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P.2 

k V 

<*» ««0(/( U.S. NUCLEAR REGULATORY COMMISSION 

Revision 1 

October 1977 

REGULATORY GUIDE 

»**** OFFICE OF STANDARDS DEVELOPMENT 

/oZ&q-p/^---^'/^ 

REGULATORY GUIDE 1.109 

CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE 

RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 

10 CFR PART 50, APPENDIX I 

USNRC REGULATORY GUIDES 

Regulatory Guides *wtx» issued to describe and make available to the public methods 

acceptable to the NRC staff of implementing specific parts of the Commission's 

regulations, to delineate techniques used by the staff in evaluating specific problems 

or postulated accidents, or to provide guidance to applicants. Regulatory Guides 

are not substitutes for regulations, and compliance with them is not required. 

Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance 

of a permit or (icense by the Commission. 

Comments and sugoestions for improvements in these guides are encouraged at all 

times, and guides will be revised, as appropriate, to accommodate comments and 

to reflect new information or experience. This guide was revised as a reriuit of 

substantive comments received from the public and additional staff review 

Comments should be sent to the Secretary of the Commission, U 5 . Nuclear Regulatory Commission, Washington, O.C. 20555, Attention Docketing and Service 

Branch. 

The guides are issued m the following ten broad divisions' 

1. Power Reactors 6. 

2. Research and Test Reactors 7 

3. Fuels and Materials Facilities 8. 

4. Environmental and Siting 9. 

5. Materials and Plant Protection 10. General 

Products 

Transportation 

Occupational Health 

Antitrust Review 

Requeits for single cop m of issued guides (which may be reproduced) or lor placement on an automatic distribution hst (or single copies of future guides m specific 

divisions should be made in writing to the US . Nuclear Regulatory Commission. 

Washington, O C 20555. Attention Director, Division of Document Control. 

•IndflaS'S-^J

 nUmber o f chan 9e s in thi* revisio n has made U impracti °a l t 0 

naicate the changes with lines in the margin. 
P.3 

TABLE OF CONTENTS 

. Page 

A. INTRODUCTION 1.109-1 

B. DISCUSSION 1.109-1 

C. REGULATORY POSITION 1.109-2 

1. Doses from Liquid Effluent Pathways 1.109-2 

a. Potable Water 1.109-2 

b. Aquatic Foods 1.109-2 

c. Shoreline Deposits 1.109-2 

d. Irrigated Foods 1.109-3 

2. Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere 1.109-4 

a. Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks 

More Than 80 Meters High 1.109-4 

b. Annual Gamma Air Dose from All Other Gas Releases; Annual Beta Air Dose 

from All Noble Gas Releases 1.109-5 

c. Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks 

More Than 80 Meters High 1.109-5 

d. Annual Skin Dose from Noble Gas Releases from Free-Standing Stacks More 

Than 80 Meters High 1.109-6 

e. Annual Total Body Dose from All Other Noble Gas Releases 1.109-6 

f. Annual Skin Dfcse from All Other Noble Gas Releases 1.109-6 

3. Doses from Radioiodines and Other Radionuclides Released to the Atmosphere... 1.109-6 

a. Annual Organ Dose from External Irradiation from Radionuclides Deposited . 

onto the Ground Surface 1.109-7 

b. Annual Organ Dose from Inhalation of Radionuclides in Air 1.109-7 

c. Annual Organ Dose from Ingestion of Atmospherically Released 

Radionuclides in Food 1.109-7 

4. Integrated Doses to the Population 1.109-8 

5. Summary of Staff Position 1.109-8 

0. IMPLEMENTATION 1.109-8 

APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS 1.109-11 

1. Generalized Equation for Calculating Radiation Dose via Liquid Pathways 1.109-11 

a. Radionuclide Concentration in Environmental Media (C ) 1.109-11 

b. Usage (U ) IP 1.109-11 

c. Dose Factor (D,.„.) 1.109-11 

a ipj 

2. Equations for Liquid Pathways 1.109-12 

. a • Potable Water 1.109-12 

b. Aquatic Foods •. 1.109-12 

c. Dose from Shoreline Deposits 1.109-12 

d. Dose from Foods Grown on Land with Contaminated Water 1.109-15 

REFERENCES FOR APPENDIX A 1.109-18 

i11 
P.4 

TABLE OF CONTENTS (Continued) 

Page 

APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE 

ATMOSPHERE 1.109-19 

1. Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks 

More Than 80 Meters High 1.109-19 

2. Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta 

Ai r Dose from Al 1 Nobl e Gas Rel eases 1.109-20 

3. Annual Total Body and Skin Doses from Noble Gas Effluents 1.109-20 

a. Releases from Free-Standing Stacks More Than 80 Meters High 1.109-20 

b. All Other Releases 1.109-22 

REFERENCES FOR APPENDIX B 1.109-23 

APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES 

AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE 1.109-24 

I.i Annual External Dose from Direct Exposure to Activity Deposited on the 

Ground Plane 1.109-24 

2. Annual Dose from Inhalation of Radionuclides in Air 1.109-25 

3., Concentrations of Airborne Radionuclides in Foods 1.109-25 

a. Parameters for Calculating Nuclide Concentrations in Forage, Produce, 

and Leafy Vegetables 1.109-25 

b. Parameters for Calculating Nuclide Concentrations in Milk 1.109-27 

c. Parameters for Calculating Nuclide Concentration in Meat 1.109-28 

4. Annual Dose from Atmospherically Released Radionuclides in Foods 1.109-28 

REFERENCES FOR APPENDIX C 1.109-29 

APPENDIX; 0, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT 

EFFLUENTS. • • 1.109-30 

1. General Expressions for Population Dose 1.109-30 

2. Use of the Models 1.109-33 

a. Population-Integrated Doses from Liquid Effluents 1.109-33 

b. Population-Integrated Doses from Airborne Effluents 1.109-34 

REFERENCE FOR APPENDIX D 1.109-35 

APPENDIX E, NUMERICAL DATA FOR THE CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE 

RELEASES OF REACTOR EFFLUENTS 1.109-36 

1. Environmental Data 1.109-36 

2. Human Data 1.109-36 

3. Dose Factors 1.109-36 

4. Other Parameters 1.109-43 

REFERENCES FOR APPENDIX E 1.109-70 

Iv 
P.5 

TABLE OF CONTENTS (Continued) 

Page 

APPENDIX F, METHODS FOR EVALUATING THE I FUNCTION 1.109-72 

1. Derivation of the I Function 1.109-72 

2. Evaluation of the I Function 1.109-75 

REFERENCES FOR APPENDIX F 1.109-80 
* * 

LIST OF TABLES 

Table Page 

1 Summary of Staff Position - Methods of Evaluating Compliance with 

Appendix I 1.109-9 

A-1 Bioaccumulation Factors To Be Used in the Absence of Site-Specific Data 1.109-13 

A-2 Shore-Width Factors for Use in Equations (A-5), (A-6), and (A-7) 1.109-15 

B-l Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 1.109-21 

D-1 Recommended Values for the Transport Times in the Food Distribution System 1.109-32 

E-1 Stable Element Transfer Data 1.109-37 

E-2 Nuclide Transfer Parameters for Goat's Milk... .... 1.109-38 

E-3 Animal Consumption Rates 1.109-38 

E-4 Recommended Values for U To Be Used for the Average Individual in lieu of 

Sittj-Specific Data 77 1.109-39 

E-5 Recommended Values for Uap To Be Used for the Maximum Exposed Individual in 

lieu of Site-Specific Data 1.109-40 

E-6 External Dose Factors for Standing on Contaminated Ground 1.109-41 

E-7 Inhalation Dose Factors for Adults 1.109-44 

E-8 Inhalation Dose Factors for Teenagers 1.109-47 

E-9 Inhalation Dose Factors for Children 1.109-50 

E-10 Inhalation Dose Factors for Infants 1.109-53 

E-ll Ingestion Dose Factors for Adults 1.109-56 

E-12 Ingestion Dose Factors for Teenagers 1.109-59 

E-13 Ingestion Dose Factors for Children 1.109-62 

E-14 Ingestion Oose Factors for Infants 1.109-65 

E-15 Recommended Values for Other Parameters 1.109-68 

LIST OF FIGURES 

Figure Page 

F-l Staff-Written Computer Listing '... 1.109-76 

F-2 Wamawi-Written Cemputsr Listing. 11,111 >II J • i n m : T-.I . ,: •• • JI,J • I • t >••••• •< 1.103*78 

vi 
P.7 

I I 

A. INTRODUCTION 

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 LightWater-Cooled Nuclear Power Reactor Effluents," to 10 CFR Part 50 provides numerical guidance for 

radioactive effluent design objectives and technical specification requirements for limiting 

conditionslof 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 documented. 

Portions of this guide supersede 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 has been withdrawn. 

B. DISCUSSION 

Appendix I to 10 CFR Part 50 provides guidance on the doses to members 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. 

Appendix A of this guide describes suggested models and assumptions for calculating the 

estimated doses to man from discharges to the hydrosphere. Appendix B of this guide describes 

suggested models and assumptions for calculating doses from noble gases discharged to the atmosphere, and Appendix C gives models and assumptions for estimating doses from radioiodines and 

other radionuclides released to the atmosphere. Appendix D describes the models and assumptions 

for calculating population doses (man-rem and man-thyroid-rem) from radionuclide releases to the 

atmosphere and hydrosphere. Appendix E presents tabular data pertaining to two or more of the 

other appendices. Appendix F provides a discussion of, and derivation for, the I function used 

in computing gamma doses from elevated noble gas releases. '' 

In providing guidance for implementing Section II of Appendix I, the NRC staff has made use 

of the maximum exposed individual approach. In this approach the numerical design objectives of 

Section II are compared to the calculated radiation exposures to maximum individuals in each of 

four age groups. 

The population is considered to be made up of infants (0 to 1 year), children (1 to 11 years), 

teenagers (11 to 17 years), and adults (17 years and older). For the purpose of evaluating dose 

commitment, the maximum infant is assumed to be newborn, the maximum child is taken to be 4 years 

old, the maximum teenager is taken to be 14 years old, and the maximum adult 1s taken to be 

17 years old. 

