ML19206A237

Forwards Final Suppl to Fes Covering Radiological Impacts & Environ Impact of Transportation of Fuel & Waste

ML19206A237
Person / Time
Site:	Crane
Issue date:	11/11/1976
From:	Vollmer R Office of Nuclear Reactor Regulation
To:	Moore V Office of Nuclear Reactor Regulation
References
NUDOCS 7904180419
Download: ML19206A237 (26)

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5.X P.ADI0 LOGICAL IMFACTS

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5.x.1 Radiolcaical Ir:3ct on Man i

The nodels and considerations for envircn.~ ental P3thways leading to I

esticates of radiaticn dose ccomittents to individuals are discussed l

in datail in draft Rcgulatory Guide 1.103.

Similarly use of th3se t

i nodels, and additional assumpticns, for population dose esticates are described in Appendix A of this statanant.

5.x.l.1 Exoosure Fathwavs f

The envircnmental path <.ays which i ere considered in preparing this t

secticn are sho'..n in Figure 5.X.1.

Estinatas were made of radiation I

doses to man at and beyond the site boundary based on NRC staff estimates of expected effluents as shown in Tables 3.

and 3.____,

l site meteorol gical and hydrological considerations, and exposure f

i pathways at the Three Mile Island Unit 2 nuclear power station.

t Inhalation of air and ingestion of food and s ater ccntaining tritium, C-14 and radiocesium are estimated to account for essentially all I

i of total body radiation dose come.itrants to individuals and the population within 50 miles of the station.

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5.X.1.2 yseCc.mit:2Ms f a Odicqiyq_Mpps to the Atmosdare Radicactive effluents released to the atmosphere frc.n the Three Mile Isl:nd Unit 2 facility will result in snall radiation deses to the i

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j 1 public. NRC staff esticates of the expected gaseous and particulate releases listed in Table 3.

, and the site reteorological consid-i erations discussed in Section 2.

of this statement and sumr.arized in Table 5.X.1 were used to estimate radiation doses to individuals and ?;pulations.

The results of he calculaticns are discussed below.

I Radiation Dose Co.v.itments to Individuals The predicted dose commitments to " maximum" individuals at the off-site l

locations where doses are expected to be largest are listed in Table 5.X.2.

A maximum individual is assumed to consume well above average quantities of the foods ccnsidered (see Table A-2 in 7.egulatory Guide 1.109).

The standard NRC models ware used in order to realistically f

model features of the Three Mile Island Unit 2 plant design and the o

site anvirons.

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Radiaticn Doses Commitmants to Poculations The estimated annual radiation dose ccnmitr.ent to the population i

I (within 56 ailes) for the Three Mile Island Unit 2 Nuclear Pcwer Plant f

r from gasecus and particulated releases were based cn the projected l'

site population distribution for the Year 2010.

Doses beycnd I

the 50-inile radius were based on the average population densities 1

i discussed in "pp:ndix A of this statar. ant. T!,e annual p;pulaticn

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i dose commitments are presented in Table 5.X.5.

Background radiation I

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doses are provided for ccmparison.

The doses from atmospheric

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releases from the Three Mile Island Unit 2 facility during normal j

cperation represent an extremely small incre?se in the normal popula-f i

tien dose fr:m background radiation sources.

1 Dose Corniitments from Padicactive Licuid Releases to the Hvdroschere-5.X.1.3 I

Radicactive effluents released to the hydrosphere frcm the Three i

Mile Island Unit 2 facility during normal operation will result in small radiation doses to individuals and populations.

NRC staff I

I estimates of the expected liquid releases listed in Table 3.__, and the site hydrological considerations discussed in Section 2.__ of I

I this statement and summarized in Table 5.X.3 were used to estimate radiation dose ccamitments to individuals and populations. The t

results of the calculations are discussed below.

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Radiation Case Ccamitnents to Individuals t

The estimated dose ccmmitments to individuals at selected off-site locations whare exposures are expectad to be largest are listed in t

I Table 5.X.4.

