p. 1 

# PICK-U P DATE : BO X 

# 1 0 O F 

# 10 Step2 : FO RASR C INTERNA

L US E ONLY 

### (PARTA

_of_ B )



# EP ADOCKE TID : 102RQ-R N 41 ) 102RQ-RN-5- 3 43 ) 102RQ-RN-5- 5 45 ) 102RQ-RN-5- 7 47 ) 102RQ-RN-5- 9 49 ) 102RQ-RN-5-1 1 51 ) 102RQ-RN-5-1 3 53 ) 102RQ-RN-5-1 5 55 ) 102RQ-RN-3- 4 57 ) 59 ) 61 ) 63 ) 65 ) 67 ) 69 ) 71 ) 73 ) 75 ) 77) 79) Ste p 3 : FOR ASR C INTERNA LUS E ONL Y CD : OA : / 

# 42 ) 102RQ-RN-5- 4 44 ) 102RQ-RN-5- 6 46 ) 102RQ-RN-5- 8 48 ) 102RQ r 

# RNil 0 50)(l02RQ-RN-5-1 2 3 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 )

Ste p 1 : FOR ASR

C INTERNA LUS E ONL Y Ar e ther e more documents fo rthi s Docketi n anothe rbox?(*YES// N O "'Fil l ou tContinuatio n Shee tan d go t o Ste p 2 Interna l SFUN D Bo

xNumbe r 3 5 O F 28 3 Initials/Date : LD S / 3-8-200 7PJ.
SFu*b-t9$l-0O0*fTECHNICA LBACKGROUN D DOCUMEN TT O SUPPOR T PROPOSE D RULEMAKIN G PURSUAN TT O SECTIO N 102 O F TH E COMPREHENSIV E ENVIRONMENTA LRESPONSE , COMPENSATION ,

AN D LIABILIT YACT : RADIONUCLIDE S

ARepor tt o th e EMERGENC YRESPONS E DIVISIO N Offic e o fEmergenc yan d Remedia l Respons e U.S

. Environmenta l Protectio n Agenc y

Decembe r198 6

Prepare d b y IC F INCORPORATE D an d ENVIRONMENTA LMONITORIN G AN D SERVICES , IN C

EP AContrac t68-03-318 2

y_P. 3 

### (02RQ)~RN-5-(2 ?

TECHNICA LBACKGROUN D DOCUMEN TT O SUPPOR T PROPOSE D RULEMAKIN G PURSUAN TT O SECTIO N 102 O F TH E COMPREHENSIV E ENVIRONMENTA LRESPONSE , COMPENSATION ,

AN D LIABILIT YACT : RADIONUCLIDE S

ARepor tt o th e EMERGENC YRESPONS E DIVISIO N Offic e o fEmergenc yan d Remedia l Respons e U.S

. Environmenta l Protectio n Agenc y

Decembe r198 6

Prepare d b y IC F INCORPORATE D an d ENVIRONMENTA LMONITORIN G AN D SERVICES , INC

.

EPAContrac t68-03-318 2

## P. 4

TABL E O F CONTENT S
Pag e CHAPTE R1 : BACKGROUN D AN D INTRODUCTIO

N1- 1 1. 1 Backgroun

d o nCERCL

Aan d R Q NotificationRequirement s 1- 1 1. 2 R Q Adjustment s for Radionuclide s 1- 2 1. 3 Th e Scop e o f the Radionuclid e Releas e Proble m1- 5 1.3. 1 The Affected Community1- 6 1.3. 2 Radionuclid e Releas e Histor y1- 9 1. 4 Organizationo f Thi s Repor t 1-1 0 CHAPTE R2 : OPTIONS FO RTHE ADJUSTMEN

T OF RADIONUCLID E RQ s 2- 1 2. 1 Optio n1 : Allowing the Radionuclid e RQ t o Remai nat On e Poun

d 2- 1 2. 2 Optio n2 : Considering Radionuclide s a s a Generi c Clas s o f Substances , Withou t a nR Q an d No t Subjec t t o CERCL A Reporting Requirement s 2- 2 2. 3 Optio n3 : Establishing a Dose-Equivalen t Leve l a s the Radionuclid e R

Q 2- 3 2. 4 0ption-4 : Considering Radionuclide s a s a Clas s Wit ha Singl e ActivityLeve l 2- 5 2. 5 Optio n5 : Grouping Radionuclide s int o Categorie s Wit h a n ActivityLeve l Assigned t o Eac ho f the Separat e Categorie s 2- 5 2. 6 Optio n6 : Establishing a nActivityLeve l R

Q for Individua l Radionuclide s 2- 7 CHAPTE R3 : IDENTIFICATIO NO F ALIS T O F RADIONUCLIDE S 3- 1 3. 1 Rar e Radionuclide s 3- 2 3. 2 Short-Lived Radionuclide s 3- 3P. 5



### TABLEO FCONTENT S

(continued ) Pa^ e CHAPTE R4 : METHODOLOG YFO RPROPOSE D R

Q ADJUSTMENT S 4- 1 4. 1 Method s Considered for Relatin g RadiationDamag e t o Release s inUnit s o f Curie s 4- 1 4. 2 Method for Determining RQ s Based onInhalation , Ingestion , an

d Direc t Exposur e 4- 2 4.2. 1 Releas e Value s for the InhalationPathwa y4- 3 4.2. 2 Releas e Value s for the IngestionPathwa y4- 5 4.2. 3 Releas e Value s fo r the Direc t Exposur e Pathwa y4-1 2 4. 3 Assignmen t o f Radionuclide s t o Proposed R Q Group s 4-1 8 4. 4 Reporting Requirement s for Mixture s o f Radionuclide s 4-2 0 4.4. 1 Mixture s o f Know nComposition4-2 0 4.4. 2 Mixture s o f Unknow nComposition4-2 1 4.4. 3 Commo nRadionuclid e Mixture s 4-2 2 APPENDI XA : Existing Reporting Requirement s A- 1 APPENDI XB : Affected Facilitie s B- l APPENDI XC : Othe r Method s fo r Calculating RQ s C- l APPENDI XD : Releas e Fraction s for InhalationD- l APPENDI XE : Derivatio no f the Atmospheri c Relative Concentratio n

Valu e E- l APPENDI XF : Route s for Ingestiono f Radionuclide s F- 1 APPENDI XG : Calculationo f Direc t Exposur e Releas e Value s G- 1

## P. 6

CHAPTE R1 BACKGROUN D AND INTRODUCTIO N

Thi s repor t discusse s th e option s tha t wer e considered b yth e Environmenta l ProtectionAgency(EPA ) for adjusting the one-poun d statutor

y reportabl e quantity(RQ ) for radionuclides , an d present s indetai l the option an d method 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 LiabilityAc t (CERCLA ) an d the specifi c reporting requirement s for radionuclides . Section1. 1 describe s CERCL Areportin

g requirement s an

d the type s o f potentia l respons e activitie s triggered b yCERCL Areporting ; Section 1. 2 describe s the statutor yauthorit yfo r an

d th e intended purpos e o f the RQ adjustmen t for radionuclides ; Section1. 3 explain s the scop e o f the radionuclid e releas e problem ; an d Section 1. 4 introduce s the remainin g chapter s o f thi s report . 1. 1 BACKGROUN D O N CERCL AAN D R Q NOTIFICATIO N REQUIREMENT S Th e Comprehensive Environmenta l Response , Compensation , an d LiabilityAc t o f 198 0 (CERCLA ) establishe s broad 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 nt o the Nationa l Respons e Cente r whe na hazardou s substanc e designate d unde r CERCL Ai s released int o the environmen t inanamoun t equa l t o o r greate r thanth e R Q for 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 :

• Section s 30 7 an d 31 1 o f th e CleanWate r Act ;

• Sectio n300 1 o f the Resourc e Conservatio nan d Recover

y Act ;

• Section11 2 o f the CleanAi r Act ; an d

• Section7 o f the Toxi c Substance s Contro l Act . I naddition , EP

Aha s the authorityunde r Sectio n102(a ) o f CERCL At o designat e additiona l hazardou s substances . Currently , ther e ar e 71 7 CERCL Ahazardou s substance s i f "radionuclides " ar e considered on e hazardou s substance . Radionuclide s ar e considered hazardou s substance s unde r CERCL Abecaus e the

y wer e designate d genericall ya s a hazardou s ai r pollutan t pursuan t t o Sectio n 11 2 o f the CleanAi r Act . Sectio n102(b ) o f CERCL Aestablishe s a one-poun d RQ for al l designate d substances , excep t thos e for whic hanRQ wa s established

## P. 7

1- :

pursuan t t o Sectio n31 1 o f th e Clea n Wate r Act . Sectio n 102(a ) o f CERCL A authorize s EP At o adjus t statutor yRQ s b yregulation. 1 Unde r regulation s implementin g th e genera l reportin g requirement s o f Section s 103(a ) and (b ) o f CERCLA , a perso n i n charg e o f a vesse l o r facilit y i s require d t o notif yth e 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 a n amoun t tha t equal s o r exceed s th e R Q fo r tha t substanc e (4 0 CF RSectio n 302.6(a)) . Thos e person s require d t o notif ybu t wh o fai l t o repor t immediatel yt o th e Nationa l Respons e Cente r 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 fromth e Sectio n10 3 notificatio n requirements . Th e purpos e o f R Q notificatio n i s t o aler t th e federa l governmen t t o release s o f hazardou s substance s tha t ma yrequir e rapi d respons e t o protec t publi c healt hand welfar e an d th e environment . Unde r Sectio n 10 4 o f CERCLA , th e federa l governmen t ma ytak e 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 whic hma ypresen t a n imminen t and substantia l dange r t o publi c healt ho r welfare. 2 Notificatio n base d o n RQ s serve s t o infor mth e governmen t o f a release , therebyenablin g a n evaluatio n o f th e situatio nand a timel yfiel d respons e shoul d on e b e deeme d necessary . Notificatio n doe s no t necessaril ymea ntha t a federa l fiel d respons e wil l occur , no r doe s i t eliminat e liabilit yo r responsibilit yfo r respons e cost s o r natura l resourc e damage s associate d wit hth e release . 1. 2 R Q ADJUSTMENT S FO R RADIONUCLIDE S Ther e ar e approximatel y180 0 know n radionuclides . Aradionuclid e i s a n isotop e wit ha nunstabl e combinatio n o f proton s and neutron s i n it s nucleus . Instabilit yi s th e resul t o f a n imbalanc e i n repulsiv e and adhesiv e force s betwee nthes e tw o type s o f nuclea r particles . T o achiev e a mor e stabl e configuration , th e nucleu s release s energ yi n th e formo f particle s o r ray s b y a proces s o f deca ycalle d radioactivity . Th e energ yleve l o f th e resultin g nucleu s (i.e. , th e daughter ) differ s fromth e origina l nuclea r energ yleve l b y th e su mo f th e energie s emitted . Eac hradionuclid e decay s b ya specifi c

l Th e RQ s fo r 34 0 hazardou s substance s wer e adjuste d b yEP Ao n Apri l 4 , 196 5 (5 0 F R13456) . R Q adjustment s fo r a n additiona l 10 2 substance s wer e promulgate d i na fina l rulemakin g publishe d o n Septembe r 29 , 198 6 (5 1 F R 34534) . Th e radionuclid e R Q wa s not adjuste d no r propose d fo r adjustmen t i n eithe r o f thes e rulemakings . Notificatio n t o th e 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 th e applicabl e RQ . Release s consistin g 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 th e Nationa l Respons e Center .P. 8

l- J

mechanis manda t a specifi c rat e and , a s a result , a poun do f tw o differen t radionuclide s coul drepresen t significantl ydifferen t level s o f radioactivity . Ther e ar e thre e type s o f radioactiv e emission s fromradionuclide s during [ th e deca yprocess : alph a particles , bet a particles , andgamm a rays . Th e : particle s andray s diffe r i nthei r mass , charge , energ ycontent , andrang e o f penetratio ni nsurroundin g media . ! Alph a particle s consis t o f tw o proton s andtw o neutron s andhav e a j positiv e charg e o f +2 . Alph a particle s posses s energie s i nth e rang e o f 2 t o 1 2 millio nelectro nvolt s (MeV) , wit htypica l value s fallin g betwee n4 and9 ; MeV . Th e alph a ray s trave l byshort , straigh t paths , andar e highl y] disruptiv e i ntissu e becaus e o f thei r hig hmomentumandcharge . ; Bet a particle s ar e eithe r electron s o r positrons , bu t ar e mos t ofte n electrons . Th e energ yrang e o f bet a particle s i s 0.0 2 Me V and1 4 MeV , wit h\ typica l value s fallin g betwee n0.0 4 and6 MeV . Bet a particle s ar e mor e penetratin g (i.e. , hav e a longe r rang e i nmatter ) tha nalph a particles , an d ar e mor e easil yscattere dandar e les s disruptiv e tha nalph a particles . Gamm a ray s ar e photon s tha t hav e n o mas s andn o charge , andposses s energie s i nth e rang e o f 0.0 1 t o 1 0 MeV . Gamm a ray s ar e no t scattere deasil y andca nb e ver ypenetrating . , i A s note dpreviously , radionuclide s ar e designate da s hazardou s ai r ' pollutant s unde r Sectio n11 2 o f th e Clea nAi r Ac t andare , therefore , I designate dCERCL Ahazardou s substances . Sectio n10 2 o f CERCL Aestablishe s a 1 one-poun dreportabl e quantit yfo r radionuclides , a s a generi c clas s o f substances , bu t authorize s EP At o adjus t thi s R Q b yregulation . EP A recognize s tha t a nR Q o f on e poun dfo r radionuclide s i s no t appropriat e i n mos t case s becaus e release s o f les s tha non e poun do f a radionuclid e ma y presen t a substantia l dange r t o publi c healt handwelfar e andt o th e environment . I naddition , "pound " unit s ar e no t commonl yuse dfo r measurin g radionuclides . CERCL Ahazardou s substance s othe r tha nradionuclide s hav e reportabl e j quantitie s rangin g fromon e poun dt o 500 0 pounds . Fo r thes e substances , th e principa l healt hconcern s ar e chemica l toxicity , ignitability , reactivity , o r potentia l carcinogenicity . Thes e criteri a ma yb e relate dt o a specifi c numbe r o f pound s o f th e hazardou s substanc e released . Radionuclide s ar e ver y differen t fromothe r CERCL Ahazardou s substance s becaus e th e principa l healt h hazar dassociate dwit hexposur e t o radionuclide s i s radioactivity , no t chemica l toxicit yo r th e othe r concern s mentione dabove . Althoug hth e leve l o f radioactivit yfo r a give nradionuclid 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 adverse ^ healt handenvironmenta l effects . Fo r thi s reason , activit ylevel s ar e mos t ; generall yuse da s indicator s o f radiatio nintensit yandpotentia l hazard . Th e quantit yo f radioactivit yi s measure di nunit s o f curies 3 (Ci ) and , fo r 3 Th e curi e i s a measur e o f th e rat e o f radioactiv e decay , wit hon e curi e equa l t o 3. 7 x10 1 0 disintegration s pe r second .P. 9

1- 4

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 , th e statutor yone-poun d R Q translate s int o a wid e ] rang e o f curie s fo r differen t radionuclides , coverin g twent yorder s o f magnitude . I nadditio nt o curies , anothe r widel yuse d uni t fo r measuremen t o f radiatio nhazar d i s th e re m(originall yRoentge n Equivalen t Man) . Th e re mi s a uni t o f measur e fo r radiatio n dose-equivalen t and i s ofte n expresse d a s som e numbe r o f remdelivere d t o a specifi c orga n suc ha s th e lungs , thyroid , o r whol e body . Wherea s th e curi e i s a measur e o f th e quantit yo f radiatio n emitted , th e dose-equivalen t i n remconsider s th e route s o f exposur e and type s o f radiatio nencountere d and therefor e directl yreflect s th e leve l o f tissue ' damage . Curie s ca nb e converte d int o re mbyidentifyin g th e radionuclide , rout e and duratio no f exposure , quantit yo f intake , tissue s mos t affected , typ e o f radiation , and othe r factor s tha t determin e th e hazardou s effect s of ; th e radiation . Th e nuclea r industr ygenerall yuse s unit s o f curie s and remand , i nfact , mos t existin g reportin g trigger s fo r radionuclid e release s ar e expresse d i n term s o f on e o r th e other , o r both , o f thes e tw o units. * I n addition , essentiall yal l existin g regulation s and control s establishe d byth e Nuclea r Regulator yCommissio nand th e Departmen t o f Energy , whic hgover n a majo r portio no f th e nuclea r industry , ar e base d o n unit s o f curie s o r rem . Therefore , fo r th e R Q unde r CERCL At o b e consisten t and meaningful , and t o ensur e tha t th e radionuclid e R Q allow s fo r timel yreportin g and timel yfiel d response , i f necessary , th e statutor yone-poun d R Q i s bein g adjuste d i na propose d regulation . Th e propose d R Q adjustment s ar e i n unit s o f curies . Th e Agenc yi s proposin g specifi c R Q adjustment s fo r th e 75 7 radionuclide s fo r whic hth e Internationa l Commissio n o n Radiatio n Protectio n (ICRP ) ha s provide d metaboli c dat a an d recommende d intak e limit s i n ICR P Publicatio n 30. s Al l radionuclide s no t liste d byth e ICR P ar e groupe d int o a generi c clas s o f "Radionuclides, " wit hon e propose d R Q fo r th e entir e class . Chapter s 3 and 4 o f thi s repor t discus s th e numerou s type s o f radionuclide s and th e R Q adjustmen t proces s i nmor e detail . Th e harmfu l effect s o f radiatio n o n human s ha s bee n th e focu s o f mos t o f th e researc heffort s concernin g radiatio n exposur e i n th e past . EPA' s .mandat e unde r CERCL Ais , o f course , concerne d wit hth e broade r proble mo f potentiall y deleteriou s effect s t o th e environmen t a s wel l a s t o humans . I n proposin g

''Radiationmeasurement s ca n als o b e expresse d i n internationa l metri c unit s o f becquerel s o r sieverts ; however , thes e term s ar e les s commo n i nth e Unite d States . 5 Internationa l Commissio n o n Radiatio n Protection , Annal s o f th e ICRP : Limit s fo r Intake s o f Radionuclide s byWorkers , ICR P Publicatio n 30 , Par t 2 , 1980 . 

# IP.1 0

1- 3

adjustment s t o th e radionuclid e RQ , th e Agency' s goa l i s t o ensure , t o th e exten t possible , ampl e protectio n fo r th e mos t sensitiv e specie s o f flor a and fauna . Th e Agenc yreviewe d th e existin g literatur e and determine d tha t presen t informatio nindicate s tha t protectio n o f huma n healt hwoul d b e sufficientl yprotectiv e o f th e environmen t a s well . Th e Nationa l Academ yo f Scienc e states :

Th e principa l potentia l impac t o f radioactiv e effluent s o n th e biospher e i s th e inductio n o f deleteriou s healt heffect s i nman . Comparabl e level s o f impac t undoubtedl yexis t i n othe r biota , bu t ther e i s n o presen t evidenc e tha t ther e i s anybiologica l specie s whos e sensitivit yi s sufficientl y hig ht o warran t a greate r leve l o f protectio n tha n tha t adequat e fo r man. 6
I naddition , th e Internationa l Commissio n o n Radiatio n Protectio n (ICRP ) ha s state d a s par t o f it s recommende d objective s that :

Althoug hth e principa l objectiv e o f radiatio n protectio n i s th e achievemen t and maintenanc e o f appropriatel ysaf e condition s fo r activitie s involvin g huma n exposure , th e leve l o f safet yrequire d fo r th e protectio n o f al l huma n individual s i s though t likel yt o b e adequat e t o protec t othe r species , althoug hno t necessaril yindividua l member s o f thos e species . Th e Commissio n therefor e believe s tha t i f ma ni s adequatel yprotecte d the n othe r livin g thing s ar e als o likel yt o b e sufficientl yprotected. 7 Th e Agenc yha s determined , therefore , tha t R Q adjustment s fo r radionuclide s develope d wit hth e goa l o f protectin g publi c healt hwil l protec t th e environmen t a s well . Th e Agenc yis , however , solicitin g comment s o nthi s issu e i nth e propose d rul e and wil l conside r an ydat a o n thi s subjec t submitte d durin g th e publi c commen t period . 1. 3 TH E SCOP E O F TH E RADIONUCLID E 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 fromothe r activitie s a s well . Th e Nuclea r Regulator yCommission , agreemen t states , and th e Departmen t o f Energy '

6 Nationa l Academyo f Sciences , Th e Effect s o n Populatio n o f Exposur e t o Lo wLevel s o f Ionizin g Radiation , Repor t o f th e Advisor yCommitte e o n th e Biologica l Effect s o f Ionizin g Radiation , Nationa l Researc hCouncil , November ! 1972 , p.11 . j internationa l Commissio n o n Radiatio n Protection , Recommendation s o f ! th e Internationa l Commissio no n Radiatio n Protectio n (ICRP) , Publicatio n26 , ; Januar y1977 , p . 3 . jP.1 1

1- 6

(DOE ) al l licens e o r overse e a variet yo f industria l facilitie s and non-industria l operation s tha t emi t radionuclides . I n addition , severa l industria l categorie s no t license d b yth e Commissio n o r a n agreemen t stat e ' coul d potentiall yreleas e radionuclides . Coal-fire d utilitie s and industria l boilers , and minera l extractio n industrie s suc ha s uranium , aluminum , zinc , i copper , lead , and phosphorou s minin g al l releas e certai n amount s o f ! radionuclide s durin g thei r operations . Thi s sectio n discusse s th e type s o f ; facilitie s mos t likel yt o b e affecte d b yth e propose d R Q adjustment s and j review s briefl yth e availabl e dat a o n pas t radionuclid e releases . j 1.3. 1 Th e Affecte dCommunit y Th e Nuclea r Regulator yCommissio n ha s authorit yunde r th e Atomi c Energ y; Ac t t o licens e source , byproduct , an d specia l nuclea r materials , Agreement , state s ar e thos e which , afte r enterin g int o a n agreemen t wit hth e Commission ; hav e th e authorit yt o licens e source , byproduct , and specia l nuclea r material s fo r facilitie s withi nthei r boundarie s (se e Appendi xA , Exhibi t A-1 , fo r a lis t o f agreemen t and non-agreemen t states) . A s o f 1984 , ther e wer e 8,90 0 Commissio nlicensee s and 13,00 0 agreemen t stat e licensees. 9 Bot hstat e and ! federa l licensee s ar e subjec t t o th e radioactiv e materia l releas e limit s > specifie d i n1 0 CF RPar t 20 , a s wel l a s othe r control s specifie d byth e [ license . Licensee s ca nb e divide d int o th e followin g fiv e genera l categories :

• powe r reactors ;

• researc hand tes t reactors ;

• radiopharmaceuticals ;

• radiatio nsourc e manufacturers ; and othe r licensees , includin g laboratories , low-leve l wast e disposa l sites , minera l and meta l processin g • facilities , uraniummills , fue l cycl e facilities , and Departmen t o f Defens e facilities , includin g th e Arme d Force s Radiobiolog yResearc hInstitut e and nin e nava l shipyards .

8 Thes e term s ar e define d i n Sectio n 11(e ) o f th e Atomi c Energ yAct . Sourc e materia l i s define d a s natura l uranium(comprise d o f 99.2 7 percen t U 238 , 0.7 2 percen t U 235 , and 0.005 7 percen t U 2 3 * ) , natura l thorium (Th 232 ) , an d anycombinatio n o f natura l uraniuman d thorium . Specia l nuclea r materia l i s define d a s plutoniumo r anycombinatio n o f uranium isotope s i nwhic hU 2 3 5 i s enriche d (i.e. , make s u p mor e tha n 0.7 2 percen t by weight) . Byproduc t materia l i s define d a s an yradionuclid e whic hi s yielde d i no r mad e radioactiv e byexposur e t o radiatio n inciden t t o th e proces s o f producin g o r utilizin g specia l nuclea r material . 9 U.S . Nuclea r Regulator yCommission , 198 4 Annua l Report , p . 73 .P.1 2

Th e Atomi c Energ yAc t o f 195 4 (Sectio n16 1 o f Publi c La w83-703 ) authorize s DO E "t o protec t th e publi c healt handsafety " wit hrespec t t o th e operatio no f so-calle d"GOCO " facilitie s - - facilitie s whic har e "governmen t I owned , contracto r operated. " A s o f 1980 , 7 8 GOC O facilitie s i n2 4 state s wer e subjec t t o th e healt handsafet yrequirement s containe di nDO E Orde r 5484.1 . Althoug hradionuclid e release s i ncomplianc e wit hDO E Order s ar e considere d federall ypermitted , thes e facilitie s ar e no t Commissio nlicensees . Majo r DO E facilitie s includ e nationa l laboratories , facilitie s associate dwit hth e Formerl yUtilize dSite s Remedia l Actio nProgra m(FUSRAP) , th e Uranium Mil l Tailing s Remedia l Actio nProgra m (UMTRAP) , th e Gran dJunctio nRemedia l Actio n Progra m(GJRAP) , th e Surplu s Facilitie s Managemen t Progra m (SFMP) , and. facilitie s involve di nspecifi c researc handdevelopmen t programs. 1 0 DO E i s als o responsibl e fo r operatin g uranium enrichmen t facilities , a ste p i nth e ! nuclea r fue l cycle . Othe r DO E operation s involvin g radionuclide s includ e ' nuclea r weapon s research , development , andproduction ; medica l andbiologica l research ; andindustria l application s anddevelopment . I n1982 , ther e wer e j thirt y"active " DO E complexes , manyo f whic hhav e severa l operatin g facilitie s A 1 Ove r 7 0 percen t o f th e facilitie s tha t us e o r generat e radionuclide s ar e j no t license dbyth e Nuclea r Regulator yCommission , a nagreemen t state , o r by; th e Departmen t o f Energy . Thes e facilitie s ar e discusse dbriefl ybelow . ' Larg e coal-fire dboiler s ar e use dt o generat e electricit yfo r publi c and industria l us e andt o provid e proces s steam , proces s ho t water , andspac e heat . Mor e tha n60 0 millio nton s o f coa l ar e burne deac hyea r i nutilit yand industria l boilers . Coa l contain s minera l matte r includin g trac e quantitie s o f naturall yoccurrin g radionuclides . Uranium-23 8 andthorium-23 2 andthei r deca yproduct s ar e foundi nrelativel ylarg e quantitie s i ncoal, 1 2 however , base do nsampl e result s fo r fiv e utilit yboilers, 1 3 les s tha nthre e percen t ' o f th e tota l quantit yo f radionuclide s inpu t fromcoa l i s usuall yrelease dto j th e air . \

1 "Roger s andAssociate s Engineerin g Corporation , Radioactiv e Contaminatio na t Federall yOwne dFacilities , Jun e 1982 , pp . 3-2 , 3-3 . 11 "Active " i s define dt o mea nfacilitie s currentl ygeneratin g radioactiv e waste . 1 2 U.S . Environmenta l Protectio nAgency , Radionuclide s Backgroun d Informatio nDocumen t fo r Fina l Rules , Volum e II , Octobe r 1984 , p . 4.0-1 . 1 3 U.S . Environmenta l Protectio nAgency , Surve yo f Fiv e Utilit yBoiler s fo r Radionuclid e Emissions , Fina l Report , Offic e o f Radiatio nPrograms , Washington , D.C , Decembe r 1983 , p . 3 .P.1 3

i- 0

I nearl y1985 , ther e wer e 1,28 1 coal-fire d unit s operatin g i n th e utilit y industry , wit ha tota l generatin g capacit yo f 28 1 gigawatts . ll> Majo r user s o f coal-fire d industria l boiler s (producin g proces s steamand ho t water , generatin g electricit yfo r th e producers ' ow n use , and providin g spac e heat) ; includ e th e steel , aluminum , chemical , and pape r industries . Ther e ar e a n estimate d 51,18 7 coal-fire d industria l boiler s operatin g i n th e Unite d States . Radionuclid e emissio nlevel s fromlarg e utilit yboiler s ar e generall yi nthe i rang e o f 0.000 1 curie s pe r day ; radionuclid e emissio n level s fro mth e smalle r industria l boiler s ar e generall yi n th e rang e o f 0.0000 1 curie s pe r day. 1 5 ; Almos t al l minera l extractio n industrie s tha t involv e th e remova l and processin g o f ore s t o recove r meta l releas e som e radionuclides . Th e Agenc y' ha s identifie d th e followin g minera l extractio n industrie s a s havin g potentia l fo r releas e o f radionuclides : th e uraniumminin g industry , th e aluminum> industry , th e coppe r industry , th e zin c industry , th e lead industry , and th e ' phosphat e industry . Thes e industrie s wer e identifie d becaus e o f th e larg e i quantit yo f or e mine d domesticall yand becaus e th e minin g processe s use d ! creat e a likelihoo d o f radionuclid e emissions . Individua l radionuclid e emissio nlevel s ar e generall yi n th e rang e o f 0.0000 1 curie s t o 0.00000 1 curie s pe r da yfro mthes e facilities. 1 6 [ Thes e industrie s includ e th e followin g facilitie s whic hus e o r produc e radionuclides :

Categor yo f Facilit yNumbe r o f Facilities 1 7 Uranium

Mine s 18 1 (2 1 active ) Aluminum

Smelter s 3 2 Coppe r Smelter s 1 5 Zin c Smelter s 5 Lea d Smelter s 5 Phosphat e Roc k Processin g 3 1 Elementa l Phosphoru s Plant s 6
l *IC F Energ yService , Summer/Fal l 198 5 Coa l and Electri c Utilitie s Marke t Assessment , p . 1- 2 (1985) . 1 S U.S . Environmenta l Protectio n Agency , Th e Radiologica l Impac t o f Coal-Fire d Industria l Boiler s (Draft) , Offic e o f Radiatio n Programs , Washington , D.C , Octobe r 1981 , p . 4.2-7 . !

1 6 U.S . Environmenta l Protectio n Agency , Radionuclid e Backgroun d Informatio nDocumen t fo r Fina l Rules , Volum e II , Octobe r 1984 , p . 7.1-1 , 7.1-8 , 7.2-6 , 7.3-4 , 7.4-4 , 6.1-11 . 17 U.S . Departmen t o f Energy , Statistica l Dat a o f th e UraniumIndustry , ] GJ0-100(83) , Gran d Junction , Colorado , Januar y1983 , p . 9 . Schroeder , H.J. , Minera l Commodit yProfile s - - Copper , U.S . Departmen t o f th e Interior , Bureau ' o f Mines , Washington , D.C , 1979 . U.S . Environmenta l Protectio n Agency , > Phosphat e Roc k Plants , Backgroun d Informatio n fo r Propose d Standards , EP A 450/3-79-017 , Offic e o f Ai r Qualit yPlannin g and Standards , 1979 , p . 7-5 . i U.S . Environmenta l Protectio n Agency , Radionuclide s Backgroun d Informatio n; Documen t fo r Fina l Rules , Volum e II , Octobe r 1984 , p . 6.3-1 .P.1 4

1- 9

Appendi xB i nthi s repor t summarize s th e regulate dcommunit yb ysourc e ', category , numbe r o f facilities, majo r radionuclid e o f concern , andexistin g [ regulations . Se e als o Appendi xAo f th e Economi c Impac t Analysi s fo r th e Propose dReportabl e Quantit yAdjustment s fo r Radionuclide s unde r Sectio n102 ; o f CERCL Afo r a nexpande ddiscussio no f th e regulate dcommunity . 1.3. 2 Radionuclid e Releas e History A s par t o f thi s regulator ydevelopmen t process , releas e dat a wer e i collecte dfro mth e majo r federa l agencie s licensing , regulating , and' controllin g radionuclid e releases : th e Nuclea r Regulator yCommission , th e Departmen t o f Transportation , th e Departmen t o f Energy , andEPA . Th e dat a wer e examine dt o understan dth e scop e o f th e radionuclid e releas e problem . [ Th e followin g releas e dat a wer e collected : |
i
• Report s maintaine db yth e Nuclea r Regulator y! Commission' s Offic e fo r Analysi s andEvaluatio no f Operationa l Dat a (AEOD) , 198 1 throug h1985 ;

• Report s maintaine db yth e Transportatio nTechnolog y Cente r (TTC ) o f Sandi a Nationa l Laborator yi n' Albuquerque , Ne wMexico , 1 9 7 1 throug h1985 ; ;

• Dat a provide db yth e Departmen t o f Energy' s Offic e o f | Environmen t andHealth , Emergenc yOperation s Cente r (EOC) , Marc h198 3 throug hApri l 1986 ;

• Report s t o th e Nationa l Respons e Center , 198 2 throug h 1985 ; ;

• Report s t o th e EPA' s Offic e o f Radiatio nProgram s (ORP) , Octobe r 198 1 throug hSeptembe r 1983 ; and

• Report s t o th e Nuclea r Regulator yCommission' s ! Operation s Center , Januar y198 3 throug hJanuar y1986 . ', Th e availabilit yandqualit yo f dat a varie dfromsourc e t o source , bu t duplicatio namon g th e si xsource s appear s t o b e relativel ylimited . Th e AEO D dat a includ e som e 30 0 report s annually , althoug habou t tw o third s o f th e report s ar e incident s involvin g monitorin g complianc e o r som e othe r technica l infractio nwhic hdoe s no t involv e radionuclid e releases . Th e TT C dat a includ e betwee n1 and1 2 report s annuall yo f transportatio nincident s involvin g radionuclid e releases . Thes e event s ar e alreadyrequire dt o b e reporte dt o th e Nationa l Respons e Cente r unde r Departmen t o f Transportatio n regulation s (4 9 CF RPart s 171-177) . Th e Departmen t o f Energ yEO C dat a includ e 5 2 releas e event s ove r a 3-1/ 2 yea r perio d(betwee n1 1 an d2 2 event s annually ) andinclud e release s tha t ar e reportabl e unde r DO E Orde r 5484.1 . Th e Nationa l Respons e Center dat a includ e approximatel y8 0 report s (abou t 3 0 report s annually ) an dth e OR P dat a includ e approximatel y6 0 report s (abou t 3 0 reports .P.1 5

annually) . Th e Nationa l Respons e Cente r dat a includ e littl e detai l o n th e radionuclid e identit yand th e quantit yreleased . Th e OR P dat a reflec t mostl y release s frompowe r reactors . Th e fina l dat a source , th e Nuclea r Regulator y Commissio nOperation s Center , includ e dat a o n 2 6 event s (abou t 8 event s annually) . Althoug hth e 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 th e environment . W e hav e data , therefore , o n approximatel y20 0 releas e event s annually . Thes e dat a sources , however , d o no t cove r release s fromal l facilitie s tha t handl e and tha t are , therefore , likel yt o releas e : radionuclides . Fo r example , release s fromunlicense d facilitie s and release s from facilitie s i nagreemen t state s woul d no t b e expecte d t o b e wel l represente d i nth e dat a sets . I n addition , no t al l type s o f radioactiv e materia l i s wel l represented . On e particula r typ e o f radioactiv e materia l tha t i s no t wel l represente d i n th e dat a set s i s naturall yoccurrin g and accelerator-produce d radioactiv e materia l (NARM) . Whil e th e Nuclea r Regulator yCommissio ndoe s addres s naturall yoccurrin g sourc e materia l i nit s licensin g whe nsuc hmateria l i s use d i n conjunctio n wit hsource , byproduct , , and specia l nuclea r material , ther e ar e n o othe r unifor mregulator yo r i reportin g requirement s fo r NAR M(othe r than , o f course , reportin g o f release s t o th e Nationa l Respons e Center) . Virtuall yal l states , bot hagreemen t and i non-agreement , hav e NARMregulator yprograms ; however , th e dat a collecte d unde r thes e program s hav e no t bee n gathere d becaus e the ywer e to o diffuse . W e are , therefore , unabl e t o analyz e NARMproductio n and release . 1. 4 ORGANIZATIO N O F THI S REPOR T! Thi s repor t discusse s th e variou s option s considere d fo r adjustin g th e one-poun d R Q fo r radionuclide s an d examine s i n detai l th e selecte d option . Th e remainde r o f thi s repor t i s organize d a s follows :

Chapte r 2 : Option s fo r th e Adjustmen t o f Radionuclid e RQ s

- - a revie wo f th e regulator yapproache s considere d and th e on e selected ; ; Chapte r 3 : Identificatio n o f a Lis t o f Radionuclide s - - a discussio no f th e univers e o f radionuclide s t o b e regulate d bythi s rulemaking ; Chapte r 4 : Methodolog yfo r Propose d R Q Developmen t - - th e technica l analysi s and establishmen t o f propose d R Q values ; Appendi xA Appendi xB Appendi xC Appendi xD Existin g reportin g requirements ;

Affecte d facilities ; Othe r method s fo r calculatin g RQs ; Releas e fraction s fo r inhalation ;P.1 6

1-1 1

Appendi xE : Derivatio n o f th e atmospheri c relativ e concentratio nvalu e (X/Q) ; Appendi xF : Groun d wate r transpor t o f radionuclides ; and Appendi xG : Calculatio n o f direc t exposur e releas e values .P.1 7

CHAPTE R2 OPTION S FO RTH E ADJUSTMEN T C F RADIONUCLID E RQ s

Severa l option s fo r adjustin g radionuclid e RQ s wer e carefull yexamine d durin g th e developmen t o f th e propose dregulation . Eac hoptio npresente d certai nadvantage s an d disadvantage s bu t eac ho f th e rejecte doption s wa s determine dt o b e inferio r t o th e selecte dapproach . Thi s chapte r discusse s th e followin g regulator yoption s and explain s th e Agency' s positio nand rational e fo r selectin g Optio n6 , th e approac huse dt o develo p th e propose d RQs : ;

• Optio n1 : Allowin g th e radionuclid e R Q t o remai na t on e pound ; '

• Optio n2 : Considerin g radionuclide s a s a generi c clas s o f substances , withou t a nR Q and no t subjec t t o CERCL Areportin g requirements ; '

• Optio n3 : Establishin g a dose-equivalen t leve l a s th e radionuclid e RQ ; \

• Optio n4 : Considerin g radionuclide s a s a clas s wit h a singl e activit ylevel ; j

• Optio n5 : Groupin g radionuclide s int o categorie s wit ha nactivit yleve l assigne dt o eac ho f th e separat e i categories ; and

• Optio n6 : Establishin g a nactivit yleve l R Q fo r individua l radionuclides . 2. 1 OPTIO N 1 : ALLOWIN G TH E RADIONUCLID E R Q T O REMAI N A TON E POUN D Sectio n102(b ) o f CERCL Aestablishe s th e R Q fo r radionuclide s a t on e pound . Whil e a one-poun dR Q migh t b e usefu l t o ensur e reportin g o f ver ylarg e radionuclid e releases , th e Agenc ydoe s no t believ e tha t thi s R Q leve l i s appropriat e t o trigge r timel yreportin g o r timel yfiel dresponses , i f necessary , fo r release s o f manyradionuclide s becaus e release s o f radionuclide s tha t ar e severa l order s o f magnitud e smalle r tha non e poun dma y represen t a seriou s healt hand environmenta l threat . I naddition , a one-poun d R Q doe s no t confor mt o commonl yaccepte dunit s o f measuremen t fo r radionuclides . Mos t radiatio nmeasurement s i nth e Unite dState s ar e i nterm sP.1 8

o f curie s o r rem, 1 no t pounds . Aone-poun d R Q leve l would , therefore , diffe r markedl yfromreportin g requirement s unde r othe r radionuclid e regulation s develope d b yEP Aand othe r agencies . | Aone-poun d R Q fo r th e entir e clas s o f radionuclide s woul d als o no t tak e | int o accoun t th e variet yo f hazard s pose d b ydifferen t radionuclides . Becaus e eac hradionuclid e ha s a uniqu e specifi c activit y(i.e. , a certai n numbe r o f curie s fo r on e pound) , a singl e one-poun d R Q woul d relat e t o differen t number s o f curie s - - and differen t radiatio n emissio n level s - - fo r eac h radionuclide . Th e Agency , therefore , conclude d tha t a one-poun d R Q wa s no t sufficientl yprotectiv e o f publi c healt han d welfar e and th e environment . 2. 2 OPTIO N

2 : CONSIDERIN GRADIONUCLIDE S A S A GENERI C CLAS S O F SUBSTANCES , WITHOU T A N R Q AN DNO T SUBJEC T T OCERCL A REPORTIN G REQUIREMENTS . I nth e Apri l 4 , 198 5 fina l rul e establishin g notificatio n requirement s and adjustin g RQ s fo r certai nhazardou s substance s (5 0 F R13456) , EP Adecide d not 1 t o establis hRQ s fo r broa d generi c classe s o f organi c and metalli c compound s eve nthoug hthe yar e designate d a s toxi c pollutant s unde r Sectio n 307(a ) o f th e Clea nWate r Ac t and thu s include d i n CERCLA' s hazardou s substanc e list . Th e reasonin g fo r thi s decision , a s state d i n th e preambl e t o tha t rule , was :

Manyo f th e generi c classe s o f compound s encompas s hundred s , o r eve nthousand s o f specifi c compounds . I t woul d b e virtuall yimpossibl e fo r th e Agenc yt o develo p a reportabl e quantit ytha t woul d tak e int o accoun t th e varyin g characteristic s o f al l th e specifi c compound s i n th e clas s (5 0 F R13461) . ; Becaus e ther e ar e ove r 180 0 know n radionuclides , th e Agenc yconsidere d usin g a simila r approac hfo r radionuclides , tha t is , no t establishin g a n R Q fo r radionuclide s and no t requirin g radionuclid e release s t o b e reporte d t o th e Nationa l Respons e Center . I n considerin g thi s approach , however , th e Agenc y determine d tha t th e sam e technica l argumen t coul d no t b e use d t o suppor t a decisio nno t t o establis ha n R Q fo r radionuclides . Althoug hth e ter m; radionuclide s encompasse s hundred s o f radioactiv e isotope s and countles s \ chemica l compound s involvin g thes e isotopes , i t i ^ possibl e t o se t a singl e R Q i nterm s o f dose-equivalen t (rem ) fo r th e generi c clas s o f radionuclide s ' an d stil l tak e int o accoun t som e o f th e uniqu e characteristic s o f individua l : radionuclides . I t i s als o possibl e t o se t a n R Q i n term s o f activit ylevel s ; (curies ) fo r group s o f radionuclide s base d o n a predetermine d acceptabl e exposur e level . Th e argumen t use d fo r th e generi c classe s o f organi c and : metalli c compound s was , therefore , no t applicabl e t o radionuclides .

