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ECONOMI C IMPACT ANALYSI S FO RTHE FINA

L REPORTABL E QUANTITYADJUSTMENT S FO RRADIONUCLIDE S UNDE RSECTIO

N 10 2 O F THE COMPREHENSIV

E ENVIRONMENTA

L RESPONSE , COMPENSATION , AN

DLIABILITYAC T

A Repor t t o th

e

EMERGENC

YRESPONS E DIVISIO N Offic e o f Emergency an dRemedia l Respons e U.S . Environmenta l ProtectionAgency

Februar y 15 , 198 9

Preparedby : IC F Incorporated Contrac t No. : 68-03-345 2

930 0 Le eHighwa y Fairfax , Virginia 22031-1207 

# IC F INCORPORATE

DP. 2 

## 1

ECONOMI C IMPACT ANALYSI S FO RTHE FINA

L REPORTABLE QUANTIT

YADJUSTMENT S FO

RRADIONUCLIDE S UNDE RSECTIO

N 10 2 O F THE COMPREHENSIV

E ENVIRONMENTA

L RESPONSE , COMPENSATION , AN

DLIABILIT

YAC T

A Repor t to th

e

EMERGENC

YRESPONS E DIVISIO

N Offic e o f Emergenc

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

Februar y 15 , 198 9

Prepare dby : IC F Incorporate

d Contrac t No. : 68-03-345 2P. 3

TABL E O F CONTENT S Pag e EXECUTIV

E SUMMAR

Y ES- 1 CHAPTE R I : BACKGROUN D AN D INTRODUCTIO

N1- 1 1. 1 Purpos e o f the Analysi s 1- 1 1. 2 Th e Notificatio n Proces s 1- 2 1. 3 R Q Adjustment s fo r Radionuclide s 1- 3 1. 4 Release s Exempte d fro mCERCL AReporting Requirement s .... . 1- 5 1. 5 Facilitie s Affecte d b yFina l R Q Adjustment s 1- 7 1. 6 Organizatio n o f thi s Repor t 1-1 0 CHAPTE R II : BASELINE REPORTABL E EPISODI C RELEASE S - . 2- 1 2. 1 Methodolog

yt o Estimat e the Numbe r o f Baselin e Reportabl e Release s 2- 1 2. 2 Derivatio n o f Tota l Annua l Numbe r o f Radionuclid e Release s (Facto r A ) 2- 5 2. 3 Derivatio n o f Radionuclid e Releas e Probabilit y2-1 2 2. 4 Siz e Distributio n o f Radionuclid e Release s 2-1 5 2.5

- Baselin e Reportabl e Episodi c Release s 2-2 0 CHAPTE R III : UNI T COST S ASSOCIATE D WIT H REPORTABL E

EPISODI C RADIONUCLID E RELEASE S 3- 1 3. 1 Action s Take n wit ha Reportabl e Radionuclid e Episodi c Releas e 3- 2 3. 2 Valuatio n o f Action s Take n b yEpisodi c Releaser s o f Radionuclide s 3- 4 3. 3 Valuatio n o f Governmen t Action s 3- 9 CHAPTE R IV : ESTIMATE D ANNUAL COS T O F R Q ADJUSTMENT S 4- 1 4. 1 Estimate d Numbe r o f Incrementa l Reportabl e Episodi c Release s 4- 1 4. 2 Estimate d Cos t o f Fina l R Q Adjustmen t 4- 2 4. 3 Estimat e o f Numbe r o f Othe r Incrementa l Reportabl e Release s 4- 9 4. 4 Fir

mLeve l Economi c Effect s 4-1 7 CHAPTE R V : SENSITIVITY ANALYSI S 5- 1 5. 1 Concept s an

d Ke yVariable s 5- 1 5. 2 Result s o f the Sensitivit yAnalysi s 5- 4 5. 3 Statistica l Analysi s o f EI ARadionuclid e Dat a Bas e 5- 6 5. 4 Summar

y5- 6 APPENDI X A : PROFILE S O F FACILITIE S THA T RELEAS E RADIONUCLIDE S A- l APPENDI X B : ESTIMAT E O F TH E NUMBE R O F FACILITIE S WIT H COAL-FIRE D

BOILER S EXPECTE D T O REPORT UNDE R SECTIO N103(f)(2 ) B- lP. 4

LIS T O F EXHIBIT S
Exhibi t Pag e ES- 1 Incrementa l Cost s o f Reporting Episodi c an d Continuou s Release s o f Radionuclide s ES- 4 2- 1 Assumption s Use d t o Estimat e Baselin e Reportabl e

Release s 2- 2 2- 2 Profil e o f Episodi c Release s i n Nuclea r Regulatory

Commissio n AEO D Dat a Se t 2-1 0 2- 3 Characteristic s o f the Unifie d Radionuclid e

Dat a Bas e 2-1 4 2- 4 Frequenc yo f Episodi c Release s fo r Eac hRadionuclid e

i n the Unifie d EI ADat a Bas e 2-1 6 2- 5 Siz e Distributio n o f Radionuclid e Release s i n the

EI ADat a Bas e 2-1 9 2- 6 Reportabl e Baselin e Radionuclid e Release s

Estimate d fro

mth e Unifie d EI ADat a Bas e 2-2 3 3- 1 Uni t Notificatio n Cost s t o Facilit yOwners/Operator s

o f a Reportabl e Episodi c Releas e 3- 7 3- 2 Radionuclid e Respons e Cos t Estimate s 3-1 0 3- 3 Uni t Cost s t o Al l Governmen t Entitie s o f a

Reporte d Episodi c Releas e 3-1 2 4- 1 Reportabl e Radionuclid e Release s unde r Fina l

Adjuste d RQ s Estimate d fro mEI ADat a Bas e 4- 3 4- 2 Uni t Notificatio n Cost s t o Facilit yOwners/Operator s

o f a Reportabl e Episodi c Releas e 4- 5 4- 3 Calculatio n o f Tota l Annua l Cost s t o Facilit y

Owners/Operator s 4- 6 4- 4 Calculatio n o f Tota l Annua l Cost s t o

Governmen t 4- 8 4- 5 Estimate d Numbe r o f Reporting Facilitie s Unde r CERCL A Sectio n 103(f)(2 ) , 4-1 2 4- 6 Tota l Cost s o f Reporting Unde r Sectio n 103(f)(2 )

(excluding facilitie s wit hcoal-fire d boilers ) 4-1 8 4- 7 Tota l Cost s o f Reporting Unde r Sectio n 103(f)(2 ) ... . 4-2 0P. 5

LIS T O F EXHIBIT S (continued )
Exhibi t Pag e 5- 1 Result s o f the Sensitivit yAnalysi s 5- 5 B- l Distributio n b yCapacit yo f Coal-fire d Powe r Plant s B- 7 B- 2 Distributio n b yCapacit yan

d Typ e o f Coal-fire d Inustria l Boiler s B- 7P. 6

EXECUTIV

E SUMMAR

Y Sectio n 10 3 o f the Comprehensiv e Environmenta l Response , Compensation , an d Liabilit yAc t o f 198 0 (CERCLA ) require s notificatio n o f the Nationa l Respons e Cente r whe n release s o f hazardou s substance s occur i n amount s tha t equa l o r excee d a n RQ . Sectio n 30 4 o f the Superfun d Amendment s an

d Reauthorizatio n Ac t o f 198 6 (SARA ) amend s CERCL At o requir e tha t Stat e Emergenc yRespons e Commission s (SERCs ) an d Loca l EmergencyPlanning Committee s (LEPCs ) als o b e notifie d whe n a releas e occur s o f a reportabl e CERCL A hazardou s substance . Radionuclide s ar e CERCL Ahazardou s substances ; sectio n 10 2 o f CERCLAestablishe s a one-poun d R Q fo r radionuclides , a s a generi c clas s o f substances . EPArecognize s tha t a one-poun d R Q i s no t appropriat e i n mos t case s becaus e radionuclid e release s o f les s than one-poun d maypresen t a substantia l hazar d t o publi c healt han d welfar e an

d the environment . Th e purpos e o f thi s Economi c Impac t Analysi s (EIA ) i s t o estimat e the incrementa l cost s t o facilit yowner s an d operator s an

d t o the governmen t tha t mayb e attribute d t o the fina l regulatio n adjusting the reportabl e quantitie s (RQs ) fo r approximatel y1,50 0 radionuclides . METHODOLOGY Ther e ar e approximatel y950,00 0 facilitie s i n the Unite d State s tha t us e and , therefore , potentiall ycoul d releas e radionuclide s int o the environment . Ther e ar e n o comprehensiv e dat a o n the numbe r o f radionuclid e release s tha t occu r annually , o r o n the amoun t o f thos e releases . T o establis ha n EI A releas e dat a base , therefore , thi s analysi s use s dat a tha t ar e availabl e from si xsources , including th e Transportatio n Technolog yCente r o f Sandi a Nationa l Laboratory , the Departmen t o f Energy , the Nationa l Respons e Center , EPA' s Offic e o f Radiatio n Programs , the Nuclea r RegulatoryCommission' s Offic e fo r Analysi s and Evaluatio n o f Operationa l Dat a (AEOD) , an d the Commission' s Operation s Center . T o estimat e the potentia l chang e i n the numbe r o f reportabl e episodi c radionuclid e releases , historica l report s o f episodi c release s ar e use d t o predic t th e characteristic s o f futur e release s b yassuming tha t futur e radionuclid e release s wil l occu r wit hthe sam e frequencyan

d b e o f the same siz e a s historica l radionuclid e releases . An EI Adat a bas e i s developed , consisting o f 1,13 9 radionuclid e releas e events . Sixty-thre e differen t radionuclide s ar e identifie d i n the EI Adat a base , an d 1,11 3 event s hav e quantit yinformatio n relate d t o the releas e event . Th e EI Adat a bas e i s use d t o estimat e the historica l frequencyo f releas e o f a particula r radionuclide , an d thereb

yt o projec t the futur e likelihoo d o f a releas e o f a specifi c radionuclide . I f a radionuclid e i s no t identifie d i n the EI Adat a base , the analysi s assume s tha t the particula r radionuclid e wa s neve r release d i n the pas t an d assign s zer o t o the probabilit ytha t a releas e even t i n the futur e woul d involve tha t particula r radionuclide . Th e EI Adat a bas e als o i s use d t o estimat e a secon d parameter , th e amoun t release d during a n event . Releas e o f a radionuclid e t o the environmen t b y itsel f doe s no t mea n tha t th e releas e mus t b e reporte d t o the Nationa l Respons e Center . Areleas e i s reportabl e onl yi f the amoun t release d equal s o r exceed s a n RQ . A s eac hradionuclid e ha s bee n assigne d on e o f seve n RQs , i tP. 7

i s importan t t o determin e the probabilit ytha t the release d quantit yi s sufficientl ylarg e t o warran t a repor t t o the Nationa l Respons e Cente r an d othe r governmen t bodies . Th e analysi s assume s tha t ther e i s n o correlatio n betwee n the identit yo f the radionuclid e release d an d the quantit yrelease d during a n event . Therefore , b

ymultiplying the probabilit ytha t a particula r radionuclid e wil l b e released , b

ythe probabilit ytha t the releas e wil l equa l o r excee d it s RQ , the analysi s derive s the numbe r o f reportabl e radionuclid e releases . Th e methodologyals o consider s the amoun t o f the radionuclid e releas e tha t i s federall ypermitted , and , thus , exclude d fro mthe CERCL

Aan d SAR Areporting requirements . Release s tha t ar e no t i n complianc e wit hfederall ypermitte d releas e level s onl ynee d t o repor t t o the Nationa l Respons e Cente r an d t o SERC s and LEPC s i f the releas e equal s o r exceed s the federall ypermitte d leve l b ya n R Q o r more . I n additio n t o episodi c releases , some facilitie s tha t releas e radionuclide s regularl ya s a resul t o f norma l operation s mayb e affecte d b y the fina l adjuste d radionuclid e RQs . Thes e facilitie s typicall ymove , process , o r consume larg e quantitie s o f lowactivit ymaterial s suc ha s coa l o r ore . Becaus e the dat a use d t o estimat e the incrementa l numbe r o f reportabl e episodi c release s ar e no t appropriat e t o estimating release s fro mthes e facilities , a differen t methodolog yi s used . Facilitie s potentiall yreleasing radionuclide s o n a continuou s basi s ar e estimate d b yreviewing the dat a availabl e o n thes e release s o n a n industr yb yindustrybasis . ESTIMATE D COST S O F RADIONUCLID E R Q ADJUSTMENT S Afte r estimating the numbe r o f reportabl e releases , the analysi s identifie s the action s tha t facilit yowner s an d operator s an

d the governmen t woul d likel ytak e whe n a reportabl e radionuclid e releas e occurs . Thes e action s includ e notification , recordkeeping , an d respons e activitie s fo r facilit yowner s an

d operators , an

d notificatio n processing , off-scen e an d on scen e monitoring , an d direc t remova l fo r the government . Th e analysi s the n estimate s th e uni t cost s o f eac ho f thes e actions , and consider s the likelihoo d tha t eac ho f thes e action s woul d actuall yb e taken . Fo r example , simpl ybecaus e a facilit yowne r o r operato r notifie s the Nationa l Respons e Cente r tha t a radionuclid e releas e ha s occurre d doe s no t mea n tha t a respons e actio n wil l b e take n byeithe r the governmen t o r the facilit yoperators . Th e analysis , therefore , mus t accoun t fo r bot hthe likelihoo d tha t a n actio n wil l b e take n an

d the natur e (i.e. , cost ) o f tha t action . Ultimately , the analysi s mus t estimat e ho wthes e action s (an d costs ) wil l b e modifie d b ythe fina l R Q adjustments . EPAi s adjusting the RQ s downwar d (i.e. , belo won e pound ) fo r nearl yal l radionuclides , and , therefore , expect s a n increas e i n the numbe r o f reportabl e radionuclid e releases . Thi s analysi s estimate s tha t ther e ar e approximatel y 1 9 episodi c radionuclid e release s tha t would.b e reportabl e annuall yi f the R Q wer e t o remai n on e pound , and.estimate s tha t ther e wil l b e approximatel y7 8 reportabl e episodi c release s annuall ywhe n the R Q adjustment s ar e final . Therefore , ther e ar e 5 9 incrementa l reportabl e episodi c release s annuall ya s a resul t o f th e fina l R Q adjustments . A s a result , facilit yowner s an d ES- 2P. 8

operator s an

d the governmen t wil l incur increase d cost s becaus e bot hentitie s wil l likel yincreas e the numbe r o f respons e an d recordkeeping action s taken , reflecting the increas e i n the numbe r o f reportabl e releases . Thi s analysi s estimate s tha t thes e additiona l cost s wil l b e approximatel y$256,40 5 annually . Th e analysi s als o estimate s the numbe r and'cost s o f radionuclid e release s tha t equa l o r excee d the fina l RQs , bu t ar e expecte d t o b e reporte d unde r the provision s o f CERCL Asectio n 103(f)(2 ) becaus e thes e release s ar e "continuous " and "stabl e i n quantit yan d rate. " Facilitie s tha t ar e eligibl e t o repor t release s unde r sectio n 103(f)(2 ) mus t repor t release s initially , annually , an d wheneve r a statisticall ysignifican t increas e (SSI ) occurs . Th e type s o f facilitie s mos t likel yt o hav e a continuou s radionuclid e releas e includ e coal

fire d utilit yan

d industria l boile r sites , certai n mining an d ore-processing operations , an

d energ yextractio n an

d processing facilities . I t i s estimate d tha t approximatel y2,71 0 facilitie s ar e likel yt o releas e a n R Q o r mor e o f a radionuclid e o n a continuou s basis . Th e majorit yo f thes e facilitie s (1,724 ) ar e utilit yan d industria l facilitie s wit hcoal-fire d boilers . Becaus e o f the availabilit yo f dat a regarding the characteristic s o f release s fro

mthes e facilities , U.S . Environmenta l Protectio n Agenc y(EPA ) ha s examine d thes e facilitie s i n greate r detai l tha n othe r facilitie s wit h continuou s releases . Becaus e continuou s release s ar e differen t i n natur e than episodi c releases , the action s undertake n b yindustr

yan d governmen t following a continuou s releas e o f a radionuclid e ar e als o different . Specifically , the reporting requirement s unde r sectio n 103(f)(2 ) requir e initia l an d annua l notificatio n an

d the immediat e reporting o f a statisticall ysignifican t increas e i n the release . Becaus e thes e release s ar e assume d t o b e incidenta l t o norma l operating procedure s an d t o hav e bee n reviewe d b ythe appropriat e governmen t bodie s throughthe initia l an d annua l notificatio n reports , i t i s assume d tha t n o incrementa l respons e action s wil l b e undertake n (or cost s incurred ) b

yeithe r industr

yo r governmen t a s a resul t o f thes e releases . Th e annualize d cost s o f reporting unde r sectio n 103(f)(2 ) ar e estimate d a s $3,160,00 0 fo r industr yan d $660,00 0 fo r government . Th e tota l annualize d cost s t o al l partie s i s estimate d t o b e $3,820,000 . Excluding facilitie s wit hcoal-fire d boilers , the numbe r o f facilitie s tha t hav e continuou s release s and ar e expecte d t o repor t unde r sectio n 103(f)(2 ) i s estimate d a t approximatel y1,000 . Th e annualize d cost s t o thes e facilitie s o f reporting release s i s estimate d a s $1,150,000 . Th e annualize d cost s t o governmen t o f processing thes e releas e report s i s estimate d t o b e $240,000 , resulting i n tota l cost s t o al l partie s o f $1,390,000 . Th e estimate d cost s fo r reporting episodi c an d continuou s release s unde r the fina l adjuste d radionuclid e RQ s ar e presente d i n Exhibi t ES-1 .

ES- 3P. 9

EXHIBI T ES- 1 INCREMENTA

L COST S O

F REPORTIN

GEPISODI C AN

D CONTINUOU S RELEASE S O F RADIONUCLIDE S

EPISODI C RELEASE S

Part y Industry(5 9 episodi c releases ) Governmen t TOTAL : Annua l Cost s $39,70 0 S216.70 0 $256,40 0

CONTINUOU S RELEASE S (Al l facilities )

• Part y Industr y(2,71 0 facilities ) Governmen t TOTAL : Annualize d Cost s * $3,160,00 0 $660.00 0 $3,820,00 0

CONTINUOU S RELEASE S (Excluding facilitie s wit hcoal-fire d boilers )

Part y Annualize dCost s * Industr y(98 6 facilities ) $1,150,00 0 Governmen t $240.00 0 TOTAL : $1,390,00 0

* Cost s ar e annualize d ove r a te n yea r perio d a t a four percen t discoun t rate . Al l cost s ar e i n 198 7 dollars .

ES- 4P.1 0

CHAPTE R1 BACKGROUN

DAN DINTRODUCTIO

N
The Comprehensiv e Environmenta l Response , Compensation , an d Liabilit yAc t o f 198 0 (CERCLA ) establishe s broa d federa l authorit yt o undertak e remova l an d remedia l action s i n respons e t o release s o r threat s o f release s o f hazardou s substance s an

d certai n pollutant s o r contaminant s int o the environment . Sectio n 10 3 o f CERCL Arequire s notificatio n o f the Nationa l Respons e Cente r whe n release s o f hazardou s substance s occur i n amount s tha t equa l o r excee d a reportabl e quantit y(RQ) . Notificatio n o f the Nationa l Respons e Cente r serve s t o aler t the federa l governmen t t o release s o f hazardou s substance s tha t may requir e respons e t o protec t publi c healt han d welfar e an

d the environment . Radionuclide s ar e designate d a s hazardou s ai r pollutant s unde r sectio n 11 2 o f the Clea n Ai r Ac t and , a s such , ar e designate d CERCL Ahazardou s substances . Sectio n 10 2 o f CERCL Aestablishe s a one-pound R Q fo r radionuclides , a s a generi c clas s o f substances , bu t authorize s the Administrato r o f the U.S . Environmenta l Protectio n Agenc y(EPA ) t o adjus t the R Q b yregulatio n i f appropriate . EPArecognize s tha t a n R Q o f on e pound fo r radionuclide s i s no t appropriat e i n mos t case s becaus e release s o f les s tha n on e pound maypresen t a substantia l hazar d t o publi c healt han d welfar e an

d the environment . EPA , therefore , i s issuing a fina l regulatio n t o adjus t the RQ s fo r approximatel y150 0 radionuclides . 1. 1 PURPOS E O

F TH E ANALYSI S Ther e ar e severa l purpose s fo r conducting a n Economi c Impac t Analysi s (EIA) . On e objectiv e o f a n EI Ai s t o estimat e the incrementa l cost s an d cos t saving s resulting fro ma regulatoryaction . Asecon d objectiv e o f a n EI Ai s t o determin e whethe r o r no t the regulatio n constitute s a majo r rule . Executiv e Orde r (E.O. ) 1229 1 require s regulatoryagencie s t o prepar e analyse s o f the economi c impact s o f a regulation . ARegulatoryImpac t Analysi s i s require d fo r al l majo r rules . According t o E.O . 12291 , majo r rule s ar e regulation s likel yt o resul t in :

(1 ) An annua l effec t o n the econom yo f $10 0 millio n o r more ; o r (2 ) Amajo r increas e i n cost s o r price s fo r consumers , individua l industries , federal , state , o r loca l governmen t agencies , o r geographi c regions ; o r (3 ) Significan t advers e effect s o n competition , employment , investment , productivity , innovation , o r o n the abilit yo f Unite d States

base d enterprise s t o compet e wit hforeign-base d enterprise s i n domesti c o r expor t markets . Finally , a n EI Ai s conducte d t o determin e whethe r a regulatio n woul d hav e a significan t impac t o n smal l businesses .P.1 1

Fo r mos t radionuclides , the fina l regulatio n adjusting RQ s wil l requir e reporting release s tha t ar e considerabl ysmalle r than on e pound . Th e fina l regulation , therefore , i s expecte d t o impos e additiona l reporting and repor t processing cost s bot ho n the regulate d communit yan d o n the governmen t becaus e a large r numbe r o f release s wil l b e reportable . Thi s analysi s discusse s and quantifies , t o the exten t possible , the cost s tha t wil l b e incurre d b y facilit yowner s an

d operator s an

d the governmen t a s a resul t o f the fina l R Q adjustments . Thi s chapte r o f the EI Adescribe s the reporting requirement s fo r release s o f radionuclide s unde r section s 103(a ) an d (b ) o f CERCLA , an d als o the additiona l reporting requirement s tha t the Superfun d Amendment s an

d Reauthorizatio n Ac t o f 198 6 (SARA ) adde d t o the requirement s o f CERCLA . Sectio n 1. 2 describe s the notificatio n process , the CERCL Aan d SAR Areporting requirements , an

d the rang e o f potentia l respons e activitie s triggere d b ya reportabl e release ; Sectio n 1. 3 describe s the purpos e o f the R Q adjustment s fo r radionuclides ; Sectio n 1. 4 describe s the release s o f hazardou s substance s tha t ar e exemp t fro mthe notificatio n requirements ; Sectio n 1. 5 describe s thos e facilitie s tha t potentiall yar e affecte d b ythe R Q adjustments ; an d Sectio n 1. 6 outline s the remaining chapter s o f thi s report . 1. 2 THE NOTIFICATIO N PROCES S Regulation s implementing the genera l reporting requirement s o f section s 103(a ) and (b ) o f CERCL Arequir e a perso n i n charg e o f a vesse l o r facilit yt o notif yth e Nationa l Respons e Cente r a s soo n a s h e ha s knowledg e tha t ther e ha s bee n a releas e o f a hazardou s substanc e during a 24-hou r perio d i n a n amoun t equa l t o o r exceeding the R Q fo r tha t substanc e (4 0 CFR 302.6(a)) . CERCL A sectio n 103(b ) make s thos e person s wh o ar e require d t o notif ythe Nationa l Respons e Center , bu t fai l t o do s o immediately , subjec t t o crimina l penalties . CERCL Asectio n 10 1 als o provide s exclusion s t o the reporting requirement s fo r certai n type s o f release s o r certai n type s o f substances. 1 Notificatio n base d o n RQ s serve s t o infor mthe governmen t o f a release , thereb yenabling a n evaluatio n o f the inciden t an d a timel yfiel d respons e shoul d on e b e necessary . Notificatio n doe s no t necessaril ymea n tha t a fiel d repons 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 hthe release . CERCL Asectio n 10 1 define s the ter m"release " t o includ e withi n it s scop e virtuall yal l way s tha t substance s mayente r the environment :

"release " mean s an

yspilling , leaking , pumping , pouring , emitting , emptying , discharging , injecting , escaping , leaching , dumping , o r disposing int o the environmen t (including the abandonmen t o r discarding o f barrels , containers , an

d othe r close d receptacle s containing an y

1 Fo r example , CERCL Asectio n 101(10 ) exempt s federall ypermitte d release s fro

mthe CERCL

Anotificatio n an

d liabilit yprovisions. 1 1- 2P.1 2

hazardou s substanc e o r pollutan t o r contaminant ) [section 101(22 ) a s amende d b ysectio n 101(c ) o f SARA ] Sectio n 101(14 ) o f CERCL Adefine s a hazardou s substanc e t o b e an y substanc e designate d under :

• Sectio n 30 7 an d 31 1 o f the Clea n Wate r Act ; Sectio n 300 1 o f the Resourc e Conservatio n an d RecoveryAc t (RCRA) ; Sectio n 10 2 o f CERCLA ; Sectio n 11 2 o f the Clea n Ai r Act ; an d Sectio n 7 o f the Toxi c Substance s Contro l Ac t (TSCA ) Sectio n 102(b ) o f CERCL Aestablishe s a one-poun d R Q fo r eac hhazardou s substance , excep t thos e fo r whic ha n R Q wa s establishe d pursuan t t o sectio n 31 1 o f the Clea n Wate r Act . Sectio n 102(a ) o f CERCL Aauthorize s EP

At o adjus t statutoryRQ s b

yregulation. 2 I n additio n t o the reporting requirement s establishe d b yCERCLA , SAR

A sectio n 30 4 require s stat e an d loca l reporting fo r release s o f CERCL A hazardou s substances . Th e SAR Asectio n 30 4 notificatio n i s t o b e give n b ythe owne r o r operato r o f a facilit yimmediatel yafte r the releas e o f a n R Q o r mor e (on e pound o r mor e i f a reporting trigge r i s no t establishe d b yregulation) . Th e notificatio n i s t o b e give n t o the communit yemergenc ycoordinato r fo r eac hLoca l Emergenc yPlanning Committe e (LEPC ) fo r an yare a likel yt o b e affecte d b

yth e release , an

d t o the Stat e EmergencyRespons e Commissio n (SERC ) o f an ystat e likel yt o b e affecte d b ythe release . 1. 3 R Q ADJUSTMENT S FO

RRADIONUCLIDE S Ther e ar e approximatel y150 0 known radionuclides . Aradionuclid e i s a n elemen t wit ha n unstabl e combinatio n o f proton s an d neutron s i n it s nucleus . Th e instabilit yo f suc helement s i s the ne t effec t o f force s betwee n thes e two type s o f nuclea r particles . I n orde r t o achiev e a mor e stabl e configuration , the nucleu s release s energ yi n th e for

mo f particle s o r ray s b ya proces s o f deca ycalle d radioactivity . Radionuclide s deca ya t differen t rates ; a s a result , a pound o f two differen t radionuclide s coul d represen t significantl y differen t level s o f radioactivity , an d thu s pos e differen t threat s t o publi c healt han

d welfar e an

d the environment .

2 Th e RQ s fo r 34 0 hazardou s substance s wer e adjuste d b yEP Ao n Apri l 4 , 198 5 (5 0 FR 13456) . R Q adjustment s fo r a n additiona l 10 2 substance s wer e establishe d i n a fina l rul e publishe d o n Septembe r 29 , 198 6 (5 1 FR 34534) . EPApublishe d a Notic e o f Propose d Rulemaking adjusting th e RQ s fo r 27 3 chroni c toxicant s an d potentia l carcinogen s (5 2 FR 8140) . Ther e ar e currentl y 71 9 CERCL

Ahazardou s substances . 1- 3P.1 3

Al l othe r CERCL

Ahazardou s substance s hav e RQ s i n unit s o f pounds , ranging fro

m1 pound t o 500 0 pounds . Fo r thes e substances , the principa l healt hconcern s ar e chemica l toxicity , ignitability , reactivity , o r potentia l carcinogenicity . Thes e healt hconcern s mayb e relate d t o the numbe r o f pound s o f a substanc e released . Th e principa l healt hhazar d associate d wit hexposur e t o radionuclide s i s carcinogenicity , however,.th e hazar d i s relate d mor e closel yt o the radioactivit yemitte d rathe r tha n the mas s o f the substance . Althoughthe leve l o f radioactivit yi s directl yproportiona l t o the mas s (i.e?- , the numbe r o f pounds ) o f the radionuclid e released , activit ylevel s generall yar e use d a s indicator s o f radiatio n hazard . Th e quantit yo f radioactivit yi s measure d i n unit s o f curies 3 (Ci ) and , fo r eac hradionuclide , the same numbe r o f pound s translate s int o a differen t numbe r o f curies . Thus , the statutor

yone-poun

d R Q translate s int o a wid e rang e o f curie s fo r differen t radionuclides , covering twent yorder s o f magnitude . Anothe r widel yuse d radiatio n measuremen t i s the Roentge n Equivalen t Ma n (rem). * Th e re

mi s a uni t measur e o f radiatio n dos e an d ofte n i s expresse d a s some numbe r o f re

mt o a specifi c orga n suc ha s the lungs , thyroid , o r whol e body . Th e differenc e betwee n curie s an d remi s tha t the forme r consider s th e amoun t o f radioactive material ; the latte r consider s the route s o f exposur e an d biologica l effect s and , therefore , directl yreflect s th e level s o f tissu e damage . Curie s ca n b e converte d int o remb yidentifying the radionuclide , mod e an d duratio n o f exposure , quantit yo f intake , tissue s mos t acutel y affected ; an

d othe r factors . Th e nuclea r industr ygenerall ywork s wit hunit s o f curie s an d rem , an

d mos t existing reporting trigger s fo r radionuclid e release s ar e expresse d i n term s o f on e o f thes e tw o units . Nearl yal l existing regulation s an d control s establishe d b

ythe Nuclea r RegulatoryCommissio n an d the Departmen t o f Energy , whic hgover n a majo r portio n o f the nuclea r industry , ar e base d i n unit s o f curie s o r rem . Th e fina l regulatio n bein g analyze d i n thi s EI Ai s adjusting the R Q fo r radionuclide s t o mak e CERCL Aregulation s consisten t wit hothe r industr y measure s an

d t o ensur e timel yreporting an d timel yfiel d response s t o releases . Th e fina l RQ s ar e i n unit s o f curie s an d ar e no t uniformacros s al l radionuclides . Th e Agenc yi s dividing radionuclide s int o seve n R Q groups : 0.00 1 curie , 0.0 1 curie , 0. 1 curie , 1 curie , 1 0 curies , 10 0 curies , and 100 0 curies . Th e Agenc yi s establishing RQ s fo r 75 7 individua l radionuclide s fo r whic hther e ar e metaboli c dat a presente d i n the Internationa l Commissio n o n Radiatio n Protectio n (ICRP ) Repor t Numbe r 30 . Th e Agenc yals o i s establishing a n R Q fo r al l radionuclide s no t liste d b ythe ICRP . Thes e othe r radionuclide s hav e a fina l R Q o f 1 curi e fo r the entir e class .

3 Th e curi e i s a measur e o f the 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 .
* Radiatio n measurement s als o ca n 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 n the Unite d States . Thi s analysi s wil l us e curie s and remt o measur e amount s o f radionuclides . 1- 4P.1 4

1. 4 RELEASE S EXEMPTE DFRO M CERCL A REPORTIN

GREQUIREMENT S I t i s importan t t o defin e clearl ythe type s o f release s an d facilitie s tha t ar e subjec t t o CERCL Anotificatio n requirement s becaus e onl ythos e facilitie s wil l b e affecte d b yth e radionuclid e R Q adjustments . No t al l radionuclid e release s tha t equa l o r excee d a n R Q ar e reportabl e immediatel yt o the Nationa l Respons e Center . CERCL Asectio n 101(22 ) define s "release " and , i n s o doing , eliminate s certai n radionuclid e emission s fro mthe definitio n o f release . CERCL

Asectio n 101(10 ) define s "federall ypermitte d releases" ; unde r sectio n 103 , suc hrelease s ar e exemp t fro mCERCL Anotificatio n provisions . CERCL Asectio n 103(f)(2 ) provide s fo r reduce d reporting fo r release s tha t ar e "continuous " an

d "stabl e i n quantit yan d rate. " Eac ho f thes e provision s ar e discusse d briefl ybelow , wit ha n explanatio n o f ho wtheymaypertai n t o release s o f radionuclides . Th e exclusio n unde r sectio n 101(22 ) o f CERCL Amos t likel yt o b e o f greates t importanc e fo r radionuclide s i s fo r release s o f source , byproduct , o r specia l nuclea r material 5 fro ma nuclea r inciden t subjec t t o requirement s o f the Nuclea r RegulatoryCommissio n fo r financia l protectio n unde r sectio n 17 0 o f the Atomi c Energ yAc t (AEA). 6 Nuclea r reactor s ar e the primarytyp e o f facilit ysubjec t t o AE Asectio n 170 . EPAdoe s no t hav e the lega l authorit yt o requir e report s o f nuclea r incidents ; suc hrelease s d o no t nee d t o b e reporte d t o the Nationa l Respons e Center , regardles s o f the quantit yreleased . I t i s necessary , however , fo r release s fro mnuclea r powe r plant s no t constituting nuclea r incidents , bu t a t leas t a n R Q abov e permitte d levels , t o b e reporte d immediatel yt o the Nationa l Respons e Center . Sectio n 10 3 o f CERCL Aexclude s release s tha t ar e federall ypermitte d fro m it s notificatio n requirements ; federall ypermitte d release s ar e define d i n sectio n 101(10) . An yreleas e o f a CERCL Ahazardou s substanc e mus t b e reporte d immediatel yt o the Nationa l Respons e Cente r i f the releas e exceed s federall y permitte d level s b

ya n R Q o r more . I f the releas e i s les s than a n R Q abov e

5 Sourc e materia l i s define d a s (1 ) natura l uranium , thorium , o r an y combinatio n thereo f o r (2 ) ore s whic hcontai n 0.0 5 percen t (b yweight ) o f uraniu mo r thoriu

m(sectio n ll(z ) o f the Atomi c Energ yAc t (AEA) , and Nuclea r RegulatoryCommissio n regulation s i n 1 0 CFR Par t 40) . Byproduc t materia l i s (1 ) an ymateria l mad e radioactiv e b yexposur e t o radiatio n i n the proces s o f producing o r using specia l nuclea r materia l o r (2 ) the waste s produce d b ythe extractio n o r concentratio n o f uraniu mo r thoriu

mfro mor e (sectio n 11(e ) o f the AEA) . Specia l nuclea r materia l i s define d a s plutonium , o r uraniu m enriche d i n the U-23 5 o r U-23 3 isotop e (AEAsectio n ll(aa)) . Al l o f thes e material s ar e license d b ythe Nuclea r RegulatoryCommissio n an d it s Agreemen t States .

6 Areleas e o f source , byproduct , o r specia l nuclea r materia l fro ma processing sit e designate d unde r section s 102(a)(1 ) o r 302(a ) o f the Uraniu m Mil l Tailing s Radiatio n Contro l Ac t o f 197 8 i s no t a "release " fo r purpose s o f respons e action s unde r CERCLA , bu t i s subjec t t o the notificatio n requirement s o f section s 103(a ) an d (b ) (se e sectio n 101(22) ) an d liabilit yunde r sectio n 107 . 1- 5P.1 5

the permitte d level , the releas e i s no t federall ypermitted , bu t nonetheles s doe s no t nee d t o b e reporte d t o the Nationa l Respons e Center . An yfederall y permitte d releas e i s exemp t fro mCERCL Anotificatio n an

d liabilit yprovisions . Sectio n 101(10)(K ) o f CERCL Aexempt s fro

mreporting "an

yreleas e o f source , specia l nuclear , o r byproduc t materia l .. . i n complianc e wit ha legall yenforceabl e license , permit , regulation , o r orde r issue d pursuan t t o the .. . [AEA]. " The Nuclea r RegulatoryCommissio n i s responsibl e fo r man y activitie s unde r the AEA . License s an d permit s mayb e issue d b ythe Nuclea r RegulatoryCommissio n o r b ystate s t o whomthe authorit yt o regulat e radiation-relate d activitie s ha s bee n relinquishe d unde r a n agreemen t wit hthe Nuclea r RegulatoryCommissio n (i.e. , Agreemen t States) . Release s i n complianc e wit hlicense s an d permit s issue d b

ythe Nuclea r Regulatory Commissio n o r b

yAgreemen t State s unde r suc hagreement s ar e federall y permitte d releases . Administratio n o f the AE Adoe s no t resid e solel ywit hthe Nuclea r RegulatoryCommission , and , therefore , release s fro mfacilitie s othe r tha n thos e regulate d b

ythe Commissio n o r Agreemen t State s mayb e federall y permitte d i f theyar e authorize d unde r the AEA . T o the exten t release s ar e i n accordanc e wit hlicenses , permits , orders , o r regulation s issue d unde r the AE A throughprovision s no t administere d b ythe Commission , theyals o woul d b e federall ypermitte d releases . Fo r example , th e Departmen t o f Energ y(DOE ) govern s it s radiatio n protectio n activitie s unde r the AE Ab ya serie s o f interna l orders . Whe n suc horder s ar e issue d unde r DOE' s AE Aauthorit yand release s ar e i n complianc e wit hthe applicabl e order(s) , thes e release s als o ar e federall ypermitted . Th e Departmen t o f Defens e issue s regulation s governing weapon s an d reactor s withi n thei r jurisdiction ; release s i n complianc e wit hthes e regulation s ar e federall ypermitted . Regulation s issue d b ythe Nuclea r RegulatoryCommissio n specificall y exemp t certai n facilitie s fro mthe Commission' s licensing , permitting , an d regulatoryrequirements . Becaus e o f thi s specifi c exemption , the Agenc ydoe s no t conside r release s o f radionuclide s fromthes e facilitie s t o b e "federall y permitted. " Suc hreleases , therefore , woul d no t fal l unde r the reporting exemptio n define d i n sectio n 101(10)(K ) o f CERCLA . Othe r aspect s o f the federall ypermitte d releas e exemptio n als o coul d appl yi n the cas e o f radionuclides . Th e exemptio n generall ycover s discharge s an d emission s i n complianc e wit hpermit s an d contro l regulation s unde r specifi c environmenta l statute s liste d i n sectio n 101(10 ) o f CERCLA . Emission s covere d unde r thi s exemptio n includ e thos e regulate d b ysection s 11 1 an d 11 2 o f the Clean Ai r Ac t (CAA ) an d Stat e Implementatio n Plan s (SIPs) . Radionuclides , fo r example , ar e regulate d b yEPAa s a hazardou s ai r pollutan t unde r sectio n 11 2 o f the CAA . Anyradionuclid e releas e subjec t t o an d i n complianc e wit ha permi t o r contro l regulatio n establishe d unde r tha t sectio n woul d b e exemp t a s federall ypermitted , i f the permi t o r contro l regulatio n i s specificall ydesigne d t o limi t o r eliminat e suc ha release . I f the release , however , exceede d the permitte d leve l b ya n R Q o r more , the releas e woul d b e subjec t t o th e CERCL Anotificatio n requirements .

