Regulatory Guide 1.109

Calculation of Annual Does to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1.

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RG-1.109
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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE OFFICE. OF STANDARDS DEVELOPMENT March 1976 4,

s. REGULATORY

GUIDE 1.109 " " CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING C 10 CFR PART SO, APPENDIX I 7.?OMPLIANCE WITH\'~ *%~5-I-~ ~USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission.

U.S. Nuclear Regulatory Guides are issued to describe and matte available to the publc Regultory Commission.

Washingon D.C 20. Attention.

Doceing and methods acceptable to the NRC still of implementing specific parts of the Service Section Commission's regulations, to delineate techntiques used by the sltff in evolu The guides are issued in the foffowing tIn broad divisions sating specific problems or postulated accidents.

or to provide guidance to eppli cants. RFegulatory Guides are not substitute% for regulatlons.

end compliance 1. Power Reactors S. Products with them is not required.

Methods end solution* different from those sot out in 2. Research and Test Roesctors 7 Transportation the guides will be acceptable It they provide a basis for the findings requistse to 3. Fuels and Materials facilitlee a Occupational Health the issuance or continuance of a permit or license by the Commission 4. Environmental and Siting 2 Antitrust Review Comments and suggestions for improvements in these guides are encouraged S. Meterials and Plant Protection 10 General at ail times, and guides will be revised. as appropriate, to accommodate corn mints and to reflect now information or aspetrience.

However. cuminvets nn Copies of published guiides msa be obteined by written request indicating the this guidea. f received within about Iwo months alter its Issuance will h. por divisions desired to the U.S. Nuclear Regulatory Commrsrsun Washington.

O.C ticularly useful in evaluating the need for an early revision 206. Attention: Director.

Office of Standards Development TABLE OF CONTENTS Page

A. INTRODUCTION

...................................................................... 1.109-7

B. DISCUSSION

........................................................................ 1.109-7 C. REGULATORY POSITION ............................................................... 1.109-8 1. Radiation Doses from Liquid Effluent Pathways.

.......................... 109-8 a. Potable Water ........................................................... 1.109-8 6. Aquatic Foods ........................................................... 1.109-8 c. Shoreline Deposits ....... ... ........................................... 1.109-8 d. Irrigated Foods ......................................................... 1.109-8 2. Gamma and Beta Doses from Gaseous Effluents .................................. 1.109-10 a. Gamma Air Dose Rates for Elevated Releases .............................. 1.109-10 b. Ganma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases ........................... 1.109-11 c. Total Body Dose Rates from Elevated Releases ............................ 1.109-11 d. Skin Dose Rate from Elevated Releases ................................... 1.109-12 e. Total Body Dose Rates from Ground-Level Releases ........................

.109-12 f. Skin Dose Rates from Ground-Level Releases ..............................

1 109-12 3. Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere... 1.109-12 a. External Irradiation from Activity Deposited onto the Ground Surface .... 1.109-13

b. Inhalation

............................................................... 1.109-13 c. Ingestion.

.................................................. 1.109-13 4. Integrated Doses to the Population ........................................... l.lO9-l1 5. Summary of Staff Position..........................................1.109-14

D. IMPLEMENTATION

.................................................................... 1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO THE AQUATIC ENVIRONMENT ................................................................ 1.109-17 1. Equation for Calculating Radiation Dose via Liquid Pathways .................. 1.109-17 a. Concentration in Environmental Media (Cip) .............................. 1.109-17 b. Usage (U ap) ............................................................. 1.109-17 C. Dose Factor (Dp "p ) ..................................................... 1.109-20 2. Equation for Liquid Pathways ................................................ l.l09-20 a. Potable Water ............................................... 1.109-20 b. Aquatic Foods.. ............................ 1.109-20 c. Dose from Shoreline Deposits ............................................ 1.109-30 d. Dose from Foods Grown on Land Irrigated by Contaminated Water ........... 1.109-33 REFERENCES FOR APPENDIX A .............................................................. 1.109-36 APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE ATMOSPHERE ............................................................................ 1.109-39 1.109-3 TABLE OF CONTENTS (Continued) Page 1. Annual Gamma Air Dose from Elevated Releases of Noble Gases .................. 1.109-39 2. Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose .............................................................. 1 .109-40 3. Annual Dose to Tissue from Noble Gas Effluents .............................. 1.109-40 a. Elevated Releases ....................................................... 1.109-40 b. Ground-Level Releases ................................................... 1.109-42 REFERENCES FOR APPENDIX B .............................................................. 1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 1. Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane ................................................................. 1.109-45 2. Annual Dose from Inhalation of Radionuclides in Air .......................... 1.109-46 3. Concentrations of Airborne Radionuclides in Foods ............................ 1.109-46 a. Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man ............................................. 1.109-55 b. Parameters for Calculating Nuclide Concentrations in Milk............ 1.109-55 c. Parameters for Calculating Nuclide Concentration in Meat ................ 1.109-59 I 4. Annual Dose from Atmospherically Released Radionuclides in Foods ............. 1.109-59 REFERENCES FOR APPENDIX C .............................................................. 1.109-60 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS............................................................................... 1 .109-63 1. General Expressions for Pý.pulation Dose ...................................... 1.109-63 2. Use of the Models ............................................................. 1.109-67 a. Population-Integrated Doses from Liquid Effluents ....................... 1.109-67 b. Population-Integrated Doses from Airborne Effluents ..................... 1.109-68 REFERENCE FOR APPENDIX D ............................................................... 1.109-69 1.109-4 TABLE OF CONTENTS (Continued) Page 1. Annual Gamma Air Dose from Elevated Releases of Noble Gases .................. 1.109-39 2. Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose .............................................................. 1.109-40 3. Annual Dose to Tissue from Noble Gas Effluents .............................. 1.109-40 a.. Elevated Releases ....................................................... 1.109-40 b. Ground-Level Releases ................................................... 1.109-42 REFERENCES FOR APPENDIX B .............................................................. 1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 1. Annual External Dose from birect Exposure to Activity Deposited on the Ground Plane ................................................................. 1.109-45 2. Annual Dose from Inhalation of Radionuclides in Air .......................... 1.109-46 3. Concentrations of Airborne Radionuclides in Foods ............................ 1.109-46 a. Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man ......................................................... 1 .109-55 b. Parameters for Calculating Nuclide Concentrations in Milk ............... 1.109-55 c. Parameters for Calculating Nuclide Concentration in Meat ................ 1.109-59 4. Annual Dose from Atmospherically Released Radionuclides in Foods ............. 1.109-59 REFERENCES FOR APPENDIX C .............................................................. 1.109-60 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS... ........................................................................... 1.109-63 1. GeneralExpressions for P p,,jlation Dose ...................................... 1.109-63 2. Use of the Models ................................... ........................ 1.109-67 a. Population-Integrated Doses from Liquid Effluents ....................... 1.109-67 b. Population-Integrated Doses from Airborne Effluents ..................... 1.109-68 REFERENCE FOR APPENDIX D ............................................................... 1.109-69 E 1.109-4 LIST OF TABLES Table Page 1 Summary of Staff Position -Methods of Evaluating Compliance with Appendix i .................................................................. 1 .109-15 A-I Definition of Points at Which Concentrations in Environmental Media (Clp)Should be Calculated ........................................................ 1.109-18 A-2 Recommended Values for Uap to be Used for the Maximum Exposed Individual in.Lieu of Site-Specific Data ............................................... 1.109-19 A-3 Adult Ingestion Dose Factors .................................................. 1.109-21 A-4 Teenager Ingestion Dose Factors ............................................... 1.109-25 A-5 Child Ingesticn Dose Factors .................................................. 1 .109-26 A-6 Infant Ingestion Dose Factors ................................................. 1.109-27 A-7 External Dose Factors for Standing on Contaminated Ground ..................... 1.109-28 A-8 Bioaccumulation Factors ....................................................... 1 .109-31 A-9 Shore Width Factors for Use in Equations (A-5) and (A-6) ...................... 1.109-34 A-10 Animal Consumption Rates ...................................................... 1.109-34 B-i Dose Factors for Noble Gases and Daughters .............................. 1.109-41 C-1 Adult Inhalation Dose Factors ................................................. 1.109-47 C-2 Teenager Inhalation Dose Factors .............................................. 1.109-51 C-3 Child Inhalation Dose Factors ................................................. 1.109-52 C-4 Infant Inhalation Dose Factors ................................................ 1.109-53 C-5 Stable Element Transfer Data .................................................. 1.109-56 C-6 Nuclide Transfer Parameters for Goat's Milk ................................... 1.109-57 0-1 Recommended Values to be Used for the Average Individual in Lieu of Site-Specific Data .......................................................... 1.109-64 0-2 Recommended Values for the Transport Times in the Food Distribution System ...................................................................... 1 .109-66 1.109-5

A. INTRODUCTION

Section 20.106, "Radioactivity in Effluents to Unrestricted Areas," of the Nuclear Regulatory Commission's regulations in 10 CFR Part 20, "Standards for Protection Against Radiation," estab-lishes limits on concentrations of radioactive material in effluents to unrestricted areas.Paragraph (c) of 5 20.1, "Purpose," of 10 CFR Part 20 states that licensees s;hould, in addition to complying with the limits set forth in that part, make every reasonable effort to maintain releases of radioactive materials in effluents to unrestricted areas as far below the limits specified as is reasonably achievable.

Sections 50.34a, "Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents -- Nuclear Power Reactors," and 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities," set forth design objectives and technical specifications to control releases of radioactive efflu-ents from light-water-cooled nuclear power reactors.

Section 50.36a of 10 CFR Fart 50 further provides that, in order to keep power reactor effluent releases as low as is reasonably achiev-able, each operating license will include technical specifications that (a) require compliance with the provisions of § 20.106 dealing with effluent discharge limits, (b) require that operating procedures for the control of effluents be established and followed and that eqi ipment installed in the radioactive waste system be maintained and used, and (c) establish re( :,-ements for reporting measured releases of radionuclides to the environment.

Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents," to 10 CFR Part 50 provides numerical guidance for radioactive effluent design objectives and technical specification requirements for limiting conditions of operation for light-water-cooled nuclear power plants.To implement Appendix I, the NRC staff has developed a series of guides that provide methods acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man. This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.The methods used herein are general approaches that the NRC staff has developed for application in lieu of specific parameters for individual sites. The use of site-specific values by the applicant is encouraged.

However, the assumptions and methods used to obtain these parameters should be fully described and dncumented.

The procedures and models provided in this guide will be subject to continuing review by the-staff with the aim of providing greater flexibility to the applicant in meeting the require-ments of Appendix I. As a result of such reviews, it is expected that alternative acceptable methods for calculation will be made available to applicants and that calculational procedures found to be unnecessary will be eliminated.

This guide supersedes portions of Regulatory Guide 1.42, Revision 1, "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors," which is being withdrawn.

B. DISCUSSION

Appendix I to 10 CFR Part SO provides guidance on the levels of exposure of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable.

This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses. These estimates can be used to implement Appendix I in lieu of site-specific phenomena actually affecting the estimation of radiation exposure.In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU).1.109-7 Appendix A of this guide describes suggested methods for calculating the estimated doses to man from discharges to the hydrosphere.

Appendix B of this guide describes suggested models and assumptions for calculatinr submersion doses from radionuclides discharged to the atmosphere, and Appendix C gives equations for estimating doses from radioiodines and other radionuclides released to the atmosphere.

Appendix D describes the models and assumptions for calculating population dose (man-rem and man-thyroid-rem) from radionuclide releases to the atmosphere and hydrosphere.

The models and assumptions described in Appendices A, B, C, and D of this guide are accept-able to the NRC staff for calculating doses to individuals and populations.

If other models are selected, they should include the same exposure pathways and physical mechanisms as are used in the models described in this guide.As discussed in Section III.A.2 of Appendix I to 10 CFR Part 50, the applicant may take into account any real phenomena or actual exposure conditions that affect or modify the estimate of radiation exposure.

Such conditions should include actual values for agricultural productiv- ity, residence times, dose attenuation by structures, measured environmental transport factors (suchas bioaccumulation factors), or similar values actually determined at a specific site.The applicant should provide e-ough information on the measurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.C. REGULATORY POSITION 1. Radiation Doses from Liquid Effluent Pathways The NRC staff will calculate radiation doses from potable water, aquatic food, shoreline deposits, and irrigated food pathways by using the following equations from Appendix A of this guide.a. Potable Water MU1100 M ,n R QiDaipjexp(-Xitp) (1)b. Aquatic Foods Raj'1100 U apM -At2 Rapi 1100 F QiBipoaipjexp(-Aitp) (2)c. Shoreline Deposits I W n 0 Rapj = 110,000 I QiTiOai [exp('Xitp)][l -exp(-'0t)] d. Irrigated Foods For all radionuclides except tritium: (3)ap veg p n dIexp( A t )D .[r[l -exp(-AEite)] Biv[l -exp(-xitb)]] Rapj Uap I i ih alpj L YvEi *J Uanimal n {QFd exp(Xith) r[ -exp(-Eite)] + Uap SiA aipj YvxEi BivDl -ep-lb]+ pexp(-itb)] + CIAwQAw} (4)For tritium: Rp -vegC D animal api = ap v apj + Uap Dapj L A"(w +QAw)(5)4 1.109-8 where Bip is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentratio., in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/lizer), in liters/kg; Biv is the concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;CiAw is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter); Ciw is the radionuclide concentration in water, in pCi/liter; D aipi is the dose factor, specific to a given radionuclide i, pathway p, organ j, and individual's age a, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in water, expressed as a ratio of the dose rate (in mrem/hr) and the radionuclide concentration in water (in pCi/liter); di is the deposition rate of nuclide i, in pCi/m2 per hr;F is the flow rate of the liquid effluent, in ft 3/sec;k is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle);Mp is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food) as described in Table A-1 (in Appendix A of this guide), dimensionless; n is the number of radionuclides that are to be considered; 2 P is the effective "surface density" for soil, in kg(dry soil)/m .Assuming a uniform mixing of all radionuclides in a plow layer of 15 cm (6 in.) depth, P has a value of approximately 240 kg/mi 2;QAw is the consumption rate of contaminated water by an animal, in liters/day; QF is the consumption rate of contaminated feed or forage by an animal, in kg/day (net weight);Qi is the release rate of nuclide i, in Ci/yr;r is the fraction of deposited activity retained on crops (which is 0.25 for sprinkler irrigation, 0.2 for particulates, and 1.0 for airborne deposition of radionuclides), dimensionless; R .i is the total annual dose to organ j of individuals of age a from all of the RaPj nuclides I in pathway p, in mrem/yr;Si is the transfer coefficient for radionuclide i which relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product)per pCi/day;t is the period of time for which sediment is exposed to the contaminated water, nominally taken to be the mid-point of the operating lifetime of the facility, in hours;tb is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours;te Is the time period that crops are exposed to contamination during the growing season, in hours;1 .109-9 th is a holdup time that represents the time interval between harvest and consumption of the food, in hours;T is the radioactive half life of nuclide i, in days;tp is the average transit time required for nuclides to reach the point of exposure.

For internal dose, t is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;Ua is a usage factor that specifies the exposure time or intake rate for an Uap individual of age a associated with pathway p, in hr/yr or kg/yr (as appro-priate);w is the water intake rate via fresh forage (28 liters/day for beef cattle and 38 liters/day for dairy cattle);W is the shoreline width factor, dimensionless; Yv is the agricultural productivity (yield), in kg(wet weight)/m2 A Ei is the effective removal rate constant for radionuclide i from crops, in hr" provided that AEN : Ai + Awl where Ai is the radioactive decay constant, in (hr)-I, and Aw is the removal rate constant for physical loss by weathering (Xw = 0.0021 hr-1 , which corresponds to a removal half-life of 14 days);Ai is the radioactive decay constant of nuclide i, in hr , AM is the water elimination rate constant (0.32/day for beef cattle and 0.28/day for dairy cattle);1100 is the factor to convert from (Ci/yr)/(ft 3/sec) to pCi/liter; and 110,000 is the factor to convert from (Ci/yr)/(ft 3/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose to the total body or any organ of an individual from the sum of the exposure path-ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.

2. Gamma and Beta Doses from Gaseous Effluents The NRC staff will calculate radiation doses from gaseous effluents using the following equations from Appendix B of this guide. The definitions of elevated and ground-level releases are found in Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors," and Appendix B to this guide.a. Gamma Air Dose Rates for Elevated Releases 260 I DA-7(o n~~ un ns I(Ek)IE(H,u,s,oz,Ek ik (6)where Aki is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration; DY(r,o) is the annual total gamma air dose at a distance r in the sector at angle 0, in mrad/yr;Ek is the energy of the kth photon energy group, in MeV/photon; 1.109-10 fns is the fraction of the time that stability class s and wind speed n occur for sector 0, dimensionless; I(H,utsoz,Ek) Is the result of the numerical integration accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and.atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (o). In addition, I is a function of the photon energy E,1 and is T = 1 4 kT 2 as formulated in Slade (see Reference I fi: Appendix B of this guide);'D Qn 1 is the release rate of radionuclide i, corrected fnr decay during transit to the distance r under wind speed un, in Ci/yr;r is the distance from the release point to the receptor, in meters;un is the me;'n wind speed of wind speed class n, in m/sec;AO is the sector width over which atmospheric conditions are averaged, in radians;and ua(Ek) is the air energy absorption coefficient for the kth photon energy group, in m 1.b. Gamma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases o3 Q '/ )D r ( or DF')Dy(r,o) or DO(r,0) = 3.17 x 1O4 I[/Q ](r,o)(OFi or (7)where DF'Y OF 8 I' I Dy(r,O) or D'(r,o)Qi[x/Q']O(r,e) 3.17 x lO4 c. Total are the gar,.na and beta air dose factors for radionuclide I, in mrad per yr/pCi per n 3;are the annual gamma and beta air doses at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;is the release rate of the radionuclide I, in Ci/yr;is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," for methods to estimate x/Q'); and is the number of pCi per Ci divided by the number of seconds per year.Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t] (8)where oT(r,e)DY(r,o)k is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr;is the annual gamma air dose associated with the kth photon energy group at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;1.109-11 SF is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless; t is the product of tissue density and depth used to determine a "whole-body" exposure.

This depth is 5 cm, which is equivalent to t = 5 g/cm 2;T(Ek) is the tissue energy absorption coefficient, in cm 2/g; and k)1.11 is the average ratio of tissue to air energy absorption coefficients.

d. Skin Dose Rate from Elevated Releases oS(r,O) = l.1ISFOY(r,O) + 3.17 x 10 ' Qi[x/QJ]D(rO)DFS (9)F where DFSi is the beta skin dose factor for the radionuclide i which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr.