1 Radiatio n measurement s ca n als o b e expresse d i n internationa l unit s o f becquerel s o r sieverts , however , thes e term s ar e les s commo n i n th e Unite d States .P.1 9

2- 3

Th e Agenc yals o considere d establishin g n o R Q fo r radionuclide s base d on ' th e findin g tha t existin g reportin g mechanism s fo r radionuclid e release s wer e adequat e and tha t an yadditiona l reportin g pursuan t t o CERCL Awoul d provid e h o additiona l benefit . Unde r thi s approach , eve n withou t a n R Q and therefor e withou t a requiremen t t o repor t release s o f radionuclide s unde r CERCLA , i radionuclide s woul d remai nliste d a s a hazardou s substanc e and woul d b e subjec t t o CERCL Arespons e and liabilit yprovisions . Eliminatio n o f anR Q fo r radionuclide s woul d rel yo nexistin g reportin g requirement s o f othe r agencies. 2 Thi s approac hwoul d minimiz e duplicatio n o f and conflict s wit h othe r federa l and stat e reportin g requirements . Th e Agenc ydetermined , however , tha t thi s optio n woul d no t b e sufficientl y protectiv e o f publi c healt hand welfar e an d th e environment . Les s tha non e thir d o f facilitie s tha t handl e o r produc e radionuclide s ar e license d b yth e ' Nuclea r Regulator yCommission , a n agreemen t state , o r th e Departmen t o f ' Energy . NAR Mar e onl ylicense d byth e Nuclea r Regulator yCommissio n i f the y, ar e use d bya license e i nconjunctio n wit hsource , byproduct , o r specia l ' nuclea r material . Facilitie s usin g onl yNARM , therefore , ar e no t subjec t t o federa l contro l and licensing . Release s fromthes e facilitie s coul d g o | unreporte d i f n o R Q wer e t o b e established . Th e Agenc yconcluded , therefore, 1 tha t i t woul d no t b e fulfillin g it s mandat e unde r CERCL Ai f n o R Q wa s establishe d fo r radionuclides . i

i 2. 3 OPTIO N 3 : ESTABLISHIN G ADOSE-EQUIVALEN TLEVE LA S TH E RADIONUCLID E R Q Adose-equivalen t leve l i s a direc t measuremen t o f th e amoun t o f biologica l damag e resultin g fromexposur e t o ionizin g radiation . Dose
equivalen t i s generall ymeasure d i n term s o f re mo r sievert s and i s equa l t o ' th e produc t o f th e absorbe d dose , i n unit s o f rad s o r grays , and a qualit y facto r (Q ) assigne d t o th e typ e o f radiatio n bein g emitted. 3

2 Se e Appendi xB o f thi s repor t fo r furthe r detai l o n existin g reportin g requirements . 3 Th e gra yi s a uni t o f absorbe d dose . On e gra yi s equa l t o a n absorbe d dos e o f 1 joule/kilogra mo r 10 0 rads . Th e ra d i s a uni t o f absorbe d dose . On e ra d i s equa l t o a nabsorbe d dos e o f 10 0 ergs/gra mo r 0.0 1 joule/kilogram. ; Th e siever t i s a uni t o f dose-equivalent . On e siever t i s equa l t o a dose

equivalen t o f 1 joule/kilogra mo r 10 0 rem . Originall y"Roentge n Equivalen t Man, " th e re mi s a uni t o f dose-equivalent . Th e dose-equivalen t i n remi s numericall yequa l t o th e absorbe d dos e i n rad s multiplie d byth e qualit y facto r (Q) . Q i s equa l t o 1 fo r X-rays , gamm a rays , and bet a particles ; Q is ; equa l t o 1 0 fo r fas t neutron s fromfission , fo r example , and fo r protons ; and Q i s equa l t o 2 0 fo r alph a particle s and fissio n fragments .2- 4 P.2 0

Dose-equivalent , unlik e activity , i s no t a measur e o f th e emitte d radiation , bu t i s a metho d o f normalizin g th e effectivenes s o f a n absorbe d ; dos e o f radiatio ni ndamagin g tissue , regardles s o f th e typ e o f radiation . I t mus t als o b e understoo d tha t activit yi s a physica l phenomenon , wherea s dose- ; equivalen t i s a descriptio no f th e biologica l effectivenes s o f a give n exposur e circumstance . Nevertheless , usin g standar d assumption s regardin g suc hfactor s a s rout e an d duratio n o f exposure , quantit yo f intake , and determinatio no f th e tissue s mos t affected , a dose-equivalen t leve l ma yb e relate d directl yt o a leve l o f activit yfo r particula r radionuclides . Th e Agenc yconsidere d establishin g a n R Q fo r radionuclide s i n term s o f dose-equivalen t (rem ) becaus e remi s a n acceptabl e uni t o f measuremen t fo r radionuclid e release s and , i n fact , mos t existin g reportin g requirement s ar e i nunit s o f rem . I naddition , 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 , a n R Q i n term s o f a rem leve 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 anyreleas e which , unde r existin g circumstance s (whateve r the yma ybe) , coul d resul t i n th e specifie d numbe r o f rem . Ther e ar e severa l importan t disadvantage s t o thi s option , however . First , dose-equivalen t limit s typicall yspecif yacceptabl e exposure s fo r certai n situations , suc ha s a perio d o f exposur e and a particula r targe t organ . A radionuclid e R Q i nunit s o f dose-equivalent , therefore , woul d hav e t o specif y th e sensitiv e organ s o f concern . Thi s woul d represen t a complicate d reportin g trigger . Second , th e Agenc ydetermine d tha t a n R Q i n term s o f dose-equivalen t (rem ) woul d leav e a significan t amoun t o f judgmen t t o th e perso n i n charg e o f th e facilit yo 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 , th e potentia l route s o f exposure , th e perio d o f exposure , an d th e mos t vulnerabl e orga n o f th e bodypotentiall yaffecte d by th e release . I nessence , i f th e R Q wer e t o b e establishe d i n unit s o f rem , th e perso ni ncharg e o f th e vesse l o r facilit ywoul d b e place d i n a positio n o f determinin g whethe r th e releas e pose d a threa t t o publi c healt ho r welfare ; o r th e environment . CERCL Aestablishe s tha t rol e fo r th e federa l government , no t fo r th e perso ni ncharg e o f th e vesse l o r facility . i I naddition , th e calculatio n (o r 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 th e | judgment s an d assumption s require d t o estimat e dose-equivalent , th e estimated ) dose-equivalen t fo r tw o differen t release s wit hth e sam e leve l o f activit yo f th e sam e radionuclid e ma yvar ydrasticall yunde r differen t assumptions . Thi s potentia l variability , eve nwit ha standardize d calculatio n methodology , make s i t difficul t t o (1 ) assur e tha t th e governmen t wil l b e notifie d o f al l radionuclid e release s tha t i t deem s necessary ; and (2 ) enforc e a n R Q i n dose

equivalen t units .P.2 1

2- 5

2. 4 OPTIO N 4 : CONSIDERIN G RADIONUCLIDE S A S ACLAS S WIT H ASINGL E ACTIVIT YLEVE L Becaus e activit ylevel s ar e eas yt o measur e quickl ydurin g a releas e even t throug hth e us e o f availabl e surve yinstruments , th e Agenc yconsidere di establishin g anR Q fo r radionuclides , a s a generi c class , i nunit s o f curies; . Aleve l o f activity , i nunit s o f curie s (o r becquerels) , i s a measur e o f the ; rat e o f radioactiv e deca yand thu s th e amoun t o f radiatio ngive nof f b ya substance . However , a nR Q i nunit s o f curie s applicabl e t o al l radionuclide s doe s no t accoun t fo r varyin g degree s o f hazar dpose db ydifferen t radionuclides . Exhibi t 2- 1 show s th e rang e o f differen t dose-equivalen t level s (reflectin g relativ e level s o f damag e t o th e body ) whic hma yresul t fromth e inhalatio no f on e microcuri e o f differen t radionuclides . Whil e simplicit yi nreportin g mus t b e sought , th e Agenc ydoe s no t believ e tha t i t shoul db e accomplishe db yignorin g substantia l difference s amon g \ individua l radionuclides . I t woul db e extremel ydifficul t t o deriv e a nR Q i n term s o f a singl e leve l o f activit ytha t woul dprovid e timel yreportin g o f th e mos t hazardou s radionuclide s whil e no t bein g overl yprotectiv e fo r others . 2. 5 OPTIO N 5 : GROUPIN G RADIONUCLIDE S INT O CATEGORIE S WIT H A N : ACTIVIT YLEVE LASSIGNE D T O EAC H O F TH E SEPARAT E CATEGORIE S Radionuclide s ma yb e segregate dint o variou s group s i nsuc ha wa ytha t a 1 singl e leve l o f activit yma yb e a nappropriat e R Q fo r al l th e radionuclide s \ withi na give ngroup . On e RQ , whic hwoul dassur e timel yreportin g fo r < release s o f th e mos t hazardou s radionuclides , coul db e assigne dt o eac h group . Fo r example , th e Agenc yconsidere dgroupin g radionuclide s int o ; "half-lif e categories " wit hprogressivel yhighe r RQ s fo r thos e categorie s havin g shorte r hal f lives . Anothe r optio nconsidere dwa s t o separat e radionuclide s int o group s o f alpha , beta , an d gamm a emitter s wit h progressivel yhighe r RQ s fo r eac ho f thes e categories . Th e RQ s fo r non-radioactiv e substance s hav e bee nestablishe di nthi s fashion , wit h differen t RQ s fo r differen t group s o f chemical s havin g simila r chemica l and toxicologica l properties . Th e Agenc ychos e no t t o adop t th e tw o method s o f categorizin g radionuclide s mentione dabove . Th e Agenc ybelieve 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 havin g shorte r hal f live s ma yno t b e protectiv e 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. , te n days ) coul demi t hig henerg yradiatio na t a hig hrat e fo r whic hth e federa l ' governmen t ma ywis ht o receiv e notificatio nt o determin e whethe r a respons e : actio ni s necessary . Wit hregar dt o categorizin g radionuclide s o nth e basi s o f whethe r the yar e primaril yalpha , beta , o r gamm a emitters , th e actua l ; threa t t o publi c healt hand welfar e and th e environmen t i s ofte nles s dependen t o nth e typ e o f emissio ntha no nth e energ yo f th e radiatio n(i.e. , a hig henerg ybet a particl e migh t b e mor e harmfu l tha na lo wenerg yalph a ! particle) . [

\

# 1 1 1 I I I I I 1 I I I I I I 1 1 1 2- 6

EXHIBI T2- 1 DOSE-EQUIVALENT S RESULTIN G FRO M TH E INHALATIO N O F ON E MICROCURI E O F DIFFEREN TRADIONUCLIDE S

Radionuclid e Dose-Equivalen t t o adul t lung s i f on e microcuri e i s inhale d (rem ) a /

Tritium( H ) Technetium-9 9 Uranium-23 8 Radium-22 6 Plutonium-23 8 .000 1 .0 5 4 9 5 6 6 4 P.2 2

a / Th e numbe r o f remt o th e lung s resultin g fromth e intak e o f a radionuclid e depend s on , amon g othe r factors , th e particl e siz e and solubilit y o f th e radionuclid e involved . T o facilitat e compariso n o f th e hazar d level s ' associate d wit heac ho f th e abov e radionuclides , th e dose-equivalen t level s ar e base d o neac hradionuclid e (excep t fo r tritium ) havin g th e sam e solubilit y ( a "W " compound ) and particl e siz e (a n activit ymedia n aerodynami c diamete r o f 1 ym) . : 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 Occurrin g i n Routin e Release s Fro mNuclea r Fuel-Cycl e Facilities , Vol . Ill , NUREG-0150 , 1981 .

\P.2 3

2- 7

Th e Agenc ydi 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 examinin g eac h individua l radionuclid e and estimatin g th e effec t o f a releas e o f each . 2. 6 OPTIO N 6 : ESTABLISHIN G A N ACTIVIT YLEVE LR Q FO R INDIVIDUA L RADIONUCLIDE S Th e Agenc yultimatel ydecide d t o propos e R Q adjustment s fo r individua l radionuclide s base d o nlevel s o f activity . Ther e ar e severa l advantage s t o [ basin g radionuclid e RQ s o nactivit ylevels . Fo r example , a leve l o f radioactivit yi s muc heasie r t o estimat e tha n a dose-equivalent . Surve y instrument s ar e readil yavailabl e and widel yuse d t o measur e directl yth e [ ionizin g radiation . Th e Agenc ybelieve s tha t settin g RQ s i n term s o f activit y would , therefore , provid e mor e timel yreportin g tha n a n R Q expresse d i n term s o f dose-equivalent . ! Asecon d advantag e o f usin g activit ylevel s i s tha t establishin g RQ s for ' radionuclide s individuall ywoul d allo wconsideratio n o f individua l radionuclid e characteristic s includin g th e typ e an d strengt ho f ionizin g > radiatio nproduce d durin g a release . An R Q i n term s o f dose-equivalen t (rem ) woul d als o (b

ydefinition ) hav e considere d typ e and strengt ho f ionizin g ; radiation , bu t woul d hav e lef t muc hgreate r judgmen t t o th e perso n i n charge : o f th e vesse l o r facility . Activity-leve l RQ s (curies ) als o conside r eac h; radionuclid e individually , bu t minimiz e judgment s byth e perso n i n charg e of , th e vesse l o r facility . Th e optio n t o establis hRQ s i n term s o f curies , therefore , wa s considere d advantageous . ! Th e Agenc yrecognize s tha t th e 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 byitsel f doe s no t necessaril yreflec t a leve l o f dange r t o huma n health . A s i s presentl yth e cas e fo r RQ s fo r non-radioactiv e substances , a case-by-case ; evaluatio nbyth e On-Scen e Coordinato r wil l b e necessar yt o estimat e th e huma n healt hand welfar e an d environmenta l hazard s associate d wit ha radionuclid e release , and t o determin e i f a federa l respons e i s warranted . EP Abega nit s developmen t o f th e individua l RQ s byfirs t identifyin g the [ univers e o f radionuclide s t o b e analyze d individuall yand th e univers e o f radionuclide s t o b e covere d byth e propose d regulation . Chapte r 3 o f thi s repor t discusse s ho wth e Agenc yidentifie d thes e universes .P.2 4

prepare dinfrequentl yo r a fe watom s a t a tim e t o determin e propertie s o r confir mth e predicte dmod e o f decay . Othe r radionuclide s include di nth e 75; 7 hav e extremel yshor t hal f lives , lik e chlorine-3 4 (hal f lif e o f 1. 6 seconds)! , tha t full yself-decontaminat e withi n2 4 hours . Therefore , th e Agenc y considere dreducin g th e numbe r o f radionuclide s wit hpropose dRQs . Th e Agenc yconsidere dtw o genera l categorie s o f radionuclide s fo r eliminatio nfromCERCL Anotificatio nrequirements : radionuclide s tha t ar e s o rar e tha t i t i s extremel yunlikel ythe ywoul db e release di nquantitie s o f a n R Q o r more , and radionuclide s tha t ar e ver yshor t lived . Eac ho f thes e categorie s i s discusse dbelow . 3. 1 RAR E RADIONUCLIDE S Th e Agenc yconsidere dth e followin g type s o f radionuclide s t o b e s o rare ! tha t th e likelihoo do f a releas e o f on e o f thes e radionuclides , a t level s of i a nR Q o r mor e i s extremel ylow . '

• Radionuclide s tha t ar e naturall yoccurring , bu t foun d' i nextremel ylo wabundance ;

• Radionuclide s tha t ar e produce dthroug hfissio no r activation , bu t wit hlo wprobabilit yproductio nschemes ; | and I
• Radionuclide s tha t ar e expecte dt o occu r onl yi n limite dquantitie s a s a resul t o f experimenta l studies . ! i Abrie f explanatio no f th e type s o f radionuclide s th e Agenc yexpecte dto | fal l withi neac ho f thes e group s follow s below . , Som e radionuclide s ar e naturall yoccurrin g an d ar e no t normall yproduce d throug hanyartificia l process . Becaus e th e natura l elemen t contain s a n[ extremel ysmal l percen t o f th e radionuclide , isotopi c separatio nfo r thes e radionuclide s woul db e expensiv e an d difficul t and , therefore , unexpected . ! Further , the yappea r i nnatur e i nsuc hlo wabundanc e tha t a releas e o f on e o f thes e radionuclide s a t level s o f a nR Q o r mor e i s extremel yunlikely . Man yradionuclide s ar e produce di nnuclea r reactor s throug hfission , althoug hsom e radionuclide s hav e a ver ylo wprobabilit yo f bein g produced . Fissio ninvolve s th e splittin g o f a nato m(usuall yuraniumo r plutonium ) int o tw o parts , wit ha concommitan t releas e o f energy . Eac ho f thes e tw o part s i s a nisotop e o f a specifi c elemen t wit ha well-define dnumbe r o f proton s and neutron s i nit s nucleus . Abou t 9 7 percen t o f th e isotope s forme dthroug hth e fissio nproces s fal l int o tw o groups : (1 ) a "light " grou p whos e mas s numbers. , th e sumo f neutron s and proton s i nth e nucleus , li e betwee n8 5 and 104 , andP.2 5

i- 3

(2 ) a "heavy " grou p whos e mas s number s li e betwee n13 0 and 149. 3 Radionuclide s produce dthroug hth e fissio nproces s tha t ar e no t i nth e ligh t o r heavygroup migh t b e considere dt o b e sufficientl yrar e tha t a releas e a t ; level s o f a nR Q o r mor e i s extremel yunlikely . ! Similarly , manyradionuclide s ar e produce donl yi nnuclea r reactor s by processe s knowna s neutro no r charged-particl e activation . Th e proces s ' involve s th e absorptio no f on e o r mor e particle s b yth e targe t nucleus , ; producin g eithe r a nisotop e o f th e origina l elemen t o r a ne welement . Afte r th e firs t absorption , th e probabilit ytha t additiona l neutron s wil l b e absorbe dand ne wisotope s forme ddecreases . Charge dparticl e reaction s occur , onl yrarel yi nnuclea r reactors . Othe r rar e radionuclide s ar e expecte dt o occu r onl yi nsmal l quantitie s i n specia l laborator ystudies . Thes e ar e mostl ytransuranics , member s o f th e neptuniumchain , o r isotope s o f member s o f th e uranium , thorium, and actinium i chains . Manyo f thes e element s ar e produce donl ya fe watom s a t a tim e fo r purpose s o f investigatin g thei r deca ypathway s o r fo r othe r laborator yo r researc hpurposes . Th e Agenc ydecide dt o propos e RQ s fo r thes e rar e radionuclide s becaus e rarit yi s no t a relevan t consideratio ni nR Q adjustments . Jus t becaus e a releas e o f a particula r radionuclid e i s expecte dt o b e rare , i t doe s no t mea n th e isotop e shoul dhav e n o propose dRQ . I f a releas e doe s occu r a t level s equallin g o r exceedin g a nRQ , th e Nationa l Respons e Cente r shoul db e notified ^ s o tha t i t ca nasses s th e necessit yfo r a federa l response . Establishin g RQ s fo r rar e radionuclide s will no t b e a burde nt o th e regulate dcommunit yo r t o th e governmen t becaus e release s a t level s o f a nR Q o r mor e ar e expecte dt o occu r ver yinfrequently . Therefore , th e reportin g burde nt o th e regulate d communit yand th e repor t processing/respons e burde nt o th e federa l governmen t shoul db e minimal . ' 3. 2 SHORT-LIVE D RADIONUCLIDE S O f th e 75 7 radionuclide s fo r whic hALI s hav e bee ndeveloped , 22 4 hav e hal f live s o f les s tha no r equa l t o 0. 1 day . Thes e isotope s virtuall ydeca y full ywithi na twenty-fou r hou r period . Becaus e thes e short

- live d radionuclide s virtuall yself-decontaminat e withi n2 4 hours , th e Agenc y] considere destablishin g n o propose dR Q fo r thes e radionuclide s becaus e a federa l cleanup respons e woul dno t b e necessar yan d th e potentia l hazar di s s d short-live dtha t fo r th e mos t part , a timel yfedera l respons e woul db e unlikely . However , th e Agenc ydecide dt o establis hpropose dRQ s fo r thes e ver y short-live dradionuclide s becaus e 2 4 hour s i s a relativel ylong perio do f tim e from a federa l respons e perspective . Short-live dradionuclide s giv e of f

3 Kaplan , I. , Nuclea r Physics , Addison-Wesle yPublishin g Company , Reading , Massachusetts , 1958 , p.496 .P.2 6

high-energ yradiation , albei t fo r a shor t perio d o f time . Withou t th e requiremen t t o repor t suc hreleases , respons e activitie s suc ha s evacuation s ma yb e foreclosed . T o b e mos t protective , therefore , th e Agenc yi s proposin g RQ s fo r al l radionuclides , includin g rar e and short-live d radionuclides . Chapte r 4 o f thi s repor t describe s th e methodolog yuse d t o calculat e th e propose d RQ s fo r th e 75 7 individuall yanalyze d radionuclides .CHAPTE R 4 METHODOLOG YFO R PROPOSE D R Q ADJUSTMENT S P.2 7

EP Ai s proposin g t o adjus t th e statutor yone-poun d R Q fo r al l radionuclide s an d ha s analyze d individuall yth e 75 7 radionuclide s liste d i n ICRP' s Publicatio n30 . l Thi s chapte r discusse s severa l method s considere d '< b yth e Agenc yfo r calculatin g th e propose d RQs . Sectio n 4. 1 describe s ' alternativ e method s considere d fo r relatin g radiatio n damag e t o release s o f radionuclide s i nunit s o f curies ; Sectio n 4. 2 describe s th e selecte d R Q adjustmen t methodology , whic hconsider s exposur e t o radionuclid e release s throug hinhalation , ingestion , and direc t exposur e pathways ; Sectio n 4. 3 ' describe s th e assignmen t o f radionuclide s t o propose d R Q groups ; and Sectio n 4. 4 discusse s propose d reportin g requirement s fo r mixture s o f radionuclides . , 4. 1 METHOD S CONSIDERE D FO R RELATIN G RADIATIO N DAMAG E T O RELEASE S I N UNIT S O F CURIE S Th e Agenc yconsidere d thre e method s fo r relatin g radiatio n damag e t o ; release s o f radionuclide s i n unit s o f curies : MaximumPermissibl e Concentration s (MPCs) , Limitin g Possessio n Limit s (LPLs) , and Annua l Limit s o f Intak e (ALIs) . MaximumPermissibl e Concentration s wer e originall ydevelope d i n 195 9 b y th e Internationa l Commissio no n Radiatio n Protectio n (ICRP ) and ar e currently . use d byth e Nuclea r Regulator yCommissio n i n1 0 CF RPar t 2 0 t o limi t exposure s fo r nuclea r facilit yworker s and member s o f th e genera l public . Tw o set s o f MPC s ar e used , on e fo r restricte d area s and th e othe r fo r unrestricte d areas . Th e restricte d are a MPC s represen t th e maximumpermissibl e concentration s o f a radionuclid e i nai r and wate r t o whic ha worke r i s allowe d t o b e exposed . Th e unrestricte d are a MPC s represen t th e maximumconcentration s o f radionuclide s tha t ar e acceptabl e fo r releas e int o unrestricte d areas . Ametho d fo r calculatin g RQ s base d o nMPC s i s show n i n Appendi xC o f thi s report . Anothe r mechanis muse d byth e Nuclea r Regulator yCommissio n fo r assurin g saf e operation s a t som e o f it s license d facilitie s i s th e LPL . Thi s valu e represent s th e maximum quantit yo f a give n radionuclid e tha t a license e ma y posses s withou t bein g require d byth e Commissio n t o hav e a Radiologica l Contingenc yPla n- - a formalize d pla n fo r respondin g t o release s an d emergencie s involvin g radioactiv e material . Ametho d fo r developin g RQ s usin g thes e LPL s ca nals o b e found i n Appendi xC .

1 Internationa l Commissio n o n Radiatio n Protection , Annal s o f th e ICRP : Limit s fo r Intake s o f Radionuclide s b yWorkers , ICR P Publicatio n 30 , Par t 2 , 1980 .P.2 8

4- 2

ICR P ha s develope d a thir d measur e designe d t o protec t nuclea r facilit y worker s fromradionuclid e exposur e hazards : ALIs . Th e ALI s ar e th e annua l intake s o f give nradionuclide s b y"Referenc e Man" 2 whic hwoul d resul t i n eithe r (1 ) a committe d effectiv e dose-equivalent 3 o f 5 re mt o th e whol e body (stochasti c ALI) , o r (2 ) a committe d dose-equivalent 1 * o f 5 0 remt o anyorga n o r tissu e (non-stochasti c ALI) . I n th e propose d revisio n o f 1 0 CF RPar t 20 , th e Nuclea r Regulator yCommissio n propose s th e adoptio n o f ALI s instea d o f MPC s because : "th e revisio n improve s radiatio n protectio n standard s b y reflectin g development s i nth e principle s tha t underli e radiatio n protectio n and advance s i nrelate d science s tha t hav e occurre d sinc e th e promulgatio no 1 0 CF RPar t 2 0 nearl ythirt yyear s ago " (5 0 F R1092 , Januar y9 , 1986) . I n short , th e propose d ALI s ar e healt hrisk-base d standards ; the yar e designe d t o limi t a n"effective " whol e bodydos e and , thus , th e estimate d ris k o f healt h damage . Us e o f thi s effectiv e whol e bodyris k concep t i s a majo r departur e fromth e MPC s i nth e presen t Par t 2 0 whic har e base d o n th e concep t o f protectin g a single , "critical " orga n (5 0 F R1093 , Januar y9 , 1986) . EP Aha s decide d t o us e th e ALI s develope d b yth e ICR P fo r th e calculatio n o f th e propose d RQ s becaus e th e ALI s represen t th e mos t recen t scientifi c advance s and becaus e thes e ALI s hav e bee n calculate d fo r bot hora l ingestio n and inhalation . Propose d RQs , therefore , ca n b e derive d base d o n transpor t throug hdifferen t environmenta l media . Th e Agenc ydevelope d Releas e Value s fo r specifi c radionuclide s base d o n thre e differen t route s o f exposure : inhalation , ingestion , and direc t exposure . Th e mos t sensitiv e rout e o f exposur e varie s wit heac hradionuclid e dependin g upo nth e effec t th e radionuclid e ha s o n sensitiv e organs , a s wel l a s th e differen t chemica l and physica l form s (e.g. , solubility ) o f a ! radionuclide . Fo r eac hradionuclid e t o whic ha n individua l R Q ha s bee n assigned , th e Agenc ybase d it s propose d R Q o n th e mos t sensitiv e exposur e ! rout e fo r tha t particula r radionuclide . Th e followin g sectio n o f thi s repor t discusse s th e methodolog yuse d b yth e Agenc yt o calculat e th e radionuclid e Releas e Value s base d o nexposur e throug hinhalation , ingestion , an d direc t ! exposure . 4. 2 METHO D FO R DETERMININ G RQ s BASE D O N INHALATION , INGESTION, ! AN D DIREC TEXPOSUR E Radionuclide s ar e considere d dangerou s becaus e o f th e potentia l fo r deliverin g ionizin g radiatio n t o organisms . Thi s ionizin g radiatio n

2 Referenc e ma ni s a hypothetica l individua l possessin g "average " characteristic s o f human s (suc ha s bodyweight , dietar yintake , and inhalatio n rate ) t o serv e a s a commo nbiologica l basi s fo r calculatin g MP C an d AL I values . 3 Th e tota l whol e bodydose-equivalen t resultin g fromintake s o f radionuclide s i non e year . ""Th e tota l dose-equivalen t average d throughou t a tissu e i n th e 5 0 year s afte r intak e o f a radionuclid e int o th e body .EXHIBI T4- 1 SCHEMATI C O F ASSUMPTION S USE D I N INHALATIO N SCENARI O

Win d Spoo d (u) : 1 m/ao c

Qroun d lovo l \

30 mP.3 0

H - /

a s exemplifie d b

yth e Chernoby l inciden t i n Russia . I n th e cas e o f drinking ' water , radionuclide s ma yb e ingeste d fromcontaminate d surfac e waters , suc ha s river s and lakes , o r fromcontaminate d groun d wate r (i.e. , a contaminate d well) . Becaus e ingestio no f radionuclide s vi a foo d crops , surfac e water , and groun d wate r ar e considere d equall ylikel ysource s o f exposure , th e Agenc y examine d model s fo r eac ho f thes e ingestio n pathway s t o determin e whic his , i n general , th e mos t critica l exposur e pathway . Base d o n thi s review , th e Agenc y ha s chose nt o mode l th e ingestio n pathwa ybase d o n th e consumptio n o f contaminate d groun d wate r froma drinkin g wate r well . Th e model s fo r th e foo d cro p and surface-wate r ingestio n pathways , and th e Agency' s rational e fo r excludin g the ma s a basi s fo r determinin g Releas e Values , ar e describe d briefl yi nth e followin g paragraph s and i n greate r detai l i n Appendi xF . I ngeneral , ther e ar e thre e type s o f foo d whic hca n resul t i n huma n ingestio no f radionuclides : vegetables , milk , and meat . O f thes e three , j contaminate d vegetable s (i.e. , foo d crops ) ar e expecte d t o b e th e mos t dangerou s t o human s becaus e radionuclide s deposite d o n vegetable s ar e ingeste' d directly . Fo r mil k an d meat , human s ar e expecte d t o consum e smalle r quantitie s o f radioactiv e materia l becaus e onl ya fractio n o f th e i radionuclide s ingeste d b ycow s ar e transferre d t o mil k and meat . Th e Agenc y believes , therefore , tha t considerin g onl yth e consumptio n o f contaminate d foo d crop s provide s a goo d approximatio n o f th e tota l radioactivit yingeste d , b yhuman s throug hfoo d intake . T o determin e th e concentratio n i n and o n foo d crop s resultin g fromth e depositio no f radionuclide s afte r a n airborn e release , th e Agenc yconsidere d model s develope d byth e Nuclea r Regulator yCommission 1 1 and th e Nationa l Counci l o nRadiatio nProtectio n and Measurement s (NCRP). 1 2 Bot hmodel s wer e . simila r and eac haccounte d fo r radionuclid e depositio n fromth e air , \ weatherin g and radioactiv e decay , radionuclid e buildu p i n th e soil , and uptak e fromth e soil . Afte r comparin g th e tw o models , th e Agenc yconclude d tha t the 1 NCR P mode l wa s to o conservativ e i n it s treatmen t o f radionuclid e deposition ; therefore , th e Agenc yderive d invgestio n Releas e Value s usin g th e Commissio n'• model . Th e Agenc ythe ncompare d thes e ingestio n Releas e Value s (derive d fo r th e ingestio no f contaminate d foo d crops ) t o Releas e Value s derive d fo r ingestio no f contaminate d groun d water , and found tha t ingestio n o f contaminate d groun d wate r wa s th e mor e critica l exposur e pathwa yfo r a larg e majorit yo f radionuclides . I n addition , th e Agenc yfound tha t i n th e vas t majorit yo f case s wher e th e ingestio n o f contaminate d foo d crop s wa s th e more ; critica l o f th e ingestio npathways , eithe r th e inhalatio n o r direc t exposur e

X1 U.S . Nuclea r Regulator yCommission , "Calculatio n o f Annua l Dose s t o Ma nfromRoutin 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 , 1977 . 12 Nationa l Counci l o nRadiatio n Protectio n an d Measurements , "Screenin g fo r Determinin g Complianc e wit hEnvironmenta l Standards : Release s o f Radionuclide s t o th e Atmosphere, " NCR P Commentar yNo . 3 , 1986 .P.3 1

scenario s wer e eve nmor e critica l resultin g i n eve n lowe r Releas e Values . Therefore , th e Agenc ychos e t o bas e th e ingestio n scenari o o n th e intak e o f contaminate d drinkin g water . A s state d above , drinkin g wate r i s obtaine d fromeithe r surfac e water s (i.e. , river s and lakes ) o r fromgroun d wate r (i.e. , undergroun d wells) . To ; compar e directl yth e ingestio n pathway s o f surfac e water s an d groun d waters , : th e Agenc yexamine d th e surface-wate r transpor t mode l use d i n th e RCRARis k Cos t Analysi s Model 1 3 (se e Appendi xF) . I n comparison , contaminan t transpor t i nriver s happen s o n a muc hfaste r scal e du e t o th e greate r velocitie s o f river s compare d t o aquifers . Th e highe r velocit yo f a rive r ; wil l reduc e th e contac t tim e betwee n th e contaminate d plum e and th e sourc e o f drinkin g wate r t o suc ha smal l perio d tha t fo r onl yver ylarg e release s coul d a significan t amoun t o f th e releas e b e pumpe d fromth e rive r and consume d i n drinkin g water. I naddition , th e large r flo wvolum e o f mos t river s compare d ' t o aquifer s wil l resul t i na muc hgreate r dilutio n o f th e release . Asimilar ^ situatio nexist s fo r lakes . Th e plum e volum e calculate d fo r th e ground-wate r mode l use d i nth e analysi s o f Releas e Value s i s abou t 13,30 0 cubi c meter s whic hcorrespond s t o a pon d abou t 5 0 meter s long , 5 0 meter s wide , and 5 meter s deep . Typically , lake s use d fo r drinkin g wate r supplie s ar e ver ymuc hlarge r and woul d resul t i na muc hlarge r dilutio n o f release d radionuclides . Therefore , th e ingestio no f radionuclide s base d o n consumptio n o f contaminate d groun d wate r will , base d o nth e scenario s examine d (se e Appendi xF) , b e a mor e critica l exposur e pathwa ytha n a n ingestio n scenari o base d o n th e consumption ! o f contaminate d surfac e water . Hence , t o b e mos t protective , th e Agenc yha s chose nt o mode l th e ingestio n o f radionuclide s base d o n th e consumptio no f contaminate d wel l water . Th e ingestio nReleas e Valu e i s directl yproportiona l t o th e ingestio nAL I and inversel yproportiona l t o th e dilutio n factor , contac t time , and wate r consumptio no f "Referenc e Man. " Th e metho d whic hth e Agenc yha s adopte d fo r : th e calculatio no f Releas e Value s base d o n consumptio n o f contaminate d ground ! wate r i s summarize d i nequatio n (3 ) below : (3 ) Ingestio nReleas e Valu e = ALI/((10)*(DF)*(CT)*(WC)*( 1 xIO 6 ) ) ; where : AL I = Annua l Limit s o f Intak e fo r ingestio n (microcuries) ;

D F = Dilutio nFacto r (liter " ) ; C T = Contac t Tim e (days) ; W C = Wate r Consumptio n o f "Referenc e Man " ( 2 liters/day) ; and 1x1 0 = conversio nfacto r betwee n microcurie s an d curies .

1 3 U.S . Environmenta l Protectio n Agency , Offic e o f Soli d Waste , "Th e RCRA Risk-Cos t Analysi s Mode l Phas e II I Report, " prepare d byIC F Inc. , 1984 .h- 9 P.3 2

Th e ingestio nALI s use d i n th e calculation s ar e take n fromICRP' s Publicatio n30. 1 UWher e mor e tha n on e ingestio n AL I wa s availabl e fo r a particula r radionuclide , th e lowes t AL I wa s use d fo r th e calculations . Th e facto r 1 0 convert s th e 5 remannua l occupationa l dos e limi t t o th e 50 0 millire m(0. 5 rem ) annua l limi t fo r member s o f th e genera l public , a s discusse d fo r th e inhalatio n pathway . Th e dilutio nfacto r (DF ) i s derive d byconsiderin g th e maximum concentratio ni na contaminan t plum e 3 0 meter s downgradien t froma poin t sourc e release , a s calculate d byus e o f standar d equation s modelin g ' ground-wate r transpor t (thi s ground-wate r exposur e scenari o i s illustrate d i h Exhibi t 4-2) . Th e maximumconcentratio n i s assume d t o b e uniforml yi distribute d throughou t th e plume. 1 5 Thirt ymeter s i s chose n fo r consistenc y wit hth e atmospheri c mode l and lead s t o highe r concentration s and lowe r \ Releas e Value s tha nwoul d b e th e cas e fo r a greate r distance . ' Th e Agenc yconsidere d tw o dilutio n model s durin g th e R Q developmen t ' process : a simpl e dilutio nmode l and a n advection-dispersio n model . Th e simpl e dilutio nmode l relie s o n th e estimat e tha t th e practica l nee d fo r wate r o f a singl e perso nlivin g i n a rura l are a i s 7,70 0 cubi c meter s pe r year. 1 6 ' Thi s represent s a dilutio nfacto r o f 1. 3 x1 0 pe r liter . Th e mode l assume s th e flo wrat e o f th e aquife r i s sufficientl yslo wtha t th e contac t tim e i s a n entir e yea r (36 5 days ) and th e entir e quantit yrelease d i s pumpe d fromth e wel l ove r a perio d o f on e year . ' Us e o f th e advection-dispersio n mode l fo r determinatio n o f radionuclid e concentratio ni ndrinkin g wate r relie s o n estimate s o f longitudina l and j transvers e coefficient s o f dispersion , bul k densit yo f th e aquifer , sorption , coefficient s fo r individua l radionuclides , an d aquife r flo wrate . Th e Agenc y

lu Internationa l Commissio n o n Radiatio n Protection , Annal s o f th e ICRP : , Limit s fo r Intake s o f Radionuclide s b yWorkers , ICR P Publicatio n 30 , Par t 2 , 1980 . 15 Thi s i s a conservativ e approximatio n becaus e concentration s ar e usuall ydistribute d i na Gaussia n fashio n withi n a plume , wit hsmalle r concentration s towar d th e edge s o f th e plum e an d highe r concentration s nea r , th e plume' s cente r line . 16 Th e Nuclea r Regulator yCommissio n use s th e simpl e dilutio n mode l fo r th e purpose s o f determinin g allowabl e onsit e disposa l concentration s fo r ' radioactiv e 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 suburba no r urba narea s ma yb e fromgroun d water , th e groun d wate r i s likely , t o b e pumpe d throug hsevera l high-capacit ywell s and the n distribute d throug h severa l interconnectin g pipe s t o individua l homes . Thi s typ e o f syste mwil l resul t i nmuc hgreate r dilutio n tha n a simpl e rura l syste mwher e wate r i s obtaine d fro ma backyar d wel l and take n directl yt o a tap .P.3 3 

### Exhibi t4- 2 Scenari o fo rCalculatio n ofGround-Wate rTranspor t

SID E VIE W

1 m 

# s Wel l

'""'* ' ,,,,,,.,,.,,,. .

