.2 E 3 5.2 E 2 1.0 E 3 5.2 E 2 1.0 E 3 2.I E 2 1.6 E 3 4.I E 3 2.0 E 2 *

2.8 E 2 * 1.2 E 2 * 1.6 E 4 * 2.7 E 3 8.2 E 1 *

2.2 E 5 9.7 E 1 7.7 E 4 3.3 E 2 *

2.4 E 7 2.7 E 2 * 8.5 E 1 * 3.2 E 1 * 2.0 E 1 * 8.8 E 1 * 1.9 E 1 * 1.2 E 3 2.0 E 3 * 1.0 E 1 * 2.8 E 1 3.I E 3 2.8 E 2 * 10 0 10 0 10 0 100 0 1 0 1 0 100 0 1 0 1 0. 1 10 0 100 0 10 0 10 0 1 0 1 0 1 0 1 0 1 0 10 0 100 0 1 0 10 0

E- 8P.3 8



### Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestio nIngestio nInha

- (food ) (water ) latio n Direc t Exposur e Fina l

R Q (Ci ) Europium-15 2 6 3 2.4 E 1 v.lg . 1.0 E 1 * 3.5 E 1 Europium-15 4 6 3 1.5 E 1 v.lg . 1.0 E 1 * 4.2 E 1 Europium-15 5 6 3 1.2 E 2 v.lg . 4.7 E 1 * 7.0 E 2 Europium-15 6 63-....... . 3...3 E 1 v.lg . . . ; , 2.6 E 2 2.3 E 1 * Europium-15 7 6 3 1.3 E 3 v.lg . 2.6 E 3 4.9 E 1 * Europiura-15 8 6 3 2.2 E 5 v.lg . 3.I E 4 1.0 E 3 * Fermium-25 2 10 0 2.0 E 3 LI E 4 / / 5.2 E 1 * Fermium-25 3 10 0 1.6 E 3 7.0 E 2 / / 5.2 E 1 * 5.5 E 3 Fermium-25 4 10 0 8.9 E 4 > E 9 / / 5.2 E 2 * Fermium-25 5 10 0 2.5 E 3 3.9 E 4 / / 1.0 E 2 * Fermium-25 7 10 0 1.7 E 1 3.9 E 0 / / 1.0 E 0 * 8.7 E 2 Fluorine-1 8 9 2.6 E 5 > E 9 / / 3.6 E 4 * Francium-22 2 8 7 7.9 E 4 v.lg . 2.6 E 2* Francium-22 3 8 7 1.6 E 4 v.lg . 4.I E 2 * 5.5 E 4 Gadolinium-14 5 6 4 1.2 E 6 v.lg . 1.0 E 5 8.3 E 2 * Gadolinium-14 6 6 4 3.7 E 1 * v.lg . 5.2 E 1 2.I E 2 Gadolinium-14 7 6 4 5.6 E 2 v.lg . 2.I E 3 4.3 E 1 * Gadolinium-14 8 6 4 3.0E- 1 v.lg . 4.1E-3 * Gadolinium-14 9 6 4 2 . I E 2 v.lg . 1.0 E 3 LI E 2 * Gadolinium-15 1 6 4 2.0 E 2 * v.lg . 2.I E 2 1.4 E 3 Gadolinium-15 2 6 4 6.0E- 1 v.lg . 5.2E-3 * Gadolinium-15 3 6 4 1.6 E 2 v.lg . 5.2 E 1 * 7.0 E 2 Gadolinium-15 9 6 4 1.6 E 3 v.lg . 3.I E 3 1.4 E 3 * Gallium-6 5 3 1 1.9 E 6 > E 9 / / 1.0 E 5 5.7 E 3 * 1 0 1 0 1 0

• 1 0 . - 1 0 100 0 1 0 1 0 10 0 10 0 1 100 0 10 0 10 0 10 0 1 0 1 0 0.00 1 10 0 10 0 0.00 1 1 0 100 0 100 0



### E- 9APPENDI XE (Continued ) P.3 9

Radionuclid e

Gallium-6 6 Gallium-6 7 Gallium-6 8 Gallium-7 0 Gallium-7 2 Gallium-7 3 Germanium-6 6 Germanium-6 7 Germanium-6 8 Germanium-6 9 Germanium-7 1 Germanium-7 5 Germanium-7 7 Germanium-7 8 Gold-19 3 Gold-19 4 Gold-19 5 Gold-198 m Gold-19 8 Gold-19 9 Gold-200 m Gold-20 0 Gold-20 1 Hafnium-17 0 Atom . No .

3 1 3 1 3 1 3 1 ' 3 1 3 1 3 2 3 2 3 2 3 2 3 2 3 2 3 2 3 2 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 9 7 2 Ingestio n (food )

1.0 E 1.0 E 1.7 E 1.4 E 7.I E 9.9 E 8.3 E 8.9 E 1.5 E 2.7 E 3.I E 2.7 E 7.7 E 1.3 E 5.0 E 8.0 E 1.6 E 2.0 E 1.7 E 4.6 E 5.3 E 3.5 E 1.5 E 1.9 E 3 3 5 6 2 3 4 5 2 3 4 5 3 5 3 2 2 * 2 2 2 * 2 5 6 3 Releas e Value s Ingestion (water )

4.8 E 4.I E

> E

> E 1.0 E

> E

> E

> E 3.7 E 3.7 E 6.9 E

> E 6.0 E

> E 1.6 E LI E 3.8 E 1.3 E 8.8 E 1.9 E 1.2 E
> E

> E LI E 7 /

/ 3 / / 9 / / 9it ' 6 / / 9 / / 9 / / 9 / / 2 / / 4 / / 4 / / 9 / / 7 / / 9 / / 6 / / 4 / / 2 / / 3 / / 2 / / 3 / / 5 / / 9 / / 9 / / 6 / / (Ci ) — Inha

lation

1.6 E 5.2 E 2.I E 1.0 E 1.6 E 1.0 E 1.0 E 4.7 E 5.2 E 4.I E 2.I E 4.I E 3.I E 1.0 E 1.0 E 2.6 E 2.I E 5.2 E 1.0 E 2.I E 1.0 E 3.I E 1.0 E 2.6 E 3 3 4 5 * 3 4 4 4 1 * 3 4 * 4 3 4 4 3 2 2 3 3 3 4 5 3 Direc t Exposur e

5.5 E 1 * 2.4 E 2 * 1.7 E 4 * 3.3 E 5 3.6 E 1 * 7.2 E 2 * 8.4 E 2 * 5.4 E 3 *

— 5.I E 1 *

- - 1.5 E 4 * 9.6 E 1 * 1.5 E 3 * 8.6 E 2 * 5.8 E 1 *

- - 8.8 E 1 * 1.0 E 2 * 5.3 E 2 2.8 E 1 * 3.I E 3 * 4.2 E 4 * 1.4 E 2 * Fina l

RQ (Ci )

1 0 10 0 100 0 -100 0 1 0 10 0 10 0 100 0 1 0 1 0 100 0 100 0 1 0 100 0 10 0 1 0 10 0 1 0 10 0 10 0 1 0 100 0 100 0 10 0

E-1 0APPENDI XE(Continued )

Radionuclid e

Hafnium-17 2 Hafnium-17 3 Hafnium-17 5 Hafnium-177 m Hafnium-178 m Hafnium-179 m Hafnium-180 m Hafnium-18 1 Hafnium-182 m Hafnium-18 2 Hafnium-18 3 Hafnium-18 4 Holmium-15 5 Holmium-15 7 Holmium-15 9 Holmium-16 1 Holmium-162 m Holmium-16 2 Holmium-164 m Holmium-16 4 Holmium-166 m Holmium-16 6 Holmium-16 7 Hydrogen- 3 Atom . No .

7 2 7 2 7 2 7 2 7 2 7 2 7 2 7 2 7 2 7 2 7 2 7 2 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 1 Ingestion (food )

3.0 E 2.2 E 1.0 E 6.2 E 2.6 E 1.8 E 1.2 E 3.8 E 3.7 E 6.0 E 1.8 E 4.7 E 4.8 E 1.4 E 3.5 E 3.8 E 4.2 E 1.9 E 1.5 E 3.9 E 1.8 E 3.4 E 6.2 E

- - 1 3 2 * 8 6 6 4 1 * 5 0 5 3 5 7 6 5 5 7 6 6 1 2 * 4 Releas e Value s Ingestio n (water )

7.4 E 1 /

/ 1.6 E 5 /

/ 2.4 E 2 /

/

> E 9 / /

> E 9 / /

> E 9 / /

> E 9 / / 8.7 E 1 /

/

> E 9 / / 1.5 E 1 /

/

> E 9 / /

> E 9 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 5.9 E 3 (Ci ) —

Inha

lation

4.7 E 0 * 5.2 E 3 4.7 E 2 3.I E 4 * 5.2E-1 * 1.6 E 2 * 1.0 E 4 1.0 E 2 4.7 E 4 4.1E-1 * 2.6 E 4 3.I E 3 1.0 E 5 5.2 E 5 5.2 E 5 2.I E 5 1.6 E 5 1.0 E 6 1.6 E 5 * 3.I E 5 * 3.6 E 0 * 1.0 E 3 3.I E 4 8.3 E 2 * Direc t

Exposur e

1.5 E 1.6 E 1.2 E 2.I E 5.7 E 5.6 E 1.2 E 7.4 E 6.7 E 1.6 E 7.9 E 6.7 E 7.8 E 9.2 E 5.4 E 4.5 E 1.1 E 3.7 E 6.9 E 3.5 E 2.2 E 2.2 E 6.I E

- - 3 2 * 2 6 5 5 2 * 1 2 * 2 2 * 2 * 3 * 3 * 3 * 4 * 3 * 4 * 6 5 1 3 2 * Fina l

RQ (Ci )

1 10 0 10 0 100 0 0. 1 10 0 10 0 1 0 10 0 0. 1 10 0 10 0 100 0 100 0 100 0 100 0 100 0 100 0 100 0 100 0 i

i I 1 10 0 10 0 ' 10 0 1
E-l lAPPENDI XE(Continued ) P.4 1

Radionuclid e

Indium-10 9 Indium-11 0 (69. 1 min ) Indium-11 0 (4. 9 hr ) Indium-Il l Indium-11 2 Indium-113 m Indium-114 m Indium-115 m Indium-11 5 Indium-116 m Indium-117 m Indium-11 7 Indium-119 m Iodine-120 m Iodine-12 0 Iodine-12 1 Iodine-12 3 Iodine-12 4 Iodine-12 5 Iodine-12 6 Iodine-12 8 Iodine-12 9 Iodine-13 0 Atom . No .