This attenuation is for 70 micrometers or 7 mg/cm 2 .f tissue; and DS(r,0) is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/yr.All other parameters are as defined in preceding sections.e. Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF xi(r,o)DFBi (l0)where DFBi is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn 2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in 4 Appendix B of this guide);DT(r,) is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3.All other parameters are as defined above.f. Skin Dose Rates from Ground-Level Releases D 5 (r,0) = 1.11 SF + xi(rO)OFSi (1i)where D 5 (r,O) is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr.All other parameters are as defined above.3. Doses from Radioiodines and Other Radionuclides Released to the Atmosphere The NRC staff will calculate radiation doses from radioiodines and other radlonuclides released to the atmosphere using the following equations from Appendix C of this guide.i 1.109-12 a. External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF G cG(r,o)DFG.. (12)where CG is the ground plane concentration of radionuclide i, in pCi/m 2;Ci DFGij is the open field ground plane dose conversion factor for organ J from radio-nuclide i, in mrem-m 2/pCi-hr;DG(r,O) is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr;SF is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless; and 8760 is the number of hours in a year.b. Inhalation DA (r,o) R R xi(r,o)DFAi (13)where O (rO) is the annual dose to organ j of an individual in the age group a at location* CrO) due to inhalation of all radionuclides, in mrem/yr;DFA. a is the inhalation dose factor for radionuclide i, organ j, and age group a, ija in mrem/pCi;3 Ra is the annual air intake for individuals in the age group a, in m /yr; and xi(r,o) is the concentration of radionuclide i in air at location (r,o), in pCi/m 3.c. Ingestion o r v m .FL L 1)a (ro= 2DFIi -cV(r,+) + UaCim(r,o) + U.i(r,o) + Uaf Ci(r, (14)D. (ro)ja [I a 9 i a ai + a z (4 where ,CF(r,O), C.(r,o), C.(r,O) are the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg. These variables are determined using Equation (C-7) from Appendix C of this guide;D3 (r,o) is the annual dose to the organ j of an individual in age group a from inges-ja tion of all radlonuclides at location (r,o), in mrem/yr;DFlija is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi;f ft are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note: fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U Uvn, Um , UF are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a Ua' a a respectively, for individuals in the age group a, in kg/yr.1.109-13 4. Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1, 2, and 3. Because of the various conditions under which the equa-tions in Appendix D are used, they are not presented in this section. It is recommended that Appendix D be read for a detailed discussion of the staff's models.5. Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I is presented in Table 1.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.This guide reflects current Nuclear Regulatory Commission practice.

Therefore, except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as a result of suggestions from the public or additional staff review.II I 1.109-14 TABLE 1 SUMMARY OF STAFF POSITION -TYPE OF DOSE Liquid Effluents Dose to total body from all pathways Dose to any organ from all pathways Gaseous Effluents** Gamma dose in air Beta dose in air Dose to total body of an individual Dose to skin of an individual METHODS OF EVALUATING APPENDIX I DESIGN OBJECTIVE 3 mrem/yr per unit 10 mrem/yr per unit POINT OF DOSE EVALUATION COMPLIANCE WITH APPENDIX I EQUATIONS TO BE USED Location of the highest dose offsite*(see also Table A-I).Same as above.1, 2, 3, 4, & 5 1, 2, 3, 4, & 5 10 mrad/yr per unit 20 mrad/yr per unit 5 mrem/yr per unit 15 mrem/yr per unit Location of the highest dose offsite.*** 6 or 7, as appropriate Same as above.7 Location of the highest dose offsite.*Same as above.8 or 10, as appropriate 9 or 11, as appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ from all pathways 15 mrem/yr per unit Location of the highest dose offsite.,' 12, 13, & 14 Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.

Calculated only for noble gases.Evaluated at a location that could be occupied during the term of plant operation.

Doses due to carbon-14 and tritium intake from terrestrial food chains are included in this category.tt Evaluated at a location where an exposure pathway actually exists at time of licensing.

How-ever, if the applicant determines design objectives with respect to radioactive iodine on the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine: (l) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives; (2) whether changes in land and water usage and food pathways which would result in individual exposures greater than originally estimated have occurred; and (3) the content of radioactive iodine and foods involved in the changes, if and when they occur.1.109-15 APPENDIX A METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO THE AQUATIC ENVIRONMENT The equations for estimating radiation exposure to man from four principal exposure path-ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide. The equations can be used to calculate the annual doses to various organs of a child, 0 -11 years; a teen, 12 -18 years;and an adult, 18+ years.1. Equation for Calculating Radiation Dose via Liquid Pathways(A-l) is the fundamental equation for calculating the radiation dose to man via liquid effluent pathways.aipj C ip Uap aipj (A--)where Cip is the concentration of nuclide i in the media of pathway p, in pCi/kg;D ai is the dose factor which is specific to a given radionuclide.

i, pathway p, organ j, and individual's age a. It represents Lhe annual dose due to the intake of a radionuJide, in mrem/pCi, or from exposure to a given concen-tration of a radionuclide in water, in mrem per hr/pCi per liter;Raip is the annual dose to organ j of an individual of age a from nuclide i via apip pathway p, in mrem/yr; and U ap is the exposure time or intake rate (usage) associated with pathway p for lap .ge group a, in hr/yi or kg/yr (as appropriate). The three factors making up Equation (A-1) are discussed in the following sections, most of which were taken directly from the WASA-1258 report (Ref. 1). (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the BNWL-1754 report (Ref. 2).)a. Concentration in Environmental Media (Cip)The points at which concentrations in environmental media of interest should be evaluated are shown in Table A-1. The concentrations can be estimated from the mixing ratio M p , the bio-accui;ýulation factor Bip, the radionuclide release rate Qi, and other terms presented in the path-way equations that appear later in this discussion.

b. Usageý (Uap)The second term of Equation (A-l) is the usage term U ap. Usage is expressed as a consumption rate in kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the pathway p and age group a under consideration.

The NRC staff encourages the use of site-specific data, whenever possible, for param-eters such as those included in Table A-2. Such data should be documented.

In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Table A-2 are reconmnended.* In selecting usage values, not only the present land and water uses should be considered, but also changes in land and water uses made possible by such activities as chemical pollution abatement.

Radioactive material released into waterways may include long-lived radionuclides that have potential for accumulation in sediments and biota and may persist for many years --perhaps beyond the lifetime of the nuclear power station.1.109-17 TABLE A-I DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip)SHOULD BE CALCULATED SUBMERGED (single or multi-PATHWAY SURFACE -LOW VELOCITY SURFACE -HIGH VELOCITY port) -HIGH VELOCITY Fish (fresh and salt water)Invertebrates Shoreline Drinking water CO Discharge canal Discharge canal Discharge canal Nearest anticipated downstream supply***Nearest anticipated point of withdrawal for irrigation t Edge of initial mixing zone*Edge of initial mixing zone*Point of contact of diluted effluent with shoreline Nearest anticipated downstream supply,*Nearest anticipated point of withdrawal for irrigation +Edge of initial mixing zone**Edge of initial mixing zone**Point of contact of diluted effluent with shnreline Nearest anticipated downstream supply***Nearest anticipated point of withdrawal for irrigation- Irrigated crops Point where effluent has Point where effluent has Fresh water sites only.over the plant lifetime, AFresh water sites only.use projections over the or could exist.undergone prompt dilution near the surface (about 5:1 for large receiving water bodies).undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water).The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections is the closest point to the site where a drinking water supply exists or could exist.The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists____ PATHWAY Fruits & vegetables Leafy vegetablesa Milka,c Meat & poultrya Fish (fresh or salt)Sea fooda Drinking waterc'e Shoreline recreation e Boating Inhalation TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U EXPOSED INDIVIDUAL IN LIEU OF S]CHILD& graina'b 520.0 26.0 330.0 41.0 d 6.9 1.7 510.0 5 e 14.0 29.0 2 7 0 0.0 e 51 190P.O(infant)g SED FOR THE MAXIMUM ITE-SPECIFIC DATA TEEN ADULT 630.0 520 P?.0 64 100.0 310 65.0 110 16.0 21 3.8 5 510.0 730 67.0 12 52.0 52 ,O0.,e 7 3 0 0 f UNITS kg/yr kg/yr liters/yr kg/yr kg/yr kg/yr liters/yr hr/yr hr/yr m 3/yr aconsumption rate obtained from Reference 3 for average individual and age-prorated and maximized using techniques contained in Reference 4.bconsists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24? grain.CAn additional category of maximum individual (1-yr old) should be added for these pathways.Consumption rates are the same as the child's.dConsumption rate for adult obtained by averaging data from References 4, 6-9 and age-prorating using techniques contained in Reference 4.eData obtained directly from Reference 4.fData obtained directly from Reference 15.glnhalation rate for infant obtained by averaging data from References 10-14.1.109-19 C. Dose Factor (D aip.)Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref.

15) for body burden and ma):imur permissible concentration (r.IPC). Effective absorbed energies for the radionuclides are calcu-lated from the ICRP model. Appendix D of Reference 16 was used as a basic source of age-dependent dose factors for ingestion.

Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.The dose factors for external exposure were based on the assumption that the con-taminated medium is large enough to be considered an "infinite volume" relative to the range of the emitted radiations.

Under this assumption, the energy emitted per gram of medium is equiva-lent to the energy absorbed per gram of medium corrected for the differences in energy absorption between air or water and tissue and for the physical geometry of each specific exposure situation.

Material deposited from sedimentation in an aquatic systet, or from irrigation water onto the ground represents a fairly large, nearly uniform thin sheet of contamination.

The factors for converting surface contamination given in pCi/m 2 to the annual gaisia dose at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 4, 5, and 17). Dose factors for exposure to soil sediment have units of mnrern/hr per pCi/1n2 surface.A set of dose factors for 45 radionuclides was originally calculated for the year 2000 model (Ref. 4). These factors have since been recalculated using recent decay scheme informia-tion (Ref. 18) and expanded to include additional radionuclides.

The revised list is given in Tables A-3 through A-7; it contains several radionuclides for which the daughter is not listed separately (e.g., Ru-Rh-106, Cs-137-Ba-137m, and Ce-Pr-144). In those instances, the daughter's decay energy has been included in the factor.2. Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel. Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated.

The doses from the four pathways should be added to determine the total dose.a. Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below: Rapj = 1100 U ap Qjexp(-x. .t )Daipj (A-2)apF 1 p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.The sunmation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected.

The Q!/F termis in Equation (A-2) define the concentration of nuclide i in the effluent at the point of discharge.

The expression (QMM /F)exp(-A t ) yields the concentration of nuclide i at the time the water is consumed.I p i p This concentration is the term Cip in Equation (A-1). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system. The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake. Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 4.It should be noted that, depending on the hydrological dispersion model employed, the mixing ratio, M'Ip, or dilution factor may not be explicitly defined. In those instances (e.g., buildup of activity in a cooling pond), the relative concentration in the mixed stream (compared to the effluent concentration) may be supplied as a function of the radiological decay constarnt.

with any potential effluent recycling taken into account. Suggested hydrological dispersion ,:odels will be contained in another regulatory guide now under preparation on the subject of methods for estimating aquatic dispersion of liquid effluents from routine reactor releases for the purpose uO implementing Appendix I.b. Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations, 1.109-20 TABLE A-3 ADULT INGESTION DOSE FACTORS (mirem/pCi ingested)'JUCLIDE BO.E I 3 0.0 4BE 10 3.l18-06 bC 14 P.BUE-06 7N 13 B.37E-09 QF IS b.2SF-07 IPJA 22 1.70F-05 IlIA 24 21,2OF-Ob 1 5P 32 1.Q3F-04 20CA ul 1.87E-0'J 21SC Ub. 5.SIF-OQ 24CP 51 o.0 254.4 a n0 25mN 5b 0.0 2hFE 55 b.20E-0O 2bFE 59 U.3UE-0b 27Cf0 57 0.0 27C0 5B 0.0 27C0 60 0.0 28,NI 59 9.77E-06 28N1 63 1.30E-O0 284I b5 5,20E-07 2qCU b4 ).0 30ZN 65 U.SE-06 30ZN b94 1.70F-07 30ZN b9 1.03E-08 34SE 79 0.0 35RP A? n.0 355P 93 0,0 35.P 84 0.0 35BR 85 0.0 37RB 0b 0.0 37BR 87 0.0 37RB 48 0.0 37RR 89 n.0 38SR B9 3.09F-0'J 3BSR QO 7.61F-03 3RSR 91 5.82F-Ob 38SR 92 2.IbE-Ob 39Y go 9.63F-09 39Y 91M 9.10E-11 39Y 91 1.alE-07 LTVER 1.34E-n7 4.91E-n7 5.69E-07 9.37E-09 1.0 I .74E-05 2.?bE-0b 1. 21 E-05 0.0 I .nBE-08 S.57E-o6 I .I9E-07 2.79F-oS 1 .03E-09.7 5 -07/ .I, SE -{') 7 2. 15E-0b 3. 35E-O0 9.02E-O0 b.B7E-ng 5.3'JE-06 1 .54F-05 u .0, E-07 1 9SE-08 2. 6I-06 0.0 0.0 0.0 0.0?.11 F-05 I .?3E-OS 6.06F-()8 U.0 1IE-O8 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TnTAL 81)Y 1 .3UE-07 7.o5EF-0 ri.bqE-7ý. 37E-09 b.93E-OR I .74E-05 2.2hE-rib 7,

• 7F.-t0h 2. olE-nS 3.11 E-OQ 2.bbE-19.8 73E-.07 2. 0SE-OR 7.33E-06 3.9?E-06 2.JI1E-07 I .67E-1b U,72E-nb I .b3E-06 4.36F-Ob 3.1 3E-08 3.92E-OR 6.97E-08 3.731E0'I .37E-0O M.dOE-07 2.?PhE-n6 4 .2E-ný, 5.22E-O0 2.1 4E-O9 9.8UE-0b 4.28E-4b 3 .21 E-04 2.93E-0.5.89F-06 I .86E-03 P.ShE-07 9.31E-08 2.5RE-10 3.53E-I?3,7RE-09 1,i 3lI-O1 n n 5, qF -07*l 3 7EF-0 9 n.n I .711E-05 22.2SE-0b 0.n0.0 n n 0.0 0.0 n.0 0.0 0,0 0.0 ( n 0,0 0.0 0.0 0.0 0,0 0.n 0.0 0.0 0.0 0.0 0,0 0.0 0.0 KT)NEY I, S. 3 E-fl7 3. 71E-n7 5.69F-07 8. 37E-ng 0.0 I .74E-nc 22. ?6F.-06 0.0 0.0 I .OOF-0B 36RIE-06 l,6bE-07 0.0 0.n 0.0 0.0 0.0 0.0 0.0? 1 n F -n 1 03E-nS?. USE- n7 I ?O2F-OR 41, 5 6F. -n6 n00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 LUNG I .,OE-07 0.0 S.bqE-07'. $7F-09 0.0 I .74E-05>. 0.0 ,0.3. 53F-n9 0.0 0.0 1.23E-05-nb 0.0 ,00 n0.0.0 0,0 0 .n 0,0 0.00 ,00 0.0 0.0 0.0 n00 n,0 0,0 0.0 0.0 0.0 0.0 0.0 0.0)0.0 GI-LL I I .SiF-n7 2.bMF-0'i 5.bQE -07 6. 371F-09 I ASE-05 P. 26F-Uh 2.1I 7E -09 I ..ýJF -0i7 5.21F -05 1 .ttIE -07 3.h7F-O6 I .oW -05 5.4OF-06 1 .91F-05 ,022F-OS b790E-07 I1 .t i B F -O h 7 .i O-06 Q.70E-(6 2.49F-05 2. 9b-09 5, 38F-07 2.54F-Ob.,79F-OR u0nqF-13 0.0 4, 1bE-Oh 5. 7(E-07 8.3bF-19 0.0 MI,*4E-05 I .02E-nu 2.Q3E-05 4 , 2bf -05 1.02E-04 2,b7L-1 0 77bE7-05 Note; 0.0 means insufficient data or that the dose factor is <].OE-20.1.109-21 TABLE A-3 (Continued)

NUCLIDE 39Y 92 39Y 93 4OZR 93 0OZR 95 a0ZR 97 14tN q33 41.J N 5 QLNB q7 u2mO q3 4240 9q 43TC 994 43TC q9 43TC 101 44RIJ 103 40RU 105 LILRU 106 45RH 105 46PD 107 6bPD 109 47AG 1104 L7AG III 48CO 1134 48Co 1154 50SN 123 50SN 125 50SN 126 SISB 124 S1SB 125 SISH 12b SISB 127'52TE 1254 52TE 127M 52TE 127 527E 12qM 52TE 129.52TE 1314 52TE 131 52TE 132 52TE 1334 52TE 134 531 129 531 130 531 131 531 132 BONE 8.46F-10 2.6E-09 4 .IqF-08 3.0UE-OR I.68F'-09 2.55E-08 b,2sF-09 5.23E-1 I 0.0 0.0 2.47F-10 I 2bE-07 2.54F- 10 1 .85E-07 I .S4E-08 2.75E-O0 1 .22E-07 0.0 0.0 1.6bOE'-07 5.82E-0R 0.0 0.0 3.1 IF-05 8. 3bE-06 8. U6E-05 2.81E-06 2.23F-Ob 1. 15F-Oh 2.5E-07 2.b8E-Ob 6.78E-06 I 1 IOE-07 1015E-05 3. ISE-08 S1,74E-06 1.97E-08 2.53E-05 4.63F-08 3.24F-08 3.27E-Ob 7,57E-07 4, tl6E-06 2.03E-07 LIVER 0.0 0.0 2.3uE-Oq 9.76E-09 3.39F-10 S. 33E-09 3.46RE-09 1.32E-1 I 7.52E-nb U,31E-0b 6.98E-I0 1 .8hF-07 3.67E-1 0 0.0 0.0 0.0 8.86E-08 1 .47E-07 I .77E-07 2!.'JRE-07 2.44LE-08 3. 1qF-Db I .84E-0b 5.16E-07 1 .6AF-n7 1.68E-Ob 5.30E-00 2.4nF-08 2,3'E-n8 5.bhE-09 9.73E-07 2.37F-Ob 3,95E-08 4L,30E-06 1. 19E-0FB 9, 47E-07 5.24E-09 1.6LAF-0b 2.80E-08 2, 13E.-08 2.8lE-Oh S. 96E'-06 5.43E-07 TOTAL BODv TH)ROID 2.07E-1I 0.0 7.40E-11 n., 1.09E-09 0.0 6.61E-09 n.0 1.56E-10 0.0 2.05E-09 o0n 1.36E-nq n.n L.e2E-12 0.0 2.03E-07 010 8.20E-07 A.('9.9nE-Aq n.0 5.OUE-08 o.n 3.60E-19 n.0 7.qgE-0R 0.0 6.ORE-Oq 0.0 3.48E-07 0,0 S.SIE-OR 0.0 9.UIE-Oq 0.0 U.OOE-08 0.0 4.80E-04 0.0 1.21E-0B n.0 1.02E-07 0.0 5.AgE-OR 0.0 7,6OE-07 L.38F-07 3.79E-0 7 1.39E-07 2.JIE-06 4,92E-07 I.IIE-0.b 6.79E-09 4.J8E-07 1.9BF-09 U.ISE-07 7.0SE-09 9,q2E-0M 3,IIE-09 3.59E-07 8.07E-07 9.26E-07 1.73E-06 2.3AE-OR 8.16E-0B 1.82E-06 3.qSF-06 7.66E-09 2.IE-0B 7.06E-07 1.34E-06 b.22E-O9 1.62E-OR 1.51E-06 I.BOE-06 4.06E-08 3.92E-03 1.3nE-0' 2.,3E-05 9.22E-0b 7.23E-03 8.R1E-07 2.85E-OIA 3.41E-06 1.95F-n3 1.93E-07 7.15E-05 KIDN EY 0.P 0.0 8.99E-O9 I .SUF-08 5 1 P .E -10 5,58E-09 3. U 5 E-0q I .5AE-1 I I O0hF-AR 2,34E-nb ().bOE-09 7.07E-n7 1 .'9E-07 5.32E-0b 3.76F-07 1 ..32E-06 I .02E-O1 2. 91E-n7 7.8SF-nA 3.50F-nb I4.6F-06 0.0 0.0 0.0 0.0 0.0 0.0 I .09E-05 2.75E-05 LAI*,LRE-07 Li,.!lE-n5 1.3?E-n7 8.5E-06 R.b'E-nf 1,58E-05 2.57E-07 2.09E-n7 60 OSE-(b 3.UIE-Oh I. O.E -05 , bhE'-07 n.0 0,0 0.0 ,00 0.0 (0,0 0.0 0.0 0.0I 1 ,S2E-10 I .9SE-OP 0.0 (1.0 0.0 0.0 0.0 0,0 0.0 2.1 8E-Ob 2.33F-04 7,05E-n7 I .53E-n7 0.0 0,0 0.0}0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Gl-I.Ll 9