Maximum individuals are characterized as "maximum" with regard to food consumption, occupancy, 

and other usage of the region in the vicinity of the plant site and as such represent Individuals 

with habits representing reasonable deviations from the average for the population in general. 

In all physiological and metabolic respects the maximum exposed individuals are assumed to have 

those characteristics that represent the averages for their corresponding age group in the genera. 

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). When applied to the evaluation of internal deposition of radioactivity, 

the term "dose." as used here, includes the prospective dose component arising from retention 

in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose 

commitment is evaluated over a period of 50 years. 

1.109-1 
P.8 

1 I 

population.. Although specific individuals will almost certainly display dietary, recreational, 

and other living habits considerably different from those suggested here, and actual physiological 

and metabolic parameters may vary considerably, the NRC staff considers the maximum exposed 

individual to be a well-defined reference for implementation of Section II of Appendix I. The 

characterization of maximum exposed individuals is subject to continuing review by the NRC staff, 

and the applicant is encouraged to use information and data applicable to a specific region or 

site when possible. Where site-specific information and data is used, its justification should 

be documented for the NRC staff's review. 

i! 

Since|!the radiation dose commitment per unit intake of a given radionuclide usually varies 

as a function of age, four sets of internal dose conversion factors have been calculated. These 

dose factors are appropriate for the four different age groups defined above. Specifically, 

these doseifactors are based on continuous intake over a one-year environmental exposure period 

and an associated dose commitment extending over a 50-year period from initiation of intake. 

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

selected, they should include the same exposure pathways considered 1n the models described 1n 

this guide. The assumptions and methods used should be fully described and documented. 

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. Such conditions could include 

actual values for agricultural productivity, dietary habits, residence times, dose attenuation 

by structures, measured environmental transport factors (such as bioaccumulation factors), or 

similar values actually determined for a specific site. The applicant should provide enough 

information on the measurements or other methods used to derive these substitute values to 

enable thei NRC staff to evaluate their validity. 

l; 

C. REGULATORY POSITION 

Equations are provided below by which the NRC staff will estimate radiation exposure for 

maximum individuals and the population within 50 miles. These equations are appropriate for the 

exposure pathways that the staff routinely considers in its evaluations. In addition, other 

exposure pathways that may arise due to unique conditions at a specific site should be considered 

if they are likely to provide a significant contribution to the total dose. A pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or 

more than 10 percent of the total from all pathways considered In this guide. 

i' • ' 1. 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, which are described in 

detail in Appendix A of this guide. 

a. Potable Water 

"apj 31100 ^ { Q.D.-1PJ«P<-*lV

 0 ) 

b. Aquatic Foods 

R

apj

 = ll00^| Q

i

B

1p Da1pJexp(-

X

i

t

P

) (2 ) 

Shoreline Deposits 

,ap. = no.ooo H ri . rilp J R - 110,000 "-*££ I Q1TiDa . [exp(-A.t p )][l - exp(-X.tb)] (3) 

1.109-2 
I I 

P.9 

Irrigated Foods 

For all radionuclides except tritium: 

r[l - exp(-AE 1te)] fjB^ l - exp(->..tb)] 

Rapj * "1? \ d1ex<><-Vh>Da1pj V EI Px, 

Y xc . 

v Ei 

PX 

For tritium: 

• .animal, 

'apj "ap "v"apj ap apj R . = Uveg C D . + ^""""'D • F.(C Qc + C, QA ) 

--- ap

 uv apj ap apj Av v'F AwvAw' 

(4) 

(5) 

where 

V 

ip 

iv 

MAw 

Civ 

aipj 

FiA 

*Aw 

Qi 

r 

R . 

apj 

is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed 

as the ratio of the concentration in biota (in pCi/kg) to the radionuclide 

concentration in water (in pCi/liter), in liters/kg; 

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; 

is the concentration of radionuclide i in water consumed by animals, in 

pCi/liter; 

is the concentration of radionuclide i in vegetation, in pCi/kg; 

is the dose factor, specific to a given age group a, radionuclide i, pathway p, 

and organ j, 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 sediment, expressed as a ratio of the dose rate 

(in mrem/hr) and the area1- radionuclide concentration (in pCi/m2); 

2 

is the deposition rate of nuclide i, in pCi/m per hr; 

is the flow rate of the liquid effluent, in ft /sec; 

is the fraction of the year crops are irrigated, dimensionless; 

is the stable element transfer coefficient that 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; 

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), dimensionless; 

2 

is the effective "surface density" for soil, in kg(dry soil)/m ; 

is the consumption rate of contaminated water by an animal, in liters/day; 

is the consumption rate of contaminated feed or forage by an animal, in 

kg/day (wet weight); 

is the release rate of nuclide i, in Ci/yr; 

is the fraction of deposited activity retained on crops, dimensionless; 

is the total annual dose to organ j of individuals of age group a from all 

of the nuclides i in pathway p, in mrem/yr; 

1.109-3 
P.10 

tb is the period of time for which sediment or soil is exposed to the contaminated 

water, in hours; 

t is the time period that crops are exposed to contamination during the growing 

season, in hours; 

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 1, in days; 

t is the average transit time required for nuclides to reach the point of 

p exposure. For internal dose, t is the total time elapsed between release 

of the nuclides and ingestion of food or water, in hours; 

U is a usage factor that specifies the exposure time or intake rate for an 

p Individual of age group a associated with pathway p, in hr/yr, i/yr, or 

kg/yr; 

W is the shoreline width factor, dimensionless; 

2 

Y is the agricultural productivity (yield), in kg(wet weight)/m ; . 

X,-. is the effective removal rate constant for radionuclide i from crops, in hr" , 

where x ^ = x^ + x , x. is the radioactive decay constant, and x is the 

removal rate constant for physical 'oss by weathering (see Appendix E, 

Table E-15); 

X. is the radioactive decay constant of nuclide i, in hr" ; 

1100 is the factor to convert from (Ci/yr)/(ft /sec) to pCi/liter; and 

110,000 is the factor to convert from (C1/yr)/(ft3/sec) to pC1/liter and to account 

for the proportionality constant used in the sediment radioactivity model. 

These equations yield the dose rates to various organs of individuals from the exposure 

pathways!!mentioned above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose 

commitments to the total body or any organ of any individual from the sum of the exposure pathways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, 

respectively. 

2. Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere 

The NRC staff will calculate radiation doses from noble gases using the following equations 

from Appendix B of this guide. Atmospheric dispersion models are found in Regulatory Guide 1.111, 

"Methodsi! for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine 

Releases: from Light-Water-Cooled Reactors." 

a. Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks More Than 

80 Meters HfgF 

260 

where 

Y(r,0)

 "^liVn4

v^] Eki(H

«

u

-

s

«vEk> i <Ai <6> 

A. . is the photon yield for gamma-ray photons in energy group k from the decay 

of radionuclide 1, in photons/disintegration; 0 

D

Y(r,'e) is the annual gamma air dose at a distance r (meters) in the sector at angle 0, 

tn mrad/yr; 

E. is the energy of the kth photon energy group, in MeV/photon; 

1.109-4 
P.11 

I > 

f is the joint frequency of occurrence of stability class s and wind speed 

ns class n for sector 0, dimensionless; 

I(H,u,s,o ,E. ) is the dimensionless numerical integration constant accounting for the 

z 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 £. and is T = T, + kT- as formulated in 

Slade (Appendix B, Reference 1); 

Q . is the release rate of radionuclide i, corrected for decay during transit to 

'm the distance r under wind speed u_, in Ci/yr; 

u is the mean wind speed of wind speed class n, in m/sec; 

_e is the sector width over which atmospheric conditions are averaged, in 

radians; 

u (E. ) is the air energy absorption coefficient for the kth photon energy group, in 

a K , 

m ; and 

260 is the conversion factor to obtain DY(r,e), in mrad/yr, and has the units 

of mrad-radians-m -disintegration/sec-MeV-C1. 

b. Annual Garnna Air Dose from All Other Noble Gas Releases; Annual Beta Air Dose from All 

Noble Gas Releases 

D

Y

(r,8) or DB(r,e) = 3.17 x IO4 \ Q^x/QlV.eMDF} or DF*) (7) 

where 

where 

DF?, DF? are the gamma and beta air dose factors for a uniform semi-infinite cloud of 

3 radionuclide i , in mrad-m /pC1-yr; 

D

Y

(r,e) or 

D (r.a) 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; 

Q. is the release rate of the radionuclide i, in Ci/yr; 

[x/Q] (r.e) is the annual average gaseous dispersion factor (corrected for radioactive 

decay) at the distance r in sector e in sec/m (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 

3.17 x 10 is the number of pCi per Ci divided by the number of seconds per year. 

c. Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than 

80 Meters High 

0

T(r,e) = 1.11 SF I DY(r,0)exp[-Mj(Ek)td] (8) 

D (r,e) is the annual total body dose at the distance r in sector 0, in mrem/yr; 

D^(r,e) is the annual gamma air dose associated with the kth photon energy group at 

the distance r in sector e, in mrad/yr; 

1.109-5 
I I 

Sr is the attenuation factor that accounts for the dose reduction due to 

F shielding provided by residential structures, dimensionless; 

where 

t. is the product of tissue density and depth used to determine a total body 

2 dose, in g/cm ; 

T 2 

u (E. ) is the tissue energy absorption coefficient, in cm /g; and 

ct K 

1.11 is the average ratio of tissue to air energy absorption coefficients. 

d. Annual Skin Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High 

D

s(r,0) = l.HSFD".(r,e) + 3.17 x IO4

 \ Q1[x/Q]D(r.e)DFS1 (9) 

DFS. is the beta skin dose factor for a semi-infinite cloud of radionuclide i, 1 which includes the attenuation by the outer "dead" layer of the skin, in 

3 

mrem-m /pCi-yr; and 

D

s(r,9) is the annual skin dose at the distance r in sector 0, in mrem/yr. 