### 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 Ingestion

(food )

4.6 E 4 1.7 E 5
9.8 E 3
6.8 E 2 7.9 E 6 2.9 E 5 1.1 E 1 * 2.I E 4 1.2 E 0 2.I E 5 4.9 E 4 8.0 E 5 1.3 E 6 2.I E 3 5.6 E 2 1.1 E 3 4.5 E 1 * 1.2E-1 * 2.8E-2 * 2.3E-2 * 1.8 E 4 3.0E-3 * 6.3 E 0 * Releas e Value s

Ingestio n (water )

> E 9 / /

> E 9 / /

> E 9 / /
3.2 E 3 /

/

> E 9 / /

> E 9 / / 2.5 E 1 /

/

> E 9 / /

> E 9 / /

> E 9 / /

> E 9 / /

> E 9 / /

> E 9 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci ) —

Inha

latio n

2.I E 4 2.I E 4
1.0 E 4
3.I E 3 3.I E 5 5.2 E 4 3.I E 1 2 . I E 4 5.2E-1 * 4.I E 4 1.6 E 4 1.0 E 5 5.2 E 4 * 2.I E 2 * 9.3 E 1 * 2.I E 2 * 6.2 E 1 8.3E- 1 6.2E- 1 4.1E- 1 1.0 E 3 * 9.3E- 2 7.2 E 0 Direc t

Exposur e

4.5 E 2 * 6.8 E 2 *
4.5 E 1 *
1.1 E 2 * 6.0 E 4 * 1.5 E 3 * 4.8 E 2 8.9 E 2 *

— 3.3 E 2 * 5.2 E 2 * 1.2 E 3 * 9.I E 4 2.4 E 2 4.9 E 2 1.5 E 3 4.5 E 2 5.3 E 1

- - 1.0 E 2 1.7 E 4

- - 3.2 E 1 Fina l

RQ (Ci )



### 10 0 10 0 1 0 

### 10 0 100 0 100 0 

### 1 0 

### 10 0 0. 1 10 0 10 0 100 0 100 0 

### 10 0 1 0 

### 10 0 1 0 

### 0. 1 0.0 1 0.0 1 100 0 0.00 1 

### 1 E-1 2APPENDI XE(Continued )

Radionuclid e

Iodine-13 1 Iodine-132 m Iodine-13 2 Iodine-13 3 Iodine-13 4 Iodine-13 5 Iridium-18 2 Iridium-184 Iridium-18 5 Iridium-18 6 Iridium-18 7 Iridium-18 8 Iridium-18 9 Iridium-190 m Iridium-19 0 Iridium-192 m Iridium-19 2 Iridium-194 m Iridium-19 4 Iridium-195 m Iridium-19 5 Iron-5 2 Iron-5 5 Iron-5 9 Atom . No .



### 5 3 5 3 5 3 ;:-53

- 

### 5 3 5 3 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 2 6 2 6 2 6 Ingestio n

(food )

4.6E-2 * 5.5 E 2 3.2 E 2 -••--9.7E-1 * 4.3 E 3 2.3 E 1 1.5 E 7 2.6 E 5 3.5 E 4 1.3 E 4 9.3 E 4 5.I E 3 2.9 E 3 1.6 E 7 6.2 E 2 1.2 E 7 3.I E 2 1.9 E 2 5.2 E 3 2.0 E 5 3.4 E 5 1.1 E 3 2.7 E 2 * 3.0 E 1 * Releas e Value s

Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9

> E 9 4.9 E 6 8.I E 5 1.4 E 8 6 . I E 3 /

/ / / / / / / 

### it it 6.3 E 2*/ /

> E 9 1.3 E 2

> E 9 7.3 E 1 4.6 E 1 1.0 E 5

> E 9
> E 9 v.lg . v.lg . v.lg . 

### it it it it it it it it (Ci ) — Inha

lation

5.2E- 1 8.3 E 1 * 8.3 E 1 * 3.I E 0 5.2 E 2 2.I E 1 * 5.2 E 5 1.0 E 5 5.2 E 4 3.I E 4 1.6 E 5 1.6 E 4 2 . I E 4 1.0 E 6 * 4.7 E 3 1.0 E 2 * 1.0 E 3 4.7 E 2 1.0 E 4 1.0 E 5 2.I E 5 1.0 E 3 1.0 E 3 1.6 E 2 Direc t

Exposur e

1.0 E 2.I E 1.5 E 5.6 E 2.9 E 6.6 E 4.8 E 1.6 E 1.3 E 5.4 E 3.7 E 2.7 E 1.8 E

- - 3.4 E 6.7 E 4.8 E 1.6 E 7.I E 5.6 E 1.5 E 5.I E

- - 3.I E 

### 2 2 3 1 2 * 

### 1 3 * 2 * 2 * 1 * 2 * 1 * 

### 3

1 * 

### 8 1 * 1 * 2 * 2 * 4 * 2 *



### 1 Fina l

RQ (Ci )

0.0 1 

### 1 0 1 0

0 . 1 -•• • 

### 10 0 1 0 100 0 

### 10 0 10 0 .0 

### 10 0 1 0 

### 10 0 100 0 

### 1 0 

### 10 0 1 0 1 0 

### 10 0 10 0 100 0 

### 10 0 10 0 1 0 E-1 3APPENDI XE (Continued ) P.4 3

Radionuclid e

Iron-6 0 Krypton-7 4 Krypton-7 6 Krypton-7 7 Krypton-7 9 Krypton-8 1 Krypton-83 m Krypton-85 m Krypton-8 5 Krypton-8 7 Krypton-8 8 Lanthanum-13 1 Lanthanum-13 2 Lanthanum-13 5 Lanthanum-13 7 Lanthanum-13 8 Lanthanum-14 0 Lanthanum-14 1 Lanthanum-14 2 Lanthanum-14 3 Lead-195 m Lead-19 8 Lead-19 9 Lead-20 0 Atom . No .



### 2 6 3 6 3 6 36.— . 

### 3 6 3 6 3 6 3 6 3 6 3 6 3 6 5 7 5 7 5 7 5 7 5 7 5 7 5 7 5 7 5 7 8 2 8 2 8 2 8 2 Ingestio n (food )

8.9E-1 * 

### na na .--' n a 

### n a n a n a na na na n a 4.8 E 5 6.0 E 3 2.I E 4 3.0 E 2 2.7 E 1 1.6 E 2 9.8 E 3 5.0 E 4 1.6 E 6 2.3 E 6 1.2 E 5 1.3 E 5 1.4 E 3 Releas e Value s

Ingestion (water )

v.lg . 

### n a n a n a n a n a n a n a n a n a n a
> E 9

> E 9 3.8 E 6 7.3 E 2 6.6 E 1 2.0 E 3

> E 9

> E 9

> E 9 v.lg . v.lg . v.lg . v.lg . /

/ / / / / / / / / / / / / / / / / (Ci ) — Inha

lation

3.I E 0 

### n a n a

*. .n a 

### n a n a n a n a n a n a n a 5.2 E 4 5.2 E 3 4.7 E 4 3.I E 1 * 2.I E 0 * 5.2 E 2 4.7 E 3 * 1.0 E 4 4.7 E 4 * 1.0 E 5 3.I E 4 3.6 E 4 3.I E 3 Direc t

Exposur e

6.2 E 3.0 E 9.0 E 4.0 E 2.0 E 7.0 E 1.0 E 2.0 E 1.0 E 5.0 E 2.0 E 2.5 E 1.0 E 5.8 E

- - > E 2.0 E 6.6 E 2.3 E 4.7 E 2.2 E 7.3 E 5.3 E 4.7 E 

### 2 1* + 1* + 1* + 2* + 3* + 5* + 2* + 3* + 1* + 1* + 3 * 2 * 3 *



### 9 1 * 

### 3 2 * 

### 4 3 * 2 * 2 * 2 * Fina l

RQ (Ci )



### 0. 1 1 0 1 0 1 0 

### 10 0 100 0 100 0 

### 10 0 100 0 

### 1 0 1 0 100 0 

### 10 0 IOOO 

### 1 0 

### 1 1 0 100 0 

### 10 0 100 0 100 0 

### 10 0 10 0 10 0
E-1 4APPENDI XE(Continued ) P.4 4

Radionuclid e

Lead-20 1 Lead-202 m Lead-20 2 Lead-20 3 Lead-20 5 Lead-20 9 Lead-21 0 Lead-21 1 Lead-21 2 Lead-21 4 Lutetium-16 9 Lutetium-17 0 Lutetium-17 1 Lutetium-17 2 Lutetium-17 3 Lutetium-174 m Lutetium-17 4 Lutetium-176 m Lutetium-17 6 Lutetium-177 m Lutetium-17 7 Lutetium-178 m Lutetium-17 8 Lutetium-17 9 Atom . No .