1- 6P.1 6

I n additio n t o the statutor yexemption s fromthe R Q notificatio n requirement s fo r release s o f hazardou s substances , sectio n 103(f)(2 ) o f the Ac t provide s a reduce d reporting requiremen t fo r release s tha t ar e "continuous " an

d "stabl e i n quantit yan d rate. " Suc hrelease s onl ynee d t o b e reporte d annuall yan d whe n ther e i s a statisticall ysignifican t increas e i n the quantit yo f th e hazardou s substanc e released . 1. 5 FACILITIE S AFFECTE D BY FINA L RQ ADJUSTMENT S Some facilitie s tha t us e o r produc e larg e amount s o f radionuclide s ar e regulate d b

ya federa l agency(e.g. , Departmen t o f Energ yo r Nuclea r RegulatoryCommission ) o r b yAgreemen t States . Othe r facilities , particularl y thos e tha t us e smal l quantitie s o f radionuclide s o r tha t us e naturall y occurring o r accelerator-produce d radioactive materia l (NARM) , ar e no t federall yregulated . Al l o f thes e facilitie s mus t compl ywit hCERCL A notificatio n requirement s an d thu s the fina l R Q adjustment s mayaffec t al l o f thes e facilitie s eithe r b yincreasing o r decreasing the numbe r o f reportabl e releases . SARA' s Titl e II I provision s requir e tha t the appropriat e Stat e Emergenc yRespons e Commissio n (SERC ) an d Loca l Emergenc yPlanning Committe e (LEPC ) als o receiv e report s o f release s o f hazardou s substance s tha t equa l o r excee d the RQ s establishe d unde r CERCLA , an d the fina l regulation , therefore , wil l affec t the numbe r o f thes e report s tha t wil l b e submitted . Appendi xAo f thi s repor t provide s detai l o n the approximatel y956,10 0 facilitie s tha t potentiall ycoul d releas e radionuclides . Thes e facilitie s includ e the following :

Nuclea r RegulatoryCommissio n licensee s - 8,900 ; Agreemen t Stat e licensee s - 13,000 ; Departmen t o f Energ yfacilit ycomplexe s - 78 ; Coa l mine s - 4,100 ; Coal-fire d utilit yboiler s - 514 ; Coal-fire d industria l boiler s - 51,187 ; Unlicense d laboratorie s - 700 ; Low-energ

yaccelerator s - 1,500 ; Uraniu mmine s - 181 ; Aluminu msmelter s an

d bauxit e mine s - 44 ; Coppe r mine s an

d smelter s - 76 ; Zin c mine s an

d smelter s - 41 ; Lea d smelters/refinerie s - 5 ; Elementa l phosphoru s plant s - 6 ; Phosphat e roc k plant s - 35 ; We t proces s fertilize r plant s - 35 ; Iro n mines/smelter s - 68+ ; Fluorospa r mine s - 15 ; Clayextractio n facilitie s - 1,317 ; Limeston e extractio n facilitie s - 2,900 ; Geotherma l energ

yplant s - 20 ; Oi l & Ga s Productio n Facilitie s - 869,406 ; an d Natura l Gas-fire d Boiler s - 2,00 5

1- 7P.1 7

Thi s lis t o f facilitie s mayno t cove r completel yal l type s o f activitie s tha t releas e o r coul d caus e the releas e o f radionuclides . Othe r type s o f activitie s als o mayresul t i n the releas e o f radionuclide s t o the environment , bu t mos t likel yo f a magnitud e no t relevan t t o the fina l R Q adjustments . Th e Atomi c Energ

yAc t o f 195 4 (AEA ) give s the Nuclea r Regulatory Commissio n the authorit yt o regulat e source , byproduct , an d specia l nuclea r materials . Th e Nuclea r RegulatoryCommissio n ha s delegate d the,authorit yt o regulat e thes e same material s t o state s tha t ente r int o a n agreemen t wit hthe Commission . Th e regulation s i n thes e so-calle d Agreemen t State s mus t b e a t leas t a s stringen t a s thos e o f the Nuclea r RegulatoryCommission . Ther e ar e five primarytype s o f facilitie s regulate d b ythe Commissio n an d Agreemen t States : (1 ) powe r reactors ; (2 ) researc han d tes t reactors ; (3 ) radio

pharmaceutica l suppliers ; (4 ) radiatio n sourc e manufacturers ; an d (5 ) othe r facilitie s including laboratories , wast e disposa l sites , minera l an d meta l processing facilities , fue l cycl e facilities , an d uraniu

mmilling . Th e Nuclea r RegulatoryCommissio n als o license s some Departmen t o f Defens e facilities , specificall yresearc hfacilitie s an d nava l shipyard s tha t servic e nuclear-powere d ships . Th e arme d force s operat e severa l researc h reactor s an

d a linea r accelerator , mainl yt o researc hthe effect s o f nuclea r radiatio n o n huma n healt han d o n electronics . I n addition , nin e nava l shipyard s involve d i n th e construction , testing , refueling , an d maintaining o f nuclear-powere d ship s ar e licensed . Th e Departmen t o f Energ y(DOE ) als o regulate s facilitie s tha t us e radionuclides . Ther e ar e 7 8 DO E complexes ; approximatel y4 7 o f thes e complexe s activel yus e radionuclides . Thes e complexe s rang e i n siz e fro m singl e structure s t o site s tha t includ e severa l hundre d individua l facilities , suc ha s Hanford , Washington . Althoughuraniu

mmine s an

d elementa l phosphoru s plant s ar e no t license d b ythe Nuclea r RegulatoryCommission , Agreemen t States , o r DOE , EP Aanalyze d radionuclid e ai r emission s fro mthes e industrie s an d foun d uraniu

mmine s an

d elementa l phosphoru s plant s t o emi t some radionuclide s a t controllabl e levels . Thes e ai r emission s fromuraniu mmine s an

d elementa l phosphoru s plants , therefore , ar e controlle d unde r sectio n 11 2 o f the Clea n Ai r Act . Release s i n complianc e wit hsectio n 11 2 limitation s ar e federall ypermitte d unde r CERCL A sectio n (101)(10)(H ) and woul d nee d t o b e reporte d t o the Nationa l Respons e Cente r onl yi f th e quantitie s release d excee d federall ypermitte d level s b ya n R Q o r more . Release s o f thes e radionuclide s t o othe r medi a an d release s o f othe r radionuclide s t o al l medi a ar e no t federall ypermitte d an d mus t b e reporte d i f theymee t o r excee d the relevan t RQs . Othe r type s o f radionuclid e release s als o mayb e affecte d b ythe fina l R Q adjustments . Radionuclid e release s du e t o contaminatio n o f sludg e mayb e reportabl e unde r CERCL Ai f the releas e i s equa l t o o r above a n RQ . Th e Supreme Cour t rule d i n Trai n vs . Colorad o Publi c Interes t Researc hGroup , 42 6 U.S . 1 (1976 ) that , i n the contex t o f release s t o water , "source, " "specia l nuclear, " an

d "byproduct " material s ar e no t pollutant s withi n the meaning o f the Clea n Wate r Act . A s such , specifi c release s o f radionuclide s wer e no t considere d i n developing effluen t limitation s unde r the Act . However , NARM 1- 8P.1 8

(naturall yoccurring an d accelerato r produce d materials ) ca n b e limite d specificall yi n wate r discharg e permits , an d regulatio n o f certai n ke y indicato r pollutant s ca n resul t i n the contro l o f othe r pollutants , including radionuclides . Wate r release s o f radionuclides , therefore , mayo r mayno t b e federall ypermitte d unde r sectio n 101(10 ) o f CERCLA . Th e Nuclea r RegulatoryCommissio n doe s no t hav e authorit yt o regulat e certai n type s o f radionuclides , including naturall yoccurring an d accelerato r produce d radioactive material s (NARM) . Th e AE Aals o provide s the Commissio n the authorit yt o exclud e fro mregulatio n facilitie s tha t the Commissio n determine s do no t warran t regulation . Th e Commissio n an d Agreemen t State s do no t licens e facilities , fo r example , whe n theyhandl e radionuclide s i n sufficientl ysmal l quantities . Ther e ar e approximatel y70 0 unlicense d laboratorie s an

d 1,50 0 low-energ

yaccelerator s tha t us e radionuclides . Becaus e the quantit ylevel s tha t trigge r licensing generall yar e belo wthe fina l R Q levels , i t i s unlikel ytha t thes e facilitie s woul d eve r releas e radionuclide s a t level s tha t equa l o f excee d a n R Q (excep t perhap s fo r NARM) . Th e remaining facilitie s tha t potentiall ycoul d releas e radionuclide s includ e coal-fire d utilit yan d industria l boilers , unlicense d laboratories , low-energ

yaccelerators , an

d mineral , energy , and meta l extractio n facilities . Ther e ar e thre e mai n source s o f radionuclid e release s a t thes e facilities : (1 ) the dumping o f larg e volume s o f lo wactivit ymateria l outsid e a building ; (2 ) emission s fro

mstockpile s o r fro mwork-in-proces s materials ; an d (3 ) smokestac k emissions . Becaus e thes e release s resul t fro mlarg e quantitie s o f lowactivit ymaterial , theyar e unlikel yt o b e episodi c i n nature . Rather , thes e release s ar e expecte d t o b e continuou s an d stabl e i n quantit yan d rate . Thes e release s mayb e reported , therefore , unde r the continuou s releas e reporting requirement s unde r CERCL Asectio n 103(f)(2) . Wit hthe exceptio n o f coal-fire d boilers , EPAha s limite d informatio n availabl e t o determin e the numbe r o f thes e facilitie s likel yt o b e releasing a n R Q o r mor e o n a continuou s basi s an d t o asses s the risk s pose d b yrelease s t o the environmen t fro mlarg e are a o r volum e sources . Th e informatio n tha t i s availabl e suggest s tha t some release s fro mthes e source s mayexcee d a n R Q o n a dail ybasis , an

d thus , thes e release s woul d hav e t o b e reporte d unde r CERCLA . O f the facilitie s withou t federa l permit s tha t ar e potentiall yreleasing radionuclides , 2,71 0 ar e estimate d t o mee t o r excee d a n R Q o n a regula r (i.e. , daily ) basis . (Appendi xAprovide s a detaile d descriptio n an d estimat e o f the numbe r o f facilitie s likel yt o mee t o r excee d a n RQ. ) Excluding facilitie s wit hcoal-fire d boilers , approximatel y1,00 0 facilitie s ar e likel yt o continuousl yreleas e radionuclide s abov e the RQ . EPAha s examine d i n detai l release s fro mcoal-fire d utilit yan d industria l boilers , whic hcompris e the overwhelming majorit yo f facilitie s likel yt o mee t o r excee d a radionuclid e R Q o n a regula r basi s and , thus , t o repor t unde r the continuou s releas e reporting provision s o f sectio n 103(f)(2) . (Appendi xB provide s a detaile d estimatio n o f the numbe r o f facilitie s wit h coal-fire d boiler s likel yt o b e affecte d b ythe regulation. )

1- 9P.1 9

1. 6 ORGANIZATIO

N O F THI S REPORT Thi s repor t analyze s the economi c impact s o f the fina l R Q adjustment s fo r radionuclides . Th e remainde r o f thi s repor t i s organize d a s follows : Chapte r 2 : Baselin e Reportabl e Episodi c Release s --a n analysi s o f baselin e (pre-regulatory ) episodi c reportabl e releases , including a discussio n o f availabl e releas e data , siz e an d frequencydistributio n o f releases , an d the estimate d numbe r o f baselin e reportabl e releases ; Chapte r 3 : Uni t Cost s Associate dwithReportabl e Episodi c Radionuclid

e Release s --a n explanatio n o f the uni t value s use d t o estimat e the incrementa l cost s o f the fina l regulation ; Chapte r 4 : Estimate dAnnua l Cost s o f th e Fina l R

Q Adjustment s --a n analysi s o f the additiona l cost s tha t the regulate d communit yan

d the governmen t wil l incur a s a resul t o f the fina l regulation ; Chapte r 5 : Sensitivit y Analysi s - - a tes t o f the assumption s use d throughou t thi s repor t t o determin e the sensitivit yo f the result s t o variou s assumptions ; Appendi xA : Profile s o f Facilitie s that Releas e Radionuclide s -- a

discussio n o f the type s an d numbe r o f facilitie s tha t potentiall yreleas e radionuclide s an d a n estimat e o f the numbe r o f facilitie s likel yt o b e require d t o repor t continuou s release s unde r sectio n 103(f)(2) ; an d Appendi xB : Estimat e o f th e Number o f Facilitie s withCoal-fire d Boiler s Expecte

dto Repor t Release s Under Sectio n 103(f)(2) .

1-1 0CHAPTE R2 BASELIN E REPORTABLE EPISODI C RELEASE S

Aregulatorybaselin e i s the starting poin t fo r an yEconomi c Impac t Analysi s (EIA) . Th e baselin e provide s a measur e o f the estimate d cost s tha t the affecte d communit yan d governmen t woul d incur i f a regulatio n wer e no t t o tak e effect . Estimate s o f post-regulatorycost s tha t societ yincur s ca n b e measure d onc e the baselin e i s estimated , an d the differenc e betwee n the post
regulatio n cost s an d the baselin e cost s i s the incrementa l cos t o f the fina l regulation . Th e baselin e cost s i n thi s EI Aar e a functio n o f the numbe r o f reportabl e radionuclid e release s tha t equa l o r excee d CERCLA' s statutor yR Q o f on e pound . Th e baselin e cost s represen t the valu e place d o n the action s o f a responsibl e part yan

d the federa l governmen t a s a resul t o f a radionuclid e releas e tha t equal s o r exceed s th e R Q (i.e. , on e pound) , and th e valu e place d o n action s o f Stat e Emergenc yRespons e Commission s (SERCs ) an d Loca l EmergencyPlanning Committee s (LEPCs ) becaus e suc hradionuclid e release s ar e als o reportabl e t o SERC s an

d LEPC s unde r sectio n 30 4 o f Titl e II I o f the Superfun d Amendment s an

d Reauthorizatio n Ac t o f 198 6 (SARA) . Thi s chapte r estimate s the numbe r o f radionuclid e release s tha t ar e reportabl e i n the baseline . Th e baselin e estimate s presente d i n thi s chapte r represen t estimate s o f radionuclid e releas e events , o r episodi c releases , a s oppose d t o "continuous " release s fro

mradioactiv e materia l suc ha s stockpile s o f coa l o r or e materials . Thi s i s a n importan t distinctio n becaus e althoughradionuclid e release s tha t occu r i n a manne r tha t i s "continuous " an d "stabl e i n quantit y an d rate " ar e als o subjec t t o CERCL Anotificatio n an

d liabilit yprovisions , sectio n 103(f)(2 ) o f CERCL Aprovide s fo r reporting relie f fo r facilitie s wit h "continuous " an

d "stable " releases . Th e require d reporting regime mayb e quit e differen t fo r facilitie s wit h"continuous " release s o f radionuclide s tha t equa l o r excee d the RQ , a s oppose d t o the reporting regime require d fo r facilitie s tha t experienc e episodi c radionuclid e releases . Th e potentia l burde n o n facilitie s wit h"continuous " radionuclid e release s i s describe d mor e full yi n Chapte r 4 o f the EIA . Sectio n 2. 1 o f thi s chapte r describe s the methodolog yuse d t o derive the numbe r o f baselin e reportabl e episodi c releases . Section s 2.2 , 2.3 , an d 2. 4 describ e the parameter s o f the methodologytha t ar e require d t o estimat e the numbe r o f baselin e reportabl e releases ; an d Sectio n 2. 5 present s the result s o f the analysis , a n estimat e o f the numbe r o f baselin e reportabl e releases . 2. 1 METHODOLOG

YTO ESTIMATE THE NUMBE RO F BASELIN

E REPORTABLE RELEASE S Baselin e reportabl e episodi c release s ar e the numbe r o f episodi c release s (e.g. , spill s o r events ) tha t woul d nee d t o b e reporte d t o the Nationa l Respons e Cente r and t o SERC s an d LEPC s i f the fina l radionuclid e R Q adjustment s wer e no t t o tak e effec t an d the R Q remaine d a t 1 pound fo r al l radionuclides . Th e methodolog ytha t i s use d i n thi s analysi s t o estimat e th e numbe r o f baselin e reportabl e release s i s base d o n severa l importan t assumptions . Thes e assumptions , show n i n Exhibi t 2- 1 and discusse d mor e full yP.2 1

EXHIBI T 2- 1 ASSUMPTIONS USEDT

O ESTIMATE BASELIN

E REPORTABLE RELEASE S

Th e numbe r o f baselin e reportabl e release s ca n b e estimate d fro mthe following equation : BASELINE REPORTABL E RELEASE S = A* S [B i * C J wher e Ai s the tota l numbe r o f radionuclid e release s tha t occu r irrespective o f the siz e o f the release ; Bi i s the probabilit ytha t a releas e wil l b e a particula r radionuclid e i ; an d C L i s the probabilit ytha t an yradionuclid e i s release d i n a quantit ytha t equal s o r exceed s the R Q fo r radionuclid e i . Ther e i s n o significan t relationshi p betwee n the identit yo f a radionuclid e release d an d the mea n siz e o f a radionuclid e release . Historica l releas e report s fro mthe Nuclea r RegulatoryCommission' s Offic e o f Analysi s an d Evaluatio n o f Operationa l Dat a (AEOD ) ar e relativel ycomplet e fo r us e i n deriving the annua l numbe r o f release s pe r facilit yfro mCommissio n an

d Agreemen t Stat e licensee s an d DO E facilities ; under-reporting i n the AEO D i s n o mor e tha n twent ypercent . Ther e ar e approximatel y4 7 activ e DO E complexe s tha t us e an d coul d releas e radionuclides . A t eac ho f thes e complexes , ther e ar e approximatel y1 0 facilitie s tha t releas e radionuclide s i n a manne r simila r t o thos e facilitie s tha t reporte d release s t o the AEOD . Facilitie s subjec t t o radionuclid e releas e limitation s establishe d pursuan t t o the Clean Ai r Ac t ar e i n complianc e wit hthos e limitations . Th e historica l frequencyo f reporte d radionuclid e release s represent s accuratel ythe likelihoo d o f futur e release s o f tha t radionuclide . Th e historica l siz e distributio n o f reporte d radionuclid e release s represent s accuratel ythe futur e siz e distributio n o f radionuclid e releases . Federall ypermitte d release s ar e equivalen t t o release s tha t equa l the R Q level s establishe d b ythe fina l regulation .

2- 2throughou t thi s chapter , ar e necessarybecaus e n o dat a ar e availabl e tha t

permit s the direc t calculatio n o f the numbe r o f radionuclid e release s tha t equa l o r excee d the baselin e RQ . Th e methodolog

yuse d t o estimat e th e numbe r o f reportabl e radionuclid e release s i n the baselin e i s base d o n the us e o f historica l radionuclid e releas e dat a an

d the assumptio n tha t radionuclide s reporte d release d i n the pas t fairl yrepresen t futur e releas e events . Thi s approac hi s subjec t t o criticis mi n tha t the R Q adjustmen t rulemaking i s lowering the reporting trigger s fo r the vas t majorit yo f radionuclide s an d i f thi s analysi s attempte d t o projec t futur e releas e event s base d solel yo n historica l release s reporte d t o the Nationa l Respons e Cente r i t woul d surel yunderestimat e the numbe r o f release s reportabl e a t the lowe r RQs . Becaus e radionuclide s wer e no t require d t o b e reporte d t o the Nationa l Respons e Cente r i f the releas e di d no t excee d on e pound (th

e statutor

yRQ) , fewsmalle r release s woul d hav e bee n reporte d historicall yt o the Nationa l Respons e Center. 1 Facilitie s tha t produc e o r us e radionuclide s i n an ysignifican t quantit y ar e highl yregulated , however , b ythe Nuclea r RegulatoryCommission , the Departmen t o f Energ y(DOE) , and EPA . A s such , radionuclid e releas e dat a ar e collecte d routinel yfro mman yfacilities , an

d facilitie s ar e encourage d t o repor t radionuclid e release s regardles s o f the releas e quantity . I t i s believed , therefore , tha t a dat a bas e ca n b e develope d tha t fairl yrepresent s the vas t majorit yo f radionuclid e releas e events , an d tha t thi s dat a bas e ca n b e use d t o estimat e reportabl e radionuclid e release s unde r the baselin e (one pound ) R Q an

d unde r the lowe r adjuste d RQ s i n EPA' s fina l rule . Th e methodolog

yuse d t o estimat e the reporting burde n a s a resul t o f the radionuclid e R Q adjustment s relie s o n a unifie d dat a bas e o f radionuclid e releas e informatio n derive d fro mfour differen t sources , including the Nuclea r RegulatoryCommission , DOE , the Departmen t o f Transportatio n (DOT) , and EPA . Th e frequencywit hwhic heac hradionuclid e i s reporte d i n the unifie d dat a bas e i s assume d i n thi s analysi s t o b e a fai r representatio n o f the likelihoo d tha t the particula r radionuclid e wil l b e release d i n the future . I t i s als o use d t o deriv e a n independen t estimat e o f the probabilit ytha t the releas e even t wil l b e reportabl e eithe r i n the baselin e o r afte r the radionuclid e RQ s ar e adjusted . Hence , the unifie d dat a bas e i s use d t o deriv e the probabilit y tha t a particula r radionuclid e wil l b e involve d i n a reportabl e releas e even t i n the future . Th e methodolog

yuse d i n thi s analysi s estimate s thre e separat e parameters , an

d the n combine s the parameter s t o estimat e the numbe r o f baselin e reportabl e episodi c releases . Specifically , the numbe r o f baselin e reportabl e release s ca n b e calculate d fro mthe following equation :

1 Anotabl e exceptio n i s fo r release s o f radionuclide s tha t occu r during a transportatio n incident ; ther e i s n o minimu mreportabl e quantit yfo r suc h releases . 2- 3P.2 3

BASELINE REPORTABL E RELEASE S - (A ) * 2 [B i * Ci ] wher e Ai s the Tota l annua l numbe r o f episodi c radionuclid e releases ,

irrespective o f the siz e o f th e release ; Bi * i s the Probabilit ytha t the releas e i s o f a particula r

radionuclid e i , give n tha t a radionuclid e releas e occurs ; an

d C ± i s the Probabilit ytha t a particula r radionuclid e

releas e equal s o r exceed s the R Q fo r radionuclid e i . Thi s equatio n result s i n the following relationshi p fo r an yradionuclid e (i) . Assuming tha t a radionuclid e releas e occurs , the produc t o f B ± * C L i s the probabilit ytha t a particula r radionuclid e wa s release d an d tha t the releas e equal s o r exceed s on e pound 2 (i.e. , wa s reportabl e i n the baseline) . Th e su mo f the product s i s the aggregat e su mo f th e probabilities , an d i s the probabilit ythat , give n tha t a radionuclid e releas e ha s occurred , the releas e wa s reportable . Multiplying thi s aggregat e probabilit yb y(A) , the averag e annua l numbe r o f radionuclid e release s tha t occur , produce s the numbe r o f annua l radionuclid e release s equa l t o o r greate r than the baselin e R Q (i.e. , on e pound) . An implici t assumptio n i n using thi s methodolog yi s tha t ther e i s n o significan t relationshi p betwee n Facto r B , the probabilit ytha t a radionuclid e wil l b e released , an d Facto r C , the probabilit ytha t a releas e i s a certai n size . Th e assume d independenc e o f thes e probabilitie s enable s a meaningfu l product , tha t is , Bi * Ci . Thi s produc t ca n b e interprete d t o b e the probabilit ytha t a particula r radionuclid e wil l b e release d i n quantitie s tha t equa l o r excee d it s RQ . Whe n the su mo f thes e probabilitie s i s multiplie d b y Facto r A , the tota l annua l numbe r o f radionuclid e releases , the fina l answe r represent s the numbe r o f radionuclide s tha t wil l b e release d annuall ytha t equa l o r excee d thei r RQ . Th e thre e factor s i n thi s equatio n ar e derive d fro mon e o f two source s o f information . Facto r A , the tota l annua l numbe r o f radionuclid e releases , i s derive d fro

mreleas e report s t o the Nuclea r RegulatoryCommission' s Offic e fo r Analysi s an

d Evaluatio n o f Operationa l Data . Thi s derivation , an d the assumption s o n whic hi t i s based , ar e explaine d i n sectio n 2.2 . Th e remaining two factors , Facto r B (th e probabilit ytha t a particula r radionuclid e i s released ) an

d Facto r C (th

e probabilit ytha t a releas e equal s o r exceed s a specifi c quantity ) ar e derive d fro ma unifie d dat a bas e o f historica l releas e

2 Fo r an

ygive n radionuclide , a pound translate s int o a differen t numbe r o f curies . Becaus e radionuclid e releas e dat a generall yar e i n unit s o f curies , quantit yrelease d during eac hreleas e even t mus t b e translate d int o pound s t o determin e i f the on e pound R Q wa s exceeded . Alternatively , the on e pound R Q fo r radionuclide s mus t b e translate d int o a differen t numbe r o f curie s fo r eac hradionuclid e t o compar e the release d quantit ywit hthe curie

equivalen t o f on e pound . 2- 4P.2 4

reports . Th e source s an d characteristic s o f thi s unifie d dat a base , an d the assumption s o n whic hthe derivatio n o f thes e factor s i s based , ar e describe d i n section s 2. 3 an

d 2. 4 o f thi s chapter . 2. 2 DERIVATIO

N O F TOTA L ANNUA L NUMBE RO F RADIONUCLID

E RELEASE S (FACTO

RA ) Th e tota l annua l numbe r o f episodi c radionuclid e release s tha t occu r i s relate d t o the numbe r o f facilitie s tha t us e radionuclides , the amoun t o f radionuclide s handle d a t thes e facilities , an d the manne r i n whic h radionuclide s ar e handle d a t thes e facilities . Ther e ar e severa l type s o f facilitie s tha t coul d releas e radionuclides . Thes e facilitie s vary considerabl yi n the typ e an d quantit yo f radionuclide s tha t coul d b e released , an d the frequencywit hwhic hrelease s coul d occur . A s describe d i n Chapte r 1 o f thi s report , mos t facilitie s tha t us e o r produc e radionuclide s i n an y significan t quantit yar e license d b ythe Nuclea r RegulatoryCommissio n o r b y a n Agreemen t State . Facilitie s controlle d b yDO E als o coul d potentiall y releas e a significan t amoun t o f radionuclides . Othe r type s o f facilities , suc ha s mine s an

d facilitie s tha t proces s mineral s an d metals , als o coul d releas e radionuclide s eve n thoug htheyar e no t license d b ythe Commissio n o r b ya n Agreemen t State . Si xsource s o f radionuclid e releas e dat a wer e identifie d during thi s analysis . Thes e dat a source s ar e describe d i n the nex t sectio n o f thi s chapter . • N o on e dat a source , however , provide s a complet e recor d o f al l radionuclid e release s tha t hav e occurred , no r doe s the combinatio n o f these

si xsource s provid e a complet e record . I n addition , some o f the dat a source s includ e report s fro mman ydifferen t type s o f facilities ; theygenerall yd o no t presen t a complet e pictur e o f the numbe r o f release s tha t occur fro man y particula r typ e o f facility . On e dat a set , however , doe s provid e a relativel y complet e recor d o f mos t o f the release s tha t occu r fro mthe 8,90 0 facilitie s license d b

ythe Nuclea r RegulatoryCommission . Th e Commission' s reporting requirement s ar e stringen t an d requir e licensee s t o repor t immediatel yt o it s Offic e fo r Analysi s an d Evaluatio n o f Operationa l Dat a (AEOD ) losses , thefts , an d release s tha t mayhav e cause d o r threate n t o caus e certai n dos e level s t o individuals . AEO D maintain s complet e record s o f the release s tha t ar e reported . Th e AEO D data , therefore , ar e use d t o estimat e the averag e numbe r o f release s pe r Commissio n licensee . Fo r purpose s o f thi s analysis , the estimate d numbe r o f release s pe r Commissio n license e i s assume d t o b e identica l t o the numbe r o f potentia l release s pe r Agreemen t Stat e license e an d the numbe r o f release s pe r DO E facility . I t i s furthe r assume d tha t Commissio n licensees , Agreemen t Stat e licensees , an

d DO E facilitie s compris e the entir e univers e o f facilitie s likel yt o releas e reportabl e quantitie s o f radionuclide s during a n episodi c event. 3

3 A n episodi c even t i s use d her e i n contras t t o thos e radionuclid e release s tha t occu r i n a manne r tha t i s "continuous " an d "stabl e i n qualit y an d rate" , an

d therefor e coul d b e reporte d unde r CERCL Asectio n 103(f)(2) . 2- 5P.2 5

Agreemen t Stat e licensee s ar e expecte d t o b e n o differen t fro mCommissio n licensees . The ymust , a t a minimum , mee t the releas e limitation s establishe d i n 1 0 CF R Par t 20 , an d theyrepresen t simila r type s o f facilitie s (i.e. , reactors , large r laboratories , etc.) . AlthoughDO E facilitie s are , generally , verydifferen t fro

mCommissio n licensee s i n tha t theyproduc e an d us e differen t radionuclides , performdifferen t activities , an d us e differen t handling procedures , littl e dat a exis t t o develop an accurat e characterizatio n o f radionuclid e release s fro mDO E facilities . I t i s assumed , therefore , fo r purpose s o f thi s analysis , tha t radionuclid e release s fro mDO E facilitie s followa simila r patter n t o release s fro mCommissio n licensees . Ther e ar e 7 8 complexe s manage d b yDOE , 4 7 o f whic hactivel yus e radionuclides. 4 DO E complexes , suc ha s the on e a t Hanford , Washington , ar e comprise d o f man

yfacilitie s (i.e. , laboratories , reactors , etc. ) tha t us e radionuclides . Fo r purpose s o f thi s analysis , a n assumptio n i s mad e tha t a n averag e o f 1 0 facilitie s withi n a n active DO E comple xus e radionuclide s an d coul d releas e themi n a patter n simila r t o release s fro mCommissio n licensees . Thi s analysi s assumes , therefore , tha t ther e ar e 47 0 DO E facilitie s (4 7 complexe s x1 0 facilitie s pe r complex ) simila r t o Commissio n licensees . Th e AEO D data , therefore , ar e assume d t o b e representativ e o f release s from approximatel y22,40 0 facilitie s (8,90 0 facilitie s license d b ythe Nuclea r RegulatoryCommission ; 13,00 0 facilitie s license d b yAgreemen t States ; an d 47 0 facilitie s controlle d b yDOE) , an

d tha t thes e 22,40 0 facilitie s compris e the univers e o f facilitie s tha t potentiall ycoul d releas e radionuclide s during a n episodi c even t a t level s tha t excee d the RQ . Estimate d Numbe r o f Annua l Radionuclid e Episodi c Release s i n AEO D Dat a An estimat e o f the averag e numbe r o f episodi c release s o f radionuclide s tha t occu r annuall yfro mCommissio n licensee s and , b yanalogy , fro

mAgreemen t Stat e licensee s an

d DO E facilities , ca n b e determine d b yanalyzing the AEO D records . Thi s analysi s examine d radionuclid e releas e report s mad e t o th e AEO D fro m198 1 t o 1985 . Thes e releas e event s ar e no t necessaril ylarge , no r d o theynecessaril ypos e a dange r t o publi c healt ho r welfar e o r the environment . Theyinclud e al l release s reporte d t o the Nuclea r RegulatoryCommissio n ove r the las t five years . Th e AEO D dat a ar e assume d t o represen t mos t episodi c release s tha t occu r fro mCommissio n licensee s becaus e reporting o f a n inciden t i s relativel y simpl e an

d becaus e the nuclea r industryi s monitore d closel yan d i s highl y sensitive , t o publi c concerns . Th e data , however , require s som e modificatio n befor e i t ca n b e use d t o estimat e the tota l numbe r o f radionuclid e release s subjec t t o CERCL

Areporting requirement s tha t occur fro mCommissio n licensees . Fo r example , the AEO D dat a includ e transportatio n incidents . Th e Departmen t o f Transportatio n (DOT ) require s tha t al l release s o f radionuclide s tha t occu r during transportation , regardles s o f the amoun t released , mus t b e reporte d t o th e Nationa l Respons e Cente r (4 9 CF R 171.51(a)) . Becaus e o f thi s DO T

ATh e sourc e o f thi s informatio n i s a n IC F estimat e base d o n a n examinatio n o f dat a i n U.S . Environmenta l Protectio n Agency , Radionuclide s Background Informatio n fo r Fina l Rules . Volume II , Octobe r 1984 . 2- 6P.2 6

regulation , the numbe r o f reportabl e release s during transportatio n incident s wil l no t b e affecte d b ythe R Q adjustments ; al l radionuclid e release s mus t b e reporte d regardles s o f the quantit yreleased . Transportatio n incidents , therefore , ca n b e exclude d fromthe dat a set . Anothe r reaso n wh

yi t i s no t appropriat e simpl yt o us e the averag e numbe r o f release s reporte d annuall yi n the AEO D dat a se t i s tha t al l o f the release s reporte d t o the AEO D mayno t b e release s int o the environment ; onl yrelease s int o the environmen t ar e reportabl e unde r CERCLA . Stric t determination s o f the numbe r o f "releases " i n the AEO D dat a ar e difficul t t o make , however , becaus e the report s generall ylac k detail . Fo r example , i t i s sometime s difficul t t o determin e fro mthe informatio n reporte d whethe r a radionuclid e releas e wa s containe d b ya structur e o r whethe r the radionuclide s escape d int o the environment . Nonetheless , i t i s clea r tha t some adjustmen t mus t b e mad e t o the AEO D dat a t o eliminat e report s o f mislabeling an d othe r "non-release " events . Th e fina l reaso n fo r screening the releas e event s i n the AEO D dat a i s tha t i t i s likel ytha t some facilitie s mayno t b e reporting al l releas e event s t o th e AEOD , an

d the dat a mos t likel yshoul d b e adjuste d fo r potentia l under

reporting . Tw o steps , therefore , ar e take n t o estimat e the numbe r o f release s likel y t o occu r fro

mNuclea r RegulatoryCommissio n licensees . Thes e step s are : (1 ) T o defin e wha t i s mean t b ya releas e event , adjus t the dat a bas e accordingly , an d determin e a n averag e annua l numbe r o f historica l releas e event s fo r the 8,90 0 Nuclea r RegulatoryCommissio n facilities ; an d (2 ) T o estimat e the potentia l numbe r o f futur e release s b yadjusting the historica l numbe r fo r under

reporting . T o defin e a releas e even t unde r CERCL Aand t o eliminat e al l non-releas e event s fro

mthe AEO D dat a set , criteri a wer e develope d t o categoriz e the release s i n the AEO D data . Thes e criteri a ar e conservativ e i n orde r t o develop a n upperbound estimat e o f the numbe r o f episodi c releas e event s likel y t o occu r annuall yfro mthes e facilities . Approximatel y2 5 percen t o f al l report s classifie d i n thi s analysi s a s releas e event s ar e clearl yevent s involving release s t o the environment . Th e remaining event s wer e classifie d a s release s t o the environmen t i f theyexhibite d the following characteristics :

• Report s o f loss , theft , o r buria l o f radioactiv e equipmen t o r source s (approximatel y4 0 percen t o f the reports ) - - Report s o f los t radioactiv e seeds , stole n machinery , an

d burial s o f radioactiv e machineryo r wast e i n landfill s wer e classifie d a s release s t o the

. environment . Th e mos t commonl yreporte d even t throughou t th e AEO D dat a wa s the abandonmen t o f source s i n drilling holes . Becaus e th e source s ar e 2- 7P.2 7

no t recoverable , EPAconsider s al l suc hevent s t o b e a releas e t o the environment , eve n i f the source s ar e encapsulate d wit hcemen t o r slurry .

• Report s o f contaminatio n o f shippe d product s o r equipmen t (approximatel y1 5 percen t o f al l releases )

- - Report s o f contaminate d o r leaking equipmen t involve d i n shipping wer e considere d event s involving release s t o the environment . The ywer e classife d a s transportatio n releases , however , onl ywhe n escap e o r leakag e o f radioactiv e material s wa s eviden t t o shipping personne l an d reporte d b

ythem . Aspil l o f materia l o n a highway , fo r example , wa s considere d a transportatio n release . Damage , loss , o r contaminatio n o f a packag e during shipping tha t wa s no t clearl yeviden t t o shipping personnel , however , wa s assume d t o b e a nontransportatio n release . Fo r example , i f a packag e wa s receive d damaged , an d the repor t doe s no t stat e tha t the shipping agen t wa s awar e o f the damag e an d actuall yha d reporte d the incident , the repor t wa s considere d a nontransportatio n release .

• • Report s o f highstac k concentration s an d radiatio n i n unrestricte d area s (approximatel y1 5 percen t o f al l reports ) - - Citation s o f highconcentration , o f radioactiv e materia l i n exhaus t stack s an d airborn e radiatio n i n unrestricte d area s wer e classifie d a s release s t o the environment . Tha t is , i f report s di d no t specif ythe locatio n o f airborn e radioactive materials , i t wa s assume d the even t involve d a releas e t o the environment .

• Report s o f allegation s o f release s (abou t 2 percen t o f al l reports ) - - Althoughno t officiall yconfirmed , allegation s b

ypersonne l o f releas e event s (e.g. , the buria l o f radioactiv e wast e i n a landfill ) wer e treate d a s i f theywer e confirme d release s t o the environment .

• Report s o f fir e (abou t 2 percen t o f al l reports ) - - Citatio n o f a fir e wa s considere d evidenc e o f a releas e excep t wher e a repor t indicate d specificall y tha t n o contaminatio n occurred . Th e following event s wer e no t classife d a s release s t o the environment :

• Report s o f leaking source s - - Althoughi t wa s no t alway s possibl e t o determin e whethe r the reporte d lea k occurre d i n a secur e enclosure , event s suc ha s thes e wer e no t classifie d a s release s t o the environment . 2- 8P.2 8

• Report s o f positiv e radioactiv e tes t result s - - Report s citing tes t result s tha t foun d "removable " radiatio n o n laban d industria l equipmen t wer e no t classifie d a s release s t o the environment .

• Report s o f exposur e o f badge s o r personne l - - Wher e badge s wor n b

ypersonne l reflecte d exposur e t o radioactivity , thi s analysi s assume d exposur e occurre d i n a containe d structure . Badg e exposur e therefor e wa s no t classifie d a s a releas e t o the environment .

• Repor t o f loos e packaging - - Report s o f loos e o r imprope r packaging use d fo r purpose s o f transpor t wer e no t considere d evidenc e o f a release . Th e observe d escap e o f liqui d o r soli d materia l fro m packaging , however , wa s assume d t o b e a releas e t o the environment . Base d o n thes e criteria , the examinatio n o f release s i n the AEO D dat a produce d a coun t o f the numbe r o f "releas e events " tha t occurre d during eac h o f the las t five years . A"releas e event " wa s define d t o b e a releas e t o the environment . Th e numbe r o f thes e releas e event s reporte d t o AEO D i s show n i n Exhibi t 2-2 . Subtracte d fromth e numbe r o f releas e event s tha t occurre d eac h yea r i s the numbe r o f transportatio n release s tha t wer e include d i n the AEO D data . Thi s i s don e becaus e the numbe r o f reportabl e transportatio n release s wil l no t b e affecte d b ythe R Q adjustment s and , therefore , wer e exclude d from thi s analysis . Thes e adjustments , als o show n i n Exhibi t 2-2 , produc e a n estimat e o f the averag e numbe r o f releas e event s i n eac ho f the las t five year s tha t ar e consisten t wit hthe purpose s o f thi s analysis . Adjustmen t o f the AEO D dat a produce s a n estimat e tha t a n averag e o f approximatel y8 0 episodi c releas e event s hav e occurre d annuall yan d hav e bee n reporte d during eac ho f the las t fiv e year s b ythe 8,90 0 Nuclea r Regulatory Commissio n licensees . Thi s numbe r o f releas e events , however , stil l mus t b e adjuste d fo r an

yunder-reporting o f release s tha t mayhav e occurred . Ther e ar e n o dat a o n the amoun t o f under-reporting tha t occur s annually . Becaus e Commissio n licensee s ar e highl yregulate d an d verysensitive t o publi c concern s regarding radiation , however , the assumptio n wa s mad e tha t 8 0 percen t o f al l releases , irrespective o f size , wer e reported . Th e estimat e o f the degre e o f "under-reporting " i s no t assume d t o b e lowe r becaus e ther e wil l alway s b e som

e release s tha t ar e no t reported ; thi s analysi s wa s trying t o b e reasonabl yconservativ e i n it s estimatio n procedures . I t i s importan t t o not e tha t althoughthe ter m"under-reporting " i s used , i t i s no t mean t t o impl ytha t the unreporte d release s represen t an yleve l o f noncomplianc e wit hexisting reporting requirements . Thi s analysi s i s attempting t o estimat e the numbe r o f radionuclid e release s tha t occur annually , regardles s o f th e quantit yreleased ; i t i s ver ylikel ytha t smal l release s wel l withi n the licens e limitation s ar e no t reported . Th e 2 0 percen t
2- 9P.2 9

EXHIBI T 2- 2 PROFILE O

F EPISODI C RELEASE S IN NUCLEA RREGULATOR

YCOMMISSIO

N AEO DDAT A SET

Yea r
198 1 198 2 198 3 198 4 198 5 Annua l Average b Tota l Numbe r Ep o f Lsodi c Releas e Events 3

10 3 8 2 10 3 9 2 8 3 9 3 Tota l Numbe r o f

Transportatio n Release s
7 5 8 3 9 6 Tota l Numbe r

o f Nontransportatio n Episodi c Release s fro m Agreemen t State s
2I-I 8 3 1 5 6 Commissio n

State s
9 4 7 6 8 7 8 6 5 9 8 0

a An episodi c "releas e event " i s define d a s a n even t wher e radionuclide s ar e release d int o the environment . I t ofte n i s difficul t t o determin e fro mthe informatio n i n the report s whethe r a releas e t o the environmen t actuall y occurred . Whe n i n doubt , the even t wa s assume d t o resul t i n a releas e t o the environment . Th e release s represente d i n thi s exhibi t ar e no t necessaril y reportabl e unde r eithe r the one-pound R Q o r the fina l adjuste d RQs . I n addition , no t al l event s reporte d i n th e AEO D dat a ar e represente d i n thi s exhibit ; event s tha t wer e no t considere d t o b e release s hav e bee n exclude d fro mthe exhibit . Thes e exclude d event s include , fo r example , report s o f failur e t o submi t monitoring dat a an d incorrec t label s o n containers . bNumber s mayno t ad d du e t o rounding .

2-1 0P.3 0

"under-reporting " adjustmen t include s thes e small , license d releases , a s wel l a s an yothe r release s tha t wer e no t reporte d i n the past . Th e effec t o n the result s o f the under-reporting assumptio n i s teste d i n Chapte r 5 . Base d o n the assumptio n o f 8 0 percen t reporting , an d give n th e estimat e tha t an averag e o f 8 0 annua l releas e event s hav e bee n reporte d t o the AEO D during eac ho f the las t five years , thi s analysi s assume s tha t ther e hav e bee n approximatel y10 0 releas e event s tha t occu r fro mthe 8,90 0 Nuclea r Regulatory Commissio n licensee s during eac ho f the las t five years . I f 10 0 release s coul d occur fro

m8,90 0 facilities , i t i s assume d tha t approximatel y25 0 release s coul d occur fro m22,40 0 facilitie s (i.e. , Commissio n licensees , Agreemen t Stat e licensees , an d DO E facilities) . T o summarize :

• Th e AEO D data , afte r adjustmen t o f reporte d event s t o eliminat e transportatio n incident s an d al l event s tha t di d no t reflec t "release s t o the environment, " showabou t 8 0 release s t o the environmen t annuall y (se e Exhibi t 2-2) .

• Ther e i s probabl ysome under-reporting tha t occur s becaus e the purpose s o f thi s estimatio n proces s i s t o estimat e the tota l numbe r o f release s tha t occu r annually , irrespective o f the amoun t released ; annua l releas e event s wer e adjuste d upwar d t o 10 0 releases , reflecting a n assume d 2 0 percen t under-reporting .

• Onl y8,90 0 facilitie s ar e require d t o submi t report s t o AEOD ; approximatel y22,40 0 facilitie s ar e assume d t o releas e radionuclide s i n a patter n simila r t o Commissio n licensees .

• I f 10 0 release s coul d occu r fro ma univers e o f 8,90 0 facilities , 25 0 release s coul d occur annuall yfrom 22,40 0 facilities . Thi s i s a gros s estimat e o f the numbe r o f episodi c release s tha t ca n occu r annually . Becaus e the 22,40 0 facilitie s tha t ar e assume d t o releas e radionuclide s ar e no t homogeneous , theycanno t b e expecte d t o hav e uniform releas e patterns . Instead , theyar e likel yt o releas e differen t radionuclide s wit hdifferen t propensities . Thi s estimat e i s believe d t o b e a n upperbound estimat e o f the numbe r o f episodi c radionuclid e release s tha t coul d occu r annually , althoughno t al l facilitie s tha t potentiall ycoul d releas e radionuclide s hav e bee n include d i n thi s estimatio n procedure . I n particular , facilitie s tha t us e naturall yoccurring and accelerato r produce d radioactiv e materia l (NARM ) hav e no t bee n include d i n thi s estimat e becaus e ther e i s limite d informatio n abou t thei r radionuclid e releases . Thes e facilitie s ar e discusse d mor e full yi n Chapte r 4 o f thi s report .