All other parameters are as defined In preceding paragraphs. 

e. Annual Total Body Dose from All Other Noble Gas Releases 

'ol(r.e) = SF I xi(r,0)DFBi (10) 

where ^ 

DFB. is the total body dose factor for a semi-infinite cloud of the radionuclide i, 

i 2 3 

which includes the attenuation of 5 g/cm of tissue, in mrem-m /pCi-yr; 

D^fr.o) is the annual total body dose due to immersion in a semi-Infinite cloud at 

the distance r in sector 0, in mrem/yr; and 

x.('r

1 ,0) is the annual average ground-level concentration of radionuclide i at the 

 3 

distance r in sector e, in pCi/m . 

All other parameters are as defined above. 

f. Annual Skin Dose from All Other Noble Gas Releases 

0

S

Jr,Q) = 1.11 SF I Xi(r,0)DFY + \ Xl(r,0)DFS. (11) 

where 

• D*(r,0) is the annual skin dose due to immersion in a semi-infinite cloud at the 

distance r in sector 0, in mrem/yr. 

All other parameters are as defined above. 

3. Doses1,from Radioiodines and Other Radionuclides* Released to the Atmosphere 

The NRC staff will calculate radiation doses from radioiodines and other radionuclides 

released to the atmosphere using the following equations from Appendix C of this guide. 

* 

Not including noble gases. 

1.109-6 
P.13 

' > l i 

a. Annual Organ Dose from External Irradiation from Radionuclides Deposited onto the 

Ground Surface 

D

G 

where 

J(,r,e) = 8760 SF I C^r.ojDFG^ (12) 

p 

C(r,0) is the ground plane concentration of radionuclide i at distance r in 

2 

sector 8, in pCi/m ; 

DFG.. is the open field ground plane dose conversion factor for organ j from radioij 2 

nuclide i, in mrem-m /pCi-hr; 

p 

D.(r,o) is the annual dose to the organ j at location (r,o), in mrem/yr; 

J 

Sp is a shielding factor that accounts for the dose reduction due to shielding 

provided by residential structures during occupancy, dimensionless; and 

8760 is the number of hours in a year, 

b. Annual Organ Dose from Inhalation of Radionuclides 1n Air 

where 

Dja(r.e) = Ra I Xi(r,0)DFAi ja (13) 

A 

D. (r,0) is the annual dose to organ j of an individual in the age group a at location 

J

/ (r,e) due to inhalation, in mrem/yr; 

\ DFAj . is the inhalation dose factor for radionuclide i, organ j, and age group a, 

J in mrem/pCi; 

3 

R. is the annual air intake for individuals in the age group a, in m /yr; and 

a 

x,-(r,e) is the annual average concentration of radionuclide i in air at location 

3 

(r,0), in pCi/m . 

c. Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food 

D°a(r,o) - I OFIija[ua

vfgC^(r,0) • l£cm(r,o) • ujcf(r.e) + UflLf.c'r(r.o)] (14) 

where 

C*(r,e). Cm(r,0), 

C-(r,0), C.(r,G) are the concentrations of radionuclide i in produce (non-leafy-vegetables, 

v ' " v fruits, and grains), milk, leafy vegetables, and meat, respectively, at 

location (r, 0) , in pCi/kg or pCi/n; 

D. (r,o) is the annual dose to the organ j of an individual in age group a from 

J a ingestion of produce, milk, leafy vegetables, and meat at location (r,0), in 

mrem/yr; 

DFI. - is the ingestion dose factor for radionuclide i, organ j, and age group a, 

1ja in mrem/pCi; 

f ,f are the respective fractions of the ingestion rates of produce and leafy 

9 vegetables that are produced in the garden of interest; and 

u_» UT> u_> u_ are the annual intake (usage) of produce, milk, meat, and 1-eafy vegetables, 

a' -a' "a" "a respectively, for individuals in the age group a, in kg/yr or 5,/yr (equivalent 

t 0V1.109-7 
P.14 

4. Integrated Doses to the Population 

The NRC staff will calculate integrated doses to the local population from all pathways 

discussedi'in Sections Cl , 2, and 3. Because of the various conditions under which the equations 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 the numerical 

guides for design objectives of Appendix I is presented 1n Table 1. Methods of evaluating 

compliance with the cost-benefit provisions of Appendix I are addressed in Regulatory Guide 1.110, 

"Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors." 

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. 

1.109-8 
TABLE 1 

SUMMARY OF STAFF POSITION -

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I 

o 

vO 

TYPE OF DOSE 

Liquid Effluents 

Dose to total body 

from all pathways 

Dose to any organ 

from all pathways 

Non-tritium releases 

Gaseous Effluents*** 

Gamma dose in air 

Beta dose in air 

Dose to total body 

of an individual 

Dose to skin of an 

individual 

APPENDIX I* 

DESIGN OBJECTIVES 

3 mrem/yr per unit 

10 mrem/yr per unit 

10 mrad/yr per unit 

20 mrad/yr per unit 

5 mrem/yr per unit 

15 mrem/yr per unit 

RM-50-2 

DESIGN OBJECTIVES* 

5 mrem/yr per site 

5 mrem/yr per site 

5 Ci/yr per unit 

10 mrad/yr per site 

20 mrad/yr per site 

5 mrem/yr per site 

15 mrem/yr per site 

POINT OF DOSE 

EVALUATION 

EQUATIONS 

TO BE USED 

Location of the 1, 2, 3, 4, & 5 

highest dose offsite.** 

Same as above. 1, 2, 3, 4, & 5 

Location of the 6 or 7, as 

highest dose offsite. appropriate 

Same as above. 7 

Location of the 

highest dose 

offsite.** 

Same as above. 

8 or 10, as 

appropriate 

9 or 11, as 

appropriate 

See footnotes at end of table, on following page. 
TABLE 1 (Continued) 

SUMMARY OF STAFF POSITION 

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I 

_. 

o 

IO 

TYPE OF DOSE 

Radioiodines and Particula 

Dose to any organ 

from all pathways 

I-l31 releases 

* 

Evaluated for a maximum 

APPENDIX I* RM-50-2 

DESIGN OBJECTIVES DESIGN OBJECTIVES* 

tes Released to the Atmosphere 

15 mrem/yr per unit 15 mrem/yr per site 

- - - - 1 Ci/yr per unit 

individual, as described in Section B of this guide. 

POINT OF DOSE 

EVALUATION 

Location of the 

highest dose 

offsite. 

EQUATIONS 

TO BE USED 

12, 13, & 14 

Evaluated at a location that ts 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. 

+ Evaluated at a location where an exposure pathway and dose receptor actually exist at the time of licensing. However, 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: 

(1) 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 in foods 

involved in the changes, if and when they occur. 
P.17 

t . 

APPENDIX A 

METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS 

The equations for estimating radiation exposure to man from four principal exposure pathways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated 

foods) are listed in Section C, "Regulatory Position," of this guide. 

1. Generalized Equation for Calculating Radiation Dose via Liquid Pathways 

Equation (A-1.) is the generalized equation for calculating the radiation dose to man via 

liquid effluent pathways. 

where 

Raipj = SpVaip j (A1} 

C. is the concentration of nuclide i in the media of pathway p, in pC1/a, 

TP 2 

pCi/kg, or pCi/m ; 

D 'oi is the dose factor, specific to age group a, radionuclide i, pathway p, 

PJ and organ j. It represents the dose due to the intake of a radionuclide, 

in mrem/pCi, or from exposure to a given concentration of a radionuclide in 

2 sediment, in mrem per hr/pCi per m _ 

R . . is the annual dose to organ j of an individual of age group a from nuclide i 

PJ via pathway p, in mrem/yr; and 

U is the exposure time or intake rate (usage) associated with pathway p for 

p age group a, in hr/yr, z/yr 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 WASH-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. Radionuclide Concentration in Environmental Media (C. ) 

The concentrations in environmental media of interest can be estimated from the mixing 

ratio M , the discharge flow F, the radionuclide release rate Q^, and other terms presented in 

the pathway equations that appear later in this discussion. 

b. Usaae (ua p) 

The second term of Equation (A-1) is the usage term U Usage is expressea as a 

ap 

consumption rate iri kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the 

pathway and age group under consideration. 

The NRC staff encourages the use of site-specific data, whenever possible.. Such data 

should be documented. In the absence of site-specific data, however, the usage values (consumption 

rates and exposure times) presented in Appendix E, Table E-5, are recommended. 

c. Dose Factor (Dajpj) 

Dose factors for internal exposure via ingestion are provided in Appendix E, Tables E-ll, 

12, 13, and 14. Appendix E also provides further discussion of the data, models, and assumptions 

used. . 

Material deposited from sedimentation in an aquatic system represents a fairly large, 

nearly uniform thin sheet of contamination. The factors for converting surface contamination 

given in pCi/m to the dose rate at one meter above a uniformly contaminated plane have- been 

described by Soldat and others (Refs. 3 and 4). Dose factors for exposure to soil sediment have 

I in Appen 

1.109-11 

2 units of mrem/hr per pCi/m and are presented in Appendix E, Table E-6. 
P.18 

i t • 

2. Equations for Liquid Pathways 

This section develops the equations required for the liquid pathway models. The principal 

difference!!between 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: 

w^^ivw^-w

 (A

-

2) 

Symbols for this equation were defined earlier, in Section C l 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 expression (1100 Q.M /F)exp(-X.t ) yields 

the concentration of nuclide i at the time the water is consumed, in pC1/i. This concentration 

is the term C. in Equation (A-1). As a minimum, the transit time t may be set equal to 12 

hours to allow for radionuclide transport through the water purification plant and the water 

distribution system (Ref. 5). 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 fjpr radionuclide removal by water purification processes using techniques such as those 

outlined ih Reference 3. 

if 

It should be noted that, depending on the hydrological dispersion model employed, the 

mixing ratio, M , 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 effiluent concentration) may be supplied as a function of the radiological decay constant, 

with any potential effluent recycling taken into account. Suggested hydrological dispersion 

models arej presented in Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from 

Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I." 

b. [Aquatic Foods 

The concentrations of radionuclides in aquatic foods are assumed to be directly.related 

to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations, 

called bioaccumulation factors in this guide, can be found in the literature (Ref. 6) . The 

inclusion of the bioaccumulation factor B. in Equation (A-2) yields Equation (A-3), which is 

suitable for calculating the internal dose from consumption of aquatic foods. 