Oirectlo n o fQround-wata rFlo w XMMMII * •''''' '

)lli)MMM)H)| l Poin to freleas e 30 m

Olfactio n o f Qround-wata rFlo w / Plum e a ttim e ygreate rtha n zer o

Poin t/ o frelease- ^ ( We nP.3 4

4-1 1

believe s that , fo r th e purpos e o f developin g RQs , th e advection-dispersio n mode l i s mor e appropriat e tha nth e simpl e dilutio nmodel . Th e simpl e dilutio n mode l assume s tha t al l o f th e releas e wil l b e pumpe dfromth e wel l andal l o f th e pollute dwate r wil l b e consume db ya nindividual . Althoug hth e simpl e dilutio nmode l appear s appropriat e fo r determinin g concentratio nlevel s fo r , purpose s o f ris k assessment , th e advection-dispersio nmode l i s base do nth e somewha t les s conservativ e bu t mor e likel yassumptio ntha t onl ya fractio no f th e releas e wil l b e pumpe dfromth e wel l andconsume dbya nindividual . Th e : Agency , therefore , base dit s ingestio nexposur e calculation s o nth e advection-dispersio nmodel . Th e Agenc yals o considere dus e o f severa l ground-wate r model s use db y EPA' s Offic e o f Soli dWast e t o suppor t analyse s unde r th e Resourc e Conservatio nandRecover yAc t (RCRA) . Th e equation s use di nth e RCRAmodel s ar e simila r t o th e equation s use di nth e advection-dispersio nmodel ; however, , becaus e th e RCRAanalyse s ar e ris k based , som e parameter s use di nth e ' equation s i nth e RCRAmodel s ar e muc hmor e conservativ e tha nthos e use dfo r ; purpose s o f R Q adjustmen t i nth e advection-dispersio nmodel . Furthe r discussio no f th e advection-dispersio nmodel , th e simpl e dilutio nmodel , and' th e fou r RCRAmodel s ca nb e foundi nAppendi xF o f thi s report . [ i Th e ground-wate r advection-dispersio nmodelin g equation s utiliz e a retardatio nfacto r fo r estimatin g th e amoun t o f a releas e tha t coul db e pumpe d froma naffecte dwel l locate d3 0 meter s fro mth e source . Retardatio nfactor s fo r eac hradionuclid e diffe r becaus e differen t radionuclide s ar e adsorbe d! differentl yont o th e sando r soi l i na naquifer . Becaus e o f thei r chemica l nature , som e radionuclide s ar e adsorbe donl yweakl yo r no t a t al l (e.g. , technetium) , whil e other s ar e adsorbe dstrongl y(e.g. , cesium) . Atabl e o f sorptio ncoefficient s ca nb e foundi nAppendi xF . Th e retardatio nfacto r use d i nth e mode l take s int o accoun t th e soi l bul k density , porosity , andth e sorptio ncoefficient , K, . Whe nth e sorptio ncoefficien t i s equa l t o zero , th e retardatio nfactor , R, , i s equa l t o one ; tha t is , ther e i s n o retardation . Whe nth e sorptio ncoefficien t i s greate r tha nzero , th e retardatio nfacto r i s greate r tha non e andnuclid e retardatio nha s occurred . Th e dilutio nfacto r i s relate ddirectl yt o th e sorptio ncoefficient . Th e greate r th e sorptio ncoefficient , th e greate r i s th e nuclid e retardatio ni n th e aquifer , andth e greate r i s th e dilutio nfactor . Th e retardatio nfacto r als o affect s th e estimatio no f th e contac t time , th e tota l tim e a contaminan t plum e wil l b e i ncontac t wit ha naffecte dwell . I f th e retardatio nfacto r i s equa l t o one , th e advection-dispersio nmode l ! assume s tha t th e contaminatio ni s movin g a t th e sam e velocit ya s th e wate r i n th e aquife r (i.e. , n o retardatio noccurs) , andth e wel l i s i ncontac t wit hth e contaminatio nfo r nin e days . I f th e retardatio nfacto r i s greate r tha none , th e advection-dispersio nmode l assume s tha t th e contaminatio ni s bein g i retarde dan di s movin g a t a slowe r rat e tha nth e wate r i nth e aquifer . Th e contac t time , therefore , wil l b e longe r tha nnin e days . Appendi xF describe s furthe r th e relationshi p betwee nth e sorptio ncoefficient s andretardatio n factors , an dthei r affect s o nth e dilutio nfactor s andcontac t time s fo r differen t radionuclides .P.3 5

I ncalculatin g th e ingestio n Releas e Values , whe n th e sorptio n coefficien t i s greate r tha no r equa l t o 4 fo r a particula r radionuclide , th e contac t tim e i s assume d t o b e 36 5 days . I n reality , i t coul d tak e significantl ylonge r tha n36 5 day s fo r th e contaminan t plum e t o pas s th e wel l head , bu t becaus e ALI s reflec t annua l intak e levels , th e contac t tim e i n th e advection-dispersio n mode l i s constraine d no t t o excee d 36 5 days . Th e dilutio n factor , however , wil l als o reflec t th e sorptio n coefficient ; th e dilutio n facto r i s ver ylarg e whe nth e sorptio ncoefficien t i s significantl yabov e 4 . > Finally , th e dail ywate r consumptio n o f "Referenc e Man " i s assume d t o be '• 2 liters. 1 7 Th e Releas e Value s calculate d fo r th e ingestio n pathwa yar e presente d a t th e end o f thi s chapte r i n Exhibi t 4-5 . 4.2. 3 Releas e Value s fo r th e Direc t Exposur e Pathwa y Th e methodolog yfo r determinin g Releas e Value s fo r direc t exposur e t o '< radiatio ndepend s o nth e formo f th e radionuclid e released . Fo r nobl e ga s isotopes , th e Releas e Value s ar e base d o n exposur e du e t o tota l body; submersio ni na radioactiv e ga s cloud . Fo r al l othe r radionuclides , Releas e Value s ar e base d o nth e quantit yo f radioactivit yreceive d b ya n individua l expose d t o a poin t sourc e o f radiation . Th e calculatio n o f Releas e Value s fo r poin t sourc e and nobl e ga s release s ar e discusse d furthe r below ; th e value s ar e presente d a t th e end o f thi s chapte r i n Exhibi t 4-5 . , Direc t Exposur e Fro ma Poin t Sourc e A s wit hth e inhalatio nand ingestio n scenarios , direc t exposur e Releas e ' Value s ar e base d o na 50 0 millire mexposur e limit . Th e releas e i s assume d t o occu r i nth e cente r o f a hemispher e wit ha 3 0 mete r radius , and a n expose d individua l i s assume d t o b e tangen t t o thi s hemispher e (se e Exhibi t 4-3) . Th e metho d use d byth e Agenc yfo r calculatin g direc t exposur e Releas e Value s from a fixe d poin t sourc e i s adapte d fromfro mth e Healt hPhysic s an d Radiologica l Healt hHandboo k 1 8 and include s gamm a rayattenuatio n i n ai r betwee n th e sourc e and th e receptor . I t reflect s th e effect s o f gamm a radiatio n and ca n i b e simplified , a s showni nAppendi xG , t o yiel d th e followin g equation : (5 ) Direc t Exposur e Releas e Valu e =

where : (6.41xl0" 5 )'KDn)*(S 2 )/((E 1 )^( u )*(T)*(exp(- u S)) ) ± a

a.

D n= Dos e equivalen t i n rem ; S = Distanc e fromth e releas e (3 0 m) ;

17 Thi s intak e rat e i s generall yuse d a s th e averag e wate r consumptio n leve l fo r man . Fo r example , 2 liters/da ywa s use d b yEP Ai n developin g th e Nationa l Interi mPrimar yDrinkin g Wate r Regulations . 18 Nucleo n Lecter nAssociates , Th e Healt hPhysic s an d Radiologica l Healt hHandbook , 1984 , p . 41 .EXHIBI T4- 3 SCHEMATI C O F ASSUMPTIO N USE D I N DERMA LEXPOSUR E PATHWA Y

Groun d Lava l

Poln l o l Releas e

T l C OP.3 7

•1 4

E = Th e su

mo f th e product s o f th e gamm a rayenergie s (MeV ) and , th e gamm a rayfractions ; i

u = Linea r energyabsorptio n coefficien t fo r gamm a ray s i n ai r , 3. (c m) ; and T = Duratio no f exposur e (2 4 hours) . exp(- u S ) = Attenuatio nfacto r Th e direc t exposur e Releas e Valu e represent s th e quantit yo f radionuclide , i ncuries , necessar yt o provid e a gamm a rayexposur e o f 50 0 milliroentge n (th e sam e a s a dose-equivalen t o f 50 0 millirem) , ove r a 24-hou r exposur e period , t o a nindividua l 3 0 meter s (S ) froma poin t sourc e releas e o f radioactiv e material. 1 9 Gamm a ray s alon e ar e considere d i n thi s equatio n becaus e th e mea nrang e o f alph a and bet a particle s wit henergie s lowe r tha n 1 0 Me V i s les s tha n3 0 meters. 2 0 Th e Agenc yi s awar e tha t othe r approache s ca n b e take n t o calculat e direc t exposur e Releas e Values . I n particular , i t ha s bee n suggeste d tha t specific ' gamm a ra yconstant s b e applie d t o thi s calculation . Th e specifi c gamm a ray constan t i s define d a s th e produc t o f th e exposur e rat e a t a give n distanc e , froma poin t sourc e and th e squar e o f tha t distanc e divide d b yth e activit yo f th e source , neglectin g attenuation . Table s ar e availabl e tha t lis t th e specifi c gamm a rayconstan t fo r a limite d numbe r (approximatel y90 ) o f th e 75 7 radionuclide s fo r whic hspecifi c RQ s ar e proposed . Becaus e thes e value s wer e no t readil yavailabl e fo r al l o f th e radionuclide s o f interest , th e Agenc yha s chose nt o us e Equatio n(5 ) t o calculat e direc t exposur e Releas e Values . Th e direc t exposur e Releas e Valu e wa s calculate d usin g Equatio n (5 ) 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 no t emitte d ever ytim e tha t th e nuclid e decay s (i.e. , disintegrates) . I naddition , a gamm a raytha t i s emitte d froma give n

19 Ara d (radiatio nabsorbe d dose ) i s a measur e o f th e amoun t o f energ y absorbe d i na gramo f tissue , wherea s a remi s a measur e tha t account s fo r th e biologica l respons e o f tha t absorbe d dose . Multiplyin g rad s time s a "qualit y factor " yield s rem s and , fo r gamm a rays , th e qualit yfacto r equal s one . 2 0 A1 0 Me V

alph a o r bet a particl e woul d b e a n extremel yenergeti c parti

cle . Th e mea nrang e o f a 1 0 Me V alph a particl e i n ai r i s les s tha n 1 5 • centimeters . Bet a particle s typicall yrang e i n energ ybetwee n 0.0 4 and 6 MeV , althoug hther e ar e a fe wradionuclide s whic hemi t bet a particle s wit hhigher ; energie s (e.g. , th e maximumbet a particl e energ yfo r carbon-1 5 and bromine-8 7 i s abou t 1 0 and 8 MeV , respectively) . Th e mea n rang e o f a 6 Me V bet a particl e i nai r i s onl yabou t 2 0 meter s and thes e hig henerg ybet a particle s ar e very ' rare . Therefore , althoug hther e ar e on e o r tw o nuclide s fo r whic hbet a ; particle s ca nconceivabl ytrave l approximatel y3 0 meter s i n air , exposure s a t thi s distanc e ar e fo r th e mos t par t onl ya concer n fo r gamm a rays .P.3 8

H- L~>

radionuclid e doe s no t necessaril yalway s hav e th e sam e energ ylevel . Thi s phenomeno ni s illustrate di nExhibi t 4-4 . A s showni nthi s exhibit , ever y tim e argon-4 1 disintegrates , i t emit s a gamm a raywit ha nenergyleve l o f 1. 3 MeV . Krypton-8 5 emit s a gamm a rayfo r onl ya smal l fractio no f it s disintegration s (0. 4 percent) , whil e severa l differen t gamma s wit hdifferen t energie s ar e emitte db ymolybdenum-99 . [i T o accoun t fo r thes e variou s gamm a rayenergie s andfraction s whe nusin g Equatio n(5) , th e energ yleve l ( E ) fo r a give nradionuclid e wa s derive dby takin g th e sumo f th e product s o f th e gamm a rayenergie s andth e gamm a ray, fractions . Fo r example , th e E valu e use dfo r argon-4 1 wa s 1. 3 MeV andth e E valu e use dfo 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 nradionuclid e andaccount s fo r th e fractio no f tim e tha t suc ha gamm a rayi s actuall yemitted . Th e linea r energ yabsorptio ncoefficien t fo r gamm a ray s i nai r ( u ) 3 . varie s wit hth e gamm a rayenergy . Whe nth e gamm a rayenerg yi s 1 MeV , th e [ linea r energ yabsorptio ncoefficien t i s 3. 7 x1 0 /cm. 2 1 Fo r gamm a ray s wit henergie s betwee n0.0 7 Me V and2 MeV , th e absorptio ncoefficien t wil l var y from3. 7 x1 0 b

yplu s o r minu s 1 5 percent . Becaus e th e variatio ni s s o slight , fo r purpose s o f calculatin g th e direc t exposur e Releas e Values , w e ; hav e assume dth e absorptio ncoefficien t i s 3. 7 x1 0 /c mfo r al l ' radionuclide s o f concern . Th e duratio no f exposure , T , i s assume dt o b e 2 4 hours . Thi s tim e perio d i s selecte dbecause , withou t notification , i t i s possibl e fo r a perso nt o b e expose dt o a radionuclid e releas e fo r a nextende dperio do f time . However , i t i s unlikel ytha t exposur e wil l occu r ove r mor e tha na 24-hou r perio dwithou t a perso nmovin g outsid e o f th e radiatio nrange . Assumin g th e duratio no f exposur e i s 2 4 hour s i s conservative , therefore , bu t allow s fo r a maximum exposur e tim e fo r a release . I norde r t o accoun t fo r attenuatio no f gamm a ray s i nai r betwee nth e sourc e o nth e receptor , th e exponentia l term exp(- u S ) i s used . Incorporatio no f a termfo r gamm a rayattenuatio n

a . result s i na sligh t increas e i nth e direc t exposur e Releas e Valu e becaus e approximatel y1 0 percen t o f th e gamm a ray s emitte dwil l b e absorbe di nth e 3 0 meter s o f ai r betweenth e sourc e andth e receptor . Th e expression , showni nEquatio n(5) , fo r determinin g th e Releas e Valu e fo r th e direc t exposur e pathwa yfro ma fixe dpoin t sourc e ca nb e simplifie d;b y substitutin g th e followin g value s int o th e equation :

D n= 0.5 ; S = 30 ;

• u = 3.7x10 " ; and a T = 24 .

21 Nucleo nLecter nAssociates , Th e Healt hPhysic s an dRadiologica l Healt h Handbook , 1984 , p.41 .P.3 9

EXHIBI T4- 4 GAMM ARA YENERGIES , GAMM ARA Y FRACTIONS , AN D ENERG YLEVEL S FO R SELECTE D RADIONUCLIDE S

Radionuclid e Argon-4 1 Krypton-8 5 Molybdenum-9 9 Gamm a Ra y Energy , E (MeV )
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

Source : Nationa l Counci l o n

Handboo k o f Radioac t Gamm a Ra y Fraction (percent )
10 0 0.4 3 1 5 6 1 1 2 4 0. 1 Gamm

a Ra y Fraction Time s E (MeV )
1. 3 2.2xl0" 3 4.1xl0' 4 70.5xl0" 4 108.6xl0" 4 36.6xl0" 4 88.8xl0" 3 310.8xl0~ 4 8.2xl0 - 4 Radionuclide

Energ yLevel , E i : (MeV ) j
1. 3 2. 2 x10" 3
1 | 0.1 4 | ; | J
Radiatio n Protectio nan d Measurements , A ivit yMeasuremen t Procedure s . NCRP Repor t No. ; 58 . Washington , D.C . Novembe r 1978 .P.4 0

•17

Equatio n(5 ) simplifie s to : !

(6 ) Direc t Exposur e Releas e Valu e = 36.3/E. . Direc t exposur e Releas e Value s calculate dfo r th e radionuclide s tha t emi t ; gamm a ray s ar e presente da t th e endo f thi s chapte r i nExhibi t 4-5 . Submersio ni na Radioactiv e Clou do f Nobl e Ga s Becaus e th e nobl e gase s argon, krypton , andxeno nar e chemicall yver y stable , the yar e no t likel yt o formsoli do r liqui dcompound s whic hca nb e ingested . Also , becaus e the yar e relativel yinsolubl e i nbloo dandar e easil y displace dbymor e commo ngase s suc ha s oxyge nan dnitrogen , nobl e gase s ar e i no t incorporate dreadil yint o th e bodyafte r inhalation . A s a resul t o f thi s inertness , ingestio nandinhalatio nar e no t significan t exposur e pathway s and ALI s fo r ingestio nan dinhalatio nwer e no t develope dbyth e ICR P fo r mos t | nobl e gases . However , submersio ni na radioactiv e clou dca ncaus e a I significan t whol e bodydos e du e t o direc t exposure . Therefore , direc t exposur e Releas e Value s fo r argon, krypton , andxeno nwer e derive dassumin g ' tha t a nexpose dindividua l i s submerge di na clou do f th e ga s 3 0 meter s from ! th e releas e point. 2 2 Adifferen t equatio nfo r th e calculatio no f direc t exposur e Releas e Value s i s appropriat e fo r radioactiv e nobl e gase s becaus e submersio ni na clou d result s i na nintegrate ddos e fromal l direction s a t varyin g distance s fro m! th e body . Th e direc t exposur e Releas e Value s fo r submersio ni na radioactiv e clou do f a nobl e ga s ar e derive dthroug hth e followin g equation: 2 3 (7 ) Direc t Exposur e Releas e Valu e = ((83)*(DAC)*(T))/((10)*(X/Q)*(lxl0 6 )| ) where : '•

DAC = Derive dAirborn e Concentratio n(microcuries/cm 3 ) ; j T = Duratio no f Exposur e ( 1 day )

22 Argon , krypton , andxeno nar e th e onl ynobl e gase s whos e Releas e Value s ar e calculate dbase do ntota l submersio ni na cloud . Th e nobl e gase s heliumandneo nd o no t formisotope s wit hhal f live s longe r tha na fe w seconds . ALI s fo r thes e isotope s hav e no t bee ndevelope dand , therefore , n o Releas e Value s hav e bee ncalculated . Th e nobl e ga s rado nha s tw o isotope s (radon-22 0 an dradon-222 ) wit hinhalatio nALIs . Becaus e thes e tw o isotope s , emi t alph a particles , inhalatio ni s a mor e critica l exposur e pathwa ytha n' submersio ni na radioactiv e clou dan dth e lowes t o f th e propose dALI s i neac h cas e wa s use dt o calculat e inhalatio nReleas e Value s fo r thes e radionuclides! . 23 Thi s equatio ni s derive dfroma nequatio nfoundi nth e Annal s o f th e ICRP , Publicatio nNo . 30 , Par t 1 , Volum e 2 , No . 3/4 , 1979 , pp . 1 0 an d47 .P.4 1

4-1 8

X/ Q = Atmospheri c Relativ e Concentratio n Valu e a t 3 0 meter s (8.4xl0 _1 3 day/cm 3 ) ; and 1x1 0 = Conversio nfacto r betwee n microcurie s and curies . Th e DAC valu e specifie s th e airborn e concentratio n tha t woul d resul t i na 5 re mwhol e bodydos e equivalen t fo r a 200 0 hou r exposur e period . T o adjus t th e airborn e concentratio nfroma 200 0 hou r t o a 2 4 hou r exposur e period , th e DAC valu e i nEquatio n(7 ) i s multiple d by8 3 (i.e. , 200 0 hour s * 2 4 hours) . Th e facto r o f 1 0 i nth e denominato r o f Equatio n (7 ) convert s th e 5 remwhol e body

limi t fo r occupationa l exposur e t o th e 0. 5 rem(50 0 millirem ) limi t fo r exposur e t o th e genera l public . X/ Q i s th e ground-leve l concentratio n value ; 3 0 meter s fromth e releas e poin t (se e Sectio n 4.2. 1 abov e and Appendi xE fo r furthe r discussio no f X/Q) . Th e expression , showni n Equatio n (7) , fo r determinin g th e Releas e Value ; fo r th e direc t exposur e pathwa ydu e t o submersio n i n a clou d o f radioactiv e '• nobl e ga s ca nb e simplifie d bymultiplyin g th e number s i n th e denominator . Equatio n(7 ) simplifie s to :

(7 ) Direc t Exposur e Releas e Valu e = DAC/(lxl 0 ) Th e direc t exposur e Releas e Value s fo r argon , krypton , and xeno n ca n b e found a t th e end o f thi s chapte r i n Exhibi t 4-5 . 4. 3 ASSIGNMEN TO F RADIONUCLIDE S T O PROPOSE D R Q GROUP S \ Exhibi t 4- 5 a t th e end o f thi s chapte r display s th e thre e Releas e Values ; calculate d fo r eac hradionuclide . Th e lowes t Releas e Valu e fo r eac h radionuclid e ha s a nasteris k besid e it . Th e lowes t Releas e Value s rang e i n: valu e fromove r 10,00 0 curie s t o approximatel y0.00 1 curie . Fo r administrativ e feasibilit yand simplicity , th e Agenc ydecide d t o assig nth e ; radionuclide s t o on e o f seve n distinc t group s identifie d byspecifi c propose d RQs . Eac hradionuclid e i s assigne d a propose d R Q o f 0.00 1 curie , 0.0 1 curie i 0. 1 curie , 1 curie , 1 0 curies , 10 0 curies , o r 100 0 curies . Assignmen t o f a | propose d R Q t o a particula r radionuclid e wa s mad e byexaminin g th e lowes t j Releas e Valu e fo r eac hradionuclid e an d roundin g tha t valu e dow n t o th e neares t propose d R Q group . ! Th e 75 7 radionuclide s wit hpropose d RQ s ar e represente d a s follows : i

• 6 radionuclide s (0.8% ) hav e lowes t Releas e Value s les s tha n0.0 1 curi e and , therefore , hav e a propose d R Q o f 0.00 1 curie ; ;

• 2 5 radionuclide s (3.3% ) hav e lowes t Releas e Value s ; greate r tha no r equa l t o 0.0 1 curi e bu t les s tha n 0. 1 curi e and , therefore , hav e a propose d R Q o f 0.0 1 curie ; ;P.4 2

4-1 9

• 2 4 radionuclide s (3.2% ) hav e lowes t Releas e Value s greate r thano r equa l t o 0. 1 curi e bu t les s than1 curi e and , therefore , hav e a propose d RQ o f 0. 1 curie ;

e 3 5 radionuclide s (4.6% ) hav e lowes t Releas e Value s greate r thano r equa l t o 1 curi e bu t les s than1 0 curie s and , therefore , hav e a propose d RQ o f 1 curie ;

• 34 2 radionuclide s (45.2% ) hav e lowes t Releas e Value s greate r thano r equa l t o 1 0 curie s bu t les s than10 0 curie s and , therefor e hav e a propose d RQ o f 1 0 curies ;

• 23 6 radionuclide s (31.2% ) hav e lowes t Releas e Value s greate r thano r equa l t o 10 0 curie s bu t les s than100 0 | curie s and , therefore , hav e a propose d RQ o f 10 0 curies ; an d

• 8 9 radionuclide s (11.7% ) hav e lowes t Releas e Value s greate r thano r equa l t o 100 0 curie s and , therefore , ' hav e a propose d RQ o f 100 0 curies . T o accommodat e fo r unusua l releas e event s tha t ar e no t foreseencurrentl y b yth e Agency , a

nR Q o f 1 curi e i s als o assigne d t o al l know nradionuclide s no t listed i nICRP' s Publicatio n30. 2 4 Th e Agencybelieve s tha t b y establishing anRQ for the broad generi c clas s "Radionuclides, " i t i s ( fulfilling th e CERCL Amandat e t o protec t publi c health , welfare , an d the environment . A s see nabove , th e 1 curi e R Q i s th e middl e R Q leve l an d th e majorit y(93% ) o f the radionuclide s wit hpropose d RQ s have minimu mReleas e Value s greate r thano r equa l t o 1 curie . Therefore , the generi c R Q o f 1 curi e for al l othe r radionuclide s i s a conservative value . Tw o o r mor e radionuclide s wit hthe same propose d RQ d o no t reflec t a determinatio ntha t a releas e o f on e wil l b e a s hazardou s a s the releas e o f another , o r eve ntha t the releas e o f on e wil l b e hazardou s a t the propose d R Q leve l an

d no t hazardou s belowtha t level . Th e Agencyha s foun d tha t the actua l hazard wil l var ywit hthe uniqu e circumstance s o f the release , an d '< extensive scientifi c dat a an d analysi s woul d b e necessar yt o determin e the hazard presente d b

yeachsubstanc e unde r a numbe r o f possibl e circumstances . '< Instead , th e RQ s ar e designe d t o b e a trigge r fo r notificatio nan d reflec t the Agency' s judgmen t tha t th e 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 . Th e reportabl e quantitie s represen t a determinatio nonl 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 be harmfu l t o publi c healt ho r welfar e o r th e environment .

2 * Internationa l Commissio no nRadiatio nProtection , Annal s o f the ICRP : Limit s for Intake s o f Radionuclide s b yWorkers , ICRP Publicatio n30 , Par t 2 , 1980 .P.4 3

4-2 0

Th e Agencyi s soliciting comment s o nthe selected methodolog yan d the propose d RQ s for individua l radionuclide s tha t mayb e to o lo wo r to o high . EP Awoul d b e interested i nsuggestion s an d dat a regarding wha t criteri a the Agencyshoul d conside r i nadjusting technicall yo r administrativel ya propose d RQ fo r anindividua l radionuclide . Th e Agencyi s awar e tha t reporting requirement s simila r t o thos e presente d her e hav e bee ndevelope d previously . Th e Nuclea r RegulatoryCommissio nha s establishe d conten t limit s ( Aan d A „ values) , presente d i n1 0 CFRPar t * 71 , Appendi xA . Th e conten t limit s ar e applicabl e t o Typ e Apackaging whic h i s intended t o provid e saf e an d economica l transportatio npackaging fo r a larg e numbe r o f smalle r activityconsignments . Th e conten t limit s listed i n 1 0 CFRPar t 7 1 ar e base d o na dose-equivalen t leve l o f 5 re man d ar e base d o n! exposur e pathway s simila r t o thos e develope d for the propose d RQs . However , the conten t limit s ar e base d o ndifferen t calculationa l assumption s and , mor e importantly , ar e designe d t o limi t the exposur e an d healt hrisk s resulting fro manacciden t occurring during the transportatio no f radionuclides . I na transportatio nacciden t situation , immediat e respons e (i.e. , fir e an d polic e departments ) i s expecte d an d the genera l publi c wil l be remove d fro mdange r quickly . Contaminatio nis , therefore , likel yt o b e isolated i na shor t perio d o f time an

d exposur e o f th e publi c wil l b e limited . I nthi s situation , th e individual s mos t likel yt o b e affecte d b ythe contaminatio nar e thos e involve d i nth e acciden t an

d i nthe resulting isolationan d cleanu

p activities . Onthe othe r hand , the propose d RQ s presente d her e ar e designe d t o protec t the unsuspecting publi c wh o ar e no t awar e immediatel yo f a release . Th e propose d i RQ value s reflec t mor e genera l releas e an d exposur e scenario s an d ar e base d o n situation s wher e respons e time s ar e expecte d t o b e longer . Whil e the conten t limit s an

d propose d RQ s ar e base d o nsimila r methodologies , an d sometime s ar e equivalen t values , th e RQ s propose d her e ar e designe d t o protec t th e publi c healt han

d welfar e an

d the environmen t i na broade r fashion . 4. 4 REPORTIN G REQUIREMENT S FO R MIXTURE S O FRADIONUCLIDE S Some 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 b e on e o f two genera l types : mixture s o f know ncompositio no r mixture s o f unknow ncomposition . Th e convention s adopte d b

yth e Agencyi nestablishing reporting requirement s fo r mixture s an d the propose d RQ s for two commo nradionuclid e mixture s ar e presente d below . 4.4. 1 Mixture s o fKnow n Compositio n i Reporting requirement s fo r release s involving mixture s o f know n compositio ncanb e obtaine d directl yfro mthe propose d RQ s for individua l constituent s o f the mixture . I f the identityan d quantit yo f each radionuclid e involve d i na releas e even t i s known , the decisio nt o repor t a releas e mus t b e mad e i nth e following manner : for eachradionuclid e i nth e mixture , the rati o betwee nthe quantit yrelease d (incuries ) an d the propose d RQ fo r the radionuclid e mus t b e determined . I f the su mo f th e ratio s fo r al l radionuclide s i s les s than1 , the releas e nee d no t b e reported . I f th e su mi s equa l t o o r greate r than1 , the releas e mus t b e reporte d t o the Nationa l ! Respons e Center . ;P.4 4

•2 1

Fo r example , i f radionuclide s a , b, and c ar e release d i n quantitie s o f Qa , Qb , and Q c curie s i na mixture , and i f th e propose d RQ s ar e RQa , RQb, 1 and RQc , respectively , the nth e quantit yrelease d fo r th e mixtur e doe s no t : excee d th e propose d R Q and th e releas e nee d no t b e reporte d t o th e Nationa l Respons e Cente r i f (Qa/RQ a + Qb/RQ b+ Qc/RQc ) i s les s tha n 1 . Thi s conventio n fo r handlin g release s o f radionuclid e mixture s i s recommende d b yth e ICRP . ! 4.4. 2 Mixture s o f Unknow n Compositio n Reportin g requirement s fo r mixture s o f unknow n compositio n canno t b e base d o nth e determinatio no f quantitie s released . Fo r mixture s o f unknow n composition , ther e ar e thre e possibilities : (1 ) th e identit yo f th e radionuclide s involve d i s known , bu t th e amount s release d o f eac hi s unknown, (2 ) th e identit yo f th e radionuclide s (o r on e o f th e radionuclides ) i n th e mixtur e i s unknown , bu t th e amoun t release d i s know n i n tota l curie s pe r uni t volum e o r weight , o r (3 ) th e identit yo f th e radionuclide s involve d i s unknow n and th e amoun t o f radionuclide s release d i n th e mixtur e i s unknown . Fo r thes e cases , th e decisio nt o repor t a releas e i s mad e a s follows : :

(1 ) Identit yknown , bu t concentratio n unknown . , I f th e identit yo f eac hradionuclid e i n th e mixtur e i s know nbu t th e concentratio n o f on e o r mor e o f th e radionuclide s i s unknown , th e R Q fo r th e mixtur e shal l ' b e th e lowes t R Q o f anyradionuclid e i n th e mixture . ; Thi s metho d fo r determinin g th e R Q o f a mixtur e assure s a repor t t o th e Nationa l Respons e Cente r i f th e 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 tha nth e R Q i n curie s o f th e substanc e wit hth e lowes t R Q i nth e mixture .

(2 ) an d (3 ) Identit yo f radionuclide(s ) i n th e releas e i s unknown . I f th e identit yo f a radionuclid e i n a releas e i s unknow no r i f th e identit yo f on e o r mor e radionuclide s i nth e 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 th e Nationa l Respons e Cente r i f th e tota l releas e i s equa l t o o r greate r tha n 1 curie , o r i f th e tota l releas e i s equa l t o o r greate r tha nth e lowes t R Q o f anyknow n radionuclid e i n th e mixture , whic heve r i s lower . Establishin g a nR Q o f 1 curi e fo r a releas e i n whic hth e identit yo f th e radionuclid e o r radionuclide s involve d i s unkow n i s consisten t wit hth e 1 curi e R Q fo r th e clas s o f radionuclide s fo r whic hinsufficien t dat a exis t t o extablis hindividua l RQs . Th e mixtur e rul e require s reportin g i f th e releas e equal s o r exceed s 1 curie , or , i f som e componen t o f th e mixtur e i s kno wand it s R Q i s les s tha n1 curie , the n th e tota l releas e mus t b e reporte d i f i t equal s o r exceed s th e R Q o f th e know n component . Th e Agenc yi s considerin g and solicitin g commen t o na n R Q o f 0.00 1 fo r mixture s wher e th e identit yo f th e radionuclide s i s unknown. A n R Q o f 0.00 1 fo r thi s clas s o f mixture s correspond s t o th e lowes t R Q categor ydevelope d i n thi s repor t and woul d b e mor e conservativ e tha na nR Q o f 1 curie .P.4 5

• -2 2

4.4. 3 Commo nRadionuclid e Mixture s Propose d RQ s hav e bee ndevelope d fo r tw o commo n radionuclid e mixtures : radium-22 6 i nequilibriumwit hit s daughters , an d natura l uranium . Mixe d fissio nproduct s ar e als o recognize d byth e Agenc ya s a n importan t and commo n radionuclid e mixture . However , th e Agenc yi s proposin g RQ s currentl yonl yfo r th e individua l radionuclid e component s withi n thi s latte r mixtur e becaus e a n! R Q fo r mixe d fissio nproduct s woul d hav e t o b e tim e dependent . Tha t is , a t differen t tim e intervals , th e concentratio n o f th e differen t component s o f ' thi s mixtur e wil l b e different . I n addition , th e component s o f th e mixe d fissio nproduc t wil l differ , dependin g o n th e typ e o f reacto r involved . 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 th e 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 equilibriumi s establishe d i n th e mixture , suc htha t th e \ activit ypresen t fo r eac hdaughte r produc t and th e paren t radiu mi s equal. 2 5 Fo r example , i f on e curi e o f radium-22 6 i s released , whe n j equilibriumi s reached , th e activit yleve l o f th e mixtur e wil l b e 1 2 curies . \ Whe nradium

and it s daughter s reac hthi s stat e o f equilibrium , it s R Q i s 0.4 3 curies . :

i ' Natura l uraniumi s compose d o f th e isotope s U-23 8 (99.2 7 percen t b y weight) , U-23 4 (0.005 7 percen t b yweight) , and U-23 5 (0.7 2 percen t b yweight) . Becaus e th e compositio nbyweigh t o f natura l uraniumi s known , w e ca n deriv e th e activit ylevel s o f eac ho f it s components . Th e propose d rul e result s in j a nR Q fo r natura l uranium , derive d throug hth e mixtur e rule , o f 0. 1 curies .

2S Kaplan , I. , Nuclea r Physics , Addison-Wesle yPublishin g Company , Reading , Massachusetts , 1958 , p . 202 . Usin g th e mixtur e rule , th e R Q fo r radiumi nequilibriumwit hit s daughter s wa s calculate d fro mth e followin g formula : 1 1 2 1 R Q . = —I mix 1 2 i= l RQ . I where : RQ . i s the reportabl e quantit y o f radiu

m o r th e daughte r o f concern .EXHIBI T 4- 5 - RADIONUCLIDE S WIT H PROPOSE D RQ s
Releas e Value s (Ci ) P.4 6

Radionuclid e

Actinium-22 4 Actinium-22 5 Actinium-22 6 Actinium-22 7 Actinium-22 8 Aluminum-2 6 Americium-23 7 Americium-23 8 Americium-23 9 Americium-24 0 Americium-24 1 Americium-242 m Americium-24 2 Americium-24 3 Americium-244 m Americium-24 4 Americium-24 5 Americium-246 m Americium-24 6 Antimony-11 5 Antimony-116 m Antimony-11 6 Antimony-11 7 Antimony-118 m Atom . No .

8 9 8 9 8 9 8 9 8 9 1 3 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 5 1 5 1 5 1 5 1 5 1 Half-Lif e

2. 9 h r 10. 0 da y 1. 2 da y 21.7 7 y r 6.1 3 h r 7.2 E 5 y r 1.2 2 h r 1.6 3 h r 11.90 1 h r 50. 9 h r 432. 2 y r 14 1 y r 16.0 1 h r 7.37 E 3 y r 2 6 mi n 10. 1 h r 2.0 5 h r 25. 0 mi n 3 9 mi n 32. 1 mi n 6 0 mi n 1 6 mi n 2.8 0 h r 5.0 0 h r Ingestio n

(water )

5.4 E 1.3 E 2.7 E 5.4 E 5.4 E 3 . I E 2 . I E LI E 1.3 E 5.4 E 2.7 E 2.7 E 1.3 E 2.7 E 1.6 E 8 . I E 8 . I E 1.3 E 8 . I E 2.3 E 5.7 E 2.3 E 2.0 E 1.4 E 4 3 3 0 4 1 # 6 6 5 4 1 1 5 1 6 4 5 6 5 3 2 3 3 2 Inha

latio n

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 Direc t

Exposur e

2.9 E 1.3 E 2.6 E 5.3 E 4.9 E 2.0 E 1.6 E 5.2 E 4.3 E 3.8 E

- - 3.2 E

- - 7.9 E

- - 4.6 E 2 . I E 4.2 E 5.7 E 7.2 E 1.2 E 2.I E 2.5 E 1.4 E 2 3 2 5 1 1 * 2 * 1 * 2 * 1 *

5

2

1 * 3 * 1 * 1 * 1 * 1 * 1 * 2 * 1 * Propose d R Q (Ci )

10 0 1 ; 1 0

: 0.00 1 1 0 1 0 10 0 i 1 0

, 10 0 1 0

: 0.0 1 0.0 1 10 0 0.0 1 

## ioo o

; 1 0 

## ioo o

' 1 0

: 1 0

' 1 0 ! i o
: i o 10 0

: i oEXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) - • P.4 7

Radionuclid e
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 Atom . No .

5 1 5 1
5 1
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 Half-Lif e

36. 1 h r 15. 9 mi n
5.7 6 da y
2.7 1 da y 20. 3 mi n 60.2 0 da y 2.7 6 y r 19. 0 mi n 12. 4 da y 3.8 4 da y 1 0 mi n
9. 1 h r
4. 4 h r 38. 4 mi n 23. 0 mi n 26 9 y r 1.8 3 h r 15. 1 mi n 52. 6 mi n 6 2 h r 26. 0 h r 7 8 da y Ingestio n

(water )

2.9 E 2.9 E
2.6 E
2.0 E 5.7 E 1.4 E 5.7 E 1.4 E 1.4 E 2.0 E 2.3 E
2.9 E
8.6 E 5.7 E 2.9 E
na na 2.3 E 7.7 E 3 . I E 6.9 E 6 . I E 2 * 3
1
1 * 3 * 1 * 1 * 3 1 1 * 3
1
1 2 2

3 2 2 1 2 * Inha

latio n

1.6 E 4 2 . I E 5
5.2 E 2

5.2 E 2 3 . I E 5 1.0 E 2 2.6 E 2 1.0 E 5 2.6 E 2 4.7 E 2 2 . I E 5
1.6 E 3
4.7 E 3 3 . I E 4 1.0 E 4
na
na 5.2 E 4 2.6 E 4 2.6 E 3 5.2 E 2 1.0 E 3 Direc t

Exposur e

1.7 E 3 *

1.5 E 1 *
8.2 E 1

- - 2.0 E 1 8.9 E 1 2.3 E 1 * 1.4 E 1 * 6 . I E 1 1.9 E 1 *

1.3 E 1 *
3.0 E 1 * 1.3 E 1 * 2.7 E 1 * 2.0 E 3* + 3.0 E 1* + 1.5 E 3 * 1.5 E 1 * 1.6 E 2 * 4.I E 1 * [Proposed

R Q (Ci )

10 0 100 0
1 0

: 1 0 1 

### ioo o 1 0 ! i o ! 1 0
: 1 0 

### : i o 1 0

'• 1 0 

### ; i o | 1 0

: 1 0 100 0

: i o 100 0 1 0 10 0

: 1 0 10 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) — P.4 8

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 Half-Lif e

17.7 8 da y 26. 3 h r 38. 8 h r 1.51 5 h r 1.8 1 h r 7.2 1 h r 9 9 mi n 2.4 3 da y 14. 6 mi n 11. 8 da y 38. 9 h r 10.5 3 y r 28. 7 h r 83.3 1 mi n 12.7 6 da y 18. 3 mi n 10. 7 mi n 4.9 4 da y 1. 8 da y 1.4 E 3 y r 32 0 da y 3.2 2 h r 53.2 9 da y 2.7 E 6 y r Ingestio n

(water )

7.7 E 7.7 E 3 . I E 6.I E 4.6 E 7.7 E 1.6 E 1.3 E 

### LI E 8 . I E 5.4 E 5.4 E 8 . I E 2.7 E 1.3 E 5.4 E 1.3 E 3.8 E 5.6 E 1.9 E 9.4 E 1.9 E 8 . I E 2.0 E 1 * 1 * 2 * 2 2 # 0* # 4 3 6 3 3 3 3 4 3 4 5 4 4 1 3 5 4 3 Inha

latio n

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

7.9 E 9.9 E 5.0 E 3.5 E 4.0 E 2 . I E 1.0 E 9.5 E 6.0 E 9.0 E 7.7 E 1.0 E 8.5 E 8.3 E 2.0 E 6.5 E 3.6 E 4.3 E 4.9 E 3.2 E

- - 4 . I E 7.4 E 1 1 3 1 * 1 * 4 2 * 2 * 2 * 1 * 2 * 2 * 2 * 2 * 2 * 1 * 1 * 2 * 1 * 2

1 * 2 * Propose d !R Q (Ci )

1

## ! i ° ! 1 0 

### ! io o

: 1 0

• 1 0 1

• 10 0 10 0 10 0 1 0 

### ! io o i : 10 0 1 ; 10 0

, 10 0

: 10 0 ; 1 0 1 0 10 0 

## 1° 0.0 1 1 1 0 ,10 0 1EXHIBI T 4- 5 (Continued )

- - Releas e Value s (Ci ) P.4 9

Radionuclid e

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 Atom . No .