2-1 1P.3 1

2. 3 DERIVATIO

N O F RADIONUCLIDE RELEAS E PROBABILIT Y Th e estimate d 25 0 annua l episodi c radionuclid e release s fro mfacilitie s includ e some release s tha t potentiall yequa l o r excee d the statutor yone-poun

d RQ , an d thu s some tha t ar e baselin e reportabl e releases . Th e 25 0 release s als o includ e some release s tha t ar e smalle r than 1 pound , an d thu s tha t ar e no t reportabl e unde r the baseline . T o estimat e the numbe r o f the annua l release s tha t equa l o r excee d 1 pound , estimate s o f the probabilit ytha t a particula r radionuclid e wil l b e release d (Facto r Bi ) , an d the probabilit ytha t the releas e equal s o r exceed s 1 poun d (Facto r Ci ) mus t b e developed . A s wa s the cas e wit hthe derivatio n o f Facto r A , ther e i s n o singl e dat a sourc e tha t allow s the direc t calculatio n o f thes e probabilities . Severa l dat a source s ca n b e combined , however , t o provid e som e indicatio n o f the radionuclide s tha t hav e bee n release d i n the pas t an d the siz e o f thos e releases . O f course , historica l evidenc e i s no t necessaril yindicative o f the identit yan

d siz e o f futur e releases ; technologica l innovation s occu r an d processe s chang e tha t ca n alte r the patter n o f radionuclid e releases . Fo r purpose s o f thi s analysis , however , the assumptio n i s mad e tha t the probabilit ytha t a particula r radionuclid e wil l b e release d i n the future , an d the probabilit ytha t the releas e wil l equa l o r excee d a n RQ , ca n b e estimate d base d o n the characteristic s o f historica l radionuclid e releases . Availabl e Dat a Source s o n Historica l Radionuclid e Release s Aunifie d dat a bas e wa s assemble d fo r thi s analysi s tha t incorporate s releas e report s fro msi xsources :

• Report s maintaine d b ythe Nuclea r Regulatory Commission' s Offic e fo r Analysi s an d Evaluatio n o f Operationa l Dat a (AEOD) , 198 1 throug h1985 ;

• Report s maintaine d b ythe Transportatio n Technolog y Cente r (TTC ) o f Sandi a Nationa l Laborator yi n Alburquerque , Ne wMexico , 197 1 through1985 ;

• Dat a provide d b ythe Deparmen t o f Energy' s Offic e o f Environmen t an

d Health , EmergencyOperation s Cente r (EOC) , March , 198 3 throughApril , 1986 ;

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

• Report s t o EPA' s Offic e o f Radiatio n Program s (ORP) , October , 198 1 throughSeptember , 1983 ; an d

• Report s t o the Nuclea r RegulatoryCommission' s Operation s Center , January , 198 3 throug hJanuary , 1986 . Th e mos t complet e o f thes e si xsources , bot hi n term s o f releas e description s and th e populatio n o f releas e event s include d i n the data , i s the 2-1 2P.3 2

Nuclea r RegulatoryCommission' s Offic e o f Analysi s an d Evaluatio n o f Operationa l Dat a (AEOD ) inciden t reports . Thes e report s usuall ycontai n detail s o n the quantit yan d the identit yo f the radionuclid e released . Th e releas e dat a obtaine d fro mthe Transportatio n Technolog yCente r (TTC ) and DOE' s EmergencyOperation s Cente r (EOC ) ar e equall ycomplet e i n term s o f informatio n provided . Thes e sources , however , provid e informatio n o n a muc h smalle r subse t o f releas e event s than the AEO D set . Th e TT C dat a ar e limite d t o transportatio n accident s o r incident s involving radioactive material ; the EO C dat a ar e limite d t o the pas t thre e year s (1983-1986 ) an d includ e onl y reportabl e event s unde r DO E Orde r 5484.1 . Th e releas e dat a fro mthe Nationa l Respons e Cente r d o no t contai n detaile d quantit yinformation . Report s examine d fro mthe Nuclea r Regulatory Commission' s Operation s Cente r includ e onl yevent s tha t the Nuclea r Regulatory Commissio n define s a s releases . Th e Commission' s definitio n i s narrowe r tha n CERCLA' s definitio n o f release . Release s fro mfacilitie s i n Agreemen t State s ar e no t represente d i n the Nuclea r RegulatoryCommission' s dat a set , the Sandi a Nationa l Laboratorydat a set , the DO E dat a set , o r the EPAOffic e o f Radiatio n Program s dat a set . I t i s possibl e tha t release s fro mAgreemen t State s ar e represente d i n the dat a se t fro mthe Nationa l Respons e Center , bu t the dat a fro

mthi s sourc e ar e mostl yqualitativ e and , fo r the mos t part , wer e no t include d i n the unifie d EI Adat a base . Inciden t repor t duplicatio n betwee n the si xsource s appear s t o b e relativel ylimited . Doubl e counting o f release s i n the developmen t o f the unifie d EI Adat a bas e wa s avoide d b ycross-checking the detail s abou t particula r releas e events . Th e incompletenes s o f the report s i n some set s and the inconsis-tencie s i n the date s o f the events , however , mad e thi s a complicate d effort . I t i s likel ytha t som e duplicat e counting exist s despit e effort s t o preven t it . Th e unifie d EI Adat a bas e develope d fo r thi s analysi s include s 1,13 9 releas e events . Thes e release s rang e i n siz e from5. 0 xIO" 9 curi e t o 56,89 2 curies . Ther e ar e 45 5 event s i n the unifie d EI Adat a bas e wit hn o quantit y informatio n o r fo r whic hthe unit s o f curie s coul d no t b e determine d from availabl e information . Thes e 45 5 event s ar e use d onl yt o estimat e the frequencyo f releas e fo r particula r radionuclides . Ther e als o ar e 2 3 event s i n the EI Adat a bas e tha t ar e no t identifie d b yradionuclid e bu t d o hav e informatio n o n the quantit yreleased . Thes e event s wer e include d i n determining the siz e distributio n bu t no t i n calculating the frequencyo f a radionuclid e release . Exhibi t 2- 3 summarize s the characteristic s o f the unifie d EI Adat a base . FrequencyDistributio n o f Release s o f Radionuclide s Th e unifie d EI Adat a bas e assemble d fo r thi s analysi s include s informatio n o n 6 3 uniqu e radionuclide s tha t wer e release d during 1,13 9 releas e events . Becaus e thi s analysi s assume s tha t the probabilit yo f a futur e releas e o f a radionuclid e i s n o differen t fro mthe frequencywit hwhic ha particula r radionuclid e wa s release d i n the past , the probabilit yo f a futur e
2-1 3P.3 3

EXHIBI T 2- 3

CHARACTERISTIC S O F TH E UNIFIE D RADIONUCLID E DAT ABAS E

Tota l Numbe r o f Releas e Event s - 1,13 9
Numbe r o f releas e event s withou t quantit yinformatio n - 45 5 Numbe r o f releas e event s wit h' 1,13 9 quantit yinformatio n (used t o | estimat e siz e distribution ) - 68 4
Numbe r o f releas e event s wit h radionuclid e unidentifie d - 2 3 Numbe r o f releas e event s wit hi 1,13 9 radionuclid e identifie d (used t o estimat e releas e frequency ) - 1,11 6
Source : IC F Analysis .

2-1 4P.3 4

releas e o f eac hradionuclid e include d i n the unifie d dat a bas e i s derive d fro m the frequencyo f pas t reporte d release s fo r tha t particula r radionuclide . Exhibi t 2- 4 display s the frequencydistribution s fo r eac hradionuclid e i n the unifie d EI Adat a base , (i.e. , fo r eac hradionuclid e tha t ha s bee n release d a t leas t onc e during the five year s represente d i n the EI Adat a base) . Fo r example , Uranium-23 8 (U-238 ) wa s involve d i n 12 9 o f the 1,11 6 event s wit h identifie d radionuclide s i n the unifie d dat a base. 5 Therefore , base d o n the assumptio n tha t the frequencyo f pas t release s o f a radionuclid e i s indicative o f the probabilit yo f it s futur e release , thi s analysi s estimate d that , give n tha t a radionuclid e releas e occurs , the probabilit yi s 0.11 5 (129/1,116 ) tha t the radionuclid e wil l b e Uranium-238 . Th e releas e frequencie s show n i n Exhibi t 2- 4 wer e use d t o estimat e the probabilit ytha t a particula r radionuclid e wil l b e release d i n the future . Anothe r exampl e i s Iodine-129 , reporte d i n the unifie d dat a bas e t o b e release d onl yonc e i n the 1,11 6 releas e event s tha t identif ythe radionuclid e released . Thi s analysi s assume s tha t the probabilit yo f a releas e o f Iodine

12 9 i n the futur e i s 0.000 9 (1/1116) . Fo r purpose s o f thi s analysis , radionuclide s tha t ar e no t represente d i n the unifie d dat a bas e (i.e. , thos e tha t hav e no t bee n reporte d release d i n the five yea r perio d represente d b ythe dat a base ) ar e assume d t o hav e a zer o probabilit yo f being release d i n the future . Thi s is , o f course , a simplifying assumptio n becaus e n o dat a bas e o f historica l release s ca n perfectl yreflec t futur e releases . Th e unifie d dat a base , however , i s believe d t o b e a reasonabl e representatio n o f the type s an d quantitie s o f radionuclide s tha t wil l b e release d i n the future . Some isotope s ar e mor e commo n an

d use d mor e ofte n b yfacilitie s than other s and , therefore , ar e mor e likel yt o b e release d than radionuclide s tha t ar e use d les s frequently . Man y radionuclide s ar e create d i n laboratorie s an d mayexis t fo r onl ya few seconds ; other s hav e a n extremel yshor t half-lif e an d maydecaywithi n 2 4 hours . Therefore , althoughonl y6 3 uniqu e radionuclide s ar e identifie d i n the unifie d dat a base , i t i s believe d tha t the historica l releas e frequencie s show n i n Exhibi t 2- 4 ar e a reasonabl e approximatio n fo r th e probabilit yo f a releas e i n the futur e o f a particula r radionuclide . 2. 4 SIZ E DISTRIBUTIO N O F RADIONUCLIDE RELEASE S Facto r B , derive d i n the las t sectio n o f thi s analysis , i s the probabilit ytha t a particula r radionuclid e wil l b e released . T o determin e whethe r a radionuclid e releas e i s reportabl e unde r the baseline , however , quantitie s release d mus t b e examined . Th e baselin e R Q fo r radionuclide s (i.e. , 1 pound ) i s i n mas s units , althoughradionuclid e release s generall yar e reporte d i n activit ylevel s (i.e. , curies) . I n fact , curie s ar e a muc hmor e commo n an d appropriat e uni t

5 Althoughther e ar e a tota l o f 1,13 9 releas e event s i n th e data , onl y 1,11 6 event s include d informatio n sufficien t t o identif yth e radionuclid e released . 2-1 5w Q H • J O (/

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YO F EPISODI C RELEASE S FO REAC HRADIONUCLIDE I N THE UNIFIE

DEI A DAT A BAS E (Continued )

Radionuclid e Identit y
OS-18 5 OS-19 1 P-3 2 PB-21 0 PB-21 2 PM-14 7 PO-21 0 PU-23 8 PU-23 9 RA-22 6 RB-8 8 RU-10 6 S-3 5 SB-12 5 SR-9 0 TA-18 2 TC-9 9 TH-23 2 TH-23 4 TL-20 1 TL-20 4 U-23 5 U-23 8 XE-13 3 ZN-6 5 SUBTOTAL Unknown isotope s TOTAL Numbe r o f 1

i n Dat a Bas e

1

1 2r-i 9 1 1 1 4 1 7 3 9 4r-i 2 4r-i 1 7 2 3 7 1 2 1 2 4 1 8 12 9 1 5 3 11 6 2 3 13 9 Frequencyo f Releas e (Facto r B )
0.001 8 0.000 9 0.008 1 0.000 9 0.000 9 0.012 5 0.015 2 0.002 7 0.008 1 0.003 6 0.000 9 0.001 8 0.003 6 0.000 9 0.015 2 0.001 8 0.033 2 0.010 8 0.000 9 0.001 8 0.003 6 0.016 1 0.115 6 0.013 4 0.002 7

Source : IC F estimates .

2-1 7P.3 7

o f measuremen t fo r radioactivity , an d on e pound o f eac hradionuclid e translate s int o a wid e rang e o f curie-equivalents . T o determin e i f a releas e i n the dat a bas e exceed s 1 pound , therefore , the curie-equivalen t o f 1 pound wa s derive d fo r eac hradionuclide . Th e curie-eqivalen t o f 1 pound fo r eac h radionuclid e i s a functio n o f a radionuclide' s half-lif e an d atomi c mass . Fo r example , 1 pound o f Radium-22 6 i s equa l t o 449 . curies ; 1 pound o f Uranium-23 8 i s equa l t o 0.000 2 curie . A s a resul t o f the differen t ranslation s fro mon e pound t o unit s o f curies , the probabilit ytha t a particula r radionuclid e releas e wil l equa l o r excee d the 1 pound R Q wa s estimate d individuall yfo r eac hradionuclide . Onl y68 4 event s i n the dat a bas e hav e informatio n abou t the quantit y released . Asummar yo f the siz e distributio n o f thes e 68 4 event s i s show n i n Exhibi t 2-5 . A n analysi s o f the dat a show s tha t theyar e skewed , reflecting a muc hhighe r probabilit yo f a smal l releas e an d a smal l probabilit yo f a larg e release . Alogarithmi c analysi s o f 68 4 releas e event s produce s a lo g norma l distribution , wit ha mea n o f 0.1 5 curi e an d a standard deviatio n o f 2. 7 curies . Th e lo g norma l distributio n o f the dat a illustrate s tha t mos t o f the release s ar e small . Exhibi t 2- 5 show s tha t 28 0 o f 68 4 releas e events , o r approximatel y4 1 percent , wer e a t leas t 1 curi e i n size . Th e exhibi t als o show s tha t onl y7 o f the 68 4 releas e event s i n the five-yea r perio d equalle d o r exceede d 100 0 curies . Thi s analysi s assume d tha t the historica l frequencywit hwhic ha radionuclid e releas e occurre d a t a give n quantit yi s a goo d approximatio n o f th e probabilit ytha t a futur e radionuclid e releas e als o wil l occu r a t tha t quantity . Fo r example , 28 0 o f the 68 4 release s i n the dat a bas e wer e a t leas t 1 curie ; thi s analysi s assume d tha t the probabilit ytha t a futur e radionuclid e releas e wil l b e a t leas t 1 curi e i s 0.40 9 (280/684) . Similarly , becaus e onl y 7 o f the 68 4 releas e event s i n the dat a bas e wer e 1,00 0 curie s o r greater , thi s analysi s assume d tha t the probabilit ytha t a futur e radionuclid e releas e wil l b e 1,00 0 curie s o r mor e i s 0.01 0 (7/684) . Thu s far , i t ha s bee n assume d tha t Facto r B an d Facto r C ar e independen t an d tha t the probabilit ytha t a reportabl e radionuclid e releas e occur s ca n b e determine d b

ythe produc t o f Facto r B an d Facto r C . An analysi s o f the correlatio n betwee n Facto r B an d Facto r C i n the unifie d dat a bas e wa s conducte d t o tes t the validit yo f thi s assumption . Althoughthe result s o f the statistica l tes t wer e no t conclusive (se e Chapte r 5 fo r details) , ther e wa s sufficien t suppor t fo r the assumptio n tha t Facto r B an d Facto r C ar e no t

2-1 8P.3 8

EXHIBI T 2- 5 SIZ E DISTRIBUTIO

N O F RADIONUCLID

E RELEASE S I N TH E EI A DAT A BAS E

Quantit y (Curies ) Numbe r o f Release s

i n Dat a Bas e tha t Equal s o r Exceed s Quantit y Probabilitytha t an yReleas e Wil l Equa l o r Excee d Quantity 3

0.00 1 0.0 1 0. 1 1 1 0 10 0 100 0 52 1 43 7 33 7 28 0 12 8 1 8 7 0.76 2 0.63 9 0.49 3 0.40 9 0.18 7 0.02 6 0.01 0

a Derive d b ydividin g 68 4 int o th e numbe r o f release s i n th e unifie d dat a bas e tha t equal s o r exceed s tha t quantity . Ther e i s a tota l o f 68 4 release s wit hquantit yinformatio n i n th e unifie d dat a base . Source : IC F analysis .



## DAT ABAS E RELEAS E QUANTIT YDISTRIBUTIO N 40 0

u z I d e 

## 5 u 

## 8 u. O c

- I 

# i

_ 35 0 - 30 0 - 25 0 - 20 0 - 15 0 - 10 0 - 5 0 -

i.- a 3 0 4 0 5 0 a o ROEAS C QUANTIT

Y(Cl ) 7 0 9 0 10 0 >10 0

2-1 9correlate d an d thu s ar e independent , an d tha t the numbe r o f reportabl e radionuclid e release s ca n b e estimate d b ymultiplying the two factors. 6 2. 5 BASELIN

E REPORTABLE EPISODI C RELEASE S Sectio n2. 1 o f thi s repor t presente dth e methodolog

y fo r derivin

g th e thre e factor s necessaryt o calculat e the numbe r o f baselin e reportabl e episodi c releases . Sectio n 2. 2 estimate d Facto r A(i.e. , 25 0 radionuclid e releases , occur annually) ; Sectio n 2. 3 derive d estimate s fo r Facto r B (i.e. , the probabilit ytha t a particula r radionuclid e wil l b e released) ; an d Sectio n 2. 4 derive d estimate s fo r Facto r C (i.e. , the probabilit ytha t the releas e wil l equa l o r excee d a give n quantity) . Thi s sectio n combine s thes e thre e factor s an

d estimate s the numbe r o f baselin e reportabl e episodi c releases . Ther e i s on e additiona l factor , however , tha t mus t b e considere d befor e estimating the numbe r o f baselin e reportabl e release's . Becaus e some facilitie s ar e license d an d ar e allowe d i n thei r licens e t o releas e certai n quantitie s o f radionuclide s (i.e. , federall ypermitte d releases) , thi s analysi s mus t accoun t fo r the amoun t o f a releas e tha t i s federall ypermitted , befor e calculating the numbe r o f baselin e reportabl e releases . Sectio n 101(10 ) o f CERCL Adefine s federall ypermitte d releases . Release s tha t ar e no t i n complianc e wit hfederall ypermitte d releas e level s onl ynee d t o b e reporte d t o the Nationa l Respons e Cente r an d t o stat e an

d loca l emergencyrespons e commission s i f the releas e equal s o r exceed s the federall y permitte d leve l b

ya n R Q o r more . Therefore , i n the baseline , reportabl e release s ar e thos e tha t ar e a t leas t 1 pound abov e federall ypermitte d levels . Th e federall ypermitte d releas e leve l a t an yfacilit ydepend s upo n the specifi c releas e bein g controlled , an d upo n the relevan t regulation s (e.g. , 1 0 CFR Par t 2 0 fo r the Nuclea r RegulatoryCommissio n licensees) . Mos t federall y permitte d radionuclid e release s ar e controlle d throughNuclea r Regulatory Commissio n o r Agreemen t Stat e licenses ; the federall ypermitte d releas e leve l fo r man yfacilities , therefore , i s a 50 0 milliremwhol e bod ydose-equivalen t fo r a maximu

mexposur e t o the genera l public .

6 Th e us e o f on e siz e distributio n i s no t the idea l methodology . T o b e sure , the releas e behavio r o f al l radionuclide s i s no t identical . Ideally , a separat e siz e distributio n o f release s fo r eac hradionuclid e shoul d b e developed . Give n the paucit yo f the dat a availabl e o n radionuclid e releas e events , however , the creatio n o f on e siz e distributio n i s no t unreasonable . T o tes t the sensitivit yo f our result s t o thi s assumption , however , the El A dat a bas e wa s divide d int o tw o groups . Th e firs t grou p consiste d o f thre e radionuclide s (Cs-137 , A m241 , an

d Co-60 ) tha t ar e use d commonl yi n larg e quantitie s an

d accoun t fo r ove r one-thir d o f th e tota l numbe r o f releas e event s i n the dat a set . Th e secon d grou p wa s comprise d o f the remaining 6 0 radionuclide s i n the dat a set . Auniqu e siz e distributio n o f release s wa s calculate d fo r eac hgorup . Th e analysi s showe d tha t the numbe r o f incrementa l reportabl e release s increase d b y1 5 percent , a relativel ysmal l increase . Therefore , althoughus e o f on e siz e distributio n i s a simplification , th e effect s o

nthe result s o f th e economi c analysi s appear t o be minimal . 2-2 0P.4 0

Th e RQ s ar e derive d using exposur e scenario s base d o n the numbe r o f curie s that , i f release d int o the environmen t ove r a 24-hou r period , coul d resul t i n a 50 0 milliremwhol e bod ydose-equivalen t t o a n individua l standing 3 0 meter s fro

mthe releas e point . Becaus e the RQ s ar e the quantitie s o f radionuclide s released , i n curies , tha t coul d resul t i n a 50 0 millirem exposure , an

d becaus e 50 0 millire mi s the exposur e limitatio n t o the genera l publi c fo r the Nuclea r RegulatoryCommissio n an d Agreemen t Stat e licensees , thi s analysi s assume s tha t federall ypermitte d releas e amount s ar e equivalen t t o * the RQs . Thi s assume d equivalencybetwee n RQ s an d the federall ypermitte d releas e level s i s a simplification . EP Ause d conservative assumption s i n developing RQs , an d generall yfacilitie s ca n releas e mor e than a n R Q withou t exceeding the 50 0 milliremexposur e leve l t o the genera l public . Fo r example , the Agenc yuse d exposur e model s tha t assume a n individua l i s locate d 3 0 meter s fro ma releas e poin t an d wil l maintai n tha t positio n fo r 2 4 hours . Man y facilitie s tha t potentiall ycoul d releas e radionuclide s (e.g. , powe r reactors ) hav e restricte d zones ; the genera l publi c ofte n coul d b e locate d 15 0 meter s away . Thus , i f a releas e o f a n R Q occurre d fro msuc ha facility , i t i s unlikel ytha t the genera l publi c woul d receiv e a 50 0 milliremwhol e bod ydose

equivalen t becaus e theywoul d b e muc hfarthe r awa yfro mthe releas e poin t tha n 3 0 meters . Similarly , the occupationa l exposur e limitatio n unde r 1 0 CFR Par t 2 0 i s 5 rem(1 0 time s 50 0 millirem) . Th e RQ s ar e derive d base d o n a n exposur e limi t an 1 orde r o f magnitud e lowe r than the occupationa l exposur e limit s i n Commissio n licenses . Fo r purpose s o f thi s analysis , however , the RQ s ar e assume d t o equa l the federall ypermitte d level . Althoughthi s assumptio n i s fa r fro mprecise , i t i s a reasonabl e approximatio n fo r purpose s o f thi s analysis . However , i t wil l ten d t o overestimat e the numbe r o f reportabl e release s and , therefore , the cost s an d impact s o f the radionuclid e R Q adjustments . Give n thi s assumption , therefore , unde r the baseline , radionuclid e release s tha t equa l o r excee d the su mo f on e pound plu s the fina l adjuste d R Q fo r tha t radionuclid e ar e reportabl e release s fro mfacilitie s tha t hol d federa l permits ; tha t is , baselin e reportabl e release s ar e thos e release s tha t ar e a t leas t 1 pound abov e "federall ypermitted " levels . Base d o n the methodolog ydescribe d i n Sectio n 2.1 , estimate s o f the numbe r o f baselin e reportabl e episodi c release s ca n b e derive d fo r facilitie s license d b

ythe Nuclea r RegulatoryCommission , Agreemen t States , o r DO E (i.e. , reportabl e release s tha t ar e a t leas t on e pound abov e the federall ypermitte d level s a t thes e facilities) .

BASELINE REPORTABL E EPISODI C RELEASE S = A* 2 [B i * Ci ] Ai s the Estimate d tota l numbe r o f annua l

episodi c release s (250) , derive d b y assuming tha t the AEO D dat a bas e i s representativ e o f release s fro m Nuclea r RegulatoryCommission , Agreemen t State , an d DO E facilities ;
2-2 1P.4 1

Bi i s the Probabilit ytha t radionuclid e i wil l

b e released , derive d b yassuming historica l reporte d release s ar e representativ e o f the probabilit ytha t a futur e releas e o f an yradionuclid e (i ) wil l occur ; and CAi s the Probabilit ytha t a radionuclid e

releas e i s reportable , derive d b y assuming historica l release s ar e representativ e o f the probabilit ytha t a futur e releas e equal s o r exceed s a give n quantity . Thi s give n quantit y i s th e su

mo f the curie-equivalen t o f on e pound o f eac hradionuclid e (th e statutoryRQ ) plu s the fina l adjuste d RQ , a prox

yfo r the federall y permitte d releas e level . Give n thi s methodolog yan d the estimate s fo r eac ho f the thre e factor s derive d i n thi s chapter , the numbe r o f baselin e reportabl e episodi c release s ca n b e calculated . First , fo r eac hradionuclide , Facto r B i s multiplie d b y Facto r C . Fo r example , Cesium-13 7 ha s a n estimate d frequencyo f releas e o f 0.201 6 becaus e ther e wer e 22 5 report s i n the unifie d EI Adat a bas e i n whic h Cesium-13 7 wa s identifie d a s the radionuclid e tha t wa s release d (se e Exhibi t 2-4) . I t i s assumed , therefore , tha t ther e i s a twent ypercen t probabilit y tha t Cesium-13 7 wil l b e release d i n the futur e (Facto r Bi ) . Th e fina l R Q fo r Cesium-13 7 i s 1 curie ; 1 pound o f Cesium-13 7 i s equa l t o 3,94 0 curie s (se e Exhibi t 2-6) . Becaus e federall ypermitte d releas e level s ar e assume d i n thi s analysi s t o equa l the fina l adjuste d RQ , a releas e o f 1 pound above federall y permitte d level s fo r Cesium-13 7 i s a releas e o f 3,94 1 curie s (3,94 0 curie s + 1 curie) . Ther e ar e 2 historica l radionuclid e release s reporte d i n the unifie d EI Adat a bas e tha t equa l o r excee d 3,94 1 curies . Thi s analysi s assumes , therefore , tha t ther e i s a 0.002 9 (2/684 ) probabilit ytha t the releas e wil l b e a t leas t 3,94 1 curie s (Facto r C) . Multiplying Facto r B fo r Cesium-13 7 b y Facto r C fo r Cesium-13 7 produce s the probability , therefore , tha t a reportabl e releas e o f Cesium-13 7 occurs . Th e estimate d probabilit ytha t a Cesium-13 7 releas e wil l occu r a t level s tha t equa l o r excee d the R Q plu s on e pound i s equa l t o 0.0005 8 (0.201 6 x0.0029) . The calculatio n o f the numbe r o f baselin e reportabl e release s i s show n i n Exhibi t 2-6 . Thi s exhibi t show s fo r eac hradionuclid e i n the unifie d EI Adat a base , the probabilit ytha t the radionuclid e wil l b e release d i n the futur e (Facto r Bi ) an

d the probabilit ytha t a releas e equal s o r exceed s the baselin e R Q fo r tha t radionuclid e (Facto r Ci) . Thi s produc t i s the n multiplie d b ythe tota l numbe r o f annua l radionuclid e episodi c release s (250) , an d summe d acros s al l radionuclide s i n the EI Adat a base . Th e exhibi t show s the estimate d numbe r o f baselin e reportabl e releases ; tha t is , the su mo f th e numbe r o f estimate d reportabl e episodi c release s fo r eac hradionuclid e represent s the tota l numbe r o f baselin e reportabl e episodi c release s fromfederall ypermitte d facilitie s (i.e. , Commissio n an d Agreemen t Stat e licensees , an d DO E facilities) . A s show n o n the secon

d pag e o f the exhibit , ther e ar e 1 9 2-2 2

### EXHIBI T 2- 6

REPORTABL E BASELIN E RADIONUCLID E RELEASE S ESTIMATE DFROM TH E UNIFIE DEI A

DATA BAS E

RADIONUCLID E

AM-24 1 AM/B E AR-4 1 BA-13 3 C-1 4 CA-4 5 CD-10 9 CE-14 1 CM-24 4 CO-5 7 CO-5 8 CO-6 0 • CR-5 1 CS-13 1 CS-13 4 CS-13 7 EU-15 2 EU-15 4 F-1 8 FE-5 5 FE-5 9 6A-6 7 GE-7 7 H- 3 HG-19 7 1-12 3 1-12 5 1-12 9 1-13 1 IN-11 1 IR-19 2 K-4 2 KR-8 1 KR-8 5 MO-9 9 NA-2 4 NI-5 9 NI-6 3 OS-18 5 OS-19 1 P-3 2 PB-21 0 PB-21 2 R

Q (CURIES )

0.0 1 0.0 1 1 0 1 0 1 0 1 0 1 1 0 0.0 1 100 1 0 

### i o 100 0 100 0 1 1 1 0 1 0 100 0 10 0 1 0 100 1 0 100 100 0 1 0 0.0 1 0.00 1 0.0 1 10 0 1 0 100 100 0 100 0 100 1 0 100 100 1 0 100 0. 1 0.0 1 1 0 NUMBERO

F CURIE S PE

R POUNDOF RADIONUCLID E

1.47E+0 3 1.47E+0 3 1.90E+1 0 1.70E+0 5 2.02E+0 3 7.99E+0 6 1.06E+0 5 1.29E+0 7 3.58E+0 4 3.84E+0 6 1.43E+0 7 5.13E+0 5 4.18E+0 7 2.19E+1 0 5.90E+0 5 3.94E+0 4 8.42E+0 4 1.35E+0 5 4.32E+1 0 1.14E+0 6 2.23E+0 7 2.28E+0 9 1.63E+0 9 4.38E+0 6 1.11E+0 8 8.70E+0 8 7.95E+0 6 2.00E-0 4 5.63E+0 7 1.90E+0 8 4.16E+0 6 2.73E+0 9 9.60E+0 0 1.78E+0 5 2.15E+0 8 3.95E+0 9 3.44E+0 1 2.80E+0 4 3.42E+0 6 2.07E+0 7 1.29E+0 8 3.79E+0 4 6.31E+0 8 BASELINE

REPORTABL E LEVE L (R Q+ 1 POUND )

1.47E+0 3 1.47E+0 3 1.90E+1 0 1.70E+0 5 2.02E+0 3 7.99E+0 6 1.06E+0 5 1.29E+0 7 3.58E+0 4 3.84E+0 6 1.43E+0 7 5.13E+0 5 4.18E+0 7 2.19E+1 0 5.90E+0 5 3.94E+0 4 8.42E+0 4 1.35E+0 5 4.32E+1 0 1.14E+0 6 2.23E+0 7 2.28E+0 9 1.63E+0 9 4.38E+0 6 1.11E+0 8 8.70E+0 8 7.95E+0 6 2.00E-0 4 , 5.-63E+0 7 1.90E+0 8 4.16E+0 6 2.73E+0 9 9.60E+0 0 1.78E+0 5 2.15E+0 8 * 3.95E+0 9 3.44E+0 1 2.80E+0 4 3.42E+0 6 2.07E+0 7 1.29E+0 8 3.79E+0 4 6.31E+0 8 FREQUENCYOF

RADIONUCLID E RELEAS E (FACTO RB )

0.099 5 0.025 1 0.000 9 0.005 4 0.009 0 0.002 7 0.000 9 0.001 8 0.001 8 0.005 4 0.001 8 0.0609 ' 0.002 7 0.000 9 0.000 9 0.201 6 0.001 8 0.000 9 0.000 9 0.005 4 0.001 8 0.006 3 0.000 9 0.036 7 0.001 8 0.001 8 0.057 3 0.000 9 0.028 7 0.000 9 0.081 5 0.000 9 0.000 9 0.024 2 0.013 4 0.004 5 0.000 9 0.029 6 0.001 8 0.000 9 0.008 1 0.000 9 0.000 9 FREQ . OF RELEAS E

ABOVE BASELINE REPORTABL E LEVE L (FACTO RC )

0.010 2 0.010 2 0.000 0 0.000 0 0.010 2 0.000 0 0.000 0 0.000 0 0.002 9 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.002 9 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.831 9 0.000 0 0.000 0 0.000 0 0.000 0 0.187 1 0.000 0 0.000 0 0.000 0 0.051 2 0.002 9 0.000 0 0.000 0 0.000 0 0.002 9 0.000 0 TOTA

L NUMBER OF RADIONUCLID E RELEASE S (FACTO RA )

25 0 250 25 0 25 0 25 0 25 0 250 250 25 0 25 0 25 0 250 25 0 250 25 0 25 0 250 25 0 25 0 25 0 25 0 250 25 0 250 25 0 250 250 25 0 250 25 0 25 0 250 25 0 250 25 0 25 0 25 0 25 0 250 250 250 250 250 NUMBER

OF BASELINE REPORTABL E RELEASE S (A*B*C )

0.2 5 0.0 6 0.0 0 0.0 0 0.0 2 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.1 5 * 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.1 7 0.0 0 0.0 0 I 0.0 0 0.0 0 0.0 0 0.0 0 

### o.o o | 0.0 0 0.0 0 0.0 2 

### o.o o ! 0.0 0 0.0 0 0.0 0 0.0 0 

### 2-2 3P.4 3



### EXHIBI T 2- 6 (continued )

REPORTABL E BASELIN E RADIONUCLID E RELEASE S ESTIMATE DFROM TH E UNIFIE DEI A

DATA BAS E

RADIONUCLID E

PM-14 7 PO-21 0 PU-23 8 PU-23 9 RA-22 6 RB-8 8 RU-10 6 S-3 5 SB-12 5 SR-9 0 TA-18 2 TC-9 9 TH-23 2 TH-234 - • TL-20 1 TL-20 4 U-23 5 U-23 8 XE-13 3 ZN-6 5 R

Q (CURIES )

1 0 0.0 1 0.0 1 0.0 1 0. 1 100 0 1 1 1 0 0. 1 1 0 1 0 0.00 1 10 0 100 0 1 0 0. 1 0. 1 10 0 1 0 NUMBEROF CURIE S PE

R POUN DOF RADIONUCLID E

4.20E+0 5 2.04E+0 6 7.90E+0 3 2.79E+0 1 4.49E+0 2 5.45E+1 0 1.52E+0 6 1.92E+0 9 4.72E+0 5 6.40E+0 4 2.83E+0 6 7.75E+0 0 5.00E-0 5 1.05E+0 7 9.56E+0 7 2.09E+0 5 1.00E-0 3 2.00E-0 4 8.46E+0 7 3.73E+0 6 BASELINE

REPORTABL E LEVEL (R Q + 1 POUND )

4.20E+0 5 2.04E+0 6 7.90E+0 3 2.79E+0 1 4.49E+0 2 5.45E+1 0 1.52E+0 6 1.92E+0 9 4.72E+0 5 6.40E+0 4 2.83E+0 6 7.75E+O 0 5.00E-0 5 1.05E+0 7 9.56E+0 7 2.09E+0 5 1.O0E-O 3 2.00E-0 4 8.46E+0 7 3.73E+0 6 FREQUENC YO F

RADIONUCLID E RELEAS E (FACTO RB )

0.012 5 0.015 2 0.002 7 0.008 1 0.003 6 0.000 9 0.001 8 0.003 6 0.000 9 0.015 2 0.001 8 0.033 2 0.010 8 0.000 9 0.001 8 0.003 6 0.016 1 0.115 6 0.013 4 0.002 7 FREQ . O F RELEAS E

ABOVE BASELINE REPORTABL E LEVEL (FACTO RC )

0.000 0 0.000 0 0.004 4 0.058 5 0.014 6 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.000 0 0.193 0 0.859 6 0.000 0 0.000 0 0.000 0 0.761 7 0.831 9 0.000 0 0.000 0 TOTA

L NUMBER O F RADIONUCLID E RELEASE S (FACTO RA )

25 0 250 25 0 250 250 25 0 250 25 0 250 25 0 250 250 25 0 250 25 0 250 250 25 0 250 250 NUMBER

OF BASELIN E REPORTABL E RELEASE S (A*B*C )

0.0 0 0.0 0 0.0 0 0.1 2 0.0 1 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 0.0 0 1.0 1 2.0 3 0.0 0 0.0 0 0.0 0 1.9 2 13.7 7 0.0 0 0.0 0

TOTAL BASELIN E REPORTABL E RELEASE S 1 9

SOURCE : ICF ANALYSI S

* Number s may

no t adddu e t o rounding .



### 2-2 4baselin e reportabl e releases . Chapte r 5 test s the sensitivit yo f the

assumption s tha t underli e the methodolog yuse d t o estimat e the numbe r o f reportabl e releases . Thi s chapte r ha s addresse d onl yradionuclid e release s fro mfederall y permitte d facilities . Ther e als o ca n b e reportabl e radionuclid e release s fro m unlicense d facilities . Thes e additiona l reportabl e release s ar e discusse d i n Chapte r 4 late r i n thi s report .

2-2 5P.4 5

CHAPTE R3 UNI T COST S ASSOCIATEDWITH REPORTABLE EPISODI C RADIONUCLID E RELEASE S

On e purpos e o f an Economi c Impac t Analysi s (EIA ) i s t o estimat e the incrementa l cost s tha t resul t fro ma regulator

yaction . Thi s sectio n o f the repor t identifie s the uni t cost s associate d wit haction s attributabl e t o the fina l R Q adjustments . Sectio n 3. 1 describe s action s tha t ar e expecte d a s a resul t o f reportabl e episodi c release s o f radionuclides ; Sectio n 3. 2 estimate s the valu e o f the action s tha t facilit yowners/operator s ar e expecte d t o tak e whe n a reportabl e episodi c releas e occurs ; an d Sectio n 3. 3 estimate s the valu e o f action s tha t governmen t official s ar e expecte d t o take . Th e statutor

yR Q fo r radionuclide s i s on e pound . Th e fina l radionuclid e R Q adjustment s wil l lowe r the R Q belo won e poun d fo r 73 0 radionuclide s an d wil l rais e the R Q abov e on e pound fo r 2 7 radionuclides. xBecaus e the R Q adjustment s ar e generall ydownward , the fina l regulatio n woul d b e expecte d t o resul t i n a n increas e i n the numbe r o f reportabl e episodi c release s t o the Nationa l Respons e Cente r an d t o stat e an

d loca l emergencyrespons e commissions . Thes e additiona l reportabl e episodi c release s impos e cost s o n the facilit yowner s o r operators , wh o mus t immediatel ynotif ygovernmen t entities , an

d the n mayfollow-u p the telephon e call s wit hrespons e action s an d writte n reports . Th e increas e i n reportabl e episodi c release s als o impose s cost s o n governmen t employees , wh o mus t proces s the report s an d ensur e tha t partie s tak e prope r action s i n respons e t o the releases . Th e increas e i n the numbe r o f episodi c reportabl e release s tha t result s fro mthe R Q adjustment s wil l generat e benefit s fo r society . Generally , ther e i s a positiv e correlatio n betwee n reporting episodi c radionuclid e release s an d faste r an

d mor e efficien t cleanup s o f the releases , resulting i n les s harmt o publi c healt han

d welfar e an

d the environment . Fo r 2 7 radionuclides , the fina l R Q adjustment s rais e th e RQ . A s a result , cost s saving s (benefits ) fo r bot hthe regulate d communit yand the governmen t mayaccru e becaus e fewe r release s wil l nee d t o b e reporte d t o the Nationa l Respons e Cente r an d t o stat e an

d loca l emergencyrespons e commissions . Th e remainde r o f thi s chapte r describe s the action s take n b yal l partie s affecte d b

ythe radionuclid e R Q adjustments , the incrementa l action s tha t ar e attributabl e t o the fina l R Q adjustments , an d the valu e o f the action s take n b yal l parties .