Rapj = 1100^ApiBiPDaipjexP^lV (A'3) 

Values of B- are given in Table A-1; the other parameters have been previously defined. The 

ji <P 

methodology presented in Reference 7 for the development of site-specific freshwater bioaccumulation factors is considered to be acceptable by the NRC staff. 

The transit time t 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 

•* 

Here, and in a number of other instances, the NRC staff has found it necessary to set forth 

guidance!as to a parameter value in the absence of empirical data. In such instances judgments 

have been made after considering values assumed by others and model sensitivity to the parameter 

value in question. In this particular instance, the total body dose from fish ingestion, for a 

typical situation, was found to vary by less than a factor of two for a range of environmental 

transit times of from one to seven days. 

1.109-12 
z 

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P.20 

suspended and deposited materials. One method of approaching this problem was presented 1n the 

Year 2000; Study (Ref. 3). Based on this model, an estimate of the radionuclide concentration in 

shoreline;sediments can be obtained from the following expression: 

;, C. [1 - exp(-x.t.)] 

'is^c^*—T. ~ <A"

4> 

where 

C. is the concentration of nuclide i in sediment, in pCi/kg; 

; C. is the concentration of nuclide i in water adjacent to the sediment, in 1W pCi/liter; 

K is an assumed transfer constant from water to sediment, in 11ters/kg per hr; 

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 

X. is the decay constant* of nuclide i, in hours" . In the original evaluation 

of the equation, x. was chosen to be the radiological decay constant. The 

true value should include an as yet unknown "environmental" removal constant. 

The value of K 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 Richland, 

Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth 

(Refs. 9 and 10). Since the primary use of the equation is tb facilitate estimates of the 

exposure rate from gamma emitters one meter above the sediment, an effective surface contamination was estimated. This surface contamination was assumed to be contained within the top 2.5 

2 cm (1 in.) of sediment (with a mass of 40 kg/m of surface). The dose contribution from the 

radionuclides at depths below 2.5 cm was ignored. The resulting equation is 

Si = lOOT^^W.l - exp(-Xitb)] (A-5) 

where 

2 

S. is the "effective" surface contamination, in pCi/m , that is used in 

subsequent calculations; 

T. is the radiological half-life of nuclide i, in days; 

W is a shore-width factor that describes the geometry of the exposure; and 

100 is equal to [KcU/kg-hr)*40(kg/m2)* 24(hr/day)/0.693], in */m2-day. 

Shore-width factors were derived from experimental data (Ref. 11) and are summarized in 

Table A-2. 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-1) leads to 

Equation (A-6) below for calculation of radiation dose from exposure to shoreline sediments. 

Rapj = Uap I SiDaipj = 10 ° U a pH

 I SwVaipjt 1 " "P^i ^ <*-«> 

As in the development of Equation (A-2), the expression (1100 Q^ M /F)exp(-Xjt ) may be substituted 

for C. . This results in the following relationship: 

Rapj " 110'°00 -*P- I ViOaipj^-Vp^1 " ^(-x^)] (A-7) 

* T 

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). 

1.109-14 
P.21 

TABLE A-2 

SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5), (A-6), AND (A-7) 

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 

d. Dose from Foods Grown on Land with Contaminated Water 

The equations in the following paragraphs can be used to calculate doses from radionuclides released in liquid effluents but appearing in crops or animal products. Separate 

expressions are presented fbr 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 

model 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. 3). 

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 C. of radionuclide i in the edible portion of crop 

species v, in units of pCi/kg, is given by: 

"r[l - exp(-x£ite)] frB1v[1 - exp(-x1tb)] 

C = d. iv i 

Vv*E1 PXi 

expf-x^ ) (A-8) 

where the terms are defined in Section C, "Regulatory Position." Appendix E, Table E-15, presents 

suggested values for the parameters r, Y , t , P, and t. . Values for B.y are in Table E-1. 

The deppsition rate, d., from irrigated water is defined by the relation 

d. = C. I (water deposition) (A-9) 

where 

C. is the concentration of radionuclide i in water used for irrigation, in 

1W pCi/liter, and 

2 

I is the average irrigation rate, in liters/m /hr, during the growing season. 

For a cow grazing on fresh forage, t 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 

(Refs. 3 and 12). 

For tritium, the equation for estimating C, is (see Ref. 13): 

Cv = Cw (A-10) 

1.109-15 
.(2) Animal Products 

The radionuclide concentration in an animal product such as meat or milk 1s 

dependenton the amount of contaminated feed or forage eaten by the animal and its intake of 

contaminated water. The radionuclide concentration in animal products C . in terms of pC1/liter 

or pCi/kgiis proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w) : 

• . i *> 

C

i A ' F 1A£ C 1F<> F

 + CiAw<W (A-ll) 

The second set of terms in the brackets in Equation (A-ll) can be omitted if the 

animal does not drink contaminated water. Values for Qr and Q. are presented in Appendix E, 

Table E-3. Values for B. and F.. are given in Appendix E, Table E-1.* 

(3) Total Dose from Food Grown on Land 

is given by: 

R = „»eg 

The total dose R . from irrigated foods and animal products (excluding tritium) 

. U ¥ C 9 7 C D . . + U anima 1 7 C,AD . 

apj ap < ""iv aipj ap 4 ''iA ai PJ (A-12) 

If values for C- from Equation (A-8) and C.. from Equation (A-ll) are substituted 

in Equation (A-12): 

Rapj " C I d1exp(-Ait:h)Oa1pJ 

r[l - exp(-xE-te)] fjB.v[l - exp(-><tb)] 

Y xc... 

v Ei n. 

^ar^piA^ipj^i^^i^h) 

r[l - exp(-xE.te)] 

Yv*E1 

^ Bi v [l - exp(-xitb)] 

Pxi 

+ CiAwQAw| 

(A-13) 

where the terms are defined in Section C, "Regulatory Position." 

It should be noted that the two components of Equation (A-12) imply that contributions from the individual vegetable and animal products have already been summed. In actual 

use, it wiill be necessary to compute separately the milk and meat portions of the dose due to 

animal products (also applicable to Equation (A-16)). 

For tritium, the concentration in animal products (milk or meat) is given by the 

following equation: 

CA = W F + SwV (A-14) 

where the terms are defined in Section C, "Regulatory Position." 

Since by Equation (ArlO) C '= C , and since for all practical purposes CA w = Cw, 

Equation (A-14) can be restated as follows: 

CA = FACW^F + <W (A-15) 

Values for F.„ appear as F and F, in Table E-1. iA m t 

1.109-16 
P.23 

Similarly, the above equations for tritium concentration can be combined with the 

general Equation (A-1): 

R . = UvegC D • + Uanima1C.D • apj ap v apj ap A apj (A-16) 

1.109-17 
P.24 

REFERENCES FOR APPENDIX A 

1. "Final Environmental Statement Concerning Proposed Rule Making Action: Numerical 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 Environmental Radiation 

Doses," USAEC Report BNWL-1754, Pacific Northwest Laboratories, February 1974. 

3. J. F. Fletcher and W. L. Dotson (compilers), "HERMES - A Digital Computer Code for 

Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Report 

HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971. 

o 

4. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (uC1/m ), " Item 04.3.4 

in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, 

Hanford Laboratories, 1962. 

5. D. H. Denham and J. K. Soldat, "A Study of Selected Parameters Affecting the Radiation Dose 

from^Radionuclides in Drinking Water Downstream of the Hanford Project," Health Physics, 

Vol. 28, pp. 139-144, February 1975. 

6. 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. 

7. H. A; Vanderploeg et al., "Bioaccumulation Factors for Radionuclides 1n Freshwater Biota," 

ORNL45002, Oak Ridge, Tenn., November 1975. 

8. G. G. Kilaugh and L. R. McKay, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," ORNL-4992, Oak Ridge National Laboratory, Oak Ridge, 

Tenn.i, March 1976. 

9. J. L. Nelson, "Distribution of Sediments and Associated Radionuclides 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. 

10. 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. 

11. "Handbook of Radiological Protection, Part I: Data," prepared by a panel of the Radioactivity 

Advisory Committee (H. J. Dunster, Chairman), Department of Employment, Department of Health 

and Social Security, Ministry of Health and Social Services, Northern Ireland, Number 

SNB 11-360079-8, Her Majesty's Stationery Office, London, England, 1971. 

12. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy 

Cows," USAEC Report UCRL-12479, 1965. 

13. 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. 

1.109-18 
P.25 

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 noble gases 

discharged to the atmosphere. 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 immersion in a semi-infinite cloud. 

1. Annual Gamma Air Dose* from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters H I _ r _ , 

Slade (Ref. 1) describes a derivation of equations for estimating annual air doses from 

photon emitters dispersed in the atmosphere. The following expression can be used for calculating 

annual doses: 

DY<r'8> " !& . I F. \ f

n I ua(Ek)EkKH.u...o2.Ek) J Qj ^ (B-l) 

Symbols for this equation were defined earlier, in Regulatory Position C.2.a"bf this guide. 

A discussion of, and derivation for, the I function are presented in Appendix F of this guide. 

The photons are combined into energy groups, and each photon intensity within a group is 

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, 

A.., is determined to be 

Aki = I CAmWEm»/[EkPa(Ek)] (B-2) 

m 

where 

A is the fraction of the disintegrations of nuclide i yielding photons 

of energy E ; 

E 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 

Qj., = Qi exp(-\.r/xin) (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 component of the air dose. 

1.109-19 
i \ 

where 

Q.j is the initial release rate of nuclide i, In Ci/yr ; 

r is the distance from the source to the receptor, in m; and 

x. Is the decay constant of nuclide i, 1n sec . 

All other parameters are as previously defined. 

2. Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta Air Dose* from All 

Noble Gas Releases 

Plumes of gaseous effluents are considered semi-infinite in the case of ground-level noble 

gas releases. The annual average ground-level concentration of radionuclide i at location (r,e) 

1s determined from 

Xf.r.e) - 3.17 x 104Q.[x/QJ°(r,9) (B-4) 

where 

Xi(i",e) is the annual average ground-le>'el concentration of nuclide i at the, 

distance r in the sector at anqie 8 from the release point, in pCi/m , and 

[x/Q] (r.e) is the annual average gaseous Mipersion factor (corrected for radioactive 

decay) in the sector at angle < it the distance r from the release point, 

in sec/m . (See Regulatory Gu' u 1.111 for atmospheric dispersion models.) 

All other parameters are as previously defined. 

The associated annual gamma or beta air dose is then 

D

Y(r,e) or DS(r,e) = [ Xi(r,e)(DF} or DF*) (B-5) 

where the terms are as defined in Regulatory Position C.2.b. 

Table B-l presents a tabulation of the dose factors for the noble gases of interest. 

3. Annual Total Body and Skin Doses 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 

2 

and the skin dose at a depth of 7 mg/cm of tissue (Ref. 4).* * 

a. Releases from Free-Standing Stacks More Than 80 Meters High 

The annual total body dose is computed as follows: 

D

T(r,6) = 1.11 x SF [ DY(r,9)exp[-uJ(Ek)td] (B-6) 

The term "beta air dose" refers to the component of the air dose associated with particle 

emissions during nuclear and atomic transformations, i.e., s+, B-, and conversion electrons. 

** 

See discussion in Appendix E, Section 3. 

1.109-20 
P.27 

f i 

TABLE B-l 

DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES 

Nuclide 

Kr-83m 

Kr-85m 

Kr-85 

Kr-87 

Kr-88 

Kr-89 

Kr-90 

Xe-131m 

Xe-133m 

Xe-133 

Xe-135m 

Xe-135. 

Xe-137 

Xe-138 

Ar-41 

* 3 mrad-m 

pCi-yr 

** 3 mrem-m 

pCi-yr 

*** 

B-air*(DFj) 

* ** 

2.88E-04 

1.97E-03 

1.95E-03 

1.03E-02 

2.93E-03 

1.06E-02 

7.83E-03 

1 .11E-03 

1 .48E-03 

1.05E-03 

7.39E-04 

2.46E-03 

1.27E-02 

4.75E-03 

3.28E-53 

. 

-4 

B-Skin**(DFS.) 

1.46E-03 

1.34E-03 

9.73E-03 

2.37E-03 

1.01E-02 

7.29E-03 

4.76E-04 

9.94E-04 

3.06E-04 

7.11E-04 

1.86E-03 

1.22E-02 

4.13E-03 

2.69E-03 

Y -A1r*(DF|) 

1.93E-05 

1.23E-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 

1.92E-03 

1.51E-03 

9.21E-03 

9.30E-03 

Y -Body**(DFB.) 

7.56E-08 

1.17E-03 

1.61E-05 

5.92E-03 

1.47E-02 

1 . 66E-02 

1.56E-02 

9.15E-05 

2.51E-04 

2.94E-04 

3.12E-03 

1.81E-03 

1.42E-03 

8.83E-03 

8.84E-03 

2.88E-04 = 2.88 x 10" 

1.109-21 
P.28 

Symbols for this equation are defined in Regulatory Position C.2.c of this guide. The 

factor Sp accounts for the dose reduction provided by the shielding effect of typical residential 

structures (see Appendix E, Section 4 and Table E-15). 

The skin dose has two components, the gamma and beta contributions. The skin dose 

rate is computed by 

|Ds(r,0) = 1.11 x SFD

Y(r,o) + 3.17 x IO4

 \ Qi[x/Q]D(r,0)DFS. (B-7) ,4 

1 

SSymbols for this equation are defined in-Regulatory Position C.2.d of this guide. 

The skin beta dose factors DFS were determined using the decay scheme source documents 

cited above and the methods used in References 5, 6, and 7. They are presented in Table B-l. 

b. All Other Releases 

The annual total body dose is computed as follows: 

D I (r »e ) ° S F . X1(r,e)DFB1 (B-8) 

Symbols for this equation are defined in Regulatory Position C.2.e of this guide. 

The annual skin dose is computed as follows: 

to*(r.e) = 1.11 x SF £ X,(r,e)DF} • J Xi(r,e)DFS. (B-9) 

Symbols for this equation are defined in Regulatory Position C.2.f of this guide. 

I v 

1.109-22 
P.29 

'" > -' k 

REFERENCES FOR APPENDIX B 

1. "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," NEDO12037, 1970. 

4. J. K. Soldat et al., "The Dosimetry of the Radioactive Noble Gases," The Noble Gases 

(A. A. Moghissi and R. E. Stanley, eds.), ERDA-CONF 730 915, U.S. Energy Research and 

Development Administration, 1975. 

5. R. Loevinger et al., in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.), Academic 

Press, New York, 1956. 

6. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR 

73-107, 1973. 

7. M. J. Berger, "Beta-Ray Dose in Tissue - Equivalent Material Immersed 1n a Radioactive 

Cloud," Health Physics, Vol. 26, pp. 1-12, January 1974. 

1.109-23 
i '. 

APPENDIX C 

MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS 

FROM RADIOIODINES AND OTHER RADIONUCLIDES* 

DISCHARGED TO THE ATMOSPHERE 

1. Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane 

The ground plane concentration of radionuclide i at the location (r,e) with respect to the 

release point may be determined by 

' [1.0 x IO1 2 ] [6Y(r,e) Q J 

cj(r.e) = - * *- [1 - exp(-x.tb)] (C-l) 

where 

r* 

C"(r,e) is the ground plane concentration of the radionuclide i in the sector at 

2 angle e at the distance r from the release point, in pCi/m ; 

Qi is the annual release rate of nuclide i to the atmosphere, in Ci/yr; 

tb is the time period over which the accumulation is evaluated, which is 15 

years (mid-point of plant operating life). This is a simplified method of 

approximating the average deposition over the operating lifetime of the 

facility; 

6ij(r,6) is the annual average relative deposition of effluent species i at location 

-2 (r,e), considering depletion of the plume during transport, in m ; 

x. is the radiological decay constant for nuclide i, in yr" ; and 

12 1.0 x 10 is the number of pCi per Ci. 

The annual dose resulting from direct exposure to the contaminated ground plane, from all 

radionuclides, is then 

D

G(r,9) = 8760 Sp J C^r.ejDFG^ (C-2) 

where the terms are defined in Regulatory Position C.3.a of this guide. 

Values for the open field ground plane dose conversion factors for the skin and total body 

are given in Appendix E, Table E-6. The annual dose to all other organs is taken to be equivalent 

to the total body dose. The factor Sp is assumed to have a value of 0.7, dimensionless. 

Does not include noble gases. 

1.109-24 
P.31 

./ . 

2. Annual Dose from Inhalation of Radionuclides in Air 

The annual average airborne concentration of radionuclide i at the location (r,e) with respect to the release point may be determined as 

X i (r,e) = 3.17 x 104Q.[x/Q]D(r,e) (C-3) 

where 

Qi is the release rate of nuclide i to the atmosphere, in Ci/yr; 

x.(r,e 1 ) is the annual average ground-level concentration of nuclide i in air in 

 3 

sector 9 at distance r, in pCi/m ; 

D 3 

[x/Q] (r.e) is the annual average atmosphere dispersion factor, in sec/m (see Regulatory 

Guide 1.111). This includes depletion (for radioiodines and particulates) 

and radioactive decay of the plume; and 

4 

3.17 x 10 is the number of pCi/Ci divided by the number of sec/yr. 

The annual dose associated with inhalation of all radionuclides, to organ j of an individual 

in age group a, is then 

D j a ( r 'e ) " Ra lxi(r,e)DFA.ja (C-4) 

Values for DFA.. are given in Appendix E, Tables E-7 through E-10; values for R. are given 

I ja a 

in Appendix E, Table E-5. All other symbols are as defined earlier in Regulatory Position C.3.b. 

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 similar to the 

model developed for estimating the transfer of radionuclides from irrigation water given in 

Appendix A of this guide. 

a. Parameters for Calculating Nuclide Concentrations in Forage, Produce, and Leafy Vegetables 

For all radioiodines and particulate radionuclides, except tritium and carbon-14, the 

concentration of nuclide i in and on vegetation at the location (r.e) is estimated using 

C*(r,e) = d^V.e) 

r[l - exp(-xE.t )] B. [1 - exp(-x.tb)] 

v v x E .

 El e + ^-w. —h xp(

-

A

i V

 (c

-

5) 

See Regulatory Position C l of this guide for definitions of terms. Values for the 

parameters r, t , Y , P, and th are provided in Appendix E, Table E-15. For the parameters t , 

Yu , and t., different values are given (in Appendix E) to allow the use of Equation (C-5) for 

different purposes: estimating concentrations in produce consumed by man; in leafy vegetables 

consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or 

goats; and iri forage consumed as stored feed by dairy cows, beef cattle, or goats. 

1.109-25 
I \, 

The deposition rate from the plume is defined by 

d.(r,e) = 1.1 x l0851(r,e)Q1 (C-6) 

where 

d.(r,e) is the deposition rate of radionuclide i onto ground at location (r,9), in 

1 2 

pCi/m -hr; 

6-(r,e) is the relative deposition of radionuclide i, considering depletion and 

-2 decay in transit to location (r,e), in m (see Regulatory Guide 1.111); and 

8 12 

1.1 x 10 is the number of pCi per Ci (10 ) 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 

emissionsjlmay be considered nonelemental (Ref. 1). With this consideration included, 

Equation (C-6) for radioiodine becomes 

d^r.e) = 5.5 x l07«1(r,e)Q1 (C-7) 

where Qi is the total (elemental and nonelemental) radioiodine emission rate. The retention 

factor r for elemental radioiodine on vegetation should be taken as unity, since the-"experimental 

measurements (Refs. 1, 2, and 3) used to evaluate this transfer mechanism consisted of direct 

comparison of the gross radioiodine concentration on vegetation and the concentration in air 

(Refs. 4 and 5). 

For radioiodines, the deposition.model is based only on the dry deposition process. Wet 

deposition', including "washout" of the organic and nonorganic iodine fractions, should be considered 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-5)) 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 (Refs. 6 

and 7). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as 

particulates. 