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 Half- 1

3 6 1.8 0 1.7 2 11.7 6 15.3 1 6.24 3 32. 2 3.0 E 6 5.0 1 60. 6 45. 6 19. 9 41. 5 25. 3 9 8 16. 1 57. 0 4.4 2 17. 6 35. 3 2.3 9 31. 8 5 8 6. 5 Lif e

mi n hr hr hr da y da y yr yr da y mi n mi n mi n mi n mi n mi n h r h r h r mi n h r h r mi n mi n h r Ingestio n

(water )

8 . I E 2.7 E 2.7 E 5.4 E 2.7 E 1.6 E 2.7 E 1.1 E 2.2 E 1.4 E 1.9 E 5.4 E 7.7 E 1.5 E 2.3 E 3 . I E 1.5 E 1.5 E 3.8 E 2.3 E 3.8 E 1.5 E 2.7 E 2.7 E 3 3 3 2 2 2 2 1 2 3 3 3 2 3 3 2 3 # # # # # 3* # 3 2 # # 3* # 3 4 4 # Inha

latio n

4 . I E 1.6 E 2 . I E 3 . I E 5.2 E 4.7 E 2 . I E 3.6E

1.6 E 1.0 E 1.6 E 4.I E 2 . I E 3.6 E 2.6 E 2 . I E 1.0 E 5.2 E 1.0 E 2 . I E 3 . I E 3 . I E 3.6 E 2.6 E 4 4 4 3 2 2 2 •1 * 1 * 2 * 2 * 2 4 4 4 3 4 3 5 3 4 4 4 4 Direct Exposur e

1.7 E 5.I E LI E 2.2 E 4.3 E 1.2 E 2.5 E 1.5 E 1.3 E 3.5 E

- - 2.7 E 1.3 E 2.4 E 3.2 E 1.8 E 1.3 E

- - 7.0 E 1.4 E 5.0 E 2.2 E 1.6 E 5.6 E 1 * 1 * 2 * 1 * 1 * 1 * 1 * 2 8 2

1 * 1 * 1 * 1 * 1 * 2 *

2 * 1 * 3 1 * 2 * 3 * Proposed RQ (Ci )

1 0 1 0 10 0 1 0 1 0 1 0 1 0 0. 1 1 0 10 0 10 0 1 0 1 0 1 0 1 0 1 0 10 0 100 0 10 0 1 0 100 0 1 0 10 0 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 0

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 Half-Lif e

462. 3 da y 13. 7 y r 1.3 E 1 5 y r 44. 6 da y 53. 5 h r 3. 4 h r 2.4 9 h r I E 5 y r 163. 8 da y 4.53 6 da y 19. 4 mi n 3 6 h r 33 4 da y 35 1 y r 13. 1 y r 89 0 y r 2.6 4 y r 17. 8 da y 60. 5 da y 20. 3 mi n 573 0 y r 7 6 h r 17. 8 h r 34. 4 h r Ingestio n

(water )

4.0 E 2.7 E 2.7 E 4.0 E 1.2 E 6.7 E 6.7 E 1.2 E 8 . I E 3.2 E 2.3 E 3 . I E 1.5 E 7.7 E 2.3 E 7.7 E 4.6 E 4.6 E 2.3 E 3.8 E 1.5 E 2.7 E LI E 1.1 E 2 1 1 2 3 3 3 3 * 2 2 3* # 1* # 0 # 2 #

• 1 #

• 2 #

- 1 # 1 #

• 1 # 4 2 4 5 5 Inha

latio n

2.I E 1 * l'.O 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

LI E 4 6.9 E 5

- - LI E 3 9.8 E 1 * 1.4 E 1 * 4.2 E 1 *

- -

- - 3.3 E 1 *

- - 2.7 E 6

- - 1.2 E 2

- -

- - 3.6 E 6

- -

- - 3.6 E 1 *

- - 1.2 E 3 5.I E 1 * 1.1 E 3 * Proposed

RQ (Ci )

1 0 1 1 1 0 1 0 1 0 1 0 100 0 10 0 1 0 100 0 1 0 0. 1 0.0 1 0.0 1 0.0 1 

### o. i 1 0 0. 1 1 0 1 0 10 0 1 0 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 1

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-13 4 Cesium-13 4 Cesium-135ra 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 5 5 1 7 1 7 1 7 2 4 2 4 2 4 Half-Lif e

9. 0 hr 14 0 da y 32. 5 da y 33. 0 hr 284. 4 da

y 4 5 mi n 6. 2 hr 32. 3 hr 29. 2 mi n 9.6 9 da y 6.4 7 da y 2.9 1 hr 2.06 5 y r 5 3 mi n 3 E 6 yr 13. 1 da y

, 30.1 7 y

r 32. 2 mi n 3 E 5 yr 37. 2 mi n 55. 7 mi n 21. 6 h r 42. 1 mi n 27.7 0 da

y Ingestio n (water )

2.7 E 2.7 E LI E 5.4 E LI E 2.7 E 3.2 E 1.1 E 3.2 E LI E 1.6 E 5.4 E 3.8 E 5.4 E 3.8 E 2.2 E 5.4 E 1.1 E 1.5 E 1.5 E 1.5 E 4.6 E 2.3 E 3. . I E 6 5 5 4 4 6 6 6 6 6 5 6 3 6 4 4 3 6 2 3 3 2 # 3 # 3 # Inha

lation

5.2 E 3.6 E 3 . I E 1.0 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 . I 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 Direc t Exposur e

3 . I E 2.7 E 5.2 E 1.5 E 2.3 E 1.4 E 1.2 E 1.5 E 8.7 E

- - 5.4 E 2.2 E 2.3 E 2.3 E

- - 1.9 E 6.5 E 1.6 E

- - 2.6 E 2.5 E 8.7 E 4.I E 1.1 E 3 * 2 * 1 * 2 * 3 2 * 2 * 2 * 2 *

1 * 3 * 1 * 1 *

1 * 1 * 1 *

1 * 1 * 1 * 2 * 3 * Propose d R Q (Ci )

100 0 10 0 1 0 10 0 1 10 0 10 0 10 0 10 0 100 0 1 0 100 0 1 0 1 0 10 0 1 0 1 0 1 0 10 0 1 0 1 0 1 0 10 0 100 0EXHIBI T 4- 5 (Continued )

- Releas e Value s (Ci ) P.5 2

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 2 7 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 Half-Lif e

17. 5 h r 77. 7 da y 27 1 da y 9. 1 h r 70.9 1 da y 10.4 8 mi n 5.27 2 y r 1.6 5 h r 13. 9 mi n 23. 2 mi n 3.4 1 h r 12.70 1 h r 61. 9 h r 2. 4 h r 2 7 da y 32. 8 da y 162. 5 da y 28. 5 y r 18.1 1 y r 8.5 E 3 y r 4.78 E 3 y r 1.56 E 7 y r 3.4 E 5 y r 64.1 5 mi n Ingestio n

(water )

5.4 E 2.2 E 2.2 E 3.2 E 5.4 E 5.4 E 1.1 E 1.1 E 2.2 E 2.3 E 7.7 E 7.7 E 3.8 E 2.7 E 1.3 E 1.3 E 8 . I E 2.7 E 2.7 E 1.3 E 1.3 E 1.3 E 5.4 E 6.7 E 4 4 5 6 4 7 4 6 6 3 # 2 # 2* # 2 # 5 3 4 2 1 1 1 1 1 0 5 Inha

lation

1.6 E 1.0 E 3.6 E 3 . I E 3.6 E 1.6 E 1.6 E 3 . I E 1.0 E 4.7 E 1.6 E 1.0 E 2.6 E 5.2 E 2.6 E 1.0 E 1.6 E 4.1E

5.2E

2.6E

2.6E

3.1E

5.2E

1.0 E 4 3 3 5 * 3 7 2 5 6 4 4 4 3 3 * 0 * 2 0 *

• 2 * •2 *

• 2 * •2 * •2 *

• 3 * 5 Direc t Exposur e

3 . I E 1.1 E 3.0 E 4.2 E 4.4 E 3 . I E 1.4 E 4.0 E 1.4 E 2.3 E 1.7 E 4.5 E 3.2 E

- -

- - 9.4 E 1.0 E 5.0 E 1.4 E 1.7 E

- - 1.2 E

- - 2.0 E 1 * 1 * 2 * 6 1 * 4 * 1 * 2 * 1 * 1 * 2 * 3 2 *

1 * 7 2 7 3

2

3 * Propose d R Q (Ci )

1 0 1 0 10 0 100 0 1 0 100 0 1 0 10 0 1 0 1 0 10 0 10 0 10 0 100 0 1 1 0 1 0.0 1 0.0 1 0.0 1 0.0 1 0.0 1 0.00 1 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) - • P.5 3

Radionuclid e
Dysprosium-15 5 Dysprosium-15 7 Dysprosium-15 9 Dysprosium-16 5 Dysprosium-16 6 Einsteinium-25 0 Einsteinium-25 1 Einsteinium-25 3 Einsteinium-254 m Einsteinium-25 4 Erbium-16 1 Erbium-16 5 Erbium-16 9 Erbium-17 1 Erbium-17 2 Europium-14 5 Europium-14 6 Europium-14 7 Europium-14 8 Europium-14 9 Europium-15 0 (12. 6 hr ) Europium-15 0 (34. 2 yr ) Europium-152 m Atom . No .

6 6 6 6 6 6 6 6 6 6 9 9 9 9 9 9 9 9 9 9 6 8 6 8 6 8 6 8 6 8 6 3 6 3 6 3 6 3 6 3 6 3
6 3
6 3 Half-Lif e

1 0 8. 1 14 4 2.3 3 81. 6 8. 6 1.3 8 20.4 7 1.6 4 27 5 3.2 4 10.3 6 9. 4 7.5 2 2.0 5 5.9 3 4.5 8 24. 3 54. 5 93. 1 12. 6
3 6
9. 3 hr hr da y hr hr 

### h r da y da y da y da y hr hr da y hr da y da y da y da y da y da y h r
yr 

### h r Ingestio n

(water )

6.9 E 1.5 E 7.7 E 7.7 E 4.6 E 3.8 E 5.4 E 1.5 E 2.3 E 1.5 E 1.5 E 4.6 E 2.3 E 3 . I E 7.7 E 2.7 E 1.3 E 4.0 E 1.3 E 1.3 E 4.0 E

LI E
4.0 E 2 # 3 # 2 # 2* # 1* # 3 # 2* # 1 # 1 # 0 # 3 # 3* # 2* # 2 # 1 # 4 4 4 4 5 4
4
4 Inha

lation

1.6 E 3.I E 1.0 E •2.6 E 3.6 E 3.6 E 5.2 E 1.0 E 5.2 E 5.2 E 3 . I E 1.0 E 1.6 E 5.2 E 5.2 E 1.0 E 5.2 E 1.0 E 2 . I E 1.6 E 4 . I E
1.0 E
3 . I E 4 4 3 4 2 3 3 1 * 0 * -1 * 4 5 3 3 2 3 2 3 2 3 3
1 *
3 Direc t Exposur e

9.8 E 1.2 E 1.2 E 2.3 E 2.5 E 3.6 E

- - 2 . I E 7.9 E 7.6 E 6.3 E

- - 2.3 E LI E 7.2 E 3.0 E 1.9 E 8.7 E 1.9 E 1.2 E LI E 2.8 E
1.3 E 1 * 2 * 2 * 3 3 1 *

5 1 4 1 *

7 2 * 1 * 1 * 1 * 1 * 1 * 3 * 3 *
1
2 * Proposed R Q (Ci )

1 0 10 0 10 0 10 0 1 0 1 0 10 0 1 0 1 0. 1 1 0 100 0 10 0 10 0 1 0 1 0 1 0 1 0 1 0 100 0 100 0
1 0
10 0P.5 4

EXHIBI T 4- 5 (Continued )
Releas e Value s (Ci )

Radionuclid e
Europium-15 2 Europium-15 4 Europium-15 5 Europium-15 6 Europium-15 7 Europium-15 8 Fermium-25 2 Fermium-25 3 Fermium-25 4 Fermium-25 5 Fermium-25 7 Fluorine-1 8 Francium-22 2 Francium-22 3 Gadolinium-14 5 Gadolinium-14 6 Gadolinium-14 7 Gadolinium-14 8 Gadolinium-14 9 Gadolinium-15 1 Gadolinium-15 2 Gadolinium-15 3 Gadolinium-15 9 Gallium-6 5 Atom . No .

6 3 6 3 6 3 6 3 6 3 6 3 10 0 10 0 10 0 10 0 10 0 9 8 7 8 7 6 4 6 4 6 4 6 4 6 4 6 4 6 4 6 4 6 4 3 1 Half-Lif e

13. 4 8. 5 4.7 3 15. 2 15.1 5 4 6 25. 4 3 3.2 4 20. 1 100. 5 109. 8 14. 4 21. 8 2 3 48. 3 38. 1 7 5 9. 3 12 0 LI E 1 4 241. 6 18. 6 15. 2 y r y r y r da y hr mi n hr da y hr hr da y mi n mi n mi n mi n da y h r y r da y da y y r da y 

### h r mi n Ingestion

(water )

LI E 6.7 E 5.4 E 8 . I E 2.7 E 2.7 E 3.8 E 7.7 E 2.3 E 3.8 E 3.8 E 3.8 E LI E 3.2 E 6.7 E 1.3 E 2.7 E 1.3 E 4.0 E 8 . I E 2.7 E 6.7 E 4.0 E 3.8 E 4 3 4 3 4 5 1* # 1 # 2* # 1* # 0 # 3* # 4 3 5 4 4 2 4 4 2 4 4 3 # Inha

latio n

1.0 E 1.0 E 4.7 E 2.6 E 2.6 E 3 . I E 5.2 E 5.2 E 5.2 E 1.0 E 1.0 E 3.6 E 2.6 E 4 . I E 1.0 E 5.2 E 2 . I E 4.1E

1.0 E 2 . I E 5.2E

5.2 E 3 . I E 1.0 E 1 * 1 * 1 * 2 3 4 1 1 * 2 2 0 * 4 2 * 2 * 5

1 * • 3 3 * 3 2 * 3 * 1 * 3 5 Direc t Exposur e

3.5 E 1 4.2 E 1 7.0 E 2 2.3 E 1 * 3.0 E 1 * 4.6 E 1 *

- - 4.9 E 3

- -

- - 8.6 E 2

- -

- - 1.2 E 3 1.9 E 1 * 2 . I E 2 3.5 E 1 *

- - LI E 2 * 1.4 E 3

- - 7.0 E 2 9.3 E 2 * 8.7 E 1 * Proposed

RQ (Ci )

1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 10 0 1 0 1 100 0 10 0 10 0 1 0 1 0 1 0 0.00 1 10 0 10 0 0.00 1 1 0 10 0 1 0 

# KEXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 5

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 Half-Lif e

9. 4 h r 78.2 5 h r 68. 1 mi n 21. 1 mi n 13.9 5 h r 4.8 7 h r 2.2 7 h r 19. 0 mi n 28 8 da y 39. 1 h r 11. 2 da y 82. 8 mi n 11.3 0 h r 1.4 5 h r 17. 6 h r 39. 5 h r 186. 1 da y 2.3 0 da y 2.69 3 da y 3.1 4 da y 18. 7 h r 48. 4 mi n 2 6 mi n 16. 0 h r Ingestio n

(water )

7.7 E 5.4 E 1.5 E 3.8 E 7.7 E 3.8 E 1.5 E 2.3 E 3.8 E 7.7 E 3.8 E 3 . I E 6.9 E 1.5 E 6.9 E 2.3 E 3.8 E 7.7 E 7.7 E 2.3 E 7.7 E 2.3 E 5.4 E 2.3 E 1 2 3 # # # 3* # 1 2 3 3 2 2 4 3 2 3 2 2 2 1 # # # # # # # # # # # # # # 1* # 2* # 1 3 3 2 # # # # Inha

latio n

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..0E 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

2.6 E 2.2 E LI E 6.9 E 2 . I E 2.0 E LI E 1.0 E

- - 4.I E

- - 1.2 E 5.0 E 1.3 E 5.6 E 4.7 E

- - 7.6 E 9.0 E 4.8 E 1.8 E 1.5 E LI E 8.7 E 1 * 2 * 3 * 3 1 * 2 * 2 * 2 *

1 *

3 * 1 * 2 * 2 * 1 *

1 * 1 2 1 * 2 * 3 * 1 * Proposed RQ (Ci )

1 0 10 0 100 0 100 0 1 0 10 0 10 0 10 0 1 0 1 0 100 0 100 0 1 0 10 0 10 0 1 0 10 0 1 0 1 0 10 0 1 0 10 0 100 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) - • P.5 6

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 Half-Lif e

1.8 7 y r 23. 6 h r 7 0 da y 1.0 8 se c 4. 0 se c 18. 7 se c 5.51 9 h r 42. 4 da y 6 2 mi n 9 E 6 y r 64 mi n 4. 1 h r 4 8 mi n 12. 6 mi n 3 3 mi n 2. 5 h r 6 8 mi n 1 5 mi n 37. 5 mi n 2 9 mi n 1.2 E 3 y r 1.11 7 da y 3. 1 h r 12.2 6 y r Ingestio n

(water )

7.7 E 3.8 E 2.3 E 1.5 E 2.3 E 7.7 E 5.4 E 7.7 E 3 . I E 1.5 E 1.5 E 1.5 E 6.5 E 4.8 E 3.2 E 1.6 E 8 . I E 8 . I E 1.6 E 3.2 E 9.7 E 1.5 E 3.2 E 6 . I E 1 # 2 # 2 # 3 # 1 # 1* # 2 # 1 # 3 # 1 # 3 # 2* # 5 6 6 6 5 6 6 6 3 4 5 3 Inha

latio n

4.7 E 5.2 E 4.7 E 3 . I E 5.2E

1.6 E 1.0 E 1.0 E 4.7 E 4.1E

2.6 E 3 . I E 1.0 E 5.2 E 5.2 E 2.I E 1.6 E 1.0 E 1.6 E 3 . I E 3.6 E 1.0 E 3 . I E 8.3 E 0 * 3 2 4 1 * 2 4 2 4 1 * 4 3 5 5 5 5 5 6 5 * 5 0 * 3 * 4 2 * Direc t Exposur e

1.5 E 1.2 E 1.2 E 3.8 E 3.8 E 1.7 E 3.8 E 7.3 E 4 . I E 1.6 E 5 . I E 1.6 E 3.7 E 1.2 E 1.8 E 6.8 E 7.6 E 5.5 E 2.6 E 1.0 E 2.2 E 1.6 E LI E 3 2 * 2 * 1 * 1 2 1 * 1 * 1 * 2 1 * 2 2 * 2 * 2 * 3 * 1 * 2 * 5 4 * 1 3 2 * Proposed R Q (Ci )

1 10 0 10 0 1 0 0. 1 1 0 1 0 1 0 1 0 0. 1 1 0 10 0 10 0 10 0 10 0 100 0 1 0 10 0 100 0 100 0 1 100 0 10 0 10 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 7

Radionuclid e

Indium-10 9 Indium-11 0 (69. 1 min ) Indium-11 0 (4. 9 hr ) Indium-11 1 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 Half-Lif e

4. 2 h r 6 9 mi n
4. 9 h r
2.80 6 da y 14. 4 mi n 1.65 7 h r 49.5 1 da y 4.48 6 h r 4.4 E 1 4 y r 54. 1 mi n 1.93 3 h r 43. 1 mi n 18. 0 rain 5 3 mi n 1.3 5 h r 1. 8 h r 13. 1 h r 4.1 7 da y 59. 9 da y 1 3 da y 25.0 0 mi n 1.6 E 7 y r 12.3 6 h r Ingestio n

(water )

1.5 E 1.5 E
3.8 E
3 . I E 1.5 E 3.8 E 2.3 E 7.7 E 3 . I E 1.5 E 7.7 E 4.6 E 3 . I E 8,2 E 3.3 E 8.2 E 2.5 E 4 . I E 3.3 E 1.6 E 3.3 E 4.1E

3.3 E 3 3
2
2 4 3 # # # # # # 1* # 2 0 3 2 3 3 2 2 2 2 0 0 0 3 1 1 # # # # # # 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

LI E 4.7 E
1.3 E
9.5 E 8.6 E 1.4 E 4.8 E 2.3 E

- - 1.8 E 6.0 E 5.3 E 1.6 E 1.3 E 4.0 E 1.7 E 2.5 E 4.9 E

- - 9.8 E 4.3 E

- - 1.7 E 2 * 1 *
1 *
1 * 2 * 2 * 2 2 *

1 * 1 * 1 * 3 * 1 * 1 * 2 * 2 1

1 2 *

1 Proposed R Q (Ci )

10 0 1 0
1 0
1 0 10 0 10 0 1 0 10 0 0. 1 1 0 1 0 1 0 100 0 1 0 1 0 10 0 1 0 0. 1 0. 1 0. 1 10 0 0.0 1 1EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 8

Radionuclid e

Iodine-13 1 Iodine-132 m Iodine-13 2 Iodine-13 3 Iodine-13 4 Iodine-13 5 Iridium-18 2 Iridium-18 4 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-194 Iridium-195 m Iridium-19 5 Iron-5 2 Iron-5 5 Iron-5 9 Atom . No .

5 3 5 3 5 3 5 3 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 Half-Lif e

8.04 0 da y 8 3 mi n 2. 4 h r 20. 8 h r 52. 5 mi n 6.58 5 h r 1 5 mi n 3. 0 h r 1 4 h r 15. 7 h r 10. 5 h r 41. 4 h r 13. 2 da y 1. 2 h r 11. 8 da y 1.4 4 mi n 73.8 3 da y 17 1 da y 19. 2 h r 3. 9 h r 2. 8 h r 8.2 8 h r 2. 7 yr 44.5 1 da y Ingestio n

(water )

2.5 E 3.3 E 3.3 E 8.2 E 1.6 E 6.6 E 3 . I E 6 . I E 3.8 E 1.5 E 7.7 E 1.5 E 3.8 E 1.5 E 7.7 E 2.3 E 6.9 E 4.6 E 7.7 E 6 . I E 7.7 E 3.6 E 3.6 E 3.2 E 0 2 2 0 3 1 3 # 2 # 2 # 2 # 2 # 2 # 2* # 4* # 1 # 2 # 1 # 1 # 1* # 2 # 2* # 3 4 3 Inha

latio n

5.2E

8.3 E 8.3 E 3 . I E 5.2 E 2 . I E 5.2 E 1.0 E 5.2 E 3 . I E 1.6 E 1.6 E 2 . I E 1.0 E 4.7 E 1.0 E 1.0 E 4.7 E 1.0 E 1.0 E 2 . I E 1.0 E 1.0 E 1.6 E 1 * 1 1 * 0 * 2 1 * 5 5 4 4 5 4 4 6 3 2 * 3 2 4 5 5 3 3 * 2 Direc t Exposur e

9.6 E 1.7 E 2 . I E 3.8 E 1.5 E 2.4 E 7.I E 2.9 E 7.8 E 3.3 E 1.8 E 2.2 E 1.8 E

- - 3.3 E 9.7 E 4.7 E 1.6 E 4.7 E 1.3 E 2.5 E 2.2 E

- -

' 3 . I E 1 1 * 2 1 1 * 1 1 * 1 * 1 * 1 * 2 * 1 * 3

1 * 5 1 * 1 * 2 2 * 3 2 *

1 * Propose d R Q (Ci )

0. 1 1 0 1 0 1 1 0 1 0 1 0 1 0 1 0 1 0 10 0 1 0 10 0 100 0 1 0 10 0 1 0 1 0 1 0 10 0 10 0 10 0 100 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.5 9

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-1 3 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 3 6 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 Half-Lif e

3 E 5 y r 11. 5 mi n 14. 8 h r 1.2 4 h r 35. 0 h r 2.I E 5 y r 1.8 6 h r 4.4 8 h r 10.7 2 y r 76. 3 mi n 2.8 4 h r 5 9 mi n 4. 8 h r 19. 5 h r 6 E 4 y r 1.06 E 1 1 y r 40.2 8 h r 3.9 3 h r 9 2 mi n 14. 1 mi n 1 5 mi n 2. 4 h r 1. 5 h r 21. 5 h r Ingestio n

(water )

1.2 E 2
na na na na na na
na na na
na 3.8 E 3 2.3 E 2 #

# 3.I E 3* # 7.7 E 2 6.9 E 1 4.6 E 1 #

# # 3.I E 2* # 6 . I E 2 3 . I E 3 6.5 E 6 3.2 E 6 2.2 E 6 3.2 E 5 #

# Inha

latio n

3.I E 0 *
na na na na na na na
na na
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 8.9 E 4.0 E 2.0 E 6.9 E 9.9 E 2.0 E 9.9 E 5.0 E 2.0 E 1.5 E 2.9 E 3.9 E

- - 3.0 E 1.6 E 1.5 E 2 . I E 6.6 E 3.3 E LI E 4.8 E 3.3 E 2 1*4

- 1*4

- 1* + 2* + 3*4

- 4*4

- 2*4

- 2*4

- 1*4

- 1*4

- 2 * 1 * 3

1 1 * 3 1 * 2 * 1 * 2 * 1 * 2 * Propose d R Q (Ci )

1 1 0 1 0 1 0 10 0 100 0 100 0 10 0 10 0 1 0 1 0 10 0 1 0 100 0 1 0 1 1 0 10 0 1 0 10 0 1 0 10 0 1 0 10 0P.6 0 

# I 8 1 EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci )

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 Half-Lif e

9.3 3 h r 3.6 2 h r 5.3 E 4 y r 52. 1 h r 1.51 E 7 y r 3.2 5 h r 22. 3 y r 36. 1 mi n 10.6 4 h r 26. 8 mi n 1.41 9 da y. 2.0 1 da y 8.2 4 da y 6.7 0 da y 1.3 7 y r 14 2 da y 3.3 1 y r 3.6 3 h r 3.6 E 1 0 y r 16 0 da y 6.7 1 da y 2 3 mi n 28. 5 mi n 4. 6 h r Ingestio n

(water )

7.5 E 9.7 E LI E 5.4 E 4.3 E 2.2 E 6.5 E LI E 8.6 E 9.7 E 2.3 E 7.7 E 1.5 E 7.7 E 3.8 E 1.5 E 3.8 E 6 . I E 5.4 E 5.4 E 1.5 E 3.8 E 3 . I E 4.6 E 5 5 4 5 5 6 1 6 3 5 2 # 1 # 2 # 1 # 2 # 2 # 2 # 2* # 1 # 1 # 2* # 3 # 3 # 2* # Inha

lation

1.0 E 1.6 E 2.6 E 4.7 E 5.2 E 3 . I E 1.0 E 3 . I E 1.6 E 4.I E 2 . I E 1.0 E 1.0 E 5.2 E 1.6 E 1.0 E 5.2 E 1.0 E 2.6 E 4.I E 1.0 E 1.0 E 5.2 E 1.0 E 4 4 1 * 3 2 * 4 * •1 * 2 * 1 * 2 3 3 3 2 2 * 2 * 1 * 4 0 * 1 3 5 4 4 Direct Exposur e

6.4 E 1.9 E

- - 1.5 E

- -

- -

- - 6.7 E 3.2 E 1.7 E 6 . I E 2 . I E 6.7 E 2.2 E 6.8 E 4.3 E 4.3 E 4.6 E 7.8 E 4.0 E 1.2 E 8.3 E 3.6 E 1.4 E 1 * 1 *

2 *

2 2 2 * 1 * 1 * 1 * 1 * 2 3 2 3 1 1 * 3 2 * 2 * 3 Propose d R Q (Ci )

1 0 1 0 1 0 10 0 10 0 100 0 0. 1 10 0 1 0 10 0 1 0 

### i o 1 0 1 0 10 0 10 0 1 0 10 0 1 1 0 10 0 10 0 10 0 10 0

\P.6 1

Pag e No . 12/19/8 6 1 6 Releas e Value s (Ci )

Radionuclid 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-93 m Molybdenum-9 3 Molybdenum-9 9 Molybdenum-10 1 Neodymium-13 6 Atom . No . Half-Lif e

1 2 2 5 2 5 2 5 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 21. 0 hr

46. 2 mi n 21. 1 mi n 5.5 9 da y 3.7 E 6 y

r 31 2 da y 2.57 9 hr 5. 2 hr 5 6 da y 11. 8 hr 3. 8 hr 52 0 yr 40. 0 h r 9. 5 hr 23. 8 hr 64. 1 hr 42. 6 mi n 46. 6 da y 5.6 7 hr 6. 9 hr 3.5 E 3 yr 65.9 4 hr 14. 6 mi n 50. 7 mi n Ingestion

(water )

5.4 E 1 # 1.5 E 3* # 2.3 E 3 # 5.4 E 1 # 3.8 E 3* # 1.5 E 2 # 3.8 E 2 # 6.9 E 2 # 5.4 E 0 # 2.3 E 2 # 1.5 E 3 # 1.5 E 0* # 1.5 E 2* # 7.7 E 2 # 2.3 E 2* # 4.6 E 2* # 4.6 E 3 # 3.8 E 1* # 2.7 E 2 5.5 E 2 5.5 E 2 1.4 E 2 * 5.5 E 3 1.3 E 5 Inha

lation

5.2 E 2 2.6 E 4 4.7 E 4 4.7 E 2 5.2 E 3 4 . I E 2 1.0 E 4 5.2 E 2 * 1.6 E 0 * 4 . I E 3 1.6 E 4 1.6 E 1 2.I E 3 1.6 E 4 2.6 E 3 4 . I E 3 4 . I E 4 4 . I E 2 2.6 E 3 5.2 E 3 1.0 E 2 * 5.2 E 2 5.2 E 4 2.6 E 4 Direc t

Exposur e

2.6 E 1 * 6.9 E 3 2.6 E 1 * 1.6 E 1 *

4.4 E 1 * 2.2 E 1 *

2.9 E 1 * 5.I E 1 *

2 . I E 2 3.0 E 2 * 7.9 E 2 2.4 E 3 2.7 E 2 * 1.6 E 2 4.7 E 1 * 1.6 E 1 *

1.5 E 2 6.5 E 1 * 2.6 E 2 * Proposed

RQ (Ci )

1 0 100 0 1 0 1 0 100 0 1 0 1 0 10 0 1 1 0 1 0 1 10 0 10 0 10 0 10 0 10 0 1 0 1 0 1 0 10 0 10 0 1 0 10 0EXHIBI T 4- 5 (Continued )
Releas e Value s (Ci ) P.6 2

Radionuclid e
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 Atom No .

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
9 3 9 3 9 3 9 3 2 8 2 8 2 8 2 8 2 8 2 8 Half-Lif e

2 2 mi n 5. 1 hr 3 0 mi n 2. 5 hr 10.9 9 da

y 1.7 3 hr 12. 4 mi n 14. 7 mi n 36. 2 mi n 4. 4 da y 1.0 8 yr 1.2 E 5 yr 22. 5 hr 2.14 E 6 yr 2.11 7 da

y 2.3 5 da y 1.0 3 hr 6.1 0 da y 36. 1 hr 9 E 4 y r 10 0 yr 2.5 2 hr 54. 8 h r Ingestion

(water )

2.7 E 4 6.7 E 4 1.2 E 6 2.7 E 6 1.3 E 4 1.3 E 5 9.4 E 5 8 . I E 3 2.2 E 5 5.4 E 2 2.7 E 3 * 1.1E-1 *
1.4 E 2 *
1.9E-2 * 2.2 E 2 5.4 E 2 5.4 E 3 2.7 E 3 5.4 E 3 5.4 E 4 2.4 E 4 2.2 E 4 1.1 E 3 Inha

lation

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
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 * Direc t

Exposur e

3.3 E 3 3.2 E 1 * 3.8 E 2 * 1.7 E 3 * 3.0 E 2 * 8.I E 1 * 5.8 E 1 * 3.6 E 1 * 5.3 E 3 * 3.6 E 1 *

- - 6.9 E 2
4.8 E 3
2.6 E 3 5.8 E 1 * 3.4 E 2 * 3.3 E 1 * 2.I E 1 * 2.4 E 1 *

- -

- - 6.8 E 1 *

__ Proposed

RQ (Ci )

100 0 1 0 10 0 100 0 10 0 1 0 1 0 1 0 100 0 1 0 100 0 0. 1
10 0
0.0 1 1 0 10 0 1 0 1 0 1 0 100 0 100 0 1 0 10 0EXHIBI T 4- 5 (Continued )

- - Releas e Value s (Ci ) P.6 3

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 Niobium-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 Half-Lif e

14. 3 6 6
12 2
14. 6 13. 6 2.4 E 4 3.6 1 34.9 8 23.4 73. 6 2. 8 21. 7 1.7 5 21. 5 93. 6 5. 8 13. 1 15. 4 31. 1 6. 0 3. 6 8. 4 16.9 7 mi n mi n mi n hr y r y r da y da y 

### h r mi n se c mi n h r hr da y hr h r da y hr y r da y h r da y Ingestio n (water )

2.7 E 5.4 E
2.7 E
5.4 E 4.8 E 4.8 E 1.1 E 1.1 E 5.4 E 1.1 E 5.4 E 7.7 E 7.7 E 1.5 E 1.5 E 6 . I E 7.7 E 1.5 E 1.5 E 3 . I E 1.3 E 1.3 E 8 . I E 6 5
5
4 5 4 5 5 4 6 5 3* # 2 # 2 # 2 # 3* # 2* # 2* # 2* # 1 # 3 4 3 Inha

latio n

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

LI E 2.0 E
9.9 E
9 . I E

- - 2.3 E 5.5 E 4.8 E 1.6 E 5.5 E 5.5 E

- - 4.7 E 9.7 E 5.5 E

- - 7.0 E LI E 8.6 E

- - 2 . I E 1.6 E 4.0 E 1 * 1 *
1 *
0 *

1 2 * 1 * 1 * 1 * 2 *

1 * 1 * 1 *

5 3 2

2 * 2 * 5 Propose d R Q (Ci )

1 0 1 0
1 0
1 10 0 1 0 10 0 1 0 1 0 1 0 10 0 100 0 1 0 1 0 1 0 100 0 10 0 10 0 10 0 1 10 0 10 0 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.6 4

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 1 5 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 Half-Lif e

6.5 E 6 y r 13.4 7 h r 14.2 8 da y 25. 3 da y 2. 0 h r 10. 2 da y 10. 9 h r 2.9 6 da y 4.3 3 da y 5 0 y r 4.0 2 da y 95.4 mi n 18. 3 h r 30. 8 mi n 12. 5 h r 8. 8 h r 25. 6 mi n 2.8 5 y r 45. 1 da y 87.74 y r 2.411 E 4 y r 6.537 E 3 y r 14. 4 y r 3.76 E 5 y r Ingestio n

(water )

4.0 E 2.7 E 4.6 E 4.6 E 7.7 E 1.5 E 7.7 E 3 . I E 2.3 E 3 . I E 1.5 E 1.5 E 2.3 E 3.8 E 7.7 E 2.4 E 2.4 E 5.4 E 2.7 E 1.9 E 1.6 E 1.6 E 8 . I E 1.9 E 4 3 1 # 2 # 2 # 2* # 2 # 2 # 2* # 3* # 2* # 3 # 2* # 3 # 1* # 4 6 * 1 4 1 1 1 2 1 Inha

lation

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

9.0 E 3

- -

- - 4.8 E 1 * 3.0 E 2 2.2 E 2 * 1.9 E 2 * 2.4 E 5

- - 2.5 E 3 9.5 E 2 * 4.8 E 3 2.I E 2 * 1.9 E 3

- -

- -

- -

- -

- - 1.7 E 6 5.0 E 6 1.4 E 8 4 . I E 6 Proposed

RQ (Ci )

10 0 100 0 1 1 0 1 0 10 0 10 0 10 0 10 0 100 0 10 0 10 0 10 0 10 0 1 0 100 0 100 0 0. 1 100 0 0.0 1 0.0 1 0.0 1 1 0.0 1EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.6 5

Radionuclid e

Plutonium-24 3 Plutonium-24 4 Plutonium-24 5 Polonium-20 3 Polonium-20 5 Polonium-20 7 Polonium-21 0 Potassium-4 0 Potassium-4 2 Potassium-4 3 Potassium-4 4 Potassium-4 5 Praseodymium-13 6 Praseodymium-13 7 Praseodymium-138 m Praseodymium-13 9 Praseodymium-142 m Praseodymium-14 2 Praseodymium-14 3 Praseodymium-14 4 Praseodymium-14 5 Praseodymium-14 7 Promethium-14 1 Promethium-14 3 Atom . No .

9 4 9 4 9 4 8 4 8 4 8 4 8 4 1 9 1 9 1 9 1 9 1 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 5 9 6 1 6 1 Half-Lif e

4.9 5 8.2 E 7 10. 5 34. 8 1. 8 5.8 3 138. 4 1.25 E 9 12.3 6 22. 3 22. 1 17. 3 13. 1 7 7 2. 1 4.4 1 14. 6 19.1 3 13.5 8 17. 3 5.9 8 13. 4 20. 9 26 5 hr yr hr mi n hr hr da y yr h r hr mi n mi n mi n mi n h r h r mi n 

### h r da y mi n h r mi n mi n da y Ingestio n (water )

5.4 E 1.9 E 5.4 E 2.0 E 1.3 E 5.4 E 2.0 E 2.8 E 4.7 E 5.7 E 1.9 E 2.8 E 6.7 E 5.4 E 1.3 E 5.4 E 1.1 E 1.3 E 1.2 E 4.0 E 4.0 E 6.7 E 8 . I E 8 . I E 4 1 3 4 4 3 0 2 3 3 4 4 5 5 5 5 6 4 4 5 4 5 5 4 Inha

latio n

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 Direc t

Exposur e

1.6 E

- - 1.6 E 3 . I E 3.0 E 3.I E 4.5 E 2.4 E 1.3 E 4 . I E 1.5 E 2.0 E 3.0 E 1.2 E 1.7 E 3.9 E

- - 6.2 E 4.9 E 1.3 E 3 . I E 6.2 E 5.6 E 1.3 E 3 *

2 * 1 * 1 * 1 * 6 2 2 * 1 * 1 * 1 * 1 * 3 * 1 * 2 *

2 * 8 3 * 3 * 1 * 1 * 2 * Propose d R Q (Ci )

100 0 0.0 1 10 0 1 0 1 0 1 0 0. 1 10 0 10 0 1 0 1 0 1 0 1 0 100 0 1 0 10 0 100 0 10 0 10 0 100 0 100 0 1 0 1 0 10 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) - • P.6 6

Radionuclid e Atom . Ingestio n Inha

- Direc t Propose d No . Half-Lif e (water ) latio n Exposur e R Q (Ci )

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 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 36 3

17. 7 5.5 3 2.62 3 41. 3 5.3 7 53. 1 2.6 9 28. 4 38. 3 2 2 17. 4 3.27 E 4 1.3 1 27. 0 6.7 0 11.4 3 3.6 6 14. 8 160 0 42. 2 5.7 5 55. 6 3.8 2 da y y r yr y r da y da y hr hr hr mi n hr da y yr da y da y hr da y da y da y y r mi n y r se c da y 1.6 E 1.6 E 3.2 E 6.5 E 1.1 E 6.5 E 1.6 E 8 . I E 3.2 E 4.3 E 1.1 E 6.5 E 2.2 E 1.1 E 1.1 E 2.2 E 1.3 E 2.2 E 2.2 E 5.4 E 5.4 E 5.4 E
na na 4 5 4 4 4 3 4 4 4 5 5 4 1 5 5 5 1 1 1 0 4 0 5.2 E

1.0 E 2 . I E 5.2 E 1.6 E 2.6 E 1.0 E 1.0 E 1.6 E 5.2 E 5.2 E 2 . I E 1.0E

1.0 E 3 . I E 3.6 E 3.6 E 1.0 E 3.6 E 3 . I E 5.2 E 5.2 E 1.0E

5.2E

1 2 * 1 * 1 * 2 2 3 * 4 3 2 * 1 1 * 2 * 2 3 4 0 * 1 * 0 * 0 * 4 0 * 1 * 1 * 2.4 E 2.8 E 5.0 E 9.5 E 1.8 E 6.5 E 3.4 E 3.0 E 1.6 E 1.9 E 4.8 E 6.3 E 1.8 E 4.0 E 2.3 E 2.8 E 4.5 E 3.8 E

- - 5.9 E 3.2 E

- -

- - 1.0 E 1 * 4 1 6 1 * 1 * 3 1 * 2 * 4 1 * 1 3 1 * 2 * 1 * 2 3

3 2 *

5 1 0 10 0 1 0 1 0 1 0 1 0 100 0 1 0 10 0 10 0 1 0 1 0 0.0 1 1 0 10 0 1 0 1 1 0 1 1 10 0 1 0. 1 0. 1EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.6 7

Radionuclid e

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-101 m Rhodium-10 1 Rhodium-102 m Rhodium-10 2 Rhodium-103 m Rhodium-10 5 Rhodium-106 m Atom . No .

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 Half-Lif e

14 mi n 13. 2 mi n 2 0 h r 12. 7 h r
64. 0 h r
16 5 da y 3 8 da y 2.0 E 5 h r 9 0 h r 4.5 E 1 0 y r 18. 7 mi n 16.9 8 h r 24 h r 4. 7 h r 16. 1 da y 20. 8 h r 4.3 4 da y 3. 3 y r 20 6 da y 2. 9 y r 56.1 2 mi n 35. 4 h r 2.1 8 h r Ingestio n

(water )

6.9 E 5.4 E 3.8 E 5.4 E

7.7 E
1.5 E 1.5 E 7.7 E 1.5 E 4.6 E 6 . I E 1.5 E 2.3 E 1.5 E 1.5 E 1.5 E 4.6 E 1.5 E 7.7 E 4.6 E 3 . I E 3 . I E 6 . I E 3 # 3 # 2 # 2 #

1 #
2* # 2 # 1* # 2* # 4* # 3 # 2* # 2* # 3 # 2 # 2 # 2 # 2 # 1 # 1 # 4* # 2* # 2 # Inha

lation

1.6 E 1.6 E 4.7 E 5.2 E
1.0 E

2 . I E 5.2 E 1.0 E 1.0 E 5.2 E 5.2 E 1.6 E 2 . I E 3 . I E 1.0 E 2 . I E 4 . I E 1.0 E 5.2 E 3 . I E 5.2 E 3 . I E 1.6 E 5 5 3 3
3
2 2 2 3 4 4 3 3 4 3 3 3 2 * 1 * 1 5 3 4 Direc t Exposur e

8.5 E 6.0 E 7.2 E 3.8 E
2.2 E
2.I E 4.4 E 3.3 E 2.7 E

- - 2 . I E 8.2 E 8.4 E 6.4 E 8.5 E 1.4 E 1.3 E 1.3 E 8.4 E 1.4 E

- - 4.7 E 1.3 E 1 * 1 * 1 * 1 *
1 *
2 1 * 3 3

3 * 2 2 1 * 1 * 1 * 2 * 2 1 1 *

2 1 * Propose d R Q (Ci )

1 0 1 0 1 0 1 0
1 0
10 0 1 0 1 0 10 0 100 0 100 0 10 0 10 0 1 0 1 0 1 0 10 0 10 0 1 0 1 0 100 0 10 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.6 8

Radionuclid e

Rhodium-10 7 Rubidium-7 9 Rubidium-81 m Rubidium-8 1 Rubidium-82 m Rubidium-8 3 Rubidium-8 4 Rubidium-8 6 Rubidium-8 8 Rubidium-8 9 Rubidium-8 7 Ruthenium-9 4 Ruthenium-9 7 Ruthenium-10 3 Ruthenium-10 5 Ruthenium-10 6 Samarium-141 m Samarium-14 1 Samarium-14 2 Samarium-14 5 Samarium-14 6 Samarium-14 7 Samarium-15 1 Samarium-15 3 Atom . No .