• SO F -6C'5 2.U3f -Oh I O5E -na 2.1 OE -05 t.SiF-05 U
• 7 F-OR I .b??F -n, ,153F-n7 b.08F -('6 1bF-05 7 6 7E -('74 1,07Et-O5 b. 0Laf-it, 2.2bF-n5 7 .7 a"E -r* S b. 33E-05 2.'3E-0S 7.95F-O5 I .97F-O0 9.40F-05 S QO2E-nh-1,07E-05?.27f -15 8. b8F -Ph 2. 37Fl-08 9.4 £0E-05 7.*71 F-05 Li. I 7F -00 1 .92E-nt, I .57F-I~b 1 .n2E-07 I 1.109-22 TABLE A-3 (Continued)

SUCLIDE 531 133 531 134 531 135 55CS 13U 5SCS 135 55CS 13b 55CS 137 55CS 135 55CS 139 569A 139 5654 1 a 0 5bBA IUI Sb8A IUP S7LA 1UO 57LA I U1 57LA IL2 58CE I U 5CE 143 58CE tUQ S9Pq 143 59PR 10I4 6OND lU7 6IPM ¶LI7 61PM I aB7 6IPM tuB 61Pm 151 62SM 151 b2SM 153 63EU 152 63EU 154 63EU 155 b3EU 156 65TB IbO b740 16bM 74M~ 191 740 185 744 187 52PH P O 8381 210 84PO 210 BONE 1.43F-06 1 ObE-07 4.43F-07 2.1 3E-09 6.2?F-05 I q.F-05 b.51F-ob 7.98E-05 5. 5F-08 3.£4 F-Os 0 .7 1 F-O0S 2.03E-05 0.0 P. 13E-08 2.SOF-OQ 3.19E-10 1.28E-10 q,3 IE-Oq I.%5E-09 u.BQE-07 9.21E-09 3.02E-1 I h.30E-oq 7.55E-08 3.07E-08 7, 1BF-09 1 .52E-09.l9 7F-I 0 6.91E-08 8.5RF-IO I .q5E-O7 6. 1bE-07 5.61E-08 I .37F -08 4.70E-08 2.70E-07 9.9?E-09 40.bE-07 I .03E-07 I .53F-02 0.b2E-07 3.57E-OU LIVER 2.USF-06 2.SRE-07 I .I 7E-06'J' (IQE -0B 1I USE -04.I 80E-a5 2.57E-o5 I. .OE-0O I. OoF-o 7 5.08F-08 5.92E-I I 2.55E-08 3.56E-i 1 2. 19E-1 I I .26E-O9 9.91E-1l 5.82E-11 6, 3£4E-09 I.22E-O0 2,uE-07 3 .70aF.-O0 I .25E'-11I 7.28E-09 7 .10 E -09 7.96E-09 I .I9E-09 2. 1SE-I 0 1.1 7E-1 0 1.1I9E-0B 7.16E-1 0 U1 ,L"JE-OB 7o.7E-08 1 .22F -n8 I .ObE-0 0.0 13.44E-09 3.24E-09 I. 35E-07 8.62E-08 U.38E-03 3.19F-Ob 7.57E-o0 TOTAL RODY THYROID KIDNEY 7.57E-07 1.03E-n7 (429E-n7?. 3nE-os 1.21E-OU 8.OOE-06 I .85E-05 7. 1SE-05 S.. iE-ns I .SE-08 2,84E-09 I .3E-06 1.59E-09 I .3UE-09 3.30E-10 I .62E-1 I 1 .£4S5- 11 7 .18E-10 1.3SE-10 2.bE-08 4,57E-10 1.53E-12 4.35E-I0 2.P7E-Oq b.OSE-09 6.OOE-t0 S.7qE-1 I 5.92E-1 I 2.BbE-09 5.23E-1 I 3.9IE-O0 5.39E-08 7.88E-0Q I .71E-ng 5.FbE-09 bAlE-08 3.46E-10 1.4?E-08 3,02E-08 5. £E-Oa 3.97E-08 8.60E-n5 4.77E-04 3. 74E-05 I .5jE-n0 D.0 0.0 0.(I 0.0 0.()0.0 0.0 0.0 0.0 0.0 0.0 0I.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 0.0 (0.0 0 .0 0.0 0.0l 0.0 0.0 0.0 0.0 4. 33E-flb'.*5 E-9 07 1. 86E-.nh 2. 4 E .. n£4. OE..0n I , 3E..n5 3. 71E'.-)5 8.02E.-n8 4.07E-08 6.£7E-- I R.6bE-09 3.3tIF-I 1.,SFE-II I,.95E-1t 0.0 0.0 0.0 5.3.E-10 I .21E-07 2. 1 3E-09 7. 06E-1 2 I.25E-09 1I1 3UE-08 1 .2 1IF-O0S 2.25F-09 4.O7-1 0 2 .0 9 F -1 1 .33E-08 2.3?F-10 2.775E-07 3.621--07 5.,LIE-rib 7.09E-09 I.94E-08 1.26E-07 0.0 0,0 0.0 1.23E-n2 3. 84E-05 2.52E-03 LUNG 0.0 0.0 0.0 3.83E-2,OSE-(I .S9F-I ,23E-1 .Q2F-3.70E-3.92E-I '46F-2, 02E-I .2UE-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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GI-LLI 2. 18EOb 2.51F-1 0 1.31E-06 09 1.58E-08 05 2.%9E-O0 06 4.. 21F-07 06 2.92E-0b OS 2.10E-06 09 4.65E-13 09 0.0 11 1.72E-07 08 11 2,22E-17 11 0.0 Q,25E-OS 4.25E-07 2,42E-05 4,S6E-05 I bSE-OS 4,03E-05 4.33E-18 3.49E-05 8.93E-06 6. 7E-05 9.34F-05 3,22E-n5 S *25E-Ob 2,55E-05 2.56E-05 5.48E-05 9,60E-O0 7.26E-05 4.33E-05 0.0*.bSE-07 1,56E-05 2,82E-05 5,42E-05 4.75E-05 6,36E-05 1.109-23 TABLE A-3 (Continued) NUCL B8RA 88RA 8BRA 88RA B8RA B9AC 89AC 90TH 90rH 90TH 90TH 90TH 90TH 91PA 91PA 92UL 92U 92U 92U 92U 92U 92U 93NP 93NP 93NP 9'PU 94PU 9UPU 9IJPU guPU 9JPU 95AM 95AM 95AM 96CM 96CM 96CM 96CM 96CM 96CM 9bCM 98CF IDE BONE 223 4.q8E-03 224 1.b2E-03 225 h.57E-03 226 3.05F-01 228 1.12F-01 225 4. -1F-06 227 1.88E-03 227 1.37E-05 229 4.96F-OU 229 R.ObE-03 230 2.08E-03 232 l.SOE-03 23Q .9.02F-08 231 4.I4F-03 233 5.26F-09 232 u.l4E-03 233 8.7?E-0O 234 8.37F-014 235 8.02E-04 23b 8.02E-O4 237 S.53F-08 238 7.67F-OU 237 l.38E-03 235 1.37E-08 239 1.20E-09 238 6.7SF-OU 239 7,60F-04 240 7.58E-04 2U1 1.5bE-05 242 7.22E-04 2L4L 9.60E-0O4 241 8.IOE-04 2Q2M 8.32E-0O 2i3 8.12E-0O 2U2 1.58E-05 243 b.43E-0O 244 4.851-04 24S. 1.03F-03 2U6 1.02F-03 247 9.95E-04 2'8 8.27E-03 252 1.96E-O4 LIVER 7.bbE-Ob 3.90E-Ob 7.79E-06 5.75E-06 3.1?E-06 6,07F-06 2. 2.4BE-07 3.41E-06 1.21E-O04 1 I1 BE -O04 I .OIE-04 4.*72F-09 I.56E-0l I .0bE-09 0.0 0.0 G00 0.0 0.0 0.0 0.0 1.20E-O0 3i,6E-10 1.18E-1O.31E-05 I OMiE-OQ 1,04iE-04S 9.4l7E-07 990E-05 I I 1BE-O4 2.79E-04i 2.78F-00 2.7 3E-O0i I .64E-ý05 2.QIE-0OJ 2.07E-04 2.B8E-O0 2. 88E-04 2. B3E-O0 2. 33E-03 0.0 9.95E-OU 3.23E-04 I .31E-01 2.21E-01 1.21E-01 2,QsE-07 I I II E-0Q 3.96E-07 I.b8E-AS 3.95E-O0 5.76E-05.4,9?E-05 2.32E-09 I .61E-Ou Q,2AE-In 2.95E-04 5.29E-05 5. 1RE-05 A.86E-05 4.97E-05 I .47E-O0 4.55E-05 5.5qE-05 2.1 3E- 10 6.4AE-1 1 1 .67E-n5 I .88E-05 I.88E-05 3.33E-07 I .79E-05 2.13E-05 5.26E-05 5,47E-05 5.24E-05 I.OUE-Ob 3.77E-05 2.BRE-05 5.BIE-05 5,BOE-05 5.72E-05 4.71E-O4 4.95E-06 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 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 0.0 0.0 0.0 0.0 0.0 0.0 0.0 000 TOTAL BODY THYROID 2.17F-04 1.11 E-oiU 2.21F-ou 1.b3E-04 8.84E-0s 6. 90F-6 7 R.03E-05 tl IE-Ob 4.67F-05 5.80E-OU 5.b9E-04 U.'3bE-ou 2.b7E-OR 1.0 3.99F-nq 4.47E-04 2.0TE-OQ I 40E -no 2.27E-07 I,75E-0U I *7E-04 I .26E-n9 3.S5E-10 7. 1* E-o0?.9bE-05 7.96E-05 I .53E-nS 7.SRE-n5 9.03E-05 3.QbE-OU..O8E-n4 3.95E-0O 4o.7E-0b SI *7bE-0O 1. 3LE-04 2.71E-04 2.7,1E-n4 2.67E-O0 2.20E-03 0.0 KIDNEY .LUNC 0.0 0.0.0 0.0 0.0 ,0.0.0 0.0 ,0.0.0 0.0 n010 0.0 0.0 n100 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 0,0 0.0 0.0 11.0 0.0 0.0)0.0 0.0 0.0 G[-I.'.'3.2 E-Ou S.,32E-Ou 5.64E-05 4.07E-04 7.q'E-05 5.JOE-Ou 5.h3E-Ou 5,12E-Oa 6,O2E-OS I *?'E-On 1.13E-Oa b.?T7-Ou I , 4F -0s b. 72E-0ýb,27E-05 b. 1 UE-05 7,BIE-05 5. 7bE-OS t.bbE-O0 7.94E-A5 7qUE-05 2.a0E-05 7.30E-05 h1b6F-05 6.78E-05 l.u0E-O0 6.5 SE-os q.,5SE-05 9,75SE-OS 7.02F-05 9. 34E-09 9. 73E-Oi 7.92E-05 7.8IE-09 7.55E-05 7.0F-05 6,9I1L-05 q. 09E-05 1.87E-O.3 2. 88E-04 I 4 1.109-24 TABLE A-4 TEENAGER INGESTION DOSE FACTORS (mrenm/pCi ingested)NUCLIDE BONE LIVER TOTAL B:oY I H 3 6C 1'J IINA 22 27C0 513 27C0 bO 38SR B9 38SR 9o 39Y qo 39Y 91 unZR 95 41,NB 95 44RU 103 OULRU job 505N 123 SPTE 1254 52TE 127 52TE 129M 52 T E 13?531 129 531 131 531 13 95cS 134 55CS 137 5b0A 1U n 57LA 140.5.1CE I1i0 5RCE I1aQ b3EU) 154 92U 232 92U 234 gaPU 238 9UP I 23-QUPU 240 9'PU 2a!95AM 241 9bCM ?42 96CM 24U 0.0 7.55E-07 2.36E-09 ,00 0.0 1 .OE-02 3. 3OF-08 1 .9hE-07 3.72E-08 7.2JE-09 2,37F-07 U OOE-Ob U .3AF -05 3.93E-06 1.51E-07 I bhF-05 3.55F-O0 L.bbF-O6 5.57E-0h 2. 03E-Ob 8.05E-05 1 .07F-O0 2.83E-05 3.43 *8F -09 1 .2bE-08 7.22E-07 1 I5E-Ob 60.bE-03 1,22F-0,3 5,£0E-0a 9.2bE-04 9,25F-04 u.03E-07 9,q3E-04 2.26E-05 b

• hL F-0 L I ObE-07 7 .55E-07 2. 35E-35 9.92F-67 2. 76F-nb 0.0 0.0 0.0 I .2'JE-08*.36E-0q 0.0 0.0 7,22E-o7 I .37E -0h 5.3?E-OM 5.15F-Ob 2,22E-Ob 3.92F-O0 7.87E-06 3."UE-Oh 1 .9QE-01 I lUUE-0LJ 3.u4E-os I .72E-09?.9bE-07 I .OnE-n7 0.0 0 0 I I* 1 E-O0 I .29E -n4 I .30F-oil 1.852E-o (.1 7E-nU 2,33E-05 3. 33E-0O I .06F-A7 7.SSF-07 2. 3SE-05 TqYq!10 1.n0E-07 7 .SSE-07 2.35F-05 2.26E-Ob 6. 30E-Ob I .3E-15 2.57E-03 A.87F-ln0 5.?P3E-n9 8.6hE-nQ?.u7E-OQ 1 OhE-07 5.03E-07 1 .0E-Ob 5.0AE-07 3.23F-08 2.61E-nb 2.1 nE-n6 1 .31F-05 U.6qE-nh I OhE-Ob nO 0.0 n o 0.0 0~o 0 .n 0,0 I5,13E-07 5.37E-07 I .03E0O7 5,30E-06 235SE-6 5 2.27E-03 b.?5F-0U 0.0 (USE n 0 0.0 ADULT 3.75E-nS 0.0 0.0 T 0.0 DOSE' 0.0 0.0 FACTOR) 0 ° 0 0.0 0.0 0.0 0.0 I .3JF -05.31E-05 4.49F-n5 2.4? eo-O0 1 .O9F-O0 7.53E-05 2.68E-05 I .78E-05 1 .6SEF-0s I .IE-o0 6. 31F-05 I ,07F-05 I .22E-0O 5.R0E-05 8,00E-05 4.31E-07 1.49E-06 2,50E-06 OC I -)NF Y I .06F-07 7.55F-n7 2. 35F-05 GI-LLI 1.0h-07 7.55F-07 9. OhE-05 5.05E-05 I.fPE-06 4.59E-10 3,83E-O8 R.7qE-ng n,2tE-0 7.UnE-05 2.ORE-05 2.2QE-05 2.31E-05 1.02E-00 6.66E-05 I .50E-06 U.n3E-05 0.0 0.0 o.6 0).0 0,0 0.0 0.0 0.0 0.0 2.35E-05 2.24E-Oh 1.91F-05 1.q2F-06?.33E-09 4.tUE-Oh 0.0 Q.8F.-0O n.O 2.29L-05 0.0 1.70E-04 0.0 5.12E-05 0.0 6.72E-05 0.0 6,14E-05 0.0 7.30E-05 o.0 6bE6F-05 0.0 b.bbE-05 0.0 1.28f.-07 0.0 7.17E-05 0.0 7.80E-05 0.0 7.42E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-25 TABLE A-5 CHILD INGESTION

DOSE FACTORS (mrem/pCi ingested)NUCLIOE BONE LIVER TOTAL B.11Y I H 6C I INA 27C0 27CO 38SR 39Y 39Y, (J1NB 44 RU 44LRU SO SN S2TE 52TE 52TE 531 531 55c S SscS 56BA 57LA 58CE SOCE b3EU 92U 9?U 911PU 94iPU 94PU 94 U 95AM 96CM 96CM 3 22 58 bO 89 qO 90 91 95 95 103 lob 123 1 25H 127 129M 132 129 131 133 137 110 1 a1 I a 1 154 232 234 238 239 2a0 2at 201 242?' 11 0.0 2.26E-06 5. 89E-05 0.0 0.0 1.* 38F-03 1.*72E-02 4,1. E-08 5.65E-07 1 .04F-07 1 .95E-08 6,78E.-07 I*1.19E-05 1 .31E-0(1 t I 1'JF-05 4A.50F-07 41.95SO5 I .02F-O5 1 739-E -05 1 .63E-05 5,98E-06 2,24JE-041 3. 12E-04 8.26E-05 I .01E-08 3.76E-OR 2,14'E-06 2.58E-0b 1 .77E-02 3,57E-03 I .21F-03 1 .32E-03 1 .32F-03 7. 12E-07 1.4£2E-03 6,74E-05 1. 12E-03 2.03E-07 2.26F-06 5,89F-05 I .8SE-nb 5. 17E-06 0.0 0.0 0.0 o,0 2,012E-08 8. 32E-09 0.0 0.0 1 .641E-06 3.09E-flb t .20E-07 1 .38E-05 UI.5OE -06 8.S(1F-06 1 .67E-DS 7.38E-06 3.77E-fl'3.02E-04I 7.2SE-n8 3.52E-09 I BR8E-08 6. 70E-017 2.08F-07 0.0 0.0 1 .52E-04I 1 .62E-04i I .63E-noL b.211E-n4 5.28E-nS 5. L f -0 1 5.58E-flb 1 .55E-05 3.95E-05 41.36E-0 3 I

• I3E-oq I .56E08)2.?OE-OA 6. I IE-09 2.71jE-07 I USJE-06 3.22E-0b I .S2E-0b 9.65E-06 7.65E-06 5.'I2E-Ob 3.81EF-05 I 426E-05 2,90E-06~2,03E-07 2. 26E-06 S.8QE-05 TH~YRODI 2.03E-07 2.26E-06 5.R~9E-05S

K I )NEY 0.0 0.0 o.0 0.0 0.0 0.0 0.0 I .73E-06 3.20E-06 3. 1 OE-07 1.58E-O5 b.62E -05b 2.79E-02 5,USE-03 1 .7F-0_0.0 (USE 0.0 ADULT 0.0 0.11 ,).0 DOSE 0.0 0.0l 0.0 FACTOR) 0.0 (.0 0.0 0.0 0.0 0n0 JS. iSF-OS.2 .8b -051 7. 77E-05 2.50F-05 1 .J44E -05 I

• ThF -n03 I .k5F-va 1 , I OF -OS.1 .'0?f-fl S5.96EF-05

7 .89F-O5 LI

• 9L .f7 1 .43E-06?.Q9E-oh LUNr P .0 3E -07 PQE-06S G; I -LL I 2.0 3E-07 2. S7k-Ob 4 8. 02E-05 41.50F-05£1.SSE-0b 1 .I QE-09 2.80E-09 I.14 (E -07 2.03E-07 1 .26E-03 2.2 1 E-04J 3.09E-OS 3.27E-05 13flnE-05 1 .81E-08 9,9&E-05'1.41hE-06

6.99E-95 0.0 0.0 0.00 0.0 0.0h 0.0 0.0 0.0 0.00 0.0 0.0 0.0 0.0 n , n n , u.19F-05 3.54E-05 u.32E-08 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2.04FI-0(, 1 .8ar-06 0. *21 E-0b 1.noQE-011 2 .36E-05 I .711F-0'J ai. /Ok -05 b.91L-OS 6. 3eF -0'3 7 .50EF -V5 6

• PSE -0 6 1SL -05 I .32F -0 7 7 .37 F -f'5 8.03E-05 7 .bUjE -OS Im Note: 0.0 means insufficient data or that the dose factor is <I.OE-20.O