Carbbn-14 is assumed to be released in oxide form (CO or CO-). The concentration of carbon-14 

in vegetation is calculated by assuming that its ratio to the natural carbon in vegetation is the 

same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see 

Refs. 8 and 9). Also, in the case of intermittent releases, such as from gaseous waste decay 

tanks, the parameter p is employed to account for the fractional equilibrium ratio achieved. The 

parameter p is defined as the ratio of the total annual release time (for C-14 atmospheric releases) 

to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the 

condition! that the value of p should never exceed unity. For continuous C-14 releases., p is taken 

to be unity. These considerations yield the following relationship: 

C*4(r,9) = 3.17 x 107pQ14[x/Q](r,9). 0.11/0.16 

= 2.2 x 107pQu[ x /Q](r,9) (C-8) 

where 

C,_(r,9) is the concentration of carbon-14 in vegetation grown at location (r.g), in 

pCi/kg; 

Q,. is the annual release rate of carbon-14, in Ci/yr; 

p is the fractional equilibrium ratio, dimensionless; 

0.11 is the fraction of total plant mass that is natural carbon, dimensionless; 

1.109-26 
3 

0.16 is equal to the concentration of natural carbon in the atmosphere, in g/m ; 

and 

3.17 x 107 is equal to (1.0 x 1012pCi/Ci)(1.0 x IO3 g/kg)/(3.15 x 107sec/yr). 

The concentration of tritium in vegetation is calculated from its concentration in the air 

surrounding the vegetation. Using the method described in Reference 10, the NRC staff derived 

the following equation: 

C*(r,e) = 3.17 x 107QT[x/Q](r,9)(0.75)(0.5/H) 

= 1.2 x 10;QT[x/Q](r.9)/H (C-9) 

where 

C»(r,9) is the concentration of tritium in vegetation grown at location (r,e), in 

1 pCi/kg; 

H is the absolute humidity of the atmosphere at location (r,9), in g/m ; 

Q, is the annual release rate of tritium, in Ci/yjr; 

0.5 is the ratio of tritium concentration in plant water to tritium concentration 

in atmospheric water, dimensionless; and 

0.75 is the fraction of total plant mass that is water, dimensionless. 

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 

as 

where 

where 

C

m(r,9) = FmC^(r,9)QF exp(-X.tf) (C-10) 

C

1?(r,e) is the concentration in milk of nuclide i, in pCi/liter; 

C^(r,9) is the concentration of radionuclide i in the animal's feed, in pCi/kg; 

F is the average fraction of the animal's daily intake of radionuclide i which 

m appears in each liter of milk, in days/liter (see Appendix E, Tables E-1 

and E-2 for cow and goat data, respectively; for nuclides not listed in 

Table E-2, use the values in Table E-1); 

Qp 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 milk 

and to the receptor (a value of 2 days is assumed); and 

xi is the radiological decay constant of nuclide i, in days" . 

The concentration of radionuclide i in the animal's feed is estimated as 

Cj.r.e) = fpfscj(r.9) + (1 - fp)cj(r,e) + fp(l - fs)c}(r,e) (C-ll) 

P C(r,e) is the concentration of radionuclide i on pasture grass (calculated using 

1 Equation (C-5) with th =0), in pCi/kg; 

C-(r,9) is the concentration of radionuclide i in stored feeds (calculated using 

Equation (C-5) with t.=90 days), in pCi/kg; 

1.109-27 
f is the fraction of the year that animals graze on pasture; and 

f is the fraction of daily feed that is pasture grass when the animal grazes 

on pasture. 

I: 

The values of the parameters t. , t , Y , and t, that will be employed in evaluating 

the milk pathway, unless site-specific data is supplied, are provided in Appendix E, Table E-15. 

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 concentration in meat is estimated as 

cj(r.e) = FfC^(r,9)QF exp(-x.ts) (C-12) 

where 

C,(r,g) is the concentration of nuclide i in animal flesh, in pCi/kg; 

» 

F, is the fraction of the animal's daily intake of nuclide i which appears in 

each kilogram of flesh, in days/kg (see Appendix E, Table E-1 for values); and 

t is the average time from slaughter to consumption (see Appendix E, Table E-15). 

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 to organ j of an individual in age group a resulting from ingestion of all 

radionuclides in produce, milk,-meat, and leafy vegetables is given by 

D°a(r,e) = I DFIi j a [U^fgC^r.e) + UmC*(r,e) + UFC

F(r,9) + U^cjtr.e)] (C-13) 

where 

D- (r.e) is the annual dose to organ j of an individual in age group a from dietary 

Ja intake of atmospherically released radionuclides, in mrem/yr; 

DFI.. is the dose conversion factor for the ingestion of nuclide i, organ j, and 

J age group a, in mrem/pCi (from Tables E-ll through E-14 of Appendix E of 

this guide); and 

U

v, Um, U , U^ are the ingestion rates of produce (non-leafy vegetables, fruit, and grains), 

a milk, meat, and leafy vegetables, respectively, for individuals in age 

group a (from Table E-5 of Appendix E of this guide). 

All the other symbols are as previously defined. Values of f and f to be assumed in the absence 

of site-specific information are given in Table E-15 of Appendix E as 0.76 and 1.0, respectively. 

1.109-28 
P.35 

•' \ 

REFERENCES FOR APP.N'DIX C 

1. B. H. Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk Around 

Three Operating Reactor Sites," NUREG-75/021, U.S. Nuclear Regulatory Commission, 

Washington, D.C , March 1975. 

2. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two," 

USAEC Report IDO-12063, January 1968. 

3. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the 

National Reactor Testing Station, Progress Report Number Four," USAEC Report IDO-12065, 

December 1968. 

131 

4. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of I 

in Milk and the Subsequent Dose to the Thyroid," Institute ftir Reaktorsicherheit, Cologne, 

West Germany, IRS-W-6, June 1973. 

5. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport 

of

 131 I from Air to Milk," Institute fur Reaktorsicherheit, IRS-W-13, April 1975. 

137 

6. C. A. Pelletier and P. G. Voilleque, "The Behavior of Cs and Other Fallout Radionuclides 

on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971. 

7. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consumption 

n7 u 144 144 

of Cow's Milk as Critical Pathways for ° Cs,

 3 Mn and Co- Pr Released to the 

Atmosphere," Health Phys., Vol. 27, p. 189, 1974. 

8. Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear 

Devices, IV Handbook for Estimating the Maximum Internal Dose from Radionuclides Released 

to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968. 

9. R. C. Weast (ed.), "Handbook of Chemistry and Physics,".CRC Press, Cleveland, Ohio, 1970. 

10. L. R. Anspaugh et al., "The Dose to Man via the Food-Chain Transfer Resulting from Exposure 

to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1, 1972. 

1.109-29 
t v ^ ' 

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 0, Section II 

of Appendix I to 10 CFR Part 50. 

Forjjthe 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 appropriate 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 considered to be exposed to the average radionuclide concentrations estimated for the subregion, 

the annual population-integrated dose is calculated as follows: 

D- = 0.001 I Pd I 0.d.fd. (D-1) 

d a 

where 

D- . is the annual dose to organ j (total body or thyroid) of an average 

J individual of age group a in subregion d, in mrem/yr; 

p 

D- is the annual population-integrated dose to organ j (total body or thyroid), 

J in man-rems or thyroid man-rems; 

fd is the fraction of the population in subregion d that is in age group a; 

P. is the population associated with subregion d; and 

0.001 is the conversion factor from mrem to rem. 

The annual dose to the total body or thyroid of an average individual should be evaluated 

with the usage factors of Table E-4 of Appendix E. Models and equations for the detailed dose 

calculations are presented in Appendices A, B, and C of this guide. The annual populationintegrated doses from ingestion of potable water, inhalation of airborne effluents, and external 

exposure! to airborne or deposited radionuclides should be evaluated. In addition to the pathways 

for which equations are presented in Appendices A, B, and C, other exposure pathways should be 

evaluated if conditions at a specific site indicate that they might provide a significant contribution to the total population dose from all pathways. In this context, a significant contribution is defined as 10 percent or more. 

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 weighting 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 . 

V 0/Vp ) exp(-xitp) J Cdip vd p (0-2) 

* 

The population-integrated dose is the summation of the dose received by all individuals and 

has uni]ts of man-rem when applied to the total body dose and units of man-thyroid-rem when 

applied to the sunmation of thyroid dose. 

1.109-30 
^ 

•' I ./ 

i. 

1 

where 

The 

where 

The 

where 

and 

'! 

Cdip 

% 

s 

v

dp 

VP 

A

i 

population 

'I • Vp/J 

f

. 

* 

p

p 

Uap 

VP 

annual pop 

P.37 

is the average concentration over subregion d of the nuclide i in pathway p, 

in pCi/kg or pCi/liter (see Appendices A and C of this guide for models 

and equations for calculation of pathway concentrations); 

is the 50-mile average concentration of nuclide i in pathway p, in 

pCi/kg or pCi/liter; 

is the transport time of the food medium p through the distribution system, 

in days (Table D-1 presents estimates of the transport times that may be 

used in lieu of site-specific data); 

is the annual mass or volume of food medium p produced in subregion d, in kg 

or liters; 

is the mass or volume of the food medium p produced annually with the 50-mile 

radius about the site, in kg or liters; and 

is the radiological decay constant for nuclide i, in days" . 

served by all the food produced within 50 miles of the site is estimated as 

V a <D"

3> 

is the fraction of the population within the age group a; 

is the estimated population that can be served by the quantity of food p 

likely to be produced within 50 miles of the site; 

is the use or consumption factor of food medium p for the average individual 

in age group a, in kg/yr or liters/yr (taken from Table E-4); and 

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. 

ulation-integrated dose is then calculated as 

D

P - 0.001 1 Pp I I fa C1 p Ua p D Fa i (D-4) 

t * 

P 

(

P50 

0 Fai 

if VP 50 

if VP 50 

1s the ingestion dose factor for age group a and nuclide i, in mrem/pCi 

(taken from Appendix E, Tables E-11 to E-14); 

1.109-31 
P.38 

1 V I 

TABLE D-1 

RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD 

DISTRIBUTION SYSTEM* 

FOOD MEDIUM 

Fruits, grains, and vegetables 

Milk 

Meat and poultry 

Sport fish 

Commercial fish 

Drinking water 

DISTRIBUTION TRANSPORT TIME (in days) 

14 

4 

20 

7 

10 

1 

To be used in lieu of site-specific data on food distribution. 