8 2 8 2 8 2 8 2 8 2 8 2 8 2 8 2 8 2 8 2 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 7 1 Ingestio n

(food )

7.3 E 3 2.4 E 4 3.0 E 0 * 1.1 E 3 1.2 E 2 * 5.9 E 4 1.8E-2 * 1.6 E 5 7.4 E 1 1.9 E 5 9.2 E 2 2.3 E 2 1.5 E 2 8.7 E 1 1.5 E 2 * 6.5 E 1 * 1.5 E 2 2.I E 4 2.I E 1 2.2 E 1 * 1.7 E 2 * 1.2 E 6 8.0 E 5 1.3 E 4 Releas e Value s

Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . - v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 1.8 E 4 /

/ 1.9 E 3 /

/ 3.5 E 2 /

/ 2 . I E 2 /

/ 3.7 E 2 /

/ 1.5 E 2 /

/ 3.7 E 2 /

/

> E 9 / / 5 . I E 1 /

/ 5.4 E 1 /

/ 4.2 E 2 /

/

> E 9 / /

> E 9 / /

> E 9 / / (Ci ) — Inha

latio n

1.0 E 4 1.6 E 4 2.6 E 1 •4.7 E 3 5.2 E 2 3.I E 4 * 1.0E- 1 3.I E 2 * 1.6 E 1 * 4.I E 2 * 2.I E 3 1.0 E 3 1.0 E 3 5.2 E 2 1.6 E 2 1.0 E 2 5.2 E 1 * 1.0 E 4 * 2.6 E 0 * 4.I E 1 1.0 E 3 1.0 E 5 5.2 E 4 1.0 E 4 Direc t

Exposur e

1.4 E 2 * 8.7 E 1 *

- - 1.8 E 2 *

- -

- -

- - 1.9 E 4 6.3 E 2 6.3 E 3 7.7 E 1 * 2.5 E 1 * 7.0 E 1 * 2.4 E 1 * 6.8 E 2 4.3 E 3 4.3 E 2 2 . I E 4

> E 9 4.I E 1 1.3 E 3 3.6 E 4 * 1.3 E 4 * 5.I E 3 * Fina l

R Q (Ci )

10 0 1 0 1

- - 10 0 10 0 100 0 0.0 1 10 0 1 0 10 0 1 0 1 0 1 0 1 0 10 0 1 0 1 0 100 0 1 1 0 10 0 100 0 100 0 100 0 E-1 5Radionuclid e

Magnesium-2 8 Manganese-5 1 Manganese-52 m Manganese-5 2 Manganese-5 3 Manganese-5 4 Manganese-5 6 Mendelevium-25 7 Mendelevium-25 8 Mercury-193 m Mercury-19 3 Mercury-19 4 Mercury-195 m Mercury-19 5 Mercury-197 m Mercury-19 7 Mercury-199 m Mercury-20 3 Molybdenum-9 0 Molybdenum- 9 3 m Molybdenum-9 3 Molybdenum-9 9 Molybdenum-10 1 Neodymium-13 6 Atom . N o .



### 1 2 2 5 2 5 25,-. ; 

### 2 5 2 5 2 5 

### 10 1 10 1 8 0 8 0 8 0 8 0 8 0 8 0 8 0 8 0 8 0 4 2 4 2 4 2 4 2 4 2 6 0 APPENDI XE (Continued ) t>_ l t

r 1. . fm \ Ingestio n (food )

3.3 E 2 2.5 E 5 8.0 E 5 :y:;:yE: l 1.5 E 3 * 6.I E 1 1.8 E 4 1.7 E 5 2.5 E 1 2.4 E 3 4.9 E 4 5.8E-1 * 5.2 E 2 9.9 E 3 1.2 E 3 1.0 E 3 * 7.8 E 5 1.8 E 1 * 3.4 E 3 5.6 E 3 1.2 E 2 1.7 E 2 * 1.6 E 6 1.1 E 5 Ingestion

(water )

4.2 E 4 /

/

> E 9 /

/

> E 9 /

/ 1.8 E 2 /

/ * . 3.7 E 3 /

/ 1.5 E 2 /

/ > E9 it

> E 9 / / 5.8 E 0 /

/ 1.3 E 7 /

/

> E 9 / / 1.5 E 0 /

/ 6.8 E 3 /

/ 4.2 E 8 /

/ 9.2 E 4 /

/ 5.4 E 3 /

/

> E 9 /

/ 4.3 E 1 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . E-1 6 Inha

lation

5.2 E 2.6 E 4.7 E 4.7 E 5.2 E 4.I E 1.0 E 5.2 E 1.6 E 4.I E 1.6 E 1.6 E 2.I E 1.6 E 2.6 E 4.I E 4.I E 4.I E 2.6 E 5.2 E 1.0 E 5.2 E 5.2 E 2.6 E 

### 2 4 * 

### 4 2 3 2 4 2 * 0 * 

### 3 4 1 3 4 3 3 . 

### 4 2 3 3 2 * 

### 2 4 4 Direc t Exposur e

3.7 E 1 * 1.5 E 5 1.2 E 3 * 1.7 E 1 *

- - 4.4 E 1 * 1.4 E 2 *

- -

- - 5.4 E 1 * 2.3 E 2 *

- - 2.5 E 2 * 6.4 E 2 * 1.1 E 3 * 2.8 E 3 6.3 E 3 * 1.6 E 2 1.5 E 2 * 4.2 E 1 *

- - 1.7 E 2 4.5 E 3 * 5.I E 3 * Fina l

R Q (Ci )



### 1 0 100 0 100 0 

### ~1 0 100 0 

### 1 0 

### 10 0 10 0

- 1 1 0 

### 10 0 0. 1 10 0 10 0 100 0 100 0 100 0 

### 1 0 

### 10 0 1 0 

### 10 0 10 0 100 0 100 0 P.4 5P.4 6

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestion Ingestio n Inha

- (food ) (water ) lation Direc t Exposur e Fina l

RQ (Ci )
Neodymium-13 8 Neodymium-139 m Neodymium-13 9 Neodymium-14 1 Neodymium-14 7 Neodymium-14 9 Neodymium-15 1 Neptunium-23 2 Neptunium-23 3 Neptunium-23 4 Neptunium-23 5 Neptunium-23 6 (1. 2 E 5 yr ) Neptunium-23 6 (22. 5 hr ) Neptunium-23 7 Neptunium-23 8 Neptunium-23 9 Neptunium-24 0 Nickel-5 6 Nickel-5 7 Nickel-5 9 Nickel-6 3 Nickel-6 5 Nickel-6 6 6 0 6 0 6 0 6 0 6 0 6 0 6 0 9 3 9 3 9 3 9 3 9 3

9 3 5.2 E 4

9.5 E 3 1.7 E 6 7.7 E 5 6.4 E 1 * 5.5 E 4 3.2 E 6 1.2 E 7 1.3 E 8 2.4 E 3 3.I E 3 * 1.2E-1 *
2.2 E 3 v.lg .

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 

### 9 3 9 3 9 3 9 3 2 8 2 8 2 8 2 8 2 8 2 8 2.1E-2 *

1.7 E 3 3.9 E 3 1.8 E 6 9.3 E 1 5.8 E 2 5.9 E 2 * 2.7 E 2 * 3.0 E 4 8.I E 1 * v.l g

v.l g v.l g v.l g v.l g v.l g v.l g v.l g v.l g v.l g 2.6 E 3 *

5.2 E 3 1.6 E 5 3.I E 5 4.I E 2 1.0 E 4 1.0 E 5 1.0 E 4 1.6 E 7 1.6 E 4 5.2 E 3 1.6E- 1

2.I E 2 * 1.5 E 5

LI E 2 * 1.3 E 4 * 1.2 E 4 * 3.I E 2 7.8 E 2 * 4.7 E 3 * 2.5 E 3 * 1.5 E 5 * 3.9 E 1 *

6.9 E 2
6.9 E 3
3.1E- 2 4.7 E 2 1.0 E 4 4.I E 5 5.2 E 2 1.6 E 3 2.I E 3 1.0 E 3 1.0 E 4 3.I E 2 2.6 E 3

6.9 E 1 * 3.9 E 2 * 5.4 E 2 * 2.3 E 1 * 3.0 E 1 *

- -

— 4.5 E 2 *

_ _ 100 0

10 0 100 0 100 0 1 0 10 0 100 0 100 0 100 0 1 0 100 0 0. 1
10 0
0.0 1 1 0 10 0 10 0 1 0 1 0 10 0 10 0 10 0 1 0
E-1 7APPENDI XE(Continued ) P.4 7

Radionuclid e

Niobium-8 8 Niobium-8 9 (6 6 min ) Niobium-8 9 (12 2 min ) Niobium-9 0 Niobium-93 m Niobium-9 4 Niobium-95 m Niobium-9 5 Niobiura-9 6 Niobium-9 7 Niobium-9 8 Osmium-18 0 Osmium-18 1 Osmium-18 2 Osmium-18 5 Osmium-189 m Osmium-191 m Osmium-19 1 Osmium-19 3 Osmium-19 4 Palladium-10 0 Palladium-10 1 Palladium-10 3 Atom . No .