The standard NRC models given in Regulatory Guide 1.109 were used for these analyses.

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i' Radiation 00ses Ccnmitnents to Fooulations t

f The estimated p;pulation radiation dose ccmmitments to 50 miles for I

the Three ,ile Island 'Jni: 2 facility from liquid releases, based on l

the use.of water and bicta from the Susquehanna River, are shown in Table 5.X.5.

Case con.itrants 2eyond 50 miles were based cn the I

assumptions discussed in Appendix A.

t Sackground radiation doses are provided for ccm;arison.

The dose t

commitments from liquid releases from the Three Mile Island Unit 2 j.

i facility represent small increases in the population dose from i

t, background radiation sources.

t 5.X.1.4 Direct Radiation f

Radiation frca the facility. Radiation fields are produced in nuclear plant environs as a result of radiactivity contained within the reactor a.nd its associated components.

l Doses from sources within the plant are pricarily due to nitrogan-16, a radionuclide produced in the reactor core.

Secause of variations f

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m.arall plant design. Since the prirary coolant of pressurized water reactors is centained in a haavily shielded area of the plant, dose I

rates in the vicinity cf P'.lR's are centrally undetectable (less than I.

5 mram/yr).

Low level radiactivity stcrage containers outside the plant are estimated to contribute less than 0.01 mrem / year at the site boundary.

Occuostional Radiation Exposure Eased on a review of the applicant's safety analysis report, the staff has determined that the applicant is ccmaitted to design features and operating practices that will assure that individual cccupational radiation doses (occupational dose is defined in 10 CFR Part 20) and that individual and tctal plant population doses will i

be as icw as is reasonably achievable.II) For the purpose of portraying l

i the raciological impact of the plant operation cn all cn-site par-sonnel, it is necessary to estimate a man-rem occupational radiation i

I dose.

For a plant designed and proposed to be operated in a manner consistent with the 10 CFR Part 20, there will be many variables which influcnce exposure and make it difficult to determine a quanti-tative total occupational radiation dose for a specific plant.

Thtcefere, past ef;; care 2x?ariance frra cparating nuclear pouer statiens(2) has been used to provide a sidely cpplicable esticate to i

l J C,:R..rt 20, Si: brJs fcr Pr;tectica ",ains t ?-diaticn

' tar bO' 'dG 75/022, Occt. :ticnal 'adiati:a E:p::;re t3 Lic.it

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be used for all light water reactor power plants of the type and size for the Three Mile Island Unit 2 plant.

This experience indicttes i

a value of 500 can-rem per year per reactor unit.

l Cn tiiis basis, the projected occa;aticnal radiation cxposure impact 6

of the Three Mile Island unit 2 statien is estimated to be 500 man rem t

i per year.

I Transoortation of Radicactive Material The transportation of cold fuel to a reactor, of irradiated fuel i~

from the reactor to a fuel reprocessing plant, and of solid radicactive l~

wastes from the reactor to burial grounds is within the scope of the i

I NRC report entitled, "Envircnmental Survey of Transportation of i

Radicactive Faterials to and from Nuclear Power Plants." The envircn-l mental effects of such transportation are suararized in Table 5.X.6.

i 5.X.1.5 Cercarison of Case Assessment !!cdels The applicant's site and environmental data provided in the Environ-f a

mental Report and in Evaluaticn to Dcmenstrate Ccmpliance.iith 10 CFR 50 Aprendix I. as used extensively in the dcse calculaticns.

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Three :',ile Isl:nc uclear Staticn Unit 2 Enviccam:ntal Repart, i

Operating License Stage, "etropolitan Edison Co., Cocket f: umber 50-320.

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E.X.1.6 Evaluation of Radiolocical Ircact The radioicgical ir: pact of operating the proposed Three Mile Island Unit 2 r.uclear pc. 2r station is presented in 12rns of individual i

I dose ccm:.i'.ments in Table 5.X.5.