I 1.109-26 TABLE A-6 INFANT INGESTION DOSE FACTORS (mrem/pCi ingested)NI b C 27C'38S1 385 39y 4 1 P(50S~52TI JCLTr)E qti'*E.3 0.0 14 U.81F-Ob A 22 1.OnF-OLI LIVER TflTAL ~VlDy 3.0 7F-o7 4.*81 F-ob I *00E-nd 3. 07E-07 U.BI E-06 I OO0E-04 T H4 Y 4 110 3. 07E-07 a0, 4 B I-n0b I.o 0F -04 K 1 3N F Y LONG 3. 07F-07 6 1 E-Ob OO.0F-04~GJ-LLI 3.07E-07 2

• 45E-Oh aJ Sa 0.0 3.78E-06 9.26E-06 0.0 0 .09.79E-0 60n 0.0 1 .07 E- 05 2.56E-05 0.0 n0. 0 2bF R C 2,q3F-03 0.0 A.U2E-05 0.0 (USE 0.0 5."l8E-05 R 90 2.91F-02 0.0 6.U0E-03 6.0 0.0 2 F-04 40 BQIE-08 0.0 2.41E-!ý9

0 .n ADUL.T .01.29 0 Q I I. 2S9F -0h 0.0 3.33E-OR .0 0 (.0 8.27E-05 R .5 ? .IIF -07 5.32E-nR 3.78E-08 n .n 0 .0 ?.38E-05 Q P95 I.g9E-nR I. 75E-1)8 1 .0 3E -1 0.0 DOSF 0 .0 1 .LJE-Oc J 103 1.OilE-0 0 ,0 U.BSE-07 n .0 1.0 1.7F0 J 1.06 2.5"&E-05 0.0 3.12E-16 0,0 0.0 19E0 N 123 2.7'9E-0Li Q.33F-oh h.96E-lb 4.33E-(16 FACTOR) 0.0 b.41E-05 E1254 2.'J3F-0'S 5.19E-nb 3,20E-flh R.OnE-OS 0.0 1.17E-05 b 5 5 u 5 5 5 52TE 127 9.58F-07 52TE I?9M 1.05F-04 521E 132 2.t3F-05 531 129 2.95F-09 531 131 3.U2E-OS 531 133 1,2bF-05 55CS 130 U.SAE-04 55CS 13 6.53F-O0 56BA 1'&0 1,74E-00 57LA 100 2.12E-08 S8'E 141I S.OOE-08 58CE lU4 0.49E-0b 63EU 154 4.30F-06 92U 232 3.66F-02 920J 234 7.u00F-n3 qAPO P38 1.71F-03 9'IPU ?39 1.70E-03 qqpU ?'40 1.78E-03 94PU P.01 11OhE-0b 95AM 241 1.93F-03 96CM 2U2 1.43E-nu 96CM 244 1.bdE-03 3. 1 9F-n7 3.61F-05 I n05E-05 2. IbE-OS 401 0F-05 1 BUE -05 9~ .2 4E-0 4 7 .31 -4 1 '75-n7 5. 17E-ng 4:91F.08 1 .7 7E -0 h O .RUE-n7 0.0 0.0 2.1 BE-a04 2. 2bF-q0 22 8F? E- fl I .37F-D7 I .01F-n3 I UOOE-04 1.6 7E -00 2. 06E-n7 1 .60E-05 0* 76E-Oh 7 .76E-05 2.3RE-05 S.'BE-06'7.75E-0 7 3.q9E-05 I *99E-'n5 h.* 79 F-02 I .31E-62 u.*35E-0 S..0 0.0 n,0 0.0 0.0 ,0o0 2.?27E-05 6. 33E-05 A, 08F.---05 4.46JE-07 1 .53E-06 3.*27E -06 6.97E-05 0. *20E-05 8 qqF-0b 2

• I E-fO)5.75E-IQ 2.0?E-n7 3.29E-07 2.68E-03 4.71EC-04 0 .25E-q5 0
• I E-1)5 0 .45E-05 2.70E-OP 1 .IIE-nu 9 .Q9F-nb 1 .04E-04 0.0 0 5 0).00.0 0l,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9.42E-05 R.81E-05 I .07E-07 0.0 0.0 O.0 0.0 0.0 0.0 0.0 0l.0 0).0 0.0 0.0 (0.0 n0.0 I .OuF-04 2. 39E-05 I .85E-04 4.*7bE -05 7.*34E -05 6. 72F-05 7.98E -05 7.*29F -09 7.28E-05 I .40OF-07 7.8'4E-O5 13.b,3r-05

8. 12E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-27 TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND*tmrem/hr per ptl/'.)TOTAL BODY SKIN TOTAL BODY sKirt i H 4BE b C 74 9F I TMA-11 NA 1P 20CA 2 1 S C 214CR.25MN 25MN 26FE 2bFE 27C0 27C0 27CO 28NI 28NI 28NI 29CU 30ZN 3nzN 3'JZN 34SE 35BR 358R 35BR 37RB 37RB 37RB 37R8 38SR-38SR 38SR 3ASR 34Y 39Y 39Y 39Y 39Y 3 10 18 22 32 U 1 Ub 51 50 5b 55 59 57 58 6n 5q 63 65 ba b5 694 69 79 82 83 85 87 88 5Aq 59 90 92 90 914 91 q2 93 0'.0 0.0 7 60kE-0q b. 0FO-09 I ,66E-08 2.50E-0B 0,0)3.'JlE-09 0 .nO -O I *30F-08 2.20E-I0 9.60E-09 1 *BOE-ORq 0.0 9. OE-t0 7.OOE-09 1, 70F-08 3. 70E-09 I .50E-09 UQ,00F-09 2.90E-09 0.0 0.0 I .90E-AA 6 .9O0E -I b.UOE-t 1 I .20F-08 0.0 6.30E-1O 3.50E-09 I .50E-08 5.60F-1 3 0.0 7.o I OE-Oq 9.OOE-09 2.20E-12 3.80E-0q 2. 4 OF- II I .6bOF-09 5.70E-I0 0,n 0.0 0 0 5.80E-09 8. OOE-09 I .OE-08 2.90E-08 0.0 U.01E-n9 1 .50E- -B 2.b0E-1 0 I IOE.-08 0.0 9,4OE-O9 I.OOE-OQ R.20E-0Q 2. 00E-O0 0.0 0.0 1 .70E-09 I,70E-Oq 3.0OE-09 0.0 0.0 2.20F-ro8 9. 30E- II.40E-08 0.0 7.20F-10 0.0 4.OOE-09 1.80E-08 b.5OE-13 0.0.3 0E-09 I .OOE-08 2,60E-12 4.40 E-09 2.70E-i I 17.90F-n 7 .80E-1 0 UOZR 4OZR 4OZR 41N8 42MO LJ3TC 43TC'i3TC 44RU U £4 P D LA RU LA 9RH 46PD 47AG 47AG 4 A C r)5""s 52TE 52TE 5128 515R 51TE 52TE 52TE 52TE 5?TE 52TE 521E 52TE 52TE 52TE 531 531 531 93 95 97 93*4 95 97 99 9q4 04 101 103 105 1 nb 105 i07 109 I I~111 123 125 12b t 246 125 I ?b 127 12741 127 12 2'4 129 t31M 131 13 2 I 3M 129 130 131 13 2 133 6.0 5.00F-09 5. SOE -()q o0.5. 1OF -A9 4A*bOE-0q 2.29E-I I 1 .qUF-0O Q. *,,E-10 0.0 2.7WF-0O S.bOE-OO 4.5UF-Oq I .50F-09 b.6OE-10 0.0 3.50E-I I I ,80F-08 I .80E-10 2.3nF-12 0,0 0.0 5. 7OF-t0 Q.DOF-09 1.30E-08 3. IOE-09* .9OF -') 9 5. 7OF-09 3.50F-12 I OOF-I I 7.70F-10 7. IOE-10 S., U OF -09 2,20F-09 I .70F-0Q 1 .50E-08 I .OOF-09 4 .SOE-1 0 I *U0E-08 2.80F-09 I .7nE-0O 3.7UE-09 3.0 s .G010 5. O0)E -A9 i,4nE-Oq*20F-09 I* OE-OQ I.OOF-Oq 4 .20F-o9 5. 101-O I jAnF-0q 7.7nE-10 S.0 14.001-I11 '. tOE-08 2. tOE-Io 2.60F-12 0.0 b,* bE-qR b.bOE-10 I DO0E-nm 1 .50F-09 3.50E-09 I .OOE-O8I 1. 0E- II I .IOF-1 I P *OOE-It0 g.uOE-I0 4.90E-09 2,b0E-Ob 2.00F-09 I .70F-OA 1.20E-09 7,50F-I 0 1 .70E1-ri 1 7 0E -n9 5.40FO-DQ 2. O0E -08 U.5AE-09 I*The same factors apply for adult, teen, child.Note: 0.0 means insufficient data or that the dose factor is <l.OE-20.E 1.109-28 TABLE A-7 (Continued) TOTAL BODY SKIN 53! 13u I.bOF-0 l.90t-o0i 531 13 1 .20EE-08 1uOE-O8 55CS 134'1 b.P0E-10 7.Y0E-10 55CS 134 1 .2F-08 IQOE-0p 55CS 135 0.0 D.0 55CS t36 1.5OF-'4 '.70E-08 55CS 137 4 .2OF QJ -.90E-0Q 55CS 13A 2,tOE-05 2.uOE-OR 55CS t39 b.30E-ng 7.20F- nq 5b65 139 2.uOE-0Q 2.70E-0Q 5hBA 140 2.lOE-0q 2,unE-09 56BA 1UI U.IOF-o9 qt90F-0Q 5b6A 1u2 9.00E-DO 57LA lU0 1.50E-0R 1.70E-08 57LA 141 2.5vE-10 2.5nE-t0 57LA IQ2 1.50E-OR t.ROE-05 58CE ]at 5.50E-10 b.20E-t0 58CE 143 2.20E-0q 2.50E-0Q 58CE Ua a 3.20F-10 3.70F- 10 59PR 143 0.0 0.0 59PR IOU 2.OOF-10 '.3nF-10 bOND 147 1.00E-0q 1.20E-09 blPM I7 0.0 0.0 tIPM 4RM4 1.UtF-.F0 5 6.-01-bIP4 10B bIPM 14Q 2.50E-11 2.QoE-il biPH 151 2.2'F-OQ 2.30E-o9 b25 151 u.80E-11 2.10F-10 b2SM 53 2.70F-In 3.0OE-10 13EU 152 7.37E-09 3.53E-0O 63EU 15u 7.BUE-09 4.00F-19 b3EU 195 I.RIE-10 U.33E-10 b3EU 156 7.80F-09 3.70E-Mg 65TB 160 A.6(0E-A9 1.00E-0A 67H40 I664 5.90F-00 1.OOE-nS 7UA 181 2,ROE-12 7Ui 185 n 0 .0 a 74" 187 3.1'E-AQ 3.bOE-09 82PH 210 1.30E-11 1.70E-11 381B 213 0.0 0.0 RaPO 210 5,10E-'1 b.2OE-tu TOTAL BODY SKIN 8RRA 2?3 1.50F-09 I.ROF-09 8SRA 22u 3.9nE-0q 1.OOE-08 88PA P25 ;. 11F -t I I. 2()F -1A 88AA 22b b.41JF-oq 7.40E-O0 R.RA 228 I,?f'F-0 1 t.4OF-n8 89AC P2? IrNF-OQ 1.80E-oQ 9A9C 227 2.OOE-09 2.40F-59 90TH 227 5.10F-10 b.30F-t0 90TH 22? ,.QOF-0Q t.00E-0A 90TH 229 2.20F-0 0 2.70E-09 90TH 230 h.S0E-nq 7.SOE-nq Q0TH ?32 S.OOF-OQ U.nOE-Oq qOTH 23u 1.1OE-10 1.30F-10 91PA 231 2.20F-0Q ý.70E-09 qtPA 233 1.30F-09 1.50F-99 92U P32 2.5qF-12 2.b9E-11 92U 233 2.30E-09 2.rtOF-o9 92U 234 b.32F-13 1,59E-10 q2U 235 i.20F-Oq 4.OOF-ng 92L P3b 2. IF-I I .80E-11 92U 237 t.00F-09 1.30E-0q 92U 238 1.10F-10 1.50E-10 13NP 2;7 1.40F-09 1.bOE-Pq 93NP 238 2.8nF-09 3.20E-oq 93NP 23q 9.50F-10 1.10E-0q Q9PUJ 238 1.30E-12 1.80F-11 9LPU P39 7.90F-13 7.70E-12 94PU 240 1.30F-12 t.80E-11 9LPU 241 4.h0E-12 b.80E-12 QUPU 242 1.10F-12 1.60F-11 9qPki 2441 8.95E-10 1.62E-10 9SAM 241 1.801E-10 2.60F-10 95AM .4??4 2.h6F-11 1.80E-1l 95AM 24.3 1.30E-09 1.50E-09 96CM 2U2 5.50E-12 2.30E-11 96CM 243 2.30F-Oq 2.90E-0Q 96CM 2ila 2.qnE-12 1.8OE-11 96CM 245 9,50E-10 1,20E-09 96CM 246 1.00E-12 1S50E-11 96CH ?P7 2,20E-0Q 2.bOE-09 9bCM 2a8 6.8IE-0q 5.23E-09 98CF 252 b6b0F-0R 7.20E-08 1.109-29 called bioaccumulation factors in this guide, can be found in the literature (Pnf. 19). The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose for consumption of aquatic foods.Rap = 1100 Uap Q.B. D (A-3)i aipj , p Values of Bip are given in Table A-8; the other parameters have been previously defined.The transit time tp may be set equal to 24 hours to allow for radionuclide decay during transit through the food chain, as well as during food preparation.

c. Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with suspended and deposited materials.

One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21). Based on these references, an estimate of the radio-nuclide concentration in shoreline sediments can be obtained from the following expressions: Ciw[l -exp(-.it)] C.s Kc 1w i (A-4)is c where Cis is the concentration of nuclide i in sediment, in pCi/kg;CiW is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter; Kc is an assumed transfer constant from water to sediment, in liters/kg per day;t is the length of time the sediment is exposed to the contaminated water, nominally 15 years (approximate midpoint of facility operating life), in hours; and Ai is the decay constant* of nuclide i, in hours-l. In the original evaluation of the equation, Xi was chosen to be the radiological decay constant, but the true value should include an "environmental" removal constant.The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period of several years in the Columbia River between Richiand, Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 22 and 23). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters meter above the sediment, an effective surface contamina- tion was estimated.

This surface contamination was assumed to be contained within the top 2.5 cm (I in.) of sediment.** The dose contribution from the radionuclides at depths below 2.5 cri was ignored. The resulting equation is Si MOT 1 iCi WDl -exp(-Ait)] (A-5)where Si is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations; If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).With a mass of 40 kg/m 2 of surface.1.109-30 TABLE A-8 BIOACCUMULATION FACTORS CpCilkg per pCi/liter) FRESHNATER SALTMA17ER ELEMENT FISH INVERTF3RATE PLANT PIS' TIVERTE3RATE PLANT H 9,0E-Ol q.oE-01 9.OE-01 9.OE-ni 4.3E-01 9.3E-01 HE 1.0E 00 1.0f 00 10Elf 1.0ff O0 1.fOE 00 t.OE no LI 5,0E-Ol C.oE: 01 3.0E 00 5.OE-01 50fE-Ol 3.0E 00 BE 2.OE 00 InE 01 2.0E 01 ',OE 02 e.OE 02 1.OE 03 B 2.2E-01 5.OE 01 2.2E 00 2.2E-Ot QO.E-01 2.2E oA C U. 0E 03 Q 03 4.bF 03 t.5F Os 1.14E 03 1.8E 03 N 1.5ES 05 1.;E 05 1.3f3E 04 h. E 04 1T7E "04 1 .0f p 0 0 9.2E-O 9.?fE-01 9.2E-0l 9.bF-01 9.bE-01 Q.bE-O0 F 1.0E 01 1 .oE 02 2.0E 00 3.bF 00 3.6f on 1 .4E 00 NE I.OE O0 I.nE 00 1. r E 00 1.0E 00 1.0OE 00 1.OF 00 NA I.OE 02 2.oE. 02 5.OE 02 b.7E-02 1.QE-01 9.SE-O1 MG 5.OE 01 1.oE 02 1.0OE 02 7.7Ff-01 7.7fE -01 7.7E -0 1 AL ioE0f 01 6.;E 01 U.2E 02 1.0OF n1 b.OE O0 6.OE 02 SI 2.5E 00 2.';E 01 1.3E 02 1.0f 01 3.3E 01 6.7P 01 F 1.0oE 05 2.oE. OU 5.0E 0'; 2.fE n4 3.0E O4 3.0E 03 T 7.5E 02 I.oE. 02 1.0E 02 1.7E 00 4,UE-01 U.4E-01 CL 5.0E 01 .ofE 02 5.OE 01 1.3E-02 I.QE-02 7.6E-02 AR I.OE 00 1.nE 00 1,OE 00 1.0ffno I.OE 00 1.OE 00 K I.OE 03 8.lE 02 6.7E 02 1.IE 01 .6fE 00 2.6E 01 CA 4,OE 01 3,3E 02 1.3E 02 5.0E-Ol 1.3E 01 5.OE 00 SC 2.0f 00 1.fE' 03 t0OE 0 Oi 2.0fE 00 1.fOE 0 Q I.0 E 05 TI t.OE 03 3.OE. 03 5.OE 02 1.OE o3 1.OE 03 2.0E 03 V 1.OE 01 3.E 03 1.0E 02 1.0E Ol 5.OE O i.OE 02 CR 2.0E 02 2.nE 03 .",OE 03 4.0E 02 2.0E 03 2.0E 03 m, ,40OE 02 9.oE 04 1.0fE 04 5.5E 02

• 4.OE 02 5.5E 03 FE 10OE 02 3.pE 03 1.0E 03 3.0E 03 2.OE O4 7.3E 02 c0 5fOE 01 2.nE 02 2,0E 02 .0OE 02 I.0E 03 I.OE 03 NI 1.OE 02 1.OE. 02 5.0E 01 I.OE 02 2.5E 02 2.5E 02 CU 5.OE 01 'i.nE, 02 2.0E 03 .7ffE 02 1.7f 03 1.0E 03 ZN 2.0E 03 i.nE 04 2.0E 04 2.0E 03 5.0E OU 1.0E 03 GA .3E 02 6.7E 02 1.7fE 03 3.3fE 02 b.7E 02 1.7fE 03 GE 3.3E 03 3.fE- 01 3.3E 01 3.3E 03 1.7fE OU 3.3E 02 AS 1.OE 02 i.nE. 01 3.0E 03 3.3E 0R 3.3E 02 1.7E 03 SE 1.7E 02 1.7E 02 1.0E 03 4.0E 03 1.0E 03 1.0E 03 BR 4.2E 02 3.iE 02 5.OE 01 1.5E-02 3.1E 00 1.5E 00 KR 1.0E 00 1.nE:00 102 0:0 Ij 0E 0 .f0E 00 .0fE 00 RB 2.0E 03 i.nE, 03 t.0E 03 8.3E 00 1.7E 01 1.7E 01 SR 3.0E 01 l.nE 02 5.0E 02 2.0E 00 20OF 01 I.OE 01 Y 2.5E 01 1.0E 03 5,OE 03 2.5E 01 .0OE 03 5.OE 03 ZR 3.3E 00 6.7fE 00 1.0E 03 2.OE 02 OE n1 I.OE 03 NB 3.0E Oi l.nE u2 8.OE 02 3.0E n4 I.OE 02 5.0E 02 Mo 1.0fE 01 1.nE' 01 I.OE 03 OE f0 1.0fE 0t 1.0fE 01 TC I.5E 01 5.Off 00 U.0f1 1.0f 1O 5.0fE 01 4,OE 03 RU 10OE 01 3.0E 02 2.0E 03 .0OE 00 1.0E 03 2.OE 03 RH 1.fOE 01 3onE:02 2.OE 02 1.OE 01 2.0OE 03 2.0E 03 PD 1.0E 01 3.0E 02 2.OE 02 I.OE Ot 2.0E 03 2.0E 03 AG 2.3E 00 7.7Ef 02 2.OE 02 3.3E 03 3,3E 03 2.0E 02 CO 2.0E 02 2.nE. 03 1.0E 03 3.0E 03 2.5E 05 1.0E 03 IN I.OE 05 l.nE 05 1.0E 05 1.0E 05 I.OE 05 I.OEf 05 SN 3.OE 03 1.0E 03 1.OE 02 3.0E 0 1.0fE 03 t.OE 02 sB 1.OE 00 1..ff,01 1.5E 03 1JQ,OE 01 S.0IE 00 1.5E 03 TE 4.OE 02* 1.0E. 05 I.OE 02* I.OE 01** I.OE 05 i.OE 03**1 1.5E Ot 5.0E 00 4.OE Ol I1.0E 01 5.0F O0 I.OE 03 1.109-31 TABLE A-8 (Continued)