### 4 1 4 1 4 1 4 1 4 1 4 1 4 1 4 1 4 1 4 1 4 1 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 7 6 4 6 4 6 4 6 Ingestion

(food )

2.0 E 8.7 E
2.4 E
6.8 E 2.7 E 2.7 E 2.8 E 8.0 E 4.3 E 1.6 E 1.2 E 2.6 E 5.5 E 9.4 E 6.7 E 1.3 E 7.5 E LI E 6.7 E 1.2 E 1.4 E 1.2 E 3.I E 

### 6 4 4 2 2 1 2 * 

### 1 2 5 8 6 4 2 1 5 3 * 2 * 2 * 

### 1 2 * 

### 4 2 * Releas e Value s Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9 / /

> E 9 / / 1.1 E 5 / / 1.6 E 2 /

/
> E9it 1.7 E 7 /

/ 2.3 E 2 /

/ 1.8 E 4 / / 2.9 E 1 /

/ v.lg . v.lg . v.lg . (Ci ) —

Inha

lation

1.0 E 2.I E
1.0 E
1.0 E 1.0 E 1.0 E 1.0 E 5.2 E 1.0 E 3.6 E 2.6 E 2 . I E 2.I E 2.I E 2.6 E 1.0 E 1.0 E 5.2 E 1.6 E 4.I E 5.2 E 1.6 E 2.I E 

### 5 4 4 3 2 * 1 * 

### 3 2 3 4 4 * 5 * 

### 4 3 2 5 * 

### 4 2 3 0 * 

### 2 4 3 Direc t Exposur e

7.9 E 2 * 3.0 E 2 *
8.I E 2 *
1.5 E 1 *

- - 2.3 E 1 6.I E 2 4.8 E 1 * 2.2 E 1 * 7.4 E 2 * 1.2 E 7

- - 4.4 E 2 * 1.4 E 2 * 5.5 E 1 *

- - 1.2 E 6 1.1 E 3 1.1 E 3

- - 2.3 E 2 3.7 E 2 * 4.I E 5 Fina l

RQ (Ci )



### 10 0 10 0 10 0 1 0 

### 10 0 1 0 

### 10 0 1 0 1 0 

### 10 0 100 0 100 0 

### 10 0 10 0 1 0 100 0 100 0 

### 10 0 10 0 

### 1 10 0 10 0 10 0 E-1 8APPENDI XE (Continued )

Radionuclid e

Palladium-10 7 Palladium-10 9 Phosphorus-3 2 Phosphorus-3 3 Platinum-18 6 Platinum-18 8 Platinum-18 9 Platinum-19 1 Platinum-193 m Platinum-19 3 Platinum-195 m Platinum-197 m Platinum-19 7 Platinum-19 9 Platinum-20 0 Plutonium-23 4 Plutonium-23 5 Plutonium-23 6 Plutonium-23 7 Plutonium-23 8 Plutonium-23 9 Plutonium-24 0 Plutonium-24 1 Plutonium-24 2 Atom .



### No .

4 6 4 6 1 5 

### is--- - 7 8 7 8 7 8 7 8 7 8 7 8 7 8 7 8 7 8 7 8 7 8 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 9 4 Ingestio n

(food )

8.9 E 2 1.5 E 3 * 6.0E-1 * :*:*-_4-.7 E 0 * 4.8 E 4 1.3 E 2 * 9.0 E 3 6.5 E 2 3.6 E 2 * 1.2 E 3 * 2.5 E 2 * 1.2 E 5 1.6 E 3 * 9.2 E 5 7.9 E 2 * 9.9 E 4 2.0 E 8 6.0 E 0 3.8 E 3 * 2.I E 0 1.8 E 0 1.8 E 0 9.0 E 1 2.I E 0 Releas e Value s

Ingestio n (water )

v.lg . v.lg . 7.2 E 1 /

/ 5 . 8E 2 it

- - > E 9 it 2.9 E 2 /

/ 9.5 E 7 it 2.9 E 3 /

/ L I E 3 /

/ 2.9 E 3 /

/ 8 . I E 2 /

/

> E 9 / / 4.2 E 5 /

/

> E 9 / / 2.6 E 6 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci ) —

Inha

latio n

2.I E 2 * 2.6 E 3 4.I E 0 3 . I E 1 2.I E 4 1.0 E 3 1.6 E 4 4.I E 3 3.I E 3 1.0 E 4 2.I E 3 2.I E 4 4.7 E 3 5.2 E 4 1.6 E 3 1.0 E 3 * 1.6 E 7 * 1.0E-1 * 1.6 E 4 3.1E-2 * 2.6E-2 * 2.6E-2 * 1.6 E 0 * 3.1E-2 * Direc t

Exposur e

_ . _ 1.6 E 4

- -

4.0 E 2 * 3.I E 2 4.4 E 2 * 2.2 E 2 * 2.6 E 5

- - 2.7 E 3 9.9 E 3 * 7.3 E 3 6.7 E 3 * 3.4 E 3

- -

- -

- -

- -

- - 1.7 E 6 5.0 E 6 1.4 E 8 4.I E 6 Fina l

R Q (Ci )



### 10 0 100 0 

### 0. 1-H 

### 10 0 10 0 10 0 10 0 1Q 0 100 0 

### 10 0 100 0 100 0 100 0 

### 10 0 100 0 100 0 

### 0. 1 100 0 0.0 1 0.0 1 0.0 1 

### 1 0.0 1

E-1 9P.4 9

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestio n Ingestio n Inha

- (food ) (water ) lation Direc t Exposur e Fina l

RQ (Ci )

Plutonium-24 3 9 4 3.9 E 5 v.lg . Plutonium-24 4 9 4 2.I E 0 v.lg . Plutonium-24 5 9 4 1.9 E 4 v.lg . Polonium-20 3 8 4 4.9 E 5 v.lg . Polonium-20 5 8 4 1.1 E 5 v.lg . Polonium-20 7 8 4 1.3 E 4 v.lg . Polonium-21 0 8 4 9.7E-2 * v.lg . Potassium-4 0 1 9 8.6 E 0 * v.lg . Potassium-4 2 1 9 3.9 E 3 v.lg . Potassium-4 3 1 9 2.6 E 3 v.lg . Potassium-4 4 1 9 5.0 E 5 v.lg . Potassium-4 5 1 9 9.6 E 5 v.lg . Praseodymium-13 6 5 9 2.2 E 6 v.lg . Praseodymium-13 7 5 9 3.0 E 5 v.lg . Praseodymium-138 m5 9 4.6 E 4 v.lg . Praseodymium-13 9 5 9 8.7 E 4 v.lg . Praseodymium-142 m5 9 3.I E 6 v.lg . Praseodymium-14 2 5 9 5.3 E 2 * v.lg . Praseodymium-14 3 5 9 5.2 E 1 * v.lg . Praseodymium-14 4 5 9 9.9 E 5 v.lg . Praseodymium-14 5 5 9 4.9 E 3 v.lg . Praseodymium-14 7 5 9 2.I E 6 v.lg . Promethium-14 1 6 1 1.4 E 6 v.lg . Promethium-14 3 6 1 1.6 E 2 v.lg . 2.I E 5 3.1E-2 * 2.I E 4 3.I E 4 2.I E 4 1.6 E 4 3.1E- 1 2.I E 2 2.6 E 3 4.7 E 3 3.6 E 4 5.2 E 4 1.0 E 5 5.2 E 4 2.I E 4 5.2 E 4 5.2 E 4 * 1.0 E 3 3.6 E 2 5.2 E 4 * 4.I E 3 * 1.0 E 5 1.0 E 5 3.I E 2 5.7 E 3 *

3.I E 2 * 8.8 E 2 * 2.7 E 2 * 9.4 E 1 * 4.5 E 6 2.4 E 2 2.3 E 2 * 5.9 E 1 * 6.8 E 2 * 1.2 E 3 * 2.3 E 3 * 1.5 E 4 * 1.4 E 2 * 1.5 E 3 *

9.3 E 2 5.0 E 8 7.4 E 4 9.2 E 3 4.6 E 3 * 2.7 E 3 * 1.3 E 2 * 100 0

0.0 1 10 0 10 0 10 0 1 0 0.0 1 1 10 0 1 0 10 0 100 0 100 0 100 0 10 0 100 0 100 0 10 0 1 0 100 0 100 0 100 0 100 0 10 0
E-2 0P.5 0

APPENDI XE (Continued )

Radionuclid e

Promethium-14 4 Promethium-14 5 Promethium-14 6 Promethium-14 7 Promethium-148 m Promethium-14 8 Promethium-14 9 Promethium-15 0 Promethium-15 1 Protactinium-22 7 Protactinium-22 8 Protactinium-23 0 Protactinium-23 1 Protactinium-23 2 Protactinium-23 3 Protactinium-23 4 Radium-22 3 Radium-22 4 Radium-22 5 Radium-22 6 Radium-22 7 Radium-22 8 Radon-22 0 Radon-22 2 Atom . 