The annual individual dose commit-f, I

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. nts resulting fr:: routi..e cperaticn of the plant are a tr.all I

fractior. of the dose limits specified in 10 CFR Part 20.

The popula-tien dose cerr.itments are small fracticns of the dose from natural envircr antal radicactivity. As a result, the staff ccocluded that there will be no measurable radiological impact on r.an frcm routine b.

cp2 ration of this plant.

5.X.1.7 Corrarison of Calculated Doses with NRC Desian 00i_ectives Tables 5.X.7 and 5.X.8 shcw a ccmparison of calculated doses from routine releases of liquid and gasecus effluents from the Three Mile I

t Island Unit 2 plant with the design objectives of Appendix I to 10 CFR 50 and with the prcpesed staff design objectives of Fli-50-2.

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5.X.1 SU:'.P.ARY CF ATMOSFEERIC DIS?ERSION FACTORS AND DEFC51T"

i VALUES FCR SELECTED LOCATIONS NEAR THE ThREE MILE ISLAND UNIT 2 NUCLEAR PCWER STATICN*

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RELATIVE LOCATICN SOURCE X/O ( sec/m )

DEF051TICN ( m-2) 3

'; ear?st Site A

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Land Ecundary B

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(0.37 mi WNW)

C 4.5 E-05 1.1 E-07 N2arest Residence A

1.4 E-C6 2.2 E-03 and gardan B

6.7 E-C6 1.4 E-07 (C.37 mi nNW)

C 4.5 E-05 1.1 E-C7 l

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I "The doses presented in the folicwing tables are corrected for radioactive I

decay and cloud depletien from deposition, where appropriate, in accordance with Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport i

and Dispersion of Gaseous Ef fluents in Routine Releases from Light Water Reactors," March 1976.

• • " Nearest" ref ers to timt type of location where the highest radiation l

dose is expected to occur from all approprict: patkeys, Source A is Reactor Building Vent Source B is Reactor Building Vent Purge l

r Source C is Turbine Building Vent 9

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TAJLE 5.X.4 AliNUAL ItiDIVIDUAL DOSE COF?ilT!1EtiTS DUE TO LIQUID EFFLUErlTS DOSE (mrem /yr)

L6CATIOTI PATHi!AY TOTAL BODY BONE LIVER TilYR010 LUT;G GI TRACT 0.04 0.08 0.04 0.04 i:e rcst River l!ater Drinking Water 0.04 Use (16 mi. downstream) i:aarest Fish Fish Production (Outfall Area) 1.6 1.2 2.1 0.19 0.24 0.23

(.i mi. downstream)

+

th rest Sediments Shareline

(,1 mi. downsi. ream)

.:::urast Use*

Irrigation of irrigated lla ter-Food Ec.ed Crops Crops (Adult) 0.05 0.05 0.04 0.05 (3.5 mi. downstream) 0.05 N'ssum.ed for purposes of an upper limit estimate-detailed information on usage and productivity not available.

^^Less than 0.01 mrem /yr i

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T/sulE 5.X.5 AhhUAL POPULATION DOSE C0:iMITMEf4TS IN THE YEAR 2010 Population Dose Cow;ituent (otan-rem) 50 miles U.S. Population Cutegory

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IMtural Radiation Background (3) 310,000.(h) 28,000,000.(c)

Three Mile Island Unit 2 Nuclear Power Plant Operation 500.

Plant Work Force 11.

33.

Q General Public (Total) 2.

2.

Noble Gases Submersion 1.

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Inhalation i

Ground Deposition Terrestrial Foods (including irrigated crops) 5.

18.

3.

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Drinking Water Aquatic Foods Recreation Transportation of nuclear 7.

fuel and radioactive wastes

~N.ess than i'~uan-rea/yr yncluded in the U.S. population, since some exposure is received by persons residing outside 50 mile radius.