FRESHWATER ELEMENT XE CS BA LA FISH I .0E 2,OE* 0E 2.SE INVERYF3PATE SALTWAE;ýTrIH T1JVEITE3RATE PLA'NT 00 03 00 01 I .nE I PoE 2.0E I .nE 00 02 02 03 PLANT I .OE 00 5.OE 02 5.OE 02 S.E 03 1 0 OE 0i 0OE 1 0 OE 2. 5E 00 oft 0!01 I .O0E 2.5f 1 .0OE I if E 00 01 02 03 I5. nE 5. OE 00 Dl 02 03 CE 1.OE 00 1.nE 03 4*OE 03 t I.OE O b.6OE 02 b.OE 02'PR 2.5E 01 I.OE 03 5.OE 03 2.5E O I.OE 03 5.OE 03 ND 2.5E 01 I.nE, 03 S.OE 01 2.5E 01 1.OE 03 5.6c 03 PM 2.5E 01 IoE' 03 5.OE 03 2.5E 01 1.0E 03 5.OE 03 Sm 2.5E 01 I.OE 03 5.OE 03 2.5E 01 1.OE 03 S.nE 03 EU 2.5E 01 1.nE 03 S.OE 03 2.SE n1 1.0E 03 S.OE 03 GD 2.5E 01 10oE. 03 5.hE 03 2.5E 01 1,OE 03 5.OE 03 TB 2.5E o0 1.oE 03 5.OE 03 ?.SE 01 1.0E 03 5.0F 0.3 DY 2,SE 01 I.oE 03 5,OE 03 2.SE 01 I.OE 01 5.OE 03 HO 2.5E 01 1.OE 03 5.OE 03 2.SE o0 I.oE 03 5.Or n3 ER 2.5E 01 I.oE 03 5.OE n3 2,5E 01 I.OE 03 5.OE 03 TM 2.5E o0 1.hE 03 S.hE 03 2.SE 01 t.OE 03 S.OE 03 YB 2.5E 01 1.oE 03 S.OE 03 2.5E o1 I.OE 03 5.OE 03 LU 2.5E 01 1.nE 03 5.OE 03 2.SE O0 1.OE 03 5.OF 03 HF 3.3F 00 6,7E. 00 I.OE 03 2.OE 02 2.OE 01 2.OE 03 TA 3.OE 04 b.7E-02 8,OE 02 3.OE Ol 1.7E 04 I.OE 03 W 1o2E 03 1.oE 01 1.2E 03 3.0E 01 3.OE 01 3.OE 01 RE 1.2E 02 6.nE 01 2.UE 02 U.E 00 b.OF 01 2.uE 02 0S 1.OE 01 3.0E 02 2.OE 02 1.OE 01 2.OE 03 2.OE 03 rR I.OE 01 3.E' 02 2.OE 02 1.OE (1 2.OE 03 2.E 03 PT 1.OE 02 3.nE 02 2.OE 02 1.OE 02 2.OE 03 2.0E 03 AU 3,3E 01 5oE 01 3.3E 01 3.3E 01 3.3E 01 3.3E 01 HG I.OE 03 1.oE 05 I.OE 03 1.7E 01 3,3E 34 t.OE 03 TL 1,OE 04 1.;E 04 I.OE 05 1.0E 04 1,5E 04 I1.E 05 PB 1.OE 02 1.nE 02 2.OE 02 3.OE 02 1,E 03 5.OE 03 B t.SE o0 2.aE 01"**2.E 01***tS 1.5E 01 2.UE 01"** 2. a 0 1 F**PD 5.OE 02 2.nE Ou 2.OE 03 3.OE 02 51OE 03 2.OE 03 AT 1,5E 01 5,E' 00 ..OE 01 1.OE 4.0;7 03 RN 1.OE 00 I.oE 00 t.OE 00 1,OE 00 1,OE 00 I.OE 00 FR 4.OE 02 1,oE 02 8.OE 01 3,OE 01 2.OE 01 2.OE 0l RA 5.OE 01 2,'E 02 2.5E 03 S.OE 01 1,OE 02 I.OE 02 AC. 2.5E 01 1.oE 03 SOE 03 2.5E 01 I.OE 03 5.OE 0O TH 3.OE 01 5.nE 02 1.5E 03 t.OE 01 2,OE 03 3.OE 03 PA 1.IE 01 .iEE 02 1.IE 03 I.OE 01 I.OE 01 6.OE 00 U 2.OE 00 6,OE: O0 S.OE-0 1.OE 01. !.OF 01 b.6E 01 NP I.OE 01 4.nE. 02 3.OE 02 I.OE o1 1.OE 01 i. OE 00 PU 3,5E 00 I.oE 02 3.5F 02 3.OE 00 2.OE 02 I.OE 03 AM 2.5E 01 1.0E 03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 CM 2.5E 01 1.nE. 03 S.OE 03 2.5E 01 1.OE 03 5.0E 03 BK 2.5E 01 I.nE; 03 5.0E f3 ?.SE 01 1.OE 03 5.OE 03 CF 2.5E 01 I.oE'03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 ES I.OE 01 1.oE, 02 I.OE 03 I.OF 01 I.OE O0 b.OE 01 i I.OE 01 1.E 02 I.OE 03 I.OE 01 I.OE 01 bOE 01*ORNL -Private Communication

• • Freke, A.M., "A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol. 13, p. 749, 1967.***Derived from data in Bowen, H.J.M., Trace Elements in Biochemistry, New York, Academic Press (1966).1.109-32 Ti is the radiological half-life of nuclide i, in days; and W is a shore-width factor that describes the geometry of the exposure.Shore-width factors were derived from experimental data (Ref. 24) and are sunanarized in Tdble A-9. They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.

The combination of Equations (A-4) and (A-5) into the general Equation (A-i) leads to(A-6) below for calculation of radiation dose from exposure to shoreline sediments.

Rapj U S*D 100 U W C T D [ -exp(-- t)] (A-6)ap i aipj Iap iw i aij U III W 110,000 --'--. QiT D .[exp(-."\t )][l -exp(-:i t)] (A-7)F lli ipj iP 1 d. Dose from Foods Grown on Land Irrigated by Contaminated Water The equations in the following paragiaphs can be used to calculate doses from radio-nuclides in irrihjated crops. Separate expressions are presented for tritium because of its unique environmental behavior.(1) Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The rmodel used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 4).The equation for the model (for radionuclides except tritium) is presented below in slightly modified form. The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility.

Thus for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg, is given by: iv i" -exp(- '"U t e)]v Biv[I -ex 1(-'P 'itb)1]exp(-..it ) (A-8 )The de;,osition rate, di, from irrigated water is defined by the relation d'i = C iw (water deposition) (A-9)where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I is the irrigation rate, in liters/m 2/hr; i.e., volume of water (liters)sprinkled on unit area of field in 1 hour.For tritium, the equation for estimating Civ is (see Ref. 25): Cv M Ctl (A-10)For a cow grazing on fresh forage, te in Equation (A--8) is set equal to 720 hours (30 days), the typical time for a cow to return to a particular portion of the grazing site.I 1.109-33 TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6)EXPOSURE SITUATION SHORE-WIDTH FACTOR, W Discharge canal bank 0.1 River shoreline 0.2 Lake shore 0.3 Nominal ocean site 0.5 Tidal basin 1.0 TABLE A-10 ANIMAL CONSUMPTION RATES I ANIMAL Milk cow Beef cattle QF FEED OR FORAGE (kg/day [wet weight])50 (pasture grass)50 (stored feed grain)QAw WATER (;./day)60 5o From Reference 4, Tables 111-B and -10.P 1 .10g-34 (2) Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water. The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref. 4) is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w): CiA = F iAECiFQF + CiAwQAw] (A-li)The second set of terms in the brackets in Equation (A-1l) can be omitted if the animal does not drink contaminated water. Values for QF and QAw are presented in-Table A-i1.Values for Biv and FiA are given in Table C-5 (see Appendix C).*The total dose Rapj from irrigated foods (excluding tritium) is given by: R a veg CiD + Uanimal Y D apj ap iv aipj ap iA aipj (A-12)If values for Civ from Equation (A-3) and CiA from Equation (A-11) are substituted in Equation (A-12): veg i[)Da [ -exp(- Ei te)] Biv[l -exp(-'it R ve dix(, hi ai iv , X Lb apj ap v ipJ YvEi i U panima -r[l -exp( '1Ei te)]ap iA ai pj OFui Y- / ~v Ei+ Biv[l -exp(-,.,itb)] (A-13)+PN i )]+ CiAwQAwj It should be noted that the two components of Equation (A-12) imply that contribu-tions from the individual vegetable and animal products have already been summed. In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)).For tritium, the concentration in animal products is given by the following equation (adapted from Reference 25): kWCv +QAwCAw (A-14)C A -+kQCA m in Since by Equation (A-IO) Cv = Cw, and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows: kC C A = 3 (w + QAw) (A-15)in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1): Ra. U ve C D animal CAD apj (A-16)Rapj : u~gvap vapj" + Uap Aaj(-6 Uve v ,,animal Da (w+ QAw) (A-17)V uea Daa apjs + Uap apj-inab Q(C--.Valus fr FA appear as Fin and Ff in Table C-5.1.109-35 REFERENCES FOR APPENDIX A 1. "Final Environmental Statement Concerning Proposed Rule Making Action: Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents," USAEC Report WASH-1258, Washington, D.C., July 1973.2. J. K. Soldat et al, "Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.3. "Food Consumption, Prices, and Expenditures," AER-138, U.S. Department of Agriculture, Washington, D.C., December 1974.4. J. F. Fletcher and W. L. Dotson (compilers), "HERMES -A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Peport HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.5. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (;.Ci/m2),' Itemi 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.6. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-,41638, General Electric Co., Richland, W'ash., February 1956.7. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption -Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA, Seattle, Wash., June 1971.8. "The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.9. "Draft Environmental Statement -Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September 1974.10. "Radiological Health Handbook," USPHS, Rockville, Md., January 1970.11. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1311 Dose to the Thyroid," IRS-W-5, Institute for Reactor Safety, Cologne, Germiany, April 1973.12. P. S. Rohwer and S. V. Kaye, "Age-Dependent Models for Estimating Internal Dose in Feasibility Evaluations of Plowshare Events," ORNL-TM-2220, Oak Ridge, Tenn., April 1968.13. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I and 137Cs to the Atmosphere," Health Physics, Vol. 17, pp. 51-57, July 1969.14. W. S. Snyder, "Dosimetry of Internal Emitters for Population Exposure," in Population Eýx ures, CONF-741018, Proceedings of the Eighth Midyear Topical Symposium of the Health Physics Society, Knoxville, Tenn., October 1974.15. "Report of ICRP Committee II on Permissible Dose for Internal Radiation, International Commission on Radiological Protection," ICRP Publication 2, Pergamon Press, 1959.16. J. K. Soldat, "Modeling of Environmental Pathways and Radiation Doses from fluclear Facilities," USAEC Report BNWL-SA-3939, Pacific Northwest Laboratory, 1971.17. C. M. Lederer et al, Table of Isotopes, 6th Ed., John Wiley and Sons, Inc., 1967.18. S. E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, Lawrence Radiation Laboratory, October 1972.1 1. 109-36 19. J. K. Soldat, "A Statistical Study of the Habits of Fishermen Utilizing the Columbia River Below Hanford," Chapter 35 in Environmental Surveillance in the Vicinity of Nuclear Facilities, W. C. Reinig (ed.), Charles C. Thomas Publishers, 1970.20. J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.21. J. L. Nelson, "Distribution of Sediments and Associated Radionuc:lides in the Columbia River below Hanford," p. 3.80 in "Hanford Radiological Sciences Research and Development Annual Report for 1964," D. W. Pearce and J. K. Green (eds.), USAEC Report BNWL-36, Pacific Northwest Laboratories, 1965.22. G. L. Toombs and P. B. Cutler (compilers), "Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 -July 31, 1967," Oregon State Board of Health, Div. of Sanitation and Engineering, 1968.23. "Handbook of Radiological Protection, Part I: Data," prepared by a panel of the Radio-activity Advisory Committee (H. J. Dunster, Chairman), Dept. of Employment, Dept. of Health and Social Security, Ministry of Health and Social Services, Northern Ireland, Nlumber SNB 11 360079 8, Her Majesty's Stationery Office, London, England, 1971.24. L. R.. Anspaugh et al, "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.), CONF-710809, 1973.1.109-37 APPENDIX B MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE ATMOSPHERE The following analytical models are used for calculating doses from exposure to gaseous effluents.

Separate models are given for air and tissue doses due to gamma and beta rays.Except for the case of noble gas doses resulting from elevated releases, all models assume submersion in an infinite cloud at the exposure point.1. Annual Gamma Air Dose from Elevated Releases of Noble Gases Slade (Ref. 1) describes the derivation of the equations for estimating annual air doses from photon emitters dispersed in the atmosphere.

The following expression can be used for calculating annual doses: D 260 D n un s I )1 ik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient.

Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki I [AmEmpa(Em)]/[Ekwa(Ek)] (B-2)m where A is the fraction of the disintegrations of nuclide i yielding photons m of energy E Em is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em) is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined. The summation is carried out over all photons within energy group k. Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2. For radionuclides not contained in Reference 2, data were obtained from Reference 3.Decay during travel from the point of release to the receptor is QD = exp(-Xir/un) (B-3)The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays. Annihilation and bremsstrahlung photon radiations are possible contributors to this compunent of the air dose.Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures. (See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.") 1. 109-30 where Qi is the initial release rate of nuclide i, in Ci/yr, and Ai is the decay constant of nuclide i, in sec" 1 All other parameters are as previously defined.2. Annual Gamma Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents. The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.The annual average ground-level concentration of gaseous effluent species i at location (r,o)from the release point is determined from xi(ra) = 3.17 x 10 41 D(r,o) (6-4)where xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 , and[/Q')1D(r,o) is the annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle e at the distance r from the release point,.3 in sec/mi The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year. All other parameters are as previously defined.The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then I DY(r,e) or DO(r,e) = or DFO) (B-a)where the terms are as defined in Regulatory Position C.2.b.Table B-1 presents a tabulation of the dose factors for the noble gases and daughters of interest.3. Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas. The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue.a. Elevated Releases The annual total body dose is computed as follows: DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t] (B-6)Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed. (See Regulatory Guide 1.111.)The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.

I 1.109-40 TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Nuci ide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-1 31m Xe-1 33m Xe-i133 Xe-i 35m Xe-1 35 Xe-1 37 Xe-138 Ar-41 a-air* (DFB)2.88E-04 I .97E-03 1 .95E-03 1 .03E-02 2. 93E-03 1. 06E-02 7. 83E-03 1.11 E-03 I .48E-03 i .05E-03 7. 39E-04 2: 46E-03 1. 27E-02 4. 75E-03 3.28E-03 1 .46E-03 I .34E-03 9. 73E-03 2. 37E-03 1 .01 E-02 7. 29E-03 4. 76E-04 9. 94E-04 3. 06E-04 7.11 E-04 1.86E-03 1. 22E-02 4.1 3E-03 2. 69E-03 y-Air* (DFB)1.93t-05 1.23-03 1. 72E-05 6. 17E-03 1.52E-02 1. 73E-02 1. 63E-02 1. 56E-04 3. 27E-04 3.53E-04 3. 36E-03 1. 92 E-0:3 1.51 E-0:3 9.21 E-03 9.30E-03 y-Body (DFBi)7.56E-08 1 17E-03 1.61E-05 5 92E-03 1 .47E-02 1 .66E-02 1 56E-02 9. 5E-05 2.51 E-04 2.94E-04 3.12E-03 1.81E-03 1 .42E-03 8.83E-03 8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr**'2.88E-04 = 2.88 x I0"4 1.109-41 Symbols for this equation were defined earlier in Regulatory Position C.2.c of this guide. The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.The skin dose has two components, the ganmia and beta contributions.