1 Thi s discussio n refer s onl yt o the individuall yadjuste d RQs ; othe r radionuclide s ar e assigne d a n R Q o f 1 curi e tha t mayb e abov e o r belo wa pound . Althoughi t wil l varywit heac hradionuclide , generall yth e fina l 1 curi e R Q wil l b e lowe r tha n the statutor yR Q o f on e pound fo r thes e othe r radionuclide s a s well .P.4 6

3. 1 ACTIONS TAKE

N WIT HA REPORTABLE RADIONUCLIDE EPISODI C RELEAS E ACTION S B Y RELEASER S Facilit yowners/operator s ca n b e expecte d t o tak e thre e type s o f action s whe n a n episodi c radionuclid e releas e occurs : notification , recordkeeping , an d response . Th e notificatio n actio n i s require d b yCERCL Aan d SAR Ai n respons e t o a reportabl e release . Recordkeeping an d respons e actions , however , ar e no t require d b ythe statute s an

d onl yoccur indirectl ya s a resul t o f the regulation . I t i s the actio n o f owner s o r operator s notifying the governmen t tha t trigger s subsequen t action s b yal l partie s an

d that , i n turn , result s i n an ycost s societ yincurs . Notificatio n b

ya responsibl e part yo f a reportabl e episodi c releas e include s reporting t o the Nationa l Respons e Cente r a s require d unde r sectio n 103(a ) o f CERCLA , an d t o stat e an

d loca l emergenc yrespons e commission s a s require d unde r SAR

Asectio n 304 . Notificatio n involve s mor e than the tim e spen t b ya plan t manage r i n a telephon e conversatio n wit hthes e agencies . I t als o include s th e time spen t b yanyon e a t a facilit ywh o migh t become involve d i n communicating wit hth e governmen t a t the tim e o f the releas e o r subsequen t t o it . Depending o n the siz e o f the facilit yresponsibl e fo r the release , the siz e o f the release , an d the identit yo f the substanc e tha t comprise s the release , the following peopl e a t a facilit ymigh t spen d tim e communicating wit hthe Nationa l Respons e Cente r an d othe r federal , state , an d loca l governmen t agencies : foreman , plan t manager , plan t environmenta l contro l specialist , plan t safet yspecialist , an d attorneys . Sectio n 30 4 o f SAR

Aals o require s tha t a facilit yowne r o r operato r provid e a writte n follow-u p repor t afte r th e initia l telephon e notification . Thi s follow-u

p repor t mus t includ e (1 ) action s take n t o respon d t o an d contai n the release ; (2 ) an yknown o r anticipate d acut e o r chroni c healt hrisk s associate d wit hthe release ; an d (3 ) wher e appropriate , advic e regarding medica l attentio n necessaryfo r expose d individuals . Recordkeeping i s ofte n associate d wit hnotification . Althoughneithe r CERCL Ano r SAR

Arequire s tha t record s o f release s b e kept , facilit y owners/operator s coul d b e expecte d t o maintai n log s o f call s t o the Nationa l Respons e Center . Suc ha lo g mayb e usefu l fo r manager s i n establishing tha t the notificatio n requirement s o f CERCL Asectio n 103(a ) hav e bee n met , an d i n preparing the follow-u p writte n repor t t o stat e an d loca l emergencyrespons e commission s a s require d unde r SAR Asectio n 304 . Th e lo g migh t includ e a descriptio n o f the incident , it s cause , a brie f accoun t o f conversation s wit h governmen t officials , an d a descriptio n o f the outcome o f the inciden t an d cleanu p actions . Respons e include s action s take n b ythe responsibl e part yt o mitigat e the effect s o f the episodi c release . Typica l respons e action s includ e sampling the air , wate r o r soil ; evaluating the necessit yfo r evacuatio n an d relocation ; directl ycontaining the release ; removing o r neutralizing the releas e throughsuc htechnique s a s pumping , activate d carbo n treatment , o r aeration ; decontaminating affecte d areas ; an d removing an

ycontaminate d soi l o r other materials . 3- 2P.4 7

ACTION S B Y GOVERNMEN T Th e governmen t take s four type s o f action s i n respons e t o notificatio n o f a n episodi c reportabl e release : notificatio n processing , off-scen e monitoring , on-scen e monitoring , an d direc t removal . Official s taking thes e response s includ e official s responding t o call s fro mthe Nationa l Respons e Center , an

d thos e official s responding t o call s fro mthe stat e an

d loca l emergencyrespons e commissions . Notificatio n Processing include s the initia l communicatio n wit hthe perso n wh o call s the Nationa l Respons e Cente r t o repor t a n episodi c radionuclid e release . I t als o include s evaluatio n o f the reporte d information , determining the nee d fo r a fiel d response , i f any , an d subsequen t recordkeeping . Notificatio n processing b ystat e an

d loca l official s include s action s simila r t o thos e o f federa l officials . Stat e an d loca l emergenc y respons e commission s receive call s fro mfacilitie s tha t releas e radionuclides , an d thes e loca l official s mus t notif ythe appropriat e personne l wh o ca n evaluat e the informatio n an d determin e the nee d fo r a fiel d response . Stat e an d loca l official s als o mus t proces s the releaser' s follow-u p writte n repor t whe n i t i s submitted . Off-scen e monitoring include s supervisio n an d monitoring o f the responsibl e party' s action s throug htelephon e an

d dat a monitoring . Thes e action s coul d includ e inquirie s abou t the nee d fo r furthe r dat a collection , determinatio n o f the exten t o f the release , o r report s o n the selectio n and progres s o f cleanu

p actions . On-scen e monitoring include s a governmen t officia l providing advic e an d assistanc e i n perso n t o the cleanu p team , coordinating communication s among agencies , providing informatio n t o th e public , and ensuring tha t the Agency' s concern s ar e represente d i n determining the appropriat e response . Th e initiatio n o f on-scen e monitoring mayb e relate d t o the dange r o r threatene d dange r tha t a releas e pose s t o publi c healt ho r welfar e o r the environment , o r mayoccu r i f a facilit yneed s o r request s a particula r typ e o f assistance . Direc t remova l i s necessarywhe n the responsibl e part ycanno t o r wil l no t adequatel yclean u

p the radionuclid e releas e an d the releas e represent s a hazar d t o publi c healt ho r welfar e o r the environment . Althoughthe governmen t respons e agencynormall ywil l us e a privat e contracto r t o clean u p the release , governmen t respons e team s nevertheles s hav e sampling , monitoring , containment , an

d safet yequipmen t t o assis t i n handling the initia l emergency an d t o assis t the contractor s i n the cleanup . Direc t removal s als o coul d requir e o r utiliz e mor e than on e governmen t agency. 2

2 Fo r example , EPA , the Coas t Guard , the Nuclea r RegulatoryCommission , the Departmen t o f Energy , the Federa l Emergenc yManagemen t Agency , stat e respons e agencies , stat e an d loca l polic e and highwayresources , o r loca l fir e department s coul d become involve d i n a releas e event . 3- 3P.4 8

ACTION S ATTRIBUTE D T O RADIONUCLID E R O ADJUSTMENT S Facilit yowner s o r operator s an d the governmen t performsome numbe r o f action s whe n a reportabl e episodi c releas e o f a radionuclid e unde r the baselin e scenari o occur s (i.e. , whe n a releas e exceed s on e pound) . Becaus e the fina l regulatio n adjust s the RQ s downwar d fo r 73 0 o f 75 7 radionuclides , ther e i s expecte d t o b e a n increase d numbe r o f reportabl e episodi c release s an d a corresponding increas e i n the numbe r o f time s eac hactio n i s performed . Thes e additiona l action s ar e the incrementa l action s attribute d t o th e fina l regulation. . Th e fina l regulatio n coul d increas e notification , recordkeeping , an d respons e activitie s fo r facilitie s handling an d releasing radionuclide s tha t hav e a fina l R Q o f les s tha n on e pound . Similarly , i t coul d decreas e notification , recordkeeping , an d respons e activitie s fo r facilitie s handling an d releasing radionuclide s wit ha fina l R Q exceeding on e pound . Th e additiona l cos t (or cos t savings ) an yfacilit ywil l incur i s relate d t o the numbe r o f reportabl e release s fro mtha t facility , the quantit yan d typ e o f radionuclide s handle d a t the facility , an d the forms o f radionuclide s (i.e. , seale d sources , solid , liquids , o r gases ) use d a t a facility . I n additio n t o the economi c cost s an d cos t saving s resulting fro mthe chang e i n the numbe r o f release s reporte d t o the Nationa l Respons e Cente r an d t o stat e an

d loca l emergencyrespons e commissions , the fina l R Q adjustment s affec t publi c healt han d welfar e and environmenta l quality . Th e fina l R Q adjustment s coul d hav e the following effects : Raising RO s fo r particula r radionuclide s maydecreas e the numbe r o f reportabl e releases . Assuming tha t some releaser s ar e les s likel y t o clea n u

p release s o f radionuclide s belo wthe RQ , mor e publi c healt han

d welfar e an

d environmenta l damage s coul d occur wit hhighe r RQs . Thes e incrementa l damage s ar e cost s o f raising the RQ s fo r some radionuclides . Decreasing RO s fo r a particula r radionuclid e wil l increas e the numbe r o f reportabl e release s fo r tha t substance . I f thes e lowe r RQ s lead t o increase d an d earlie r notification s o f release s an d t o appropriat e an

d timel yrespons e action s tha t woul d no t otherwis e hav e occurred , publi c healt han d welfar e an

d environmenta l damage s coul d b e mitigated . Thes e decrease d o r avoide d damage s ca n b e considere d t o b e a benefi t o f lowering the RQ s fo r some radionuclides . 3. 2 VALUATIONO F ACTION S TAKE NBY EPISODI C RELEASER S O F RADIONUCLIDE S Economi c cost s includ e the valu e o f resource s tha t mus t b e use d a s a resul t o f a reportabl e episodi c release . Th e majorit yo f the tim e estimate s

3- 4P.4 9

use d i n thi s analysi s ar e take n directl yfro mthe RegulatoryImpac t Analysi s (RIA ) tha t supporte d the R Q adjustmen t fo r 34 0 CERCL Ahazardou s substances. 3 Notification . Becaus e the CERCL Aan d SAR Anotificatio n requirement s requir e a perso n i n charg e o f a facilit yt o notif ythe Nationa l Respons e Cente r an

d stat e an

d loca l emergencyrespons e .commissions , i t i s reasonabl e t o assume tha t a plan t manage r o r representativ e wil l become involve d i n the notificatio n proces s soo n afte r a releas e i s discovered . I n additio n t o the plan t manager , the time expende d and the typ e o f othe r peopl e wh o become involve d i n notificatio n activitie s likel ywil l depen d o n the following four factors : the amount , identity , an d for m(solid , liqui d o r gas ) o f the radionuclid e released ; the locatio n o f the release ; the response s o f governmen t officials ; an d the siz e an

d organizationa l structur e o f the responsibl e party' s business . Base d o n tim

e estimate s i n the RI Ai n suppor t o f the R Q adjustment s fo r 34 0 CERCL

Ahazardou s substance , i t i s assume d tha t the cos t o f notifying the Nationa l Respons e Cente r o f release s o f les s than 5 5 gallon s o f a hazardou s substanc e i s $7 6 pe r report , an d notificatio n cos t fo r release s ove r 5 5 gallon s i s $19 7 pe r report. 4 I t woul d no t b e appropriate , fo r two reasons , t o differentiat e notificatio n cost s fo r radionuclid e release s o n the basi s o f whethe r the releas e i s abov e o r belo w5 5 gallons . First , gallon s i s no t a n appropriat e measur e fo r amount s o f radionuclides ; second , a radionuclid e releas e wel l belo won e pound coul d b e extremel ydangerou s an d coul d generat e a grea t dea l o f concer n an d publi c interest , resulting i n relativel yhigh notificatio n costs . Radionuclid e release s engende r publi c concer n an d scrutin ybecaus e o f the lac k o f understanding an d genera l fea r fel t b ythe publi c regarding radiatio n an d radioactive contamination . Th e responsibl e part ymayhav e t o respon d t o mor e call s fro mstat e an

d loca l governmen t official s an

d fro mthe pres s afte r a releas e o f a radionuclid e than i f anothe r typ e o f hazardou s substanc e wa s released . Fo r thes e reasons , i t seem s appropriat e t o b e conservativ e an d t o assume tha t the cost s fo r facilit yowner s o r operator s t o notif ythe Nationa l Respons e Cente r o f a n episodi c radionuclid e releas e ar e close r t o $19 7 (which include s thre e hour s o f manageria l time an d two hour s o f technica l time ) tha n t o $7 6 (whichinclude s on e hou r o f manageria l time and on e hou r o f technica l

3 IC F Incorporated , RegulatoryImpac t Analysi s o f Reportabl e Quantit y Adjustment s Unde r Sectio n 10 2 an d 10 3 o f the Comprehensiv e Environmenta l Response . Compensation , an d Liabilit yAct . Volume I , March , 1985 . AIbid. . p . 3-9 . Th e compensatio n rate s fo r industr yar e take n fro

mU.S . Environmenta l Protectio n Agency , Estimate d Cost s o f the Fina l Comprehensiv e Assessmen t Informatio n Rule . Fina l Report . Marc h31 , 1988 , pp . 44-46 . Thes e assume d industr

ywag e rate s consis t o f direc t salar yan d persona l fring e benefit s bu t d o no t includ e the allocatio n o f othe r overhea d costs . Th e hourl ywag e rates , update d t o Thir d Quarte r 198 7 dollar s an d rounde d t o the neares t whol e dollar , are : Management , $45 ; Technical , $31 ; an d Clerica l $1 4 (Memorandu

mt o Bria n Muehling an d Kat e Devine , RegulatoryImpact s Branch , EPA , fro mJef f Karnes , Kearney/Centaur , Apri l 5 , 1988) . 3- 5P.5 0

time) . Th e analysi s assumes , therefore , tha t eac hepisodi c releas e notificatio n cost s th e regulate d communit y$19 7 t o notif ythe Nationa l Respons e Center . Th e cost s involve d i n reporting a n episodi c releas e unde r SAR Asectio n 30 4 ar e the cost s o f manageria l an d technica l personne l placing telephon e call s t o stat e an

d loca l emergencyrespons e commissions . Thi s effor t i s estimate d t o requir e 0.0 8 hour s o f manageria l tim e an d 0.0 8 hour s o f technica l time fo r preparatio n o f necessaryinformation , resulting i n a tota l cos t o f $6.10. 5 Th e telephon e cal l t o the loca l emergencyplanning committe e i s expecte d t o tak e 30-minutes , wit han associate d labo r cos t o f $22.5 0 (30

- minute s o f manageria l time) . Anothe r phon e cal l t o the stat e commissio n i s require d an

d als o i s likel yt o b e a 30-minut e tol l call . A30-minut e call , a t averag e busines s rates , cost s approximatel y$8.87 . Therefore , the estimate d tota l cos t o f notifying th e stat e commissio n i s $31.3 7 ($22.5 0 plu s $8.87) , an d the estimate d cos t o f notifying bot hstat e an d loca l authoritie s i s estimate d t o b e $59.9 7 ($6.1 0 + $22.5 0 + $31.37) . Facilit yowner s an d operator s als o mus t follow-u p thei r call s t o the stat e an d loca l emergency respons e commission s wit ha writte n report . Th e cos t o f producing thi s repor t wil l varywit hthe siz e an d severit yo f the release . Th e RI Ai n suppor t o f rulemaking unde r section s 302 , 303 , an d 30 4 o f the Superfun d Amendment s an

d Reauthorizatio n Ac t o f 198 6 estimate d the averag e cost 6 o f producing a follow

up repor t t o b e $117.30 . Exhibi t 3- 1 provide s a summar yo f the notificatio n cost s describe d here . Recordkeeping . Th e RI Asupporting the R Q adjustmen t fo r 34 0 CERCL A hazardou s substance s estimate d the resource s require d t o perfor minterna l recordkeeping t o b e 1 clerica l hou r pe r release , an d assume s a rati o o f 1 supervisoryhou r t o eac h1 0 hour s o f clerica l time. 7 Thi s estimat e implie s a cos t o f $18.5 0 pe r release , assuming $1 4 pe r hou r fo r clerica l tim e an d $4 5 pe r hou r fo r manageria l time . Recordkeeping cost s associate d wit ha chemica l releas e an

d recordkeeping cost s associate d wit ha radionuclid e releas e shoul d no t diffe r substantially . Thi s same uni t cost , therefore , i s use d i n thi s analysi s fo r radionuclides . I t als o i s assume d tha t the cost s t o facilitie s fo r recordkeeping associate d wit hthe notificatio n o f stat e an d loca l emergenc yrespons e personne l i s include d i n the estimate s fo r complying wit h CERCLA , an

d n o additiona l time i s required .

5 Thes e time estimate s wer e develope d in : U.S . Environmenta l Protectio n Agency , RegulatoryImpac t Analysi s i n Suppor t o f Rulemaking Unde r Section s 302 . 303 . an

d 30 4 o f Titl e II I o f the Superfun d Amendment s an

d Reauthorizatio n Ac t o f 1986 . Economic s an d Technolog

yDivision , Offic e o f Toxi c Substances , EPA , Apri l 10 , 1987 . p . A-9 .

6 Ibid . 7 IC F Incorporated , RegulatoryImpac t Analysi s o f Reportabl e Quantit y Adjustment s Unde r Section s 10 2 an d 10 3 o f the Comprehensiv e Environmenta l Response . Compensation , and Liabilit yAct . Volume I , Marc h1985 , p.3-11 . 3- 6EXHIBI T 3- 1 UNI T NOTIFICATIO

N COST S T

O FACILIT

YOWNERS/OPERATOR S O F A REPORTABLE EPISODI C RELEAS E P.5 1

Actio n Labo r Category Hour s Hourl y Wag e Cos t Telephon e Nationa l Respons e Cente r Manage r Technica l 3

2 $45.0 0

$31.0 0 $19 7

Preparatio n t o Telephon e Stat e an

d Loca l Emergency Respons e Commission s Telephon e Loca l Emergency Respons e Commissio n Telephon e Stat e Emergency Respons e Commissio n Manage r Technica l
Manage r Manage r .0 8 .0 8
0. 5
0. 5 $45.0 0

$31.0 0 $45.0 0 $45.0 0 $ 6.1 0

$ 22.5 0 $ 31.3 7

Cos t o f half-hou r tol l cal l $8.8 7

Tota l cos t o f notifying stat e an d loca l emergencyrespons e commission s $ 59.9 7

Prepar e Writte n Follow-u p Repor t fo r stat e an

d loca l emergencyrespons e commission s $117.3 0

Source : IC F analysis .

3- 7Response . T o estimat e respons e costs , tw o consideration s mus t b e factore d int o the analysis . Th e firs t facto r i s the probabilit ytha t a facilit ywil l respon d t o a n episodi c release ; the secon d facto r i s the cos t tha t i s associate d wit ha response . Bot hfactor s likel yar e correlate d wit h the siz e o f a releas e an d the damag e tha t i t ha s cause d o r threaten s t o cause . Althoughaccurat e dat a ar e generall yunavailable , Nuclea r Regulatory Commission , Departmen t o f Energy , an d EPAsource s agre e generall ytha t responsibl e partie s currentl yrespon d adequatel yt o a verylarg e percentag e o f episodi c releases . Responsibl e partie s ar e liabl e fo r respons e cost s and natura l resourc e damage s fo r al l releases , whethe r thes e release s ar e abov e o r belo wthe RQs , episodi c o r continuous . I t i s logica l t o assume , however , tha t a responsibl e part yi s mor e likel yt o respon d t o a releas e tha t i s above the R Q than i t i s t o a releas e tha t i s belo wthe R Q simpl ybecaus e the releas e i s large r an

d the responsibl e part ymus t notif ythe Nationa l Respons e Cente r an d stat e an

d loca l emergencyrespons e commissions . Fo r the purpose s o f thi s analysis , therefore , i t i s assume d tha t responsibl e partie s adequatel yrespon d t o 9 0 percen t o f episodi c radionuclid e release s belo wthe R Q an d 9 5 percen t o f episodi c radionuclid e release s above the RQ . Hence , i f the R Q i s lowered , a 5 percen t increas e i n respons e activitie s i s expecte d fo r thos e episodi c release s tha t ar e no wreportable . Th e RI Afo r R Q adjustment s fo r 34 0 CERCL Ahazardou s substance s estimate d tha t facilitie s incurre d a rang e o f respons e cost s o f betwee n $20 2 an d $2,29 6 pe r release; 8 thi s rang e wa s a functio n o f the siz e o f the release . Radionuclid e release s are , i n general , muc hsmalle r tha n the on e pound t o 500 0 pound chemica l release s considere d i n the RIA . Radionuclid e releas e responses , however , ofte n requir e specia l equipmen t an d protectiv e clothing , resulting i n respons e cost s tha t mayb e highe r tha n the respons e cost s associate d wit hothe r chemica l releases . Fo r thes e reasons , the RI Aestimate s wer e no t use d i n thi s analysi s t o estimat e radionuclid e respons e costs . Instead , thre e mode l releas e scenario s wer e develope d fo r thi s analysi s base d o n representativ e episodi c releas e report s i n the EI Adat a base . Th e thre e scenario s represen t a rang e o f respons e action s an d respons e costs . Base d o n the thre e respons e scenarios , cos t estimate s wer e derive d t o determin e a weighte d averag e respons e cos t fo r a n episodi c radionuclid e release . Scenari o 1 represent s a smal l radionuclid e releas e resulting fro ma fault yvalv e a t a conversio n facilit yo r laboratory . Th e radionuclid e release d coul d b e Uranium-238 , Tritium , o r Krypton-85 . Th e appropriat e respons e fo r scenari o 1 woul d likel yb e monitoring fo r a n 8-hou r period . Cost s fo r scenari o 1 ar e use d fo r al l release s whos e respons e cost s woul d b e expecte d t o b e minimal . Scenari o 2 represent s a laborator yo r hospita l situatio n wher e a radionuclid e accidentl yi s dispose d wit hthe regula r garbage . Th e radioactiv e materia l i s the n shredde d an d pu t i n a dumpster . Radionuclid e release s likel y t o b e represente d i n thi s mode l includ e Cobalt-60 , Iodine-125 , Iodine-131 , an d Iridium-192 . Scenari o 2 cost s includ e monitoring an d decontamination .

8 Ibid. . p . 3-11 . 3- 8Scenari o 3 involve s a hypothetica l releas e o f Uranium-23 8 t o surfac e

water . Th e releas e mayhav e resulte d froma pip e failur e o r lagoo n overflo w an d involve s majo r respons e actions , including monitoring an d dredging o f contaminate d sediment . Exhibi t 3- 2 shows , fo r eac hscenario , the estimate d cost s o f hypothetica l responses . Al l cost s ar e i n 198 7 dollars . Base d o n the frequencyo f occurrenc e o f differen t type s o f release s i n the EI Adat a base , i t i s assume d tha t scenari o 1 cost s ar e representativ e cost s fo r 6 6 percen t o f respons e actions ; scenari o 2 cost s ar e representativ e cost s fo r 2 7 percen t o f respons e actions ; an

d scenari o 3 cost s ar e representativ e cost s fo r 7 percen t o f respons e actions . Therefore , thes e respons e scenario s yiel d the following averag e weighte d respons e cos t fo r radionuclid e releases :

$5,60 8 pe r respons e - [(0.66 ) x($166) ] + [(0.27 ) x($5,937) ] + [(0.07 ) x($55,637) ]
Thi s analysi s als o assume s tha t governmen t official s woul d agre e o n wha t respons e a facilit yshoul d tak e t o clea n u p a n episodi c releas e o f radionuclide s an

d tha t an

yrespons e cost s associate d wit hreporting t o stat e o r loca l emergenc yrespons e commission s ar e capture d alread yi n the above estimates . 3. 3 VALUATIO

N O F GOVERNMEN

T ACTION S Mos t action s performe d b ythe governmen t involve cost s tha t do no t vary wit hthe typ e o f CERCL Ahazardou s substanc e released . Notificatio n processing , an

d off-scen e and on-scen e monitoring cost s fo r radionuclid e release s ar e simila r t o cost s incurre d fo r othe r CERCL Ahazardou s substances . Th e RI Ai n suppor t o f the R Q adjustmen t fo r 34 0 CERCL Ahazardou s substance s provide s uni t time estimate s o f governmen t action s an d ar e use d i n thi s analysis . Th e following estimate s o f cost s ar e summarize d i n Exhibi t 3-3 . Notificatio n Processing bvGovernmen t Officials . Th e RI Ai n suppor t o f the R Q adjustment s fo r 34 0 CERCL Ahazardou s substance s estimate d tha t processing a cal l t o the Nationa l Respons e Cente r take s approximatel y3 0 percen t o f a governmen t workday. 9 Fo r purpose s o f thi s analysis , i t i s assume d tha t a governmen t workdayi s value d a t $184. 1 0 Thi s produce s a n

9 Th e tw

o an d a hal f hour s o f governmen t time fo r notificatio n processing include s time fo r severa l governmen t official s t o confe r abou t the releas e situation . Depending upo n the natur e an d siz e o f the releas e an d the facilit y responsibl e fo r th e release , i t i s likel ytha t representative s fro mEPA , DOE , o r the Nuclea r RegulatoryAgenc ycoul d b e calle d t o asses s the situation .

1 0 Th e assume d compensatio n rat e fo r governmen t employee s i s base d o n the GS-1 1 step 1 pa yleve l and i s adjuste d t o includ e th e cos t o f persona l fring e benefits , assume d t o b e 4 0 percen t o f direc t wages . Th e annua l compensatio n fo r 22 0 workday s i s $40,393 , translating int o a dail ywag e rat e o f $184 . 3- 9EXHIBI T 3- 2 RADIONUCLID

E RESPONS E COS T ESTIMATE S

RELEAS E SCENARI O # 1

CIRCUMSTANCE : Asmal l radionuclid e releas e fro ma faile d valv e a t a conversio n facilit yo r laborator y TYPICAL RADIONUCLIDES : IO" 2 curie s o f Uranium-238 , Tritium , o r Krypton-8 5 RESPONS E ACTIVITIE S AND COS T ESTIMATES :

Arespons e mayno t b e necessaryno r appropriat e fo r ai r release s o f thi s size . However , thi s analysi s assume s respons e require s 8 hour s o f monitoring . Tota l Estimate d Cost : $16 6

RELEAS E SCENARI O # 2

CIRCUMSTANCE : Radionuclid e sourc e accidentl ydispose d o f a s standar d soli d waste , shredded , an d pu t i n dumpste r TYPICAL RADIONUCLIDES : IO" 2 curie s o f Cobalt-60 , Iodine-125 , Iodine-131 , o r Iridium-19 2 RESPONS E ACTIVITIE S AND COS T ESTIMATES :

Monitoring an

d decontaminatio n o f bench , tras hca n an d car t - $33 2 Monitoring an

d decontaminatio n o f shredde r an d dumpste r - $560 5 Tota l Estimate d Cos t - $593 7

3-1 0P.5 5

EXHIBI T 3- 2 (continued ) RADIONUCLID

E RESPONS E COS T ESTIMATE S

RELEAS E SCENARI O # 3

CIRCUMSTANCE : Radionuclid e releas e fro mproces s discharg e pip e t o strea m tha t feed s int o a rive r TYPICAL RADIONUCLIDES : 2 0 curie s o f Uranium-23 8 RESPONS E ACTIVITIE S AND COS T ESTIMATES : Monitoring ( 1 wk. ) a t outfall , ditch , stream , an d rive r - $166 1 Ground wate r monitoring wel l (drillin g an d sampling ) - $103 8 Treatmen t o f 5,00 0 gallon s o f contaminate d wate r ($0.20/gal , including mobilizatio n fo r ion-exchang e resin ) - $103 8 Dredging an

d disposa l o f contaminate d sediment s (100 0 c u ft ) - $51,90 0 Tota l Estimate d Cos t - $55,63 7

Source : IC F analysi s base d o n the following sources : U.S . Environmenta l

Protectio n Agency , Remedia l Respons e a t Hazardou s Wast e Site s (EP A 540/2-84-002) , Marc h1984 ; Tawil , J.J . et . al. , Off-Sit e Consequence s o f Radiologica l Accidents : Methods . Costs , an d Schedule s fo r Decontamination . Battelle.Northwes t Laboratories , Prepare d fo r U.S . Nuclea r RegulatoryCommission , Augus t 1985 ; IC F 1987 .

3-1 1EXHIBI T 3- 3 UNI T COST S T

O AL L GOVERNMEN

T ENTITIE S O F A REPORTE

DEPISODI C RELEAS E

Actio n Estimate d Cos t

Proces s on e cal l t o the Nationa l Respons e Cente r Proces s on e cal l t o loca l emergencyrespons e commissio n Proces s on e cal l t o Stat e emergencyrespons e commissio n Proces s writte n follow-u p report s (stat e and loca l commissions ) Off-scen e monitoring activitie s On-scen e monitoring activitie s Direc t remova l $ $ $•CO- $ 

### $ 2 $5 5 5 7 5 7 5 7 1 1


### 21 9 71 0 63 7 5 0 5 0 5 0 5 0
0 0 0 0 0 0

Source : IC F analysis .

3-1 2P.5 7

estimat e fo r processing notification s t o the Nationa l Respons e Cente r o f $57.50 . Notificatio n processing b ystat e an

d loca l official s involve s action s simila r t o thos e performe d b ythe federa l government . Stat e an d loca l official s mus t proces s call s t o the stat e an d loca l emergencyrespons e commission s tha t ar e simila r t o thos e receive d b ythe Nationa l Respons e Center . Thi s analysi s assumes , therefore , tha t th e cost s incurre d b ystat e an d loca l government s als o ar e $57.5 0 fo r eac hreport ; an d tha t two report s (one t o eac hcommission ) ar e required , yielding a tota l cost s o f $115 . Stat e an d loca l official s als o mus t proces s writte n follow-u p reports ; thi s analysi s assume s processing follow-u p report s require s a half-hou r o f governmen t time , fo r a tota l cos t pe r repor t o f $11.50 . Off-scen e Monitoring . Th e RI Ai n suppor t o f the R Q adjustmen t fo r 34 0 CERCL Ahazardou s substance s estimated 1 1 tha t the activitie s o f off-scen e monitoring ar e expecte d t o consume 6 0 percen t o f a governmen t workdayan d 3 0 percen t o f a contracto r workday(valued a t $35 8 pe r day) . Thes e assumption s produc e an estimate d cos t fo r off-scen e monitoring o f $219 . Th e RI Aals o assume s tha t the likelihoo d o f off-scen e monitoring b ythe governmen t varie s wit hthe siz e o f the reporte d release . Th e RI Aassume s governmen t off-scen e monitoring i s likel ybetwee n 4 0 percen t an d 7 0 percen t o f the time . Thi s analysi s assume s tha t a governmen t respons e actio n i s mor e likel yfo r a radionuclid e releas e tha n fo r the averag e chemica l releas e becaus e o f publi c awarenes s an

d concer n ove r radiatio n contamination . Therefore , i t i s assume d tha t the likelihoo d o f off-scen e monitoring b ythe governmen t i s 7 0 percent . On-scen e monitoring . Th e RI Afo r adjusting the RQ s o f 34 0 CERCL A hazardou s substance s estimate d tha t on-scen e monitoring woul d requir e five governmen t workday s an d five contracto r workdays , resulting i n a n estimate d cos t o f $2,71 0 fo r eac hoccurrenc e o f on-scen e monitoring . Th e RI Aals o assume s tha t the likelihoo d o f the governmen t becoming involve d i n on-scen e monitoring i s i n the rang e o f 5 t o 2 0 percent . Becaus e a governmen t respons e actio n mayb e mor e likel yfo r a radionuclid e releas e than fo r a chemica l release , thi s analysi s assume s the likelihoo d o f on-scen e monitoring i s 2 0 percent . Th e sensitivit yo f the result s t o thi s assumptio n i s teste d i n Chapte r 5 . Direc t Removal . Th e RI Afo r 34 0 CERCL Ahazardou s substance s estimate d direc t remova l costs 1 2 t o b e $39,273 . Thi s cos t estimat e i s modifie d i n thi s analysi s becaus e direc t respons e action s fo r radionuclid e release s ar e differen t fro

mdirec t respons e action s fo r othe r chemica l releases .

1 1 Ibid . Th e differenc e i n dail ycos t betwee n a contracto r an d a n EP A worke r reflect s difference s i n task s performe d an d the personne l neede d t o performthos e tasks , a s wel l a s the inclusio n o f overhead expense s (sucha s equipment ) i n contracto r cost s tha t ar e no t include d i n the estimat e fo r a governmen t worker .

1 2 Th e RI Afo r the 34 0 CERCL Ahazardou s substance s assume d the likelihoo d o f a direc t governmen t respons e actio n wa s betwee n on e an d five percent . Th e hig hend o f thi s range , five percent , i s assume d t o b e mor e appropriat e fo r radionuclid e releases , Ibid. . p . 3-17 . 3-1 3P.5 8

Decontaminatio n procedures , fo r example , ofte n involve specia l equipmen t an d protectiv e clothing . Th e mode l cos t scenario s discusse d earlie r i n the chapte r an

d describe d i n Exhibi t 3- 2 ar e the basi s fo r estimating the direc t remova l cost s associate d wit ha radionuclid e release . I t i s assume d tha t the governmen t woul d ge t involve d onl yi n the mos t costl yo f the thre e scenario s (#3 ) an d the cos t estimat e fo r i t ($55,637 ) i s a plausibl e estimat e o f the direc t remova l cost s tha t the governmen t woul d incur . An assumptio n i s mad e tha t the governmen t woul d ge t involve d i n direc t remova l five percen t o f the time . Th e sensitivit yo f thi s assumptio n o n the result s i s teste d i n Chapte r 6 . Thi s analysi s assume s tha t an ycost s associate d wit hoff-scen e monitoring , on-scen e monitoring , an d direc t remova l b

ystat e an

d loca l emergenc yrespons e commission s ar e include d i n the estimate s above an d tha t action s b

ythes e official s d o no t increas e the cos t estimates .

3-1 4P.5 9

CHAPTE R4 ESTIMATE

DANNUA L COS T O

F R Q ADJUSTMENT S
Thi s chapte r estimate s the tota l cost s o f the fina l R Q adjustments , including the increase d economi c burde n fo r facilit yowners/operator s an d the governmen t tha t mayresul t fro m lowering the RQ s fo r 73 0 radionuclides , an d the potentia l cos t saving s tha t mayresul t fro mraising the RQ s fo r 2 7 radionuclides . Th e analysi s i n thi s chapte r combine s the informatio n presente d i n Chapter s 2 an d 3 an d compute s the incrementa l annua l cos t attributabl e t o the fina l regulation . Th e cos t an

d cos t saving s associate d wit hthe R Q adjustment s ar e a resul t o f the chang e i n the numbe r o f release s reportabl e t o th e Nationa l Respons e Cente r an

d t o stat e an

d loca l emergencyrespons e commissions . Reporting a releas e cause s the facilit yowners/operator s t o incur cost s fo r notification , recordkeeping , an

d respons e activities , and cause s the governmen t t o incur cost s fo r notificatio n processing , off-scen e an d on-scen e monitoring , an d direc t removals . Sectio n 4. 1 o f thi s chapte r estimate s the numbe r o f incrementa l reportabl e episodi c release s tha t occur du e t o th e fina l regulation ; Sectio n 4. 2 estimate s the incrementa l cost s o f the regulatio n associate d wit hthes e episodi c releases ; Sectio n 4. 3 describe s the numbe r o f release s tha t coul d occur fro mothe r facilitie s an d the estimate d cos t o f reporting thos e releases ; an d Sectio n 4. 4 discusse s potentia l firm-leve l economi c effect s o f the incrementa l cost s du e t o the fina l regulation . 4. 1 ESTIMATE

DNUMBE RO F INCREMENTA

L REPORTABLE EPISODI C RELEASE S Th e estimate d chang e i n the numbe r o f reportabl e episodi c release s i s equa l t o the differenc e betwee n the numbe r o f baselin e reportabl e episodi c release s an

d the numbe r o f episodi c release s tha t ar e reportabl e unde r the fina l regulation . I n the baseline , a radionuclid e releas e i s reportabl e t o the Nationa l Respons e Cente r an d t o stat e an

d loca l emergenc yrespons e commission s i f i t equal s o r exceed s the statutoryR Q o f 1 pound. 1 Chapte r 2 o f thi s repor t estimate d tha t ther e ar e 1 9 baselin e reportabl e radionuclid e release s annually . A s i n the baseline , thi s analysi s mus t accoun t fo r the amoun t o f a releas e tha t i s federall ypermitte d i n calculating the numbe r o f episodi c release s tha t ar e reportabl e afte r the R Q adjustments . Mos t federall y permitte d release s ar e controlle d throughthe Nuclea r RegulatoryCommissio n o r Agreemen t States ; 1 0 CFR Par t 2 0 establishe s a whol e bod ydose-equivalen t exposur e limi t t o the genera l publi c o f 50 0 millirem , the same exposur e leve l tha t EP Ause d t o deriv e the RQs . Fo r purpose s o f thi s analysis , therefore , federall ypermitte d releas e level s ar e assume d t o equa l th e RQs . Thus , a reportabl e radionuclid e releas e unde r the fina l regulatio n froma facilit y

1 Reportabl e radionuclid e release s fromfacilitie s tha t ar e license d b y the Nuclea r RegulatoryCommission , a n Agreemen t State , o r DOE , o r tha t ar e controlle d b

ypermit s o r limitation s issue d pursuan t t o th e provision s liste d i n sectio n 101(10 ) o f CERCLA , ar e on e pound o r mor e abov e the federall y permitte d levels .P.6 0

holdin g a federa l permi t o r licens e i s assume d i n thi s analysi s t o b e an y releas e tha t equal s o r exceed s twic e the fina l RQ . Becaus e the fina l RQ s ar e use d a s proxie s fo r the federall ypermitte d releas e levels , al l release s fro m facilitie s tha t ar e federall ypermitte d tha t equa l o r excee d twic e the fina l R Q mus t b e reporte d t o the Nationa l Respons e Cente r an d stat e an

d loca l emergenc yrespons e commissions. 2 Th e methodolog

ypresente d i n Chapte r 2 o f thi s repor t i s use d t o estimat e the numbe r o f reportabl e episodi c release s unde r the fina l regulation . I n particular , the tota l numbe r o f episodi c radionuclid e release s tha t occu r annuall y(250 ) i s multiplie d b ythe probabilit ytha t a particula r radionuclid e wil l b e release d a t level s tha t equa l o r excee d the R Q (or twic e the R Q fo r facilitie s tha t generall yar e i n complianc e wit hfedera l permits) . Th e EI Adat a bas e i s use d t o estimat e the frequencywit hwhic ha particula r radionuclid e ha s bee n release d i n the past , an d the siz e distributio n o f thos e releases . Exhibi t 4- 1 present s the detail s o f thi s analysis , depicting the calculation s performe d fo r eac hradionuclid e i n the EI Adat a base . A s show n i n the exhibit , ther e ar e a n estimate d 7 8 radionuclid e release s tha t woul d b e reportabl e t o the Nationa l Respons e Cente r an d t o stat e and loca l emergencyrespons e commission s give n th e fina l R Q adjustments . Maintaining the estimat e o f 1 9 reportabl e release s i n the baseline , an

d 7 8 reportabl e release s using the fina l adjuste d RQs , yield s a n estimat e o f 5 9 additiona l report s o f eposodi c release s unde r the radionuclid e R Q fina l regulation . 4 . 2 ESTIMATE

DCOS T O

F FINA L R Q ADJUSTMENT S Th e tota l cos t t o regulate d partie s i s the su mo f notification , recordkeeping , an

d respons e costs . Th e unit s cost s fo r eac ho f thes e action s ar e show

n i n Exhibi t 3-1 , an d hav e bee n reprinte d i n Exhibi t 4-2 . Th e tota l cos t calculation s ar e presente d i n Exhibi t 4-3 . Th e cost s o f the fina l regulatio n ar e calculate d i n the following manner :

A . Notification . Ther e ar e 5 9 incrementa l reportabl e radionuclid e releases . Reporting a n episodi c radionuclid e releas e t o the Nationa l Respons e Cente r i s estimate d t o cos t $197 , yielding a tota l annua l cos t o f approximatel y$11,623 . Th e tota l cos t o f

2 Thi s assumptio n i s a simplificatio n becaus e federall ypermitte d releas e amount s mayvaryfro mfacilit yt o facility . Th e Nuclea r RegulatoryCommissio n base s it s 1 0 CFR Par t 2 0 intak e limitation s o n a dos e o f 5 remfo r nuclea r facilit yworker s and 50 0 milliremfo r the genera l public . EPAbase d it s fina l RQ s o n a dose-equivalen t o f 50 0 milliremfo r a n individua l standing 3 0 meter s fro mthe releas e poin t fo r 2 4 hours . Thes e conservativ e assumption s wer e the n use d t o calculat e th e releas e level s fo r the fina l adjuste d RQs . Chapte r 5 test s the sensitivit yo f the result s t o th e numbe r o f reportabl e release s t o accoun t fo r thi s assumption . i 4- 2NNNMHOJUINUJCOC O i—^ - IDOOU>(O^U)U1 M n o o »-

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MrvNr\)NNNNNrONNMMr\)NNNNfS)NIN)roNNNNIN)NNNl\)NMI\)NNNNNNI\) N OOOOOOOOOO O OOOOOOOOOO O r n m r n r n m m r n m m m m r n m n n r n r n m m m m m n r n m m r n + 1 l + + + + + + + + + + + 1 1 1 + + + + + + + + + + OOOOOOOOOOOOOOOOOOOOOOOOOO O ^r\)MNMrN)NMNwwNMNNUivi-*OiroHi\>(->roo>Mh - 000 0 ooooo o ooo o r n m m m r n r n m m m m r n m m m + + + + + t + + + + + + 1 1 OOOOOOOOOOOOO O WO)HHNNHOHHHI-.N N

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T JP.6 2



### EXHIBI T 4- 1 (continued ) REPORTABL E RADIONUCLID E RELEASE S UNDERFINA L ADJUSTE DRQ s ESTIMATE DFRO M EI A DATA BAS E

RADIONUCLID E

PM-14 7 PO-21 0 PU-23 8 PU-23 9 RA-22 6 RB-8 8 RU-10 6 S-3 5 SB-12 5 SR-9 0 TA-18 2 TC-9 9 TH-23 2 TH-23 4 TL-20 1 TL-20 4 U-23 5 U-23 8 XE-13 3 ZN-6 5 R

Q (CURIES )

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

, 0.00 1 10 0 100 0 1 0 0. 1 0. 1 10 0 1 0 REPORTABL E RELEASE S FRO M FACILITIE S WIT HFEDERA

L PERMIT S (2*RQ )

2.00E+0 1 2.00E-0 2 2.00E-0 2 2.00E-0 2 2.00E-0 1 2.00E+0 3 2.00E+0 0 2.00E+0 0 2.00E+0 1 2.00E-0 1 2.00E+0 1 2.00E+0 1 2.00E-0 3 2.00E+0 2 2.00E+0 3 2.00E+0 1 2.00E-0 1 2.00E-0 1 2.00E+0 2 2.00E+0 1 FREQUENC YOF

RADIONUCLID E RELEAS E (FACTO RB )

0.012 5 0.015 2 0.002 7 0.008 1 0.003 6 0.000 9 0.001 8 0.003 6 0.000 9 0.015 2 0.001 8 0.033 2 0.010 8 0.000 9 0.001 8 0.003 6 0.016 1 0.115 6 0.013 4 0.002 7 FREQUENC YO F

RELEASE S ABOVE REPORTABL E LEVE L (FACTO RC )

0.093 6 0.578 9 0.578 9 0.578 9 0.459 1 0.010 2 0.330 4 0.330 4 0.093 6 0.459 1 0.093 6 0.093 6 0.735 4 0.019 0 0.010 2 0.093 6 0.459 1 0.459 1 0.019 0 0.093 6 TOTAL NUMBER

O F RADIONUCLID E RELEASE S (FACTO RA )

25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 25 0 NUMBEROF

REPORTABL E RELEASE S (A*B*C )

0.2 9 2.2 0 0.3 9 1.1 7 0.4 1 0.0 0 0.1 5 0.3 0 0.0 2 1.7 5 0.0 4 0.7 8 1.9 8 0.0 0 0.0 0 0.0 8 1.8 5 13.2 7 0.0 6 0.0 6

TOTAL REPORTABL E RELEASE S 7 8

SOURCE : ICF ANALYSI S

Number s ma y

no t adddu e t o roundin g

4- 4P.6 3

EXHIBI T 4- 2 UNI T NOTIFICATIO

N COST S T

O FACILIT

YOWNERS/OPERATOR S O F A REPORTABLE EPISODI C RELEAS E

Actio n Telephon e Respons e Nationa l

Cente r

Preparatio n t o ' Stat e an d Respons e Telephon e Respons e Telephon e Loca l relephon e

Emergenc y Commission s Loca l Commi s Stat e Emergenc y s io n Emergenc y Labo r

Categor y
Manage r Technica l

Manage r Technica l
Manage r
Manage r Hour s
3 2

0
0 0 8 0 8
5
5 Hourl y

Wag e $4 5 $3 1

$4 5 $3 1 $4 5 $4 5 0 0 0 0

0 0 0 0
0 0
0 0 Cost

$19 7

$ 6 $ 2 2 $ 3 1 1 0
5 0
3 7 Respons e Commissio n

- Cos t o f half-hou r tol l cal l $8.8 7

Tota l cos t o f notifying Stat e an d Loca l Emergenc yRespons e Commission s $ 59.9 7

Prepar e Follow-u

p Repor t $117.3 0

Source : IC F analysis .



### 4- 5P.6 4

EXHIBI T 4- 3 CALCULATIO

N O F TOTA L ANNUA L COST S T

O FACILIT

YOWNERS/OPERATOR S

A . Cost s o f Notification : $22.08 2 1 . Nationa l Respons e Cente r (5 9 incrementa l reports ) * $19 7 $11,62 3 2 . Stat e an

d Loca l Respons e Commission s
a . Cost s o f Immediat e Notification s (5 9 incrementa l reports ) * $59.9 7 $ 3,53 8 b . Cost s o f follow-u p reporting (5 9 incrementa l reports ) * $117.3 0 $ 6,92 1 B . Cos t o f Recordkeeping $ 1,09 2

(5 9 incrementa l reports ) * $18.5 0 C . Cos t o f Respons e $16,54 4

(5 9 incrementa l reports ) * .0 5 * $5,60 8 TOTAL COS T TO FACILITY OWNERS/OPERATOR S $39,71 8

Source : IC F analysis .

4- 6P.6 5

reporting a releas e t o stat e an d loca l official s i s estimate d t o b e $177.2 7 ($59.9 7 fo r the initia l call s an d $117.3 0 fo r the follow-u p report) , yielding a tota l annua l cos t o f reporting 5 9 additiona l episodi c release s o f $10,459 . Th e tota l cost s o f notificatio n ar e the su

mo f the cost s t o repor t t o the Nationa l Respons e Cente r an

d t o repor t t o stat e an d loca l officials , o r approximatel y$22,100 . B . Recordkeeping . Multiplying 5 9 incrementa l reportabl e release s b

y$18.50 , the cos t o f recordkeeping pe r release , yield s a tota l annua l recordkeeping cos t o f $1,092 . C . Response . Thi s analysis 3 assume s tha t the probabilit yo f a respons e t o a give n releas e i s 9 0 percen t i f the releas e i s belo wthe R Q an d 9 5 percen t i f the releas e i s above the RQ . Therefore , five percen t o f the incrementa l reportabl e release s wil l experienc e respons e action s a s a resul t o f the lowe r RQs . Multiplying the numbe r o f incrementa l reportabl e releas e (59 ) b ythe incrementa l probabilit yo f respons e (0.05 ) an d b ythe weighte d averag e cos t pe r respons e ($5,608 ) yield s a n estimate d annua l respons e cos t o f $16,544 . Th e tota l cos t o f the fina l regulatio n t o facilit yowners/operator s responsibl e fo r reportabl e episodi c release s o f radionuclide s i s the su mo f the cost s i n eac ho f the thre e areas . Thi s i s estimate d t o b e abou t $39,700 . Th e tota l cos t t o the governmen t o f R Q adjustment s i s the su mo f notificatio n processing fo r federa l officials , notificatio n processing fo r stat e an

d loca l officials , off-scen e monitoring , on-scen e monitoring , an d direc t remova l costs . Thes e cost s ar e show n i n Exhibi t 4- 4 an d the calculation s ar e summarize d below: *

A . Notificatio n Processing fo r Federa l Officials . A tota l annua l notificatio n processing cos t o f $3,39 3 i s calculate d b

ymultiplying 5 9 incrementa l reportabl e release s b y$57.5 0 (th

e estimate d cos t o f processing on e notificatio n a t the Nationa l Respons e Center) .