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W/"t:atural Radiation Exposure in the United States," U.S. Environmental Protection Agency, ORP-SID 72-1 gj (June 1972).

(b)Using the average Pennsylvania state background dose (97. mrem /yr) in (a), and year 2010 projected population of 3,200,000.

Wlusing the average US background dose (102 meem/yr) in (a), and year 2010 projected U.S. population of 2110,000,000 fcca " Population Estimates and Projections," Series II, U.S. Dept. of Conr.1erce, Bureau of the Census, Series P-25 i;o. 541 (Feb.1975).

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I TAELE 5.X.6 EN', :::' " ENTAL L"? ACT OF T: * ',SP;RT ATICh 0F FL'EL AND 'J 57E TO AND FROM ONE LIGHT-HATER-COOLED NUCLEAR F0,;ER REAC7CR" i

urmal conditions of trars;;rt i

l Feat (par irradiated fuel cask in transit) 250,0C0 E:u/hr biight (gcVerned by Federal or State restrictions) 73,000 lbs. per truck; 100 tons par cask per rail car Traffic density

< 1 per day

< 3 per month Rail 1

uposed pcoulation Estimated Range of doses C rulative dose to number of to exposed 2 g :ed pcpulation persons individuals

(: an-rers par c ictor yr)c (millirars per rcactor yr)

Transportation

'io rke r 200 0.01 to 300 4

Ganeral Fuolic Onlookers 1,100 0.003 to 1.3 Alcng Route 600,000 0.0001 to 0.06 3

Accidents in transport d

Stali Radiological effects Cc=cn (ncnradiological) causes 1 fatal injury in 100 reactor years; 1 nonfatal injury in 10 reactor years;

$475 property damage per reactor year

'Cata supporting this table are given in the Comission's Environr.2ntal Survey of Transportation of Radioactive Materials to and from Nuclear Power Plants, UASH-1238, Cacember 1972, and Supp. I, NUREG 75/038, April 1975.

"The Fed 2ral Radiaticn Council has raccmmended that the radiation doses from all s

sources of radiation other than natural backgrcund and -3 dical exposures should be limited to 5,000 millirems / year for individuals as a result of occupational exposure and should be limited to 500 millirems / year for individuals in the general population.

The dose to individuals due to average natural background radiation is about 102 millirams/ year.

c"an-rem is an expression for the su ration of whole-bocy dos 2s to individuals in a Thus, if each camber of a pcpulaticn gccup of 1,000 p20ple..ere to rScaive grcup.

a dose of 0.001 rem (1 millirem), or if 2 pacple..are to receive a dose of 0.5 rem (500 millirems) each, the total r.an-rem in ecch case would be I r.an-rem.

d.1 bugh the 2nvir:n. ental risk of "diological ef fects staming frcm transpcrtation accid 2nts is curr3:.tly '..n;'.ble cf ;2ing vici:2ily qu ntified, the risk rurains small reg rdless of..h:ther it is

• eing a;pi d to a sugie ractor cr a..ulti-reactor site.

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I CC:'?ARISCS OF CALCULATED DOSES TO A EX:"JM I'OIVIDUAL FROM M TABLE 5.X.7 ISLANDUNITjOPERATIONWITHGUIDESFORDESIGNOBJECTIVESPROFCSED j

BY THE STAFF R"-50-2 CALCULATED DESIGN CEJECTIVE COSE

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CPITERION Liquid Effluents t

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se to total body cr any 5. rem /yr

2. 3 7.r am/yr organ frcm all pathways i

i Noble Gas Effluents (at site boundary)

Gan.ma dose in air 10,trad/yr 0.5 mrad /yr i

Eeta dose in air 20 mrad /yr 1.5 nrad/yr i

l Dose to total body of an individual 5 crem/yr 0.3 mrem /yr I

C:se to skin of an irdividual 15 mren/yr 1.0 ren/yr Radiciodine and Particulates Dose to any organ frca all paths.ays (Child) 15 nram/yr 5.9 cren/yr I

'Suides on Design Objectives preposed by the NRC staff on February 20, 1974; ccnsiders doses to individuals from all units on site.