The skin dose rate is computed by DS(r,o) 1.11 x SFD Y(r,o) + 3.17 x 104 1 Qi(x/Q']D (r,o)DFSi (8-7)1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.The skin beta dose factors OFS were determined using the decay scheme source docu-ments cited above and the methods used in References 4, 5, and 6.b. Ground-Level Releases The annual total body dose is computed as follows: DT(r,o) = 1.11 x SF ýxi(rO)DFBi (B-8)Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.The annual skin dose is computed as follows: Ds(r,o) -1.11 x SFF Zxi(r'e)DFi + xii(ro)DFSi (8-9)where D 5 (r,e) is the annual skin dose due to immersion in a semi-infinite cloud in the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra) is the airborne concentration of radionuclide i at point (r,6), in pCi/m 3.I1 I 1.109-42 REFERENCES FOR APPENU.X B I. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-24190, 1968.2. M. J. Martin, "Radioactive Atoms, Supplement I," USAEC Report ORNL-4923, November 1973.3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-12037, 1970.4. R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.), Academic Press, New York, 1956.5. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR 73-107, 1973.6. M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol. 26, pp. 1-12, January 1974.1.109-43 APPENDIX C MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE I. Annual External Dose from Direct Exposure to Activitv Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,o) with respect to the release point may be determined by 1.1 x 10, (rc~ Q!C i(r'c) 1 1-exp(-Xit)j (Cý-l);'-here C .is the ground plane concentration of the radionuclide i in the sector at angle -at the distance r from the release point, in pCi/m2;Qi is the annual release rate of nuclide i to the atmosphere, J'i/yr;t is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility;is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport, in mn-2; and The annual plant is then is the radiological decay constant for nuclide i, in yr-1.dose from nuclide i resulting from direct exposure to the contaminated ground D (r ,) 8760 SFCG(r,r.)DFG (C-2)where D. ii and other terms The annual is the annual dose to organ j from the ground plane concentration of nuclide i at the location (r,r,), in mrem/yr;are as defined previously in Regulatory Position C.3.a of this guide.dose to organ j is therefore D (r,o) = 8760 S C9(r,o)DFGi i F I 1 (C-3)Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7. The annual dose to all other organs is taken to be equivalent to the total body dose.Does not include noble gases or their shurt-lived daughters; see Appendix B.1.109-45 2. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide i at the location (r,t!) -ith res-pect to the release point may be determined as Xi(r,o) 3.17 x 104QQ[X/Q'] D(r,) (C-4)where is the release rate of nuclide i to the atmosphere, in Ci/yr;xi(r,O) is the annual average ground-level concentration of nuclide i in air in the sector at angle 6 at distance r from the, release point, in pCi/m 3;[./Q']D(r,o) is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111). This includes depletion (for radiolodines and particulates) and radioactive decay of the plume; and 4 3.17 x 10 is the product of the number of pCi/Ci and sec/yr.The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then DDA (rO) = xi(ro)RaDFAi (C-5)iiaa ija Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.The annual dose to organ j in age group a from all nuclides in the effluent is: 4 DA (ra=R(C-6) Dja(r,o) Ra zxi(re)DFAija 3. Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is six:ilar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.For all radioiodines and particulate radionuclides, except tritium and carbon-14, the con-centrition of nuclide i in and on vegetation at the location (r,Q) is estimated using CV(rO) di(r,o) r[l -exp('AEite)] Biv[l -exp(-Y tb)]] exp(-1ith) ' ' + Ax PXti (C-7)See Regulatory Position C.l of tnis guide for definitions of terms.Carbon-14 is assumed to be in oxide form (CO and C0 2). The concentration of carbon-14 in vegetation is calculated by assuming that its ratio to the natural carbon in the vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 1 and 2).I 1.109-46 TABLE C-1 ADULT INHALATION DOSE FACTORS (mreni/pCi inhaled)NUCLIDE I 3 UBE 10 bE 7N 13 QF 14 11NA 22 1 1 NA 2 a ISP 32 20CA 4L 215C U b 24CR 51 25MIN 54 25 'N 5b 26FE 55?6FE 59?7CO 57 27C0 98 27CO bo 28NI 59 28-1 65 29CU b6 30ZN 65 30ZN 694 30 N 59 3uSE 79 359R S2 35HR 93 353P 84 353R 85 374B 5h 37RB 87 37RR 58 37BR Bq 3BSR 89 3ASR 90 38SP 91 3ASR Q2 39Y 90 34Y qO1 3QY 9 1 U 39Y 91 A0IE 0.0 I .qSE-OU 2.28E-O0 6.27F-Oq 4.71E-07 1. 30F-05 1 .b9E-O6 I .b5E-0O4 3.83E-05 3.51E-05 0.0 0.0 0.0 7.b2E-06 I .a7E-Ob 0.0 A 0 0.0",0OE-0b 5.40E-05 1 .92F-I0 0.0 L.0 hE-Oh 1 .02F-09 4.23F-12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.8OE-05 I .2"E-02 7.9"E-09 8. 4 1E-1O 2,b6E-07 3.?2 E- II 5.78E-05 LIVER TfTAL 9')Y 1.3QE-07 t.34E-07 3.OhE-05 U.QbE-Oh 4.27E-07 u.27E-17 b.27E-09 h.27E-01 0.0 S.20E-oS 1.30E-n5 1.30E-05 t.69E-Ob 1.69E-0b 9.65E-Ob 6.27E-Oh 0.0 U.II3E-Ob 1.07E-04 3.11E-05 0.0 1.25E-0R+/-.95E-0b 7.A7E-07 1.55E-10 2.29E-11 3,43E-05 9.O0E-0B 3.47E-03 1.32E-06 5.bSE-08 B.39E-0O I.QBE-07 2.SQE-07 1.u4E-nb 1.8SF-Ob 1.4bE-O b.77F-07 3.92E-nh 1.PtE-06?.62E-11 I.IaE-tl 1.83F-10 7.b9E-1I 1.29E-05 S.PE-,)h 2.L5E-nq 2.2LE-I0 0.13E-12 5.61;E-13 3.83E-n7 6.0QE-O0 3.0 1.6hE-06 3.0 3.O0E-OR 0.0 3.91E-08 0.0 !.hAE-09 1.6QE-O5 7.3RE-Ob;.87E-Ob 3.?IE-0h 3.85E-B8 P.4iE-08 3.21E-OB 2.12E-O0 0.0 1.09E-Ob7.6?E-111 0.0 3.,qE-10 0.0 3.64E-11 0.0 7.01E-09 0.0 1.27E-12 0.0 1.55E-06 1 .34E-07 u.L?7E-07 8.27E-09 0.0 I 30E-05 I .69E-Ob 0.1 0.0 0.0 7.u"UE-09 0.0 0.0 0.0 0.0 0.0 0o0 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 0.0n 0.0 0.0 0.0 0.0 0.0 0.0A 0.0 KI)NEY S.3LIE-07 0.0 4.27E-07 6.27F-OQ 0.0 1I 30E-05 1 ,bqE-06 0.0 0.0 I .OOE-0O?. 5SE-09 I I23F-06 I .b3E-10 0.0 0.0 0.0)00 0.0 0.0 5,7 8 F-10 8.b2E-0b I .Q48E-09 5.27E-12 5.bQE-07 0.0 0.0 0.0 0.0 0,0 0.0 0.0 6,0 0.0 0.0 0.0 0.0 0.0 1 I 34E-07?.23E-Ou u.27F-07 6 *27E-O9 n.0 ,1 I E-n5 1 69F-Ob 0.0 0=0 S. OE-06 1 .75E-06 1 .18E-06;o.RE-05 1 .27F-04 1 .16bF-04i 7,L7E-04 A,21E-06?.23E-05 7.01E-n7*.L1E-07 I .OE-04 2,39E-Ob 1.15E-07 Li. LiE-OS n100 0.O 0.0 0.0 0.0 0.0 0.0 0.0 I .75E-04 I .20E-03 u.92F-Ob 2.06E-Ob 2.12E-05 2.L1E-07 2.1 3E-0 4 GI-LLI 1 3LiE-0 7 1 .b7E-05 Li.*27E-07

• .27F-09 9.24E-09 1 , 30E -09 1 .bqE-Ob 1
• 08E-05 2.AbE-07 3.23E-05 uL 5 I E-07 9.b7E-Ob 2.53E-06"7.SuF-Ob 2. 3SE-05 3.93E-06 I I ;3L-05 I. ,3E-OS 3 ,* .':6, -05 b. 1 IE-07 1 .67F-06 I , 5E -0O h. 12E-06 b.bBF-06 I .71E-05 2,0* E-09 3.33E-Ob I .30F-0b 2.qOE-08 2.05E-1 3 0.0 2.08E-O0 2.88E-07 4,i 11E-1I 0,0 9.02E-05 2,59E-05 5.3RE-Ob 6.3PE-05 1 .6bE-I 0 4.81E-OS Note: 0.0 means insufficient data or that the dose factor is <].OE-20.1.109-47 TABLE C-1 (Continued)

NUCLIDE BONE LIVER TOTAL BODY THYROID KIDNEY lltlN; .I-i.LI 39Y 92 1.2qE-09 0.0 3.77E-11 0,0 0.0 1.bE-0h QIqE-ob 39Y 93 1.19E-08 0.0 3.26E-10 n00 n.0 b.n7E-nh 5.,7f.-05 40ZR q3 5,22E-05 292E-o06 1,37E-O 0,0 .llF-0-5 '113E-05 I1.5F-06 UDZR 95 t.34F-05 4,30E-06 2.91E-0h m.0 b.77E-0h 2.22F-ou 1.4L-0c)40ZR 97 1.21E-OB 2.U5E-09 I.13E-nQ 0,0 3.71E-09 4.SE-0b b.5UF-05 41NB 934 3 3.lOE-05 1.0IF-n5 2.AqE-n6 A.0 1.IE -0S 3.1IF-n 2,;BEE-0b.

UINB 95 1,7kF-0 5.2hE-07 0.0 9.b7E-n7 b.12F-05 I.30E-65 41N8 97 2.783E-11 7.03E-12 P.56E-I? 0.0 5. 1E-12 .oO F-07 1.2F-0H u24n 93 0.0 1.17F-nb 3.17E-1; q.n .S55E-07 5.11E-05 1.7qF--t U2MD Q9 0.0 1.51E-0B 2.87E-19 0,n ;.°UE-nB 1,1 AE-05 i.10-05 431C 994 0.n 3.64E-13 4 .h3E-1P 0.0 5.52E-12 P.SbE-n9 S.20F-n/437C 9q 0.0 U.64F-0R I.37E-04 0.0 5.95E-07 l.nIE-04 7.SuEE-0b Q3TC 101 0.0 7.52E-15 7.38E-14 n0.0 1.35F-13 U.9qE-ns 0.0 44RU tn3 l.91E-07 0.0. 9.23E-fl 0.0 7.2qCE-07 6.32E-05 1.S -o..4uRU 105 9,ASF-11 0.0 3.RqE-l1 0.0 1.27E-10 1.3AE-0b b.0?E-flb'JLRU 106 8.64E-0b 0.0 I.0qE-06 0.0 1.67E-05 1.16E-03 1.i 1 E-oll 45RH 105 q.24F-10 b.73F-10 4.43E-10 n.0 2.hE-nQ 2.'41E-ntb 1.01)E-05 46PD 107 0.0 q,27F-08 5,87E-09 0.0 b.57E-07 Q.ugE-Ob 7.OhE-(,7 46PD 109 0.0 4.b3F-10 1.16E-itf n.0 ?.35E-og 1.85E-Ob 1.52i-fS 47AG 1I104 1.335E-06 I.25E-06 7.a3E-07 n.( 2.3bF6-06 5.OE-04 3..763 -05 47AG I1 I ,425E-08 I ./BE-08i A.8TE-Oq o,0 5. 7uE-P h 2. 34E-n)5 P.l79F-np I URCO 113M n.0 1.54E-0O '.q7E-06 0.0 1.71E-n4 2.06F-0U 1.99E-n5 48CO 115M 0.0 2.ab4-05 7.qSE-01 0.n 1.9RE-05 1.7bE-Ou .8OE-05 50SN 123 3.02E-05 6.66E-07 9.P2E-07 5.6bE-07 0.o P.89E-00 3 .92 -n5i 50SN 125 1 .IhF-0b 3.13E-08 7.03E-06 2.59E-03 0.0 7,u2E-05 .MIE-05 50SN 12b 1.58E-04 J.I BE-06 6.OOE-06 1,P3E-0b 0.n I 17E-n 3 1.59L-0P SISB 124 3.QOF-06 7.3bE-08 155E-06 9.44E-09 0.0 3.1OF-0u 9.0OBF-nl9 51S5 125 8.2bE-06 B.91E-OR I6bbE-06 7.34F-09 P.0 ?.75F-04 I.?bhf-05 51SB t2b .O50F-07 9.13E-09 1.62E-07 2.75E-0 n 0.0 1.5RF-n5 b. OIE-0q 515 127 3.30E-08 7.22E-i0 1.?7E-09 3.q7E-10 0.0 ?.nSE-05 3.771F-05 52TE 12591 4.27E-07 I.98E-n7 S.84E-0A I.31E-07 1.55F-nb 3.92F-05 8.MSF-Ob 52TE i274 1.58E-06 7.02E-07 1.9hE-07 4.11F-07 5.72E-Ob 1.?OF-OQ 1. 7F-O0 52TE 127 1.75E-10 -.03E-.11 3,87E-11 1.3.E-10 h.17F-j0 7.17E-oh 52TE 129M 1.22F-0b 5.64E-o7 1.9RE-77 4.30E-07 : .S7,-0b 5E6 11SE-Oa u.7qE -01 52TE 129 b.22F-12 2.99E-12 t.5SE-12 4.87E-12 2.3L3E-11 .a2F-07 t.9bF-0 8 52TE 1314 B .74E-09 5.SE-0q 3,63E-09 BBF-01 3. bE-1A 1.82F--05 b, .9SF-0 52TE 131 1t39E-12 7.44E-13 u .'J9E-13 1.17E-1F 5.ubE-12 1.7 F-07 2. 4uE-0q 52TE 132 3.25F-07 2.b9E-Of 2.0?E-08 ?.37E-0 I.S3E-n7 3,60F-05 6 .3 7E-f5 52TE 1I33M 7,24E-12 5.b0E-12 7.14E-12 6,27E-12 3.7TF-I1 5.51E-07 3.u5F-AQ 527E 134 3.84E-12 3.22E-12 1.57E-12 3.t)U E-12 2.1BE-11 Z.3UE-07 3.b9Emog 531 129 2.'49E-0b 2.1IE-O6 6.91E-O 5.55F-01 14.514E-0b o.l 2.2E-07 S31 130 5.73E-07 1.68E-Ob 6..hF-07 2.18F-04 2.blE-m6 0.0 q.hlF-07 531 131 3.ISE-O6 4.47E-06 2.56F-0b 1.0J9E-03 7.b7F-Oh 0.0 7.8hF-O7 531 132 1.45E-07 U.07E-07 1.45E-07 5.JBE-05 b.UqF-07 0.n 5.18F-0R E 1.109-48 TABLE C-i (Continued) NUCLIDE 531 531 531 55CS 55CS 55CS 55CS 55CS 55CS 5695 S6BA SbBA 57LA 57LA 57LA SRCE 5FCE 58CE 5QPP 51PR bO lO blPm b61 P.blPM b2SH bSM b3EU 63EU b3EU 6ST9 b7 1O 7LJ, 7iU 82PR R391 BiPo 133 134 135 135 j36 137 139 139 I40 1Ul 1 2 1UO IL I 7 149 151 151 153 15?151 155 15h 160 Tk-T 155 917 210 210 210 BONE I .0BE-O0 5.ObE-08 3.30E-07 I

• bOE-OR U .hlF-05 1 ,UbF-05 4.8QE-06 5.08F-05 L4. IIE-0b 2.50F-08 1.17F-I 0 4.,86.F-0B

5 .3 UF- 10 9 I F25 -11 2.49F-02 2. 3 5F -083 U3 2E -Ou I I.7E-06 3. 7bF- 1?6.59E-07 8.37F-05 9.82gE-Ob 3.84E-07 3. 17F-O ,5* F-0q.759F-05 I .70E-08 2. 3b8F-0d 7 IJOE-0U I *OIF-05 I .79E-Ob?. 21F-OS 3 .3 7E -O0Q 6.2 IE-05 I .9SF-07 I , ObF-OQ n.0 3.97F-O0 LI VER I 56'F-Ob 2. 16E-07 R. ?£E-M7 S.20E-D8 1 .06E-On I .29E-o5 I .83F-nS 7. 77F-05 7. 77E.-08 3.53F-n8 9. 32F -I a I E 15FO 63 3 8E- 15 9,LIE-i5 2. 1 7E-OA 1 bhF -In ,.88E-1 I I ,bQE-Ob 1 .72E-n9 1.79F-04I 4.6QE-07 S.S96E-1 2 7.b2E-07 7.87E-nb 2.5UE-16 S. 37E-o8 U.87E-09 I.42F-09 1 U.RE-05 1. iF-08 5.UOE-05 9. IOE-O5 I u3SF-nS I uSE-nb 0.0 I .OSE-n0i 2o0TE-ng 6. U7E-08 3,B5E-10 6.72E-03 I .59F-O0 9.bOE-01 5.h7E-07 7.70E- n 3.?2E-07 I .72E-0A 9.11IE-35 6.AOE-lh 1 .3 F-05 5. 36E-05 U .OE-31 3.LE-t 2 3.21F-07!1.2nE-I 3 A. 7E-1 3 5S. 71E-LnQ 2.7 1E-1 1 9.bSE-1 2 1 .QIE-07 I I* E-IQ 2.30F-05 5. 7c)E-OR I .I E-1 3 Li.S6E-ag 1 * ~ I AE -0 L6 I. QfE-Oh 3.2nE-na I .'99F-00 7.21E-10 1.SSE-Ob I O4E-09.1E7h-05 6. LRE-OS 9,21E-Oh 2.UOE-n7 2. 75E-1b q.00F-05?.1 7E-t 0 6.81E-09 3.1 OE-lO0 8A.7E-Ou I .3?E-07 Q.58E-05 TOTAL BODY THYROID 3.hbE-OLA 2.97E-05 I .1 7 F -OU 0.0 0.0 0.0 0.0 0.0 0.0.0 0).0 o.n 0.0 0,.0 0,0 0,0 0 .0 o~t 0.0 0.0 0,0 0.0 0(.0 ,0O 0.0 0.0 0l,0 0.0 0.0 0.0 h,0 0.0 0.0 0.0 KInNEY 3,*25E-O6 3.2UE-07.1 F-Ob I .07E-05 2.'1IF-05 h.Olr-nR 3705F-05 7. li3F-Ili 2.0QE-nq 2. 7E-IS 0l.0 0.0 0.0 7 .*7 .0 E-1A9.570F-07 R.55F-l 3 1 .5AQE-0S 3. 5F -0 I .f6E-17 9. IQE-O5?. 55F-nQ I .56E-05'4.* 9E-n9 3. 35E-04 La .3bE-~IL 5. 59E-05 9. 95F-07 ,I E-Oh t,57E-ou n,0 0.0 0,0 2., 1 2E-02 1 92F-05 2.-75E-03 LUNG GI-LLI 0.0 I.09E-06 0.0 0.0 bSbF-U7?.94F-OQ 7.,2E-o9 I.22E-05 I.30E-Otf 1.57E-06 2.11F-07 9. UE-Ob I.05b-0h S.07F-09 2.33F-15 ,;).9 E-09 0.0 u.70E-07 1.12E-07 1.5QE-nu 2.73L-05?.112E-07 I.115F-17 l.UqF-07 0.0 1.70E-)5 5,.73E-nE 1.SSE-Ob 7.31E-0e 7.02F-07 2.ULF-07 u.52F-n5 1.SoE-05 9.LRF-=Ob 2.USE-05 4.73F-Au 1.02F-0O1 i.51F-3S 2.50F-05 1.27F-07 2.b6)-18 2.76F-05 ?.IhE-09 5.blE-n5 5.S4E-06 2.l tjF -nU i M. 18 F- 0 3.Q1E-05 5.8OE-05 7.?2E-Ob 2.50E-05 3.Q4E-Ob 2.OOE-05 J.LbE-n5 3.25E-06 u.1SE-Ob ..58F-0S 3.u3E-n4 1,59k-os 5.P.5E-0L 3,'IOE-05 1.47F-05 5.95F-n6 9.57E-05 L.SOE-05 1.Q2E-04 2.68E-05 3.q -OL 1.59F-05 1.72F-06 2.53E-07 5.57E-05 1.07F-05 3.b3E-Ob 1.94E-O5;.63E-02 3.b6E-O5 1.11F-03 2,qSE-05 3,s1E-n2 4.19E-05 1.109-49 TABLE C-1 (Continued) NUCLIDE 88RA 223 88RA 224 68RA 225 88RA 22b 8BRA 22A 89AC 225 BqAC 227 9QTH 227 90TH 228 90TH 229 90TH 230 90TH 232 90TH 234 91PA 231 91PA 233 92U 232 92U 233 92U 23U 920 235 q2U 236 92U 237 92U 238 934P 237 93NP 23B 93NP 239 Q9PU 238 94PU 239 94PU 240 9PIJ 2ul 94tPU 242 94PU 240 95AM 201 95AM 2424 95AM 243 96CM P42 96CM 203 96CM 24, 9bCM 205 9bCM 246 96CM 247 96CM 208 98CF 252 BONE I .80F-0O 1.98F-O5 3,00E-0O 1.25E-01 4,41E-02 4.23E-0a 2.30F 00 2. 1 7F-0O 2.00F-Ol 8.88E 00 2,2QE 00 I .99E 00 I .63E-Ob S.n08 00 1.21F-06 5. I 0E-02 I .09£-02 1. O* E-02 I. OOF -02 1 .OOE-02 3.67£E-08 9.58E-03 1.69E 00 2.96E-07 2.87E-O0?.69E 00 3,05E 00 3.04E 00 6.0SF-02 2.89£ 00 3.45E 00 9.93E-O0 1.02F n0 9.qUE-01 I , I UF-02 7.8SE-Ol 5.QOE-O1 1.?bE 00 1.25E 00 1.22E 00 I.01E 01 7.33E-01 LIVER 2.77E-07 4.7BE-08 3.56F-07 2.39E-06 1.23E-Ob 5.82E-nO 3.05E-0l 3.92E-06 3.39E-03 I .33E-01 1.31E-01 1.12E-01 9.56E-08 I .91E-01 2.4 2E-07 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,47E-01 7.99E-09 2.82E-09 3.73E-01 4,19£-nl 4. 19E-01 3.28E-03 4.76E-01 3.46F-01 3.46E-01 3.40E-O0 I .18F-02 2.97E-O0 2.5IE-01 3.59E-01 3,59QE-O 3.53E-at 2.91E 00 0.0 TOTAL BODY 3.bOE-05 3.96E-06 9.13E-02 4.76E-02 2. 8OE-O5 1 .36E-01 6.25E-06 6.77E-03 4.36E-O0 6.36E-2?5.43E-O2 4.70E-08 I.9SE-OI 2.09E-07 3.66E-03 6.5QE-Ou 6,06E-Ou 6.07E-Ou 6.20E-00 9.77E-09 5.67E-O0 b.87E-OP 1.61E-n9 1.55E-09 6.6hE-£O0 7,53E-0?7.53E-0?1.29E-03 7,1 7E--2 B,5'4E-02 b6,7E-02 B.73E-02 hf.uE-n2 7.50E-04 4.61E-02 3.51E-0?7.1 £E-f2 7.03E-a?5.7qE-01 i .83E-02 THYROID n.0 0.0 0,0 040 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 nO, 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 0.0.0.0 0.0 0.0 0.0 0.0 0.0 0).0 0.0 KIDNEY 7.8SE-nb 1.35E-Ob I .OIE-05 6.77E-05 3.QSE-0O b .3£ -05 9,9 2E-02 2.22E-05 I. 89E-02 b .52E- I-6. (10E-0 1 5. *17E -01 5 *, L 1 E-0 7 0.0 9 .1 SE -07 5.56E-03 2.5E-03 2 ,. -E -03 2. 3E-n3 2, 3Sq-03 1.51£-fl?2. 1AF-03 5. 10E-O1 2. 7?£-09 8. 75E -flQ 3.?0F-01 3. 20£-0 I 5.93E-03 3,OSE-nt 3.64E-01 5. OIE-OI O.BbE-01 3.SOE-03 2.15E-01 1,64E-01 3.33E-ni 3.33E-01 3.28E-01 2.70E 00 0.0 2.5SE-02 q,78-03 2.92E-02 1 .17E-01 1. 61E-01I 2,21E-02 2.q F-0I 3. 78E-02 1.DIO E (in 3.50E 00 b.22E-01 5.31E-01 I.89E£-O 5.75E-OP 3.52E-05 2..23E-01 5.33E-02 S.?2E-02.QOF-02 5.01E-02 t.02F-0S 0.5FF-02 5.22F-02 1 .0E-05 u. 71F-Ob I .76F-01 I .b7E-0 I h7F-01 I .52F-O0 I sq9E-01 I .89F-01 5.86F-02 2.45E-02 5.bSE-n2 3.74E-02 6.32F-02 6.07F-02 5.86£-n?5.97E-02 5.86E-02 0.83E-al 1.56E-0l GI-I.1.1 2.B4E-O0 3.0 E-Ou 2.71E-Oa 2.94E-0O 5.00£-05 2.52E-04 O.92E-05 3. 3uE.-Oo 3.17E-04 3. 1 7E-OU 3. 73E-05 7.9'jF-05 7.03F-05 7