4 5 3 7 3 7 3 7 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 Half-Lif e

21. 7 mi n 2 3 mi n 3 2 mi n 4.5 8 h r 6.4 7 h r 86. 2 da y 32. 9 da y 18.6 3 da y 17. 7 mi n 15. 3 mi n 4.9 E 1 0 y r 5 2 mi n 2.8 9 da y 39.2 4 da y 4.4 4 h r 372. 6 da y 22. 6 mi n 10. 2 mi n 72. 5 rain 34 0 da y 1.03 E 8 y r 1.08 E 1 1 y r 9 0 y r 46. 7 h r Ingestio n

(water )

5.4 E 1.3 E 6.7 E 1.3 E 3.4 E 2.0 E 1.7 E 1.7 E 6.7 E 1.3 E 3.4 E 1.5 E 6 . I E 1.5 E 3.8 E 1.5 E 4.8 E 8 . I E 1.3 E 9.7 E 1.6 E 3.2 E 1.6 E 3.2 E 3 # 5 5 5 4 3 3 3 4 5 3 3 2 2 2 1 5 5 5 4 2 2 5 4 Inha

latio n

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

1.2 E 2 * 2.9 E 1 * 1.5 E 2 * 7.8 E 1 * 1.4 E 1 * 7.3 E 1 * 5.4 E 1 * 3.8 E 2 * 5.I E 1 * 2.0 E 1 *

- - 7.5 E 1 * 1.0 E 2 * 7.8 E 1 * 5.2 E 1 *

- - 2.4 E 1 * 3.5 E 1 * 5.9 E 2 * 2.5 E 6

- -

- -

- - LI E 3 * Proposed

R Q (Ci )

10 0 1 0 10 0 1 0 1 0 1 0 1 0 10 0 1 0 1 0 100 0 1 0 10 0 1 0 1 0 1 1 0 1 0 10 0 10 0 0.0 1 0.0 1 1 0 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.6 9

Radionuclid e

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-104r a Silver-10 4 Silver-10 5 Atom . No .

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 Half-Lif e

22. 2 9. 4 3.8 9 58. 6 3.9 3 83. 8 3.4 2 43. 7 57. 3 41. 1 8. 4 7. 1 118. 5 6 E 4 57. 3 18. 5 22. 3 2.6 2 68 0 1 3 6 6 3 3 6 9 41. 3 mi n hr hr hr hr da y da y h r mi n mi n da y h r da y 

### y r mi n mi n mi n hr y r mi n mi n rain mi n da y Ingestio n

(water )

9.7 E 8 . I E 5.4 E 3.8 E 3 . I E 6.9 E 1.5 E 6.I E 1.5 E 2.7 E 8 . I E 8 . I E 1.4 E 1.6 E 5.4 E 1.6 E 8 . I E 6.9 E 1.5 E 6.7 E 5.4 E 4.0 E 2.7 E 4.0 E 5 4 2 # 1* # 2 # 1 # 2* # 1 # 3* # 3 3 2 2 2 * 3 4 3 2* # 2 # 4 4 4 4 3 Inha

lation

1.0 E 4.7 E 1.0 E 3.6 E 5.2 E 1.0 E 1.6 E 5.2 E 2.6 E 2 . I E 5.2 E 5.2 E 3 . I E 3 . I E 3.6 E 1.0 E 5.2 E 1.6 E 2.6 E 1.0 E 5.2 E 4.7 E 3.6 E 5.2 E 5 3 4 2 3 2 3 2 4 4 4 3 2 2 4 5 4 4 0 * 5 4 4 4 2 Direc t Exposur e

4.0 E 3.3 E 4.4 E 1.2 E 3.I E 1.8 E 3.4 E 

### LI E 4 . I E 1.9 E 1.7 E 3.7 E 1.0 E

- - 3.5 E 3.3 E 2.3 E 4 . I E

t ? LI E 10 E 3.6 E 2.0 E 8.2 E 2 * 2 * 2 * 2 1 * 1 * 2 1 * 4 2 * 2 * 1 * 2 *

3 * 3 * 1 * 4

1 * 1 * 1 * 2 * 1 * Proposed R Q (Ci )

10 0 10 0 10 0 1 0 1 0 1 0 10 0 1 0 100 0 10 0 10 0 1 0 10 0 10 0 100 0 100 0 1 0 10 0 1 1 0 1 0 1 0 10 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.7 0

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 Half-Lif e

8. 5 24. 0 1.3 E 2 249. 8 7.4 7 3.1 4 20. 0 2.60 5 14.9 7 10 6 22. 2 32. 4 67. 6 64. 8 2.8 0 50.5 2 2 9 9. 5 2.7 1 87. 2 36. 8 3.6 5 1.1 8 10. 5 da y mi n y r da y da y hr mi n y r hr mi n mi n hr mi n da y hr da y yr hr h r da y mi n hr hr h r Ingestion

(water )

LI E 8 . I E 8 . I E 6.7 E 1.2 E 4.0 E 4.0 E LI E LI E LI E 5.4 E 5.4 E 5.4 E 8 . I E 1.1 E 1.3 E 8 . I E 5.4 E 8 . I E 4.6 E 3 . I E 5.4 E 2.3 E 4.6 E 3 4 2 2 3 3 4 2 * 3 4 4 3 5 3 5 3 1 3 3 2 # 3 # 2 # 3 # 2 # Inha

lation

3.6 E 1.0 E 1.0 E 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 1.0 E 5.2 E 5.2 E 2 . I E 2 . I E 3.6 E 2 . I E 5.2 E 1.0 E 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

1.4 E 5.I E 2.2 E 1.3 E 1.4 E 7 . I E 1.4 E

- - 8.8 E 4.4 E 2.9 E 1.0 E 1.9 E 7 . I E LI E 4.4 E

- - 3.7 E 2.7 E

- - 2.9 E LI E 6.8 E 9.3 E 1 * 1 * 1 1 * 3 1 * 2 *

0 * 1 * 1 * 2 * 2 * 1 * 2 * 6

1 * 1 *

1 * 2 * 1 * 1 * Proposed R Q (Ci )

1 0 1 0 1 0 1 0 10 0 1 0 10 0 10 0 1 1 0 1 0 10 0 10 0 1 0 10 0 1 0 1 1 0 1 0 1 0 1 0 10 0 1 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.7 1

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 Technetium-94 m Technetium-9 4 Technetium-96 m Technetium-9 6 Technetium-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 7 3 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 Half-Lif e

8.0 8 h r 2.3 6 da y 9. 3 mi n 1.8 2 y r 8.1 5 h r I E 1 3 y r 15. 9 mi n 114. 5 da y 5. 1 da y 8. 7 h r 4 9 mi n 10. 5 mi n 4 3 mi n 2.8 3 h r 5 2 mi n 4.8 8 h r 5 2 mi n 4. 3 da y 9 0 da y 2.6 E 6 y r 4.2 E 6 y r 6.0 1 h r 2.13 E 5 y r 14. 2 mi n Ingestio n

(water )

3 . I E 7.7 E 1.5 E 1.5 E 1.5 E 7.7 E 1.5 E 6 . I E 6.9 E 1.5 E 2.3 E 3.8 E 5.4 E 2.3 E 1.5 E 6.9 E 1.5 E 1.5 E 3.8 E 3 . I E 7.7 E 6 . I E 3 . I E 6.9 E 2 # 2* # 3 # 3* # 3* # 1* # 4 # 1 # 1* # 2 # 3 # 3 # 3 3 3 2 4 2 2 * 3 * 1 3 2 * 3 Inha

latio n

5.2 E 1.0 E 3.6 E 4.7 E 3 . I E 1.0 E 2 . I E 5.2 E 5.2 E 2.6 E 3 . I E 1.0 E 1.0 E 3.6 E 2 . I E 1.0 E 1.0 E 1.0 E 5.2 E 3 . I E

• 1.6 E 1.0 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

2.6 E 2.4 E 5.3 E

- - 6.7 E

- - 1.8 E 3.0 E 1.7 E 2.4 E 3.3 E 2.9 E 5.0 E 2.4 E 1.9 E 1.4 E 2.5 E 1.5 E 1.2 E

- - 2.6 E 2.9 E

- - 1.1 E 1 * 3 2 *

3

2 * 1 * 2 1 * 2 * 1 * 1 * 1 * 1 * 1 * 3 * 1 * 5

1 * 2 *

2 * Propose d R Q (Ci )

1 0 10 0 10 0 100 0 100 0 1 0 10 0 1 0 1 0 1 0 10 0 1 0 1 0 1 0 1 0 1 0 100 0 1 0 10 0 100 0 1 0 10 0 10 0 10 0EXHIBI T 4- 5 (Continued )

- Releas e Value s (Ci )

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 Half-Lif e

18. 3 mi n 2. 5 hr 154 da y 16. 8 da y 119. 7 da y 1.3 E 1 3 y r 5 8 da y 10 9 da y 9. 5 h r 33. 4 da y 69. 5 mi n 32. 4 h r 25. 0 mi n 78. 2 h r 55. 4 mi n 12. 5 mi n 4 2 mi n 1. 8 h r 4.1 5 h r 3. 3 h r 17. 6 h r 2.3 4 da y 2 2 h r 5. 3 da y Ingestio n

(water )

1.5E , 3 LI E 4 6.7 E 2 4.0 E 3 8 . I E 2 " 6.7 E 2 1.3 E 3 8 . I E 2 9.4 E 3 * 6.7 E 2 4.0 E 4 4.0 E 2 4.0 E 3 2.7 E 2 4.0 E 3 1.3 E 4 2.7 E 4 1.2 E 5 6.7 E 4 6.7 E 4 5.4 E 4 6.7 E 4 2.7 E 4 8 . I E 4 Inha

latio n

3.6 E 1.0 E 1.0 E 1.6 E 1.0 E 1.0 E 2.I E 1.6 E 1.0 E 1.0 E 3 . I E 2 . I E 2.6 E 1.0 E 2.6 E 1.0 E 1.0 E 1.6 E 3.6 E 1.0 E 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

2.4 E 6.I E 1.8 E 6.5 E 2.7 E

- - LI E 5.I E 1.0 E 7.8 E 7.6 E 3 . I E 1.0 E 1.8 E 3.6 E 4.3 E 4.4 E 2 . I E 4.2 E 4.4 E 5.5 E 2.6 E 2.2 E 4.2 E 1 * 2 * 2 1 * 2

5 5 5 2 2 * 1 * 2 * 2 2 * 1 * 1 * 1 * 1 * 1 * 1 * 2 * 1 * 2 * Propose d R Q (Ci )

1 0 10 0 10 0 1 0 10 0 10 0 10 0 10 0 100 0 10 0 10 0 1 0 10 0 10 0 10 0 1 0 1 0 1 0 1 0 1 0 1 0 10 0 1 0 10 0EXHIBI T 4- 5 (Continued )
Releas e Value s (Ci ) P.7 3

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 Thoriiim-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 Half-Lif e

5. 0 hr 2 4 hr 5. 3 da y 15 0 yr 1.2 E 3 yr 72. 4 da y 6.9 1 da y 32. 8 mi n 3 3 mi n 1.1 3 hr 2.8 3 hr 1.8 7 hr 5. 3 hr 7. 4 h r 1.0 9 da y 3.0 5 da y 12.2 3 da

y 3.7 8 yr 3 1 mi n 18.7 2 da

y 1.91 3 yr 730 0 yr 7.54 E 4 y

r Ingestio n

(water )

2.7 E
9.4 E
1.3 E 6.7 E 1.3 E LI E 2.7 E 2.8 E 1.7 E 3.3 E 3.9 E 1.7 E 1.1 E 3.3 E 4.4 E LI E 2.2 E LI E 1.3 E 2.7 E 1.6 E 1.6 E 1.1 E 5
4
4 5 4 4 4 3 4 3 3 3 3 3 2 3 * 2 2 * 5 3 2 1 2 Inha

lation

1.6 E 4 *
4.I E 3 *
5.2 E 2 1.6 E 2 * 1.0 E 1 * 1.0 E 2 1.0 E 3 * 1.0 E 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 1.0 E 4 2.6 E 3 1.0 E 3 5.2 E 2 * 1.6 E 0 * 5.2E-2 * 4.7E-3 * 3.1E-2 * Direc t

Exposur e

4 . I E 4

- - 2.3 E 1 *

- - 4.9 E 1 3.4 E 1 * 4.9 E 3 1.8 E 1 * 5.I E 1 * 5.6 E 1 * 1.4 E 2 * 3.4 E 1 * 2.5 E 1 * 2.3 E 2 * 3.4 E 1 * 1.8 E 3 9.0 E 1 *

- - 5.4 E 3 4.4 E 2

- -

- -

__ Proposed

R Q (Ci )

100 0
100 0
1 0 10 0 1 0 1 0 100 0 1 0 1 0 1 0 10 0 1 0 1 0 10 0 1 0 100 0 1 0 10 0 10 0 1 0.0 1 0.00 1 0.0 1P.7 4 

# I t EXHIBI T 4- 5 (Continued )

•- Releas e Value s (Ci )

Radionuclid e

Thorium-23 1 Thorium-23 2 Thorium-23 4 Thulium-16 2 Thulium-16 6 Thulium-16 7 Thulium-17 0 Thulium- X 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-121r a Tin-12 1 Tin-123 m Tin-12 3 Tin-12 5 Tin-12 6 Tin-12 7 Tin-12 8 Atom . No .

9 0 9 0 9 0 6 9 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 Half-Lif e

25. 2 hr 1.4 E 1 0 yr 24.1 0 21. 7 7.7 0 9.2 5 128. 6 1.9 2 63. 6 8.2 4 15. 2 4. 0 35. 3 115. 1 13. 6 29 3 5 5 27. 0 40. 1 129. 2 9. 4 I E 5 2. 1 59. 1 da y mi n hr da y da y yr hr hr mi n hr mi n da y da y da y yr h r mi n da y da y yr hr mi n Ingestion

(water )

LI E 1.9 E 8 . I E 5.4 E 3 . I E 1.5 E 6 . I E 7.7 E 5.4 E 3 . I E 5.4 E 5.4 E 9.4 E 2.7 E 2.7 E 4.0 E 4.0 E 8 . I E 6.7 E 6.7 E 5.4 E 4.0 E 9.4 E 1.2 E 5 1 3 3 # 2 # 2* # 1* # 2 # 1* # 2 # 3 # 3 4 3 3 3 3 3 4 2 2 2 3 4 Inha

lation

3 . I E 5.2E

1.0 E 1.6 E 5.2 E 1.0 E 1.0 E 1.6 E 5.2 E 5.2 E 1.6 E 5.2 E 1.0 E 2.6 E 5.2 E 5.2 E 2.6 E 5.2 E 5.2 E 1.0 E 2 . I E 3 . I E 1.0 E 1.6 E 4 3 * 3 * 5 3 3 2 2 * 2 3 5 3 5 2 2 2 * 2 * 3 * 4 2 * 2 1 4 4 Direc t Exposur e

4.4 E 7.3 E 6.9 E 4.7 E 1.9 E 3.9 E 1.3 E

- - LI E 9.5 E 4.5 E 1.3 E 3.0 E 1.4 E 2.6 E

- -

- -

- - 2.6 E 5.3 E 1.3 E 2.0 E 2.5 E 6.8 E 2 * 5 3 1 * 1 * 2 4

2 1 * 1 * 2 * 2 * 2 * 2 *

2 * 3 2 * 1 * 1 * 1 * Proposed R Q (Ci )

10 0 0.00 1 100 0 1 0 1 0 10 0 1 0 10 0 1 0 1 0 1 0 10 0 10 0 10 0 10 0 10 0 10 0 100 0 10 0 10 0 10 0 1 0 1 0 1 0EXHIBI T 4- 5 (Continued )

•- Releas e Value s (Ci ) P.7 5

Radionuclid e

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 Atom . No .

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 Half-Lif e

4 7 y r 3.07 8 hr 2. 5 hr 2.2 1 hr 21. 5 da y 37. 5 mi n 12 1 da y 74. 8 da y 23. 9 h r 69. 4 da y 20. 8 da y 4. 2 da y 68. 9 yr 1.59 E 5 y r 2.45 E 5 yr 7.08 E 8 y

r 2.34 E 7 y

r 6.7 5 day 4.46 E 9 y r 23.5 4 mi n 14. 1 hr 31. 3 mi n 15.9 8 day 33 1 da y Ingestio n (water )

2.3 E 1 # 6.9 E 2* # 7.7 E 2 # 1.5 E 3 # 3.8 E 2* # 3.8 E 4* # 1.5 E 3* # 1.5 E 2* # 1.5 E 2 # 3.I E 1* # 1.2E-1 * 1.2 E 2 * 5.8E- 2 2.9E- 1 2.9E- 1 2.9E- 1 2.9E- 1 5.8 E 1 * 2.9E- 1 2.0 E 3 * 2.9 E 1 * 2.3 E 3* # 4.6 E 1 # 5.4 E 3* # Inha

lation

3.I E 0 * 1.6 E 4 2.6 E 4 4.7 E 4 1.0 E 4 1.0 E 6 1.6 E 4 3.6 E 3 4.7 E 3 5.2 E 2 1.6 E 0 2.6 E 4 4.1E-2 * 2.1E-1 * 2.1E-1 * 2.1E-1 * 2.1E-1 * 5.2 E 3 2.1E-1 * 1.0 E 6 1.0 E 4 4 . I E 4 3 . I E 2 1.0 E 4 Direc t

Exposur e

2.7 E 2

- - 3.2 E 2 * 7.6 E 1 *

- -

- - 2.2 E 5 1.5 E 6 7.6 E 1 * 2.2 E 4 4 . I E 4 4.9 E 3

- - 1.9 E 6 7.5 E 5 2.7 E 2 1.6 E 6 6.8 E 2

- - 8.3 E 3

- - LI E 4 3.4 E 1 * Proposed

RQ (Ci )

1 10 0 10 0 1 0 10 0 100 0 100 0 10 0 1 0 1 0 0. 1 10 0 0.0 1 0. 1 0. 1 0. 1 0. 1 1 0 0. 1 100 0 1 0 100 0 1 0 100 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.7 6

Radionuclid e

Xenon-12 0 Xenon-12 1 Xenon-12 2 Xenon-12 3 Xenon-12 5 Xenon-12 7 Xenon-129 m Xenon-131 m Xenon-133 m Xenon-13 3 Xenon-135r a 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 Yttrium-8 6 Yttrium-8 7 Yttrium-8 8 Atom . ' Ingestio n Inha

- Direc t Propose d No . Half-Lif e (water ) latio n Exposur e R Q (Ci )

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 4 0

3 9 20. 0 2. 0 17. 1 36.34 1 8.8 8 11.9 2 2.1 9 5.2 5 15. 3 9.1 0 14. 1 18. 9 2.3 6 17. 5 32.0 2 4.1 9 1. 9 1.2 3 4 8 14.7 4 80. 3 106.6 1 mi n mi n h r hr hr da y da y da y da y da y mi n h r mi n mi n da y mi n da y da y 

### h r h r mi n 

### h r h r da y na

na n a na na na na na
na na na na na 5.4 E 3 7.7 E 1 2.3 E 4 # # # 1.5 E 2* # 2.3 E 2* # 1.5 E 3 # 7.7 E 2* # 2.7 E 5 1.3 E 4 2.7 E 4 1.3 E 4 1

1 3 3 1 2 2 2 1 1 1 na na na na na na na na na n a na na na 6 E .0 E .6 E .6 E .6 E 6 E .I E 6 E 6 E 6 E 0 E 5 3 5 2 3 4 4 4 3 3 2 9.9 E 2.0 E 6.9 E 6.0 E 2.0 E 9.9 E 2.0 E 4.0 E 9.9 E 9.9 E 8.9 E 9.9 E 4.0 E 4 . I E 3.7 E 2.6 E 1.9 E 9.9 E 2.5 E

- - 1.9 E 1.4 E 4.6 E 1.4 E 1*4

- 1*4

- 2*4

- 1*4

- 2*4

- 1*4

- 3*4

- 3*4

- 2*4

- 2*4

- 1*4

- 1*4

- 1*4

- 2 * 1 * 2 * 2 2 2 *

2 * 1 * 1 * 1 * 1 0

1 0 10 0 1 0 10 0 1 0 100 0 100 0 10 0 10 0 1 0 1 0 1 0 10 0 1 0 10 0 10 0 10 0 10 0 10 0 10 0 1 0 1 0 1 0EXHIBI T 4- 5 (Continued )

Releas e Value s (Ci ) P.7 7

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 Half-Lif e

3.1 9 hr 64. 0 hr 49. 7 mi n 58. 5 da y 3.5 4 hr 10. 2 hr 18. 7 mi n 10. 3 mi n 9.2 6 hr 38. 1 mi n 243. 8 da

y 13. 8 hr 5 7 mi n 3.9 7 hr 4 4 h r 16. 5 hr 8 5 da y 78. 4 hr 1.5 E 6 yr 64.0 3 da

y 16. 8 h r Ingestion

(water )

LI E 5.4 E 1.3 E 6.7 E 4.0 E 1.3 E 2.7 E 5.4 E 7.7 E 1.5 E 3 . I E 3 . I E 4.6 E 4.6 E 7.7 E 5.4 E 2.2 E LI E 5.4 E 5.4 E 3.2 E 5 3 6 3 4 4 5 5 1* # 3 # 1* # 2 # 3* # 2 # " 1* # 4 5 5 4 4 4 Inha

lation

5.2 E 3 . I E 1.0 E 5.2 E 4 . I E 1.0 E 4 . I E 5.2 E 1.6 E 3.6 E 1.6 E 3.6 E 5.2 E 1.0 E 5.2 E 1.0 E 1.0 E 1.0 E 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

5.7 E

6.9 E 1.0 E 1.5 E 4.4 E 2.6 E 3.2 E 1.2 E 2.7 E 6.4 E 8.7 E LI E 2.6 E 2.6 E 1.4 E 9.5 E 1.5 E

- - 4.9 E 4.4 E 1 *

1 * 4 2 * 2 * 1 * 1 * 2 2 * 1 1 * 7 1 * 2 2 * 1 * 2 *

1 * 1 * Proposed RQ (Ci )

1 0 10 0 1 0 1 0 10 0 10 0 1 0 1 0 1 0 10 0 1 0 1 0 100 0 1 0 1 0 10 0 1 0 10 0 1 1 0 . 1 0P.7 8



### EXHIBI T 4- 5 (Continued ) FOOTNOTE S

* Th e asteris k indicate s th e lowes t Releas e Valu e fo r th e specifi c radionuclide ; thi s valu e i s use d t o determin e th e propose d RQ group . N o gamm a ray s ar e emitte d o r th e gamm a ray s whic har e emitte d hav e gamm

a ra yenergie s o f les s tha n0.0 7 MeV an d ar e strongl yattenuate d i n air . N o Releas e Valu e fo r the direc t exposur e pathwaywa s calculated . + Th e Releas e Valu e wa s calculate d assuming submersio ni na contaminate d cloud . Th e Derive d Ai r Concentratio n(DAC ) i s use d t o estimat e th e Releas e Valu e fo r th e specifi c radionuclide . # Th e retardatio n factor , R> , i s assume d t o b e equa l t o on e (R d

### = 1 ) . na AnAnnua l Limi t o f Intak e (ALI ) fo r eithe r ingestio no r inhalatio n (or both ) wa s unavailabl e fo r thi s radionuclide . E Th e exponen t t o th e bas e 10 . Fo r example , 1.3 E 2 i s equa l t o 1. 3 x10 2 

### o r 130 . mSignifie s a nuclea r isome r whic hi s a radionuclid e i na highe r energ

ymetastabl e stat e relativ e t o th e paren t isotope . SOURCE S Handboo k o f Chemistryan d Physics . Editio n6 7 (1986-1987) , Weast , Rober t c , CR C Pres s Inc. , Boc a Raton , Florida . Handboo k o f Chemistryan d Physics . Editio n6 6 (1985-1986) , Weast,
- Rober t C. , CRC Pres s Inc. , Boc a Raton , Florida . Handboo k o f Chemistryan d Physics . Editio n6 3 (1982-1983) , Weast , Rober t C , CRC Pres s Inc. , Boc a Raton , Florida . "Tabl e o f Isotopes" , Compile d b yRussel l L . Heath , Idaho Nationa l Engineering Laboratory , EG& GIdaho , Inc. , Idah o Falls , Idaho .f X f t o O N I I o o 3 < ( B t i 0 1 p - O 3 i- h P > O r t O h i tr C D r t c m ( B 3 a f. o H o o c h | P - ( B 0 1 P l 3 P - O p ft p - ( B 0 1 O l p o i l C B n ( B P ) r t P * p - 3 0 0 za o i r t ( B f t

. r o L O X h- 1 o ^ J o £ cr f t o o B p . p i t < v— ' .• • p 3 P - o - p i » <

- ^ o P c r p - o o 3 v - / w . X JO I I > r t 3 0 0 1 x) P " ( 0 h i P - o P O C P h- ' P r t P - < ( P O O 3 O ( P 3 r t H P ) r t p - O 3 < p) h- 1 p I P

.—• . O O •f > X p O i h- ' w P O I I P O ( B •— • < B P l 0 1 ( B •* 1 h t P l o r t P - O

. 3 <• ; £

zr 0 1 i- l ( B /— \

> tr 1 h H I I tt> B P e p i h- • t Hfa p - r t 0 1 O ht i h- 1 3 r t P i 7? to h h O l- l P - 3 P * P ) f P i r t P - O 3 /— \ a p - o H O O G ft f- ( B U l t—s s . • f •^rf

h- 1 3 3 - P ) P J p i r t P - O 3 P0 ( B h- " ( P P l 0 1 ( B < P l X-t P ( B I I > t H h H

-- — f-s /~ ^ f t o ^ ^ !( - /- ^ P O v - / -C * f—\ X o • w » ' i * f \ t o P O 1( * /- ^ X-t X P » o o \ \ s t . ^ <

B X T l O 0 1 C H ( B r t zr ft o P O Q zr p - 3 r tn . p - ( P ( P O ( P h h P - O < 1 —p . h - 3 O O Q « P - PJ 3 O Q P

. O 3 o i p i C P r ti zr ( P ( P ,4 3 p - 3 G P i X-t P i r t P - O 3 •• p i fr t< P - P ) O h- - p l ( P h - 3 r t ( B XO 1 3 H i i- l ( B L n 0 1 O 0 1 o P - O 3 P P h- ' r th-< O P i-t O - (P (P 3 h t p - f\ < O ( B • L n P O ( P h ( X— 1( P ( P 3 p i ^- / 0 1 • ( P P i 3 h- •( P P ( P > 0 1 o o ( P c rp p l o 0 1 V J o i p . p . n > o < p t p poped 0 1 I P h f ( P r tT ) O h h o o p 0 1 ( P l-t < p l r t P - < C P r> f- h i O c 3 U l r t P i P O C P 0 1 w o o P X—t p . h | C P U l P i—t Ct P - P P l P ( P X T J O U l ( P p . p - p p . p - < p - p . p P ) p h i C P U l C P P r t r t tr C P p i o r t P - < p - r t ^ ! h- * C P < C P X-t o l- h C D P l O zr i-t p i p . p o 3 P O X-t P - P

. C P £ zr p - o zr p - h h r t C P h- * ( P P l 0 1 C D P P 3 a CD h i p i fp zr p i h- ' P ) r t P - o 3 C P X TJ o w p ft C P XI p) (- 1 zr K P i v j

P O ( P h- ' C P P l 0 1 C P < P ) h- ' p C P 0 1 p> H C P P - P P P P - r t 0 1 O l- h O P h t P - ( P 0 1 Q l P P

. ZT C P > O Q C P P n v j

- U l 3 C P r t P * o p o h- ' o O Q V J cr C D O Q P - P 0 1 cr t < C P U l r t P - 3 P i r t P 3 O Q P O C P h- • C P p l 0 1 C P

rr. P l f P C P U l l- h O h i f t 3 * C P • U • r o • •• u 3 0 C D (D 0) ( A roVal c ro xn -Ti O

- i r t - 3 " ro — 3 zr 0 1 0 ) rT o '

-Pathw O l < • o p l r t P " £ P i « < p - U l P

. C P 0 1 o h | P - cr C P a cr C P h- • o s p . C P o p i ^ s p i 0 1
r t p i ? r C P p p - 3 r t o p i C l o o p 3 r- t
H P " C P P O JO p l p . (—. . c 0 1 r t 3 C P 3 r t 3 C D r t P " O O - o h- • o OQ * < i- h o l- l C D p l o zr C D Xposure zr C B h i C P P l h t C P t-t o c C P l-t tr zr C P P o C P 3 o l-t C P o o 3 0 1 C P h t < p i r t P - < C P rrx zr p i 3 r t zr C P t< e. o P X-t p . c r C P C P P r t P i * • C P P

d a V 5 P ( B OQ h- " ( P o r t p - P O Q r t zr C P C P i- h h h C D o r t O h h h i P l 0 - p - o p i o r t P - < C P a C P o p i crv ; C P p - h h H p i w r t zr C P C P

. a P p i r t p - O P 0 1 P in ( P P

. h h O h t r t P " C P < P i l- t P - O P U l 0 1 o C P p p l h t P - o U l p - 3 r t 3 " P - 0 1 h | C P x> o h | r t -. r t zrfw p i * a zox> P-JOfo p l o r t P - < ( P 0 1 P - C P < C Ploped i-t o P I o zr zrasnot o o o e H 0 1 3 o h t C P U l h- ' o s h- 1 *< H P - O f i O Q zrfcx f t 0 1 X) o in tn f- cr X—t C D r t O P ) O O O P P r- t h h O h t r t zrfin P - C P o h t C P p l 0 1 C Pinthe X) C P h tfo p . U l O h h r t P 3 ( P S P " p - h- * C D H i O h t h t P l P

. P o p p o X—t f- P

. ( P 0 1 S p - r t zr X—t O P OQ C P l- l zr p i t-t h h h- • p - < ( P U l
r t zrfin O - C P o h tease h t P I ( P X a t ) p - o p c o t-t f- P . C P 0 1 s p . r t P " U l P * o H r t zr p i H h h h- ' P - < C D 0 1
r t zr f t tn P - C D o h t C P p i 0 1 C P p - 0 1 0 1 p cr 0 1 r t P i P r t p - p i X—tfP 0 1 zr o h t r t o U l P H C P P i H P l P - P - O P P o f f t 0- C D P - 0 1 o P l X) p i cr X-t C P O h h X) h t o p . c o p . p OQ a C P o h t C P P I 0 1 C P 0 1 £ p - r t P *
r t P - 3 C P

*n o h i h i P l P - P - o 3 P O H P - P - C P r t O P - C P O P i * < • b a C P o p l p in C P h t p i P

. p - o 3 P o t— 1fa C P 0 1 a C P o p i t < « p - r t P " r t p - 3 C P

- r t zr C P p i 3 O P P r t O h h P i U l XS i- l O r tXI P * C P C D h t r t P-^ J P i X-t ht l h- ' P - h h C D • Irftn f- 0 1
r t zr C D r t P - 3 C D h t C D JJ P f- h | C P P

. h h O h t zr p i h- • h h O l- h r t zr C D XI P P i 3 r t P - r t V J O h h p i p - P r t h t P - 3 U l p - o 3 P i P v j C D P < P - i i O P 3 ( P 3 r t P i h- '
r tX I O p i h- ' h- • h | P l Or P " o 3 P O x-' f- P - C D 0 1 P - 0 1 r t zr C D O P - 0 1 l- t R i O r t C D h t P - 0 1 r t P - O h t O XI ( P h t r t P - C D U l -r x—t ( P p l p . p . 3 OQ r t O < p i h t P o p 0 1 f t C P < ( P X-t tn O h h C D X p.' O C D O P l V J r t p - 3 C Pknown o U l P i-t C D

O 3 C D 1 3 h i o X) C P H r t P - C P 0 1 p - 3 r t h | p - 3 0 1 p - o r t O r t zr C P h t p i p . p - o 3 c o h- « p - p . C P 0 1 r t zr C P 3 0 1 C B X—* < C B 0 1 P l h t C P O o p 0 1 p - p . C P h t ( P P

. P ) 0 1 Cellas s : zrfX-t C P p o r t X—t C P P i XI h t o < p - p . C B r t P - 3 C D X—t P.V J p - p O Q
r t O 0 1 p cr O l r t P i 3 r t P - P i f O < C P h | 1 h i C B X) o l-t r t p - P O Q

P H P r t zr C D 0 ) C D 0 ) o C D 3 p) h | p - o 0 1 •* a O l 3 V J 3 O r t P - h h p - O P i r t p - O 3 r t O r t p - C D z p l r t P - O P 0 1 h- ' p - P p " p i X-t p l 0 1 p h t ( P P-T J C P X r tT J P - O P

r t zr C D p - 3 OQ C P 0 1 r t p - O P trP l P P - r t P * ( P P

. P - h | C D o r t C D X POT ) C B 0 1 TJ O P 0 1 C D O C D P r t C P l-t h h O h t 3 O 0 1 r t h t C P i—teases, O 0 1 P M C P T l p i r t zr « 0 1 V J 0 1 £ C P h | C P P - C D < C D X— 1 O T )edto O 0 1 P h i C P 0 1 o C P p 0 1 i-t p - o cr C P o . C P h h P - P C P p .
Cl o 3 0 1 ( P 1- 1 < 0 1 r t P - < C P C D X T J O O l P h t C D U l O C P 3 O i h i P - o 0 1 h h o h i r t zr C P l-t C P 0 1 C P p r t 0 1 O i

• a P 0 1 P r t f- r t V J O h h h t O i a p - o p P o X—t f- P - C P cr C P p - 3 O Q h t C P h - ' C P O i 0 1 C P O- — It C D , o P f- h t C D U l r t p * p> r t O i h | C Dlease T J o p - p r t

. zr C D TJ M o o C B 0 1 U l o h h h | ( B X—t p l r t P - P O Q r t zr ( B > tr 1 h H < 0 > X—t P C B U l
r t O O i 3 P O JO f t 3 O r— ; h t P - C P 0 1 r £ zrfo p - h t C D T J h t C P U l C P 3 r t Jj P 0 ) 3 r t p - r t f- C D 0 1 O h h h t P l P

. P - O 3 P O X—tfO- C D 0 1 r t P i •K ( B 3 P - 3 cr V J O i XS C D i-t 0 1 O p p> r t 0 ) P ( B X TJ O U l P x-t C P r tp - P * 3 C P < O C P P- " p < C P C P h tP . OQ V J p . P o i- h r t zr r tC D p r C D C D X T J T J O i olt U l r tC P - h ( O C D h- ' C P f\ tn p i h- • O T J i tzr p l h t P i T l v j p i 0 1 l-t •i t p - o H P - zr C P C P U l •r 3 > tr 1 c r h H ( B r t < P i O i h- ' T J P O i C D 1-1 U l r t P - P - O CP !— • < C D CP 0 1 X—t r o T J O C P i- l P

. O Q crP v j 3 3 r tf o zr C P H P l r n v ; O 0 1),andRP O i 3 O P P r t O h h h i P l p . p - P l r t p - O P P - P r t C P i-t O C P T J r t C P a

- r t zr C P T J C P l-t p - o p . o o P I p o C P h | v— • r t O
r t zr C P C P X T J O 0 1 C P P o i-t O Q P l 3 p - 0 1 3 H zr C P 0 1 C D < C P h t P - r t h h V J C P X TJ O U l P i-t C D

• * r t zr C D r t v j TJ C P O h h h t P ) P

.iation O l- h r t p r C P r t h t P i P a fo Or 0 TJ ( P P P

. 0 1 p XS onthe o 0 ) p w C P U l p . 0 1 3 0 1 O Q C P r t O
r t P - 0 1 U l P C P U l £ zr p - o zr o 0 1 p zr O i < C P U l C P l-t p - o p m o O P U l C P XI P ( D P O C P 0 1

r—sf3 O X—t P P - P - 3 O Q +

-Th e inhalatio nALI s use d i n th e calculation s ar e take n directl yfromth e ICRP' s Publicatio n30. s Wher e mor e tha n on e inhalatio n AL I wa s availabl e fo r a particula r radionuclide , th e lowes t valu e wa s use d fo r th e calculations . Thi s approac hassure s tha t releas e o f th e radionuclid e i nit s mos t hazardou s chemica l formi s take n int o consideration . Th e inhalatio nALI s ar e derive d fo r worker s i nnuclea r facilitie s and ar e 1 0 time s thos e recommende d fo r adul t member s o f th e genera l public. 6 T o adjus t th e Commission' s ALI s t o reflec t th e mor e protectiv e leve l o f exposur e t o th e genera l public , th e Agenc ydivide d b y10 . Th e releas e fraction , R , reflect s th e fractio n o f th e radionuclid e releas e tha t coul d becom e airborn e and b e o f respirabl e siz e (1 0 micron s i n diamete r o r less) . Th e Nuclea r Regulator yCommissio n ha s develope d method s fo r estimatin g releas e fraction s fo r radionuclide s unde r acciden t conditions. 7 Asummar yo f thes e method s and a tabl e o f releas e fraction s fo r thos e individua l radionuclide s wit hpropose d RQ s ca n b e found i n Appendi xD o f thi s report . Th e atmospheri c relativ e concentratio n valu e (X/Q ) use d i n th e -1 3 calculations , 8. 4 x1 0 day/cubi c cm , correspond s t o th e relativ e concentration , a t groun d level , 3 0 meter s downwin d froma ground-leve l releas e unde r stabl e (Clas s D ) meteorologica l conditions . Clas s D meteorologica l condition s ar e considere d "neutral." 8 Aground-leve l releas e unde r Clas s D meteorologica l condition s lead s t o highe r ground-leve l concentration s tha n woul d b e th e cas e fo r a nabove-groun d releas e unde r mor e turbulen t conditions . Byusin g th e higher , ground-leve l concentration , th e derive d Releas e Value s ar e greate r tha n woul d b e th e cas e i f th e Agenc yha d use d a n above-groun d concentration . Thus , th e propose d RQ s ar e base d o n a mor e protectiv e releas e scenario . Th e Agenc yha s chose n3 0 meter s a s th e distanc e fromth e releas e t o th e poin t o f exposur e becaus e cordon s aroun d a releas e o f a chemica l hazardou s

5 Internationa l Commissio n o n Radiatio n Protection , Annal s o f th e ICRP : Limit s fo r Intake s o f Radionuclide s byWorkers , ICR P Publicatio n 30 , Par t 2 , 1980 . 6 Th e ALI s develope d byth e ICR P ar e base d o n a dose-equivalen t o f 5 rem . Th e Agenc yi s developin g th e propose d RQ s base d o n a dose-equivalen t o f 0. 5 re mo r 50 0 millirem . Th e 50 0 millire mlimi t correspond s t o th e Federa l Radiatio nProtectio nGuidanc e recommende d annua l exposur e level s fo r th e genera l public . 7 McGuire , S.A. , ARegulator yAnalysi s o n Emergenc yPreparednes s fo r Fue l Cycl e and Othe r Radioactiv e Material s Licenses , NUREG-1140 , U.S . Nuclea r Regulator yCommission . 'Turner , D . Bruce , Workboo k o f Atmospheri c Dispersio n Estimates , EP A Offic e o f Ai r Programs , 1970 .P.8 1

substanc e a t a transportatio n inciden t ar e generall y3 0 meter s i n radius . A t fixe d facilities , th e distanc e t o unrestricte d area s i s likel yt o b e greate r tha n3 0 meters , therefore , 3 0 meter s wil l resul t i n a conservativ e estimat e fo r exposure . Th e Agenc yderive d th e valu e o f X/ Q fo r distance s les s tha n10 0 meter s base d o nth e dispersivit ydat a presente d i n Th e Workboo k o f Atmospheri c Dispersio nEstimates . Th e X/ Q value s presente d i n th e Workboo k d o no t includ e dat a fo r distance s les s tha n 10 0 meters ; therefor e extrapolatio ni s necessary . However , becaus e th e extrapolatio n from10 0 meter s t o 3 0 meter s ma yno t b e totall yaccurate , a mor e preferre d metho d o f determinin g a valu e fo r X/ Q coul d no t b e identified . Th e Agenc ybelieve s it s evaluatio n o f exposur e vi a inhalatio ni s conservative . Afurthe r explanatio n o f atmospheri c relativ e concentratio nvalue s and it s derivatio n ca n b e found i n Appendi xE o f thi s repor t an d i nth e Workboo k o n Atmospheri c Dispersio n Estimates . Th e inhalatio no f toxi c substance s depend s i n a n obviou s manne r o n th e breathin g rat e o f individuals . Fo r purpose s o f th e Releas e Valu e calculations , th e breathin g rat e o f "Referenc e Man " i s assume d t o b e 2. 3 x 1 0 cubi c centimeter s pe r day. ' Thi s exposur e scenari o i s illustrate d i n Exhibi t 4-1 . Th e expression , show ni nEquatio n(1) , fo r determinin g th e Releas e Valu e fo r th e inhalatio n pathwa yca nb e simplifie d bysubstitutin g th e followin g value s int o th e equation : (X/Q ) = 8. 4 xIO" 13 ; and

BR= 2. 3 x10 7

. Bymultiplin g th e number s i n th e denominator , Equatio n (1 ) simplifie s to : (2 ) Inhalatio nReleas e Valu e = AL I (inhalation)/((193.2)*(R) ) Fo r eac ho f th e individua l radionuclide s fo r whic hth e Agenc yi s proposin g R Q adjustments , th e Releas e Value s calculate d fo r th e inhalatio n pathwa yar e presente d a t th e end o f thi s chapte r i n Exhibi t 4-5 . 4.2. 2 Releas e Value s for th e Ingestio nPathwa y Radionuclide s ca nb e ingeste d throug hth e consumptio n o f contaminate d foodstuff s o r contaminate d drinkin g water . I n th e cas e o f contaminate d food

stuffs , radionuclide s ca nreac hhuman s throug hfoo d crops , meat , and milk, 1 0

'Till , J.E. , Meyer , H.R . (Editors) , Radiologica l Assessment . A Textboo k o nEnvironmenta l Analysis , NUREG/CR-3332 , U.S . Nuclea r Regulator y Commission , 1983 . 10 Nair , S. , Model s fo r th e Evaluatio n o f Ingestio n Dose s Fro mth e Consumptio no f Terrestria l Food s Followin g a n Atmospheri c Radioactiv e Release , Centra l Electricit yGeneratin g Board , Technolog yPlannin g and Researc hDivision , Berkele yNuclea r Laboratories , England , 1984 .P.8 2

APPENDI XA EXISTIN G REQUIREMENT S T O REPOR TRADIONUCLID E RELEASE S

Thi s appendi xdescribe s th e radionuclid e releas e reporting requirement s an d processe s o f the Nuclea r RegulatoryCommission , th e Departmen t o f Transportation , th e Departmen t o f Energy , an d individua l states . Th e Federa l Radiologica l Emergenc yRespons e Pla ni s als o briefl ydescribed . A . I NUCLEA R REGULATOR YCOMMISSIO N Th e Nuclea r RegulatoryCommissio ncontrol s th e handling o f nuclea r material s throughanextensiv e licensing an d regulatoryprogram . Thi s progra m include s severa l differen t requirement s fo r responsibl e partie s t o immediatel y repor t release s o f radionuclides . Th e exten t o f th e Commission' s regulatoryjurisdictio ni s limite d t o certai ntype s o f nuclea r material s an d t o certai npartie s wh o mayhandl e thes e materials . First , the Commissio nonl ylicense s source , byproduct , an d specia l nuclea r materia l a s define d b yth e Atomi c EnergyAct . I ngeneral , th e Commissio n doe s no t licens e naturall yoccurring an d accelerator-produce d radioactiv e material s (NARM) , althoughnaturall yoccurring radioactiv e material s mayb e subjec t t o Commissio nregulatio nwhe ntheyar e associate d wit hsource , byproduc t o r specia l nuclea r materia l being use d unde r an active license . Second , certai nactivitie s o f th e Departmen t o f Energyan d th e Departmen t o f Defens e - - eve nthoughthes e activitie s involve source , byproduct , an

d specia l nuclea r material s - - ar e exemp t fro mCommissio nlicens e requirements . Existin g Commissio nrequirement s fo r licensee s t o repor t radionuclid e release s immediatel yar e describe d below . I nadditio nt o thes e requirements , th e Commissio nha s severa l othe r requirement s t o repor t withi na specifie d time afte r a release , bu t no t immediatel y(e.g. , withi n2 4 hour s an d withi n3 0 days) . Thes e "non-immediate " reporting requirement s ar e no t presente d belo w becaus e theyar e no t substitute s fo r th e immediat e notificatio nrequiremen t i n CERCLA' s sectio n103 . Onc e th e Commissio nreceive s suc hreleas e notification s it , among othe r things , oversee s th e licensee' s respons e action , provide s guidanc e an

d expertise , disseminate s importan t information , an d coordinate s wit hothe r relevan t agencies . Th e Commissio ndoe s no t hav e a budge t t o undertak e activ e cleanu p response s o nit s own . A . 1. 1 Regulation s Nuclea r RegulatoryCommissio nregulation s i n1 0 CFRPar t 2 0 se t standard s fo r protectio nagains t radiatio nan d ar e applicabl e t o al l person s wh o receive , possess , use , o r transfe r an ynuclea r materia l license d b yth e Commission . Th e following ar e immediat e reporting requirement s containe d i n th e recentl ypropose d revisio no f 1 0 CF RPar t 20 :P.8 3

A- 2

• Eac hlicense e shal l repor t b ytelephone , immediatel y afte r it s occurrenc e become s known , an ylost , stolen , o r missing license d materia l i nsuc hquantitie s an d unde r suc hcircumstance s tha t i t appear s t o th e license e tha t a substantia l exposur e coul d resul t t o person s i n unrestricte d areas . Suc hreport s shal l b e mad e eithe r t o th e Commission' s Operation s Cente r o r t o th e appropriat e Commissio nRegiona l Offic e (1 0 CFRSectio n 20.1201(a)) .