Frcm "Ccncluding Statement of Position of the Regulatory Staff," Cocket No. FJi-50-2, Feb. 20, 1974, pp. 25-30, U.S. Atcmic Energy Conmission,ilashington, D. C.

bCarbon-14 and tritium have been added to this category.

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.it en DESIGN 050ECTIVE DOSE _S I

CR:TERIC';

L ;.. : d : : z. l.. e. n +. a u

s_ s, s,,, e.. v u-

.O v.v.

all ?:-tH.ays ( Acuit) 3 mrem /yr 1.7.rzr/yr

_,,. o.

_:n.

1. . r...

all :itb.3js (Acu't >_iver) 1C

.c r-/y r

2. 3

_r/yr

';cSle Gas Effluents (at site boardary) i Gi ra dose in air 10 =r.=dijr 0.5 cad /yr Esta dose in air 20 nrad/yr 1.5. rad /yr

cse :o total bcdy of an i r.;i.'i d;al 5 mren/yr 0.3 mrem /yr

33 to ssin of an individual 15 crcn/yr 1.0 rcm/yr Radioicdines and Particulates

se to any orcan frcm all pata. cays Child-bcr.e) 15 nram/yr 5.9 rre-/jr

~ tc. :-ndix I Design Cbjectives from Sections II. A, II.B, II.C of Appar. dix I, 10 CFR Part 50; considers dcsas to maxin_m individual per r.uct:r unit.

i r r:m r ederal ne gi s:er V. ~. 0, p. 194,.2,,c,.ay o, 1 c.73.

t 5 ;r':cn-la and tritium have been added to this catacar.

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i 5.Y.I Radiolocical Irract on Biota Other T'an Man n

i a

The models and considerations for environnental pathways leading to estinates of radiation doses to biota are discussed in detail in Volume 2, ' A.alytical Models and Calculaticns" of '..?SH-1258.#

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-- _cssre Fa_m.avs--

5.Y.l.1 E3 -

I The enviror.nantal pathways which were considered in preparing this section c shown in Figure 5.Y.l.

Dese estimates rare made for 1

biota at the r.earest land and water boundaries of the site, and in I

the aquatic environment at the point where plant's liquid effluents l

mix with the Susquehanna River.

The estinates ware based on estimates of expected effluents as sh;wn in Tables 3.

and 3.

i site meteorological and hydrological considerations, and the exposure j

t pathways anticipated at the Three Mile Island Unit 2 nuclear power i

station.

t i

5.Y.1.2 Cases to 3icta frcr Radicactive Releases to the Eicsobere Cepending on the pathway (as discussed in Regulatory Guide 1.109),

terrestrial and aquatic biota will receive doses approximately the same or scrawhat higher than can receives.

Dose esticates for som.e typical biota at the Three Mile Island site are shown in Table 5.Y.1 Doses to a greater number of similar biota in the off-site envirens will c2c?cally be a ch Icnar.

ES, *. narical Guid3s for Casign Objactives and Linitic.g C;r iiticns Tor

'w-tion to '*3et t'.2 Cri' iricn 'As ' r./ t.s Tc ct.:'.5 a" fa.

':.M.

c' /2

..i-i - : 3

t :riil in LO t ',::t:r-Ccol 2d ::ucla;r.':. :r 7_:. ;r Lii... :s, a

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J u l *v 1973.

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.M" 5.Y.l.3 D:ses to Biota from Direct Radiation Although many of the terrestrial sp;-cies may be continuously ex;0s?d, and thereby receive higher doses than nan, aquatic species ard some I

tarrestrial species may receive screwhat Ic..er doses d3p3nding on i

shielding by water or soil (e.g., t,urrows). As a result of thase crcertaintias, it was a:swed that the cirect rad'aticn icsas to l

biota at the site boundary will be about the sama as for an.