• 0 3-OSi 1.02£-05 0*lbE-05 3.89E-05 S.lf-05 0
• 80£-05 3.57E-05 I, 2OE -nr I .ASE-O0 4.92E-O5 2.13F-05 0 .52£F -OIi 0.52F-Os.20F -05 8. SE-07.o *05-OS t.03E -05.6bOE-09 5. 7qE-05 b.03E.-05 4.64E-05'4 *. 6E -05 0. 36F-05 0.291-O', 5.b E-OS S. 091-O0 I .78£ -00 I 4 1.109-50

TABLE C-2 TEENAGER INHALATION DOSE FACTORS (mrem/pCi inhaled)NUCL IDE I H 3 bC 14l 11!INA 22 27C0 55 27CO bO 38Sp B9 38SR 90 3c9Y 90 39Y 01'jOZR 95 JJINB 95 U'JRU 103 44RJ;U 106 S0SN' 123 52TE 1254 52TE 127 52TE t294 52TE 132 531 129 531 131 531 133 55CS 13Ll SSCS t37 56BA 1Ji0 57LA ILJO 5ACE 1'J1 58CE I1U U b3EUI ISLI QU 232 9?U 234I 9UPU 234~QLIPU 239 9Lipu 2U0 9LJPU 24I1 95AM 24J1 96CM 24I2 9CM 244L A ONE 0.0 5.66E-07 I *7bF-OS 0.0 0).0 4,.84E-06 I *.48E-03 I .41E-.08 b. 72E06b 1.*3bE -Ob I .70E-07 2.04OLE-08 I .05F-0b 5.09E-08 I b62E- II I .49E-07 3. 75F -09 3.53E-06 4I.21IE-06 I 54~E-06 6

• LE-05 8. 02E-05 6,62E-07 I .79E-09 2.84IE-07 5. 2uF-05 9.195E-05 6. lL4E-03 I .25F-03 3.22F-01 3.67E-01I 3.66,E-0 1 I .29E-04I I .20E-01 I .35E-03 b.99E-02 LIVER TOlTAL 8B1)Y 1.06E-07 1.OhE-07 5.66E-07 S.bbE-07 1.76E-05 1.76E-05 2.20E-08 2.93E-OR 1.55E-07 2.OhE-07 a3.0 1 .39E-07 0.0 9.01JE-05 0.0 3.79E-10 0 .0 1.80E-07!J.5LLE-07

3.17E-07 1.03E-07 9.7AIE-09 0.0 Q.ISF-flQ 0.0 1.3?E-07 7.6RE-08 I.1ISE-n7 2.32F-D8 b.QIE-09 7.30E-12 4I.02E-12 7.05F-08 2.40OE-08 3.-OOE-09 2.2QE-09 2.9UE.06 9.81E-06 5.90E-0b 3.SRE-06 2.58E-06 7.93E-n7 1.38F-04I 6.80E-05 1.03F-04I 3.79E-fl9 6.06E-10 LI.?7E-ng 4,.72E-10 l.b7E-10 1.90E-07 2.1RE-DA 2,17E-05 2,80E-06 I.02E-o5 ý.07E-06 0.0 LJ.37E-OLI 0.0 Z.72E-nS 3.4I3E-02 7.9FLE-03 5.OOF-02 9.06E-03 5.OLIF-n2 Q.13E-03 I.BLIE-0S 3.26E-Oh 4l.11F-02 7.79E-01 1.40OE-03 8,97E-0';2.99E-02 4I.16E-03 THYROID I .06F-01 5.bbE-07 i .7bE-05 A,(0.0 0.0 0.0 0.n 0.0 0,0 0.0 S.* 0 0.0 6.1 5E-OA 1 USE-OB 1.34E-1 1 i.FBE-05 2.54E-09 7.32E-03 I .7E-03 4.79E-04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0,0 0o0 K I 3NEY LUNG 1 .O06F-07 S.b6E-07 I .76F-05 I .71E-OLI I .07F-03 (USE 3.13E-0LJ?.n7F-03 0.0 PMULT 3.57E-04I 3.*20E-04I 9.96E-05 DOSE 4.'I9E-05?.05E-nS LI 693E-0LI FACTOR) 6.70E-05 I .33E-06 21.5LF-0LI 5.6b7E-05 0.0 0).0 0.0 I .ROE-05 1 .47F-05 P. 53F-OLI 2. 70E-05 7. 29E05 I .72E-03 9.29E-04 3.84IE-01 9.00OE-02 3.1ILI-01 2.98E-01 3.01E-01 I Q92E-04I I .0 1E -0 1 6.LI7E02 1 OSE-01 U 1-LI. I I .ObE -07 5.06eE-07 I .'J LE-Oh 1.1 I F-05 2.Q4lE-0'5 4.4 L2E -05 9.* bF-05 h. 79L-0'5 LI

• 7F -05 I .6bE -05 1.1 IOE -05 I .IRF-05 1. 16L-04I 3.91E-05 8.95E-06 I .01IE-09 LI.80E-05 b.b lE-OS 2. 16F-07 7.45FE-07 1 .25E-06 I .12E-06 9.bOE-07 5.981E-05 I .4I2E-05 1 .OSE-04*3.UIE-05 4,. IbE-OS 3.F81E-05's.52E-05'4. 13E-05 4,. 13E-05 7.94LE-08 LI.LJLE-05 LI.60E-05 N4ote: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-51 TABLE C-3 CHILD INHALATION

DOSE FACTORS.(mrem/pCi inhaled)NUCLIDE IH 3 6C i1 IINA ?2 27C0 5a 27C0 60 3ASR 89 38SR qO 39Y 90 39Y QI 4OZR 95 LINR q 5 44RU 103 44RU lOb 503N 123 52TE 125m 52TE 127 52TE 12QM 52TE 132 531 129 531 131 531 133 55CS 134 55CS 137 SbBA iaO 57LA I4O S8CE 14l 58CE 144 b3EU IS1 92U 232 92U 234 qiPU 238 94PU 239 94PU 20 94PU 241 95AM 241 96CM 242 96CM 244 BONE 0.0 1 .69E-06 4,42F-05 0.0 I..45E-05 4.A3F-03 9.87E-08 2.01E-05 3.8IE-06 06,0E-07 5.AUE-08 3.12F-O0 I OUE-OS I .52E-07 4.83E-I I a.t4UE-07 1.. 08E-08 I, 05E -05 I .?3E-05 4.53E-Ob 1.68E-O0 2.34E-O4 1 ,93E-Ob 5.20F-09 8.47E-07 1.57E-0U 2.87E-04 1 .83F-02 3.73E'03 9,62E-0I I.IOE 00 1 .09E 00 3.84E-o0 3.57E-01 4.,05F-03 2. 09E-0I LIVER TOTAL BODY 2.03E-07 2.03E-n7 1.69E-06 1.69E-06 4.42E-05 4u2E-05 0.t1F-n8 7.?3E-08 2.qOF-07 5.07E-n7 0.0 4.16E-07 0.0 2.70E-14 0.0 2.65E-OQ 0.0 5.36E-07 9.86E-A7 8.05E-07 1.96E-07 t.dLE-07 0.0 2.36E-OB 0.0 3.89E-07 1.74E-07 3.'3E-n7 5.25E-08 2.0hE-08 1.bSF-11 1.20E-11 1.58E-07 7.03E-08 6.08E-0 .91E-09 5.4OE-Ob 2.86E-fS 1°25E-05 Q.a7E-0h 5,S3E-06 2T17E-06 2.b9E-O0 6,02E-05 2.16E-o' 3.38E-05 I,26E-nq 1.laE-07 9.63E-10 L.3uE-In.24E-n7 6.30E-08'I,9tE-oS 8,37E-06 2.IPE-05 2.OqE-n5 0.0 1.31E-n3 0.0 2.31E-04 I.OOE-01 2.38E-02 1.13E-01 2.71E-0?I.I'4E-O.

2,73E-0?.16E-n5 9.73E-06 9.31E-02 2.33E-02 3,17E-03 2.bRE-0O, b.77E-02 1.24E-02 T-4YR310?.03E-07 I ,69E-06 a. a2E-05 0.0 0.0 0.0 0.0 0.000 0.0 0.0 0.0 I .9RE-07 4.35E-05 U.,IE-l 1 1 .4bE-07 7.24E-04 2.14E-02 u.t6E-03 I

• 36F -03 0.0°00 0.0 0.0 0.0 0.0 0.0 0.n 0.0)0.0r 0.0 0.0 0.0 K I )NFY LJN.G 2.03E-07 I b69E-06", '2E-05 (USE 1.67E-03_____ .0E-Oa*.OOE-n3 7.26E-05 ADULT 6190E-OI 5. 72F-O0 DOSE I 1.71E-04i 3.93F-03 FACTOR) 9.46E-04 I .30F- 04 2.5E-Ob a.T7F-OU I .03E-O0 0.1.0 0.0 3.21E-n5 2.71F-05 0.69QE-0 U*Q2E-05 I. 39E-n4 3. 32F-n3 I .67F-03 7,"J3E-nl I .70F-01 5.87E-01 5.5bF-0I 5.61E-ni 3.6lE-0OJ I .QSF-OI.2 ? E_- n_1-_?,02E-01 GI-LLI 2. 03R -07 I .bqE-06 9. -0o 2.H3F-0%I.56F -05 Q1 1 ,EF-Ob..23E-OS LI .* _-O.I S2E -05 lI. 1 I- -05 7. 13 7-07.10 3E-06 I. 53F -05 q.22E -OS)b.52(- -05 2.168-07 7. I 7E-05 I .54E-O0 I .08E-Ob , 22E-')7 2.. 28E-01 I.flE-05 I .07E-OP/J. 57F -05 3.71F -05 a. V2E-is Li, LE -05 8. 1bE-OF a. 73r-05 6 0,0 Note: 0.0 means insufficient data or that the dose factor is <1.0E-20.1.109-52 TABLE C-4 INFANT INHALATION

DOSE FACTORS (irirem/pCi inhaled)NUCLIDE bC 1" IINA 22 27C0 58 27C0 b0 38SQ Q.38SR QO 39Y 00 39Y 91 4nZR 05 4INB 05 4JRUi 103 44RU 106 50SN 123 52TE 1254 52TE i27 52TE 1294 S2TE 132 531 129 531 131 53! 133 55CS 13u 55CS 13 7 5b8. !LAO 57LA 1LO 5BCE 1l1 58CE IlUq b3EU 154 92U P32 92U 234 quPU 238 9gPU 239 gapu PLao 94PU 2U1 95AM 241 96CM 2u2 obC4 2U4 S O:N F 0.0 3.6OE-O0 7.53E-05 0.0 0.0 3.01E-05 9.4FE-03 2.lOF-07 UL27E-05 7.7uE-O6 9. I6E-07 I .21E-07 6.b5E-O6 2.22E-05 3.2uE-07 1.03E-I0 Q ,UuF-07 2,25E-08 2.23E-05 2.59F-05 9.5hE-06 3. 43E-OL".90E-04.0 7 7E-06 1 .09E-08 i .80E-Ob 3. 3IF-O4 5.99E-0O 3.q1E-02 7.94qE-03 2.05E 00 2.33E 00 2.33E 00 5. IBE--04 7.61E-01 9,62E-03 4.L45E-0 1 LIVER 3. 07E -n7 3.6OF-06 7.53E-05 8. 39E-OR!. OOE-07 0.0 0.0 0,0 1 .9SE-06 4. 11E-07 0.0 0.0 U.6IE-n7 I .39E-07 w. 31E-t II 4i 1 UE-07 I. I2E-08 I .b2E-05 3.n5E-05 I .38E-05 5.8QE-O0 5.22E-04 S05E-09 2.29E-3q 1. IIE-0b I 30E-04 4.95E-n5 0.0 0.0 2.66E-01 3.O0E-01 3.02E-01 I. I OE--04 2.47E-l1 8.40E-03 I. 70F-01 TDIAL 3J)Y 3.07E-07 3.bOE-06 7.53E-05 I .2nE-07 8.38E-07 5,89E-07 5.7hE-0A 5.65E-09 191 LE-OB 2.ULiE-07 4 .! 9E -n 8.16E-07 7.30E-07 u.UOE-08 2.56E-1 I 1.47E-07 I 5.A2E-05 I .70E-35 LA. I QE-Oh 5.23E-05 3.15E-n5 2.11IE-07E-1 0 1.2QE-17 I .7AE-05 3.72E-05 2.71E-03 0.91E-14 S.OSE-92 5.77E-02 5.81E-0?2.07E-05 L.96E-02 5.71 F- 14 3.07E-07 3.SAE-06 7.53E-0 5 0.0 0.0 0.0 0.0 0.00.0 0,0 LA. IlE-07 0 .O E-1 .0 9F-0 7 I .OOE-10 3. 63F -0 7 I .70E-05 5.21E-02 I .OIE-02 3. 33E-03 0.0 0.0 0.0 0.0 n.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 K I NE Y LU N C 3.07E-07 3.bOE-Ob 7.S3F-05 h.28F-O0 (USE 3.QRE-03 I .h5F-n3 I .09E-02 AU. Q8E-04 ADULT' , 88E-03 I .2QE-03 DOSE 3.JiF-OU D. OE -04 I .07E-02 2.SBF-A3 FACTOR) 3.54E-O4 7. 03F-00b I .31E-03 2.Q8E-04 0.0 0.0 0.0 7.22E-05 5.7%E-05 ,I 17E-03 1 .21E-04l 3.7AE-O0 9.06E-03 3. 99E-03 2.02E 00*.7LE-fl I .51E 00 I .43E 00 I .45E 00 q.9OE-nf S.32E-01 3,UIF-01 5.51E-01 GI-LLI 3.07F-n7 3.OF-Oh 1 .22L-06 8.67F-06 2. 4.6bE-9.89F- *5. 1 2E -05 I .01E-05 8. b7E-Ob 11. I SE-05 1.2bE-04 4.28F-05 9.71F-Oh I .87E-05 5.23F-05 6. b8E-05 2M2E-07 7b6hE-07 I .S3E-0b 9.80E-07 9.45E-07 2.77E-06 6.43F-05 1 .4l F-05 I 15E-OLA 3.73E-05 L.SSE-05 A. 16E-05 4.qbE-05 U.51L-05 A.51E-05 8,.bE-08 U.86E-05 5.29E-05 5.03E-05 0.n 2.65E-02 0.0 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1 .109-53 This yields C V 4 (ro) = 3.17 x 107 Q7 4[x/Q'](r,) 0.11/0.16 U= 2.2 x 107 Qi 4[x/Q'J(r,O) (C-8)where C v 4 (r,O) is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;!Q14 is the annual release rate of carbon-14, in Ci/yr;0.11 is the fraction of total plant mass that is natural carbon, dimensionless; 0.16 is equal to the concentration of natural carbon in the atmosphere, in g/M 3 and 3.17 x 107 is equal to (1.0 x 1012 pCi/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.

Using the method described in Reference 3, the NRC staff derived the following equation: CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H) = 1.2 x 10 7 Qi[X/Q'](re)/H (c-9)where Cv(r,o) is the concentration of tritium in vegetation grown at location (r,e), pCi/kg;H is the absolute humidity of the atmosphere at location (r,o) in g/m3 Qý is the annual release rate of tritium, Ci/yr;0.5 is the ratio of tritium concentration in atmospheric water to tritium con--centration in plant water, dimensionless; and 0.75 is the fraction of total plant mass that is water, dimensionless.

The deposition rate from the plume is defined by: dC(r.o) = 1.1 x 10 8 ai(r,e)Qj (C-10)where 6 1 (r,O) is the relative deposition of nuclide i, considering depletion and decay in transit to location (r,O), in m" 2 (see Regulatory Guide 1.111) and 1.1 x 108 is the number of pCi per Ci (1012) divided by the number of hours per year (8760).For radioiodines the model considers only the elemental fraction of the effluent.

The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Reference 4). With this consideration included, Equation (C-l0) for radioiodine becumes: I 1.109-54 15.5 x 107 Si(r,6)Q.(C-1l)and Q! is the total (elemental and nonelemental) radioiodine emission rate. The retention ictor r for elemental radioiodine on vegetation should be taken as unity, since the experimental mea-surement (References 5, 6, and 7) techniques used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (References 8, 9, and 10).For radioiodines, the deposition model is based only on the dry deposition process. Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con-sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).For particulates, the deposition model considers both wet and dry deposition.