1.109-32 
P.39 

p 

DJ . is the annual population-integrated dose to organ j (total body or thyroid), in man-rem/yr or thyroid man-rem/yr; 

P is the population consuming food medium p; and 

P5Q 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 age distribution of the population within 50 miles may be assumed to be the same as 

the age distribution of the U.S. population (Ref. 1). Reference 1 indicates the fractional 

breakdown to be as follows: children, 0.18; teenagers, 0.11; and adults, 0.71. Infants (0-1 year 

in age) are not projected to exceed 2% of the population (Ref. 1), and their population fraction 

has been included in that given above for children. 

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 liquid effluents should be evaluated for the following principal pathways: potable water, aquatic 

food products, external irradiation from shoreline deposits, and terrestrial food products irrigated with water that has received the liquid effluent. 

(1) Doses from Potable Water 

The annual population-Integrated total body and thyroid doses from water consumption 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 

Equation (A-2) 1n Appendix A of this guide, together with the age-dependent usage factors u _ 

ap 

obtained from Table 0-1. 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 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 1s known, it can be subtracted from the average daily Intake of the system before this value is entered into Equation 

(D-5). 

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, whose 

exposure vii drinking water should be included in the 50-mile population dose evaluation. 

1.109-33 
P.40 

(2) Doses from Aquatic Food Products 

'I 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 subregion 

using an impropriate 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 P given by the results of Equation (D-3). The agespecific ingestion rates of Table E-4 may be used in Tieu of site-specific data. 

For commercial harvests, the production within 50 miles from the site is considered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average 

concentration, with V 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 

P = PcQ.. The age-specific factors of Table E-4 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 summing the product of 

the individual doses in each subregion and the population exposed therein. All subregions 

within trie 50-mile radius should be considered where existing or designated recreational facilities 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 (D-4). Note that the term V of Equations 

(D-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 effluents, ingestion of contaminated terrestrial foods (milk, meat, and produce), and external 

irradiation from activity deposited on the ground. Available state or county agricultural production data may be used for estimating the population-integrated doses from food consumption 

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-l. 

(2) Doses due to Inhalation of Radioiodines 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 agespecific inhalation rates of Table E-4 may be used with the data of Tables E-7 to E-10. 

1.109-34 
P.41 

(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 (D-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, E-4, and E-ll to E-14, to calculate population 

doses. 

(4) Doses due to External Irradiation from Activity Deposited on 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-1). A 

household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose 

factors of Table E-6. 

REFERENCE FOR APPENDIX D 

1. "Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of 

Commerce, 1975. 

1.109-35 ! 
P.42 

APPENDIX E 

NUMERICAL DATA FOR THE CALCULATION 

OF ANNUAL DOSES TO MAN FROM ROUTINE 

RELEASES OF REACTOR EFFLUENTS 

This appendix contains data for use in the equations presented in the Regulatory Position 

and in Appendices A, B, C, and D of this guide. The numerical values presented in this appendix 

are those routinely used by the NRC staff. In instances where more appropriate information of a 

site-specific nature has been developed and documented, that information should be used. 

In a number of instances the staff has found it necessary to provide guidance as to the 

value of a particular parameter in the absence of substantial empirical data. In such instances 

the staff has exercised judgment and has considered values used by others and the sensitivity of 

the results to the value assumed. 

Information is provided below under four broad categories: environmental data, human data, 

dose factors, and other parameters. 

1. Environmental Data 

Table E-1 provides values for the following stable element transfer coefficients: 

a. B. for the estimation of produce, leafy vegetable, or pasture grass radioactivity 

from that in soil (pCi/kg in vegetation per pCi/kg in soil); 

b. F_ for the estimation of cow milk activity from that in feed (pCi/n in milk per pCi/ 

day ingested by the animal); and 

c. F, for the estimation of meat activity from that in feed (pCi/kg in meat per pCi/day 

ingested by the animal). 

The data are largely derived from Reference 1. The value of the cow milk transfer coefficient 

for radioiodine is based on the staff's review of the literature (Refs. 2-9). 

Values of transfer coefficients for goat milk are presented in Table E-2 for a limited 

number of nuclides. For nuclides not listed in Table E-2, the milk transfer coefficient from 

Table E-1 should be used. 

Various animal parameter values are presented in Table E-3 for use in estimating animal 

product activity levels as functions of the corresponding levels in feed and water supplies. 

2. Human Data 

Tables E-4 and E-5 present usage rates of various environmental media by average individuals 

and maximum individuals, respectively, according to age group. "Seafood" is used to indicate 

intake of aquatic; invertebrates such as lobster, crab, clams, and oysters. Ingestion of aquatic 

plant material is not normally assumed. 

3. Dose Factors 

Dose factors for external irradiation from a uniformly contaminated ground plane are 

2 

presented in Table E-6 (Refs. 10 and 11), in units of mrem/hr per pCi/m . These factors are 

applicable for surface contamination via deposition of liquid effluents on shoreline sediments 

or airborne effluents on ground surfaces. Dose factors are provided for the total body and skin 

only. Doses to other organs are assumed equal to the total body dose. 

Dose factors provided in Table E-6 are derived from a consideration of the dose rate to air 

1 meter above the ground plane and the penetration of the radiation into the body. The total 

body dose is computed at a penetration depth of 5 cm; the skin dose is computed at a depth of 

7 mg/cm . These tissue depths are indicated Dy Reference if, where it is suggested that, for 

1.109-36 
P.43 

TABLE E-1 

STABLE ELEMENT TRANSFER DATA* 

Element 

H** 

c** 

Na 

P 

Cr 

Mn 

Fe 

Co 

Ni 

Cu 

Zn 

Rb 

J'Sr 

Y 

Zr 

Nb 

Mo 

Tc 

Ru 

Rh 

Ag 

Te 

I 

Cs 

Ba 

La 

Ce 

Pr 

Nd 

W 

Np 

B, iv 

Veq/Soil 

4.8E 00 

5.5E 00 

5.2E-02 

1.1E 00 

2.5E-04 

2.9E-02 

6.6E-04 

9.4E-.03 

1.9E-02 

1.2E-01 

4.0E-01 

1.3E-01 

1.7E-02 

2.6E-03 

1.7E-04 

9.4E-03 

1.2E-01 

2.5E-01 

5.0E-02 

1.3E 01 

1.5E-01 

1.3E 00 

2.0E-02 

1.0E-02 

5.OE-03 

2.5E-03 

2.5E-03 

2.5E-03 

2.4E-03 

1.8E-02 

2.5ET03 

F (Cow) 

m Milk (d/i) 

1.0E-02 

1.2E-02 

4.0E-02*** 

2.5E-02 

2.2E-03 

2.5E-04 

1.2E-03 

l.OE-03 

6.7E-03 

1.4E-02 

3.9E-02 

3.0E-02 

8.0E-04*** 

1.0E-05 

5.0E-06 

2.5E-03 

7.5E-03 

2.5E-02 

1.0E-06 

1.OE-02 

5.0E-O2 

l.OE-03 

6.0E-03t 

1.2E-02*** 

4.0E-04*** 

5.0E-06 

1.0E-04*** 

5.0E-06 

5.0E-06 

5.0E-04 

5.0E-06 

Ff 

Meat (d/kg) 

1.2E-02 

3.1E-02 

3.0E-02 

4.6E-02 

2.4E-03 

8.0E-04 

4.OE-02 

1.3E-02 

5.3E-02 

8.OE-03 

3.OE-02 

3.1E-02 

6.0E-04 

4.6E-03 

3.4E-02 

2.8E-01 

8.OE-03 

4.0E-01 

4.0E-01 

1.5E-03-

1.7E-02 

7.7E-02 

2.9E-03 

4.OE-03 

3.2E-03 

2.0E-04 

1.2E-03 

4.7E-03 

3.3E-03 

1.3E-03 

2.0E-04t+ 

tt 

Data presented in this table is from Reference 1 unless otherwise indicated. 

Meat and milk coefficients are based on specific activity considerations. 

* 

From Reference 15. 

^See text. 

From Reference 13. 

1.109-37 
t

: 

i 

TABLE E-2 

NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK* 

Element

 Fm <<*ays/l1ter) 

H 0.17 

, \ 

P.44 

* 1 1 

\ 

c 

P 

Fe 

Cu 

Sr 

I 

Cs 

0.10 

0.25 

1.3E-04 

0.013 

0.014** 

0.06** 

0.30** 

Values in this table are from References 1 and 14 unless 

otherwise Indicated. 

* 

From Reference 15. 

Animal 

M1lk cow 

Beef cattle 

Goats 

TABLE E-3 

ANIMAL CONSUMPTION RATES 

Feed or Forage 

(kq/day [wet welqht]) 

50 (Ref. 10) 

50 (Ref. 10) 

6 (Ref. 17) 

QAw 

Water 

(a/day) 

60 (Ref. 

50 (Ref. 

8 (Ref. 

16) 

16) 

18) 

1.109-38 
RECOMMENDED VALUES FOR U 

ap 

TABLE E-4 

TO BE USED FOR THE AVERAGE INDIVIDUAL 

IN LIEU OF SITE-SPECIFIC DATAPathway 

Fruits, vegetables, & 

grain (kg/yr)* 

Milk U/yr) * 

Meat & poultry 

(kg/yr)* 

Fish (kg/yr)* 

Seafood (kg/yr)* 

Drinking water (n/yr)** 

Shoreline recreation 

(hr/yr)** 

Inhalation (m /yr) 

Child Teen Adult 

200 

170 

37 

2.2 

0.33 

260 

9.5 

3700*** 

240 

200 

59 

5.2 

0.75 

260 

47 

8000*** 

190 

110 

95 

- 6.9 

1.0 

370 

8.3 

8000+ 

Consumption rate obtained from Reference 19 and age-prorated using 

techniques in Reference 10. 