• Eac hlicense e shal l immediatel yrepor t an yeven t involving byproduct , source , o r specia l nuclea r materia l possesse d b

yth e license e whic hmayhav e cause d o r threaten s t o caus e an yo f the following (1 0 CFRSectio n 20.1202(a)) :
anindividua l t o receiv e a deep dose-equivalen t o f 2 5 re mo r more , a dose-equivalen t t o th e len s o f th e eye o f 7 5 re

mo r more , o r anabsorbe d dos e t o th e ski no r extremitie s o f 25 0 rad s o r more ; o r th e releas e o f radioactiv e material , insid e o r outsid e o f a restricte d area , s o that , had an individua l bee npresen t fo r 2 4 hours : (1 ) th e individua l coul d hav e receive d anintak e five time s th e occupationa l annua l limi t o f intake ; o r (2 ) fo r certai n licensees , th e individua l coul d hav e receive d aneffectiv e dose-equivalen t o f 5 re mi na year . Additiona l regulation s o f th e Nuclea r RegulatoryCommissio nspecificall y applicabl e t o th e licensing o f byproduct , source , an d specia l nuclea r materia l ar e give ni n1 0 CF RPart s 30 , 40 , an d 70 , respectively . Eac ho f thes e set s o f regulation s contai nprovision s fo r licensee s t o "promptly " repor t t o th e Commissio nan

yattemp t t o stea l o r unlawfull ydiver t certai nquantitie s o f byproduc t (tritium) , source , o r specia l nuclea r materia l (1 0 CFRSection s 30.55(c) , 40.64(c) , an d 70.52(b)) . Othe r immediat e notificatio nrequirement s i nthes e regulation s are :

• Whe n a well-logging sourc e containing byproduc t o r specia l nuclea r materia l become s irretrievabl e i na well , th e license e shal l notif yth e Commissio no f th e circumstance s o f th e los s b ytelephon e (1 0 CFRSection s 30.56(b ) an

d 70.60(b)) .

• Eac hlicense e shal l repor t immediatel yb ytelephon e an d telegraph , mailgra mo r facsimil e an

ycas e o f accidenta l criticality 1 an d an yloss , othe r tha n

l A n unplanned , uncontrolle d nuclea r fissio nreaction . 

# KA- 3

norma l operating loss , o f specia l nuclea r materia l (Section 70.52(a)) . A . 1. 2 Licens e Condition s Th e Nuclea r RegulatoryCommissio nha s th e authorit yt o incorporat e i nan y o f it s nuclea r materia l license s additiona l requirement s an d condition s a s i t deem s necessaryi norde r t o protec t publi c healt han d welfar e an

d th e environment . I f appropriate , base d o nth e particula r circumstance s involved , suc hlicens e condition s mayrequir e additiona l reporting tha nexplicitl y calle d fo r i nthe regulations . Furthermore , becaus e licensee s ar e require d (1 0 CFRSectio n20.1(c) ) t o maintai nradiatio nexposure s an d release s t o th e environmen t a s lo

wa s reasonabl yachievabl e (ALARA) , th e Commissio nmay establis hreporting leve l trigger s tha t ar e belo wthos e specifie d i n1 0 CFR Par t 20 . Fo r example , 1 0 CFRSectio n20.105(c ) require s uraniu mfue l cycl e facilitie s t o compl ywit hth e offsit e dos e limi t o f 2 5 rem/year . I f severa l year s wort ho f monitoring dat a demonstrate , however , tha t a facilit yoperate s wel l belo wth e 2 5 rem/yea r limit , th e Commissio ntypicall yimpose s a licens e conditio nrequiring notificatio no f an d respons e t o environmenta l release s tha t maycaus e les s tha n2 5 rem/year . A s anothe r example , th e Commissio n commonl yrequire s a license e t o immediatel yrepor t anenvironmenta l monitoring resul t tha t i s some fractio no f th e releas e concentratio nallowe d i nth e regulations . Thes e additiona l reporting requirement s specifie d through licens e condition s mayvarysubstantiall yfro mon e license e t o th e next . A . 1.3 " Radiologica l Contingenc yPlan s Th e Nuclea r RegulatoryCommissio nha s take nspecia l step s t o assur e adequat e acciden t respons e preparednes s a t license d facilitie s tha t hav e th e potentia l fo r accident s whic hcoul d resul t i n(1 ) offsit e dose s exceeding 1 re mt o th e whol e body , 5 re mt o th e thyroi d o r 3 re mt o othe r critica l organs, 2 o r (2 ) potentiall yseriou s radiatio noverexposure s o f worker s fro m a nuclea r criticalit yinciden t o r fromreleas e o f radioactiv e materials , o r (3 ) chemica l exposure s whic hcoul d impac t radiologica l safety . Th e Commissio n identifie d 6 2 fue l cycl e an d radioactiv e material s licensee s tha t mee t thes e criteria , an

d require d themt o eithe r submi t radiologica l contingenc yplan s o r t o lowe r th e amoun t o f nuclea r materia l kep t unde r thei r possession . Abou t hal f th e licensee s submitte d plan s which , afte r meeting Commissio napproval , hav e bee nincorporate d a s a licens e requirement . Th e othe r hal f lowere d thei r possessio n limi t o r surrendere d thei r license . Radiologica l Contingenc yPlan s incorporat e specifi c provision s t o b e followe d i nth e even t o f anaccident , including step s t o assur e (1 ) tha t notification s ar e promptl ymad e t o federal , state , an d loca l agencies , an d (2 )

2 Radiatio n dose s o f 1 re mt o th e whol e bod

yan d 5 re mt o th e thyroi d ar e th e lowes t protectiv e actio nguide s establishe d b yth e EPAfo r triggering protectiv e actio ni npubli c area s following a radiatio naccident . Se e EPA-520/1-75-001 , Draf t Revisio no f June , 1980 .P.8 5

A- 4

tha t necessaryrecoveryaction s ar e take ni na timel yfashio nt o returna plan t t o a saf e conditio nfollowing anaccident . Th e plan s specif ywha t report s wil l b e mad e t o keep variou s governmen t agencies , corporat e management , an

d th e publi c informed . Forma l agreement s betwee nth e license e an d offsit e suppor t organization s ar e als o incorporate d int o th e plans . Th e Commissio ni s als o i nth e proces s o f evaluating th e nee d fo r a ne w propose d rul e t o requir e additiona l emergencypreparednes s fo r certai n licensees . Th e purpos e o f th e rule , i f proposed , woul d b e t o requir e thos e licensee s wh o posses s radioactiv e material s i nlarg e quantitie s t o hav e additiona l emergencyprocedure s fo r offsit e releases . Thes e procedure s woul d includ e step s for notifying offsit e authoritie s an d th e Commissio ni nth e even t o f emergencysituations . A. 2 DEPARTMEN TO F TRANSPORTATIO N Th e Departmen t o f Transportatio n(DOT ) i s responsibl e fo r regulating safet yi nth e transportatio no f al l hazardou s materials . Accordingly , DO T ha s promulgate d th e Hazardou s Material s Regulation s (4 9 CF RPart s 171-177 ) t o gover nth e transportatio no f hazardou s materials , including radioactiv e materials . DO T define s radioactiv e materia l a s an ymateria l having a specifi c activit ygreate r tha n0.00 2 microcurie s pe r gram . Thi s broad definitio n include s source , byproduct , an d specia l nuclea r material s license d b yth e Nuclea r RegulatoryCommission , a s wel l a s NAR Mwhic hi s outsid e o f th e Commission' s regulatoryjurisdiction . Th e DO T regulation s ar e organize d wit hrequirement s applicabl e t o al l mode s o f transportatio ni n4 9 CFRPar t 17 1 an d requirement s applicabl e t o specifi c transportatio nmode s (e.g. , rail , aircraft , ship , an d highway ) i n subsequen t parts . DOT' s releas e reporting requirement s applicabl e t o al l mode s o f transportatio nare :

• A t th e earlies t practicabl e moment , eac hcarrie r wh o transport s hazardou s material s shal l giv e notic e afte r eac htransportatio ninciden t involving th e shipmen t o f radioactiv e materia l i nwhic hfire , breakage , spillage , o r suspecte d radioactiv e contaminatio noccurs . Thi s notic e shal l b e give nt o th e Nationa l Respons e Cente r b y telephone , an

d eac hnotic e mus t provid e informatio n spelle d ou t i nth e regulation s (4 9 CFRSection s 171.51(a ) an

d (b)) .

• Eac hcarrie r making animmediat e repor t i naccordanc e wit hSectio n171.15 , jus t discussed , shal l als o submi t t o DO T (the Material s Transportatio nBureau ) a detaile d inciden t report . Thi s writte nrepor t mus t b e submitte d withi n1 5 day s fro

mth e dat e o f discoveryo f th e inciden t (4 9 CFRSectio n171.16) . Additiona l reporting requirement s specifi c t o differen t transportatio n mode s includ e requirement s fo r carrier s t o immediatel ynotif yshipper s o f anP.8 6

A- 5

inciden t i nwhic hther e ha s bee nbreakage , spillage , o r suspecte d radioactiv e contamination . I f anacciden t occur s during th e shipmen t o f radioactiv e material s b

yaircraft , th e carrie r i s require d t o immediatel ynotif yth e neares t FA

ACivi l Aviatio nSecurit yOffic e b ytelephon e (as specifie d i n4 9 CFRSectio n175.45) . Fulfillmen t o f thi s notificatio nrequiremen t exempt s th e carrie r fro

mhaving t o notif ythe Nationa l Respons e Center . Additionally , i n case s o f obviou s leakag e o f radioactive materia l aboard th e aircraft , DO T regulation s stat e th e carrie r shoul d notif yth e Regiona l Offic e o f th e U.S . Departmen t o f Energ yo r the appropriat e Stat e o r loca l radiologica l authoritie s (4 9 CFRSectio n175.700(b)) . Fo r accident s involving radioactiv e material s onboard a vessel , the captai no f th e vesse l i s require d t o immediatel ynotif yth e neares t Coas t Guard Captai no f th e Por t (4 9 CFR Section s 176.48(a ) an d (b)) . According t o a Memorandu mo f Understanding (MOU , 4 4 F R38690-2 ) betwee n DO T an d th e Nuclea r RegulatoryCommission , DO T wil l promptl ynotif yth e Commissio no f an

yaccidents , incidents , an d instance s o f actua l o r suspecte d leakag e involving radioactiv e materia l package s i f suc haneven t occur s i n transit . Also , DO T ha s th e responsibilit yo f encouraging th e non-agreemen t states 3 t o impos e inciden t reporting requirement s fo r radioactiv e material s o nshipper s an

d receiver s subjec t t o th e states ' jurisdiction . A. 3 DEPARTMEN T O F ENERG Y Th e Departmen t o f Energy(DOE ) play s tw o entirel ydifferen t role s i n th e are a o f radionuclid e releas e reporting . First , DO E mayb e a release r o f radionuclide s subjec t t o reporting requirements . DO E control s man y government-owned , contractor-operate d facilitie s tha t mayreleas e radionuclide s t o th e environment , including facilitie s engage d i nresearc han d development , nuclea r weapon s production , enrichmen t o f uraniu mfo r nuclea r reactors , an

d facilitie s tha t process , store , an d dispos e o f radioactiv e waste . Man

yo f th e researc hfacilitie s controlle d b yDO E ar e accelerators , whic hgenerat e accelerator-produce d radioisotope s (included unde r "NARM") . Ther e ar e man

yestablishe d requirement s fo r DO E t o immediatel yrepor t radionuclid e releases . Man yo f thes e requirement s ar e self-imposed , bein g spelle d ou t i nsevera l differen t interna l orders . DO E Orde r 5000. 3 spell s ou t th e Department' s systemfo r reporting unusua l occurrences , an d Orde r 5484. 1 specifie s DOE' s reporting requirement s fo r environmenta l an d healt hprotectio n information . Thes e requirement s typicall ycal l fo r individua l facilitie s t o repor t release s t o a regiona l operation s office , whic hmayi nturnrepor t th e releas e t o DO E headquarters . Severa l differen t criteri a fo r a variet yo f

'Agreemen t state s ar e thos e state s whic hhav e entere d int o anagreemen t wit hth e Atomi c EnergyCommissio no r th e Nuclea r RegulatoryCommissio n pursuan t t o Sectio n27 4 o f th e Atomi c EnergyAc t o f 1954 , a s amended , unde r whic hth e Commissio nha s relinquishe d t o suc hstate s th e majorit yo f it s regulatoryauthorit yove r source , byproduc t an d specia l nuclea r materia l i n quantitie s no t sufficien t t o for ma critica l mass . 

# iP.8 7

A- 6

"occurrences " an

d "unusua l occurrences " hav e bee nestablishe d t o specif ywhe n reporting i s require d immediately . A s a matte r o f policy , DO E als o require s reporting t o externa l organization s t o keep themapprise d o f importan t event s a t DO E facilities . Externally-impose d reporting requirement s includ e an yo f thos e specifie d b

yEPAan

d possibl ystat e agencies . DO E i s generall yexemp t fro mlicensing b

yth e Nuclea r RegulatoryCommissio nan d i s thu s exemp t fro m th e Commission' s reporting requirement s highlighte d above . Th e othe r rol e playe d b yDO E i nth e even t o f radionuclid e release s i s t o provid e expertise , guidance , an d assistanc e i nrespons e t o radiologica l hazard s create d b

yothers . I naccordanc e wit hthe Federa l Radiologica l Monitoring an

d Assessmen t Plan(FRMAP) , othe r partie s requiring radiologica l assistanc e maycontac t DOE . Th e Departmen t i ntur nwil l wor k wit happropriat e Stat e an

d loca l agencie s t o coordinat e offsit e radiologica l monitoring an d assessmen t data . DO E wil l asses s radiologica l monitoring dat a an d presen t them , along wit hrecommendations , t o th e partie s responsibl e fo r taking emergenc yo r remedia l action . A. 4 STAT E PROGRAM S State s mayb e classifie d a s eithe r agreemen t state s o r non-agreemen t states . Agreemen t state s ar e thos e wh o hav e entere d int o anagreemen t wit h the Nuclea r RegulatoryCommissio ngiving th e stat e mos t o f th e Commission' s authorit yt o licens e certai nquantitie s o f source , byproduct , an d specia l nuclea r material . Ther e ar e presentl y2 6 agreemen t states . List s o f Agreemen t an

d non-agreemen t state s ar e containe d i nExhibi t A-1 . Non-agreemen t state s hav e no t entere d int o suc hagreement s wit hth e Commission . Regulatoryprogram s fo r radioactiv e materia l ar e no t necessaril y voi d i nnon-agreemen t states , bu t thes e state s rel yo nth e Commissio nt o carry ou t it s licensing progra mfo r source , byproduct , an d specia l nuclea r materia l withi nth e state . Stat e program s fo r regulating radioactiv e material , including requirement s t o repor t release s o f radionuclides , diffe r greatly . Al l 2 6 agreemen t state s hav e licensing program s covering NARM . I naddition , th e Commissio nha s reporte d tha t ou t o f th e 2 4 non-agreemen t states , al l bu t thre e hav e regulatoryprogram s fo r NAR Mtha t ar e reporte d t o b e a t leas t a s stringen t a s th e Nuclea r RegulatoryCommission' s regulation s i n1 0 CFRPar t 20. k A. 5 TH E FEDERA L RADIOLOGICA L EMERGENC YRESPONS E PLA N O nDecembe r 7 , 1979 , th e Presiden t directe d tha t th e Federa l Emergenc y Managemen t Agenc y(FEMA ) assume lea d responsibilit yfo r al l federa l off-sit e nuclea r emergenc yplanning an d response . Additionally , th e Presiden t

^Telephon e communicatio nbetwee nBarbar a Hostage , EPA , an d Lidi a Roche , Nuclea r RegulatoryCommission . February1985 . Ther e mayactuall yonl yb e tw o state s whic hhav e n o regulatoryprogra mcovering NAR

M--n o informatio nha s ye t bee nobtaine d o nth e regulatoryprogrami nSout hDakota .P.8 8

A- 7

EXHIBI TA- 1 AGREEMEN TSTATE S AN D NON-AGREEMEN TSTATE S

NRC Agreemen t State s Alabama Arizon a Arkansa s Californi a Colorad o Florid a Georgi a Idaho Kansa s Kentuck y Louisian a Maryland Mississipp i Nebrask a Nevad a Ne wHampshir e Ne wMexic o Ne wYor k

. Nort hCarolina Nort hDakot a Orego n Rhod e Islan

d Sout hCarolina Tennesse e Texa s Washingto n NRC Non-Agreemen t State s Alask a Connecticu t Delawar e Hawai i Illinoi s Indiana Iowa Main e Massachusett s Michiga n Minnesot a Missour i Montan a Ne wJersey Ohi o Oklahoma Pennsylvani a Sout hDakot a Utah Vermon t Virgini a Wes t Virgini a Wisconsi n Wyoming

Source : U.S . Departmen t o f Energy , Radioactiv e Wast e Management :

o f Stat e Law s an

d Administration , Decembe r 1985 . ASummaryP.8 9

A- 8

delegate d t o FEM

Ath e responsibilit yfo r th e developmen t an d promulgatio no f th e Nationa l Radiologica l Emergenc yPreparedness/Respons e Pla nfo r Commercia l Nuclea r Powe r Plan t Accidents , als o know na s th e Maste r Plan(4 5 FR84910) . Thi s Maste r Planha s bee nsupersede d b ythe Federa l Radiologica l Emergenc y Respons e Plan , o r FRER P (5 0 FR46542) . Th e FRER P establishe s forma l role s an d responsibilitie s for federa l agencie s i nrespons e t o a wid e rang e o f peacetime radiologica l emergencie s (e.g. , fixed nuclea r facilit yincidents , transportatio nincidents , an d othe r type s o f event s involving radionuclid e releases) . FEM

Ai s responsibl e fo r coordinating non-technica l response s unde r th e FRERP , providing assistanc e t o stat e an d loca l governments , an d providing logisti c suppor t t o federa l agencies . Ther e ar e a t leas t thre e importan t feature s o f th e FRER P tha t shoul d b e noted . First , th e FRER P spell s ou t a pre-establishe d syste mfo r notifying al l appropriat e federa l agencie s o f a radiologica l emergency . I ngeneral , th e owne r o r operato r o f th e facilit y(or vehicle ) involve d i nanemergencyi s responsibl e fo r notifying th e appropriat e federa l an d stat e agencies . Th e federa l agencytha t owns , regulates , o r i s otherwis e responsibl e fo r th e radiologica l activit yi s responsibl e fo r notifying FEM Aheadquarter s which , i n turn , verifie s tha t th e stat e ha s bee nnotifie d an d notifie s othe r appropriat e federa l agencies . DO E i s require d t o notif ythos e agencie s wit hmonitoring an d assessmen t responsibilitie s unde r the FRERP . I naddition , the FRER P urge s a continuou s flowo f informatio nbetwee nfedera l an d stat e authorities , an d provide s a mechanis mfo r keeping th e publi c informed . Asecon d important

- featur e i s tha t a radiologica l emergencyinitiating respons e unde r th e FRER P i s define d a s an y"typ e o f radiologica l inciden t tha t pose s anactua l o r potentia l hazar d t o publi c healt ho r safet yo r los s o f property. " Therefore , actio nunde r th e FRER P canb e take nfo r release s o f NARMa s wel l a s fo r release s o f source , byproduct , an d specia l nuclea r material . Additionally , ther e i s no t a quantitativ e trigge r leve l whic hmus t b e me t i norde r fo r th e FRER P t o b e initiated . Third , th e FRER P charge s tha t owner s o r operator s o f anaffecte d nuclea r facilit yhav e primary responsibilit yfo r action s withi nth e facility' s boundaries , an d tha t stat e an d loca l government s hav e primaryresponsibilit yfo r actio ni narea s outsid e o f thos e boundaries . I ngeneral , federa l resource s ar e use d t o suppor t stat e an d loca l measure s i f requested .APPENDI XB SUMMAR YO F COMMUNIT YPOTENTIALL YSUBJEC T T ORADIONUCLID E RQ s

Sourc e Categorie s Numbe r o f Facilitie s Majo r Radionuclid e o f Concer n Existin gRegulation s NR C License dFacilitie s

- Powe r reactor s ±/

- Researc handTes t Reactor s
Radiopharmaceutica l Manufac turin g
Radiatio nSourc e Manufacturin g Laboratorie s

Wast e Disposa l Site s
Minera l andMeta l Processin g Site s Fue l Cycl e Facilitie s 8 0 reactor s

7 0 reactor s (a s o f 1983 ) argon-41 , tritium

argon-41 , tritium

2 6 industria l supplier s (i n1979 ) technetium-99 m 10,00 0 medica l facilitie s (i n1977 ) iodine-13 1 io dine-12 5 xenon-13 3 N A 2 / 140 0 laboratorie s (estimated , 1983 )
6 license d ( 3 operational )

1 0 license d facilitie s varie s fro m sit e t o sit e tritium , carbon-1 4 xenon-133 , iodine-125 , iodine-13 1 essentiall yal l excep t transuranic s an d spe cia l nuclea rmateria l uraniu m an d thoriu m 2 operatin g UF6 conversio n faci I itie s uraniu m 1 6 uraniu m fue l fabricatio n plant s enriche d uraniu m NRC , limit s fo rairborn e an d liqui d discharge s unde r1 0 CFR Par t20 , Appendi xB , Tabl e II

. NRC , limit s fo rairborn e an d liqui d discharge s unde r1 0 CFR Par t20 , Appendi xB , Tabl e II

. NR C o ragreemen tstates ; 1 0 CF R sectio n 20.30 3 govern s release s t o sani tar ysewag e systems
. NRC , 1 0 CFR Par t20

. NRC , 1 0 CF RPar t 20 , Appendi xB , Tabl e I I and releas e reportin gre quirement s o f Par t 20 . NRC , 1 0 CF RPart s 2 0 and 6 1 NRC , 1 0 CF RPart s 4 0 and 2 0 NRC , 1 0 CF RPart s 4 0 and 2 0 NRC , 1 0 CF RPart s 7 0 an d 2 0 2 / Sectio n101(22)(c ) o f CERCL A exclude s from

th e definitio no f releas e any release s o f "source , byproduct , o r specia l nuclea r materia l from a nuclea r incident , a s thos e term s ar e define dinth e Atomi c Energ y Ac t o f 1954 , i f suc h releas e i s subjec t t o requirement s wit hrespec t t o financia l protectio nestablishe dby th e Nuclea r Regulator y Commissio n unde r Sectio n17 0 o f suc hAc t .,." . 2 / N o informatio navailable . Source : ICF Incorporated , Economi c Impac t Analysi s fo r th e Propose dReportabl e Quantit y Adjustment s fo r Radionuclide s Unde r Sectio n10 2 o f th e Comprehensiv e Environmenta l Response . Compensation , andLiabilit y Act . Appendi xA , Jun e 1986 .APPENDI XB (continued ) SUMMAR YOF COMMUNIT YPOTENTIALL YSUBJEC T T ORADIONUCLID E RQ s

Sourc e Categorie s Numbe r o f Facilitie s Majo r Radionuclid e o f Concer n ExistingRegulation s

- DO DFaci I itie s

- Uraniu

m M i I Iin g DO E Faci I itie s

- Weapon s Productio nan dTesting

- Nuclea r Material s Productio n

- Physica l Researc h

- Uraniu

m Enrichmen t Plant s Coa I — FiredBoiler s

- UtiIit y

Boiler s

- Industria I Boiler s Minera l Extractio nIndustry

- Uraniu

m Mining

- Aluminu

m Industry

- Coppe r Industry

- Zin c Industry

- LeadIndustry

- Phosphat e Industry

- - Phosphat e Roc kProcessing 1 3 facilitie s (including9 Nava l shipyards ) 3 activ e mill s 7 8 facilitie s (a s o f 1980 ) 3 0 "active " DO E complexe s (1982 ) 3 0 facilitie s (a s o f 1986 ) 4 activ e facilitie s (a s o f 1982 ) 4 activ e facilitie s (1982 ) 2 activ e facilitie s (1986 )
1,88 1 unit s (1985 ) 51,18 7 unit s (1981 ) argon-41 , nitrogen-13 , oxygen-15 , carbon-1 4 uranium , radon-222 , thoriu m essen tiaIl yal l ra d ionuclide s

uraniu m uranium-23 8 thorium-23 2

18 1 mine s (2 1 activ e mines ) (1985 ) radon-222 , uranium , thoriu m 3 2 operatin g smelter s (1980 )

1 5 operatin g smelter s 5 operatin g facilitie s
5 smelters/refinin g complexe s
2 0 firm s wit h 3 1 plant s (1983 ) radon-22 2
radon-22 2 radon-22 2 uranium-23 8 thorium-23 2 uraniu m an d thoriu m
uraniu m an d it s deca y product s phosphat e roc k dust , lead-210 , an d polonium-21 0 NRC , Arm yRegulatio n 385-11 , Chapte r5 ; Arm y Technica l Manua l 3-26 1 NRC , 1 0 CFR Par t2 0 DO E Order s 5480.1 , 5484.1 , 5000.3 , 5820.2 , 5480.1 4 an d othe rorder s

No t regulate dunde r NESHAP s (5 0 F

R5190 )

NESHAP s (5 0 F

R15386 ) fo r undergroundmine s NSP S an

dSI P Ii

m it s fo r meetin gAmbien t Ai r Qua Iity

Standard s NSP S an

dSIP s NSP S an

dSIP s

NSP S an

dSIP s

NSP S an

dSIP s

Elementa l Phosphoru s Plant s 4 firm s wit h6 plant s NESHAP s (5 0 F R5190 )P.9 2
_

APPENDI XC OTHE RMETHOD S FORCALCULATINGRQ s

EPAha s examine d severa l method s fo r calculatin g RQs . Thes e includ e usin g Maximu

mPermissibl e Concentration s (MPCs) , Limitin g Possessio n Limit s (LPLs) , an d the perferre d metho d usin g Annua l Limit s o f Intak e (ALIs) . ALI s ar e examine d i nthe bod yo f thi s report , vhil e the othe r method s usin g MPC s an d LPL s ar e discusse d here . C l MAXIMU

M PERMISSIBL E CONCENTRATION S (MPCs )
Th e developmen t o f MPC s fo r the genera l publi c va s base d o nMaximu m Permissibl e Bod

yBurden s (MPBBs ) se t a t one-tent ho f the MPBB s fo r occupationa l exposure . MPC s an d MPBB s ar e calculate d folloving a 195 9 Internationa l Commissio no nRadiatio nProtectio nmodel .
MP C table s ver e prepare d b ythe Nuclea r RegulatoryCommissio n(1 0 CF R Par t 20 ) t o establis hguideline s fo r radionuclid e exposur e fo r bot h employee s o f nuclea r facilitie s an d fo r the genera l public . Thes e MPCs , i nunit s o f microcurie s pe r milliliter , ca nb e relate d t o RQ s i ncurie s b yimposin g a se t o f hypothetica l releas e condition s an d introducing a time factor . On e possibl e equatio ni s shovnbelov :

RQ(MPC ) = ((MPC)*(T))/((R)*(X/Q)*( 1 xIO 6 ) vhere : T = Tim e facto r ( 1 year )

1.Repor t o f Committe e I I o nPermissibl e Dos e fo r Interna l Radiation , ICR P Publicatio n2 , Pergammo n Press , Oxford , 1959 . 

### C- l'.9 3

Th e Releas e fraction . Thi s relate s the portion s o f inventorie s o f radioactiv e material s tha t coul d become airbor ni na release . , 2 Releas e fraction s hav e bee nreporte d i n calculation s don e here , Ri s takena s unity . NUREG-1140 * 

### Fo r X/ Q = Atmospheri c Relativ e Concentratio nValu e (Ch i ove r Q) . Thi s valu e correspond s t o a ground leve l relativ e concentratio na t 3 0 meter s froma ground leve l releas e unde r stabl e (clas s D ) -1 5 - 3 atmospheri c condition s (2. 3 x1 0 yr-c m) . Afurthe r explanatio no f thi s ter mcanb e foun

d i nAppendi xE . 1 x1 0 i s a facto r o f one-millio nt o conver t microcurie s t o curies . I nthe MP C approac houtline d above , the dose s ar e base d o nthe critica l orga n onl yan

d n o dos e conversio nfactor s fo r othe r organ s ar e included . Thi s approac hconsider s onl yinhalatio no f radionuclide s and doe s no t conside r ingestio no r submersio ni na nairborn e cloud . Othe r modification s takin g ingestio nan d submersio nint o accoun t coul d be developed . Exhibi t C- l present s a fe vRQ s calculate d b ythi s metho d (RQ(MPC)) . C. 2 LIMITIN

GPOSSESSIO

N LIMI T (LPLs )
Limitin g Possessio nLimit s ver e develope d b ythe Nuclea r Regulatory 3 Commissio ni nNUREG-076 7 t o determin e the maximu mamoun t o f a particula r radionuclid e tha t a facilit yregulate d b ythe Nuclea r Regulatory Commissio ncoul d hav e o nhand a t anytime tha t voul d b e subjec t t o a release . Inhalatio nva s considere d the critica l pathvayexcep t fo r thos e radionuclide s i nvhic hsubmersio ni na nairborn e clou d va s the acut e

2.McGuire , S.A. , ARegulatoryAnalysi s o nEmergenc yPreparednes s fo r Fue l Cycl e and Othe r Radioactiv e Material s Licensees , NUREG-1140 , U.S . Nuclea r Regulator yCommission . 3.Fisher , F.A. , Criteri a fo r Selectio no f Fue l Cycl e an d Majo r Material s Licensee s Needin g Radiologica l Contingenc yPlans , NUREG-0767 , U.S . Nuclea r Regulator yCommission . 

### C- 2P.9 4

exposur e pathvay . The origina l formul a use db y th e Nuclea r Regulator y Commissio

nt o calculat e th

e LPL s i s a s follovs : LPL = (Dn)/((DCFn)*(R)*(I) ) vhere : D n= Dose s requirin gprotectiv

e action s (rem) . Set a t 5 re m fo r employee s at a nuclear facility an d50 0 millire

m fo r member s of th e genera l public . DCF n= The inhalatio ndos e conversio nfacto r fo r th e limitingbod

y organ . R= Releas e Fraction . Thi s relate s th e portio

no f inventorie s o f radioactiv

e material s tha

t couldbecom

e airborne ina release . For calculation s done here , th e releas e fractio ni s take

na s unity . I = Intercept fraction . Tha t portio nof th e releas e that coul db e inhale db y a nindividual . The limitin

gpossessio

nlimit s define

dabov

e ca nb e convertedt

o RQ s b y applyin gfactor s similar t o thos e use

dfo r MPCs . Thes e include developin

ga set of releas e condition s an ddeterminin

ga natmospheri c relativ e concentratio

nvalue base

do nthe m an dapplyin

ga factor fo

r vhol e bod

y submersionina

nairborne clou

dof radioactiv

e material . A

n equatio ntha t ha s bee

nuse dfo r calculatin

gRQ s base

do nLPL s i s shov

n belov : (Dn ) RQ(LPL ) = (lE9)*(R)*(X/Q)*[(DCFVBS)+(Z(Vt)*(DCFt)*(BR)) J t vhere : DCFVB S = Dos e conversio nfactor fo

r vhol e bod

y submersion . V t = Weightingfactor fo r tissue .
4.Backgroun

dDocument t

o Suppor t th

e Notic e o f ProposedRulemaking Pursuant t

o CERCL

A Sectio

n102(b) . Supplementar y Report : Radionuclides . Draft , 2 4 September 1982 . Environmenta l Monitoringan d Service s Center .


### C- 3P.9 5

DCF t » Dos e conversio nfactor for tissue .

9 B R= Breathin

grat e (8. 4 x1 0 cubi c c m per year) . 9 1E 9 = 1 x1 0 . A

factor of one-billioncompose dof one-thousan

d fo r convertin

gmillire

m t o re m an done-millionfo r conversio

no f microcurie s t o curies . Thi s approachtake s int o account bothsubmersionina nairborne clou

do f radionuclide (DCFVBS ) an da summatio

nof effect s fo

r a variety

o f individua l organ s (Vt*DCFt) . Exhibi t C- l present s a fe v RQ s calculated b y thi s metho

d(RQ(LPL)) .



### C- 4

### EXHIBI T C- l RQ s CALCULATE D FRO

MMPC s AN

D LPL s P.9 6



### Radionuclide MPC" ' (uCi/ml ) LPL "

(Ci ) RQ(MPC )

(Ci ) RQ(LPL )

(Ci )

Tritiu m Argon-4 1 Calcium-4 5 Cobalt-6 0 Krypton-8 5 Strontium-9 0 Iodine-13 1 Xenon-13 3 Cesium-13 7 Uranium-23 5 Uranium-23 8 Plutonium-23 8 Plutonium-23 9 Americium-24 1 2 x1 0 4 x1 0 1 x1 0 3 x1 0 3 x1 0 3 x1 0 1 x1 0 3 x1 0 5 x1 0 4 x1 0 3 x1 0 7 x1 0 6 x1 0 2 x1 0 - 8

- 9 -1 0

- 7 -1 1

- 1

- 7

- 7 -1 2 -1 2 -1 4 -1 4 -1 2 600 0

a 

### 80 0 400 0 700 0 

### 2 5 

### 3. 3 1000 0 

### 60 0

_ a a 

### 0. 1 0. 1 0. 3 117. 4

17. 4 0.4 3 0.1 3 130. 4 0.01 3 0.04 3 130. 4 0.2 2 0.00 2 0.00 1 0.0000 3 0.0000 3 0.000 9 

### 34 5

a 

### 4. 5 0.1 4 1770 0 0.02 7 0.8 8 114 0 0.8 1 a a 0.000 1 0.000 1 0.0000 5

a ) No LP L liste

d i nNUREG-076 7

i> . 1 0 CF

RPar t 20 . 6 . op . cit. , NURE G0767 .


### C- 5P.9 7



### APPENDI XD RELEAS E FRACTION S FORINHALATION Th e releae s fraction , R , reflect s th e fractio n o f a radionuclid e releas e tha t coul d becom e airborn e and b e o f respirabl e siz e (1 0 micron s i n diamete r o r less) . Th e Nuclea r Regulator yCommissio n ha s develope d releas e fraction s fo r radionuclide s unde r acciden t condition s . Isotope s o f th e nobl e gase s argon , krypto nand xeno nhav e hav e assigne d releas e fraction s o f 1. 0 becaus e the yar e alway s gase s a t roo mtemperature , remai n mixe d wit hair , and d o no t reac t chemicall yt o formles s volatil e compounds . Th e Nuclea r Regulator yCommissio nha s assigne d a releas e fractio n o f 0. 5 t o compound s o f hydrogen , carbon , phosphorous , sulfur , and iodine . Compound s o f thes e . element s woul d b e expecte d t o produc e les s tha n10 0 percen t volatilize d and respirabl e particle s o r gase s fo r th e followin g reasons : (1 ) som e o f th e compound s o f th e -element s wil l settl e ou t o n surface s and no t b e release d t o atmosphere , and (2 ) som e particle s found i nth e releas e mayno t b e respirable . Compound s o f th e element s selenium , mercury , cesium , polonium , bromine , tellurium , and ruthenium , amon g other s ar e onl y semi-volatil e and hav e bee nassigne 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 , and americium , amon g others , hav e bee nse 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 1 . McGuire , S.A . ARegulatoryAnalysi s o nEmergenc y Preparednes s fo r Fue l Cycl e and Othe r Radioactiv e Materia l Licensees . NUREG-1140 , Jun e 1985 .