There is also a retention factor (r of Equation (C-7)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (References 11 and 12). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.

a. Parameters for Calculating Nuclides Concentrations in Veqetation Consumed by Man When the radionuclide concentration in vegetation directly ingested by man is estimated using Equation (C-7), the following parameters are used: Parameter Value Yv (vegetation yield) 2.0 kg/mi 2 te (exposure time to plume) 60 days th (holdup after harvest) 1 day for garden-fresh leafy vegetables 60 days for stored vegetables tb (soil exposure time) 15 years (midpoint of reactor operating lifetime)All other parameters in this equation are given in Regulatory Position C of this guide.b. Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q exp(-xit) (C-12)where C'(r,a) is the concentration in milk of nuclide i, in pCi/liter; CY(r,O) is the concentration of radionuclide i in the animal's feed, in pCi/kg;Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively; for nuclides not listed in Table C-6, use the values in Table C-5);1.109-55 TABLE C-5 STABLE ELEMENT TRANSFER DATA ELEM H HE Ll BE B C N 0 F NE N A 4G AL al P S CL.AR K CA sc TI V CR MN FE CO NJ CU ZN GA GE A5 SE BR KR Re SR Y ZR NB RU RN Po AG CD IN SN Biv VEG/SOIL 4,BE O0 5.OE-02 8,3E-OG 4, 2E-o4 1.2E-01 5*5E" O0 7.5E 00 1.bE GO 6.5E-4O iE-ol 5.2E-02 1.3E-ol I .BE-04 1.5E-OM 1.IE nO S19E-0!S.OE 00 6oOE-01 3,7E-oi.,,6E"O,?I .IE-03 So"E-OS i 3E-03 2.SEOu0 2.9E-io2 6,6E-Oq 9,a4E-03 1,9E-O2 1.2E-01 (S.OE-OI 2.SE-0O i OE-ol I.OE-02 1.3E O0 7#bE-01 3,OE O0 1,3E-01 1.7E-02 2.bE"03 16.7E-04 9.4LE,-03 1.2E-01l 2,5E-01 5.OOZ02 1,3E 01 5,OE' 00 9.OE"01 t,;5E-Gt 2.5E-01 3, OE-O I 2,SE-01 2,5E'03 F m(Cow)MILK(CD/L I ,OE02**2,0E-O;5,0E-O.I,0E-Oa 2,7E-0" 1,2E-022. 1.,E-02 2. OE-O?4 .OE-02*4** IOE-02 5,OE-Ou I1OE-Oa 2,5E-OP IBE-02 5,OE-02 2.0E-028 , OE-03***5.0E'06**5,OE-06 S. GE-Ge, lOE-03 2,2E*03 2,SE-Ou 1?2E-03 I.OE-03 6,7E-01 I# 4E-02 5,0E-05 S. OE04 6,OE"03',SE-02 S.OE"O2 2, EOE.02 3#OE-O2 B OE-O4***I I OE-05 S OE-06 2#5E"03 7,5E-03 2.SE-02 IOE"O6 I.OE-02 I,OEOG.5,0E'02 5aOEw02 162E-Ou I.OE-0O 2.5E-03 Ff MEAT(D/XG) 2.2E-02 2,nE-02 i.oE-n3 B.OE-n2 3. 1IF-n2.OE-02 I .6F-02 I SF-ot 2. OF-n2 3.OE-02 SIOE-03 I ,E-o3 Q.OF-03 u.bFE-2'J.6 -n2 I a.E-nI 8. nE-o2 1.2E-02 a.bE-02 3,IE-02 2a3E-n3 1.4E-03 4.OE-04 4.OE-n2 1.3E-02 S,3E-03 8. DE-03 3OBE-62 I ý3F on?.fE 01 2.OE-03 1.5E-n3 2.OE-n2 3 a I E -0'Is.6 E-03 3,OIE.02 2. , BE -01 5,OE-o3 4. G E-ot t.SE-03 I .7E-02 8.OE-n3 R.MfE-02 ELEM SB TE I VE CS LA CE PR ,jD PM S4 EU GD TB Dy ER T YB LO NF TA w RE OS I R PT A U TL PB 81 P3 AT RN FR PA A C TH PA U NP PU A 4 9K CF ES F -8.av VES/S3IL I.IE-02 I'3E 00 2,OE-02 IOE 01 I OE-02 b,OE-03 2,SE-03 2*5E-03 2,SE-03 2 5E-03 2,SE-, 3 2.E-03 2.SE0 3 2,bE-03 2.bE-03 2,SE-03 2,#E-03 2. SE-03 2, 5E-03 2, SE-o33 2 bvE-03 1,7E-OP 6,3E-03 1. SE Ot 5,3E-01 2.SE-03 3 @3E-0I 2.5E-01 b, SE-02 I9SE-01 2oSE-01 2, SE-Ol 3,SE 00 I, E-O2 3, IE-OQ 2.5E-03 Q,2E-03 2,SE-03 2,SEmO3 2, SE,,03 2, SE"-0 2, SE"04 2, SE,03 2,SEo.03 2 , SE"03 2,SE-03 2, SE-O3 Fm(Cow)41 LK (1/L)I oSE-03 I .0E-03 b. OE-3l3 2.OE-02 I

• 2E-02".GOE-O1***5OE-Oh SOE-Ob S.OE-Ob 5.OE-Gb 5.0E-Ob S.OE-O6 5.OE-Gb SOE-Gb 5.OE-Ob SOE-Gb S.OE-Ob SoOE-06 5IOE-06 2.5E-02 S,OE-Ou 2*5E-02 5.OE-03 5,OE-03 S.OE'03 3.BE-02 2,2E-02 b.2E-O04 S5OE-O0 3,0E-O0 S.OE-02 2.oE-02 5GOE-02.80"03**5. GE-O6 S. GE-Oh SOEGOb S.OEGOU 5,GOE-b 2,OE-Oh 5.GE-Gb S.0E-Oh S.OE-Gb 5,0E-06 5,OE-Ob S.,OE-Gb 5,.OE -Oh Ff MEATT(D/KG)

POE-03 7, 7E-02 I2ý9E-03 2. E-02* OE-03 3.2E-03 2.OE-04 1.2E-03 4,7E-03 3.3E-03 4.8E-03 S. E-03 4.BE-03 3, bE-03~4, (E-03 S.3E-03 U,*E-03.uOE-03 u.OE-03 4.OE-03 ,Ci E-O1 I.bE O0 1.3E-03.,E-03 uOE-OI 1,SE-03 4.OE-03.OE-03 2.bE-G1 u.OE-O?2,9E-04 I SE-02 I 2E-02" GOE O0 2,OE-02 2.OE-02 3,UE-02 be OE-02 2. GE -04I B.OE 02 3,4E-O4-2,0E-04 2,OE-Oci 2. OE-O *i-2,OE-G04-2,0E-O*20GE-OU f II Ref. 1.Ref. 3.Ref. 13.t Refs. 7, 8, 9, 10, 14, 15, 16, 17.+t Ref. 18.E1 1.109-56 TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK ELEMENT Fm (days/liter) H 0.17 B 0.012 C 0.10 Mg 0.042 P. 0.25" Cl 0.5 K 0.057 Ca 0.47*Fe 1.3E-04 Cu 0.013 Sr 0.014 I 0.06 Cs 0.30 Po 0.0018 Computed from the data of Refs. I and 19.**Ref. 13.1.109-57 QF is the amount of feed consumed by the animal per day, in kg/day;t is the average transport time of the activity from the feed into the mil: and to the receptor (a value of 2 days is assumed); and Ni is the radiological decay constant of nuclide i, in days-Milk-producing animals are assumed to be on open pasture for the following grazing periods: Reg i Uon Southern U.S.Northern U.S.Pasture Period Whole year (fp 1)May -Sept. (fp = 1/2)where fp is the fraction of the year that animals graze on pasture.These data may be supplemented by information on site-specific dairy practices.

The concentration of radionuclide i in the animal's feed is then cv(r, a) f fCP(e)+ (I1 f )C 5 (r,) +f(1 (-3 , pfC(ro -,.p i + -I 5 C~ (-where P Ci(ra) is the concentration of radionuclide i on pasture grass, in pCi/kg;I(ro) is the concentration of radionuclide i in stored feeds, in pCi/kg; and f s is the fraction of daily feed that is pasture grass when the animal grazes on pasture.following parameters will be employed in evaluating the milk pathway, unless data is supplied.The site-specific Parameter QF (animal's daily feed)th (storage time of animal's food)te (crop exposure time)Yv (crop yield)Value 50 kg/day (wet weight) for cattle 6 kg/day (wet weight) for goats 0 for pasture 90 days for stored feed 30 days 0.75 kg/m 2 (wet weight) for pasture 2.0 kg/m 2 (wet weight) for stored feed 4 1.109-58 c. Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentra- tion in meat is estimated as F (C-14)where C 1ý(r~o)is the concentration of nuclide i in animal flesh, in pCi/kg;Ff is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t is the average time from slaughter to consumption, which is assumed to be 20 days.All the other symbols are as previously defined.Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.4. Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by 0 .(r,,,) = DFIi4a [Uvf Cv(r,.) + UCr,) + U FC(, + ULf CL(r, e ija i [a a g i a i -Ua i a U. r (C-15)where D .(r,e)Dija is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr;DFIija is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables A-3 through A-6 of Appendix A of this guide); and v m F L Ua , Ua, Ua, Ua are the ingestion rates of produce (non-leafy vegetables, fruit, and grains), milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide).All the other symbols are as previously defined.The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD = DF .rvf + m + F F L L ja ija a g 1 a i a i a k I (C-16)1.l0-59 REFERENCES FOR APPENDIX C I. Y. C. Ng et a), "Prediction of the Maximum Dosage to Man fro;m the rallout cif ucclar Devices, IV Handbook for Estimating the Maxi'ium Internal Dose tro, m RPdio!;uclide:; ,Pc :d-, to the Biosphere," USAEC Report UCRL-5D163, Part IV, 1968.2. R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, Cle,',eland, Ohio, 1D70.3. L. R. Anspaugh et al, "The Dose to Man via the Fooo-Chain Transfer EResultinq fro!:m Exposure to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1i, 1972.4. B. H. Weiss et al, "Detailed Measurement of 1-13' in Air, Veqetation and 'i1[' ;.-ound Three Operating Reactor Sites," NUREG-75/021, U.S. N~uclear Regulatory Commission, Washington, D.C., March 1975.5. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!., To," USAEC Report ID0-12063, January 1968.6. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at le National Reactor Testing Station, Progress Report Number Four," USAEC Report iO--126E.December 1968.7. B. H. Weiss et al, "Detailed Measurement of 1311 in Air, Vegetation and M.1ilk around Three Operating Reactor Sites," Environmental Surveillance around Nuclear Installatiorns.

!nter-national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. 1: pp. 169-190, 1974.8. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, West Germany, IRS-W-6, June 1973.9. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 131i Doe to the Thyroid," Institute fur Reaktorsicherheit, IRS-W-5, April 1973.10. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental of 1311 from Air to Milk," Institute fur Reaktorsicherheit, IRS-W-13, April 1975.11. C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout RadiontucI'det.

on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971.12. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption of Cow's Milk as Critical Pathways for 1 3 7 Cs, 5 4 Mn and 1 4 4 Ce-1 4 4 Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.13. R. J. Garner, "Transfer of Radioactive Materials from the "i,T,'restrial Environ;nent to Animals and Man," CRC Press, Cleveland, Ohio, 1972.14. F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol. 17, pp. 565-9, 1969.15. R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.), Pergamon Press, Oxford, England, 1966.16. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1311 and 1 3 7 Cs to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.E I.109-60 REFERENCES (Continued) 17. J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report 100-12067, p. 36, 1968.18. R. S. Booth et al, "A Systems Analysis Methodology for Predicting Dose to Man from a Radioactivity Contaminated Terrestrial Environment," Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501, Oak Ridge, Tenn., pp. 877-893, 1971.19. D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.1.109-61 APPENDIX D MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS Calculation of the annual population-integrated total body and thyroid doses should be performed for the three effluent types identified in this guide. These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50.For the purpose of calculating the annual population-integrated dose, the 50-mile region should be divided into a number of subregions consistent with the nature of the region. These subregions may represent, for example, the reaches of a river or land areas over which the appro-priate dispersion factor is averaged.

Dispersion factors, population data, and other information describing existing or planned uses of the subregions should be developed.

1. General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con-sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows: D 0.001 Z Pd f Djdafda (D-l)Dd Yd jad where Djda is the annual dose to organ j (total body or thyroid) of an average individual of age group a in subregion d, in mrem/yr;D is the annual population-integrated dose to organ j (total body or thyroid), i in man-rems or thyroid man-rems;fda is the fraction of the population in subregion d that is in age group a;P d is the population associated with subregion d; and 0.001 is the conversion factor from millirems to rems.The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide. The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.

For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption.

For all the food that is produced within the 50-mile radius, the radioactivity concentrations are averaged over the entire area by weiqhting the concentrations in each subregion by the amount produced in each subregion.

This average concentration is used in calculating the population doses. The 50-mile average concentration of nuclide i in food p is computed as C = (/V ) exp(-Ait ) C v (0-2)ip p 1 p d dip dp The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.1.109-63 TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA PER CAPITA USAGE FACTORS (I lAY CHILD TEEN ADULT Uap)PATHW JNITS Fruits & Vegetables & grain Milk Meat & Poultry Fish Seafood Drinking water Shoreline recreation Inhalation External Exposure from Deposited Airborne Radio-active Materials 200.00 170.00 37.00 2.20 0.33 260.00 9.50 2700.00 240.00 200.00 59.00 5.20 0.75 260.00 47.00 5100.00 190.0 110.0 95.0 6.9 1.0 370.0 8.3 7300.0 kg/yr 1/yr kg/yr kg/yr kg/yr 1/yr hr/yr m 3/yr 8760.00 8760.00 8760.0 hr/yr Consumption rate obtained from Reference 3 of Appendix A and in Reference 4 of Appendix A.Data obtained directly from Reference 4 of Appendix A.Data obtained directly from Reference 15 of Appendix A.age-prorated using techniques i 1.109-64 where C d is the average concentration over subregion d of the nuclide i in pathway p, Cdip in pCi/kg or pCi/liter (see Appendices A and C of this guide for models and equations for calculation of pathway concentrations); C ip is the 50-mile average concentration of nuclide i in pathway p, in Cip pCi/kg or pCi/liter; t is the transport time of the food medium p through the distribution system, p in days (Tahle D-2 presents estimates of the transport times that may be used in lieu of site-specific data);v d is the annual mass or volume of food medium p produced in subregion d, Vdp in kg or liters;V is the mass or volume of the food medium p produced annually with the p' 50-mile radius about the site, in kg or liters; andis the radiological decay constant for nuclide i, in days-The population served by all the food produced within 50 miles of the site is estimated as P p = Vp/X Uapfa (0-3)where fa is the fraction of the population within the age group a;P is the estimated population that can be served by the quantity of food p p likely to be produced within 50 miles of the site;U a is the use or consumption factor of food medium p for the average Uap individual in age group a, in kg/yr or liters/yr (taken from Table 0-1);and V is the annual mass or volume of food medium p likely to be produced within a 50-mile radius about the site, in kg or liters.The annual population-integrated dose is then calculated as?~O~ 0.001 1 P 8*U ODF. (0-4)DiP= .Ol Z p where P if Pp < P Pp p 5 P 50 if P p > Ps and DFai is the dose factor for age group a and nuclide i, in mrem/pCi (taken from Tables A-3 to A-7 and C-1 to C-4);1.109-65 TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD T DISTRIBUTION SYSTEM FOOD MEDIUM Fruits, grains, and vegetables Milk DISTRIBUTION TRANSPORT TIME (in days)Meat and poultry Sport fish Commercial fish Drinking water 14 4 20 7 10 IO To be used in lieu of site-specific data on food distribution.

4 1.109-66 D. is the annual population-integrated dose to organ j (total body or thyroid), Dj in man-rem/yr or thyroid man-rem/yr; Pp is the population consuming food medium p; and P 5 0 is the total population within 50 miles.All other factors are as defined above.Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50. In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D). Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.2. Use of the Models a. Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq-uid effluents should be evaluated for the following principal pathways: potable water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri-gated with water that has received the liquid effluent.

In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant* contribution to the annual dose received by an exposed population group.(1) Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump-tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application.

The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose. The formulation expressed in Equation (D-1) may be used.The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1. The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.

If the population served by a particular water supply system is not known, it can be estimated by the following: Pw = v/c (D-5)where c is the average daily usage of individuals on the system, in gal/day per person;P w is the estimated population served by the water system; and v is the average'daily intake of the water supply system, in gal/day.If the industrial usage from the water supply system is known, it can be sub-tracted from the average daily intake of the system before this value is entered into Equation (0-5).For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here. Any pathway so identified should then be evaluated by a model similar to that used above.1.109-67 The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle. This population may be pro-rated to include only the population within the 50-mile radius. Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius.Such exposed population should be included in the 50-mile population dose evaluation.

(2) Doses from Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions.

The mixing ratio (or dilution) should be evaluated for each sub-region using an appropriate hydrological model. For sport harvests, the entire edible harvest is assumed to be ingested by the population within 50 miles. The formulation expressed by Equation (D-4) should be used with the population Pp given by the results of Equation (D-3).The age-specific ingestion factors of Table D-I may be used in lieu of site-specific data.For commercial harvests, the production within 50 miles from the site is con-sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with Vp as the total estimated U.S. commercial harvest of the aquatic food medium p. The annual population-integrated dose is then computed using Equation (D-4) with Pp = PSO" The age-specific factors of Table 0-1 may be used in lieu of site-specific data.(3) Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by sunmming the product of the individual doses in each subregion and the population exposed therein. All subregions within the 50-mile radius should be considered where existing or designated recreational facili-ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The formulation of Equation (D-1) is appropriate.

(4) Doses from Consumption of Terrestrial Food Products Irrigated by Waters Receiving the Liquid Effluent The annual population-integrated total body and thyroid doses from consumption of food irrigated with water from the body receiving the liquid effluent are evaluated following the procedures outlined in the development of Equation (0-4). Note that the term Vp of Equations (0-2) and (D-3) denotes the total production of food medium p within 50 miles, not just the total production of irrigated food medium p. The consumption rate data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4).b. Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu-ents, ingestion of contaminated terrestrial foods (milk, meat, and vegetation), and external irradiation from activity deposited on the ground. In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant contribution to the annual dose received by an exposed population group. (See Regulatory Position C.1 of this guide.)For the evaluation of exposures from atmospheric releases, the 50-mile region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE, etc.)and annuli at distances of 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 miles from the center of the facility.

The atmospheric dispersion factors (x/Q') or similar factors should be evaluated at the radial midpoint for each of the subregions using appropriate atmospheric dispersion models such as those described in Regulatory Guide 1.111.(1) Doses due to Exposure to Noble Gases The annual population-integrated total body dose due to noble gas effluents should be evaluated by summing the products of the individual doses in each subregion and the population in each subregion.

Equation (D-1) may be used. For external exposure, the model does not differentiate between age groups. A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.E 1.109-68 (2) Doses due to Inhalation of Radlolodines and Particulates The annual population-integrated total body and thyroid doses from inhalation of airborne effluents should be evaluated by summing the products of the individual doses received in each subregion and the population in each subregion.

Equation (D-1) may be used.The age-specific inhalation rates of Table D-1 may be used with the data of Tables C-l to C-4.(3) Doses due to Ingestion of Terrestrial Food Products The annual population-integrated total body and thyroid doses from ingestion of terrestrial food products should be evaluated using the production data for each subregion.

For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-1, D-2, and A-l to calculate population doses.(4) Doses due to External Irradiation from Activity Deposited o' the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-

7. REFERENCE

FOR APPENDIX D"Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Commerce, 1975.1.109-69}}