3 Th e sensitivit yanalysi s i n Chapte r 5 test s the resul t o f assuming differen t probabilitie s o f respons e t o release s abov e an d belo wa n RQ . Derivatio n o f th e averag e cos t o f respons e i s show n i n Exhibi t 3-2 . 4 Exhibi t 3- 3 presente d the uni t cost s fo r governmen t actions . 4- 7P.6 6

EXHIBI T 4- 4 CALCULATIO

N O F TOTA L ANNUA L COST S T

O GOVERNMEN

T

A . Cos t o f Notificatio n Processing t o Federa l Official s $ 3.39 3 1 . Report s t o Nationa l Respons e Cente r (5 9 incrementa l reports ) * $57.5 0 B . Cos t o f Notificatio n Processing t o Stat e an d Loca l Official s S 8.14 2 1 . Report s t o Stat e an d Loca l Commission s (5 9 incrementa l reports ) * $115.0 0 $6,78 5 2 . Follow-u

p Report s

• (5 9 incrementa l reports ) * $23.0 0 $1,35 7 C . Cos t o f Off-Scen e Monitoring $ 9.04 5

(5 9 incrementa l reports ) * .7 0 * $21 9 D . Cos t o f On-Scen e Monitoring $ 31.97 8

(5 9 incrementa l reports ) * .2 0 * $2,71 0 E . Cos t o f Direc t Remova l $164.12 9

(5 9 incrementa l reports ) * .0 5 * $55,63 7 TOTAL COS T T O GOVERNMEN T $216,68 7

Source : IC F analysis .

4- 8P.6 7

B . Notificatio n Processing fo r Stat e an d Loca l Officials . Atota l annua l notificatio n processing cos t o f $8,14 2 i s calculate d b ymultiplying the numbe r o f incrementa l release s (59 ) b ythe uni t cost s o f processing call s ($115) , an d the same numbe r o f incrementa l report s b yth e cos t t o proces s tw o follow-u

p report s (on

e t o the stat e an

d on e t o the loca l committee ) a t $11.5 0 pe r report , an d adding the two result s together . C . Off-scen e monitoring . Multiplying 5 9 incrementa l reportabl e release s b ythe probabilit ytha t off-scen e monitoring i s required 5 (.70) , an d b ythe cos t o f off-scen e monitoring pe r releas e ($219) , yield s a tota l annua l off-scen e monitoring cos t o f $9,045 . D . On-scen e monitoring . Multiplying 5 9 incrementa l reportabl e release s b ythe probabilit ytha t on-scen e monitoring i s required 6 (.20) , an d thi s produc t b

y the cos t o f on-scen e monitoring pe r releas e ($2,710 ) yield s a tota l annua l on-scen e monitoring cos t o f $31,978 .

• E . • Direc t Removal . Multiplying 5 9 incrementa l reportabl e release s b ythe probabilit yo f a direc t remova l b

ythe governmen t (.05 ) an d b ythe estimate d cos t o f a direc t remova l ($55,637 ) yield s a tota l annua l cos t fo r direc t remova l o f $164,129 . Th e tota l cos t t o the governmen t i s the su mo f notificatio n processing costs , off-scen e monitoring costs , on-scen e monitoring costs , an d direc t remova l costs . Thi s su mi s approximatel y$216,687 . Th e su mo f the tota l cost s t o facilit yowners/operator s an d t o the governmen t fo r reporting an d responding t o report s o f 5 9 additiona l reportabl e episodi c radionuclid e releases , therefore , i s estimate d t o b e approximatel y $256,400 . 4. 3 ESTIMATE O

F NUMBE RO F OTHE RINCREMENTA

L REPORTABLE RELEASE S Unti l thi s poin t i n the analysis , onl ythe numbe r o f incrementa l release s fro mcertai n type s o f facilitie s hav e bee n estimated . Thes e facilitie s ar e generall ythos e tha t ar e license d b ythe Nuclea r RegulatoryCommissio n an d Agreemen t States , an d thos e controlle d b yDOE . Th e analysi s ha s estimate d tha t ther e wil l b e 5 9 incrementa l reportabl e episodi c release s annuall ya s a

5 Th e sensitivit yanalysi s i n Chapte r 5 test s the result s o f assuming differen t probabilitie s fo r off-scen e monitoring .

6 Th e sensitivit yo f thi s assumptio n i s teste d i n Chapte r 5 . 4- 9P.6 8

resul t o f the fina l radionuclid e R Q adjustments , an d tha t the resulting cos t du e t o the action s take n t o notif ythe Nationa l Respons e Cente r an d t o notif y SERC s an

d LEPC s i s approximatel y$256,400 . Ther e ar e a certai n numbe r o f radionuclid e release s tha t occu r fro mothe r type s o f facilitie s tha t als o coul d b e affecte d b ythe fina l R Q adjustments . Thes e othe r release s ar e no t federally-permitte d an d includ e release s fro m coal-fire d utilit yan d industria l boile r sites , unlicense d laboratories , low

energ ylinea r accelerators , energ yextractio n an

d processing facilities , and certai n mining an

d ore-processing operations . Som e o f thes e facilitie s may releas e radionuclide s a t o r above a n RQ and , therefore , hav e t o repor t unde r CERCL Asectio n 103 . Release s o f radionuclide s fro mhigh-energ

yaccelerator s ar e regulate d b y DO E throughNESHAP . Radionuclid e release s fro mlow-energ

yaccelerator s ar e no t regulate d throughNESHAP , bu t ar e permitte d b ystates . Becaus e these " release s ar e no t federall ypermitte d an d ar e no t release s o f source , specia l nuclear , o r by-produc t materials , theyar e no t covere d b yCERCL Asection s 101(10)(H ) o r (K) , and , therefore , ar e subjec t t o the reporting requirement s unde r CERCI Asectio n 103 . License d laboratorie s ar e permitte d b yAgreemen t States ; unlicense d laboratorie s ar e no t becaus e theystor e an d us e radionuclide s i n quantitie s an d concentration s belo wthe licensing thresholds . Unlicense d laboratorie s ten d t o b e specialized , smal l facilitie s using a limite d numbe r o f radionuclide s i n smal l quantities . Becaus e unlicense d laboratorie s an

d linea r accelerator s maintai n suc hsmal l inventorie s o f radionuclides , theyar e unlikel yt o releas e a n R Q o r mor e o f radionuclide s unde r les s tha n exceptiona l circumstances . Th e othe r facilitie s tha t coul d hav e radionuclid e release s tha t ar e no t federall ypermitte d move , process , o r consume larg e quantitie s o f lowactivit y material s during norma l operating processes . Th e proces s o f radioactiv e decay tha t govern s thes e release s i s predictable , continuous , an d verystabl e i n quantit yan

d rate ; a s such , thes e release s ar e generall yexpecte d t o b e continuou s an

d stabl e i n quantit yan d rat e a s define d unde r the regulation s implementing CERCL

Asectio n 103(f)(2) . Unde r the reduce d reporting requirement s o f sectio n 103(f)(2) , suc hrelease s mus t b e reporte d initially , annually , an

d wheneve r a statisticall ysignifican t increas e (SSI ) occurs . I n addition , unde r sectio n 30 4 o f the SAR A(Titl e III) , thes e release s mus t b e reporte d t o the appropriat e SERC an d LEPC . Radionuclide s mayb e release d fro mthes e facilitie s b ya numbe r o f releas e pathway s bu t thre e pathway s predominate : (1 ) the dumping o f a n intermediat e produc t o r wast e outsid e a facilit y(sucha s the stockpiling o f coal , coa l ash , o r or e tailings) ; (2 ) emission s o f rado n an d othe r radionuclide s fro

mstockpile s o r work-in-proces s inventorie s (e.g. , natura l ga s a t a processing plant) ; an d (3 ) smokestac k emissions . Wit hthe exceptio n o f release s fro mcoal-fire d boilers , EPAdoe s no t hav e muc hinformatio n abou t the quantit yo f radionuclide s release d fro mthes e facilities . I n particular , informatio n abou t releas e pathway s othe r tha n smokestac k emissions , especiall ywit hrespec t t o the frequencyan d amoun t o f stockpiling tha t occur s a t facilities , i s spars e an d incomplete . I n addition , 4-1 0P.6J L

EP Alack s detaile d informatio n abou t the characteristic s o f facilitie s withi n thes e industries , man yo f whic hshowconsiderabl e diversit yi n siz e an d operation . I t i s difficult , therefore , t o estimat e wit hprecisio n the numbe r o f facilitie s likel yt o releas e a n R Q o r mor e o f an yradionuclid e o n a regula r basis . Base d o n the informatio n available , EPAha s estimate d tha t 2,71 0 facilitie s coul d b e releasing radionuclide s i n a continuou s manne r abov e th e RQ . Th e 2,71 0 facilitie s ar e liste d b yindustr

ycategoryi n Exhibi t 4-5 . Facilitie s wit hcoal-fire d boiler s compris e nearl ytwo-third s o f thes e facilities . Th e basi s o f thi s estimat e i s provide d i n detai l i n Appendi xA . Action s an

d Valu e o f Action s Take n b vIndustr

yfo r Reporting unde r CERCL A Sectio n 103(f)(2 ) I f the owne r o r operato r report s continuou s release s unde r the authorit y o f CERCL

Asectio n 103(f)(2) , the owne r mus t mee t the following reporting requirements : Initia l Notification : Facilitie s mus t notif ythe Nationa l Respons e Cente r (NRC) , SERC , an d LEP C b

ytelephon e tha t release s fro mtha t facilit yar e continuou s an

d wil l b e reporte d unde r sectio n 103(f)(2) . Th e informatio n require d i n the initia l telephon e cal l is : (1 ) the name an

d locatio n o f the facilit yo r vessel ; (2 ) the name an

d identit yo f the hazardou s substance , the Chemica l Abstract s Servic e RegistryNumbe r (CASRN ) fo r the substance , an d the medi a affected ; (3 ) identificatio n o f the releas e a s continuous ; an d (4 ) the uppe r bound o f the norma l rang e o f the releas e unde r norma l operating conditions . I t i s estimate d tha t initia l notificatio n t o the NR C require s on e hou r o f manageria l time an

d on e hou r o f technica l time 7 a t a hourl ywag e rat e o f $45.0 0 an

d $31.0 0 respectively . I n addition , eac htelephon e cal l t o the SERC an d LEP C i s expecte d t o requir e 0.2 5 hour s o f manageria l time . Th e cos t o f a n intrastat e tol l cal l t o the SERC i s estimate d a t $8.87 . Consequently , the tota l cos t o f providing initia l notificatio n t o al l governmen t bodie s i s estimate d a s $107.4 0 ($4 5 + $3 1 + (2)(0.2 5 x$45 ) + $8.87) . Initia l Writte n Report : Facilitie s als o mus t submi t a follow-u p writte n initia l repor t t o the On-Scen e Coordinato r (OSC) , SERCs , an d LEPC s withi n 3 0 day s o f the initia l telephon e call . I n the follow-u p report , facilitie s mus t projec t estimate s o f the tota l annua l amoun t release d an d the uppe r bound o f

7 IC F Incorporated , RegulatoryImpac t Analysi s o f Reportabl e Quantit y Adjustment s Unde r Section s 10 2 an d 10 3 o f the Comprehensiv e Environmenta l Response . Compensation , and Liabilit yAct . Volum e I , Marc h1985 , p.3-11 . Base d o n estimate d notificatio n cost s fo r release s o f les s tha n 5 5 gallons . 4-1 1P.7 0

EXHIBI T 4- 5 ESTIMATE

DNUMBE RO F REPORTIN

GFACILITIE S UNDE RCERCL A SECTIO N 103(f)(2 )

Facilit yTyp e Numbe r
Coa l Mine s 36 3 Uraniu mmine s 18 1 Bauxit e mine s & aluminu msmelter s 4 4 Coppe r mine s & smelter s 7 6 Zin c mine s & smelter s 4 1 Lea d smelters/refinerie s 5 Elementa l phosphoru s plant s 6 Phosphat e roc k plant s 3 5 We t proces s fertilize r plant s 3 5 Iro n mine s & smelter s 6 8 Geotherma l energ

yplant s 2 0 Gas-fire d boiler s 11 2 SUBTOTAL : 98 6 Coal-fire d industria l boiler s 1,21 0 Coal-fire d utilit yboiler s 51 4 TOTAL : 2,71 0

Source : Appendi xAan d B

4-1 2P.7 1

the norma l rang e tha t describe s the patter n o f release s fro mthe facility . Thes e estimate s shoul d b e base d o n the operating historyo f the plan t an d professiona l judgment . Th e informatio n require d i n the initia l writte n repor t includes : (1 ) name an

d locatio n o f the facilit yo r vessel , an d name an

d telephon e numbe r o f the perso n i n charge ; (2 ) name/identit yo f the hazardou s substance , Chemica l Abstract s Servic e RegistryNumbe r (CASRN ) numbe r fo r the substance , an d medi a affected ; (3 ) a brie f descriptio n o f the patter n o r profil e o f the releas e during an

y24-hou r perio d unde r norma l operating conditions , including a descriptio n o f the source(s ) o f the releas e an d the basi s fo r asserting continuit yan d stabilit yi n quantit yan d rate , an d a descriptio n o f the natur e o f the predictabilit yo f the releas e cycle ; (4 ) the frequencyo f the releas e (i.e. , the numbe r o f time s the releas e i s expecte d t o occu r during the year) ; (5 ) ' the uppe r bound o f the norma l rang e o f the releas e during an y24

- hou r perio d unde r norma l operating condition s (i n pound s o r kilograms) ; (6 ) a n estimat e o f th e tota l annua l amoun t tha t i s expecte d t o b e release d (i n pound s o r kilograms) ; (7 ) the metho d tha t wil l b e use d t o identif ySSIs , (includin g the sensitivit yo f the statistica l test , i f used) ; (8 ) the populatio n densit ywithi n a on e mil e radiu s o f the facilit y describe d i n term s o f the following ranges : 0-1 0 persons , 11-5 0 persons , 51-10 0 persons , o r 10 0 person s o r more ; (9 ) the identit yo f an ysensitiv e population s o r ecosystem s withi n a on e mil e radiu s o f the facilit y(e.g. , elementar yschools , hospitals , retiremen t communities , o r aquifers) ; an d (10 ) the dat e electe d fo r submitta l o f subsequen t annua l reports . Al l o f the require d informatio n i s assume d t o b e readil yavailabl e t o the facility . Cost s wil l b e incurre d fo r the compilatio n an d formatting o f the informatio n int o a repor t suitabl e fo r submissio n t o the government . Th e amoun t o f time require d t o prepar e a n initia l repor t i s estimate d t o b e 3 hour s o f manageria l time , 1 hou r o f technica l time , an d 1 hou r o f clerica l

4-1 3P.7 2

time. 8 Th e hourl ycos t estimate s ar e $4 5 fo r manageria l time , $3 1 fo r technica l time , an

d $1 4 fo r clerica l time , resulting i n a fina l annua l repor t cos t o f $180.00 . Th e cost s o f photocopying an d mailing the repor t t o additiona l governmen t bodie s i s assume d t o b e negligible . Annua l Report : A n annua l writte n repor t mus t b e submitte d t o th e EP A designate d OS C an

d mus t includ e certai n specifie d summar yinformatio n abou t the substance s release d during the preceding year . Thi s repor t i s retrospectiv e an

d mus t contai n actua l releas e informatio n fo r the preceding year . Facilitie s do no t nee d t o provid e annua l report s t o SERC s an d LEPCs . Th e informatio n require d i n thi s repor t includes : (1 ) name an

d locatio n o f the facilit yo r vessel , an d name an

d telephon e numbe r o f the perso n i n charge ; (2 ) name/identit yo f the hazardou s substance , CASR Nnumbe r fo r the substance , an

d medi a affected ; (3 ) a brie f descriptio n o f the patter n o r profil e o f the releas e during an

y24-hou r perio d unde r norma l operating conditions , including a descriptio n o f the source(s ) o f the releas e an d the basi s fo r asserting continuit yan d stabilit yi n quantit yan d rate , an d a descriptio n o f the natur e o f the predictabilit yo f the releas e
• cycle ; (4 ) the frequencyo f the releas e (i.e. , th e numbe r o f time s the releas e occurre d during the year) ; (5 ) the uppe r bound o f the norma l rang e o f the releas e during an y24

- hou r perio d unde r norma l operating condition s (i n pound s o r kilograms) ; (6 ) a n estimat e o f the tota l annua l amoun t release d (i n pound s o r kilograms) ; (7 ) the numbe r o f time s during the preceding yea r tha t SSI s occurre d an d wer e reporte d t o the NRC ; (8 ) the metho d use d t o identif ySSIs , (i f a statistica l tes t i s used , the sensitivit yo f tha t tes t mus t b e included) ; (9 ) the populatio n densit ywithi n a on e mil e radiu s o f the facilit y describe d i n term s o f the following ranges : 0-1 0 persons , 11-5 0 persons , 51-10 0 persons , o r 10 0 person s o r more ; an d

8 U.S . Environmenta l Protectio n Agency , Background Documen t i n Suppor t o f th e Propose d Continuou s Releas e Reporting Regulatio n unde r Sectio n 103(f)(2 ) o f the Comprehensiv e Environmenta l Response . Compensation , an d Liabilit yAct . Emergenc yRespons e Division , EPA , September 1987 . p.5-4 . 4-1 4P.7 3



# 1 I I 

# I I I I I I I I (10 ) the identit yo f an ysensitive population s o r ecosystem s withi n a on e mil e radiu s o f the facilit y(e.g. , elementaryschools , hospitals , retiremen t communities , o r aquifers) . Becaus e the informatio n require d i n the annua l repor t i s simila r t o tha t require d i n the writte n initia l notification , i t i s assume d tha t annua l report s requir e the same amoun t an d leve l o f effor t a s the initia l report , resulting i n a pe r repor t cos t o f $180.00 . Thi s analysi s assume s tha t annua l report s wil l b e submitte d on e yea r afte r the initia l notificatio n i s provided , suc htha t the cost s o f initia l notificatio n ar e incurre d i n yea r on e an d th e cost s o f the annua l repor t ar e incurre d i n yea r tw o an d i n subsequen t years . Revisiting Initia l an d Annua l Reports : Fo r som e percentag e o f facilitie s reporting unde r sectio n 103(f)(2) , the informatio n provide d i n the initia l and/o r annua l report s wil l promp t request s fo r additiona l informatio n an d communicatio n abou t the natur e an d exten t o f the release . Fo r instance , a n OS C ma ysee k clarificatio n o r verificatio n o f informatio n concerning releas e activit yi n orde r t o asses s the degre e o f threa t the releas e pose s t o huma n health , welfare , an d the environment . I t i s estimate d tha t approximatel y5 percen t o f the initia l an d annua l report s wil l b e revisite d eac hyea r an d tha t thi s proces s wil l requir e tw o hour s o f managemen t time pe r report . Th e resulting uni t cos t i s $9 0 (2. 0 x$45) . Statisticall ySignifican t Increases : Sectio n 103(f)(2 ) als o require s tha t "statisticall ysignifican t increases" . (SSIs ) i n the continuou s release s b e reporte d t o the Nationa l Respons e Center. 9 Becaus e continuou s radionuclid e release s ar e assume d t o b e the resul t o f radioactive deca ytha t occur s a t a predetermine d an

d fixe d rate , i t i s unlikel ytha t ther e wil l b e an y statisticall ysignifican t increase s i n the release . Nevertheless , thi s analysi s conservativel yassume s tha t statisticall ysignifican t increase s i n thes e release s wil l occu r an d wil l b e reporte d t o the Nationa l Respons e Center , SERC , an

d LEPC . I t i s assume d tha t reporting o f a n SS I wil l involve les s time tha n fo r a n episodi c releas e becaus e informatio n abou t the releas e i s alread yknown and availabl e fro

mpreviou s initia l an d annua l reports . Consequently , onl yon e hou r o f manageria l time and on e hou r o f technica l time ar e estimate d t o b e require d t o repor t the releas e t o the Nationa l Respons e Center . Th e technica l time consist s o f determining i f the releas e i s reportable , briefing managemen t o f the situation , an d collecting the informatio n require d b ythe Nationa l Respons e Center . Th e manageria l tim e include s being informe d o f the situation , alerting the appropriat e personnel , an d making on e notificatio n telephon e call . Reporting o f SSI s t o othe r appropriat e governmen t bodie s i s estimate d t o requir e 0. 5 hour s o f managemen t tim e pe r phon e call , resulting i n a tota l cost s o f reporting o f $129.9 0 ($4 5 + $3 1 + (2)(0. 5 x$45 ) + $8.87) .

9 EPAcurrentl yi s evaluating five percen t an d on e percen t a s the appropriat e leve l o f significance . Thi s analysi s onl ypresent s cost s fo r the on e percen t definition . 4-1 5

# B 0 1 1 I 1 I Follow-u p Writte n Repor t o f a Release : Following a releas e requiring notificatio n unde r sectio n 304 , the facilit yowner/operato r i s require d t o provid e a follow-u

p writte n repor t t o the appropriat e SERC an d LEP C updating the informatio n give n i n the phon e cal l an d providing additiona l information . Th e estimate d cos t o f thi s activit yincrease s wit hthe siz e o f the release . Base d o n estimate s derive d fo r reporting episodi c releases , thi s activit yi s assume d t o cos t $117.30. 1 0 Recordkeeping : Althoughneithe r CERCL Ano r SAR

Arequire s tha t record s o f release s b e kept , i t i s likel ytha t a facilit ywil l maintai n a lo g o r som e othe r recor d o f reporte d releases . Suc ha lo g woul d b e usefu l fo r manager s i n establishing tha t the facilit yi s i n complianc e wit hthe provision s o f sectio n 103(f)(2) , and woul d serve a s a depositoryfo r informatio n relevan t t o preparing a follow-u p writte n repor t o r annua l report . Fo r example , informatio n recorde d i n the lo g mayb e use d t o demonstrat e the continuit yan d stabilit yo f th e release . Recordkeeping i s estimate d t o requir e on e hou r o f clerica l time pe r reporte d releas e and one-tent ho f a n hou r o f manageria l supervisio n pe r reporte d releas e fo r a cos t o f $18.5 0 ($1 4 + 0.1 0 x$45) . Althoughthe notificatio n requirement s o f CERCL Asectio n 10 3 d o no t requir e respons e action , i t wa s argue d earlie r tha t cleanu p respons e i s mor e likel yt o occu r whe n notificatio n i s required . Becaus e continuou s release s represen t regula r occurrence s fro mlarg e quantitie s o f material s incidenta l t o norma l operations , theyar e unlikel yt o provok e o r requir e a n immediat e respons e action . Mor e likely , the reporting requirement s o f sectio n 103(f)(2 ) maylead t o actio n ove r the long ter mt o mitigat e o r reduc e thes e release s throughne woperating procedures , bette r containmen t systems , o r smalle r piles . Thi s analysi s assumes , therefore , tha t facilitie s tha t releas e radionuclide s continuousl ywil l no t respon d t o o r cleanu

p thes e releases . Action s and Valu e o f Action s Take n b vGovernmen t tinde

r CERCL ASectio n 103(f)(2 ) Initia l Notification : Th e cos t o f processing a n initia l notificatio n fo r governmen t official s i s assume d t o requir e 0.2 5 hour s fo r collecting an d processing th e informatio n receive d during the telephon e call . Assuming a cos t estimat e o f $18 4 pe r governmen t workday , processing a n initia l notificatio n cost s $5.7 5 (0.2 5 x$184/8) . Writte n Initia l Notificatio n an d Annua l Report : Processing a writte n initia l repor t o r a n annua l repor t b yfedera l official s i s assume d t o requir e on e hou r o f governmen t time . A t a wag e rat e o f $18 4 pe r governmen t workday , thi s cos t i s $23.0 0 ($184/8) .

1 0 U.S . Environmenta l Protectio n Agency , RegulatoryImpac t Analysi s i n Suppor t o f Rulemaking Unde r Section s 302 . 303 . an d 30 4 o f Titl e II I o f th e Superfun

d Amendment s an

d Reauthorizatio n Ac t o f 1986 . Economic s an d Technolog

y Division , Offic e o f Toxi c Substances , EPA , Apri l 10 , 1987 . p . A-9 . 4-1 6P.7 5

Revisiting Initia l and/o r Annua l Reports : Fo r some percentag e o f facilitie s reporting unde r sectio n 103(f)(2) , the informatio n provide d i n the initia l and/o r annua l report s wil l promp t request s fo r additiona l informatio n an d communicatio n abou t the natur e an d exten t o f the release . Fo r example , facilitie s locate d nea r sensitive population s an d ecosystem s mayb e aske d t o provid e additiona l informatio n i n orde r t o asses s the risk s associate d wit h the release . I t i s estimate d tha t approximatel y5 percen t o f the initia l an d annua l report s wil l b e revisite d eac hyea r an d tha t thi s proces s wil l requir e tw o hour s o f governmen t tim e pe r repor t fo r a cos t o f $46.0 0 (2. 0 x$184/8) . Statisticall ySignifican t Increase s (SSIs) : Th e cos t o f processing a n SS I include s bot ha n immediat e evaluatio n t o determin e whethe r a respons e actio n i s necessaryan d the collectio n an d storag e o f the transmitte d information . I t wa s estimate d tha t 0. 3 governmen t workday s ar e necessaryt o proces s a n episodi c releas e notification . Th e time require d t o evaluat e a n SS I i s expecte d t o b e considerabl yles s fo r two reasons : (1 ) informatio n pertaining t o the facility , the natur e o f the release , an d the populatio n an d environmen t a t ris k wil l alread yb e availabl e fro

mfile d initia l and/o r annua l reports , an

d (2 ) the SS I repor t represent s a releas e unde r norma l operating condition s and , therefore , i s unlikel yt o requir e a response . Becaus e the informatio n previousl ysubmitte d b ythe facilit yi s assume d t o b e readil y availabl e throug

hthe EmergencyRespons e Notificatio n Syste m(ERNS) , evaluatio n o f the releas e i s expecte d t o occu r simultaneousl ywit hth e telephon e repor t fro mthe facility . Consequently , processing a notificatio n o f a n SS I i s estimate d t o requir e 0. 5 hour s o f governmen t time , fo r a cos t o f $11.5 0 (0. 5 x$184/8) . I t i s assume d tha t al l governmen t bodie s requir e the same amoun t o f tim

e t o proces s an

d evaluat e a n SSI . Follow-u

p Writte n Repor t o f a Release : SERC s an d LEPC s wil l als o receiv e follow-u

p writte n report s o f SS I releases . Becaus e thes e release s ar e unlikel yt o generat e a respons e actio n an d wil l hav e bee n evaluate d alread y during the telephon e notification , littl e time i s expecte d t o b e require d t o proces s thes e report s beyond filing an d recordkeeping activities . I t i s estimate d t o requir e 0. 5 hour s o f governmen t time fo r thi s activity , a t a cos t o f $11.50 . Th e tota l estimate d annua l cost s t o bot hindustr yand governmen t ar e summarize d i n Exhibi t 4- 6 fo r facilitie s othe r tha n thos e wit hcoal-fire d boilers . Estimate d annua l cost s fo r al l facilitie s ar e presente d i n Exhibi t 4-7 . 4. 4 FIR

M LEVE L ECONOMI C EFFECT S Th e estimate d cost s o f the fina l regulatio n ar e smal l relativ e t o the sale s an

d revenue s generate d b ythe industrie s mos t likel yt o b e affecte d b y the fina l regulation . Th e averag e facilit yhandling radionuclide s i s no t expecte d t o experienc e a radionuclid e releas e abov e the fina l RQ . Th e analysi s estimate s tha t ther e wil l b e approximatel y5 9 incrementa l reportabl e release s annuall yfro mNuclea r RegulatoryCommission , Agreemen t State , an d DO E facilities , and abou t 1,00 0 facilitie s reporting release s o f radionuclide s tha t occu r i n a continuou s manner . Ther e ar e approximatel y950,00 0 facilitie s potentiall yaffecte d b ythe fina l regulation . Th e probabilit ytha t an y 4-1 7EXHIBI T 4- 6 TOTA L COST S O

F REPORTIN

GUNDE RSECTIO

N 103(f)(2 ) (EXCLUDIN

GFACILITIE S WITHCOAL-FIRE DBOILERS ) P.7 6

ACTION UNI T COS T NUMBE R O F REPORT S OR NOTIFICATION S FIRS T YEA R COST S SUBSEQUEN T YEA R COST S

INDUSTR Y Provid e Initia l Notificatio n t o NRC , SERC , LEP C Submi t Writte n Notificatio n t o OSC , SERC , LEP C Submi t Annua l $107.4 0

$180.0 0

TOTAL COSTS : ANNUALIZE D COSTS : 

### 98 6

98 6

Repor t t o OS C Revisi t Initial / Annua l Repor t Repor t a n SS I t o NRC , SERC , LEP C Follow-u

p Repor t o f a n SS I t o SERC , LEP C Recordkeeping $18 0 $ 9 0 $12 9 $11 7 $1 8 0 0
0 0
9 0
3 0

5 0 3

3
3 98 6
4 9
59 9
59 9 ,59 9 $105,89 6

$177,48 0

$4,41 0 $467,51 0 $422,16 3

S 66.58 2 $177,48 0

$4,41 0 $467,51 0 $422,16 3

S 66.58 2 $1,244,04 1 $1,138,14 4 $1,150,00 0

Cost s ar e annualize d ove r a te n yea r perio d a t a discoun t rat e o f 4 percent . Al l cost s ar e i n 198 7 dollars .

4-1 8EXHIBI T 4- 6 (continued ) TOTA L COST S O

F REPORTIN

GUNDE RSECTIO

N 103(f)(2 ) (EXCLUDIN

GFACILITIE S WITHCOAL-FIRE DBOILERS ) P.7 7

ACTION UNI T COS T NUMBE R O F REPORT S O R NOTIFICATION S FIRS T YEA R COST S SUBSEQUEN T YEA R COST S

Proces s Initia l Notificatio n Proces s Writte n Initia l Report s Proces s Annua l Report s Revisiting Initial / Annua l Report s Proces s SSI s Proces s Follow-u

p Repor t o f a n SS I $1 7 $6 9 $2 3 $4 6 $3 4 $2 3 2 5
0 0
0 0
0 0 5 0
0 0 98 6

98 6
98 6
4 9 3,59 9 3,59 9 TOTAL COSTS : ANNUALIZE D COSTS : TOTAL ANNUALIZE D COST S T O INDUSTR Y AND GOVERNMENT : $17,00 9 $68,03 4

$2,25 4 $124,16 6 $22,67 8

$2,25 4 $124,16 6 $ 82.77 7 $ 82.77 7 $294,23 9 $231,87 5 $240,00 0 $1,390,00 0

Cost s ar e annualize d ove r a te n yea r perio d a t a discoun t rat e o f 4 percent . Al l cost s ar e i n 198 7 dollars .

4-1 9EXHIBI T 4- 7 TOTA L COST S O

F REPORTIN

GUNDE RSECTIO

N 103(f)(2 ) FO RAL L FACILITIE S

ACTION UNI T COS T NUMBE R O F REPORT S OR NOTIFICATION S FIRS T YEA R COST S SUBSEQUEN T YEA R COST S

INDUSTR Y Provid e Initia l Notificatio n t o $107.4 0 NRC , SERC , LEP C Submi t Writte n Notificatio n t o $180.0 0 OSC , SERC , LEP C Submi t Annua l 2,71 0

2,71 0

Repor t t o OS C Revisi t Initial / Annua l Repor t Repor t a n SS I t o NRC , SERC , LEP C Follow-u

p Repor t o f a n SS I t o SERC , LEP C Recordkeeping TOTAL COSTS : ANNUALIZE D COSTS : $18 0 $ 9 0 $12 9 $11 7 $1 8 0 0
0 0
9 0
3 0
5 0 2

9
9
9 71 0
13 6
89 2
89 2
89 2 $291,05 4

$487,80 0

$12,24 0

$183.00 2 $487,80 0

$12,24 0 $1,284,97 1 $1,284,97 1 $1,160,33 2 $1,160,33 2

$183.00 2 $3,419,39 8 $3,128,34 4 $3,160,00 0

Cost s ar e annualize d ove r a te n yea r perio d a t a discoun t rat e o f 4 percent . Al l cost s ar e i n 198 7 dollars .

4-2 0EXHIBI T 4- 7 (continued ) TOTA L COST S O

F REPORTIN

GUNDE RSECTIO

N 103(f)(2 ) FO RAL L FACILITIE S ACTION UNI T COS T NUMBE R O F REPORT S OR NOTIFICATION S FIRS T YEA R COST S SUBSEQUEN T YEA R COST S

GOVERNMEN

T Proces s Initia l Notificatio n Proces s Writte n Initia l Report s Proces s Annua l Report s Revisiting Initial / Annua l Report s Proces s SSI s Proces s Follow-u

p Repor t o f a n SS I $1 7 $6 9 $2 3 $4 6 $3 4 $2 3 2 5
0 0
0 0
0 0 5 0
0 0 2

2
2OV
9 71 0
71 0
71 0
13 6 89 2
89 2 TOTAL COSTS : ANNUALIZE D COSTS : TOTAL ANNUALIZE D COST S T O INDUSTR Y AN D GOVERNMENT : $46,74 8 $186,99 0

$6,25 6 $341,27 4 $227.51 6 $ 808,78 4

$660,00 0 $3,820,00 0 $62,33 0

$6,25 6 $341,27 4 $227.51 6 $637,37 6

Cost s ar e annualize d ove r a te n yea r perio d a t a discoun t rat e o f 4 percent . Al l cost s ar e i n 198 7 dollars .

4-2 1P.8 0

particula r facilit ywil l experienc e a reportabl e releas e i s a functio n o f the types , quantities , an d form s o f radionuclide s use d an d produce d a t the facility , an

d the facility' s handling procedure s o r productio n processes . Th e type s o f facilitie s tha t mayb e affecte d b ythe fina l regulatio n varywidel yfro

msmal l laboratorie s t o larg e uraniu mmining operations . I t i s no t possibl e t o identif ythe facilitie s tha t ar e mos t likel yt o experienc e reportabl e radionuclid e release s and , therefore , i t i s no t possibl e t o develop a financia l mode l o f a typica l releaser . W e can discus s i n genera l terms , however , the magnitud e o f the cost s fo r a facilit yexperiencing a reportabl e releas e unde r the fina l regulation . Thes e cost s ar e a s follows :

Notificatio n Cost s - - $ 19 7 t o the Nationa l Respons e Cente r $ 17 7 t o Stat e an d Loca l official s Recordkeeping Cost s - - $ 18.5 0 Respons e Cost s - - $5,60 8 Th e tota l cos t t o a facilit yo r vesse l experiencing a reportabl e radionuclid e release , therefore , i s estimate d t o b e approximatel y$6,000 . Th e actua l cost s tha t a facilit ywil l incur wil l depen d largel yo n cleanu p costs , estimate d t o rang e fro

m$ 0 t o $55,637 , wit ha weighte d averag e cleanu p cos t o f $5,608 . Th e tota l annua l burde n unde r the fina l R Q adjustment s experience d b y al l affecte d partie s depend s o n the siz e an d numbe r o f reportabl e releases . Th e burde n impose d b ythe CERCL

Aan d SAR Anotificatio n requirement s o n a n individua l busines s depend s directl yo n the numbe r o f reportabl e release s tha t occu r a t tha t facility . Mos t o f the facilitie s potentiall yaffected , i n fact , woul d experienc e n o cost s fro mthe notificatio n requirement s becaus e theyhav e n o reportabl e releases . Eve n assuming a reportabl e releas e occur s a t a facility , the likel ycost s incurre d ar e smal l compare d wit hthe overal l economi c situatio n a t tha t facility . Cleanu p an d othe r respons e action s ar e no t require d b

ythi s regulation ; facilitie s ar e liabl e unde r CERCL Afo r an

y respons e cost s o r natura l resourc e damage s regardles s o f whethe r the releas e i s reportable . Aconclusio n ca n thu s b e mad e tha t the regulatio n wil l no t hav e a significan t impac t o n an yfirm , larg e o r small , tha t potentiall yincur s a radionuclid e release .

4-2 2P.8 1

CHAPTE R 5 SENSITIVITY ANALYSI S

Severa l time s i n thi s analysis , dat a wer e use d whos e margi n o f erro r coul d hav e bee n improve d throug hfurthe r research . Similarly , i n severa l instances , keyassumption s i n the stud ywer e mad e tha t use d the bes t availabl e informatio n fro

ma limite d dat a bas e o f historica l radionuclid e releases . Unde r thes e circumstances , i t i s importan t t o conduc t a sensitivit yanalysi s t o tes t the impac t tha t changing ke yassumption s woul d hav e upo n the result s o f the analysis . Th e firs t two section s o f thi s chapte r conduc t a sensitivit y analysi s o n the result s o f thi s economi c impac t study . Sectio n 5. 1 discusse s the importanc e o f a sensitivit yanalysi s an d establishe s the range s fo r the keyvariable s an

d assumption s tha t wil l b e tested ; Sectio n 5. 2 present s the result s o f th e sensitivit yanalysi s usin g thes e ranges ; Sectio n 5. 3 describe s the result s o f a statistica l analysi s o f th e radionuclid e dat a base ; an d Sectio n 5. 4 summarize s the result s o f the sensitivit yanalysis . 5. 1 CONCEPT S AN

D KE Y VARIABLE S Asensitivit yanalysi s indicate s ho wthe result s o f a n analysi s migh t varyi f som

e o f the basi c component s o r assumption s o f the stud ywer e different . If , fo r example , a n analys t i s reasonabl ycertai n tha t on e o f tw o particula r value s fo r a keyvariabl e i s correc t bu t doe s no t kno wwhic hone , o r tha t two value s bracke t the tru e value , th e analys t ma yus e eac ho f the value s i n the sensitivit yanalysi s t o se e ho wth e result s migh t differ . Th e resul t i s the n presente d twic e - - onc e fo r eac hvalu e o f the ke yvariable . I n othe r situations , ther e mayb e verylittl e guidanc e o n a particula r ke yvariable . A n analys t ca n mak e a reasonabl e gues s abou t th e likel yvalu e fo r the variable ; the analys t mayselec t othe r value s t o determin e the sensitivit yo f the result s t o tha t choice . Thi s techniqu e ha s the advantag e o f indicating the rang e o f possibl e results , althoughi t doe s no t indicat e whethe r the "true " resul t i s included . Asensitivit yanalysi s ofte n add s informatio n becaus e i t provide s upper an d lower-boun

d estimate s o f the results . Nonetheless , the rang e o f result s mayb e to o smal l o r to o large , depending o n th e qualit yo f the value s use d i n the sensitivit yanalysis . Th e value s obtaine d bot hi n the initia l analysi s an d the sensitivit yanalysi s ultimatel yrel yo n the qualit yo f the inpu t data . Th e sensitivit yanalysi s i n thi s stud ytest s the impac t o f changing si x basi c assumption s tha t hav e bee n use d during the analysis . Thes e assumption s are : (1 ) the numbe r o f incrementa l reportabl e episodi c releases ; (2 ) the hour s required , and therefore , th e uni t cos t o f notification ; (3 ) the frequencyo f off-scen e monitoring ; (4 ) the frequencyo f on-scen e monitoring ; (5 ) the frequencyo f cleanup s b yresponsibl e parties ; an d (6 ) the frequencyo f direc t remova l b

ythe government . Th e las t four assumption s subjec t the frequencyo f action s t o the sensitivit ytes t rathe r tha n the uni t cost s o f performing suc haction s becaus e th e cos t estimate s ar e considere d reasonable , an d adjustment s i n th e cos t estimate s ar e overwhelme d b yth e frequency estimates .P.8 2

Th e value s use d i n the bas e cas e fo r eac ho f thes e si xkeyassumption s ar e varie d i n the following manne r i n the sensitivit yanalysis : 1 . Numbe r o f incrementa l reportabl e episodi c releases . Th e numbe r o f incrementa l reportabl e release s i s perhap s the mos t importan t variabl e o n whic hcost s ar e estimated . Th e analysi s i n Chapte r 4 estimate s tha t ther e wil l b e 5 9 annua l incrementa l reportabl e releases . Thi s estimat e mayvary becaus e the estimate s o f under-reporting coul d b e inaccurate ; the AEO D dat a se t mayno t contai n representativ e facilities ; the numbe r o f release s mayno t b e proportiona l t o the numbe r o f facilities ; o r the assumptio n tha t 13,00 0 Agreemen t Stat e an

d 47 0 DO E facilitie s releas e radionuclide s i n a patter n simila r t o Nuclea r RegulatoryCommissio n facilitie s mayb e inaccurate . I n orde r t o reflec t the orde r o f magnitud e change s i n cost s tha t woul d resul t fro mlarg e difference s i n the numbe r o f incrementa l reportabl e releases , the sensitivit yanalysi s wil l estimat e the cost s o f halving an d doubling the bas e cas e estimat e o f 59 . Thus , th e following assumption s ar e tested : Numbe r o f Incrementa l Release s Lo wEstimat e Bas e Cas e HighEstimat e 3 0 5 9 12 0 2 . Notificatio n hours . Th e cost s associate d wit hnotificatio n o f th e Nationa l Respons e Cente r an d stat e an

d loca l emergencyrespons e commission s represen t approximatel y6 0 percen t o f tota l cost s t o regulate d parties . Th e bas e cas e analysi s i n Chapte r 4 assume s tha t 3 hour s o f manageria l tim e an d 2 hour s o f technica l time woul d b e require d fo r eac hepisodi c releas e t o notif y the Nationa l Respons e Center . Notificatio n maytak e mor e o r les s tim e depending o n factor s suc ha s th e siz e o f the releas e an d the typ e o f radionuclid e released . T o estimat e the rang e o f notificatio n cost s tha t regulate d partie s migh t experience , the estimat e o f hour s ar e halve d an d double d fo r the sensitivit yanalysis , resulting i n the following uni t cos t estimates : Manageria l an d Technica l Hour s Require d fo r Notificatio n Lo wEstimat e Bas e Cas e HighEstimat e $9 9 $19 7 $39 4 3 . Frequenc yo f off-scen e monitoring . I n Chapte r 4 , i t i s assume d tha t al l release s requir e the governmen t t o incur cost s fo r notificatio n processing , bu t tha t some o f thes e release s (3 0 percent ) requir e n o furthe r governmen t action , an d tha t the remainde r (7 0 percent ) d o requir e the governmen t t o performoff-scen e monitoring . Th e sensitivit yanalysi s test s scenario s i n whic hlowe r an d highe r percentage s o f episodi c release s reporte d t o the Nationa l Respons e Cente r requir e off-scen e monitoring . Th e thre e set s o f estimate s fo r frequencyo f off-scen e monitoring use d i n the sensitivit y analysi s are : Frequenc yo f Off-Scen e Monitoring Lo wEstimat e Bas e Cas e HighEstimat e .3 5 .7 0 .9 0

5- 2P.8 3

4 . Frequencyo f on-scen e monitoring . I t als o i s importan t to ' examin e the sensitivit yo f estimate s fo r the frequencyo f on-scen e monitoring effort s tha t wil l b e neede d (i.e. , th e percen t o f reportabl e release s tha t resul t i n federal , state , o r loca l official s providing monitoring a t the scen e o f the release) . On-scen e monitoring account s fo r approximatel y1 3 percen t o f the tota l cos t o f the fina l regulatio n an d fo r 1 6 percen t o f the government' s shar e o f the tota l costs . Frequencyo f On-Scen e Monitoring Lo wEstimat e Bas e Cas e HighEstimat e .1 0 .2 0 .4 0 5 . Frequencyo f cleanup s b yregulate d parties . Th e bas e cas e assume s tha t ther e i s a measurabl e differenc e i n the percen t o f episodi c release s t o whic hregulate d partie s respond , depending o n whethe r the releas e i s above o r belo wthe RQ . I f thi s assumptio n i s inaccurat e (i.e. , i f responsibl e partie s woul d no t respon

d differentl yt o release s abov e o r belo wthe RQ) , the n n o cost s tha t resul t fro mrespons e activitie s ca n b e attribute d t o the fina l regulatio n tha t adjust s the RQs . Th e sensitivit yanalysi s test s ho wthe result s ar e change d i f the incrementa l chang e i n cleanu p activitie s b

y regulate d partie s i s 0 , an d i f the incrementa l percentag e i s highe r than the bas e cas e scenari o o f 5 percent .