## D- lP.9 8



### o f th e particle s i n a nai r stream . Eve n finel ygroun d powder s wil l generall ycontai n les s tha n a fe wpercen t o f th e powde r i n respirabl e size . Th e fractio n o f particle s o f respirabl e siz e i s kep t smal l byth e difficult yi nproducin g smal l particle s and subsequentl ybyagglomeratio nand 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 and t o themselves . Relea e fraction s fo r th e variou s element s ma yb e found i n Exhibi t D-l . Th e inhalatio n releae s fraction s wer e take n from NUREG-1140 . -Wher e releas e fraction s fo r specifi c isotope s ar e showni n NUREG-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 n fo r a specifi c elemen t o r isotope , th e releas e fraction s wer e derive d byreferenc e t o statement s a t th e end o f th e tabl e recommendin g a releas e fractio n o f 0.0 1 fo r "an yothe r beta-gamma emitter " and a releas e fractio n o f 0.00 1 fo r "an yothe r alpha•emitter. " Rado n i s th e singl e exceptio n t o thi s rule . Rado ni s no t onl ya nobl e ga s fallin g immediatel ybelo wxeno n i nth e periodi c table , bu t th e isotope s considere d b yth e ICR P i nPublicatio n30 , radon-22 0 and radon-222 , ar e alpha emitters . Areleas e fractio no f on e wa s assigne d t o rado n becaus e o f it s similarit yt o argon , krypto nan d xeno neve n thoug hi t i s no t liste d i n NUREG-114 0 and it s isotope s ar e alph a emitters . Thi s conservativ e assumptio ndecrease s th e inhalatio n Releae s Value , and thu s th e RQ , bya facto r o f one-thousan d belo wtha t whic hwoul d hav e bee ncalculate d ha d th e rado nisotope s bee n assigne d a releas e fractio no f 0.00 1 base d o n alph a emission .



## D- 2P.9 9



### EXHIBI T D- l INHALATIONRELEAS E FRACTIONS "

Actinium Aluminum Americium Antimony Argo n Arseni c Astatin e Barium Berkelium (24 9 & 250 ) Beryllium Bismut h Bromin e Cadmium Calcium Californium Carbo n Cerium Cesium Chlorin e Chromium Cobal t Coppe r Curium Dysprosiu

m Einsteinium (254m ) Erbium Europium Fermium A c A l A m S b 

### A r A s A t B a B k
B e B i B r C d C a C f C C e C s C l C r C o C u Cm D y E s E r E u Fm Rel . Frac . Inhalatio n 0.00 1 0.01 * 0.00 1 0.0 1 1. 0 0.01 * 0.001* * 0.0 1 0.001* * 0.01 * 0.01 *

- 0.0 1 0.01 * 0.0 1 0.0 1 0.00 1 0 . 5 0.0 1 0.0 1 0.0 1 0.0 1 0.00 1 0.0 1 0.00 1 0.01 * 0.001 * 0.01 * 0.01 * 0.0 1 0.001* *
D- 3

## EXHIBI T D- l (Cont. ) p. 1



## Fluorin e Franciu m Gadoliniu

m Galliu m Germaniu

m Gol d Hafniu m Holmiu m Hydroge n Indiu m Iodine Iridiu m Iron Krypton Lanthanu

m Lead Lutetiu m Magnesiu

m Manganes e Mandeleviu

m Mercur y Molybdenu

m Neodymiu

m Neptuniu

m Nicke l Niobiu m Osmiu m Palladiu

m F

F r G d Ga G e A u H f H o H I n I I r F e Kr La Pb Lu Mg Mn M d Hg M o N d N p N i N b O s Pd Re l . Frac .

Inhalation 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . 0 . .01 * .01 * .0 1 .01 * .0 1 .0 1 .0 1 .0 1

. 5 .0 1

. 5 .00 1 .0 1 0 .01 * 01 01 * 01 * 0 1 001* * 0 1 0 1 01 * 001 0 1 01 01 * 01 *



## D- 4

### EXHIBI T D- l (Cont. ) P. 2



### Rel . Frac . Inhalatio n
Phosphoru s Platinum Plutonium Polonium Potassium Praseodymium Promethium Protactinium Radium Rado n Rhenium Rhodium Rubidium Ruthenium Samarium Scandium Selenium Silico n Silve r Sodium Strontium Sulfu r Tantalum Technetium Tellurium Terbium Thallium Thorium Thulium P P t P u P o K P r Pm P a R a R n R e R h 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 Tu t 0. 5 0.01 * 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

D- 5

## EXHIBI T D- l (Cont. ) P. 3



## Rel . Frac . Inhalation

Ti n Titaniu m Tungste n Uraniu m Vanadiu m Xenon Ytterbiu

m Yttriu m Zin c Zirconiu

m S n

T i W U V Xe Y b Y Z n Z r 0.0 1 0.0 1 0.0 1 O.00 1 0.0 1 1. 0 0.0 1 0.0 1 

## o.o i 0.0 1

Indicate s tha t the releas e fraction i s based o n NUREG-114 0 statemen t "an yothe r beta-gamm

a emitter. " the

* * Indicate s tha t th e releas e fraction i s base d NUREG-114 0 statemen t "an yothe r alph

a emitter. " o n the

1 . McGuire , S.A. , ARegulator yAnalysi s o n Emergency Preparednes s fo r Fue l Cycl e an d Othe r Radioactive Materia l Liecensees , NUREG-1140 .

D- 6 

# JP. 4



### APPENDI XE DERIVATIONO F TH E ATMOSPHERI C RELATIVE CONCENTRATIONVALU E (X/Q )

I nth e calculatio n o f reportabl e quantitie s fo r radionuclide s usin g ALIs , MPC s o r LPL s and considerin g th e inhalatio nroute , i t ha s bee n necessaryt o us e th e equation s develope d fo r atmospheri c modeling , especiall ythos e involvin g atmospheri c dispersio n estimates , i n orde r t o estimat e th e fractio no f a releas e whic h migh t b e encountere d bya n individual . Th e informatio n neede d fromatmospheri c modelin g i nth e calculatio n o f RQ s byth e abov e method s i s summarize d i nth e atmospheri c relativ e concentratio nvalue , Ch i ove r Q (X/Q) . Th e appropriat e valu e fo r X/ Q ca nb e found fromExhibi t E-l , whic hi s a nextrapolatio n o f th e grap hi n Exhibi t E-2 . Exhibi t E- 2 plot s Xu/ Q pe r squar e mete r versu s distanc e from th e sourc e i n kilometer s fo r release s varyin g i n heigh t fromground leve l (the 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 nXu/ Q stand s fo r win d spee d i n meter s pe r second . Xu/ Q i s plotte d s o tha t th e plo t ca nb e applie d t o an ywin d spee d simpl ybydividin g th e valu e found i nth e plo t byth e desire d wind speed . I nth e presen t case , a wind spee d o f 1 mete r pe r second i s use d and X/ Q i n second s pe r cubi c mete r i s found . Fo r th e purpose s o f calculatin g RQs , som e conservativ e assumption s i n derivin g X/ Q hav e bee n made . Thes e assumption s include :

1 . Turner , D . Bruce , Workboo k o f Atmospheri c Dispersio n Estimates . EP AOffic e o f Ai r Programs , 1970 .

E- lP. 5

•e. l

—o.o i

—o-.ooi

1. 0 o. i Distanc eFranSourc e(tan. ) 0.0 1 0.000 1

EXHIBI T E- l - X / Q Vs

- Distanc e fo r a Ground Leve l Release , Stabilit yClas s D .



### E- 2P. 6

Xu/ Q m • ?



### 10 0 DISTANCE , k

m

EXHIBI T E- 2 Xu/ Q Vs . Distanc e a t Variou s Height s (H ) o f Releas e (meters) ,

Stabilit yClas s D . 

### E- 3P. 7



### 1 . Th e distanc e fromth e releas e t o th e poin t o f exposur e i s 3 0 meter s (abou t 10 0 feet) . Thi s distanc e i s chose n becaus e cordon s around a releas e o f a chemica l hazardou s substanc e ar e generall y3 0 meter s i n radius . Therefore , barrier s around a releas e o f a radionuclid e i n a restricte d are a woul d likel yb e se t up a t leas t thi s distanc e fromth e release . I naddition , i t i s assume d tha t a gaussia ndistributio no f contaminan t i s establishe d almos t immediatel ywithi nth e plum e an d i s full ydevelope d a t 3 0 meters . 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 RQs . 3 . Th e poin t o f exposur e i s directl ydownwind from th e releas e i n stabl e (Clas s D ) atmospheri c condition s and th e wind spee d (u ) i s 1 mete r pe r second . 4 . Th e materia l evolve d i nth e releas e i s a stabl e ga s o r aeroso l (les s tha n2 0 micron s i n diameter ) whic h remain s suspende d i n ai r fo r long period s o f time . 5 . Th e ga s o r aeroso l i s continuousl yemitte d fromth e sourc e o r th e emissio n tim e i s equa l t o o r greate r tha n th e trave l tim e 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 no f transport . Th e equation s use d t o produc e th e graph s i nExhibit s E- l and E- 2 ar e vali d onl yi f diffusio ni n thi s directio ni s assume d b e b e zero . Thi s i s a reasonabl e assumptio nbecaus e th e rat e o f diffusio ni nthi s directio n woul 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 from th e plum e a s i t move s downwind and ther e i s complet e reflectio n fromth e ground . Bearin g thi s i n mind and referrin g t o Exhibi t E-l , i t i s possibl e

- 2 t o obtai n a X/ Q o f 7. 2 x1 0 second s pe r cubi c meter . Becaus e a breathin g rat e i n unit s o f cubi c centimeter s pe r dayi s bein g use d i t i s necessaryt o conver t X/ Q t o compatibl e units . Thi s -1 3 lead s t o a valu e o f 8. 4 x1 0 da ype r cubi c centimeter , th e valu e use d i n thi s report .

E- 4 

# JP. 8



### If , instea d o f extrapolatin g downt o 3 0 meters , th e valu e fo r on e hundre d meter s (groun d leve l release ) i s chosen , X/ Q become s 9. 5 x1 0 daype r cubi c centimeter . Thi s valu e i s almos t (bu t no t quite ) a n orde r o f magnitud e smalle r tha nth e 3 0 mete r valu e and woul d lea d t o RQ s nearl ya facto r o f te nhigher . Exhibi t E- 2 als o show s value s fo r plum e height s greate r tha nground leve l ( H

= 1 0 t o H = 3 0 0 meters) . Plum e height s ar e no t necessaril yth e sam e a s th e stac k heigh t and ar e affecte d byphenomen a suc ha s inversio n layers , win d speeds , and th e velocit yo f stac k ejecta . I nanycase , i t i s clea r fromExhibi t E- 2 tha t i f RQ s wer e t o b e calculate d o n th e basi s o f a releas e fromabov e ground level , the ywoul d b e muc hlarger . Fo r example , i nth 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 x

—1 7 1 0 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 ntha t fo r a ground leve l release . I f calculate d a t 35 0 meter s (the poin t o f maximum concentratio n accordin g t o Exhibi t E-2 ) th e valu e woul d b e 3. 5 x 1 0 daype r cubi c centimeter , a valu e mor e tha n 20 0 time s smalle r tha n th e valu e i n curren t use . Th e graph s showni n Exhibit s E- l and E- 2 and use d fo r th e determinatio n o f X/ Q ar e generate d from th 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 x,y, z froma continuou s sourc e wit ha neffectiv e emissio nheight , H , i s give n i nth e equatio n below . Th e coordinat e syste mreferre d t o ca nb e found i nExhibi t E-3 .

X(x,y,z;H ) = ; 

### ex p 2 ira O 

### u 

### yz 

# mnyn-ym

E- 5i

(0,0,0 ) 

## tK-y,Z )

(x.-y,0 )

EXHIBI T l:-3 . Coordinat e Syste m fo r Atmospheri c Modelin gShowin

gGaussianDistribution s i nth e Horizonta l an

dVertical .P.1 0



## where : 3 X= chi , concentratio n(Curies/ m) ; x,y, z = position s i n th e coordinat e syste m(se e Exhibi t

E-3) ; Q = releas e rat e (curies/sec) ; 7 r = p i (3.14159 , approximately ) ; a= horizonta l dispersivit y(meters) ; a= vertica l dispersivit y(meters) ; u = win dspee d(meter s pe r second) ; exp = exp (-a/b ) = e^~ a 

## y' wher e e i s th e bas e o f

natura l logarithm s and i s approximatel yequa l t o 2.7183 ; an d H = th e effectiv e emissio nheigh t (meters) . Severa l assumption s ar e mad e concernin g th e hypothetica l releas e whic hresul t i n th e simplificatio no f Equatio n1 . Thes e simplification s ar e shownbelow . Fo r concentration s calculate da t groun dleve l fo r a groun dleve i releas e (i.e. , z = 0 ) th e equatio nsimplifie s to : Q X(x,y,0;H ) = ex p



## T Tay 

## a z 

## u 

# iyihKT)'

] ' m

Wher e th e concentratio ni s t o b e calculate dalon g th e centerlin e o f th e plum e givin g th e maximum concentratio n(i.e. , y= 0 ) furthe r simplificatio nresults :

X(x,0,0;H ) = ex p ira a u yz 

# ["&-)' ] (3 )

E- 7P.1 1



### Fo r groun d leve l sourc e wit hn o effectiv e plum e ris e (i.e. , H = 0 ) , th e equatio nsimplifie s eve n further : Q X(x,0,0;0 ) = = r4 

### v

yz 

### Th e value s fo r dispersio n i nth e yan d z direction s ( aan d a) var ywit hth e turbulen t structur e o f th e atmosphere , heigh t abov e th e surface , surfac e roughness , samplin g tim e ove r whic hth e concentratio n i s t o b e estimated , win d speed , an d distanc e fro m th e source . Value s fo r aan d aar e estimate d fo r eac h atmospheri c stabilit yclass , whic hinclud e a nestimate d win d speed . Stabilit yclas s D , use d here , assume s a ligh t win d i n overcas t condition s durin g eithe r da yo r night , usin g Stabilit y Clas s D result s i nhighe r concentration s an d lowe r RQ s tha n woul d mor e turbulen t stabilit yclassifications . Th e estimate s fo r horizonta l an d vertica l dispersio ncoefficient s ca nb e foun d i n

. . . 2 th e Workboo k o f Atmospheri c Dispersio nEstimates . Rearrangin g Equatio n 4 , above , a s shown , an d applying.value s for . o an d a_ y* . fro mth e grap hi nExhibi t E- 4 yields , 1 7 yz Xu/ Q= = = 7.5x1 0m

TOOU"(2.6)(1.65 ) 2 - 2 (5 )



### Divisio no f bot hside s o f th e equatio nb ya win d speed , u , o f 1 mete r pe r secon d gives : X/ Q = 7. 5 xIO" 2 

### se c m" 3 

### (6 ) 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

- 2 - 3 b yreferenc e t o Exhibi t E- l (7. 2 x1 0 se c m) . 2 . Turner , D . Bruce , Workboo k o f Atmospheri c Dispersio n Estimates , EP AOffic e o f Ai r Programs , 1970 .



## E- 8P.1 2

10 0

100 0 10 0 Distanc eDownwind , aeter s

EXHIBI T E- 4 - Horizonta l an d Vertica l Dispersio nCoefficien t a s a Functio n o f Downwind Distanc e Frc mth e Source .



### E- 9P.1 3



### APPENDI XF

ROUTE S FORINGESTIONO F RADIONUCLIDE S

Tw o pathway s ar e availabl e fo r th e ingestio n o f radionuclide s leadin g t o exposur e t o th e gastrointestina l trac t and , throug h transfe r t o th e bloo d streamand depositio n i nothe r organs , exposur e t o th e remainde r o f th e body . Thes e tw o pathway s ar e consumptio n o f contaminate d drinkin g wate r and consumptio no f contaminate d foodstuffs . Becaus e eac hi s a likel ysourc e o f radionuclid e ingestion , th e Agenc yreviewe d ground-water , surface-water , and foodstuf f ingestio n t o determin e whic hi s th e mos t critica l pathway . Th e method s fo r modelin g ground-wate r contaminatio nar e discusse d i n sectio n F.l , whil e th e method s fo r modelin g surface-wate r contaminatio nand foo d cro p contaminatio n ar e presente d i n section s F. 2 and F.3 , respectively .

F. l GROUND-WATE RTRANSPOR T O F RADIONUCLIDES . Tw o ground-wate r models , th e advection-dispersio n mode l and th e simpl e dilutio n model , wer e examine d i n some detai l byth e Agenc y whil e fou r othe r model s develope d fo r specialize d purpose s withi n th e Resourc e Conservatio n and Recover yAc t (RCRA ) wer e reviewed . Thes e model s ar e describe d below .

F.l. l Th e Advection-Dispersio n Model . Th e calculatio n o f a dilutio n facto r fo r a radionuclid e release d t o ground wate r ca n b e accomplishe d b yassumin g a releas e scenari o tha t i s reasonabl yconservative . I nthi s calculatio n



## F- 1P.1 4



## i t i s assume dtha t th e releas e i s directl yt o groun dwater , whic h i s a conservativ e assumptio nbecaus e i t neglect s migratio n throug hth e unsaturate dzone . Th e followin g assumption s ar e als o made : 1 . Flo wi s unifor mandsteady( V =0. 5 meter/day) . 2 . Th e aquife r i s homogeneou s andisotropic . 3 . Th e releas e i s a ninstantaneou s poin t sourc e t o th e saturate dzone . 4 . A t tim e zero , th e concentratio no f radionuclid e i nth e aquife r i s zero . 5 . Th e aquife r i s o f finit e thicknes s andinfinit e exten t (ther e ar e n o boundarie s clos e enoug ht o affec t th e transport) . 6 . Radioactiv e deca yi s neglecte d(i.e. , X = 0) . 7 . Th e drinkin g wate r wel l i s locate d3 0 meter s dow n gradien t fro mth e poin t o f release . Fo r a ninstantaneou s poin t sourc e locate do nth e z axi s i n unifor msteadyflo w(Exhibi t F-1) , th e emalytica l solutio no f th e transpor t equatio ni s :

C = J i exp -fixrUtl 2 

## + y 2 

## + z 2 

## + \t " ( 4 t) 3/2 

## (E x 

## E y 

## E 2 

## ) 1/2 

## R d 

## n[ 4E x 

## t 4E y 

## t 4E z 

## t

where : M= magnitud e o f th e instantaneou s releas e ( 1 Ci) ;

R . = retardatio nfactor ;

n= effectiv e porosit y(0.1) ; (1 )

l.Carlsaw , H. , Jaeger , J. , Conductio no f Hea t i nSolids . Oxfor dUniversit yPress , London , 1959 .

F- 2P.1 5
EXHIBIT F- 1 

### Scenari o fo rCalculatio n ofGround-Watt rTranspor t

sio c vie w

s*.*,*..*,**.....***************..*.. y Wel l

'''''"'-' '

19999999*9

999999999999999 "W* ^ • ^ ^



### J0 «

P\JM Vl fW



### Poin tJ tt rolotto ' / Plum * • ! tim e orotto rtha n tar e ( Wol l



### F- 3P.1 6



## \ « = radioactiv e decayconstan t (0 ) ; t = tim e o f trave l fromsourc e t o wel l

, ( t = 30/(V x 

## /(nR d 

## )) ; C = maximumradionuclid e concentration ;

andE , E , E , R, , and Uar e define das :

E 

## x = D 

## xx/ R 

## d ; E 

## y= D 

## yy/ V E 

## z = D 

## z Z 

## / R 

## d ; 

## U= V x 

## /nR d 

## ; R d

## = 1 + (P b 

## )*(K d 

## /n) ; where : D = longitudina l coefficien t o f dispersion ;

D = D z z 

## = transvers e coefficient s o f dispersion ; P b

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

## ) ; V = flo wo 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 sandcontainin g aquifers 2 

## b ycompariso nt o Tabl e B- 2 i nth e repor t reference d. Thi s tabl e list s 4 5 differen t saturate dzon e layer s tha t contai nsanda t varyin g concentrations . Th e smalles t flo wliste di 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 flo wi s 62 5 meters/yea r o r abou t 1. 7 meter/day . Avalu e o f 0. 5 meters/da yi s conservativ e i ntha t i t prolong s contac t tim e and lead s t o a lowe r (mor e conservative ) Releas e Value ; and K d

## = th e sorptio ncoefficien t i nc m / g (se e Exhibi t F- 2 fo r a compilatio no f thes e values) . Dispersio ncoefficient s ar e define dbyth e followin g equations :

D 

## x x" < a 

## i)*(V n 

## > ' D 

## y y- D 

## z z = (* t 

## >*<V n 

## > ' where :

a , = longitudina l dispersivit y(2 0 meters) ;

a t 

## = transvers e dispersivit y( 4 meters) . 2 . Line r Locatio nRis k and Cos t Analysi s Model . Draf t Repor t unde r Contrac t No . 68-01-6621 , Offic e o f Soli dWaste , EPA , January , 1985 . F- 4P.1 7 

### ^_w

ELEMENT Actinium

• Aluminum

• Americium

_Antimony | Argo n Arseni c

• Astatin e Bariu m

• Berkelium

• Beryllium

—

### Bismut h | Bromin e .Cadmiu m I Calciu

m Californium

• Carbo n

• Ceriu

m

—Cesiu

m | Chlorin e Chromiu m

• Cobal t Coppe r

• Curiu

m

B 

### Dysprosiu

m

• Einsteinium Erbium

• Europium A c

A l A m S b A r A s A t B a B k B e B i 

## B r C d C a C f C C e C s C l C r C o C u Cm D y E s E r E u EXHIBI T F- 2

SORPTIONCOEFFICIENT VALUE S

SORPTION COEFFICIENT . K^ * 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 50 0

F- 5 SOURC E
EPA520/4-79-007 C Assumption* * Hajek(1966) , Knoll(1965)(1969 ) EP A520/6-78-00 7 EPA520/4-79-007 C Assumption* * EPA520/4-79-007 C Analogou s t o S r (PNWL 8/2/86 ) EPA520/4-79-007 C EP A520/4-79-007 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 ) Rhodes(1957 ) Benson(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* * Sem e & Ra i (1976 )P.1 8



### ELEMEN T Fermium Fluorin e Francium Gadolinium Gallium Germanium Gol d Hafnium Holmium Hydroge n Indiu m Iodin e Iridiu m Iro n Krypton . Lanthanum Lea d Lutetium Magnesium Manganes e Mandelevium Mercur y Molybdenum Neodymium Neptunium Nicke l Niobium Osmium Palladium Phosphoru s Fm

F F r Gd G a G e A u H f H o H I n I I r F e K r L a P b L u M g M n M d H g M o Nd
Np N i
Nb O s P d P SORPTION

COEFFICIENT . K^ * 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 0 SOURC E

Assumption* * Assumption* * EP A520/4-79-007 C Chemica l Analog yt o Rar e Eart h (PNWL 8/18/86 ) Assumption* * Assumption* * Assumption* * Assumption* * EP A520/4-79-007 C EP A520/6-78-00 7 Assumption* * Shallo wLand Buria l Program Assumption* * EP A520/4-79-007 C Iner t Ga s (PNWL 8/18/86. ) Assumption* * EP A520/4-79-007 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 ) EP A520/4-79-007 C Assumption* * Estimat e (PNWL 8/18/86 ) Assumption* *

F- 6P.1 9



### ELEMENT Platinum Plutonium Polonium Potassium Praseodymium Promethium Protactinium Radium Rado n Rhenium Rhodium Rubidium Ruthenium Samarium Scandium Selenium Silico n Silve r Sodium Strontium Sulfu r Tantalum Technetium Tellurium Terbium P t

P u P o K P r Pm P a R a R n R e R h R b
R u S m S c S e S i A g N a S r S T a T c T e T b SORPTION COEFFICIENT .

0 100-1000 0 2 5 3 5 500-100 0 1000-1000 0 400 0 100-1000 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 

# V SOURC E Assumption* * EP A520/6-78-007 , AShallo wLan d Buria l Program EP A520/4-79-007 C EP A520/4-79-007 C Chemica l Analogyt o Rar e Eart h (PNWL 8/18/86 ) Benson(1960 ) Rar e Eart h EP A520/4-79-007 C EP A520/6-78-00 7 EP A520/4-79-007 C Assumption* * Assumption* * Chemica l Analogyt o C s (PNWL 8/18/86 ) Rhode s (1957 ) Chemica l Analogyt o Rar e Eart h (PNWL 8/18/86 ) Assumption* * Shallo wLand Buria l Program Assumption* * Estimat e (PNWL 8/18/86 ) EP A520/4-79-007 C Shallo wLand Buria l Program Lette r Repor t RJS-ARCH O Assumption* * Assumption* * Shallo wLand Buria l Program Estimat e (PNWL 8/18/86 ) Chemica l Analogyt o Rar e Eart h (PNWL 8/18/86 )

F- 7P.2 0



### SORPTION ELEME N Thallium Thorium Thuliu m Ti n Titanium Tungste n Uranium Vanadium Xeno n Ytterbium Yttrium Zin c Zirconiu

m T
T l

Th Tm S n T i W U V X e Yb Y Z n Z r COEFFICIENT . K

2 1000-1000 0

0 50-10 0 0 0 1-5 0 0 0 0 50 0 0 200 0 SOURC E

EP A520/4-79-007 C EP A520/6-78-00 7 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 n ranges , th e lowes t sorptio n coefficien 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 , valu e ha s bee n obtaine d and a sorptio n coefficien t o f zer o (K d 

### =0 ) wa s assume d (no retardation) .

Bensen , D . W . 1960 . Hanford . HW-67201 . SOURCE S Revie wo f Soi l ChemistryResearc ha t Environmenta l Protectio nAgenc yRep . EP A520/6-78-007 . Ames , L . L . and Dhanpa t Rai , "Radionuclid e Interaction s wit hSoi l and Roc k Media . Environmenta l Protectio nAgenc yRep . EPA520/4-79-007C . Technica l Suppor t o f Standard s fo r Hig hLeve l Radioactiv e Wast e Management , Vol . C , Migratio n Pathways , 1979 .

F- 8P.2 1



### Hajek , B . F . 1966 . Plutoniu m and AmericiumMobilit yi n Soils . BNWL-CC-925 . Knoll , K . C . 1965 . Reactio no f Hig hSal t Aqueou s Plu s Organi c Wast e vit hSoil . BNWL-CC-313 . Knoll , K . C . 1969 . Reaction s o f Organi c Waste s i n Soils . BNWL-860 . Lette r Repor t R . J . Sem e - ARCH O 6/5/75 , a lette r writte nt o Atlanti c Richfiel d Hanfor d CompanybyW . Marti nreportin g 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 , and A . V . Robinson . 1976 . 9 9 23 7 Tc , N o 24 1 *' and A

mSorptio no n Tw o Subsoil s fromDifferin g Weatherin g Intensit yAreas . BNWL-2000 . Pt . 2 , pp . 50-52 . Seme , R . J . and Dhanpa t Rai . 1976 . Adsorption-Precipitatio n Behavio r o f E u i n Soil s an d Standar d Clays . Agronom yAbstracts , p . 132 . Shallo wLan d Buria l Program- a s ye t unpublishe d result s obtaine d o na nongoin g DO E sponsore d program . Sheppard , J . C. , J . A . Kittrick , T . L . Hart . 1976 . "Determinatio n o f Distributio n Ratio s and Diffusio nCoefficient s o f Neptunium , Americium , and Curium i n Soil-Aquati c Environments, " RL0-221-T-12-2 .

F- 9P.2 2



### Fo r a f c 

### = 2 0 meters , a , = » 4 meters, n = 0.1 , and M= 1 curie , th e maximum

concentratio n a t th e wel l is :

C = 1 (5 ) (12 0 7T) 3/2 

### (20) 1/2 

### (4)(0.1)(R d 

### )(lxlO 3 

### liters/m 3 

### )
C = 7. 6 x10" 8 

### Ci-liters"VR d 

### . (6 ) Equatio n6 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 nfacto r (DF ) fo r th e aquife r is , therefore , define d as :
D F = 7. 6 x10~ 8 

### liters" 1 

### /^ * (7 )

Th e valu e o f th e retardatio nfacto r wil l affec t no t onl yth e maximum

concentratio n o f th e radionuclide s found i n th e plum e develope d b

yth e releas e bu t als o th e tim e require d fo r th e plum e t o reac hand pas s th e well . Fo r radionuclide s wit ha sorptio n coefficien t o f zer o (K . = 0 ) and a retardatio n facto r o f on e (R d 

### =l) , th e concentratio ni nth e plum e varie s a s a gaussia n distributio n alon g al l thre e axe s (tw o horizontal , on e vertical ) o f th e ellipsoida l plume . Th e tota l quantit yo f radionuclid e release d i nth e plum e i s 1 curi e (which wa s th e amoun t o f th e instantaneou s release) . Th e concentratio n i nth e wel l wil l increas e fromzer o t o a maximumo f 7. 6 x10~ 8 

### curie s pe r lite r the ndecreas e t o zer o agai na s th e plum e passes . T o arriv e a t th e exac t tim e i t take s th e plum e t o pas s th e wel l i t i s necessar yt o defin e th e concentratio na t th e boundar yo f th e plum e because , theoretically , th e plum e extend s t o infinit y wit ha n infinitel ysmal l concentratio na t tha t distance . Th e tim e tha t i t take s fo r th e plum e t o pas s th e wel l ca nb e estimate d i n tw o ways . First , w e ca nconclud e tha t th e maximu m amoun t o f tim e necessaryfo r th e plum e t o pas s th e wel l i s twelv e

F-l lP.2 3



## day s (assumin

g tha t the firs t arriva l o f th e plume wa s instantaneous , 6 day s t o reachth e centroi d an d anothe r 6 day s t o reac hth e trailing edge) . The second , an d mor e accurat e approach , i s t o us e th e rati o o f dispersivitie s whic hmus t b e th e same a s th e rati o o f the axe s o f the ellipsoida l plume . Assuming constan t concentrationi n the plume an d using the expressio n fo r th e volume o f an ellipsoid , i t follow s that : 1 C i - (4/3)*(7T)*(a)*(b)*(c)*(7. 6 xio" 5 

## ) (8 ) where : a , ban

d c ar e th e majo r an d mino r axe s o f the ellipsoi d an d ar e related i n the sam e rati o a s the dispersivities : a/ b= a/ c = a 

## i / a 

## ^ = 

## 20/ 4 =5 . Therefore ,

b= a/5 , c = a/5 , an d 1 • - (4/3)*(7T)*(a 3 

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

## ) . . - (9 ) Solving fo r a gives :

a = 4 3 meters ,
an d th e time required fo r the ellipsoida l plume t o pas s th e wel l i s give nby :

Contac t Time (CT ) - a/(V x 

## /n ) = 9 days . (10 ) I t cantherefor e b e assumed tha t a plume wit ha constan t concen tratio no f 7. 6 x1 0 ci/lite r passe s the wel l i n approximatel y9 days . Using thes e figures , aningestion Releas e Valu e (RV ) i n curie s can b e calculated fro manAL I i n microcuries .

F-1 2P.2 4



### RV = ALI/((10)*(DF)*(WC)*(CT)*(lxl0 6 

### )) . (11 ) Where : AL I = Annua l Limit s o f Intak e fo r ingestio n

(microcuries) ;
D F = dilutio n facto r (liter s ) ;
W C = wate r consumptio n rat e o f "Referenc e Man " ( 2

liters/day) ; C T = contac t tim e (days) ; 1 0 convert s th e 5 remoccupationa l exposur e limi t t o

th e mor e conservativ e 0. 5 re mexposur e limi t fo r th e genera l public ; and 1 . x1 0 convert s microcurie s t o curies . Substitutin g th e value s fo r . DF , WC , and C T give s th e following expressio n fo r th e ingestio n Releas e Value :
RV = ALI/13.68 . (12 )
A s sorptio n coefficient s ris e abov e abou t 4 (K d 

### >4) , th e tim e necessar yfo r a radionuclid e t o reac hand pas s a wel l 3 0 meter s fromth e poin t o f releas e become s greate r tha n36 5 days , thu s increasin g th e contac t time . Becaus e ALI' s dea l wit hannua l limit s o f intak e i t i s no t necessaryt o us e contac t time s greate r tha non e yea r an

d th e contac t tim e fo r al l radionuclide s wit h sorptio n coefficient s o f 4 o r greate r wer e take n t o b e 3 6 5 days . Unde r thes e circumstance s ingestio n Releas e Value s ar e calculate d a s follows :

F-1 3P.2 5



### RV = ALI/((10)*(7. 6 xIO" 8 

### liters" 1 

### /^) * ( 2 liter/day )

*(36 5 day)*( l xIO 6 

### uCi/Ci)) ; (13 )

RV = ((ALI)*(R d 

### ))/555 . (14 )
I t i s importan t t o not e tha t th e us e o f retardatio n factor s (R. ) i nth e calculatio n o f th e Releas e Valu e introduce s som e inheren t uncertaintie s particularl ywit hrespec t t o th e sorptio n coefficient s (K. ) use d t o calculat e retardatio nfactors . Thes e uncertaintie s i n K . value s include : (1 ) th e tw o tes t method s use d t o evaluat e K d

### fo r a give n elemen t i nth e laborator yofte n yiel d differen t value s fo r th e sam e soi l material , (2 ) variation s i nth e soi l typ e affec t K . value s (the aquife r modelle d assume d sandysoil s and sorptio n coefficient s fo r sand ysoil s wer e use d here) , (3 ) ther e appear s t o b e n o genera l agreemen t i nth e scientifi c communit yo nth e "correct " value s fo r sorptio n coefficient s regardles s o f th e soi l type . I t ha s bee nbrough t t o th e Agency' s attentio ntha t solubilit y dat a migh t be . use d independen t o f o r i n conjunctio n wit h retardatio n factor s i n orde r t o calculat e ingestio n Releas e Values . Althoug hsolubilitie s o f nearl yeverycompound o f nearl y ever yelemen t i n th e periodi c tabl e ar e availabl e i nth e literature , i t doe s no t appea r possibl e t o defin e a "typical " solubilit yfo r eac hradionuclid e i nthei r wid e variet yo f chemica l forms . Calculatin g a Releas e Valu e fo r eac hpossibl e chemica l formo f eac hradionuclid e woul d lead t o a plethor a o f Releas e Values . Choosin g th e lowes t Releas e Valu e amon g th e differen t chemica l form s o f a particula r radionuclid e i norde r t o b e conservativ e woul d b e equivalen t t o choosing th e mos t solubl e compound , and i n th e majorit yo f cases , produc e a Releas e Valu e unchange d from

tha t found ignoring solubilit yconsiderations . Additionally , th e solubilit yo f mos t compound s i n wate r (purified , p H = 7 ) i s greate r tha n th e concentration s calculate d byth e ground-wate r transpor t equatio n leading t o a situatio ni n whic hth e amoun t o f materia l solubl e i nwate r woul d almos t alway s

F-1 4P.2 6



### b e greate r tha nth e amoun t require d t o delive r a nALI . F.l. 2 Th e Simpl e Dilutio n Model . Th e Nuclea r Regulator yCommissio nha s suggeste d a simpl e dilutio n mode l fo r th e calculatio n o f Releas e Value s base d o nground-wate r transport . Thi s mode l wa s develope d i norde r t o determin e th e maximumconcentration s fo r on-sit e disposa l o f lo wleve l nuclea r wast e and t o identif ysite s suitabl e fo r th e disposa l o f nuclea r waste . 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 . Althoug hthi s approac hma yb e appropriat e fo r th e minimizatio no f risk , i t appear s inappropriat e fo r th e determinatio n o f RQ s whic hsimpl yac t a s trigger s fo r notificatio n o 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 Regulator yCommissio n fo r thei r calculation s usin g th e simpl e dilutio nmode l ar e shown below . 1 . Ground-wate r flo wrate s ar e betwee n0.000 5 and 0.0 3 meters/day . 2 . Longitudina l dispersivitie s ar e betwee n0.0 5 and 0. 1 meter . 3 . Transvers e dispersivitie s ar e zero . 4 . Pumpin g rate s ca nvar ybetwee n770 0 cubi c meters/yea r and 2,000,00 0 cubi c meters/year . Th e forme r figur e i s preferre d byth e Commissio nbecaus e i t represent s th e minimu mpractica l need s o f a singl e perso ni na rura l area .

. 5 

### 5 . Wate r consumptio n i s 2 liters/dayfo r a nindividua l . 5 . Oztunali , O.I. , Roles , C.W. , DeMinimi s Wast e Impact s Analysi s Methodology . NUREG/CR-3585 , February , 1984 .

F-1 5P.2 7



### Usin g thes e assumptions , th e aquife r resemble s a ver yslo w flowin g pipelin e betwee nth e poin t o f releas e and th e well . Th e flo woccur 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 tim e (CT ) is , therefore , 36 5 days . Th e dilutio nfacto r (DF ) i s calculate d below :
D F = 1/770 0 m 3 

### - 1. 3 x10~ 4 

### m~ 3 

### = 1. 3 x10~ 7 

### liter" 1 

### (15 ) Usin g thes e figures , a Releas e Valu e (RV ) i ncurie s ca nb e calculate d froma n AL I i nmicrocuries . RV • ALI/((10)*(1. 3 x10~ 7 

### /liter)*( 2 liter/day)*(36 5 day) * (16)



### ( 1 x10 6 

### uCi/Ci)) . RV = ALI/949 . (17 ) 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 n thos e calculate d byth e advection-dispersio n mode l i n th e cas e wher e sorptio n coefficient s (K. ) ar e equa l t o zero . F.l. 3 Othe r Ground-Wate r Models . Th e EPA' s Offic e o f Soli d Wast e ha s develope d severa l ground-wate r model s whic hhav e found applicatio ni nanalyse s develope d fo r th e Resourc e Conservatio nand Recover yAc t (RCRA) . Althoug hothe r model s hav e bee n develope d withi nRCRA , th e followin g fou r hav e bee nanalyze d and compare d t o thos e use d fo r th e developmen t o f RQ s base d o na 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 n healt hrisk s and 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 and Cos t Analysi s Mode l use d t o estimat e th e huma nhealt hrisk s o f land disposa l

F-1 6P.2 8



### facilitie s o f differen t design s i n differen t environmenta l settings ; o Th e Threshol d Mode l use d i n determinin g th e nee d t o ba n o r restric t hazardou s wast e fromland disposal ; and o Th e Vertica l and Horizonta l Sprea d (VHS ) Mode l use d i n analyzin g ground-wate r transpor t issue s associate d wit h delistin g petition s (i.e. , petition s t o remov e a substanc e fromRCRA' s hazardou s substanc e list) . Th e followin g discussio n compare s thos e fou r RCR Amodel s t o th e R Q ground-wate r mode l i n term s of : (1 ) th e basi c equation s use d i neac hmodel ; and (2 ) value s fo r th e inpu t variable s use d i n th e equations .

F.l.3. 1 Compariso n o f Mode l Equations . Al l simpl e ground-wate r transpor t model s —includin g th e transpor t model s use d i n th e R Q adjustmen t methodology , th e CRAM , th e Line r Locatio n Model , th e Threshol d Model , and th e VH S Mode l

—ar e base d o n th e sam e law s o f physic s and , a s such , ar e base d o ntranspor t Equatio n 1 . Th e onl ydifferenc e i nth e models ' equation s i s th e releas e scenari o use d i n developin g th e analytica l solutio n t o th e transpor t equation . Thes e releas e scenario s var yi ntw o respects . First , th e configuratio no f th e contaminan t sourc e ca nvary ; 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 bein g modele d ca nb e release d i ndifferen t tim e frames ; i t ca n b e release d instantaneously , continuously , o r a t a variabl e rate . Everythin g els e bein g 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 ndifferen 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 nExhibi t F-3 .

F-1 7P.2 9



### EXHIBI T F- 3

SOURC E CONFIGURATION S AND CONTAMINANT RELEAS E RATE S ASSUME D I NTH E RCR AAN D R Q MODE L EQUATION S

Mode l Contaminan t Sourc e Configuratio n Contaminan t Releas e Rate s

R Q Mode l CRAM 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

F-1 8P.3 0



### Th e selectio n o f instantaneou s releas e fo r th e R Q mode l wa s base d o nth e consideratio ntha 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 y rathe r tha ncontinuousl yo r a t som e 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 no f radioactivit 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 n th e othe r hand , a ninstantaneou 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 n instantaneou s released . 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 ywel l fo r a longe r perio d o f time . I ncomparin g th e differen t contaminan t sourc e configurations , 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 curi e i nth e R Q ground-wate r model , i s a t th e outse t concentrate d int o a singl e poin t and 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 h and width . Whethe r on e i s mor e conservativ e tha nth 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 fromth 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 developin g a n R 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 modelin g chroni c release s froma surfac e impoundmen t o r landfill .