As shown en Table 5.X.7, direct radiation deses will generally be lass than 5 nrad/yr.

Evaluaticn of the Radiological IrDact on Biota (,b) 5.Y.i.4 Althcu;h guidelines have not been established for dasirable linits for radiation exposure to species other than man, it is generally agreed that the limits established for hun 2ns are also ccnservative for other species.

Experience has shcxn that it is the mainter.ance of population stability that is crucial to the survival of a species, and species in most ecosystems suffer rather hich mortality rates frcm natural causes. While the existance of extramely radicsensitive biota is possible and while increased radiosensitivity in crganisms may result frca envircnmantal interactions with other stresses (e.g., heat, biocides, etc), no biota have yet baan discov2 rad '; hat show a sensitivity (in terms of increased disease or death) to r diation n;r.suras as ic1 1s those explcted in the :rea surrcu.; ding S. T. Auerbach, " Ecological Consideraticns in Siting Nuclear Pcuar Plants.

The Long Tera Biota Ef fects Problems," Nucl. Safety 12: 25 (1971),

b 'Tha Eif acts en.?cpulaticas of Exposure to le t L./als of Ic.aic,] ~~ o n cn,"

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the Three Mile Island nuclear poner station.

The "5EIE" 7.3; ort concluded that the evidence to date indicates that no otr.er living f

I crganisms are very much more radiesensitive than r.an.

Therefcre, l

I no reasurable radiolcgical impact on populations of bista is ev;:-cted I

from the radiation and radicactivity released to the bios;Eere as a result of the routir.e operaticn of the Thrae E'.ile Isla. d '. nit 2 r.uclaar POner station.

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I GASEOUS EFFLUENTS A

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FIGURE 5.Y.1 EX?CSURE ?ATH'//AYS TO 3!OTA OTHER T;1 AN,i AN 4

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UNIT 2 SITE EIOTA LOCATICN P AT H1;AY DCSE (crid/yr)

D2er Nearest Site Atmosphere Land 5:undary

( 0. 4 mi. 2,"n')

0.6 i.0 Fox l

a 0.2 l

i Terrastrial Ficra P.accoon Atmosphere Hydrosphere 2

i 10 i

'e s;.r a t 20 Haron Duck Plant Cutfall 10 Fish Hydr sphare 10 8

Invertebrates 7

Algae

!;;te: Atmospreric doses include estinatas of plume dose, ground c:?ositicn dese, inhalation dese, and ingasticn doses. hare a;;repriate.

Hydrospheric datas include esti. mates of nearsicn dose, dose frc a consrption, ar.d sedimint dose where a;;capriate.

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NEPA Faculation Dose Assess ~2nt l

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l Fopula:icn dose ccomitments are calculatad for all ir.dividuals l

living within 50 miles of tne facility erpioying the same ncdels used for individual doses (sae Regula'.ory Guide 1.lC9 in pr2 para-tion).

In addition, pcpulaticr. deses assS:iat2d with the 2/pcrt l

of food crops produced witn the 50-mile region and the atnospheric ar.d hydrosp..eric transport of the m re nobile efflu2nt s;3ci~

_ch I

as noble gases, tritium, and carbcn-14 have been censidered.

.L i

5.A.1

';oble Gas Effluents i

For locations within 50 miles of the reactor facility, exposures to I

these effluents are calculated using the atmospheric dispersion j

J, redels in P.2gulatory Guide 1.111 and the dose r,cdels described in Section 5.1 and Regulatory Guide 1.109.

3sycod 50 miles, and until i

i the effluent reaches the northeastern corner of the United States, it i

o is ass._:ed that all tha ncble casas are di:p3rced uniformly in.he Icwest 1,000 meters of the atmosphere. Dacay in transit scas also considered.

Beyond this point, noble gases having a half-life greater f

i than ene year (e.g., Kr-85) were assumed to cc pi_sely mix in the troposphere of the ucrld with no removal achanis.r.s cperating.