### No .

6 1 6 1 6 1 6 1 : . - 

### 6 1 6 1 6 1 6 1 6 1 9 1 9 1 9 1 9 1 9 1 9 1 9 1 8 8 8 8 8 8 8 8 8 8 8 8 8 6 8 6 Ingestio n

(food )

3.I E 1 3.0 E 2 6.0 E 1

__ 1.2 E 2 2.7 E 1 4.I E 1 * 2.I E 2 * 1.8 E 4 7.3 E 2 6.0 E 5 4.6 E 3 3.I E 2 6.0E- 2 3.3 E 3 4.3 E 2 2.9 E 4 3.I E 0 * LI E 1 4.4 E 0 6.0E-1 * 2.7 E 6 6.0E-1 * 

### n a n a Releas e Value s

Ingestio n (water )

v.lg . v.lg . v.lg . v-lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 

### na n a (Ci ) —

Inha

lation

5.2 E 1 1.0 E 2 * 2.I E 1 * 5.2 E 1 * 1.6 E 2 2.6 E 2 1.0 E 3 1.0 E 4 1.6 E 3 5.2 E 2 * 5.2 E 1 * 2.I E 1 * 1.0E-2 * 1.0 E 2 3.I E 3 3.6 E 4 3.6 E 0 1.0 E 1 * 3.6 E 0 * 3.I E 0 5.2 E 4 5.2 E 0 1.0E-1 * 5.2E-1 * Direc t

Exposur e

2.4 E 1 * 2.8 E 4 5.0 E 1 9.5 E 6 1.8 E 1 * 6.9 E 1 3.9 E 3 1.9 E 2 * 2.I E 2 * 5.I E 5 6.9 E 1 6.4 E 1 1.8 E 3 5.I E 1 * 2.3 E 2 * 7.6 E 1 * 4.6 E 2 4.2 E 3

- - 5.9 E 3 7.5 E 3 *

- -

- - 1.1 E 5 Fina l

RQ (Ci )



### 1 0 

### 10 0 1 0 1 0 1 0 1 0 

### 10 0 10 0 10 0 10 0 1 0 1 0 0.0 1 

### 1 0 

### 10 0 1 0 

### 1 1 0 

### 1 0. 1 100 0 

### 0. 1 0. 1 0. 1

E-2 1P.5 1

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci ) Ingestio nIngestio nInha

- (food ) (water ) latio n Direc t Exposur e Fina l

R Q (Ci )

Rhenium-17 7 Rhenium-17 8 Rhenium-18 1 Rhenium-18 2 

### (12. 7 hr ) Rhenium-18 2 (64. 0 hr ) Rhenium-184 m Rhenium-18 4 Rhenium-186 m Rhenium-18 6 Rhenium-18 7 Rhenium-188 m Rhenium-18 8 Rhenium-18 9 Rhodium-99 m Rhodium-9 9 Rhodium-10 0 Rhodium-lOl m Rhodium-10 1 Rhodium-102 m Rhodium-10 2 Rhodium-103 m Rhodium-10 5 Rhodium-106 m 7 5 7 5 7 5 7 5

7 5

7 5 7 5 7 5 7 5 7 5 7 5 7 5 7 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 3.5 E 6

2.9 E 6 2.4 E 3 5.2 E 3
1.7 E 2
6.I E 1 * 7.5 E 1 2.8 E 1 * 2.5 E 2 * 1.7 E 4 * 2.3 E 6 L I E 3 * 1.2 E 3 4.I E 4 1.1 E 2 9.7 E 2 7.I E 2 6.0 E 1 * 3.I E 1 * 1.8 E 1 4.I E 6 1.2 E 3 3.5 E 4 > E 9 / /

> E 9 / / 4.0 E 5 /

/ 1.6 E 7 /

/
9.0 E 2 /

/
1.5 E 2 /

/ 1.8 E 2 /

/ 7.3 E 1 /

/ 9 . I E 2 /

/ 4.4 E 4 /

/

> E 9 / / 4.6 E 5 /

/ 8.8 E 4 /

/

> E 9 / / 2.3 E 2 /

/ 1.3 E 5 /

/ 2.2 E 3 /

/ 1.5 E 2 /

/ 7.6 E 1 /

/ 4.4 E 1 /

/

> E 9 / / 2 . I E 4 /

/

> E 9 / / 1.6 E 5 1.6 E 5 4.7 E 3 5.2 E 3
1.0 E 3
2.I E 2 5.2 E 2 1.0 E 2 1.0 E 3 5.2 E 4 5.2 E 4 * 1.6 E 3 2.I E 3 3.I E 4 1.0 E 3 2.I E 3 4.I E 3 1.0 E 2 5.2 E 1 3.I E 1 5.2 E 5 * 3.I E 3 1.6 E 4 6.I E 3 *

4.6 E 3 * L I E 2 * 6.9 E 1 *
2.5 E 1 *
2.I E 2 4.5 E 1 * 3.3 E 3 3.0 E 3

L I E 5 1.3 E 3 1.2 E 3 * 2.3 E 2 * 8.7 E 1 * 2.I E 1 * 1.4 E 2 * 1.3 E 2 8.4 E 1 1.4 E 1 *

5.9 E 2 * 9.8 E 1 * 100 0

100 0 10 0 1 0

1 0
1 0 1 0 1 0 10 0 100 0 100 0 100 0 100 0 10 0 1 0 1 0 10 0 1 0 1 0 1 0 100 0 10 0 1 0
E-2 2P.5 2

Radionuclid e

Rhodium-10 7 P Rubidium-7 9

—Rubidium-81 m

Rubidium-8 1

• Rubidium-82 m

Rubidium-8 3 H Rubidium-8 4

—Rubidium-8 6

• Rubidium-8 8 j | Rubidium-8 9

Rubidium-8 7 I Ruthenium-9 4

Ruthenium-9 7

• Ruthenium-10 3 fl Ruthe n ium-10 5

Ruthenium-10 6 1 Samarium-141 m

Samarium-14 1

mSamarium-14 2

• Samarium-14 5

Samarium-14 6

mSamarium-14 7

Samarium-15 1

• Samarium-15 3 Atom . No .

4 5 3 7 3 7 •37 — 3 7 3 7 3 7 3 7 3 7 3 7 3 7 4 4 4 4 4 4 4 4 4 4 6 2 6 2 6 2 6 2 6 2 6 2 6 2 6 2 APPENDI XE (Continued ) Ingestio n (food )

1.8 E 6 9.9 E 5 3.6 E 6 -8.4 E 4 1.5 E 4 2.0 E 1 * 2.0 E 1 * 2.5 E 1 * 6.4 E 5 1.5 E 6 3.0 E 1 * 2.2 E 5 1.3 E 3 7.8 E 1 * 1.1 E 4 6.I E 0 7.6 E 5 2.8 E 6 6.3 E 4 1.8 E 2 * 3.0E- 1 6.0E- 1 3.0 E 2 4.6 E 2 * Releas e Value s

Ingestio n (water )

> E 9 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9 6.0 E 3 1.8 E 2

> E 9 1.5 E 1 v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . E-2 3 (Ci ) —

Inha

lation

1.0 E 5.2 E 1.6 E 2.6 E 1.0 E 5.2 E 4.I E 4.I E 3.I E 5.2 E 1.0 E 2.I E 5.2 E 3.I E 5.2 E 5.2 E 5.2 E 1.0 E 1.6 E 2.6 E 2.1E

2.1E

5.2 E 1.6 E 5 4 5 4 - 4 2 2 2 4 4 3 4 3 2 3 0 * 4 5 4 2

• 2 * •2 * 1 * 3 Direc t Exposur e

5.6 E 3 * 1.2 E 3 * 4.8 E 3 * 2.9 E 2 * 3.9 E 1 * 7.3 E 1 5.4 E 1 3.9 E 2 2.9 E 3 * 1.3 E 3 *

- - 1.4 E 3 * 1.2 E 2 * 7.9 E 1 2.0 E 2 *

- - 1.0 E 3 * 3.4 E 3 * 8.2 E 3 * 2.5 E 6

- -

- -

- - 1.3 E 3 Fina l

R Q (Ci )

100 0 100 0 100 0 10 0 1 0 1 0 1 0 1 0 j

1 100 0 J 100 0 | 1 0 | 100 0 | i 1 10 0 i 1 0 10 0 1 100 0 100 0 100 0 10 0 0.0 1 0.0 1 1 0 10 0

1

iP.5 3

Radionuclid e Atom . No . APPENDI XE (Continued )

Releas e Value s (Ci) . - Ingestion Ingestio n Inha

- (food ) (water ) lation Direc t Exposur e Fina l

RQ (Ci )