Incrementa l Frequenc yo f Cleanup s b yRegulate d Partie s Lo wEstimat e Bas e Cas e HighEstimat e .0 0 .0 5 .2 0 6 . Frequencyo f direc t remova l b ygovernment . Th e bas e cas e assume s tha t a direc t remova l i s necessaryb ythe governmen t i n 5 percen t o f al l episodi c releases . Th e sensitivit yanalysi s test s the effec t o n the result s i f governmen t remova l wer e necessaryi n a lowe r percentag e o f reportabl e radionuclid e releases , an d i f the governmen t woul d b e require d t o become involve d i n a direc t remova l actio n i n a greate r percentag e o f radionuclid e releases . Frequenc yo f Governmen t Direc t Remova l Lo wEstimat e Bas e Cas e HighEstimat e .02 5 .0 5 .2 0 Afte r the sensitivit yanalysi s i s conducte d fo r eac ho f thes e si xset s o f assumptions , a sevent hsensitivit ytes t i s conducte d b ycombining al l o f the lowan

d al l o f the highestimate s together . Fo r example , i n orde r t o se e th e impac t o f al l o f the lo westimates , the analysi s assume s tha t ther e ar e 3 0 incrementa l reportabl e releases , the notificatio n cos t i s $99 , ther e i s a 3 5 percen t chanc e o f th e governmen t conducting off-scen e monitoring , a 1 0 percen t chanc e o f th e governmen t conducting on-scen e monitoring , n o chang e i n the percentag e o f release s t o whic hregulate d partie s respond , an d a 2. 5 percen t chanc e tha t th e governmen t wil l conduc t a direc t removal . Th e combinatio n 5- 3o f thes e si xassumption s produce s a lower-boun d estimat e fo r the sensitivit y analysis . Th e sam

e i s don e fo r the highestimate s t o produc e a n upper-bound estimate . 5. 2 RESULT S O

F THE SENSITIVIT

YANALYSI S Thi s sectio n present s the result s o f the sensitivit yanalysis , an d include s a descriptio n o f change s i n the estimate d cost s t o the governmen t an d t o regulate d partie s tha t occur fro mreporting an

d cleanu

p activitie s describe d i n the las t section . Th e result s o f the sensitivit yanalysi s ar e summarize d i n Exhibi t 5-1 . 1 . Numbe r o f incrementa l reportabl e releases . Estimate s o f th e numbe r o f incrementa l reportabl e release s affec t al l o f the estimate s o f cost s tha t resul t fro

mincrease d notification , recordkeeping , an d respons e activitie s byregulate d partie s an d governmen t officials . Exhibi t 5- 1 present s the result s o f changing the estimate d numbe r o f incrementa l reportabl e release s and compare s the cos t o f the fina l regulatio n t o the bas e cas e o f 5 9 releases . 2 . Notificatio n hours . Varying the estimate d numbe r o f hour s require d t o repor t release s wil l affec t the cos t estimate s associate d wit hnotificatio n acitivitie s fo r regulate d parties . Exhibi t 5- 1 present s the result s o f the sensitivit yanalysis , i n whic hthe bas e cas e hou r estimate s ar e halve d an d doubled . Thes e cos t variation s onl yaffec t regulate d partie s an d woul d no t chang e the cost s t o governmen t official s o f processing the notifications . 3 . Frequencyo f Governmen t Off-Scen e Monitoring . Th e result s o f variation s i n the percen t o f release s tha t the analysi s assume s ar e necessary fo r the governmen t t o become involve d ar e presente d i n Exhibi t 5-1 . Thes e ar e cost s t o the governmen t official s responsibl e fo r the off-scen e monitoring . 4 . Frequencyo f Governmen t On-Scen e Monitoring . Variation s i n the assume d frequencyo f on-scen e monitoring fo r radionuclid e release s affec t the cost s tha t the governmen t incurs . Exhibi t 5- 1 show s the effec t o n on-scen e monitoring b

yassuming tha t the percen t o f release s during whic hthe governmen t mus t conduc t on-scen e monitoring ar e highe r an d lower . 5 . Frequenc yo f incrementa l response s bvregulate d parties . Varying the assumptio n concerning the differenc e i n responsibl e parties ' cleanu p effort s fo r reportabl e an

d unreportabl e release s lead s t o differen t respons e cost s fo r regulate d parties . Th e differenc e i n industr yrespons e t o reportabl e release s a s oppose d t o unreportabl e release s i s show n i n Exhibi t 5-1 . 6 . Frequencyo f direc t remova l b vgovernment . Variation s i n the assume d frequencyo f direc t respons e an d remova l b

ythe governmen t affec t the cost s o f the fina l regulation . Exhibi t 5- 1 show s the effec t o n the government' s cost s i f the governmen t respond s 2. 5 percen t an d 2 0 percen t o f the tim e t o releases , instead o f the bas e cas e estimat e o f 5 percent .

5- 4EXHIBI T 5- 1 RESULT S O

F THE SENSITIVIT

YANALYSI S

Lo wEstimate . Bas e Cas e HighEstimat e
Numbe r o f incrementa l reportabl e release s Assumptio n : Cos t o f propose d regulation : Notificatio n cost s t o Nationa l Respons e Cente r 3 0 $130,37 5 5 9

$256,40 5

Incrementa l frequencyo f cleanup s b

yresponsibl e partie s

Frequenc yo f off-scen e monitoring Assumptio n Off-scen e monitoring cost s Cos t o f propose d regulatio n Frequenc yo f on-scen e monitoring Assumptio n On-scen e monitoring cost s Cos t o f propose d regulatio n Frequenc yo f direc t govern men t remova l 12 0 $521,49 8

Assumptio n : Notificatio n Cost s : Cos t o f propose d regulation : $9 9 $5,84 1 $250,62 3 $19 7

$11,62 3 $256,40 5 $39 4

$23,24 6 $268,02 8

Assumptio n : Cos t o f Cleanup s : Cos t o f propose d regulation : .0 0 0 $239,86 1 .0 5

$16,54 3 $256,40 5 .2 0

$66,17 4 $306,03 5

.3 5 $4,52 2 $251,88 2 .7 0

$ 9,04 5 $256,40 5 .9 0

$11,62 9 $258,98 9

.1 0 $15,98 9 $240,41 6 .2 0

$31,97 8 $256,40 5 .4 0

$63,95 6 $288,38 3

Assumptio n Direc t remova l cost s Cos t o f propose d regulatio n Cos t o f Propose d Regulatio n wit hAL L assumption s varie d .02 5 $82,06 5 $174,34 1 $66,86 6 5- 5 .0 5

$164,12 9 $256,40 5 $256,40 5 .2 0

$656,51 7 $748,79 3 $1,717,84 4P.8 6

Varying al l o f the lowestimat e assumption s a t on e tim e produce s a lower-boun

d estimat e o f the cos t o f the fina l regulation . Thi s estimat e i s approximatel y$66,900 . Conducting the same tes t fo r al l o f the highestimate s produce s a n upper-bound cos t o f the fina l regulatio n o f approximatel y$1.7 2 million . I n additio n t o thes e lowe r an d upper-bound estimates , a n additiona l $1.3 9 millio n mus t b e adde d fo r the cost s o f the annua l report s fo r facilitie s tha t releas e radionuclide s an d repor t unde r sectio n 103(f)(2 ) o f CERCLA . Therefore , the lowe r an d upper-bound estimate s o f the cos t o f the fina l regulation , give n the qualit yo f the inpu t dat a tha t i s available , ar e approximatel y$1.4 6 millio n an d $3.1 1 million , respectively . 5. 3 STATISTICA

L ANALYSI S O

F EIA RADIONUCLID

E DAT A BAS E Th e analysi s fo r estimating the numbe r o f reportabl e release s i n bot h the baselin e situatio n an d unde r the fina l regulatio n implicitl yassume s tha t ther e i s n o correlatio n betwee n the siz e o f a releas e an d the identityo f the radionuclid e released . Thi s hypothesi s wa s tested . An analysi s o f varianc e mode l (ANOVA ) wa s use d t o tes t the hypothesi s tha t ther e i s n o relationshi p betwee n the siz e o f a releas e an d the identit y o f the radionuclide . Th e releas e observation s wer e groupe d b yisotop e an

d the Genera l Linea r Mode l (GLM ) procedur e o f the Statistica l Analysi s Syste m(SAS ) wa s use d fo r the test . Th e result s indicated 1 tha t w e coul d no t rejec t the hypothesi s o f n o associatio n betwee n the isotop e an d mea n releas e amount . Therefore , w e hav e assume d tha t ther e i s n o association . 5. 4 SUMMAR

Y Asensitivit yanalysi s i s a s enlightening a s the dat a tha t caus e the estimate s t o change . Th e result s i n thi s chapte r sugges t tha t halving an d doubling man

yo f the effect s an d altering othe r ke yassumption s woul d no t chang e the overal l conclusion s o f th e analysi s tha t the estimate d cos t o f the regulatio n i s small , bot hfo r regulate d partie s an d fo r the government . Becaus e dat a o n the healt han d welfar e an

d environmenta l effect s o f altering the RQ s ar e no t available , thi s sensitivit yanalysi s i s no t abl e t o varythes e effects .

1 Th e F-statisti c wa s 1.0 5 (d.f . o f 52 ; 632 ) whic hwa s a p-valu e o f 0.39 . 5- 6P.8 7

APPENDI XA PROFILE S O

F FACILITIE S THA

T RELEAS E RADIONUCLIDE S
Radionuclid e emission s ar e identifie d mos t closel ywit hth e nuclea r powe r industry , bu t commonl yoccur during othe r activitie s a s well . Th e Nuclea r RegulatoryCommission , Agreemen t State s delegate d authorit yb ythe Commission , the Departmen t o f Defens e (DOD) , an d the Departmen t o f Energ y (DOE ) al l licens e o r overse e a variet yo f industria l facilitie s an d nonindustria l operation s tha t emi t radionuclides . I n addition , severa l industria l categorie s no t license d b ythe Commissio n o r a n Agreemen t Stat e als o releas e radionuclides , an d mayd o s o a t level s tha t equa l o r excee d a n RQ . Fo r example , coal-fire d utilit yan d industria l boiler s an d facilitie s o f man yminera l extractio n industries , suc ha s uranium , aluminum , zinc , copper , lead , an

d phosphoru s mining , al l releas e quantitie s o f radionuclide s during thei r operations . Th e following section s briefl ydiscus s eac ho f the releas e categorie s cite d above , describing the sourc e o f radionuclid e emissions , the numbe r o f facilitie s withi n eac hcategory , and , wher e available , genera l trend s i n the industries . I n addition , fo r facilitie s whos e release s ar e no t federall y permitted , a furthe r estimat e i s mad e o f the numbe r o f facilitie s tha t ar e likel yt o b e releasing dail ya n R Q o n a continuou s basi s an d thus , eligibl e fo r reporting unde r sectio n 103(f)(2) . Sectio n A. l describe s facilitie s tha t ar e license d b

ythe Nuclea r RegulatoryCommissio n an d Agreemen t States ; Sectio n A. 2 discusse s Departmen t o f Defens e facilities , mos t o f whic hthe Nuclea r RegulatoryCommissio n licenses ; Sectio n A. 3 describe s Departmen t o f Energ yfacilities ; an

d Sectio n A. 4 discusse s othe r facilitie s potentiall y affecte d b

yadjustmen t o f the radionuclid e RQs . Coal-fire d utilit yan d industria l boiler s ar e discusse d i n greate r detai l i n Appendi xB .

A. l NUCLEA

RREGULATOR

YCOMMISSIO

N AN DAGREEMEN

T STAT E LICENSEE S Th e Nuclea r RegulatoryCommissio n ha s the authorit yunde r the Atomi c Energ yAc t t o licens e source , byproduct , an d specia l nuclea r materials . Th e Commissio n ha s delegate d t o Agreemen t State s licensing authorit yt o regulat e source , byproduct , an d specia l nuclea r material s fo r facilitie s withi n thei r boundaries . A s o f 1984 , the Commissio n license d approximatel y8,90 0 facilitie s an

d Agreemen t State s license d approximatel y13,00 0 facilities. 1 Release s a t facilitie s license d b ythe Nuclea r RegulatoryCommissio n an d Agreemen t State s ar e subjec t t o the radioactiv e materia l releas e limit s specifie d i n 1 0 CFR Par t 20 , a s wel l a s othe r control s specifie d b ythe license . Fo r purpose s o f thi s discussion , licensee s ar e divide d int o five categories : powe r reactors , researc hand tes t reactors , radiopharmaceutica l manufacturers , radiatio n sourc e manufacturers , an d othe r licensees . Th e Commissio n als o license s mos t o f the Departmen t o f Defens e facilities , bu t thes e facilitie s ar e discusse d separatel yi n Sectio n A. 2 o f thi s report .

U.S . Nuclea r RegulatoryCommission , 198 4 Annua l Report , p . 7 3P.8 8

Powe r Reactor s Powe r reactor s utiliz e a controlle d fissio n reactio n o f uraniu mfue l t o produc e heat . Th e hea t convert s wate r t o steam , whic hprovide s the forc e t o spi n a turbine-generato r t o produc e electricity . Th e nuclea r fissio n chai n reactio n i s controlle d b yth e reactor' s contro l rods . Th e movemen t o f th e contro l rod s u

p o r dow

n withi n the fue l assemblie s sustain s the chai n reactio n a t a desire d powe r level . Ther e ar e ove r 10 0 nuclea r plant s i n the Unite d State s i n operation , generating approximatel y1 3 percen t o f electricit y consumption . Release s resulting i n "nuclea r incidents " (section ll(q ) o f the Atomi c Energ yAct ) a t facilitie s covere d b ythe Price-Anderso n Ac t ar e exemp t fro m CERCL Areporting requirement s (section 101(22)) . Release s a t Nuclea r RegulatoryCommissio n an d Agreemen t Stat e facilitie s tha t ar e a n R Q o r mor e abov e federall ypermitte d releas e levels , bu t d o no t constitut e a nuclea r incident , mus t b e reporte d unde r CERCL At o the Nationa l Respons e Cente r an d unde r SAR

At o Stat e EmergencyRespons e Commission s (SERCs ) an d Loca l Emergency Planning Committee s (LEPCs) . Researc han

d Tes t Reactor s A s o f 1983 , ther e wer e 7 0 reactor s i n operatio n i n the Unite d State s use d i n basi c an

d applie d research , an d teaching . Th e researc hconducte d include s testing o f reacto r designs , components , an d safet yfeatures , a s wel l a s wor k i n the field s o f physics , biology , an d chemistry . Radiopharmaceutica l Manufacturer s Radiopharmaceutical s ar e radioactiv e chemical s use d fo r medica l application s and research . I n 1979 , ther e wer e 2 6 industria l supplier s o f radiopharmaceutical s producing 6 5 generall yuse d radionuclides . Thes e 2 6 firm s exclud e firm s tha t purchas e radiopharmaceutica l product s i n bul k an d repackag e themi n smalle r container s (repackagers) . I n 1984 , th e Commissio n license d mor e tha n 2,80 0 medica l facilitie s fo r us e o f radiopharmaceuticals , and Agreemen t State s license d approximatel y7,00 0 facilities. 2 Medica l facilitie s us e radionuclide s i n al l form s including solids , liquids , an d gases ; use s includ e diagnosti c an d therapeuti c procedures .

2 Th e numbe r o f medica l facilitie s tha t ar e Commissio n licensee s i s reporte d o n pag e 7 3 o f the 198 4 U.S . Nuclea r RegulatoryCommissio n Annua l Report . bu t the publicatio n doe s no t repor t the numbe r o f medica l facilitie s tha t ar e license d b yAgreemen t States . EPAestimate s tha t the tota l numbe r o f radiopharmaceutica l manufacturer s an d user s t o b e ove r 10,00 0 i n 197 7 (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 . 3.3-5) . Subtracting the 2,80 0 Commissio n licensee s fro mthe tota l estimat e o f 10,000 , yield s roughl ythe 7,00 0 Agreemen t Stat e licensees . A- 2P.8 9

Radiatio n Sourc e Manufacturing "Radiatio n sources " refe r t o radioactive material s enclose d i n seale d containers . Theyar e foun d i n a numbe r o f industria l an d consume r product s suc ha s radioisotop e gauge s use d t o measur e thickness , stati c eliminator s fo r industria l machinery , testing equipment , self-illuminating sign s and watc h dials , an

d smok e detectors . Manufacturer s o f radiatio n source s proces s bul k quantitie s o f radioactive material s receive d fro mradionuclid e productio n facilitie s suc ha s accelerator s o r reactors . Th e radiatio n sourc e manufacturer s keep inventorie s o f radioactiv e material s i n quantitie s ranging fro m1 0 curie s t o 100,00 0 curies . Othe r Commissio n o r Agreemen t Stat e Licensee s Othe r Nuclea r RegulatoryCommissio n o r Agreemen t Stat e licensee s includ e laboratories , low-leve l wast e disposa l sites , minera l an d meta l processing facilities , fue l cycl e facilities , an d uraniu

mmills . Laboratorie s Approximatel y70 0 laboratorie s ar e license d t o handl e radioisotope s i n unseale d form. 3 Thes e laboratorie s ar e locate d i n industry , governmen t agencies , an

d academi c an

d researc hinstitutions . The yar e use d t o perfor m testing an

d researc han

d development , an

d theyvarya grea t dea l i n size . Althoughsom

e institution s hav e onl yon e small , multi-purpos e laboratory , othe r institution s hav e u p t o 30 0 individua l laboratorie s i n severa l buildings . Smal l laboratorie s ten d t o specializ e i n a limite d numbe r o f radionuclide s fo r a singl e specifi c testing purpose . Academi c an d industria l laboratorie s us e byproduc t material s i n researc han d testing . Medica l laboratorie s conduc t basi c chemica l an d applie d radionuclid e researc hrelate d t o diseas e an

d healt hproblems . Governmen t laboratoryfacilitie s mayus e radionuclide s fo r foo d an d drug testing o r wate r and ai r qualit ymonitoring . Th e mos t commonl yuse d radionuclide s i n laboratorywor k ar e tritium , carbon

14 , xenon-133 , iodine-125 , an d iodine-131 . Testing and industria l laboratorie s ten

d t o us e large r quantitie s o f radionuclide s than academi c o r othe r researc hlaboratories ; conversely , academi c an d researc hlaboratorie s ten d t o us e a wide r variet yo f radionuclides .

3 Corbi t CD. , Herringto n W.N. , Higb yD.P. , Stou t L.A. , an d CorleyJ.P. , Background Informatio n o n Source s o f Low-Leve l Radionuclid e Emission s t o Air . PNL-4670 , Prepare d fo r EPAunde r U.S . DO E Contrac t b yBattell e Memoria l Institute , Septembe r 1983 . I t i s assume d tha t a n equa l numbe r o f smaller , unlicense d laboratorie s handl e unseale d radioisotopes , resulting i n a estimate d tota l o f 1,40 0 laboratorie s tha t ar e potentia l source s o f low-leve l radioactiv e emissions . Thes e unlicense d lab s ar e discusse d i n Sectio n A.4 . A- 3P.9 0

Wast e Disposa l Site s Althoughther e ar e si xlow-leve l radioactiv e wast e disposa l site s license d i n the Unite d States , onl ythre e ar e operational . Thes e site s accep t low-leve l radioactive waste s i n a stabilize d for mfro mthre e majo r sources : power-reacto r an

d fue l cycl e operations , laborator yresearch , an

d medica l facilities . Waste s accepte d b ythes e facilitie s fo r disposa l b yshallow-lan

d buria l mus t mee t specifi c sit e acceptanc e criteria . Th e disposa l site s d o no t accep t specia l nuclea r materials , transuranic s (element s having a highe r atomi c numbe r than uranium) , o r spen t reacto r fuel . Waste s ar e burie d a t the disposa l sit e i n the transpor t container s i n whic htheyarrive . Minera l an

d Meta l Processing Facilitie s Commissio n an

d Agreemen t Stat e licensee s includ e facilitie s tha t extrac t metal s fromthorium

- an d uranium-bearing ores . Te n suc hfacilitie s ar e license d i n the following nin e states : Alabama , California , Colorado , Florida , Illinois , Ne wMexico , Oregon , Pennsylvania , an d Tennessee . Thes e facilitie s generall yproces s ore s fo r eithe r refractorymetal s an d thei r oxide s (sucha s zirconium , columbium/niobium , tantalum , an d hafnium) , o r fo r rar e earth s (sucha s cerium , praseodymium , neodymium , dypsrosium , an d ytterbium) . Thoriu mals o i s use d i n som e o f thes e facilitie s t o manufactur e weldin g rod s an

d t o cas t machin e parts . Fue l Cycl e Facilitie s Th e Commissio n and Agreemen t State s als o licens e th e us e o f source , byproduct , an

d specia l nuclea r materia l a t facilitie s engage d i n the productio n o f nuclea r fuel . Thes e facilitie s includ e operating uraniu mmills , uraniu mhexafluorid e conversio n plants , an d uraniu

mfue l fabricatio n plants . Ther e i s currentl yn o plutoniu mfiel d fabricatio n don e i n the Unite d States . Uraniu mMilling Uraniu mor e i s delivere d t o mill s wher e i t i s crushe d an d ground , an

d uraniu moxid e i s extracte d chemically . Th e mil l product , als o calle d uraniu m concentrat e o r yello wcake , the n i s sen t t o conversio n facilities , wher e i t i s chemicall yconverte d t o uraniu mhexafluoride . Uraniu mmilling activit yi s a declining industry . A s o f Novembe r 1985 , ther e wer e onl ythre e active uraniu m mill s i n the Unite d State s (on e o f whic hi s expecte d t o g o o n standb ystatus) . An additiona l 1 7 mill s ar e alread yo n standb

ystatus . Tota l uraniu moxid e productio n fro

mmill s wa s abou t 7,40 0 ton s i n 1984 , dow n fro m21,80 0 ton s i n 1980. *

4 U.S . Environmenta l Protectio n Agency , Propose d Standard fo r Radon-22 2 Emission s fromLicense d Uraniu mMil l Tailings : Draf t Economi c Analysi s (EP A 520/1-86-002) , Offic e o f Radiatio n Programs , January1986 . A- 4P.9 1

A. 2 DEPARTMEN

T O F DEFENS E FACILITIE S Th e Nuclea r RegulatoryCommissio n als o license s some Departmen t o f Defens e (DoD ) facilities . Thes e facilities , therefore , mus t compl ywit h limit s fo r airborn e an d liqui d discharge s t o unrestricte d area s unde r 1 0 CFR Par t 2 0 tha t gover n federall ypermitte d release s fo r al l othe r Nuclea r RegulatoryCommissio n facilities . Th e Arme d Force s Radiobiolog yResearc hInstitut e (AFRRI) , locate d a t the Nationa l Nava l Medica l Cente r i n Bethesda , Maryland , operate s bot ha therma l researc hreacto r an d a linea r accelerato r (linac) , mainl yi n suppor t o f researc ho n the medica l effect s o f nuclea r radiatio n an d the effect s o f transien t radiatio n o n electronic s an d othe r equipment . Th e U.S . Arm yTes t an d Evaluatio n Comman d operate s tw

o reactor s tha t ar e simila r i n design an d ar e use d t o suppor t studie s o n th e effect s o f nuclea r radiation . Bot har e fuele d wit henriche d uranium . Nin e nava l shipyard s accoun t fo r almos t al l o f the radionuclid e release s fromU.S . Nav

yfacilities . Pressurize d wate r reactor s powe r the nuclea r flee t a t the nava l shipyards . Standard operation s a t the shipyard s includ e construction , startu p testing , refueling , an d maintenanc e o f the reactors . Radioactiv e waste s generate d b ythes e operation s ar e processe d an d sealed , the n shippe d t o commercia l wast e disposa l sites .
A. 3 DEPARTMEN

T O F ENERG Y(DOE ) FACILITIE S Th e U.S . Departmen t o f Energ y(DOE ) ha s authorit yunde r the Atomi c Energ yAc t o f 195 4 (Section 16 1 o f Publi c Law83-703 ) "t o protec t the publi c healt han

d safety " wit hrespec t t o the operatio n o f so-calle d "G0C0 " facilitie s - - facilitie s tha t ar e "governmen t owned , contracto r operated. " Majo r DO E facilitie s includ e nationa l laboratories ; facilitie s associate d wit hthe Formerl yUtilize d Site s Remedia l Actio n Progra m(FUSRAP) , the Uraniu

mMil l Tailing s Remedia l Actio n Progra m(UMTRAP) , the Gran d Junctio n Remedia l Actio n Progra m(GJRAP) , the Surplu s Facilitie s Managemen t Progra m (SFMP) ; an

d facilitie s involve d i n specifi c researc han d developmen t programs. 5 DO E als o i s responsibl e fo r operating uraniu menrichmen t facilities , a step i n the nuclea r fue l cycle . Othe r DO E operation s involving radionuclide s includ e nuclea r weapon s research , development , an d production ; medica l an

d biologica l research ; an d industria l application s an d development . A s o f 1980 , 7 8 "GOCO " facilitie s i n 2 4 state s wer e subjec t t o the healt h an d safet yrequirement s containe d i n DO E orde r 5484.1 . A n estimate d 4 7 o f thes e complexe s contai n facilitie s tha t activel yus e radionuclides . Thes e complexe s includ e laboratorie s operating diversifie d programs , an d facilitie s conducting weapon s productio n an d testing , nuclea r material s production , an d physica l research .

5 Roger s and Associate s Engineering Corp. , Radioactiv e Contaminatio n a t Federall yOwne d Facilities . Jun e 1982 , pp . 3-2 , 3-3 . A- 5P.9 2

A. 4 OTHE

RFACILITIE S I n additio n t o the Nuclea r RegulatoryCommissio n o r Agreemen t Stat e licensees , an

d facilitie s controlle d b yDOE , othe r facilitie s maypotentiall y releas e radionuclide s a t level s tha t equa l o r excee d the fina l adjuste d radionuclid e RQs . Thes e facilities , however,d o no t hav e federall ypermitte d releases , an

d thus , hav e t o repor t release s o f a n R Q o r mor e unde r sectio n 10 3 o f CERCLA . I n additio n t o possibl e episodi c releases , man yo f thes e facilitie s releas e low-leve l amount s o f radionuclide s i n a manne r tha t i s "continuous " an

d "stabl e i n quantit yan d rate, " an

d therefore , mayb e subjec t t o the continuou s releas e reporting requirement s unde r sectio n 103(f)(2) . Thes e facilities , principall ycoal-fire d boilers , minera l an d energ y extractio n an

d processing facilities , an d natura l ga s furnace s ar e considere d i n furthe r detai l below . Coa l Mine s A s o f 1987 , ther e wer e approximatel y1,98 0 underground an d 2,12 0 surfac e mine s i n operatio n i n the Unite d States , producing approximatel y91 9 millio n shor t ton s o f coal . Coa l productio n ha s increase d approximatel y3 percen t annuall yove r the las t severa l years , despit e a reductio n i n the numbe r o f activ e mine s an

d i n tota l employmen t i n the industry . Increase s i n productio n hav e largel yresulte d fro mth e continue d growt ho f efficien t mining o n a larg e scale . Minin g i n the state s o f Kentucky , Wes t Virginia , an d Wyoming accoun t fo r nearl y5 0 percen t o f the annua l production . Coa l contain s minera l matte r including trac e quantitie s o f radionuclides , sulfides , chlorides , hydrates , an d oxides . Th e Atomi c Energ y Ac t doe s no t give the Nuclea r RegulatoryCommissio n (or Agreemen t States ) the authorit yt o licens e release s o f thes e radionuclides , whic har e principall yi n the uraniu

man d thoriu

mseries . A s coa l i s burned , the mineral s i n the coa l mel t an d the n condens e int o a glass-lik e ash . Th e minera l conten t o f the coa l wil l determin e the concentratio n o f the contaminant s i n the ash . T o remove some o f thi s minera l conten t an d achiev e othe r desire d qualities , coa l i s frequentl ycleane d i n a three-step process : siz e reductio n an d screening , separatio n o f impurities , an d dewatering and drying . Coa l i s reduce d i n siz e througha crushing proces s tha t liberate s some impuritie s an d als o make s the coa l easie r t o bur n i n some type s o f boilers . Impuritie s ca n b e furthe r remove d fro

mcoa l b

yadditiona l cleaning . Finally , th e coa l i s dewatere d t o reduc e it s moistur e conten t t o acceptabl e levels . Coa l cleaning plant s ar e ofte n locate d clos e t o o r o n the sit e o f the min e an d maystockpil e quantitie s o f uncleane d o r cleane d coa l a t the facilit y i n unenclose d areas . Base d o n averag e concentration s o f radionuclide s i n coal , approximatel y2,36 0 ton s o f coa l contai n a n RQ o f a mixtur e o f naturall y occurring uraniu

mserie s and thoriu mserie s radionuclide s i n secula r equilibrium. 6 An

ymin e producing thi s quantit yo f coa l o n a dail ybasi s may dum p thi s amoun t outsid e o n a dail ybasi s an d thus , b e require d t o repor t

6 Se e Appendi xB fo r a detaile d derivatio n o f thi s figur e an d the assumption s underlying it . A- 6P.9 3

release s o f radionuclide s unde r CERCLA . Base d o n the averag e numbe r o f working day s a t coa l mine s throughou t the Unite d States , thi s dail yproductio n quantit yca n b e converte d t o a n annua l figure: 7

22 4 days/yea r * 2,36 0 tons/da y= 528,60 0 tons/yea r Ther e ar e 36 3 mine s i n the Unite d State s wit han annua l productio n i n exces s o f 500,00 0 tons. 8 Althoughthe operation s o f thes e facilitie s hav e no t bee n characterize d i n grea t detail , i t i s reasonabl e t o assume tha t thes e facilitie s potentiall ymayreleas e a n R Q o f radionuclide s b ythe dumping o r moving o f coa l o n a regula r basis . Coal-Fire d Utilit yan d Industria l Boiler s Larg e coal-fire d boiler s ar e use d t o generat e electricit yfo r publi c an d industria l us e an

d t o provid e proces s steam , proces s ho t water , an d spac e heat . Boiler s use d i n the utilit yindustr yar e designate d a s utilit yboilers , an d thos e use d t o generat e proces s steam , proces s ho t water , spac e heat , o r electricit yfo r in-hous e us e ar e designate d a s industria l boilers . Mor e tha n 60 0 millio n ton s o f coa l ar e burne d eac hyea r i n utilit yan d industria l boilers . I n 1983 , coal-fire d stea melectri c powe r unit s accounte d fo r 6 3 percen t o f tota l capacit yan d 5 5 percen t o f tota l energ ygeneratio n b

yU.S . electri c utilit ygenerating units. 9 I n earl y1987 , ther e wer e approximatel y1,40 0 coal-fire d unit s on-lin e wit ha tota l generating capacit yo f 30 0 gigawatts. 1 0 Coal-fire d industria l boiler s mainl yproduc e proces s stea man d ho t wate r t o generat e electricit y(fo r the producer' s ow n use) , and t o provid e spac e heat . Majo r user s o f industria l boiler s includ e the steel , aluminum , chemical , an

d pape r industries . Ther e ar e approximatel y51,20 0 coal-fire d industria l boiler s operating i n the Unite d States. 1 1 No t al l o f thes e 52,60 0 facilities , however , releas e a n R Q o f radionuclide s o n a continuou s basis . Appendi xB provide s a detaile d

7 Energ yInformatio n Administration , Coa l Productio n 1987 . EIA , Departmen t o f Energy , 1988 , p.70. .

8 Ibid. . p.28 . 9 U.S . Departmen t o f Commerce , Statistica l Abstrac t o f the U.S. . (1985) , 105t hEdition . Governmen t Printing Office , Washington , D.C , p . 564 .

1 0 U.S . Environmenta l Protectio n Agency , Repor t t o Congress : Waste s fro m the Combustio n o f Coa l b yElectri c Utilit yPowe r Plant s (EP A530-SW-88-002) , Offic e o f Soli d Wast e an d Emergenc yResponse , EPA , February1988 . p.2-22 . 1 1 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 , Octobe r 1981 . A- 7P.9 4

examinatio n o f the potentia l releas e pathway s o f radionuclide s fro mthes e facilitie s an

d a n estimat e o f the numbe r o f facilitie s likel yt o mee t o r excee d a n R Q o n a dail ybasis . UnlicensedLaboratorie s Approximatel y70 0 unlicense d laboratorie s us e smal l quantitie s o f radionuclide s i n highl ycontrolle d environments . Thes e facilitie s do no t nee d license s becaus e the yus e radionuclide s i n quantitie s an d concentration s belo w the licensing thresholds . Becaus e o f the lowquantitie s an d concentration s o f radionuclide s use d a t thes e laboratories , i t i s unlikel ytha t a facilit yuse s o r store s sufficien t quantitie s o f an yradionuclid e t o releas e a t o r abov e the R Q o n a continuou s basis . Episodi c radionuclid e release s a t o r abov e a n R Q ar e mor e probabl e an d woul d hav e t o b e reporte d unde r CERCLA . Low-energ

y Accelerator s Ther e ar e approximatel y1,50 0 low-energ yaccelerator s i n the Unite d States . Base d o n estimate s o f annua l emission s fro mtypica l particl e accelerators , radionuclid e emission s fro mthes e facilitie s d o no t excee d RQ s (EPA'8 4 p.3.2-4) . A s thes e facilitie s do no t stoc k larg e quantitie s o f materials , i t i s als o unlikel ytha t othe r releas e path s ar e significant . Uraniu m Minin g Ther e ar e severa l differen t type s o f uraniu mmine s an

d extractio n processes , including ope n pit , underground , an d in-sit u (solution ) mining operations . I n 1982 , ther e wer e 2 4 ope n pi t uraniu mmines , 13 9 underground uraniu mmines , an

d 1 8 in-sit u mine s i n operation , producing abou t 8 6 percen t o f the tota l uraniu moxid e domesti c productio n i n tha t year . Tota l uraniu m oxid e productio n wa s 13,40 0 tons. 1 2 Domesti c uraniu

mi s mine d almos t exclusivel yi n the wester n portio n o f the Unite d States , mostl yi n Ne wMexico , Wyoming , an d Texas . A s o f 1984 , uraniu mproductio n i n thes e State s collectivel yaccounte d fo r approximatel y6 5 percen t o f the nationa l total . Severa l othe r State s (including Arizona , Colorado , Florida , Sout hDakota , Utah , an d Washington ) togethe r accounte d fo r the remaining 3 5 percen t o f the total. 1 3

1 2 U.S . Departmen t o f Energy , Statistica l Dat a o f the Uraniu mIndustry . GJO-100(83) , Gran

dJunction , Colorado , January1983 , p . 9 . 1 3 Ibid , p . 9 . A- 8P.9 5

Th e majorit yo f the uraniu mindustr

yi s owne d b

ylarge , publicl yhel d corporations' . During the earl yan d mid-1970*s , the industr yexperience d rapi d growth , spurre d b

yexpectation s o f increasing demand . Thi s demand , however , di d no t materializ e and , consequently , the industr ycurrentl yi s face d wit h exces s capacit yan

d supply , an

d the potentia l fo r increase d competitio n from imports . Release s o f rado n fro munderground uraniu mmine s ar e federall ypermitte d unde r sectio n 11 2 o f the Clean Ai r Act . Release s o f othe r radionuclide s ar e no t necessaril ypermitte d an d coul d regularl yexcee d RQs. 1 AI t i s reasonabl e t o assume , therefore , tha t approximatel y18 0 uraniu mmine s coul d b e affecte d b ythe CERCL

Anotificatio n requirements , bu t ar e likel yt o repor t continuou s release s unde r the provision s o f sectio n 103(f)(2) . Aluminu mIndustr

y Severa l material s ar e use d i n the productio n o f aluminum . Bauxite , the principa l aluminu

mor e foun

d i n nature , contain s elevate d level s o f bot h Uranium-23 8 an

d Thorium-232 . Th e or e i s processe d a t the min e t o produc e alumina , the basi c fee d i n the aluminu mreductio n process . EPAreport s tha t atmospheri c emission s o f rado n fro mbauxit e mine s coul d excee d the R Q o n a continuou s basi s (EPA'8 0 p.4.5-9) . Twelv e domesti c firms produc e primaryaluminum . Almos t al l o f the bauxit e or e use d i n aluminu mproductio n i s imported . Onl yfive o f the twelve firms tha t ow

n primaryaluminu

mplant s als o ow

n domesti c plant s tha t produc e alumina . Thes e five firms ow n 7 3 percen t o f the curren t U.S . primaryalumina capacity . Currently , ther e ar e 3 2 operating primaryaluminu msmelter s i n the Unite d States . Wit hon e exception , al l o f the plant s ar e locate d i n rura l areas . Thes e smelter s releas e radionuclide s t o th e ai r fro mthe uraniu

man d thoriu mserie s a t extremel ylowlevels , typicall yi n a rang e fro mabou t IO" 6 curi e pe r da

yt o nearl yIO" 7 curi e pe r day , whic hi s wel l belo wthe lowes t adjuste d R Q valu e (EPA'84 , p.7.1-8) . Th e dat a o n emission s fro msmelters , howeve r ar e limite d t o smokestac k emission s an d do no t provid e a n adequat e basi s fo r judging emission s fro mothe r source s (e.g. , piles , lagoons) . Maintaining a conservative bia s therefore , thi s analysi s assume s tha t aluminu m smelter s coul d releas e a n R Q o f rado n o n a dail ybasi s an d woul d b e affecte d b ythe radionuclid e R Q adjustmen t rulemaking .

1AU.S . Environmenta l Protectio n Agency , NESHAP : Radionuclides : Backgroun

d Informatio n Fina l Rule . Volume I I (EP A520/1-84-022-2) , Offic e o f Radiatio n Programs , U.S . EPA , Octobe r 1984 , Chapte r 5 . A- 9P.9 6

Coppe r Industr

y Mos t firm s i n the coppe r industr yperformal l productio n processe s fro m mining throug

hrefining . Coppe r mill s an d smelter s ar e locate d nea r coppe r mines . O f the fiftee n operating primarysmelter s i n the Unite d States , al l ar e locate d i n rura l area s wit hlowpopulatio n densities . Ninet ypercen t o f the U.S . coppe r smelte r capacit yi s locate d i n Arizona , Montana , Nevada , Ne w Mexico , Texas , an

d Utah . Th e site s ten d t o b e larg e an

d generall ycontai n associate d mining an d milling operations . I n 1978 , 1. 5 millio n metri c ton s o f primarycoppe r wa s produced. 1 5 Modeling o f thes e facilitie s indicat e tha t atmospheri c emission s o f rado n fro

mcoppe r mines , o n average , coul d excee d a n RQ o n a dail ybasi s (EPA'8 0 p.4.5-9) . Th e dat a o n radionuclid e release s fro msmelter s ar e limite d t o smokestac k emission s an d d o no t provid e a n adequat e basi s fo r judging release s fro

mal l source s (smokestacks , piles , lagoons) . Give n tha t man yo f thes e facilitie s ar e co-located , thi s analysi s assume s tha t coppe r smelter s als o excee d the R Q fo r rado n an d mus t repor t unde r sectio n 103 . Zin c Industr

y Zin c usuall yi s foun d i n natur e a s a sulfid e or e calle d sphalterite . Th e ore s ar e processe d a t the min e t o for mconcentrate s typicall ycontaining 6 2 percen t zin c an

d 3 2 percen t sulfur . Base d o n a mode l facility , studie s indicat e tha t atmospheri c emission s o f rado n fro mzin c mines , o n average , coul d excee d the R Q o n a continuou s basi s (EPA'8 0 p.4.5- 9 an d EPA'8 4 p.7.3-3) . I n the pas t 1 0 years , U.S . deman d fo r zin c meta l ha s grow n slowly , bu t U.S . smelting capacit yha s decline d b ymor e tha n 5 0 percent . Plant s close d becaus e theywer e obsolete , coul d no t mee t environmenta l standards , o r coul d no t obtai n sufficien t concentrat e feed . Consequently , the meta l ha s replace d concentrat e a s the majo r for mo f import . Thi s situatio n i s expecte d t o continue . Ther e ar e five operating primaryzin c productio n facilitie s i n the Unite d States . Radionuclide s i n the uraniu man d thoriu

mserie s ar e release d fro mzin c smelter s a t extremel ylowlevels , excep t fo r Radon-222 . Emission s fro msmelter s ar e i n level s ranging from1.1x10" * curi e t o 1.5xl0" 6 curi e pe r day , al l wel l belo wthe fina l R Q values . Radon-22 2 i s release d a t a n expecte d leve l o f 0.00 1 curi e pe r da y(EPA'84 , p.7.3-4) . Becaus e informatio n o n release s vi a othe r pathway s i s no t available , thi s analysi s assume s tha t thes e facilitie s mee t o r excee d the R Q fo r a t leas t radon . Lead Industr

y Galen a i s th e principl e lead-bearing or e foun d i n nature . I t contain s smal l amount s o f copper , iron , zinc , an d othe r trac e element s (including radionuclides) . Lea d smelting involve s thre e processes : sintering , furnacing , an

d drossing . Sintering convert s the or e fro ma sulfid e t o a n

1 5 Schroeder , H.J. , Minera l Commodit yProfile s - - Copper . U.S . Departmen t o f th e Interior , Burea u o f Mines , Washington , D.C , 1979 . A-1 0P.9 7

oxid e o r sulfat e for man d prepare s the fee d material s fo r furnacing . Furnacing reduce s the oxid e fee d t o lead metal . Drossing reduce s the coppe r conten t o f the lead bullio n fro mthe furnace . Afte r drossing , additiona l refining steps , whic har e dictate d b yth e specifi c impuritie s presen t an d the intende d end-us e o f the product , ar e performe d t o produc e the purifie d lead metal .Ther e ar e five primarylead smelter s i n the Unite d States . Thre e facilitie s hav e integrate d smelter/refining complexes ; tw o facilitie s shi p thei r drosse d lead bullio n awa yfo r fina l processing . Thre e o f the smelter s ar e locate d i n Missour i an d proces s onl yore s fro mthe Missour i lead belt . Th e remaining smelter s ar e locate d i n Texa s an d Montana . Th e tw

o wester n smelter s ar e customsmelter s tha t ar e designe d t o handl e large r variation s i n or e compositio n tha n the Missour i smelters . Bot hdomesti c an d foreign ore s ar e smelte d a t the wester n plants . I n 1979 , tota l productio n fro mprimary lead smelter s wa s 594,00 0 tons. 1 6 Availabl e informatio n i s inadequat e t o determin e tota l release s fro m thes e facilities , s o thi s analysi s assume s tha t release s o f radionuclide s fro m thes e facilitie s coul d mee t o r excee d a n R Q o n a dail ybasis . Phosphat e Roc k Processing Plant s Mining o f phosphat e roc k i s the fift hlarges t mining industr yi n the Unite d State s i n term s o f quantit yo f materia l mined . Tota l 197 8 productio n wa s approximatel y57. 9 millio n metri c tons . Prio r t o 1983 , twent yfirms wer e operational , wit hplant s i n 3 1 locations . Th e te n larges t producer s controlle d abou t 8 4 percen t o f the capacity , wit hthe tw o larges t firm s controlling ove r 3 4 percen t 1 7 Phosphat e roc k plant s (generall ymin e an d beneficiatio n facilities ) mos t likel yregularl yexcee d the R Q fo r radon . Phosphat e or e drying and grinding plant s modele d b

yEP Aappea r t o releas e belo wthe R Q fo r mos t radionuclide s bu t coul d releas e a n R Q o f rado n (EPA'80 , p.4.3-1 1 - 4.3-15) . Give n tha t man y o f thes e facilitie s ar e co-locate d wit hphosphat e roc k plants , a conservativ e assumptio n i s t o assume tha t release s fro mthes e grinding an d drying plants , eithe r independentl yo r i n conjunctio n wit hmin e an d beneficiatio n operations , als o excee d the R Q fo r radon .