Transfer i

o h f f

8 t).'

esN I

3 s

P

_2-of tropospheric air between the northern and southern hemispheres, altSough inhibited by wind patterns in the equatorial region, is ccnsidar2d to yield a her:spS2re average tropospheric residence tine

.i of ab ut t.ic years with r2spect to hemispheric nixing.

Since this

.i 2 :cnstant is quits sh:-t with r2s;Ect to the expected mid-point of plar,t life (15 rs), mixing in both 52ris; hares can be assured for evaluations o.ar the life of the nuclear f 3cility.

This acditional

cpulaticn dose cco.itrant to tha U. S. ;cpulation 'i3s also evaluated.

5.A.2 Iodir.es and Farticulates Released to the Atreschere Effluent nuclidas in this cate;ory dep; sit onto the gro;nd as tne affluent moves dc nwind, which ccntinuously reduces the concentration remaining in the plume. Within 50 miles of the facility, the deposi-tien model in Regulatory Guide 1.111 was used in conjuncticn with the dose models in Regulatory Guide 1.109.

Site specific data concerning production, transport and consumption of fccds within 50 miles of the riactor ware used.

Eay:nd 5J miles, the depositica.model 'ias axt:nded until iio effluent remained in the plume.

Excess food not consumed within the 50-mile distance was accounted for, and additional food production and consumption represeatative of the eastern half of the country was assumed.

Doses obtained in this nanner were then asstmed to be received by the nurbar of individuals living within the directicn 1

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F

,i sector :nd distance described above.

The population density in this re:tcr is takan to be representative of the Eastern United States, l

t

.nich is ; tout 150 pe:ple per square mile.

l E.4.3 Carb n-l' and Tritiu 213ase to tre ' t s;',are j

d s

Carbon-14 and tritium..er e assur:-d te disperse without dapesiticn i

in the sa.re manner as kryptcn-25 cver land.

Pc.<ever, they do interact with the cce&ns.

This ca;ses the carbon-14 to be rr :ved e

with an aircspheric residence time of 4 to 6 years with the oceans this, the equilibrium ratio of the j

being the -ifor sink. Fr T.

i carbon-i-to natural carbon in the at :sph2re.as deteer,ined.

This I

same ratio.as then assured to exist in,an so that the dcse received j

by the entire population of the U.S. could be estimated. Tritium i

as assured to mix uniformly in the world's hydrcsphere, which was m

assured to include all the water in the atmosphere and in the upper l

70 reters of the oceans. k'ith this radal, the equilibrium ratio of l

i 1

tritium to hydec;an in the envircnr. ant can be calculated.

Tha same ratio was assumed to exist in man, and was used to calculate the j

populaticn dese, in the sama manner as with carbon-14.

(

5.A.4 Licuid Effluents I

Concentrations of effiuents in the recalv; g ::ater within 50 niles of the facility. ere calculated in '.he sta nrrer :s descri'.id t

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f _' ' /

9 P tj f44 l

2

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2 s

t t

_4-d abcve for the Appendix I calculaticas.

No depletion of the nucl: des

cesent in the receiving water by deposition on the bottcm of the Susa,uehar.na River was assu 3d.

It :2s also assur2d that aq;atic i

I biota con: antra:e radioactivity in the sar.e manner as nas assu..3d I

for the Ap;=ndix ! 2valua: ion.

Hr.?ver, fcad ccnsurption values apprc;riate f;r the a verage individual, rather than the r xir.um,

..ere used.

It was assumed that all the spcrt and ccrmercial fish and shell fish caught within the 50 mile area. re eaten by the U.S. population.

22j;nd 50 r.iles, it was assumed that all the liquid effitent nuclid2s except tritium have deposited on the sediments so they make no further centribution to population exposures. The tritium was assumed to mix uniformly in the world's hydrcsph:-re and to result in an exposure to the U.S. population in the same manner as dis-cussed for tritium in gasecus effluents.

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