Samarium-15 5 Samarium-15 6 Scandium-4 3 Scandium-44 m Scandium-4 4 Scandium-4 6 Scandium-4 7 Scandium-4 8 Scandium-4 9 Selenium-7 0 Selenium-73 m Selenium-7 3 Selenium-7 5 Selenium-7 9 Selenium-81 m Selenium-8 1 Selenium-8 3 Silicon-3 1 Silicon-3 2 Silver-10 2 Silver-10 3 Silver-104 m Silver-10 4 Silver-10 5 6 2 6 2 2 1 2 1 2 1 2 1 2 1 2 1 2 1 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 1 4 1 4 4 7 4 7 4 7 4 7 4 7 1.5 E 6

5.2 E 3 1.7 E 4 9.-5 E 1 * 9.8 E 3 3.I E 1 2.9 E 2 * 2.0 E 2 2.0 E 5 1.4 E 5 2.3 E 3 4.I E 3 1.6 E 1 * 1.8 E 1 * 2.0 E 5 1.9 E 6 7.7 E 5 3.3 E 4 5.9 E 1 2.2 E 6 3.4 E 5 5.I E 5 1.6 E 5 1.1 E 2 v.lg .

v.lg . > E 9 / / 5.6 E 2 /

/

> E 9 / / 7.2 E 1 /

/ 1.1 E 3 /

/ 2.0 E 3 /

/

> E 9 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9 / / 1.5 E 2 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . 1.0 E 5

4.7 E 3 1.0 E 4 •3,6 E 2 5.2 E 3 1.0 E 2 1.6 E 3 5.2 E 2 2.6 E 4 * 2.I E 4 5.2 E 4 5.2 E 3 3.I E 2 3.I E 2 3.6 E 4 * 1.0 E 5 * 5.2 E 4 1.6 E 4 * 2.6 E 0 * 1.0 E 5 5.2 E 4 4.7 E 4 3.6 E 4 5.2 E 2 1.8 E 4 *

7.0 E 2 * 1.9 E 3 * 1,3 E 2 1.3 E 2 * 1.8 E 1 * 3.7 E 2 1.3 E 1 * 7.2 E 5 4.6 E 3 * 1.7 E 2 * 9.5 E 1 * 1.0 E 2

6.I E 4 1.8 E 5 1.0 E 3 * 2.6 E 5

8.8 E 2 * 1.5 E 3 * 

### LI E 3 * 

### 2.9 E 3 * 

### 8.2 E 1 * 

### 100 0

10 0 

### 100 0 1 0 

### 10 0 1 0 

### 10 0 1 0 

### 10Q 0 100 0 10 0 1 0 1 0 1 0 

### 100 0 100 0 100 0 100 0 

### 1 10 0 

### 100 0 100 0 100 0 1 0 

### E-2 4APPENDI XE (Continued ) P.5 4

Radionuclid e

Silver-106 m Silver-10 6 Silver-108 m Silver-llO

m Silver-Il l Silver-11 2 Silver-11 5 Sodium-2 2 Sodium-2 4 Strontium-8 0 Strontium-8 1 Strontium-8 3 Strontium-85 m Strontium-8 5 Strontium-87 m Strontium-8 9 Strontium-9 0 Strontium-9 1 Strontium-9 2 Sulfur-3 5 Tantalum-17 2 Tantalum-17 3 Tantalum-17 4 Tantalum-17 5 Atom .



### No .

4 7 4 7 4 7 4 7 4 7 4 7 4 7 1 1 1 1 3 8 3 8 3 8 3 8 3 8 3 8 3 8 3 8 3 8 3 8 1 6 7 3 7 3 7 3 7 3 Ingest ]



### Lo n (food )

5.9 E 1.4 E 1.8 E 1.5 E 7.2 E 9.0 E 8.4 E 1.2 E 2.6 E 2.0 E 4.7 E 5.9 E 1.6 E 9.7 E 1.3 E 1.7 E 8.2E

1.9 E 9.8 E 3.9 E 6.2 E 1.8 E 2.4 E 5.6 E 

### 1 6 1 1 1 * 

### 3 5 1 * 

### 3 4 5 2 6 1 5 1 *

• 1 * 

### 3 3 0 * 

### 6 5 6 4 Releas e Value s Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 4.8 E 2 /

/

> E 9 / /

> E 9 / /

> E 9 / / 8.4 E 7 /

/ (Ci ) Inha

lation

3.6 E l.OE l.OE 4.7 E 4.7 E 4.I E 4.I E 3.I E 2.6 E 5.2 E 4.I E 2.I E 3.I E l.OE 5.2 E 5.2 E 2.I E 2.I E 3.6 E 2.I E 5.2 E l.OE 4.7 E 5.2 E 

### 2 5 1 * 

### 1 2 3 4 2 3 3 4 3 5 3 4 1 0 3 3 1 5 5 5 4 Direc t Exposur e

1.4E 2.I E 2.2 E 1.3 E 1.5 E 3.8 E 7.I E

- - 1.5 E 4.I E 1.3 E 1.3 E 2.7 E 7.2 E 6.8 E 4.5 E

- - 7.9 E 1.7 E

- - 8.0 E 4.9 E 9.6 E 1.9 E 

### 1 * 3 * 

### 1 1 * 

### 3 2 * 3 *

1 * 2 * 3 * 2 * 3 * 1 * 2 * 

### 6

1 * 2 *

2 * 2 * 2 * 2 * Fina l

RQ (Ci )



### 1 0 100 0 

### 1 0 1 0 1 0 

### 10 0 100 0 

### 1 0 1 0 

### 10 0 100 0 

### 10 0 100 0 

### 1 0 

### 10 0 1 0 

### 0. 1 1 0 

### 10 0 

### 1 10 0 10 0 10 0 10 0

E-2 5APPENDI XE (Continued ) Releas e Value s (Ci ) Radionuclid e

Tantalum-17 6 Tantalum-17 7 Tantalum-17 8 Tantalum-17 9 Tantalum-180 m Tantalum-18 0 Tantalum-182 m Tantalum-18 2 Tantalum-18 3 Tantalum-18 4 Tantalum-18 5 Tantalum-18 6 Technetium-93 m Technetium-9 3 Techne t ium-94 m Technetium-9 4 Technetium-96 m Technetium-9 6 Techne t ium-97 m Technetium-9 7 Technetium-9 8 Technetium-99 m Technetium-9 9 Technetium-10 1 Atom . No .

7 3 7 3 7 3 73: ; 7 3 7 3 7 3 7 3 7 3 7 3 7 3 7 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 4 3 Ingestio n

(food )

4.8 E 2.0 E 1.2 E 4 4 7 ____fi_lE: 3 2.4 E 3.0 E 7.2 E 2.6 E 9.5 E 2.2 E 3.5 E 2.7 E 7.0 E 7.6 E 1.7 E 1.3 E 1.7 E 1.8 E 1.3 E 8.9 E 2.2 E 9.7 E 8.9 E 2.7 E 5 2 7 2 2 4 6 7 5 4 5 4 6 2 2 * 2 * 1 * 4 1 * 6 Ingestio n

(water )

1.3 E 1.2 E

> E L5 E 5.6 E

> E

> E 6.2 E 2.6 E 2.4 E

> E

> E

> E

> E

> E

> E

> E 7.3 E 4.0 E 2.9 E 7.3 E

> E 2.9 E
> E 9 / / 4 / / 9 / / 3*/ / : 9 / / 9 / / 9 / / 1 / / 2 / / 8 / / 9 / / 9 / / 9 9 9 9 9 2 2 3 1 9 2 9 Inha

latio n

5.2 E l.O E 3.6 E

: : 4.7 E 3.I E l.O E 2.I E 5.2 E 5.2 E 2.6 E 3.I E l.O E l.O E 3.6 E 2.I E l.O E l.O E l.O E 5.2 E 3.I E 1.6 E l.O E 3.6 E 1.6 E 4 5 5 3 - 5 2 * 6 2 3 4 5 6 5 4 4 4 5 3 2 3 2 5 2 5 Direc t Exposur e

6.0 E 1 * 2.7 E 3 * 5.7 E 4 * --:.-.- - 1.6 E 4 *

- - 1.2 E 4 * 3.I E 1 * 1.8 E 2 * 5.4 E 1 * 6.7 E 3 * 2.8 E 3 * 1.2 E 3 * 1.4 E 2 * 3.7 E 2 * 4.8 E 1 * 4.7 E 4 * 1.6 E 1 * 1.2 E 5

- - 2.6 E 1 8.6 E 2 *

- - 8.I E 3 * Fina l

RQ (Ci )

1 0 100 0 100 0 100 0 100 0 10 0 100 0 1 0 10 0 1 0 100 0 100 0 100 0 10 0 10 0 1 0 100 0 1 0 10 0 10 0 1 0 10 0 1 0 100 0
E-2 6P.5 6

APPENDI XE (Continued )

Radionuclid e

Technetium-10 4 Tellurium-11 6 Tellurium-121 m Tellurium-12 1 Tellurium-123 m Tellurium-12 3 Tellurium-125 m Tellurium-127 m Tellurium-12 7 Tellurium-129 m Tellurium-12 9 Tellurium-131 m Tellurium-13 1 Tellurium-13 2 Tellurium-133 m Tellurium-13 3 Tellurium-13 4 Terbium-14 7 Terbium-14 9 Terbium-15 0 Terbium-15 1 Terbium-15 3 Terbium-15 4 Terbium-15 5 Atom .