1 6 U.S . Departmen t o f Commerce , U.S . Industria l Outloo k fo r 20 0 Industrie s wit hProjection s fo r 1984 . Washington , D.C , 1980 .

1 7 U.S . Environmenta l Protectio n Agency , Phosphat e Roc k Plants . Background Informatio n fo r Propose d Standard s (EP A450/3-79-017) , Offic e o f Ai r Qualit yPlanning and Standards , 1979 , p . 7-5 . 

### A-l lP.9 8

Elementa l Phosphoru s Plant s Anothe r typ e o f phosphoru s plant s produce s elementa l phosphorus , whic h i s use d primaril yi n the productio n o f highgrad e phosphori c acid , phosphate

base d detergents , an d organi c chemicals . Almos t hal f o f the elementa l phosphoru s produce d domesticall yi s use d i n the productio n o f detergents . Meta l treatment , food s an d beverages , an

d chemical s ar e the othe r majo r en d use s fo r elementa l phosphorus . Approximatel y1 0 percen t o f the tota l U.S . marketabl e phosphat e roc k mine d i s use d fo r elementa l phosphoru s production . Four majo r corporation s operat e si xplant s i n the U.S . Th e tota l amoun t o f elementa l phosphoru s produce d i n 198 3 wa s approximatel y366,00 0 ton s (EPA'84 , p.6.3-1) . Thes e plant s excee d the RQ s fo r severa l radionuclide s o n a continuou s basis , althoughsome o f the releases , suc ha s o f Polonium-210 , ar e federall y permitte d (EPA'80 , p.4.3- 1 - 4.3-10) .
We t Proces s Fertilizer Plant s Mos t phosphat e roc k produce d i n the Unite d State s i s use d fo r the productio n o f high-analysi s agricultura l fertilizers . I n 1976 , 5 0 millio n metri c ton s o f phosphat e roc k wer e use d t o produc e 9 millo n metri c ton s o f phosphori c acid , the starting materia l fo r ammoniu mphosphat e an

d tripl e superphosphat e fertilizers . Phosphat e roc k i s no t a pur e compound , bu t a fluoroappitit e materia l containing mino r quantitie s o f fluorine , iron , aluminum , silica , an d uranium . We t proces s phosphori c aci d i s produce d b ymixing groun

d phosphat e roc k wit h 9 3 percen t sulfuri c aci d an d wate r i n a digester . I n the process , gypsu m (calciu msulfate ) i s produce d a s a byproduct . Following the reactio n i n a digester , the mixtur e o f phosphori c aci d an d gypsu mi s pumpe d t o a filte r whic hmechanicall yseparate s the particulat e gypsu mfro mthe phosphori c acid. 1 8 I n 1981 , Florid a an d Nort hCarolin a supplie d 8 6 percen t o f the domesti c an

d 3 3 percen t o f the world' s phosphat e requirements. 1 9 Concentration s o f natura l uraniu mand it s deca

yproduct s (includin g radium , the immediat e paren t o f radon ) i n phosphat e deposit s rang e fro mte n t o on e hundre d time s th e concentratio n o f uraniu mi n othe r natura l rock s an d soil s (4 9 FR 43914 , Octobe r 31 , 1984) . Mos t o f radium-22 6 containe d i n the phosphat e roc k i s transferre d t o the gypsu mbyproduct . Consequently , plan t operatio n emission s an d release s fro

mwast e gypsu

mpile s generall yexcee d the R Q fo r rado n a s modele d b yEP A(EPA'8 0 p.4.3-22 ) and , therefore , woul d b e

1 8 U.S . Environmenta l Protectio n Agency , Radiologica l Impac t Cause d b y Emission s o f Radionuclide s int o Ai r i n the Unite d States . PreliminaryReport , EPA520/7-79-006 , p . 6.2-1 .

1 9 Ibid . A-1 2P.9 9

subjec t t o the reporting requirement s unde r sectio n 103(f)(2) . A t leas t commente r agree d wit hthi s assessment. 2 0 on e

Iro nMine s an

dSmelter s Crud e iro n or e productio n i n the Unite d State s amounte d t o 21 5 millio n ton s i n 1975 , wit hope n pi t mine s accounting fo r 9 6 percen t o f the or e produced . Twent ystate s hav e significan t iro n or e deposit s bu t Michigan , Minnesota , an

d Wisconsi n produce d 8 5 percen t o f the or e mine d i n 1975 . Base d o n analysi s o f a representativ e mode l facility , studie s sugges t tha t atmospheri c emission s o f rado n fro miro n mines , o n average , excee d the R Q o n a continuou s basi s (EPA'8 0 p.4.5-9) . N o dat a o n emission s fro msmelter s ar e available . Maintaining a conservative bias , w e wil l assume tha t iro n smelter s als o excee d the R Q fo r rado n an d mus t repor t unde r sectio n 103 . Fluorospar Mine s Fluorospa r mine s ar e locate d i n Illinois , Kentucky , Montana , Nevada , Ne w Mexico , Texas , an

d Utah , bu t Hardi n County , Illinoi s account s fo r approximatel y7 5 percen t o f production . Th e averag e productio n pe r min e wa s 15,00 0 shor t ton s i n 197 5 an d tota l productio n amounte d t o approximatel y 375,00 0 tons . Emission s fro

mmining an

d milling operation s a t thes e facilitie s including thos e fro mtailing pile s do no t excee d the RQ s fo r relevan t radionuclide s (EPA'8 0 p.4.5-9) . Cla y Extractio

nFacilitie s Cla yi s produce d throughou t the unite d States , wit hGeorgia , Texas , an d Ohi o bein g the leading producers . I n 1975 , 1,31 7 mine s produce d approximatel y 49. 4 millio n tons , mostl yfro msurfac e mines . Emission s o f rado n fro mcla yextractio n facilities , a s modele d b yEPA , fal l jus t belo wthe dail yR Q (EPA'8 0 p.4.5-9) . Informatio n o n release s o f othe r radionuclide s an d othe r releas e pathway s ar e inadequat e o r unavailable . Becaus e the annua l productio n amoun t pe r min e i s smal l relativ e t o othe r minera l extractio n industrie s an d becaus e ther e i s littl e o r n o wast e associate d wit hthi s mining , i t appear s unlikel ytha t release s o f radionuclide s vi a othe r pathway s coul d mee t o r excee d a n R Q o n a regula r basis .

2 0 Mobi l Minin g an

d Mineral s Compan

ycommented : "Base d o n availabl e data , calculation s showtha t rado n emission s fromth e thre e phosphogypsu m storag e area s i n Pasadena an d on e storag e are a i n DePu e wil l al l excee d th e R Q fo r radon. " (Commente r 5 , p.11 , Commen t Respons e Documen t t o Radionuclid e Rule) . A-1 3P. 1

Limeston

e Extractio

nFacilitie s I n 1975 , mor e than 2,90 0 quarrie s an d undergroun

d mine s produce d approximatel y67,000,00 0 ton s o f limestone . Thes e quarrie s an d mine s ar e locate d throughou t the Unite d States , bu t the state s o f Illinois , Missouri , Pennsylvania , Ohio , an d Texa s accoun t fo r nearl y4 0 percen t o f thi s annua l production . Mine d limeston e i s the n crushe d int o mor e usabl e forms a t processing plants . Ther e i s n o wast e associate d wit hthi s processing . Emission s o f rado n fro mlimeston e extractio n facilities , a s modele d b y EPA , ar e belo wthe dail yR Q (EPA'8 0 p.4.5-9) . Informatio n o n release s o f othe r radionuclide s an d othe r releas e pathway s ar e inadequat e o r unavailable . Geotherma l Energ

y Plant s Dissolve d rado n ga s i n subterranean wate r ca n b e liberate d an d vente d t o the atmospher e i n geotherma l energ yplants . A t the tim e o f the EPAreport , onl yon e facilit ywa s operating i n the U.S . an d i t exceede d the R Q fo r Rado n (EPA'8 0 p.4-6A- l - 4.6A-7) . I t i s likel ytha t an yadditiona l plant s tha t hav e come on-lin e sinc e the n do also .
Natura l Ga s Extractio nan dProcessin

g Facilitie s I n 1987 , ove r 20,000,00 0 millio n cubi c fee t (MMcf ) o f natura l ga s wer e withdraw

n fro mthe groun

d b ynearl y250,00 0 natura l ga s well s an d b ysome fractio n o f the 620,00 0 oi l wells . O f the approximatel y17,000,00 0 MMc f o f markete d natura l ga s production , ove r a third wa s delivere d t o industria l facilitie s an

d abou t a quarte r t o residentia l consumers . Electri c utilit y consumers , althoughfewi n number , consume d approximatel y1 6 percen t o f the 198 7 volume . Natura l ga s i s produce d i n 3 2 state s bu t Texa s an d Louisian a accoun t fo r nearl y6 0 percen t o f annua l production , an d togethe r wit hAlask a an d Oklahoma , represen t ove r 7 7 percen t o f the gros s productio n fo r 1987 . Underground natura l ga s contain s quantitie s o f dissolve d rado n produce d b ythe natura l decayo f element s i n the surrounding rock . Whe n natura l ga s i s extracte d fro

mthe ground , the rado n ga s mayb e release d t o the environmen t throug hventing , flaring , o r spo t releases . Spo t release s tha t equa l o r excee d a n R Q ar e typicall yassociate d wit hmalfunction s an d woul d hav e t o b e reporte d unde r CERCL Asectio n 103(a) ; release s o f a n R Q o r mor e o f rado n fro m venting an

d flaring mayb e reporte d unde r sectio n 103(f)(2) . Concentration s o f rado n i n natura l ga s vary , bu t averag e value s ar e o n the orde r o f 10 0 pCi/lite r o f natura l gas. 2 1 A t thi s concentration , the quantit yo f natura l ga s containing a n R Q o f rado n i s calculate d a s follows :

2 1 Lette r fro

mChevro n Corporation , date d May , 13 , 1987 , Publi c Commen t t o Notic e o f Propose d Rulemaking , (Commente r 102RQ-RN-6-7) , p.6 . A-1 4P. 2

Quantit yo f natura l ga s - = R O o f rado n containing a n R Q o f rado n Concentratio n o f rado n i n natura l ga s 100.000.000.00 0 oC i 0.035 3 liter s 10 0 pCi/ 1 xcu . ft . 35,300,00 0 cu . ft . = 35. 3 MMc f (million cubi c feet ) Natura l ga s well s typicall yven t o r flar e les s than 1 percen t o f thei r production , suggesting tha t a wel l woul d hav e t o extrac t 3,53 0 MMc f pe r da yt o releas e a n R Q o f rado n t o the ai r throughroutin e venting an d flaring. 2 2 Thi s amoun t o f ga s exceed s the dail yproductio n o f existing wells ; therefore , natura l ga s well s ar e assume d no t t o b e affecte d b ythe radionuclid e R Q adjustmen t regulation . Th e productio n o f natura l ga s i s als o associate d wit hoi l production . Fo r some well s producing oil , i t i s uneconomica l t o recove r the associate d extractio n o f natura l gas . Consequently , fo r thes e facilities , al l o f the natura l ga s remove d fro mthe groun

d i s flared , usuall yunde r a stat e permitting process . Th e uppe r limi t fo r suc hflaring unde r permi t i s typicall yabou t 40,00 0 cu . ft . pe r day , severa l order s o f magnitud e belo wwha t woul d nee d t o b e flare d t o releas e a n R Q o f radon. 2 3 Therefore , oi l well s als o ar e assume d no t t o b e affecte d b ythe radionuclid e R Q adjustmen t regulation . Natura l ga s i s ofte n processe d befor e distributio n i n larg e plant s wit h considerabl e throughpu t quantities . Althoughga s processing plant s generall y contro l routin e venting an d flaring t o a greate r exten t tha n wells , i t i s reasonabl e t o assume tha t 1 percen t o f dail ythroughpu t fo r thes e facilitie s i s los t t o the environment . A s calculate d above , t o releas e a n R Q o f rado n woul d requir e a throughpu t o f 3,53 0 MMc f pe r day ; n o plan t i n the Unite d State s ha s suc ha capacity. 2 *
Gas-Fire

dBoiler s Larg e natura l ga s boiler s ar e use d t o produc e hea t an d proces s stea

mi n man ylarg e refining an d petrochemica l plants , i n municipa l facilities , an d i n utilit ypowe r plants . Th e larges t boiler s ar e use d t o generat e electricit y

2 2 Acros s the industry , venting and flaring account s fo r approximatel y 0. 6 percen t o f annua l production , althoughsome facilitie s mayhav e highe r rates . Energ

yInfor m 2 3 Communicatio n wit hTexa s Railroa d Commission , Oi l an d Ga s Division , January12 , 1989 .

2 4 Energ

yInformatio n Administration , Natura l Ga s Monthly . Augus t 1988 , EIA , Departmen t o f Energy , 1988 , p.5 . A-1 5P. 3

fo r publi c consumption . I n 1987 , electri c utilitie s consume d approximatel y 2.8 4 trillio n cubi c fee t o f natura l gas , roughl y1 6 percen t o f tota l consumptio n fo r tha t year . Th e amoun t o f natura l ga s consume d b yelectri c utilitie s ha s decline d ove r the las t eigh t years , wit hannua l consumptio n tending t o mov e i n the opposit e directio n o f oi l prices , reflecting the abilit yo f man

yo f thes e boiler s t o bur n eithe r product . Whe n natura l ga s i s burne d i n thes e boilers , the rado n dissolve d i n the ga s i s liberate d an d release d t o the environment . Th e quantit yrelease d wil l depen d o n the volume o f ga s burne d an d the concentratio n o f rado n i n the gas . A s calculate d above , a t a rado n concentratio n o f 10 0 pCi/lite r o f natura l gas , 35. 3 MMc f o f natura l ga s contain s a n R Q o f dissolve d rado n gas . I f al l the rado n i s release d upo n burning , the n thi s quantit yi s als o the amoun t o f ga s tha t need s t o b e burne d t o trigge r a reportabl e releas e unde r sectio n 103 . T o calculat e the numbe r o f gas-fire d boiler s likel yt o bur n thi s quantit yo f ga s o n a regula r basis , thi s quantit yo f natura l ga s i s converte d t o a measur e o f it s energ

ypotential . Acubi c foo t o f natura l ga s contain s approximatel y 1,00 3 Britis htherma l unit s (Btus ) o f energy , thus : 35. 3 MMc f = 35,300,00 0 cu . f t 35,300,00 0 cu . ft./da y x1.00 3 Btus / cu . ft . 35,400,000,00 0 Btus/day Approximatel y10,00 0 Btu s ar e require d t o generat e a kilowatt-hou r (kwh ) o f electricity , s o (35,400,000,00 0 Btus/day)/(10,00 0 Btus/kwh ) = 3,540,00 0 kwh/day
= 3,54 0 MWh/day Therefore , a gas-fire d boile r capabl e o f producing 3,54 0 MW-hou r pe r da ycoul d potentiall ybur n enoughnatura l ga s t o releas e a n R Q o f rado n t o the environmen t o n a dail ybasis . Thi s generating capacit ytranslate s int o a dail ycapacit yo f 147. 5 MW(3,54 0 MW-hour/2 4 hours/day) . According t o the Utilit yDat a Institut e Powe r Statistic s Dat a Base , ther e ar e approximatel y22 5 utilit ypowe r plant s wit hnatura l ga s boiler s o f thi s generating capacity . Thi s numbe r overestimate s the actua l numbe r o f powe r plant s burnin g enough natura l ga s t o releas e a n R Q o f rado n o n a regula r basi s fo r two reasons . Becaus e man

yo f thes e boiler s ca n bur n eithe r natura l ga s o r oi l wit hsligh t modifications , i t i s likel ytha t some fractio n o f thi s numbe r o f powe r plant s actuall ybur n oi l an d no t natura l gas . I n addition , becaus e o f the economic s o f electricit ygeneration , thes e plant s seldomoperat e a t 10 0 percen t capacity , a s assume d i n the calculatio n above . Unde r a mor e realisti c assumptio n o f approximatel y5 0 percen t utilization , onl yabou t 11 2 facilitie s ar e likel yt o releas e rado n regularl yi n a continuou s and stabl e manner .

A-1 6P. 4

SUMMAR YAN DCONCLUSIONS I n additio n t o the Nuclea r RegulatoryCommissio n o r Agreemen t Stat e licensees , an

d facilitie s controlle d b ythe Departmen t o f Energy , othe r facilitie s maypotentiall yreleas e radionuclide s a t level s tha t equa l o r excee d the fina l adjuste d radionuclid e RQs . Release s fro mthes e facilitie s tha t do no t hav e federa l permit s ar e expecte d t o b e continuou s an d stabl e i n quantit yan

d rat e and , therefore , ar e expecte d t o b e reporte d unde r the continuou s releas e reporting requirement s o f sectio n 103(f)(2) . Belo wi s a tabulate d summar

yo f the estimate d numbe r an d typ e o f thes e facilitie s potentiall yaffecte d b ythe radionuclid e R Q fina l adjustments :

Coa l mine s Unlicense d laboratorie s Low-energ

yaccelerator s Uraniu mmine s Aluminu msmelters/Bauxit e mine s Coppe r mine s an

d smelter s Zin c mines/smelter s Lea d smelters/refinerie s Elementa l phosphoru s plant s Phosphat e roc k processing plant s We t proces s fertilize r plant s Iro n mines/smelter s Fluorospa r mine s Cla yextractio n facilitie s Limeston e extractio n facilitie s Geotherma l energ

yplan t Oil/Ga s Extractio n Facilitie s Natura l Gas-fire d Boiler s SUBTOTAL : Coal-fire d utilit yboiler s Coal-fire d industria l boiler s TOTAL : Tota l Numbe r

o f Facilitie s Expecte d t o Equa l o r Excee d

an RQ o n a Continuou s Basi s

an d Numbe r 4,10 0 70 0 1,50 0 18 1 4 4 7 6 4 1 5 6 3 5 3 5 68 + 1 5 1,31 7 2,90 0 2 0 869,40 6 2.00 5 882,45 4 51 4 51.18 7 SOM E N O N O YE S YES . YE S YE S YE S YE S YE S YE S YE S N O NO NO YE S N O SOM E

YE S SOM E 36 3

18 1 4 4 7 6 4 1 5 6 3 5 3 5 6 8

2 0 11 2 98 6 51 4 1.21 0 956,13 3 2,71 0

A-1 7P. 5

APPENDI X B ESTIMAT E O F TH E NUMBE R O F FACILITIE S WIT H COAL-FIRE D BOILER S

EXPECTE D T O REPORT UNDE R SECTIO N103(f)(2 )

Alon g wit hoi l an

d ga s extractio n facilitie s an d gas-fire d boilers , coal-fire d boiler s compris e the overwhelming majorit yo f the facilitie s tha t potentiall yreleas e radionuclides . Larg e coal-fire d boiler s ar e use d t o generat e electricit yfo r publi c an d industria l us e an d t o provid e proces s steam , proces s ho t water , an d spac e heat . Boiler s use d i n the utilit y industr yar e designate d a s utilit yboilers , an d thos e use d t o generat e proces s steam , proces s ho t water , spac e heat , o r electricit yfo r in-hous e us e ar e designate d a s industria l boilers . A t thes e facilities , coa l i s store d frequentl yi n large , expose d piles . Th e size , configuration , an d characteristic s o f thes e pile s varydepending o n th e typ e o f facilit yan d the typ e o f boiler . I n addition , some characteristic s o f thes e pile s o f coa l an d wast e as hchang e ove r time a s materia l i s adde d t o o r remove d fro mthe piles , o r a s inventoryan d wast e managemen t practice s change . Consequently , i n orde r t o estimat e the numbe r o f thes e facilitie s tha t coul d b e affecte d bythe radionuclid e R Q adjustmen t rulemaking (i.e. , the numbe r o f utilit yan d industria l facilitie s tha t potentiall ycoul d releas e a n R Q o r mor e o f a radionuclid e froma coa l o r as h pile) , i t i s necessaryt o mak e certai n assumption s an d generalization s that , whil e characteristi c o f man yo f thes e facilities , mayno t b e appropriat e fo r the entir e univers e o f facilitie s wit hcoal-fire d boilers . Coa l i s primaril ystockpile d i n tw o basi c type s o f geometry : cone s an d rectangula r shapes . Conica l stockpile s ar e generall yassociate d wit hsmalle r pile s and smalle r boilers , suc ha s a t industria l facilities , wher e ground spac e ma yb e a t a premiu man d the quantit yo f coa l handle d o n a regula r basi s i s no t large . Fo r facilitie s consuming large r amount s o f coa l an d maintaining large r piles , coa l i s ofte n store d i n rectangula r shapes , facilitating th e us e o f machine s t o mov e an d handl e the coal . Thi s analysi s consider s onl y rectangula r pile s becaus e onl ylarge r facilitie s ar e expecte d t o releas e a n R Q o r mor e o f a radionuclid e o n a regula r basis . As hi s generate d whe n coa l i s burned . Th e amoun t o f as hgenerate d depend s o n the minera l conten t o f the coa l burne d an d the typ e o f boile r used . Some o f the as hgenerate d i s emitte d wit hth e boile r flu e gase s a s fl yash , whil e heavie r bottomas hremain s a t the bas e o f th e boiler . Becaus e o f governmen t regulation s o n particulat e emissions , significan t percentage s o f fl yas har e ofte n recovere d an d dispose d o f wit hthe bottomash . Wast e as h generall yi s landfllle d o r otherwis e dispose d o f a t th e facilit ysit e i n larg e pile s o r lagoons , althoughsom e i s use d i n commercia l application s (e.g. , cemen t substitute) . Thi s analysi s assume s tha t thes e wast e as hpile s ar e rectangularl yshaped . Coa l contain s minera l matte r including trac e quantitie s o f naturall y occurring radionuclide s tha t th e Atomi c Energ yAc t doe s no t giv e th e Nuclea r RegulatoryCommissio n (o r Agreemen t States ) th e authorit yt o regulate .P. 6

Uranium-23 8 an

d Thorium-23 2 an

d thei r deca

yproduct s ar e the principa l radionuclide s foun

d i n significan t quantitie s i n coal. 1 Th e radioactivit y conten t o f coa l varie s ove r two order s o f magnitude , bu t mos t value s fal l i n the rang e o f 0. 1 t o 1.3 2 pCi/ g fo r th e Uranium-23 8 serie s an d slightl yles s fo r th e Thorium-23 2 series. 2 Base d o n informatio n use d b yEP Ai n th e developmen t o f airborn e emissio n standards , thi s analysi s use s reporte d mea n concentration s o f 0.4 3 pCi/ g fo r the Uranium-23 8 serie s an d 0.3 5 pCi/ g fo r the Thorium-23 2 serie s (EPA'84 , p.4.0-2) . I n stable , undisturbe d formation s ove r long period s o f time , member s o f a radioactiv e deca yserie s achieve secula r equilibriu

mwit heac hother , meaning tha t the daughte r radionuclide s ar e foun d i n the sam

e concentratio n a s the parent . Radionuclide s i n coa l hav e bee n foun d t o b e i n secula r equilibrium ; therefore , the above concentratio n figure s fo r Uranium-23 8 an

d Thorium-23 2 ar e assume d t o b e vali d fo r al l member s o f the respectiv e series . Radionuclid e release s fromthes e facilitie s mayoccur vi a numerou s releas e pathways . Ther e ar e mor e tha n 51,00 0 industria l boiler s and 1,30 0 utilit yboilers . Some facilitie s hav e multipl e boilers ; therefore , some smalle r numbe r o f facilitie s coul d potentiall yb e affecte d b ythe radionuclid e R Q adjustmen t rule . I n orde r t o deriv e a reasonabl e estimat e o f the numbe r o f thes e facilitie s potentiall yaffecte d byth e fina l regulation , five pathway s b ywhic hradionuclide s ma yb e release d ar e evaluated : (1 ) smokestac k emissions ; (2 ) dumping o f radionuclide-lade n material s ont o stockpile s o r wastepiles ; (3 ) release s o f rado n ga s t o ai r fro mcoa l stockpile s an d wast e as hpile s a t the facility ; (4 ) release s o f radionuclid e particulate s t o ai r fromcoa l an

d as hpiles ; and (5 ) release s o f radionuclide s fro mcoa l an

d as h pile s t o groundwater . Eac ho f thes e releas e pathway s i s considere d belo wt o determin e the likel ynumbe r o f facilitie s tha t coul d releas e a n R Q o r mor e o f radionuclides . Smokestac k Emission s EPAbackground document s supporting th e developmen t o f airborn e emissio n standard s indicat e tha t dail yemission s froma smokestac k a t a "model " coal

fire d boile r ar e typicall ysubstantiall ybelo wth e fina l adjuste d RQ s (EPA'84 , chapte r 4) . Smokestac k emission s shoul d no t b e sufficientl ylarg e t o trigge r th e notificatio n requirement s unde r CERCLA . Smokestac k emissions , however , ar e no t federall ypermitte d release s becaus e i n promulgating radionuclid e emissio n standard s unde r th e Nationa l Emissio n Standard s fo r Hazardou s Ai r Pollutant s (NESHAP) , EP Adi d no t establis hstandard s fo r radionuclid e emission s fro

mcoal-fire d boiler s (5 0 FR 5190 : Februar y6 , 1985) . I f a

1 U.S . Environmenta l Protectio n Agency , Radionuclide s Background Informatio n Documen t fo r Fina l Rules . Volume II , Octobe r 1984 , p . 4.0-1 . (EPA'84) . 2 Thi s rang e encompasse s 9 0 percen t o f the coal s i n a n EPAsurvey (EPA'84 , p.4.0- 2 - 4.0-3) . Anothe r evaluatio n o f ove r 90 0 coa l sample s reporte d averag e value s o f Uranium-23 8 an d Thorium-23 2 o f 0. 6 and 0. 5 pCi/ g o f coa l respectively . Beck , Harol d L . an d Kevi n M . Miller , Some Radiologica l Aspect s o f Coa l Combustion , lette r transmitta l o f paper , January1989 . B- 2P. 7

facilit yi s substantiall ylarge r tha n the "model " facilitie s analyze d i n the NESHAP documen t and , therefore , coul d potentiall yreleas e mor e tha n a n R Q o f a radionuclide , thos e release s woul d b e reportabl e unde r CERCLA . Fo r purpose s o f thi s analysis , i t i s assume d tha t smokestac k emission s fromcoal-fire d boiler s woul d b e belo wthe fina l adjuste d radionuclid e RQs . ' Dumping o f Coa l an

d As h Th e dumping o f coa l o r as houtsid e a facilit yi n a non-enclose d sit e represent s a radionuclid e releas e t o the environment . Th e siz e o f the coa l o r as hload being dumpe d determine s whethe r the releas e equal s o r exceed s the RQ . Presente d belo wi s a n estimat e o f the numbe r o f facilitie s wit hcoal-fire d boiler s tha t coul d b e affecte d b ythe lowe r radionuclid e RQ s simpl ya s a resul t o f dumping coa l o r as houtsid e thei r facilities . T o estimat e the quantit yo f coa l tha t contain s a n R Q o r mor e o f radionuclides , i t i s assume d tha t al l radionuclide s o f a particula r serie s (e.g. , Uranium-23 8 an d it s daughters ) ar e i n secula r equilibriu m(i.e. , ar e foun d i n the same concentration ) i n the transporte d coal . Becaus e al l membe r radionuclide s o f a serie s ar e presen t i n th e coal , the relativ e contributio n o f eac htoward meeting o r exceeding a n R Q mus t b e assesse d usin g the mixtur e rule . Specifically , i t i s necessaryt o calculate , fo r eac hradionuclid e released , the rati o o f the quantit yrelease d i n curie s t o the appropriat e RQ . I f the su

mo f the ratio s fo r al l radionuclide s i s les s tha n one , the releas e nee d no t b e reported . I f the su mequal s o r exceed s one , the releas e mus t b e reported . Mathematically , th e mixtur e rul e ca n b e expressed : (1 ) Percentag e o f a n V ^ Quantit yrelease d (pCi )

R Q release d /

_R Q (P ci ) wher e n i s the numbe r o f radionuclide s i n the mixtur e Th e dumping o f coa l constitute s a releas e o f member s o f the Uranium-23 8 serie s and th e Thorium-23 2 series . T o determin e th e amoun t o f coa l containing a n R Q o f radionuclides , th e left-hand sid e o f equatio n (1 ) i s se t equa l t o one , an d the equatio n i s solve d fo r the "quantit yreleased. " Th e quantit yo f radionuclid e released , i n turn , depend s o n th e concentratio n o f the radionuclide s i n the coa l and th e quantit yo f coa l dumped . Becaus e i t i s assume d tha t radionuclide s ar e i n secula r equilibriu mi n coal , the concentration s o f th e daughte r radionuclide s presen t i n th e coa l ar e known t o equa l the concentratio n o f th e parent . I n addition , the RQ s fo r natura l Uranium-23 8 an

d natura l Thorium-23 2 i n secula r equilibriu mwit hthei r daughter s ar e 0.05 2 C i an d 0.01 1 Ci , respectively . Thus , the concentratio n value s o f the radionuclide s an d the unknow

n quantit yo f coa l (Q ) ca n b e substitute d fo r the "quantit yreleased " i n equatio n (1) . Th e calculatio n reduces , therefore , t o two terms :

B- 3P. 8

(2 ) 1 R Q - (0.4 3 pCi/ g * 1 4 members ) * 0 + (0.3 5 pCi/ g * 1 1 members ) * 0 52,000,000,00 0 pC i 11,000,000,00 0 pC i Uranium-23 8 serie s Thorium-23 2 serie s wher e Q i s the quantit yo f coa l dumpe d i n gram s Simplifying terms an d solving : 1 R Q - (1.1 6 * 10" 1 0 pCi/ g + 3.5 0 * 10" 1 0 pCi/g ) * Q 1 R Q = 4.6 6 xIO" 1 0 pCi/ g * Q Q = 2,150,000,00 0 g Thi s quantit yca n b e converte d t o a mor e familia r uni t o f measurement : Q - (2,150,000,00 0 g)/(908,00 0 g/ton )

- 2,36 0 ton s Larg e quantitie s o f coa l ar e ofte n transporte d b ytrai n i n 100-to n boxcars . Th e quantit ycalculate d abov e represent s approximatel y2 4 boxcars , whic hi s a plausibl e amoun t t o b e delivere d i n a 24-hou r period . Suc ha delivery , i f dumpe d o n the ground , woul d constitut e a releas e o f a n R Q o f radionuclide s unde r th e fina l adjuste d radionuclid e RQs . Becaus e the economic s o f coa l transpor t ar e veryfacilit yspecific , littl e generalizatio n ca n b e mad e abou t the frequencyan

d siz e o f coa l shipment s tha t i s relevan t t o mor e tha n a smal l numbe r o f facilities . I f weekl ydeliverie s ar e assumed , however , the n a facilit yreceiving load s o f 2,36 0 ton s woul d consume 122,70 0 ton s o f coa l annuall y(5 2 deliverie s * 2,36 0 ton s pe r delivery) . A s a rul e o f thumb , a 10 0 MWcoal-fire d utilit yboile r consume s approximatel y275,00 0 ton s o f coa l annually. 3 Thi s relationshi p betwee n

3 Thi s rul e o f thum bi s approximat e an d i s base d o n th e assumptio n tha t the boile r i s use d a t 7 0 percen t utilization ; tha t 10,00 0 Britis htherma l unit s (Btus ) ar e necessaryt o generat e a kilowatt-hou r (Kwh ) o f electricity ; an d tha t a to n o f coa l contain s 22,000,00 0 Btu s o f energy . T o determin e the amoun t o f coa l consume d annually , th e amoun t o f electricit yproduce d i s calculate d first : Electricit yproduce d - Boile r siz e * hour s pe r yea r * capacit yutilizatio n

= 10 0 MW* 1.00 0 Kw* 8.76 0 h r * .7 0

M Wyea r

- 613,200,00 0 Kwh/yea r Th e amoun t o f coa l necessaryt o generat e thi s quantit yo f electricit yi s no w calculated : Amoun t o f coa l - Electricit yproduce d * therma l energ yneede d t o produc e consume d a uni t o f electricit y* therma l energ yavailabl e i n coa l B- 4P. 9

generating capacit yan d annua l coa l consumptio n hold s ove r a reasonabl ybroa d rang e o f boile r sizes , suggesting tha t eac hmegawat t (MW ) o f capacit yrequire s abou t 2,75 0 ton s o f coa l fo r a boile r operating a t averag e utilization . Applying thi s rati o t o th e amoun t o f annua l coa l consumptio n calculate d i n equatio n (2 ) provide s a n estimat e o f the siz e o f the boile r tha t a facilit y woul d hav e t o hav e t o b e likel yt o equa l o r excee d a n R Q o f radionuclide s o n a regula r basis . Th e boile r siz e implie d b ya n annua l coa l consumptio n o f 122,70 0 ton s is : (3 ) Boile r siz e Annua l coa l consumptio n 2,75 0 tons/yea r pe r M W Boile r siz e 122.70 0 tons/yea r 2,75 0 tons/year/M

W 4 5 MW Therefore , a facilit ywit ha coal-fire d boile r large r tha n 4 5 MWtha t receive s weekl ydeliverie s o f coa l i s expecte d t o releas e a n R Q o r mor e o f radionuclide s during suc hdeliveries . Th e as hproduce d whe n coa l i s burne d i s als o dispose d o f o n a regula r basis , usuall yint o a n as hlagoo n o r ont o a n as hpile . Dumping o f as h represent s a releas e t o the environment . Coal , o n average , ha s abou t a 10

- percen t as hconten t byweight , suggesting tha t the amoun t o f as hgenerate d i s approximatel yone-tent ho f th e amoun t o f coa l burned. * T o b e conservative , i t i s assume d tha t al l o f th e radionuclide s i n the coa l remai n i n th e as h(i.e. , non e ar e release d t o ai r o r destroye d i n the combustio n process) , s o tha t th e concentration s o f radionuclide s i n the as har e te n time s tha t o f th e rawcoal . Thus , the concentration s fo r the Uranium-23 8 an d Thorium-23 2 serie s i n secula r equilibriu

mar e 4. 3 pCi/ g an

d 3. 5 pCi/ g respectively . I n addition , i t i s assume d tha t al l o f th e as hi s recovere d an d dumped .

- 613.200.00 0 Kwh* 10.00 0 Btu s *

yea r Kw

h

= 278,80 0 tons/yea r to n o f coa l 22,000,00 0 Btu s

Fo r thi s analysis , a rounde d valu e o f 275,00 0 ton s pe r yea r i s used .
* EPA'88 , Appendi xB report s a n averag e as hconten t o f 10. 5 percen t fo r a variet yo f U.S . coals , wit ha rang e fro m6. 0 t o 18. 1 percent . Thi s averag e figur e ha s bee n rounde d t o 1 0 percent . Fo r the sak e o f simplicity , al l as h wil l b e considere d collectively ; n o attemp t wil l b e mad e t o differentiat e betwee n quantitie s o f botto mas hand fl yash . Thi s assumptio n eliminate s th e nee d t o accoun t fo r th e variou s distribution s o f as hdepending o n boile r typ e an d i s reasonabl e becaus e mos t boiler s employparticulat e contro l system s tha t captur e larg e percentage s o f th e fl yash . Mos t o f thi s fl yas hi s dispose d o f i n a manne r simila r t o botto mash . B- 5P.1 0

Becaus e the concentratio n o f radionuclide s i n th e as hi s assume d t o b e te n time s tha t o f coal , the amoun t o f as hcontaining a n R Q o f radionuclide s i s assume d t o b e one-tent htha t o f coal , o r 23 6 ton s o f ash . Assuming tha t the boile r dump s it s bottomas ho n a dail ybasis , the siz e boile r suggeste d b y suc hcharacteristic s ca n b e calculate d again . Boiler s do no t necessaril y operat e continuously ; base d o n a capacit yutilizatio n o f 7 0 percent , thi s analysi s assume s tha t the boile r operate s 25 5 day s pe r year. 5 Two hundred

thirty

- si xton s o f as hdumpe d pe r da ysuggest s a n annua l productio n o f bottom as ho f 60,20 0 ton s (23 6 ton s * 25 5 days/yr) . I f the as hconten t o f the coa l burne d i s 1 0 percent , thi s amoun t o f as hcorrespond s t o a n annua l coa l consumptio n o f 602,00 0 tons . Substituting thes e value s int o equatio n (3 ) t o determin e the siz e o f the boiler : (3 ) Boile r siz e - - Annua l coa l consumptio n 2,75 0 tons/yea r pe r MW Boile r siz e = 602.00 0 tons/yea r 2,75 0 tons/year/M

W 22 0 MW An yfacilit ywhos e boile r siz e exceed s 22 0 MW , therefore , i s likel yt o mee t o r excee d th e R Q fo r a mixtur e o f natura l Uranium-23 8 an d Thorium-23 2 i n secula r equilibriu

meac htime i t dump s as hont o it s wastepil e o r int o a n as hlagoon . Thes e same facilitie s hav e a boile r capacit ylarg e enough(i.e. , greate r tha n 4 5 MW ) tha t theyar e expecte d t o equa l o r excee d a n R Q wheneve r theyreceiv e a coa l delivery . Dumping o f coa l ash , therefore , i s no t the critica l activit y tha t woul d caus e a coal-fire d boile r facilit yt o b e affecte d bythe radionuclid e R Q adjustmen t rulemaking . A s show n i n Exhibi t B-l , th e majorit yo f powe r plant s wit hcoal-fire d boiler s hav e generating capacitie s large r tha n 4 5 MW . Becaus e th e siz e distributio n o f plant s smalle r tha n 10 0 MWi s no t known , i t i s conservativel y assume d tha t al l o f thes e facilitie s ar e large r tha n 4 5 M Wand , therefore , ar e expecte d t o mee t o r excee d a n R Q during routin e coa l deliveries . I n addition , ther e ar e 42 3 industria l boiler s large r tha n 7 5 M Wand some numbe r o f th e 1,18 1 boiler s i n the siz e rang e o f 30-7 5 MWtha t mee t th e 4 5 M Wcriterion , a s

5 Utilit yplant s operat e a t approximatel y7 0 percen t o f capacit yove r the cours e o f a year , althoughther e i s considerabl e variatio n depending o n th e typ e o f plan t (EPA'84 , p.4.1-1) . Plant s providing baseloa d generatio n typicall yshowutilizatio n rate s around 9 0 percent . Othe r plant s providing electricit yonl yduring period s o f pea k deman d hav e muc hlowe r utilizatio n rates . Th e 7 0 percen t figur e use d her e i s a n averag e fo r al l utilit yplants . Industria l boiler s generall yhav e lowe r utilizatio n rates . T o b e conservative , i t i s assume d tha t wheneve r a plan t runs , it s run s a t 10 0 percen t o f capacit yand , therefore , produce s th e mos t as hpossibl e i n a 24

- hou r period . Autilit yboile r use d a t thi s rat e woul d operat e 25 5 day s pe r yea r (36 5 * 0.7) . B- 6TYP E M WATE R TUB E

FIR E TUB E 

### I CAST IRO

N

• TOTA

L EXHIBI T B- l DISTRIBUTIO N

B YCAPACIT YO F COAL-FIRE DPOWE RPLANT S

CAPACIT Y (MW ) NUMBE R <10 0 15 1 10 1 - 50 0 15 9 50 1 - 1,00 0 8 9 1,00 1 - 2,00 0 9 2 >2.00 1 2 3 TOTAL : 51 4 Thes e plant s represen t 137 8 generatin g unit s (i.e. , boiler , turbine , an d generator) . Source : Utilit yDat a Institut e Powe r Statistic s Dat a Bas e

EXHIBI T B- 2 DISTRIBUTIO N

B YCAPACIT YAN DTYP E O F COAL-FIRE DINDUSTRIA L BOILER S

CAPACIT Y 0- 3 M W3-1 5 M W15-3 0 M W30-7 5 M WOVE R 7 5 M W 68 3 2,30 9 1,29 0 1,18 1 42 3 8,11 2 1,22 4 35,96 5
44,76 0 3,53 3 1,29 0 1,18 1 42 3

Source : EPA'8 4

B- 7 TOTA L 5,88 6 9,33 6 35,96 5
51,18 7 p.1 1

!

ishow

n i n Exhibi t B-2. 6 Assuming a unifor mdistributio n b

ysiz e o f boiler s i n the 30-7 5 MWrange , a n additiona l 78 7 boiler s fromthi s grou p als o hav e a generating capacit yo f 4 5 MWo r mor e (30/4 5 o r 0.66 7 * 1,181) . Therefore , i f eac hindustria l boile r large r tha n 4 5 MWrepresent s a uniqu e facility , the tota l numbe r o f utilit yan d industria l boile r facilitie s likel y t o releas e an R Q o r mor e o f radionuclide s during coa l deliverie s i s 1,72 4 (51 4 utilit yboile r facilitie s + 42 3 industria l boiler s large r than 7 5 M W+ 78 7 industria l boiler s betwee n 4 5 M Wan d 7 5 MW) . Rado n Release s fro

mPile s Release s o f rado n ga s fro mcoa l an

d ais hpile s ten

d t o occur a t lo wrate s ove r broa d areas , a s naturall yoccurring radiu mdecay s an

d the resulting rado n ga s escape s t o air . Althoughthe amoun t release d pe r uni t o f are a i s typicall yquit e low , aggregatio n o f thes e release s ove r larg e area s mayequa l o r excee d the R Q fo r radon . Al l othe r thing s bein g equal , the quantit yo f radionuclid e release d i s essentiall ya functio n o f the siz e an d compositio n (i.e. , coa l type ) o f the pile s o f rawan d wast e material s kep t a t the facility . Becaus e rado n ga s diffuse s upward , i t i s assume d t o b e release d t o th e atmospher e i n onl yon e directio n an d the amoun t release d i s essentiall ya functio n o f the expose d surfac e are a o f th e reserv e coa l pil e an d the wast e as hpile , no t the volume o f the piles. 7 Hence , the calculation s belo war e base d o n surfac e area , and th e result s ar e late r converte d int o volume measurement s base d o n typica l characteristic s o f coa l and as hpiles . Th e relationshi p betwee n th e amoun t o f rado n release d and th e siz e o f the pile s a t a facilit yca n b e state d mathematicall ya s follows: 8

6 Thi s coun t doe s no t includ e an yindustria l boiler s tha t hav e come on lin e sinc e thes e dat a wer e gathered .