F.l.3. 2 Compariso n o f Value s fo r Inpu t Variables . Th e primar yinpu t variable s i nth e R Q ground-wate r mode l are :

F-1 9P.3 1



### o Aretardatio n factor , whic htake s int o accoun t ho wmuc ha contaminan t i s retarde d (throughsorptio nbysoi l and othe r mechanisms ) relativ e t o th e transportin g 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 ; and o Th e distanc e t o th e neares t wate r suppl ywell . 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 n th e RCR Aground-wate r models, ar e presente d i n Exhibi t F-4 . A s showni nthi s exhibit , ou t o f th e fou r RCRAmodel s considered , al l bu t on e (the VH S model ) tak e int o accoun t contaminan t retardation . A s shown i nExhibi t F-4 , th e value s use d fo r velocity , aquife r thickness , and porosit yi n th e R Q ground-wate r mode l ar e i n th e rang e o f "thos e commonl yuse d byth e RCR Amodels . However , th e value s fo r dispersivit y(bothlongitudina l an d transverse ) use d i nth e R Q mode l ar e significantl yhighe r tha nthos e use d i nth e RCRAmodels . Th e value s o f longitudina l and transvers e dispersivit yreporte d i nth e literatur e var ywidely . Dispersivit yvalue s hav e bee n obtaine d fo r differen t soi l type s throughfiel d measurements , laboratoryexperiments , an d fromth e calibratio no f numerica l model s (i.e. , calibratio n o 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 laborator yar e th e lowest , fiel d measure d value s ar e generall yintermediat e i nsize , and th e mode l derive d value s ar e usuall yth e highest . Laboratory measure d value s o f dispersivit yar e ofte ns o lo wtha t the yar e frequentl yconsidere d unrealistic ; mode l derive d value s ar e considere d mor e realisti c tha n thos e measure d i nth e laboratory ,

F-2 0EXHIBI T F- 4
VALUE S OF INPU

T VARIABLE S USE D I

NTN E RCR AAN D
R Q GROUND-WATE RMODEL S

Mode l Retardatio na / Ground-Wate r Velocit y (mday ) Aqu i fe r

Thicknes s (m ) Porosit y

(dimensionless ) Longitudina l Dispersivit y (m ) Transvers e

Dispersivit y (m ) Distanc e

t o Wel l (m )

t ts ) R

Q Mode l CRA M Liner-Locatio n Threshol d Mode l
VH S Mode l n o ye s ye s ye s

n o 0. 5

<2 5 0.003-2 8 <2 5 N/ Ad / 2 0 5 3 b / 3 0 3-56 0 thick enoug

h s o a s t o impede d l no t sper s o n 0. 1 0.35-0.5 6 0.01-0. 3 0.3-0. 6 N/ A61 2 0

1. 8 6 5 2 2 . 8 4

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

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

a / Value s for retardatio n factor s ar e no t given ; instead the tabl e indicate s whethe r the mode l consider s retardation . b / InCRAM , saturate d aquife r thicknes s ha s anexponentia l probailit ydistributio nwit ha mean o f 53 . c / Thes e ar e the shortes t distance s t o well s use d b ythe models : the dispersivit yvalue s reported , whic har e dependen t o n distance , ar e based o nthes e minimu mdistances , d / No t applicable ; velocit yan d porosivit yar e no t use d inthe VH S model .P.3 3



### bu t no t a s realisti c a s thos e measure d i n th e field . Exhibi t F- 5 present s fiel d 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 claytha t ar e no t boun d o r hardened) . I ncomparin g th e dispersivit yvalue s use d i n th e R Q mode l t o th e value s i nExhibi t F-5 , th e R Q model' s value s ar e o nth e hig hsid e fo r fiel d measure d value s and o n th e lo wsid e fo r mode l calibratio n values . EP Aconsider s th e dispersivit yvalue s use d i nth e R Q mode l t o b e realisti c fo r a n alluvia 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 nth e value s obtaine d from the"mode l calibrations . Th e model s develope d byth e EP AOffic e o f Soli d Wast e fo r applicatio n t o RCRAar e ris k base d and a s suc har e believe d t o b e mor e conservativ e tha n necessar yfo 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 n mode l fo r determinatio n o f Releas e Value s base d o na ground-wate r ingestio nscenario .

F. 2 SURFAC E WATE RTRANSPOR T O F RADIONUCLIDES . T o mode l th e ingestio no f contaminate d surfac e water , th e Agenc y chos e th e surface-wate r transpor t mode l use d i n th e RCR A Risk-Cos t Analysi s Mode l and presente d fo r us e i nconductin g 7 

### exposur e assessment s a t Superfund site s : 6 . 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 byIC F Inc. , 1984 . 7 . U.S . Environmenta l Protectio n Agency , Offic e o f Emergenc yan d Remedia l Response , "Superfund Exposur e Assessmen t Manual, " Draft , prepare d b

yVersa r Inc. , 1986 .

F-2 2P.3 4



### EXHIBI T F- 5
FIEL D MEASUREMENT AN D MODE L CALIBRATIONVALUE S FO RDISPERSIVIT YFORALLUVIA L AQUIFER S

Settin g Fiel d Measurement s

Longitudina l Dispersivit y Transvers e

Dispersivit y 

## Cm ) Mode l Calibratio nValue s

Longitudina l Transvers e Dispersivit yDispersivit y m ; rm ) Chal k River , Ontari o 0.034-0. 1

Lyons , Franc e 0.1-0. 5 Alsace , Franc e 1 2
Barstow , CA RockyMountai n Arsena l 15. 2 1 5 6 1 30. 5 1 8

30. 5

Arkansa s Rive r Valle y 30. 5 9. 1

Californi a 30. 5 9. 1 Sutte r Basin , CA 80-20 0 8-2 0 Source : Table s 4. 1 and 4. 2 i n Codell , R . and Duigid , J. ,

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

F-2 3P.3 5



### C = Q 

### exp(-Kx/u ) (18 )

where :

Q F K

X 

### u downstreamcontaminan t concentratio n a t positio n x

(Ci/L ) ; contaminan t releas e rat e (Ci/d) ; surfac e wate r flo wrat e (L/d) ; contaminan t decayconstan t i nsurfac e wate r fo r physica l and chemica l processe s (1/sec) ; downstreamdistanc e (m) ; and mea n streamvelocit y(m/s) . Equatio n 1 8 applie s t o river s and lake s an d assume s complet e contaminan t surface-wate r mixing , steadystat e conditions , and n o longitudina l dispersio n(i.e. , n o dispersio ni nth e directio no f flow) . Because"o f thie large r volume s typicall yassociate d wit h lake s use d a s source s o f drinkin g water , th e surfac e wate r flo w rate , F , fo r a lak e woul d generall yb e large r tha n tha t o f a river , and th e concentratio n a t th e poin t o f exposur e woul d b e muc hsmaller . Therefore , t o b e mos t conservative , th e Agenc y base d it s surface-wate r ingestio nscenari o o na releas e int o a river . T o compar e th e surface-wate r mode l give n i nEquatio n 1 8 wit hth e ground-wate r mode l give n i n Sectio nF.l.l , th e Agenc yconsidere d a on e curi e releas e ove r a perio d o f on e day( Q = 1 Ci/d) , an d evaluate d th e downstreamconcentratio na t a distanc e o f 3 0 meters . Th e contaminan t decayconstan t i s determine d fromth e relatio n K = (0.693)/(th e radionuclid e half-life) . Becaus e th e ground-wate r mode l assume s n o decay , th e half-lif e i s se t equa l t o infinit yi n th e surface-wate r analysi s (i.e. , n o decayi s considered) . Usin g a shorte r half-lif e result s i n a lower , henc e les s conservative , downstreamconcentration . Becaus e a ninfinit e

F-2 4P.3 6



### half-lif e i s used , th e exponentia l term i nEquatio n1 8 equal s 1 and th e downstreamconcentratio ni s independen t o f th e mea n streamvelocit yand downstreamdistanc e (i.e. , specifyin g value s fo r u and xi s no t necessary) . Finally , a conservativ e flo w 9 8 rat e fo r a smal l rive r o f 1 x1 0 liter s pe r dayi s use d . Substitutin g thes e value s i nEquatio n1 8 yields :

c 

### = ( 1 c 

### V d a 

### y > * exp(-O ) (19 )

( 1 x10 s 

### L/day ) C = 1 xIO" 9 

### Ci/ L (20 )
A s discusse d i n Sectio n F.1.1 , a on e curi e releas e int o ground wate r wit hn o retardatio n (i.e . K . = 0 ) result s i n a downgradien t

— 8 contaminan t concentratio n o f 7.6x1 0 Ci/ L a t 3 0 meters . Thi s i s th e maximumconcentratio ncalculate d byth e ground-wate r mode l becaus e introducin g retardatio n(i.e. , K d

### > 0 ) result s i n smalle r downgradien t concentrations . I nbot hth e ground-wate r and surface-wate r scenarios , th e amoun t o f radioactiv e materia l ingeste d i s th e produc t o f th e contaminan t concentration , th e drinkin g wate r intak e rat e o f "Referenc e Man, " and th e lengt ho f tim e ove r whic ha nindividua l drink s th e contaminate d wate r (the contac t time) . Th e drinkin g wate r intak e rat e fo r "Referenc e Man " i s 2 liter s pe r day , independen t o f th e sourc e o f th e water . Assumin g contac t time s ar e th e sam e fo r bot hth e surface-wate r and ground-wate r scenarios , th e ground-wate r scenari o wit hn o retardatio n predict s a large r intak e o f radionuclide s (becaus e th e groun d wate r concentratio n i s higher ) an d i s therefor e th e mor e critica l ingestio n pathway . However , becaus e ground-wate r 9 move s muc hmor e slowl ytha n surface-wate r (0. 5 m/da ycompare d t o

4 5. 5 x1 0 m/day) , th e contac t tim e betwee nth e contaminate d groun d wate r and th e wel l wil l b e muc hlonge r tha n tha t betwee n U.S . Environmenta l Protectio nAgency , Offic e o f Soli d Waste , "Th e RCRARisk-Cos t Analysi s Mode l Phas e II I Report, " prepare d byIC F Inc. , 1984 . 4 Th e surface-wate r velocit yo f 5.5x1 0 m/ d fo r a smal l rive r i s a conservativ e valu e take nfromth e RCR ARisk-Cos t Analysi s Mode l Phas e II I Report . F-2 5P.3 7



### th e contaminate d surfac e wate r and th e poin t o f intak e fromth e river . Therefore , a nindividua l i s expecte d t o b e expose d t o contaminate d ground wate r fo r a longe r perio d o f tim e and , eve n i f concentration s wer e equal , th e ingestio no f contaminate d ground wate r woul d resul t i n a significantl ylarge r intak e o f radionuclides . Becaus e th e ground-wate r model , wit hn o retardation , predict s bot ha large r concentratio nand a greate r contac t tim e tha n th e surface-wate r model , th e ingestio no f radionuclide s throug hcontaminate d ground wate r i s a mor e critica l pathwa ytha n th e consumptio no f contaminate d surfac e water . I nth e abov e example , retardatio no f radionuclide s movin g i n ground wate r i s assume d t o b e negligible . Referin g t o Exhibi t F- 2 indicate s tha t th e majorit yo f radionuclide s liste d experienc e n o retardatio n (i.e. , K d

### = 0) . Th e ground-wate r scenari o is , therefore , th e mor e critica l ingestio npathwayfo r thes e radionuclides . Fo r radionuclide s whic har e retarde d by soils , reviewin g th e ground-wate r transpor t equation s o f Sectio n F.1. 1 show s tha t th e contac t tim e increase s and th e downgradien t concentratio n decrease s wit hincreasin g radionuclid e retardation . I t ca n b e showntha t th e contac t tim e increase s mor e tha nth e concentratio ndecreases , s o tha t th e tota l intak e rise s wit ha n increas e i n retardation . However , becaus e th e ALI' s ar e base d o n a on e yea r intake , th e tota l contac t tim e fo r thi s analysi s i s limite d t o on e yea r fo r larg e K , value s and th e tota l intak e i s reduce d whe n retardatio neffect s ar e pronounce d (i.e. , larg e K d 

### ) . Includin g retardatio neffect s result s i n a lowerin g o f th e tota l intak e bya n amoun t tha t i s proportiona l t o 1/K, . From Exhibi t F-2 , th e larges t (i.e. , leas t conservative ) radionuclid e K d

### valu e i s 10,00 0 and th e maximumconcentratio n predicte d byth e ground-wate r mode l woul d b e reduce d t o approximatel y1 x1 0 Ci/L , whic hi s tw o order s o f magnitud e smalle r tha nth e concentratio n predicte d byth e surface-wate r model , 1 x1 0 Ci/L . Fo r th e tw o model s t o predic t equa l ingestio no f radionuclides , th e contac t tim e fo r th e ground-wate r scenari o

F- 2 6P.3 8



### woul d hav e t o b e approximatel ytw o order s o f magnitud e longe r tha ntha t i n th e surface-wate r scenario . However , th e approximat e fiv e orde r o f magnitud e large r surface-wate r 4 velocity , compare d t o th e ground-wate r velocit y(5.5x1 0 m/ d an d 0. 5 m/d , respectively) , indicate s a severa l orde r o f magnitud e longe r contac t tim e fo r th e ground-wate r scenario . I t i s therefor e likel ytha t th e tota l radionuclid e intak e fo r th e ground-wate r scenari o wil l b e large r tha n tha t fo r th e surface-wate r scenari o i n everycase , irrespectiv e o f th e limitatio n place d o ncontac t time . Whil e retardatio n ma yreduc e th e ne t radionuclid e intak e predicte d i n th e ground-wate r scenario , comparin g th e leas t conservativ e ground-wate r scenari o t o a conservativ e surface

wate r scenari o show s tha t th e consumptio no f contaminate d ground wate r i s likel yt o b e a mor e critica l ingestio n pathwa ytha n consumptio n o f contaminate d surfac e water , regardles s o f retardatio neffects . Therefore , a ningestio n scenari o base d o n th e consumptio n o f contaminate d ground wate r wil l predic t lowe r Releas e Value s and i s mor e protectiv e t o huma n healt hand welfar e tha na scenari o base d o n th e consumptio no f contaminate d surfac e water .

F. 3 TRANSPOR T O F RADIONUCLIDE S T O FOO D CROPS . 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 afte r a natmospheri c radioactiv e releas e . Thes e model s typicall ybegi n wit ha n estimat e o f th e radionuclid e ai r concentratio n abov e th e foo d 10 . Nair , S. , Model s fo r th e Evaluatio no f Ingestio nDose s From th e Consumptio n o f Terrestria l Food s Followin g a nAtmospheri c Radioactiv e Release . Centra l Electricit yGeneratin g Board , Berkele yNuclea r Laboratories , England , April , 1984 .

F-2 7P.3 9



### cro p o r pastur e and subsequentl ycalculat e th e radionuclid e concentratio ni no r o nth e foo d crop . Th e leve l o f contaminatio n depend s upo n manyfactor s includin g th e rat e a t whic hth e radionuclid e i s deposited , th e fractio n retaine d byth e plan t leaf , th e area l densit yo f th e crop , and th e transfe r rat e betwee n soi l an

d crop . Thes e equation s generall yinclud e compartment s describin g mechanism s fo r remova l o f radionuclide s fromcrop s throughweatherin g and radioactiv e decay . i n addition , model s hav e bee n develope d whic hdescrib e th e transpor t o f radionuclide s t o ma n throug hmil k (the so-calle d air-grass-cow-milk-ma nroute) , meat , and vegetabl e crops . Th e Agenc yha s decide d t o focu s o n th e latte r route ; exposur e o f man throug hth e consumptio n o f contaminate d vegetabl e crop s becaus e radionuclide s deposite d o n vegetable s ar e ingeste d directly . Fo r mil k and meat , onl ya fractio no f th e radionuclide s consume d b y cow s ar e transfere d t o mil k o r mea t and human s ar e expecte d t o inges t a smalle r quantit yo f radionuclide s throug hthes e pathways . Tw o approache s fo r modelin g th e concentratio n o f radionuclide s o n vegetabl e crop s afte r a nairborn e releas e wer e evaluated . Th e firs t use d a n equatio npublishe d byth e Nationa l Counci l o n Radiatio n Protectio nand Measuremen t (NCRP ) and th e second a n equatio n develope d b yth e Nuclea r Regulator yCommissio nand recommende d bythemfo r calculatio no f dose s t o individual s and populations . F.3. 1 Th e NCR P model. 1 1 

### 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 and , throug h 11 . Screenin g Technique s fo r Determinin g 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 and Measurement , Marc h31 , 1986 .

F-2 8P.4 0



### a serie s o f screenin g calculations , ai d i n th e desig no r redesig n o f facilitie s handlin g 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 incorporate s a termfo r depositio nrat e o f radionuclide s fromai r t o crop s tha t i s ver ylarg e compare d t o th e Nuclea r Regulator yCommissio n mode l (se e below) . Becaus e o f th e highl y conservativ e natur e o f th e NCR P mode l th e Agenc ybelieve s tha t i t i s inappropriat e fo r calculatin g Releas e Value s and establishin g propose d RQs . 1 2 F.3. 2 Th e Nuclea r Regulator yCommissio nmodel . Th e Nuclea r Regulator yCommissio n mode l i s simila r t o th e NCR P mode l i n tha t i t estimate s th e concentratio no f radionuclide s i n vegetatio n produce d bydepositio nont o th e plan t foliag e fromai r and byuptak e fromactivit yinitiall ydeposite d o nth e ground . Th e mode l i s vali d fo r particulat e radionuclide s excep t tritium and carbon-14 . Differen t value s ar e give nfo r th e variou s parameter s t o allo wth e us e o f th e equatio nfo r differen t purpose s suc ha s estimatin g concentration s i n produc e consume d b y man ; i n leaf yvegetable s consume d byman ; o r i nforag e consume d byanimal s and " converte d t o mea t o r mil k consume d byman . Th e equatio n allow s fo r th e tim e perio d tha t crop s ar e expose d t o contaminatio n durin g th e growin g seaso n and therefor e ca nb e applie d t o episodi c releases . Severa l assumption s ar e mad e i n applyin g thi s mode l t o th e specifi c circumstance s o f releas e considere d here . The yare :

12 . Calculatio no 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 h 1 0 CF RPar t 50 . Appendi xI . Nuclea r RegulatoryCommission , Regulator yGuid e 1.109 , October , 1977 .

F-2 9P.4 1



### 1 . The releas e i s anepisodi c releas e an dal l radionuclide s whic har e goingt o becom e airborn e an

dbe subjec t t o depositiono no r nea r a cropar e releasedin one day . 2 . The portiono f the releas e tha t become s airborn e an di s subjec t t o depositiono nthe cropi s specifie db y the releas e fraction , R(see appendi xDfo r a discussio no f releas e fractions) . 3 . Radioactive decay a s a mechanism fo r remova l radionuclide fro

m the cropi s ignored . 

## of

4 . The exposedvegetabl e cropi s located3 0 meter s fro m the point o f releas e an dthe contaminate dfoo di s consumedo

na dail y

basi s b

y anindividua l for 6 0 day s (th e lengtho f the growingseason) . Th e equatio nusedb y the Nuclea r Regulatory Commissionalongwit h a descriptio nof- the variable s i s show nbelow :

C = d . I V 1 

### r[ l - exp(-X Ei 

### te 

### ) ] Biy 

### [ l - exp( - \.t b 

### )] '

Y 

### v X 

### E i p\ . exp(-\ i 

### t h 

### ) (21 )

where :

C 

### i v th

e concentrationo f radionuclid e i i nthe vegetation(Ci/kg) ;

d 

### i the depositionrat e o f radionuclid e i (1/ m -day) , thi s ter

m i s calculatedfro m the equationbelow : 

## d i 

## = (SiHQi )

F-3 0P.4 2



## wher e b_i s the relative depositio no f radionuclide i , considerin g depletion i n transi t

~ 5 

### —2 

## t o the poin t o f deposition(1. 7 x1 0 m ) an d Q . the tota l radionuclide emission rat e (assumed t o b e 1 Ci/day) ; r = the fractiono f deposited activityretained on

crop s (0.25 , dimensionless) ; Y= the agricultura l productivity(yield) , i nkg/m 2 

## v (we t weight) ; \-. - the effective remova l rat e constan t for E l 

## radionuclide i fro mcrop s i n l/day , wher e X 

## E i = 

## ^ i + 

## X w 

## ? XJ = Th e radioactive deca yconstan t (taken a s zero) ; X w

## = Th e remova l rat e constan t fo r physica l los s b y weatherin

g calculated on the basi s o f a weathering half-lif e o f 1 4 day s ( X w

## = 0.693/1 4 day s = 0.0495/day) , t = i s the time period tha t the crop s ar e exposed t o

contamination durin g th e growin

g seaso n( 1 day) ; B J = th e concentrationfacto r fo r uptak e o f

radionuclide i fro msoi l b

yedibl e part s o f crop s ;
13 . Bae s III , C.F. , Sharp , R.D . Sjoreen , A.L. , Shor , R.W. , A Reviewan

d Analvsi s o f Parameter s fo r Assessin g Transpor t o f Environmentall yReleased Radionuclide s Throug hAgriculture . ORNL-5786 , Oak Ridg e Nationa l Laboratory , September , 1984 , Pag e 10 .

F-3 1P.4 3



## P - th e effectiv e surfac e densit y fo r soi l (24 0 kg/m 2 

## , dry weight) ; t b

## = i s th e perio do f tim e whic hth e soi l i s expose dt o contaminatio n( 1 day) ; an d t n

## = time interva l betwee nharves t andconsumptio no f

food(zero days) . Assumin gno radioactiv e decay (X ^ • 0 ) Equation . 2 1 simplifie s to : /r[ l - exp(-X

w

## t ) ] B . \ c =d. ( JL£_ + 

## _LL ) (22 )

v w Th e relativ e depositio n(£., ) o f radionuclid e i s estimate dfro m th e relativ e depositio nrat e (se e Exhibi t F-6 ) by extrapolatio n t o 3 0 meter s andrecognizin gtha t th e curv e approache s 2. 0 x10~ 4 

## pe r mete r asymptotically . I norde r t o complet e th e calculatio n o f th e relativ e deposition , i t i s necessar y t o calculat e th e lengt ho f th e ar c subtende dby a 22. 5 degre e ( 2 7T/1 6 radians ) angl e 3 0 meter s fro m th e poin t o f releas e o f th e radionuclid e an d divid e th e valu e recovere dfro m extrapolatio no f Exhibi t F- 6 b y thi s number . Th e angl e o f 22. 5 degree s i s chose nbecaus e wind directio nfo r meteorologica l modelin gpurpose s i s determine db y dividin gth e compas s ros e int o 1 6 equa l segments . Eac ho f thes e segment s ha s a ninterna l angl e o f 22. 5 degree s (1 6 time s 22. 5 equal s 360) . Applicatio no f simpl e trigonometr y a s show

nbelow

14 . Method s fo r Estimatin gAtmospheri c Transpor t andDispersio n o f Gaseou s Effluent s i nRoutin e Release s fro m Light-Water-Coole dReactors . Regulator y Guid e 1.111 , Nuclea r Regulator y

Commission , July , 1977 , Pag e 1.111-21 .

F-3 2P.4 4



### 1 0 - 3



### 10 '

ca UJ U J S OS U J C L U J

in 

### O a . U J Q 

### u > .
UJ za 

### 1 0

1 0

1 0 •1 a^a p •_ •»•«.••» •m — ••i —i i —

i — —— « —— —- ' •I

M j w— ——•* > •_«_« « a^MMaaaaM^ M



### 0. 1 1. 0 10. 0 PLUM E TRAVE L DISTANC E (KILOMETERS ) 

### 100. 0

EXHIBI TF-6
. Relativ eDepositio nfo r Ground-Leve lRelease s (Al lAtmospheri c Stabilit yClasses ) Source : Referenc e1 4 F-3 3P.4 5



## give s a valu e fo r thi s ar c lengt ho f 11. 8 meters . Th e ter m61,

- 5 - 2 therefore , ha s th e valu e 1. 7 x1 0 m, and , fo r Q . = l/day , d i 

## = 1. 7 x10" 5 

## /m 2 

## -day

S = rd S = (3 0 meters)*(2pi/16 ) S =11. 8 meter s
Substitutin

g th e appropriat e value s int o Equation2 2 gives :

c 

### i v = (2,0 7 x10 

### " 6 + 7 

### * 0 8 x10 

### ~ 8B 

### iv ) 

### * (?3 

### > 

## Equation2 3 describe s the transfe r o f radionuclide s fro mai r t o food crops . Dividin g bot hside s o f Equatio n 2 3 b yth e magnitud e o f th e releas e ( 1 curie ) define s th e dilutio n facto r (DF ) fo r food crops < DF - (2.0 7 XIO" 6 

## + 7.0 8 X10~ 8 

## B iv 

## )kg" 1



## . . . (24 ) Releas e Value s fo r ingestion o f contaminate d drinking wate r have been"calculate d b

yapplication o f Equatio n 2 5 show n below(se e section F.1.1 , Equation11) : R V = ALI/((10)*(DF)*(CT)*(WC)*( 1 XIO 6 

## ) ) (25 ) where : R V = Releas e Valu e (curie) ; AL I = annua l limit s o f intak e fo r ingestion (microcurie )

foun d i nICRP Publication 30 ; DF = th e dilutionfacto r (1/kg) ;

F-3 4P.4 6



### W C = th e dail ywate r consumptio n o f referenc e ma nwhic h

i s replace d her e byth e valu e fo r leaf yvegetabl e consumptio n(FC ) o f th e maximall yexpose d adul t (referenc e 12 , pag e 1.109-40 , 0.17 5 kg/day) ; C T = contac t time . Thi s mus t b e calculate d i na n

entirel ydifferen t manne r tha ntha t use d fo r th e ingestio no f contaminate d water . A nindividua l ingest s contaminate d vegetable s ove r a perio d o f 6 0 day s (the growin g season ) whic hwer e contaminate d bya nepisodi c releas e o nda yone . Ignoring radioactiv e deca ya s a metho d fo r "removin

g contaminatio n and considerin g onl y remova l b

ybiophysica l processe s (weathering) , contaminatio n o f vegetabl e cro p decline s exponentiall ydurin g th e 6 0 da yperiod . Th e Nuclea r Regulator yCommissio n give s a half-lif e fo r thi s weatherin g .proces s o f 1 4 day s ( t = 1 4 days) . Th e expressio nfo r findin g th e concentratio n a t anytime , C . , i s then : C t 

### = C 0 

### e " X 

### w * where :
X w

### = ln2/t w

### = 0.0495/day , C Q 

### = initia l concentration . Th e dail yintak e i s give nby : Dail yIntak e = (FC)*C Q 

### e"^w t 

### I n orde r t o determin e th e tota l intak e ove r tim e T , th e equatio ni s integrate d fromzer o t o T giving :

F-3 5P.4 7



### Tota l Intak e = (FC)*C Q 

### (( 1 - e " ^w T 

### ) / \ ) . Th e equivalen t contac t tim e is , then : C T = ( 1 - e~^w T 

### )/X w 

### C T = 19. 0 day s fo r T = 6 0 days . 1 0 convert s th e 5 remoccupationa l exposur e limi t t o th e mor e conservativ e 0. 5 remlimi t fo r th e genera l public ; and 1 x1 0 convert s microcurie s t o curies . I natmospheri c modeling , a facto r relatin g th e amoun t o f a releas e whic hwil l becom e airborn e i s ofte nused . I norde r t o accoun t fo r th e fractio no i th e tota l releas e whic hma ybecom e airborn e and for_ . consistenc y. wit hth e equatio nuse d fo r calculatin g Releas e Value s fo r inhalation , th e AL I mus t als o b e divide d bya releas e fractio n (R) . Th e equatio nuse d fo r calculatin g Releas e Value s base d o n th e consumptio no f contaminate d vegetable s i s shown below :
RV = ALI/((10)*(DF)*(FC)*(CT)*(R)*( 1 XIO 6 

### )) . (26 ) Substitutin g th e value s fo r DF , F C and C T yields :

RV = ALI/((68. 8 +2.3B iv 

### )*R) . (27 )

I napplyin g Equatio n2 7 t o th e 75 7 radionuclide s liste d i nICR P Publicatio n 3 0 and fo r whic hReleas e Value s fo r th e ground-wate r pathwa yhav e bee n calculated , i t ha s bee nfound tha t consumptio no f contaminate d ground wate r i s th e mor e critica l

F-3 6P.4 8



### ingestio n pathwa yfo r th e majorit yo f radionuclides . Furthermore , i nth e grea t majorit yo f case s wher e th e ingestio n o f contaminate d foo d crop s i s th e mor e critica l o f th e ingestio n pathways , eithe r th e inhalatio no r direc t exposur e scenario s ar e mor e critica l exposur e pathway s tha n ingestion . Therefore , th e Agenc yha s chose nt o bas e th e ingestio nscenari o o nintak e o f contaminate d drinkin g water .

F-3 7P.4 9



### APPENDI XG CALCULATIONO F DIREC T EXPOSUR E RELEAS E VALUE S G. l Fixe d Poin t Source s Th e Radiologica l Healt hHandboo k provide s th e followin g equation s a s exac t solution s fo r gamma rayexposur e an d gamma rayabsorptio nfroma fixe d poin t sourc e o f radiation .

I Q 

### = 0.15 6 n 1 

### E (IO 5 

### u & 

### ) , and (1 ) R/h r - (n 2 

### I)/S 2 

### (2 )
I = T e~ u 

### a S 

### (3 , 

## o where : I = origina l radiatio nexposur e rat e i n Roentge n pe r

hou r (R/hr) , I = attenuate d radiatio n exposur e rat e (R/hr) , n , = gamma quant a pe r disintegration , E = energyo f gamma quant a i n MeV , u = linea r energyabsorptio ncoefficien t fo r gamma ray s

i n ai r (a t standar d temperatur e (23°C ) and pressur e ( 1 atm) ) i n cm, n 2 

### = numbe r o f curies , S = distanc e i nmeters , R/h r = exposur e rat e i n Roentge n pe r hour . Whe ncombined , thes e thre e equation s become : R/h r = ((1.5 6 x10 4 

### )*(n 1 

### )*(E)*(u a 

### )*(n 2 

### )*(e" u 

### a S 

### )/S 2 

### (4 )
1 . Th e Healt hPhysic s an d Radiologica l Healt hHandbook . Nucleo n Lecter n Associates , Olney , MD , 1984 , page s 4 1 and 45 . 

## G- 1P.5 0



### Th e valu e fo r u

_i s found i n th e Radiologica l Healt h

-5- 1 Handboo k t o b e 3. 7 x1 0 cmfo r gamma ray s wit ha n energyo f 1 MeV . Th e valu e varie s wit hth e energyo f th e gamma rayinvolve d bu t i s approximatel ycorrec t (+15% ) fo r gamma ray s wit henergie s rangin g from abou t 0.0 7 Me V

t o abou t 2 MeV . Th e distance , S , use d fo r othe r exposur e route s i s 3 0 meter s and i s use d here . Photo n attenuatio n i n ai r betwee n th e sourc e and

— u S recepto r i s represente d b ye a . Incorporatio no f a termfo r photo n attenuatio n i n th e equatio nresult s i n a sligh t increas e i nth e direc t exposur e Releas e Valu e sinc e approximatel y1 0 percen t o f th e photon s emitte d from th e sourc e wil l b e absorbe d i n3 0 meter s o f ai r betwee nth e sourc e and th e receptor . A2 4 hou r exposur e duratio n (T ) wa s chose nt o provid e a releas e valu e tha t woul d b e lo wenought o informindividual s i na timel y fashio n tha t a n exposur e occurred . Ashorte r tim e perio d migh t rais e th e releas e valu e t o suc ha nexten t tha t notificatio n migh t no t b e give no f a releas e tha t woul d b e harmfu l i f a n individua l wer e t o b e expose d for

- twenty-fou r , hours . Multiplyin g byT (2 4 hours ) t p conver t Roentge npe r hou r t o Roentgen , th e equatio nbecomes : R= ((1.5 6 x10 4 

### )*( ni 

### )*(E)*(u a 

### )*(n 2 

### )*(T)*(e" u 

### a s 

### ))/S 2 

### (5 ) Roentge n i s approximatel yequa l t o re mfo r gamma rays . 1 Roentge n= 10 0 ergs/gramo f sof t tissu e (approximately) . 1 ra d = 10 0 ergs/gram . 1 rem= 1 ra d (fo r gamma rays) . Substitutin g rem(Dn ) fo r Roentge n (R ) and rearrangin g Equatio n 4 t o solv e fo r n 2 

### gives :

n . ,- 5 -u_S , ((6.4 1 x1 0 ")*(Dn)*(S'))/((n 1 

### )*(E)*(u a 

### )*(T)*( e "a")).(6 ) Th e valu e fo r n 2 

### i s th e direc t exposur e releas e valu e and th e produc t o f n , and E i s th e gamma rayfractio n time s th e gamma ray energy . Manyradionuclide s emi t mor e tha non e gamma raype r

G- 2P.5 1



### disintegratio n o 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 energyo f eac hgamma rayemitte d (E. ) and th e fractio n o f tim e i t i s emitte d (n. ) i s summe d t o produc e a value , E, , whic hreflect s th e tota l gamma rayenergy produce d byeac hradionuclide . Th e metho d use d fo r thi s calculatio n i s shown i n Equatio n7 .

E i = I t(n i 

### )*(E i 

### ) ] (7 ) i Som e radionuclide s emi t positivel ycharge d electron s (positrons ) which , whe n the ystrik e norma l negativel ycharge d electrons , annihilat e on e anothe r and produc e tw o gamma ray s wit ha nenergy o f 0.51 1 Me V

each . Bot hannihilatio ngamma ray s ar e considere d i nth e calculation s fo r thos e radionuclide s whic hdeca yby positro n emission . Substitutin g E , fo r th e produc t o f n..' and E and usin g "Direc t Exposur e £DE ) Releas e Valu e (RV) " fo r n , yields :
D E RV = ((6.4 1 x10" 5 

### )*(Dn)*(S 2 

### ))/((E 1 

### )*(u a 

### )*(T)*(e" u 

### a S 

### )) . (8 ) Equatio n 8 abov e i s identica l t o tha t shown a s Equatio n 5 i n sectio n 4.2. 3 o f thi s report . Substitutin g numerica l equivalent s fo r D n (0.5rem) , S (30m) , u (3. 7 x1 0 ) , and T (2 4 c l 

### hours ) i n Equatio n 8 yields :

D E Releas e Valu e = 36.3/E ^ (9 )



## G- 3

### 2

G. 2 SubmersionI nA Clou do f Nobl e Gas . Th e nobl e gase s argon , krypton , and xeno nar e ver yresistan t t o combinatio nwit hothe r element s t o formsoli d o r liqui d derivatives . Th e radioactiv e form s o f thes e element s ar e no t likel yt o b e found i n compound s o r i nsoli d o r liqui d ingestibl e form . I naddition , thes e gase s hav e ver ylo wsolubilit yi nbloo d and ar e easil ydisplace d frombloo d b yth e mor e commo ngase s found i nai r suc ha s oxyge nand nitrogen . Fo r thes e reasons , neithe r ingestio nno r inhalatio n compris e a rout e o f significan t expsour e - fo r argon , krypto n o r xeno n and ALI' s fo r isotope s o f thes e element s ar e no t found i n ICR P Publicatio n 30 . 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 throug hdirec t exposur e fromsubmersio n i n a n airborn e cloud (know na s "cloudshine") . Th e equatio n use d fo r calculatio no f th e Direc t Exposur e (DE ) Releas e Valu e (RV ) base d o n submersio ni n 3 suc han.airborn e cloud i s shown belo w: D E RV - ((83)*(DAC)*(T))/((10)*(X/Q)*( 1 xIO 6 

### ) ) (10 )
2 . Th e nobl e gase s heliu mand neo nd o no t for misotope s wit h half-live s longe r tha n a fe wseconds . Non e o f thes e isotope s ar e liste d i nICR P Publicatio n3 0 an d n o Releas e Value s o r propose d RQ s hav e bee ncalculated . Th e nobl e ga s rado n ha s tw o isotope s (radon-22 0 and radon-222 ) liste d i n ICR P Publicatio n3 0 wit hinhalatio nALI s calculate d wit hand withou t daughter s present . Du e t o th e fac t tha t Radon-22 0 and Radon-22 2 emi t alph a particles , inhalatio n become s th e critica l exposur e pathway , an d submersio ni na 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 neac hcas e wa s use d i n th 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 fo r eithe r rado nisotope , Direc t Exposur e Releas e Value s wer e calculate d b ysummatio n o f th e produc t o f gamma rayenergyand gamma rayfraction . 3 . 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 and 47 .

G- 4P.5 3



### where : DAC = derive d ai r concentratio n (uCi/cubi c centimeter )

fromICR P Publicatio n30 ;
T = tim e o f exposur e ( 1 day ) ;

. . —1 3 

### X/ Q = atmospheri c relativ e concentratio nvalu e (8. 4 x1 0 day/cubi c centimeter) ; .8 3 conversio n facto r t o adjus t airborn e concentration s

froma 2 00 0 hou r wor k yea r (5 0 week s time s 4 hour s pe r week ) t o a 2 4 hou r exposur e perio d (2000/24 ) ; and 1 x1 0 conversio n facto r fro mmicrocuri e (uCi ) t o curie . Th e DA C i s th e airborn e concentratio n t o whic ha nindividua l mus t b e expose d fo r on e wor k yea r (200 0 hours ) i n orde r t o receiv e 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 to.th e 0. 5 rem/yr limi t applicabl e t o th e genera l public . Fo r consistenc ywit h othe r exposur e pathway s th e atmospheri c relativ e concentratio nvalu e (X/Q ) i s derive d fo r exposur e 3 0 meter s fromth e releas e unde r stabilit yclas s D condition s (se e Appendi xE) . I norde r t o conver t th e duratio n o f exposur e froma 200 0 hou r wor k yea r t o 2 4 hour s ( 1 day) , th e DAC mus t b e multiplie d bya 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 re mdose-equivalen t i n2 4 hours . Substitutio n o f tim e (T ) and th e atmospheri c relativ e concen tratio n valu e (X/Q ) int o Equatio n1 0 lead s t o Equatio n1 1 whic h wa s use d fo r . calculatio no 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 

### ) . (ll )



## G- 5P.5 4

CHAPTE R 3 DENTIFICATIO N O F ALIS TO F RADIONUCLIDE S

EP Ai s proposin g t o adjus t th e statutor yone-poun d R Q fo r radionuclides . W e discusse d i nChapte r 2 o f thi s repor t th e si xregulator yoption s considere d byth e Agenc ydurin g th e developmen t o f th e propose d regulation . Th e Agenc y selecte d Optio n6 , establishin g a propose d R Q i n unit s o f curie s fo r individua l radionuclides . Ther e ar e approximatel y180 0 radionuclide s o n th e Char t o f th e Nuclides. 1 However , onl y75 7 radionuclide s hav e sufficien t metaboli c dat a availabl e t o individuall yanalyz e and examin e th e effect s o f a radionuclid e release . Th e availabl e metaboli c dat a wer e develope d b yth e Internationa l Commissio no nRadiatio nProtectio n (ICRP ) and wer e publishe d i n it s Publicatio n30. 2 Thi s publicatio n include s Annua l Limitation s o f Intak e (ALIs) , i nunit s o f microcuries , fo r individua l radionuclides . Th e ALI s fo r th e 75 7 radionuclide s hav e bee n develope d fo r differen t mode s o f exposure , suc ha s inhalatio no r ingestion , and represen t th e quantit yo f eac h radionuclid e tha t correspond s t o a dose-equivalen t o f 5 rem , th e Federa l Radiatio nProtectio nGuidanc e recommende d limi t fo r worke r exposur e i n nuclea r facilities . EP Arelie d heavil yo nth e ALI s i n it s methodologie s fo r developin g propose d RQs . Withou t ALI s fo r a particula r radionuclide , insufficien t informatio nexist s fo r th e Agenc yt o determin e th e effect s o f exposur e t o th e radionuclide . Therefore , althoug hth e Agenc ydecide d t o establis han R Q fo r individua l radionuclide s i nunit s o f curie s base d o n th e particula r isotopi c characteristic s o f eac hradionuclide , sufficien t informatio n t o perfor mth e necessar yanalyse s exist s fo r onl y75 7 radionuclides . Thes e 75 7 radionuclide s ar e liste d i nICRP' s Publicatio n 3 0 and hav e ALI s availabl e fo r differen t route s o f exposure . Becaus e ther e i s insufficien t metaboli c dat a o n th e remainin g radionuclide s t o develo p individua l RQs , th e Agenc yi s proposin g t o lis t a s a clas s al l radionuclide s tha t ar e no t liste d i n ICRP' s Publicatio n 30 , and t o propos e on e R Q fo r th e entir e class . Th e 75 7 radionuclide s fo r whic hALI s hav e bee ndevelope d woul d b e analyze d individuall yt o determin e th e appropriat e R Q levels . Th e 75 7 radionuclide s fo r whic hspecifi c RQ s ar e develope d includ e radionuclide s tha t ar e ver yrar e an d exis t onl ya s laborator yanomalies ,

1 Th e Char t o f th e Nuclide s i s a graphi c displa yo f th e numbe r o f neutron s and protons , radioactiv e hal f lives , mode s o f radioactiv e decay , and othe r dat a fo r know nradioactiv e isotopes . internationa l Commissio n o n Radiatio n Protection , Annal s o f th e ICRP : Limit s fo r Intake s o f Radionuclide s b yWorkers , ICR P Publicatio n 30 , Par t 2 , 1980 .