### No .

4 3 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 5 2 6 5 6 5 6 5 6 5 6 5 6 5 6 5 Ingestio n (food )

4.7 E 5 3.I E 4 1.6 E 1 * 1.6 E 2 2.0 E 1 * 1.5 E 1 * 3.6 E 1 * 2.0 E 1 * 7.2 E 3 * 2.0 E 1 * 2.5 E 5 9.6 E 1 6.8 E 4 3.0 E 1 * 3.I E 4 4.6 E 5 2.7 E 5 4.8 E 4 1.2 E 4 1.5 E 4 2.3 E 3 9.9 E 2 9.2 E 2 6.2 E 2 Releas e Value s

Ingestio n (water )

> E 9 v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci )

Inha

lation

3.6 E l.OE l.O E 1.6 E l.OE l.OE 2.I E 1.6 E l.O E l.OE 3.I E 2.I E 2.6 E l.OE 2.6 E l.OE l.O E 1.6 E 3.6 E l.OE 4.7 E 3.6 E 2.I E 4.I E 

### 4 4 2 3 2 2 2 2 4 2 4 2 3 * 

### 2 3 * 

### 4 4 4 2 4 3 3 3 3 Direc t Exposur e

1.3 E 4.I E 1.8 E 6.7 E 2.7 E

- - LI E 5.2 E 2.I E 7.9 E LI E 4.0 E 4.I E 2.0 E 6.5 E 3.4 E l.OE 1.9 E 1.7 E 2.2 E 8.5 E 3.0 E 3.2 E 4.4 E 

### 3 * 3 * 

### 2 1 * 

### 2

5 5 5 2 4 * 1 * 

### 3 2 3 3 * 3 * 2 * 2 * 2 * 1 * 2 * 1 * 2 * Fina l

RQ (Ci )

100 0 100 0 

### 1 0

- -•••• 4 0 

### 1 0 1 0 1 0 1 0 100 0 

### 1 0 100 0 

### 1 0 100 0 

### 1 0 100 0 100 0 100 0 

### 10 0 10 0 10 0 1 0 1 

### 10 0 1 0 

### 10 0
E-2 7P.5 7
APPENDI XE(Continued )

Radionuclid e

Terbium-156 m (5. 0 hr ) Terbium-156 m (24. 4 hr ) Terbium-15 6 Terbium-15 7 Terbium-15 8 Terbium-16 0 Terbium-16 1 Thallium-194 m Thallium-19 4 Thallium-19 5 Thallium-19 7 Thallium-198 m Thallium-19 8 Thallium-19 9 Thallium-20 0 Thallium-20 1 Thallium-20 2 Thallium-20 4 Thorium-22 6 Thorium-22 7 Thorium-22 8 Thorium-22 9 Thorium-23 0 Atom . No .



### 6 5 6 5

6 5 ! 

### 6 5 6 5 6 5 6 5 8 1 8 1 8 1 8 1 8 1 8 1 8 1 8 1 8 1 8 1 8 1 9 0 9 0 9 0 9 0 9 0 Ingestio n

(food )

3.9 E 4
3.0 E 3 *

-- • l.O E 2 1.5 E 3 3.0 E 1 2.8 E 1 * 1.7 E 2 * 8.7 E 5 5.2 E 6 5.I E 5 2.4 E 5 1.5 E 5 3.6 E 4 7.9 E 4 3.I E 3 3.2 E 3 2.4 E 2 6.0 E 1 * 9.2 E 5 5.0 E 1 1.8 E 0 1.8E- 1 1.2 E 0 Releas e Value s

Ingestion (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci ) —

Inha

latio n

1.6 E 4 *
4.I E 3
5.2 E 2 1.6 E 2 * l.OE 1 * l.OE 2 l.OE 3 l.OE 5 3.I E 5 5.2 E 4 5.2 E 4 2.6 E 4 1.6 E 4 4.I E 4 5.2 E 3 l.OE 4 2.6 E 3 l.OE 3 5.2 E 2 * 1.6 E 0 * 5.2E-2 * 4.7E-3 * 3.1E-2 * Direc t

Exposur e

1.4 E 5

- - 2.5 E 1 *

- - 4.9 E 1 3.4 E 1 5.I E 3 5.4 E 2 * 1.5 E 3 * 8.2 E 2 * 8.2 E 2 * 3.I E 2 * 8.3 E 1 * 5.7 E 2 * 4.7 E 1 * 2.I E 3 * 9.2 E 1 *

- - 1.7 E 5 4.5 E 2

- -

- -

- - Fina l

RQ (Ci )

100 0
100 0 

### 1 0 

### 10 0 1 0 1 0 

### 10 0 10 0 100 0 

### 10 0 10 0 10 0 1 0 

### 10 0 1 0 100 0 

### 1 0 1 0 

### 10 0 

### 1 0.0 1 0.00 1 0.0 1 E-2 8P.5 8

Radionuclid e

Thorium-23 1 J Thorium-23 2

_Thorium-23 4

• Thulium-16 2 B Thulium-16 6

Thulium-16 7

• Thulium-17 0

_Thulium-17 1

• Thulium-17 2

• Thulium-17 3

Thulium-17 5

• Tin-11 0

Tin-Il l

• Tin-11 3

• Tin-117 m

Tin-119 m

• Tin-121 m

Tin-12 1

• Tin-123 m

• Tin-12 3

Tin-12 5 I Tin-12 6

Tin-12 7 

### I Tin-12 8 Atom . 

### No .

9 0 9 0 9 0 69

- 6 9 6 9 6 9 6 9 6 9 6 9 6 9 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 APPENDI XE (Continued ) Ingestion (food )

1.6 E 4 2.1E- 1 1.4 E 2 *
•-•-f-r-.8 E 6 5.I E 3 1.4 E 2 * 2.6 E 1 * 3.0 E 2 1.2 E 2 4.7 E 3 2.6 E 6 9.6 E 3 1.1 E 6 6.6 E 1 * 1.1 E 2 * 9.3 E 1 * 8.9 E 1 * 2.3 E 3 * 7.I E 5 1.6 E 1 * 2.8 E 1 * 8.9 E 0 * 3.2 E 4 8.7 E 4 Releas e Value s

Ingestio n (water )

v.lg . v.lg . v.lg .
>E9i t

•-•- • 2.4 E 9 /

/ 3.2 E 2 /

/ 6.2 E 1 /

/ 7.4 E 2 /

/ 6.4 E 2 /

/ 9.7 E 8 /

/

> E 9 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . E-2 9 (n \ \\Sm. ) Inha

lation

3.I E 4 5.2E-3 * l.OE 3 1.6 E 5 5.2 E 3 l.OE 3 l.OE 2 1.6 E 2 * 5.2 E 2 5.2 E 3 1.6 E 5 5.2 E 3 l.O E 5 2.6 E 2 5.2 E 2 5.2 E 2 2.6 E 2 5.2 E 3 5.2 E 4 l.OE 2 2.I E 2 3.I E 1 l.O E 4 1.6 E 4 Direc t

Exposur e

6.0 E 2 * 7.3 E 5 7.0 E 3 2.I E 3 * 4.6 E 1 * 4.0 E 2 1.3 E 4

- - 1.2 E 2 * 2.2 E 2 * 2.9 E 3 * 5.6 E 2 * 8.5 E 3 * 1.4 E 2 2.7 E 2

—

- -

— 6.6 E 3 * 5.3 E 3 1.4 E 2 2.0 E 1 2.0 E 2 * 1.1 E 3 * Fina l

RQ (Ci )



### 10 0 0.00 1 

### 10 0

- 100 0 

### 1 0 10 0 1 0 10 0 10 0 10 0 100 0 

### 10 0 100 0 

### 1 0 10 0 1 0 1 0 100 0 100 0 

### 1 0 1 0 1 10 0 100 0 1



### i

1 1P.5 9

APPENDI XE (Continued )

Radionuclid e Atom . No .

Titanium-4 4 Titanium-4 5 Tungsten-17 6 Tungsten-17 7 Tungsten-17 8 Tungsten-17 9 Tungsten-18 1 Tungsten-18 5 Tungsten-18 7 Tungsten-18 8 Uranium-23 0 Uranium-23 1 Uranium-23 2 Uranium-23 3 Uranium-23 4 Uranium-23 5 Uranium-23 6 Uranium-23 7 Uranium-23 8 Uranium-23 9 Uranium-24 0 Vanadium-4 7 Vanadium-4 8 Vanadium-4 9 2 2 2 2 7 4 7 4 7 4 7 4 7 4 7 4 7 4 7 4 9 2 9 2 9 2 9 2 9 2 9 2 9 2 9 2 9 2 9 2 9 2 2 3 2 3 2 3 Ingestio n (food )

8.9 E 0 2.8 E 4 3.8 E 4 S.6 E 4 2.3 E 2 * 7.6 E 6 6.5 E 2 * 6.9 E 1 * 8.5 E 2 1.4 E 1 * 1.9 E 0 4.9 E 3 * 6.0E- 1 3.0 E 0 3.0 E 0 3.0 E 0 3.0 E 0 1.7 E 3 3.0 E 0 1.7 E 7 7.0 E 3 * 5.5 E 5 3.2 E 1 * 2.2 E 3 * Releas e Value s (Ci ) -