7 Thi s simplificatio n hold s fo r pile s o f the thicknes s considere d here . Fo r shallo wpiles , al l o f the rado n ga s ma yb e assume d t o migrat e upwar d throughthe pil e an d escap e t o th e atmosphere . Fo r deepe r piles , some fractio n o f the rado n ga s i s unlikel yt o hav e migrate d upwar d throug hth e entir e pil e befor e decaying int o it s daughter s (th e half-lif e o f Radon-22 2 i s 3.8 2 days) . Thi s analysi s assume s tha t al l o f the rado n ga s create d i n a pil e escapes .

8 Thi s analysi s assume s tha t facilitie s maintai n bot ha coa l stockpil e an d a n as hwastepile . Thi s i s onl ytru e fo r a minorit yo f facilities . Abou t 4 0 percen t o f th e facilitie s landfil l th e as ha t the facility , o r transpor t i t off-sit e t o landfills . Thes e landfill s ar e ofte n covere d bya dept ho f soil , effectivel ylimiting rado n releases , ofte n t o norma l background levels . A n additiona l 3 5 percen t dispos e o f some o r al l wast e as hbyplacing i t i n larg e containmen t lagoon s tha t reduc e rado n emission s t o air . U.S . Environmenta l Protectio n Agency , Repor t t o Congress : Waste s fromthe Combustio n o f Coa l b y Electri c Utilit yPowe r Plant s (EP A530-SW-88-002) , Offic e o f Soli d Wast e an d Emergenc yResponse , EPA , February1988 , p.4-22 . (EPA'88) . B- 8P.1 3

Amoun t o f rado n ([Are a o f coa l stockpile ] * [amoun t o f rado n (4 ) release d pe r da y- » release d pe r da

ype r uni t area] ) + ([are a o f as hpile ] * [amoun t o f rado n release d pe r da ype r uni t area]) . Thi s equatio n simpl ystate s tha t the amoun t o f rado n release d pe r dayb ya facilit yi s the su

mo f the amount s release d b ythe individua l pile s a t the facility , which , i n turn , depend s o n the siz e o f the pile s an d the amoun t o f rado n release d pe r da ype r uni t area . Facilitie s normall ymaintai n regula r reserv e quantitie s o f coa l whic hi s burne d ove r tim

e int o wast e ash . I t i s possible , therefore , t o establis ha relationshi p betwee n the siz e o f thes e two pile s unde r consideration . Mos t utilit yboiler s maintai n approximatel ya 92-da yreserve o f coa l a t the facility , whil e industria l boiler s averag e approximatel ya 37-da yreserve. 9 Furthermore , a s note d above , coal , o n average , ha s abou t a 1 0 percen t as h conten t b

yweight . Fo r a typica l utilit yboile r consuming a quantit y(X ) o f coa l pe r year , therefore , the siz e o f it s reserv e coa l pil e (R ) is : (5 ) R = X * (92/365 ) o r R - X/ 4 Becaus e bot hquantitie s i n equatio n (5 ) ar e coal , the relationshi p establishe d i s equall yvali d i f the uni t o f measuremen t i s weigh t o r volume . Th e weigh t o f coa l as hgenerate d eac hyea r i s 1 0 percen t tha t o f the coa l burne d (i.e. , coa l ha s a 1 0 percen t as hcontent) : (6 ) V

- (0.1 0 o f Z ) o r W- X/1 0 Th e volume siz e o f th e wast e as hpil e (W ) generate d eac hyea r i s a functio n o f the amoun t o f coa l burne d an d the rati o o f the densitie s o f coa l t o ash . Ato n o f loos e bul k coa l occupie s approximatel y4 2 cubi c feet , equa l t o a bul k densit yo f abou t 4 8 lbs/cu . ft. 1 0 Th e bul k densit yo f drycoa l as h varie s depending o n the typ e o f coal , typ e o f boiler , an d kind o f as h(i.e. , fl yo r bottom ) bu t i s approximatel y7 0 t o 9 0 lbs./cu . ft. 1 1 Fo r thi s analysis , a figur e o f 7 2 lbs/cu . ft . i s use d a s a n estimate d densit yo f coa l ash . Usin g th e rati o o f th e densitie s o f coa l and coa l ash , the relationshi p betwee n b

ythe weigh t o f th e two pile s ca n b e translate d int o a relationshi p base d o n the volume o f th e two piles .

9 U.S . Environmenta l Protectio n Agency , Sourc e Assessment : Coa l Storag e Pile s (EP

A600/2-78-004) , EPA , May1978 , p.4 . (EPA'78) . 1 0 U.S . Departmen t o f Energy , Coa l Data : AReference . Energ y Informatio n Administration , DOE , Marc h1987 .

1 1 EPA'88 , p . 3-1 4 and America n Coa l As hAssociation , persona l communication , January1989 . Regardles s o f th e figur e selecte d fromthi s range , as hi s mor e dens e tha n coa l and , therefore , occupie s les s space . B- 9P.1 4

(7 ) Volum e o f as hproduce d - Weigh t o f as hproduce d * rati o o f the densitie s annuall y(expresse d a s annuall y(expresse d a s o f coa l an d as h a functio n o f th e a functio n o f th e volum e o f coal ) weigh t o f coal ) W(volume ) - W (weight ) * (48/72 ) W- (X/10 ) * (48/72 ) o r W - X/1 5 Combining equation s (5 ) an d (7) : (8 ) W = 4 R/1 5 o r W = 0.26 7 R Fo r eac hyear , therefore , the amoun t o f wast e as hgenerate d pe r yea r i s approximatel yequa l t o 2 7 percen t o f the amoun t o f coa l i n the coa l reserv e pile . Th e siz e o f the inventor yo f reserv e coa l (R ) i s assume d t o remai n relativel yconstan t ove r time , however , the siz e o f the wastepil e o f as h(A ) grow s ove r time a s mor e as hi s dumped . Thi s analysi s assume s tha t the wast e as hpil e represent s 2 0 year s o f operation; 1 2 thus , (9 ) A- 2 0 * 0.26 7 R o r A- 5. 3 R Repeating thi s calculatio n fo r industria l boilers , whic hmaintai n a smalle r reserv e pil e o f coa l (37/36 5 o r 0.10) , produce s the following relationship : (10 ) R = X * (37/365 ) o r R = X/1 0 (7 ) W - (X/10 ) * (48/72 ) o r W - X/1 5 Combining equation s (7 ) an d (10) : (11 ) W = 1 0 R/1 5 o r W - 0.66 7 R Consequently , fo r a n industria l facilit ywit h2 0 year s o f accumulate d wast e ash , th e relationshi p betwee n th e reserv e coa l pil e (R ) an d the cumulativ e as h pil e (A ) is : (12 ) A= 2 0 * 0.66 7 R o r A- 13. 3 R Thes e equation s relat e th e siz e (i.e. , volume ) o f the pile s o f coa l an d as hfo r a representativ e facility . A s note d above , the relevan t dimensio n fo r considering th e amoun t o f rado n release d i s th e expose d surfac e are a through whic hthe rado n ga s ma ydiffus e t o the atmosphere . I f i t i s assume d tha t the

1 2 Th e averag e ag e o f utilit yboiler s i n th e Unite d State s i s approximatel y2 0 years . EPA'84 , p.4.1-3 . B-1 0P.1 5

pile s hav e the same geometryan d height , the n thes e same equation s essentiall y describ e the relationshi p betwee n the surfac e are a o f the tw o piles. 1 3 Th e amoun t o f rado n release d pe r uni t are a pe r daydepend s o n tw o factors : (1 ) the amoun t o f radiu mi n the coa l o r ash 1 * and (2 ) the rat e a t whic hrado n escape s fro mth e pile , the so-calle d emanatio n rate . I n addition , two conversio n constant s ar e neede d t o ensur e tha t the unit s o n bot hside s o f the equatio n ar e consisten t an d yiel d a resul t expresse d i n acres . Th e ter m representing the amoun t o f rado n release d pe r uni t are a pe r day , thus , appear s a s follows : (13 ) Quantit yo f rado n = [(Emanation rate ) * (numbe r o f seconds/day ) *

release d (numbe r o f squar e meters/acre ) * (radiu m concentratio n i n coa l o r ash) ] Ther e ar e 86,40 0 second s i n a da y(6 0 * 6 0 * 24 ) an d 4,04 7 squar e meter s i n a n acre . Substituting thes e value s int o equatio n (13) : Quantit yo f rado n - = [Emanation rat e (pCi/sqm-se c pe r pC i o f radiu m release d i n a gra mo f coa l o r ash ) * 86,40 0 (sec/day ) * 404 7 (sqm/acre ) * radiu

mconcentratio n i n coa l o r as h (pC i pe r gram) ] Consolidating thes e term s produce s a singl e ter mo f the amoun t o f rado n released , expresse d i n pC i pe r acr e pe r day : (14 ) Quantit yo f rado n - [ Emanatio n rat e * radiu mconcentratio n * release d 349,660,80 0 ] (pCi/day-acre ) Radiu mi s a deca

ydaughte r o f Uranium-23 8 an d i s foun

d i n bul k coa l i n secula r equilibriu

mwit hit s parent . Consequently , the concentratio n valu e o f Uranium-23 8 o f 0.4 3 pCi/ g o f coa l i s assume d t o b e the concentratio n valu e fo r radiu mi n coal . I t i s assume d als o tha t al l o f the radiu mpresen t i n the coa l i s retaine d i n th e ash ; therefore , the concentratio n i n as hi s te n time s tha t o f coa l o r 4. 3 pCi/ g o f ash .

1 3 Thi s analysi s assume s tha t the pile s ar e roughl yrectangula r i n shap e an d 2 0 fee t deep (EPA 1 78 , p.2) . Extensio n o f the volum e relationshi p t o expose d surfac e are a onl yhold s tru e i f the surfac e are a along th e side s o f thes e pile s i s ignore d an d onl ythe "top " portio n o f the pile s i s considered . Thi s seem s a reasonabl e assumptio n fo r two reasons : (1 ) man yo f thes e pile s ar e place d intentionall yi n shallowpit s o r depression s t o reduc e particulat e emission s t o ai r cause d bywind and , thus , d o no t hav e expose d sides , an d (2 ) the shallo wdept ho f thes e pile s relativ e t o thei r lengt hand widt hsuggest s tha t relativel ylittl e rado n escape s throug hdiffusio n sideways . Ignoring th e possibilit yo f rado n escaping throughexpose d side s result s i n approximatel y a n 1 1 percen t distortio n i n th e relationshi p o f the surfac e area s o f thes e pile s ove r i f th e sid e surfac e area s wer e included .

1 4 Radium-22 6 decay s t o Radon-222 ; thus , th e amoun t o f rado n presen t i n a pil e varie s wit hth e amoun t o f radiu mpresent . 

### B-l lP.1 6

Th e emanatio n rat e o f rado n varie s according t o specifi c circumstances , suc ha s atmospheri c pressur e an d humidity ; however , the emanatio n rat e o f rado n fro

mcoa l an

d as hi s typicall yles s tha n tha t fro msoil , whic hi s commonl yaccepte d t o b e 0. 5 - 0. 7 pCi/sqm-se c pe r pC i o f Radium-22 6 i n a gra m o f coa l o r ash. 1 5 Labtest s o f rado n emission s fro mcoa l showconsiderabl e variatio n ove r two order s o f magnitude , yielding emanatio n rate s 'fro m0. 1 t o 6. 0 pCi/sqm-se c pe r pCi/g. 1 6 Fo r purpose s o f thi s analysis , i t i s assume d tha t th e emanatio n rat e o f rado n fro mcoa l pile s i s the uppe r rang e measuremen t fro

msoi l (0. 7 pCi/sqm-se c pe r pCi/ g o f radium) . Coa l as h typicall ydemonstrate s a muc hlowe r emanatio n rat e becaus e som e o f the as hi s vitrifie d whic himpede s the escap e o f radon . Thi s analysi s assume s the emanatio n rat e o f as ht o b e 0.1 3 pCi/sqm-se c pe r pCi/ g o f radium. 1 7 Thes e value s fo r coa l an d as hca n b e substitute d int o equatio n (14) : (14 ) Quantit yo f rado n = [ Emanatio n rat e * radiu mconcentratio n * release d 349,660,80 0 ] (pCi/day-acre ) Fo r coal : (15 ) Quantit yo f rado n = [ 0. 7 * 0.4 3 * 349,660,80 0 ] (pCi/day-acre )

release d Fo r ash : (16 ) Quantit yo f rado n - [ 0.1 3 * 4. 3 * 349,660,80 0 ] (pCi/day-acre )

release d Referring bac k t o equatio n (4) : Amoun t o f rado n ([Are a o f coa l stockpile ] * [amoun t o f rado n (4 ) release d pe r day= release d pe r daype r uni t area] ) + ([are a o f as hpile ] * [amoun t o f rado n release d pe r da ype r uni t area]) .

1 5 EPA'84 , p.4.1-6 ; NCRP#78 , p.13 ; an d Ediso n Electri c Institute , Revie w o f the EPAReportabl e Quantit yAdjustment s fo r Radionuclides . Ma y1987 , p.14 . (EEI'87) , (Commente r 102RQ-RN-6-L1) . Th e emanatio n rat e i s expresse d i n pCi/(sqm-sec ) becaus e rado n ga s mus t diffus e acros s a n expose d surfac e t o b e release d t o the atmosphere . I t i s als o possibl e tha t rado n ca n ente r othe r medi a suc ha s groundwate r throughleaching .

1 6 Energ yResources , Th e Toxicit yan d Radioactivit yo f Ashe s o f U.S . Coals : Fina l Report . Marc h1979 . DO E Contrac t No . EJ-78-C-01-63945 .

1 7 U.S . Environmenta l Protectio n Agency , Technica l Backgroun d Supplemen t i n Suppor t o f Rulemaking Adjustmen t Activitie s fo r Reportabl e Quantitie s (RO ) o f Radionuclides : Secon d Draft , (prepare d bySanfor d Cohe n & Associates) , February1989 , p.16 . (EPA'89) . B-1 2Substituting equation s (9) , (15) , an d (16 ) int o equatio n (4) : Amoun t o f rado n R (acres ) * [ 0. 7 * 0.4 3 * 349,660,80 0 ] (pCi/day

- (4 ) release d pe r da y- acre ) + 5. 3 R (acres ) * [ 0.1 3 * 4. 3 * 349,660,80 0 ] (pCi/day-acre ) B ysubstituting i n the R Q o f rado n (0. 1 Ci ) fo r th e amoun t o f rado n released , a n equatio n i s generate d tha t can b e use d t o calculat e the surfac e are a o f the coa l an d as hpile s necessaryt o releas e a n R Q o f rado n o n a dail ybasis : 0. 1 * IO 1 2pC i = R(acres ) * [ 0. 7 * 0.4 3 * 349,660,80 0 ] (pCi/day

acre ) + 5. 3 R (acres ) * [ 0.1 3 * 4. 3 * 349,660,80 0 ] (pCi/day-acre ) 0. 1 * IO 1 2pC i = 105,000,00 0 pCi/day-acr e* R+ 1,036,000,00 0 pCi/day

acr e* R Solving fo r R : R = 8 8 acre s and A= 46 6 acre s Thus , thi s analysi s suggest s tha t a representative , twent yyear-ol d utilit y boile r facilit ywoul d nee d t o maintai n a reserv e coa l pil e o f 8 8 acre s and a corresponding wast e as hpil e o f 46 6 acre s befor e thes e pile s ar e estimate d t o releas e a n R Q o f rado n o n a dail ybasis , and , therefore , b e subjec t t o CERCL A notificatio n requirements . T o determin e the numbe r o f utilit yfacilitie s tha t coul d hav e coa l and as hpile s o f thes e sizes , additiona l conversion s ar e necessary . Assumin g tha t th e pile s ar e 2 0 fee t deep an d knowing tha t a n acr e equal s 43,56 0 sq . ft. , thes e are a measurement s ca n b e converte d int o volume measurements : (17 ) Volume o f coa l - » 2 0 ft . * 43,56 0 sq . ft./acr e o r as hi n a n acr e - 871,20 0 cu . ft./acr e Thus , fo r a pil e o f 8 8 acres : (18 ) Volume o f coa l pil e - 8 8 acre s * 871,20 0 cu . ft./acr e R •

= 76,700,00 0 cu . ft . And , fo r a n as hpil e o f 46 6 acres : (19 ) Volume o f as hpil e = 46 6 acre s * 871,20 0 cu . ft./acr e A= 406,000,00 0 cu . ft . Usin g the bul k densitie s o f the two materials , thes e volume measurement s ca n b e translate d int o masses . Th e bul k densit yo f coa l i s 4 8 lbs/cu . ft . o r 4 2 cu . ft./ton . Th e bul k densit yo f as hi s 7 2 lbs/cu . ft . whic hca n b e expresse d a s 2 8 cu . ft./ton . Thes e conversion s are : (20 ) Mas s o f R - 76,700,00 0 cu . ft. / 4 2 cu . ft./to n 1,826,00 0 ton s (21 ) Mas s o f A- 406,000,00 0 cu . ft. / 2 8 cu . ft./to n 14,500,00 0 ton s B-1 3P.1 8 

# I I Referring bac k t o equatio n (5) , a reserve coa l pil e o f 1,826,00 0 ton s suggest s

a n annua l consumptio n o f approximatel y7,300,00 0 ton s (1,826,00 0 x4) . Usin g equatio n (3) , thi s annua l coa l consumptio n ca n b e translate d int o a n estimat e o f the boile r siz e neede d t o consume suc ha quantit yo f coal . (3 ) Boile r siz e - » Annua l coa l consumptio n 2,75 0 tons/yea r pe r MW (22 ) Boile r siz e • = 7.300.00 0 tons/yea r 2,75 0 tons/year/M

W 2,66 0 MW Ther e ar e 2 3 coal-fire d powe r plant s large r tha n 2,00 0 MW , a s show n i n Exhibi t B-l ; the numbe r large r tha n 2,60 0 MWi s likel yt o b e a fractio n o f thi s figure . A s thi s siz e o f boile r generating capacit yi s large r tha n th e necessarycut-of f siz e calculate d fo r coa l deliveries , al l facilitie s having t o repor t becaus e o f rado n emission s woul d hav e t o repor t als o fo r coa l deliveries . Thi s same calculatio n ca n b e repeate d fo r industria l boilers , fo r whic h i t i s assume d tha t the wast e as hpil e i s 13. 3 time s the siz e o f the coa l stockpile , a s calculate d i n equatio n (12) . Again , using equatio n (4) : Amoun t o f rado n ([Are a o f coa l stockpile ] * [amoun t o f rado n (4 ) release d pe r day- = release d pe r da

ype r uni t area] ) + ([are a o f as hpile ] * [amoun t o f rado n release d pe r daype r uni t area]) . Substituting equation s (12) , (15) , an d (16 ) int o equatio n (4) : Amoun t o f rado n R (acres ) * [ 0. 7 * 0.4 3 * 349,660,80 0 ] (pCi/day

- (4 ) release d pe r da y- acre ) + 13. 3 R (acres ) * [ 0.1 3 * 4. 3 * 349,660,80 0 ] (pCi/day-acre ) B ysubstituting i n th e R Q o f rado n (0. 1 Ci ) fo r the amoun t o f rado n released , a n equatio n i s generate d tha t ca n b e use d t o calculat e the surfac e are a o f th e coa l an d as hpile s necessaryt o releas e a n R Q o f rado n o n a dail ybasis : 0 . 1 * 10 1 2pC i - R(acres ) * [ 0. 7 * 0.4 3 * 349,660,80 0 ] (pCi/day

acre ) + 13. 3 R (acres ) * [ 0.1 3 * 4. 3 * 349,660,80 0 ] (pCi/day-acre ) 0 . 1 * 10 1 2pC i - • 105,000,00 0 pCi/day-acr e* R+ 2,600,000,00 0 pCi/day-acr e * R Solving fo r R : R - 3 7 acre s and A- 49 2 acre s Thus , a n industria l facilit ywit ha coa l stockpil e o f 3 7 acre s an d a corresponding as hpil e o f 49 2 acre s i s likel yt o releas e a n R Q o f rado n t o ai r o n a dail ybasis . T o conver t thes e surfac e measurement s int o volume unit s usin g equatio n (17) : B-1 4P.1 9

(23 ) Volume o f coa l pil e - = 3 7 acre s * 871,20 0 cu . ft./acr e R •

= 32,200,00 0 cu . ft . (24 ) Volume o f as hpil e - 49 2 acre s * 871,20 0 cu . ft./acr e A- 429,000,00 0 cu . ft . Th e bul k densit yo f coa l i s 4 2 cu . ft./to n an d tha t o f as hi s 2 8 cu . ft./ton . Usin g thes e values , thes e volum e measurement s ca n b e converte d int o masses : (25 ) Mas s o f R = 32,200,00 0 cu . ft. / 4 2 cu . ft./to n 767,00 0 ton s (26 ) Mas s o f A- 429,000,00 0 cu . ft. / 2 8 cu . ft./to n 15,300,00 0 ton s Areserv e coa l pil e o f 767,00 0 ton s suggest s a n annua l consumptio n o f approximatel y7,670,00 0 ton s (767,00 0 x10) , becaus e industria l boiler s maintai n onl ya 37-da yreserv e o f coal . Thi s quantit yo f annua l coa l consumptio n i s slightl ylarge r tha n tha t calculate d fo r utilit yboiler s i n equatio n (22 ) whic hcorrespond s t o a n aggregat e boile r capacit yo f ove r 2,60 0 MW . Althoughther e ar e utilit ypowe r plant s wit ha n aggregat e capacit yo f thi s size , i t i s highl yunlikel ytha t an yindustria l facilit yha s suc h aggregate , generating capacity , a s show n i n Exhibi t B-2 . I n summary , unde r representativ e condition s an d operating procedures , fewe r tha n 2 3 o f th e coal-fire d utilit ypowe r plant s wit ha generating capacit yove r 2,00 0 M War e expecte d t o mee t o r excee d the R Q fo r rado n base d o n release s t o ai r fro mcoa l and coa l as hpile s maintaine d a t the facility . Thes e facilitie s ar e expecte d t o hav e t o repor t release s o f radionuclide s alread ybecaus e o f release s t o land associate d wit hthe deliver yo f coal . Particulat e Release s t o Ai r Th e windborn e releas e o f radionuclide-lade n particulate s represent s a releas e t o air . A s estimate d i n equatio n (2) , th e quantit yo f coa l containing a n R Q o f radionuclide s i s 2,36 0 tons . Typica l particulat e release s t o ai r fro ma "model " coa l pil e ar e reporte d a s 61 0 k g annuall yfo r a 95,00 0 metri c to n pil e (EPA'78 , p.2) . Thi s quantit yequal s a n averag e dail ylos s o f 1.6 7 k g o r 0.00000 2 percen t o f th e pile . Usin g thi s percentag e dail ylos s an d the quantit yo f coa l known t o represen t a n R Q o f radionuclides , the siz e pil e neede d t o mak e thi s releas e pathwayrelevan t ca n b e calculate d a s follows : (27 ) Siz e o f coa l pil e - = Quantit ycontaining an ' R O Percentag e los t dail y 2.36 0 ton s 0.00000 2 percen t 118,000,000,00 0 ton s

B-1 5P.2 0

N o facilit ymaintain s a reserv e coa l pil e o f thi s size . Consequently , n o facilit yi s likel yt o releas e a n R Q o f radionuclid e vi a thi s releas e path . Thi s releas e pat hi s equall yimplausibl e fo r particulat e release s o f as hfro m wast e piles . Release s t o Groundwate r an d Leaching Pile s o f coa l an

d as hmayals o releas e radionuclide s t o groundwater . Becaus e radionuclide s ar e primaril yheav ymetal s and , therefore , no t readil y solubl e i n water , the mos t likel ypat ho f releas e i s the transpor t o f particulate s b

ywate r percolating throug hthe piles , suc ha s during a rai n showe r o r b

yleaching fro

mas hlagoons . T o estimat e th e quantit yo f wate r tha t coul d leac hou t a n R Q o r mor e o f radionuclides , i t i s assume d tha t al l radionuclide s o f a particula r serie s (e.g. , Uranium-23 8 and it s daughters ) ar e i n secula r equilibriu m(i.e. , ar e foun d i n th e same concentration ) i n the coa l an d as hpile . Becaus e al l membe r radionuclide s o f a serie s ar e assume d t o b e presen t i n the coa l an d ash , the relativ e contributio n o f eac htoward meetin g o r exceeding a n R Q mus t b e assesse d using the mixtur e rule . Specifically , i t i s necessaryt o calculate , fo r eac hradionuclid e released , the rati o o f th e quantit yrelease d i n curie s t o the appropriat e RQ . I f the su mo f the ratio s fo r al l radionuclide s i s les s tha n one, , the releas e nee d no t b e reported . I f th e su mequal s o r exceed s one , the releas e mus t b e reported . Referring t o equatio n (1) , the mixtur e rul e ca n b e expressed : (1 ) Percentag e o f a n 1 Quantit yrelease d (pCi )

R Q release d Lt [

_R Q (pCi )
_ n wher e n i s the numbe r o f radionuclide s i n the mixtur e 

# - [ <

Th e "quantit yreleased " o f a n individua l radionuclid e depend s o n four factors : (1 ) th e concentratio n o f the radionuclid e i n the coal , (2 ) the concentratio n o f th e radionuclid e i n th e ash , (3 ) th e adsorptio n coefficien t o f th e radionuclide , an d (4 ) the volum e o f wate r passing throug hthe pile . Th e adsorptio n coefficien t (Kd ) i s a measur e o f th e exten t t o whic hthe radionuclid e adhere s t o th e soi l and thus , i s no t fre e t o migrat e ou t o f the pil e vi a leaching . I t is , therefore , a measur e o f th e radionuclide' s abilit y t o b e transporte d ou t o f the pil e byleaching . Thi s analysi s assume s tha t Kd value s ar e th e same fo r radionuclide s i n coa l pile s an d i n as hpiles . Th e "quantit yreleased " o f a n individua l radionuclid e ca n b e expresse d a s the su m o f the quantitie s release d b ythe . coa l and as hpile , divide d b ythe adsorptio n coefficient , multiplie d b ythe volume o f leachate . Mathematically , thi s ter m is : Quantit yRadionuclid e Radionuclid e (28 ) release d - concentratio n i n coa l + concentratio n i n as h(pCi/g ) * Volum e

(pCi ) K d (ml/g ) wher e Volum e i s th e volum e o f leachat e passing throughthe pil e i n m l
B-1 6P.2 1

Th e concentratio n o f Uranium-23 8 an d Thorium-23 2 serie s radionuclide s i n secula r equilibriu

mi n coa l ar e 0.4 3 pCi/ g an d 0.3 5 pCi/ g respectively . Assuming n o radionuclide s ar e los t o r destroye d during combustion , the concentratio n o f thes e radionuclide s i n as har e 4. 3 pCi/ g an d 3. 5 pCi/ g respectively . Thi s analysi s assume s als o tha t al l o f the precipitatio n seep s throughthe coa l an d as hpile s an

d non e i s diverte d a s surfac e runof f o r evaporates . Becaus e o f a combinatio n o f shor t half-lif e an d highadsorptio n coefficient , som

e radionuclide s i n the Uranium-23 8 an d Thorium-23 2 serie s contribut e negligibl yt o meeting o r exceeding a n R Q o f radionuclide s vi a thi s releas e pathway . Consequently , thes e radionuclide s ar e ignore d i n thi s analysis . Belo wi s a tabl e summarizing the radionuclide s considere d relevan t t o thi s releas e pathwayan d the value s use d i n the analysis: 1 8
Radionuclid e URANIU M SERIE S Uranium-23 8 Uranium-23 4 Thorium-23 0 Radium-22 6 Lead-21 0 Polonium-21 0 Concentratio n i n

Coa l (oCi/e )

0.4 3 0.4 3 0.4 3 0.4 3 0.4 3 0.4 3 Concentratio n i n

As h(nCi/e )



### 4. 3 4. 3 4. 3 4. 3 4. 3 4. 3 Adsorptio n

Coefficien t (ml/g )

5 0 5 0 3,00 0 7 5 10 0 10 0 THORIU M SERIE S Thorium-23 2 Radium-22 8 Thorium-22 8 0.3 5 0.3 5 0.3 5 3. 5 3. 5 3. 5 3,00 0 7 5 3,00 0 Thes e value s ar e substitute d int o equatio n (28 ) fo r eac hradionuclid e and th e resulting product s ar e substitute d int o equatio n (1) . T o determin e th e volum e o f leachat e containing a n R Q o f radionuclides , the left-han d sid e o f equatio n (1 ) i s se t equa l t o on e an d the equatio n i s solve d fo r th e unknow n volume : 

## ( D (29 ) 1 R

Q (pCi ) Volum e 1.4 1 * 10" 1 1 (pCi/ml ) * Volum e

70,900,000,00 0 ml 1 9

1 8 EPA'89 , p.22-24
. 1 9 On e commente r provide d a n estimat e o f on e billio n liter s pe r dayt o excee d a n R Q o f Thorium-230 . Thi s estimat e wa s base d o n a concentratio n o f Thorium-23 0 o f 1 0 pCi/lite r and di d no t conside r othe r radionuclides , p.14 . EEI'87 , B-1 7P.2 2

70,900,000,00 0 m l * 1 cubi c inch 16.3 8 m l 4,330,000,00 0 cubi c inche s (cu . in. ) Therefore , i t i s estimate d tha t 4.3 3 billio n cubi c inche s o f wate r woul d hav e t o seep throughth e coa l an d as hpile s maintaine d a t a facilit yan d escap e t o the environmen t t o contai n a n R Q o f radionuclides . Leaching o f thi s magnitud e fro mexisting as hlagoon s doe s no t occu r o n a continuou s basis . I f the pile s ar e larg e enough , however , thi s volume o f wate r coul d pas s throug hthe mo n a regula r basi s during period s o f precipitation . T o conver t thi s volume o f precipitatio n int o a measuremen t b f surfac e area , the dept ho f the volume (i.e. , numbe r o f vertica l inche s o f rai n o r snow tha t fall s ove r 2 4 hours ) mus t b e known . Becaus e eve n a n averag e dept ho f rai n pe r stor

mvarie s greatl yacros s region s an d withi n region s acros s seasons , thi s figur e necessaril ywil l b e somewha t inappropriat e fo r al l facilitie s maintaining coa l and as hpiles . Thi s analysi s use s a reasonabl y conservativ e figur e o f si xinches . Thus , the conversio n t o surfac e are a is : (30 ) Surfac e are a o f leachat e - Volume o f leachate/dept ho f leachat e 4.330.000.00 0 cu . in .

6 in . 722,000,00 0 sq . in . 722,000,00 0 sq . in . * 1 acr e 6,270,00 0 sq . in .

- = 11 5 acre s Therefore , th e quantit yo f rai n estimate d t o contai n a n R Q o f radionuclide s mus t cove r a n are a o f 11 5 acre s t o a dept ho f si xinches . Thi s are a i s the combine d siz e o f the coa l pil e an d as hpil e necessaryt o mak e thi s releas e pathwayfeasible . Equatio n (9 ) abov e represent s the relationshi p betwee n th e surfac e area s o f coa l and as hpile s a t utilit yfacilities : (9 ) A- 5. 3 R where

- Ai s th e siz e o f the as hpil e an d R i s the siz e o f the coa l pil e Therefore , the combine d are a o f the two pile s i s 6. 3 R (i.e. , R + 5. 3 R) . Dividing thi s figur e b ythe are a calculate d i n equatio n (30) : (31 ) 6. 3 R - 11 5 acre s R - 18. 3 acre s T o determin e the numbe r o f utilit yfacilitie s tha t coul d hav e coa l pile s o f thes e sizes , additiona l conversion s ar e necessary . Assuming tha t th e pile s ar e 2 0 fee t deep and knowing tha t a n acr e equal s 43,56 0 sq . ft. , thes e are a measurement s ca n b e converte d int o volum e measurement s using equation s (17) : B-1 8P.2 3

(17 ) Volume o f coa l - 2 0 ft . * 43,56 0 sq . ft./acr e

i n a n acr e - 871,20 0 cu . ft./acr e Thus , fo r a pil e o f 18. 3 acres : (32 ) Volume o f coa l pil e = 18. 3 acre s * 871,20 0 cu . ft./acr e R = 15,900,00 0 cu . ft . Using the bul k densit yo f coal , thi s volume measuremen t ca n b e translate d int o a mas s measurement . Th e bul k densit yo f coa l i s 4 8 lbs/cu . ft . o r 4 2 cu . ft./ton . Th e conversio n is : (33 ) Mas s o f R - 15,900,00 0 cu . ft. / 4 2 cu . ft./to n 379,00 0 ton s Referring bac k t o equatio n (5) , a reserv e coa l pil e o f 379,00 0 ton s suggest s a n annua l consumptio n o f approximatel y1,520,00 0 ton s (379,00 0 x4) . Usin g equatio n (3) , thi s annua l coa l consumptio n ca n b e translate d int o a n estimat e o f th e boile r siz e neede d t o consume suc ha quantit yo f coal : (3 ) Boile r siz e - Annua l coa l consumptio n 2,75 0 tons/yea r pe r MW (34 ) Boile r siz e - 1.520.00 0 tons/yea r 2,75 0 tons/year/M

W 55 0 MW Ther e ar e 20 4 powe r plant s wit hcoal-fire d boiler s whos e aggregat e capacit yi s greate r tha n 50 0 MW , a s show n i n Exhibi t B-l . Thi s analysi s assume s tha t al l o f thes e facilitie s hav e generating capacitie s large r tha n 55 0 MW . Thi s same calculatio n ca n b e repeate d fo r industria l facilities , whic h maintai n coa l and as hpile s i n differen t proportion s t o thos e foun d a t utilit y facilities . Referring t o equatio n (12) : (12 ) A= 13. 3 R wher e Ai s the siz e o f the as hpil e an d R i s the siz e o f the coa l pil e Therefore , the combine d are a o f th e two pile s a t industria l facilitie s i s 14. 3 R (i.e. , R + 13. 3 R) . Dividing thi s figur e b ythe are a calculate d i n equatio n (30) : (35 ) 14. 3 R - 11 5 acre s R - 8. 0 acre s T o determin e th e numbe r o f industria l facilitie s tha t coul d hav e coa l pile s o f thes e sizes , additiona l conversion s ar e necessary . Assumin g tha t th e B-1 9P.2 4

pile s ar e 2 0 fee t deep an d knowing tha t a n acr e equal s 43,56 0 sq . ft. , thes e are a measurement s ca n b e converte d int o volume measurement s using equation s (17) : (17 ) Volume o f coa l - = 2 0 ft . * 43,56 0 sq . ft./acr e i n a n acr e - 871,20 0 cu . ft./acr e Thus , fo r a pil e o f 8. 0 acres : (36 ) Volume o f coa l pil e • = 8. 0 acre s * 871,20 0 cu . ft./acr e R - 6,970,00 0 cu . ft . Using th e bul k densit yo f coal , thi s volum e measuremen t ca n b e translate d int o a mas s measurement . Th e bul k densit yo f coa l i s 4 8 lbs/cu . ft . o r 4 2 cu . ft./ton . Th e conversio n is : (37 ) Mas s o f R - 6,970,00 0 cu . ft. / 4 2 cu . ft./to n 166,00 0 ton s Referring bac k t o equatio n (10) , a reserv e coa l pil e o f 166,00 0 ton s a t a n industria l facilit ysuggest s a n annua l consumptio n o f approximatel y1,660,00 0 ton s (166,00 0 x10) . Usin g equatio n (3) , thi s annua l coa l consumptio n ca n b e translate d int o a n estimat e o f the boile r siz e neede d t o consume suc ha quantit yo f coal . (3 ) Boile r siz e = Annua l coa l consumptio n 2,75 0 tons/yea r pe r M W (38 ) Boile r siz e • = 1.660.00 0 tons/yea r 2,75 0 tons/year/M

W 60 0 MW A s show n i n Exhibi t B-2 , i t i s highl yunlikel ytha t ther e ar e industria l facilitie s wit ha n aggregat e generating capacit yo f 60 0 MW . Therefore , base d o n th e assumptio n tha t a facilit yregularl yreceive s si xinche s o f precipitatio n ove r a 24-hou r perio d whic hseep s throughit s coa l and as hpiles , a tota l o f 20 4 facilitie s wit hcoal-fire d boiler s (20 4 utilit y boiler s and n o industria l boilers ) ar e likel yt o mee t o r excee d the R Q fo r radionuclide s o n a regula r basis . Thi s analysi s doe s no t conside r the cumulativ e release s occurring fro m al l separat e releas e pathway s simultaneousl ybecaus e suc ha calculatio n depend s o n to o man

yvariable s and assumption s t o yiel d a n accurat e and meaningfu l result . However , i t i s unlikel ytha t th e siz e cutof f fo r boile r facilitie s woul d chang e significantl yfromthe resul t reporte d above .

B-2 0Summary

Thi s analysi s considere d five releas e pathway s b ywhic ha n R Q o r mor e o f a radionuclid e coul d b e release d o n a regula r basi s b ya facilit ywit ha coal

fire d boiler . Th e five releas e pathway s are : (1 ) smokestac k emissions ; (2 ) dumping o f radionuclide-lade n material s ont o stockpile s o r wastepiles ; (3 ) release s o f rado n ga s t o ai r fro mcoa l stockpile s an d as hwastepiles ; (4 ) release s o f radionuclid e particulate s t o ai r fro mcoa l an

d as hpiles ; an

d (5 ) release s o f radionuclide s fro mcoa l an

d as hpile s t o groundwate r (i.e. , leaching) . Th e analysi s presente d abov e concludes :

• n o utilit yo r industria l facilit yi s likel yt o releas e a n R Q o r mor e o n a regula r basi s throug hsmokestac k emission s o r through particulat e release s t o air ;

• 2 3 utilit ypowe r plant s ar e estimate d t o releas e rado n ga s from coa l and as hpile s a t o r above th e R Q o n a continuou s basis ;

• 20 4 utilit ypowe r plant s ar e estimate d t o releas e a n R Q o f radionuclide s i n a mixtur e throughleaching fro mcoa l an

d as h piles ; and

• 51 4 utilit ypowe r plant s an d 1,21 0 industria l facilitie s ar e likel yt o receive'shipment s o f coa l large r tha n 2,36 0 ton s ove r a 24-hour perio d o n a regula r basi s and , therefore , excee d the R Q fo r a mixtur e o f natura l Uranium-23 8 an d natura l Thorium-23 2 i n secula r equilibriu

mb ythe ac t o f dumping coa l i n a n expose d site . Facilitie s tha t receiv e deliveryo f mor e tha n 2,36 0 ton s o f coa l a t on e time maintai n muc hsmalle r volume s o f coa l and as htha n ar e require d t o mee t o r excee d a radionuclid e R Q bythe two othe r relevan t pathway s (i.e. , leaching and rado n releases) . Consequently , an yfacilit ymeeting o r exceeding a n R Q becaus e o f thes e releas e pathway s i s expecte d t o excee d a n R Q becaus e o f release s associate d wit hth e deliveryo f coal . Th e fina l estimate , therefore , o f facilitie s likel yt o releas e a n R Q o r mor e o f a radionuclid e o n a regula r basi s i s 1,72 4 (51 4 utilit ypowe r plant s and 1,21 0 industria l facilities) . Thes e facilitie s ar e expecte d t o repor t thes e release s unde r the provision s o f the reporting requirement s o f sectio n 103(f)(2 ) o f CERCLA .

B-2 1P.2 6 

# PICK-UPDATE : 3/8/200 7 BO X 

# 10 O F 

# 10 Step2 : FO RASR C INTERNA

L US E ONLY 

### (PARTA o

fB )



# EP ADOCKE TID : 102RQ-R N 1 ) INDE X 3 ) 102RQ-RN-1- 2 5 ) 102RQ-RN-1- 4 7 ) 102RQ-RN-1- 6 9 ) 102RQ-RN-3- 1 11 ) 102RQ-RN-3- 3 13) 102RQ-RN-2-1- 2 15 ) 102RQ-RN-2-1- 4 17) 102RQ-RN-2-2- 1 19 ) 102RQ-RN-2-3- 1 21 ) 102RQ-RN-2-4- 2 23 ) 102RQ-RN-2-4- 4 25 ) 102RQ-RN-2-4- 6 27 ) 102RQ-RN-2-4- 8 29 ) 102RQ-RN-2-4-1 0 31 ) 102RQ-RN-4- 2 33 ) 102RQ-RN-4- 4 35 ) 102RQ-RN-4- 6 37 ) 102RQ-RN-4- 8 39 ) 102RQ-RN-5- 1 Ste p 3 : FO R ASR C INTERNA LUS E ONL Y CD : OA : / 

# 2 ) 102RQ-RN-1- 1 4 ) 102RQ-RN-1- 3 6 ) 102RQ-RN-1- 5 8 ) 102RQ-RN-1- 7 10 ) 102RQ-RN-3- 2 12 ) 102RQ-RN-2-1- 1 14) 102RQ-RN-2-1- 3 16 ) 102RQ-RN-2-1- 5 18 ) 102RQ-RN-2-2- 2 20 ) 102RQ-RN-2-4- 1 22 ) 102RQ-RN-2-4- 3 24 ) 102RQ-RN-2-4- 5 26 ) 102RQ-RN-2-4- 7 28 ) 102RQ-RN-2-4- 9 30 ) 102RQ-RN-4- 1 32 ) 102RQ-RN-4- 3 34 ) 102RQ-RN-4- 5 36 ) 102RQ-RN-4- 7 3S)3U2Rq^N^9 ^ 40 ) 102RQ^P5^ 2

Ste p 1 : FO R ASR

C INTERNA LUS E ONL YX* ^ Are ther e more documents fo rthi s Docke t i n anothe rbox?/*YES) / N O *Fil l ou t Continuatio n Shee t an d go t o Ste p 2 \^X Interna l SFUN D Bo

xNumbe r3 5 O F 28 3 Initials/Date : LD S /3-8-200 7