Ingestio n Inha

- (water ) latio n Direc t Exposur e

2.2 E 1 / / > E 9 / / > E 9 / / > E 9 / / 5 . I E 2/

/ > E 9 / / 1.6 E3 / / 1.6 E 2/ / 6.0 E 4/

/ 3.2 E1 / / v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . > E 9 / / 6.9 E 1 /

/ 5.2 E3 /

/ 3.I E 0 * 1.6 E4 * 2.6 E 4 4.7 E 4 l.O E 4 l.O E 6 * 1.6 E4 3.6 E3 4.7 E 3 5.2 E2 1.6 E 0 * 2.6 E4 4.1E-2 * 2.1E-1 * 2.1E-1 * 2.1E-1 * 2.1E-1 * 5.2 E3 2.1E-1 * l.O E 6 l.O E 4 4.I E 4 * 3.I E 2 l.O E 4 2.7 E2

2.I E 3 * 5.7 E 2 *

2.2 E5 1.5 E6 1.1 E2 * 2.3 E4 4.I E 4 5.3 E 3

1.9 E6 7.5 E 5 2.7 E2 1.6 E6 7.2 E 2 *

3.5 E5 *

3.4 E5 3.5 E1 Fina l

R Q (Ci )



### 1 100 0 100 0 

### 10 0 10 0 100 0 

### 10 0 1 0 1.00 

### 1 0 

### 1 100 0 0.0 1 

### 0. 1 0. 1 0. 1 0. 1 10 0 0.1 & 100 0 100 0 100 0 

### 1 0 100 0 E-3 0Radionuclid e

Xenon-12 0

• Xenon-12 1

_Xenon-12 2

~ Xenon-12 3 fl Xenon-12 5

Xenon-12 7 1 Xenon-129 m

Xenon-131 m

• Xenon-133 m

• Xenon-13 3

Xenon-135 m H Xenon-13 5

Xenon-13 8

• Ytterbium-16 2

• Ytterbium-16 6

. Ytterbium-16 7

• Ytterbium-16 9

Ytterbium-17 5

• Ytterbium-17 7

• Ytterbium-17 8

Yttrium-86 m I Yttrium-8 6

Yttrium-8 7

• Yttrium-8 8 Atom . No .



### 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 5 4 7 0 7 0 7 0 7 0 7 0 7 0 7 0 3 9 3 9 3 9 3 9 APPENDI XE (Continu e Ingestio n (food )



### n a n a n a n a n a n a n a n a n a na n a n a n a 2.I E 6 2.0 E 2 9.8 E 6 8.2 E 1 * 3.7 E 2 * l.OE 5 7.8 E 4 2.4 E 5 6.7 E 2 2.9 E 2 3.3 E 1 Releas e Value s

Ingestio n (water )



### n a n a n a n a n a n a n a n a n a n a n a n a n a
> E 9 1.2 E 3

> E 9 1.8 E 2 1.1 E 3

> E 9

> E 9 v.lg . v.lg . v.lg . v.lg . E-3 1 /

/ / / / / / / / / / / / / 

### d ) (Ci ) — Inha

lation



### n a n a n a n a n a n a n a n a n a n a n a n a n a 1.6 E 5 l.O E 3 3.6 E 5 3.6 E 2 1.6 E 3 2.6 E 4 2.I E 4 * 2.6 E 4 1.6 E 3 1.6 E 3 l.OE 2 Direc t

Exposur e

l.OE 2.0 E 7.0 E 6.0 E 2.0 E l.OE 2.0 E 4.0 E l.OE l.OE 9.0 E l.OE 4.0 E 2.2 E 4.2 E 1.5 E 1.9 E LI E 2.2 E

- - 3.9 E 2.3 E 5.I E 1.4 E 

### 2* + 1* + 2* + 1* + 2* + 2* + 3* + 3* + 3* + 3* + 1* + 2* + 1* + 4 * 1 * 4 * 

### 2 3 3 *

3 * 1 * 1 * 1 * Fina l

RQ (Ci )



### 10 0 1 0 

### 10 0



### - i o 

### 10 0 10 0 100 0 100 0 100 0 100 0 

### 1 0 

### 10 0 1 0 100 0 

### 1 0 100 0 

### 1 0 

### 10 0

1 100 0 100 0 1

1 100 0 ' 1 0 ! 1

! 

### 1 0 1

1

! 

## 1APPENDI XE(Continued ) P.6 1

Radionuclid e

Yttrium-90 m Yttrium-9 0 Yttrium-91 m Yttrium-9 1 Yttrium-9 2 Yttrium-9 3 Yttrium-9 4 Yttrium-9 5 Zinc-6 2 Zinc-6 3 Zinc-6 5 Zinc-69 m Zinc-6 9 Zinc-71 m Zinc-7 2 Zirconium-8 6 Zirconium-8 8 Zirconium-8 9 Zirconium-9 3 Zirconium-9 5 Zirconium-9 7 Atom .



### No .

3 9 3 9 3 9 3 9 3 9 3 9 3 9 3 9 3 0 3 0 3 0 3 0 3 0 3 0 3 0 4 0 4 0 4 0 4 0 4 0 4 0 Ingest s

(food :

2.4 E 7 . I E 1.1 E 1.8 E 8.I E 9.6 E 6.I E 2.2 E l.OE 2.9 E 1.2 E 2.7 E 5.7 E 1.4 E 2.3 E 6.0 E 1.4 E 3.0 E 3.0 E 3.5 E 3.6 E 

### .o n )



### 4 1 * 6 1 * 3 2 5 6 3 5 1 * 3 5 4 2 * 2 2 2 1 1 * 2 Releas e Value s Ingestio n (water )

v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . 5.7 E 7 /

/

> E 9 / / 3.0 E 1 /

/ 4.4 E 6 /

/

> E 9 / /

> E 9 / / 2.5 E 3 /

/ v.lg . v.lg . v.lg . v.lg . v.lg . v.lg . (Ci )

Inha

lation

5.2 E 3.I E l.OE 5.2 E 4.I E l.OE 4.I E 5.2 E 1.6 E 3.6 E 1.6 E 3.6 E 5.2 E l.O E 5.2 E l.OE l.OE l.OE 3.I E 5.2 E 5.2 E 

### 3 2 5 1 3 3 4 4 3 4 2 3 4 * 4 2 3 2 3 0 * 1 2 Direc t Exposur e

3.0 E

- - 1.4 E l.OE 7.0 E 8.8 E 1.4 E 3.I E 2.6 E 7.I E 6.4 E 1.5 E 2.0 E 

### LI E 3.I E 2.2 E 9.6E 1.6E

— 

### 5.0 E 6.9 E 2 *

3 * 4 2 * 2 * 3 * 3 * 2 * 3 * 1 2 * 8 2 * 2 2 * 1 * 2 *

1 1 * Fina l

R Q (Ci )

10 0 1 0 100 0 1 0 10 0 10 0 100 0 100 0 10 0 100 0 1 0 10 0 100 0 10 0 10 0 10 0 1 0 10 0 1 

### 1 0 1 0

E-3 2P.6 2

APPENDI XE (Continued ) FOOTNOTE S

& Th e adjuste d RQ o f on e curi e applie s t o al l radionuclide s no t otherwis e listed . Wheneve r th e RQ s foun d in 4 0 CFRPar t 302. 4 an d thi s appendi xar e i n conflict , th e lowes t RQ shal l apply . Fo r example , urany l acetat e an d urany l nitrat e hav e adjuste d RQ s show

n in 4 0 CFRPar t 302. 4 o f 10 0 pounds , equivalen t t o abou t one tent ho f th e RQ leve l fo r uranium-23 8 listed i n thi s appendix . E Exponen t t o the bas e 10 . Fo r example , 1.3 E 2 i s equa l t o 13 0 whil e 1.3 E 3 i s equa l t o 1300 . * Indicate s th e lowes t releas e valu e fo r the specifi c radionuclide ; thi s valu e i s use d t o determin e the propose d R Q group . v.lg . Indicate s tha t the sorptio n coefficien t i s greate r than zer o an d the releas e valu e i s muc hgreate r than tha t fo r othe r pathways . / / Avalu e fo r the sorption coefficien t o f thi s radionuclid e wa s unavailabl e an d the valu e i s conservativel yassume d t o be equa l t o zero . No gamm a ray s ar e emitte d o r th e gamm a rays whic har e emitte d hav e gamm a ra y energie s o f les s than 0.0 7 MeV an d ar e strongl yattenuate d in air . No releas e valu e fo r the direc t exposur e pathwaywa s calculated . mSignifie s a nuclea r isome r whic hi s a radionuclid e i n a highe r energ ymetastabl e stat e relative t o the paren t isotope . + Th e releas e valu e wa s calculate d assumin g submersio n in an airborn e cloud . Th e derive d ai r concentratio n (DAC ) i s used t o estimat e the releas e valu e fo r the specifi c radionuclide . na A n annua l limi t o f intak e (ALI ) fo r eithe r ingestion o r inhalation (or both ) wa s unavailabl e fo r thi s radionuclide . >E 9 Th e calculate d releas e valu e fo r thi s pathwa yi s greate r than on e billio n curies .

NOT E I n orde r t o determin e the fina l R Q fo r a radionuclid e in unit s o f becquerel , multipl y th e numbe r o f curie s b y3.7 E 1 0 ( 1 curi e i s equa l t o 3.7 E 1 0 becquerel) .

E-3 3