** 

Data obtained directly from Reference 10. 

*** 

Inhalation rate derived from data provided 1n Reference 20. 

Data obtained directly from Reference 20. 

1.109-39 
P.46 

> k < 

RECOMMENDED VALUES FOR U 

TABLE E-5 

TO BE USED FOR THE MAXIMUM EXPOSED 

ap 

INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA 

Pathway Infant 

Fruits, vegetables & 

grain (kg/yr)*,** 

Leafy vegetables 

(kg/yr)* 

Milk (u/yr)* 330 

Meat & poultry 

(kg/yr)* 

Fish (fresh or salt) 

(kg/yr)*** 

Other seafood (kg/yr)* 

Drinking water (i/yr)t 330 

Shoreline recreation 

(hr/yr)t 

Inhalation (m/yr) 1400tt 

Child 

520 

26 

330 

41 

Teen 

630 

42 

400 

65 

Adult 

520 

64 

310 

110 

6.9 

1.7 

510 

14 

3700+tt 

16 

3.8 

510 

67 

8000ttt 

21 

5 

730 

12 

8000tt 

Consumption rate obtained from Reference 19 for average individual and 

age-prorated and maximized using techniques contained in Reference 10. 

** 

Consists of the following (on a mass basis): 22% fruit, 54% vegetables 

(including leafy vegetables), and 24% grain. 

• * * 

Consumption rate for adult obtained by averaging data from References 10 

and 21-24 and age-prorated using techniques contained in Reference 10. 

Data obtained directly from Reference 10. 

Data obtained directly from Reference 20. 

t+t Inhalation rate derived from data provided in Reference 20. 

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P.49 

calculational purposes, the average depth of the blood-forming organs may be assumed to be 5 cm. 

Reference 12 also identifies the cells of the basal layer of epidermis as the tissue of interest 

2 

in the computation of skin dose and states an average depth for these cells of 7 mg/cm . This 

guidance Is reflected in the dose factors presented in Table E-6 and also in those presented in 

Appendix B, Table B-l, for use in calculating external doses from noble gases. 

Dose factors for internal exposure are provided in Tables E-7 through E-14, in units of 

mrem per pCi Intake (Ref. 25). Tables E-7 through E-10 are for Inhalation (one table for each 

of the four age groups), while Tables E-ll through E-14 are for ingestion. Dose factors provided 

for the inhalation of H-3 include an increase of 50 percent to account for the additional amount 

of this isotope absorbed through the skin (Ref. 25). 

As discussed in Section B, "Discussion," these dose factors are appropriate for continuous 

intake over a one-year period and include the dose commitment over a 50-year period. The calculational scheme by which these dose factors are derived includes elementary consideration of 

changing physical and metabolic characteristics during the period over which the dose commitment 

is evaluated. For example, environmental exposure of an infant over a one-year period is treated 

as follows: dose during the first year is computed based on infant physiological and metabolic 

characteristics considering both the buildup and decay of the appropriate organ burden; dose 

during years 1-10 is computed based on child physiological and metabolic data considering decay 

of the organ burden from Its peak value at age 1; dose during years 11-16 Is treated in a similar 

fashion using teenager characteristics; and dose during adulthood is computed based on the 

physiological and metabolic characteristics of an adult. Age-dependent parameters are changed in 

steps at the breaks between age groups. 

4. Other Parameters 

Table E-15 has been provided as"a central location for the recommended values of many of 

the miscellaneous parameters appearing in equations in this guide. In some instances, a parameter's 

value or units is a function of the equation it is used in. Additionally, for some parameters 

used in calculating activities in vegetation, the value is also a function of the exposure pathway. Table E-15 has been organized to note these complications. 

Values of the parameter Sp, a structural shielding and occupancy factor, are given in 

Table E-15 as 0.7 (for maximum individuals) and 0.5 (for the general population). Using the 

general approach given in Reference 26, the staff estimates an average structural shielding factor 

of 0.5 for typical reactor effluents. Assuming the maximum individual spends about 50 percent of 

the time indoors, the overall shielding and occupancy factor is then approximately 0.7. The 

factor of 0.5 is used directly for population dose calculations. These factors are applicable 

for external gamma exposure from noble gases and for external exposure from contaminated ground 

surfaces. 

1.109-43 
i 

NUCLIC E 

H 

£ 

J A 

P 

CK 

*N 

MN 

FE 

FE 

CO 

CO 

••J l 

Nil 

CU 

ZN 

ZN 

.«R 

>>R 

i'P. 

TK 

in 

«B 

$« 

s« 

s« 

SK 

Y 

Y 

Y 

Y 

3 

14 

24 

32 

51 

54 

56 

55 

59 

58 

60 

63 

65 

64 

64 

69 

8 3 

84 

8, 

bo 

88 

89 

39 

90 

91 

92 

90 

91* 

9 1 

9? 

tJONC 

NO OATA 

2.27E-06 

1.28E-06 

1.656-04 

NO DATA 

NO OATA 

NU OATA 

3.07E-C6 

1.475-06 

NC OATA 

NO UATA 

5.40_-05 

1.92E-10 

NO OATA 

4.05E-06 

4.23E-12 

NO OATA 

NO OATA 

NO OATA 

NU OATA 

NO OATA 

NU DATA 

3.80.-05 

1.24E-02 

7.746-09 

8.43E-10 

2.616-07 

3.26E-11 

5.78E-C5 

1.29E-09 

TABLE 6-

PASt 

INHALATION DOSE 

( 

LIVER 

1.58E-07 

4.26E-07 

1.28C-06 

9.64E-06 

NO UATA 

4.95C-06 

1.556-10 

2.12C-06 

3.47E-06 

1.986-07 

1 .-+46-06 

3.936-06 

2.o2C-ll 

1.836-10 

1.296-05 

8.14.-12 

JU OATA 

NU OATA 

NO OATA 

1.696-05 

4.84_-08 

3.2C_-08 

NU CATA 

NU OATA 

NO OATA 

NO CATA 

NC OATA 

NO OATA 

NO OATA 

NO OATA 

1 OF 

. 

3 

FACT09S FOR AHULTS 

"RXiH PF.K >»CI 

T.ROCY 

1.58F-07 

4.266-07 

1.28E-06 

O.26C-06 

1.25E-08 

7.8.E-07 

2.29E-U 

4.936-07 

I.32E-0 6 

2.596-0 7 

1.35E-06 

1.81E-06 

I.146-11 

7.69,-11 

5.'82 E-06 

5.65E-13 

3.01E-O8 

3.91E-0 8 

1.606-09 

7.37E-06 

2.41E-18 

2.126-08 

1.09E-06 

7.62E-04 

3.13E-10 

3.64E-11 

7.01E-09 

1.27E-12 

1.55E-06 

3.77E-U 

NHALED) 

THYROID 

1.586-C7 

4.266-07 

1.286-06 

NO OATA 

7.44E-09 

NO 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

. NO 

NO 

NO 

NO 

NO 

NO 

NO 

NC 

NO 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

OATA 

OATA 

DATA 

OATA 

CATA 

DATA 

OATA 

OATA 

DATA 

OATA 

DATA 

DATA 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

1.109-44 

MONEY 

1.58E-07 

4.26E-07 

1.286-06 

NC DATA 

2.856-09 

1.236-06 

l.63fc-:10 

NO DATA 

NO OATA 

NC OATA 

NC OATA 

NO DATA 

NC DATA 

5.786-10 

H.62L-06 

5.27L-12 

NC DATA 

NC DATA 

NC OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NC DATA 

NO OATA 

NO OATA 

NO OATA 

NC DATA 

NO DATA 

NC OATA 

LUNG 

1 .58E-07 

4.266-07 

1.286-06 

NO OATA 

1.80E-C6 

1.75E-04 

1.18E-06 

9.CIE-06 

1.27E-04 

1.166-04 

7.46E-04 

2.23E-05 

7.00E-07 

8.48E-07 

1.08E-04 

1.156-07 

NO OATA 

NO OATA 

NO DATA 

NO OATA 

NU OATA 

NO DATA 

1.75E-04 

1.20E-03 

4.566-06 

2.06E-06 

2.126-05 

2.40E-07 

2.136-04 

1.966-06 

V 

* '* 

GI-LLI 

t.586-07 

4.266-07 

1.286-06 

1.086-05 

4.156-07 

9.67E-06 

2.536-06 

7.54E-07 

2.35E-05 

1.33E-05 

3.56E-05 

1.67E-06 

1.54E-06 

6.12E-06 

6.68E-n6 ^ 

2.046-C9 

2.906-08 

2.05E-13 

LT E-24 

2.086-06 

4.18,-19 

1.16F-21 

4.37E-05 

9.02E-05. 

2.396-05 

5.386-06 

6.326-05 

1.666-10 

4.81E-05 

9.196-06 
P.51 

TA.LF 6-7, CONT'D 

PAO6 2 OF 3 

INHALATION COSC FACTORS FOR ADULTS 

(«KtM P«=i. PCI INHALED) 

-.UCLIJL BONE LIV6R T.nODY THYROID KIONFY LUNG GI-LLI 

Y 93 l.iet-OS NO DATA 3.26E-10 NO OATA NC OATA 6.066-06 5.276-05 

ZR 95 1.346-05 4.3C6-06 2.916-06 NO OATA 6.77E-06 2.216-C4 1.386-05 

ZR 97 1.21F-08 2.456-09 1.136-09 MO CATA 3.716-09 9.846-0. 6.546-05 

Nfl 95 1.76E-06 9.77L-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30F-05 

HC 99 -(0 CATA 1.516-08 2.87fc-09 NO DATA 3.64E-08 1.14E-C5 3.106-05 

TC 99M 1.296-13 3.646-13 4.616-12 NO OATA 5.526-12 9.55E-C8 5.206-07 

TC101 5..26-15 7..21-15 7.3a6-14 NO OATA 1.35.-13 4.99E-08 1.36F-21 

RU103 1.916-07 NO CATA 8.236-08 NO OATA 7.296-07 6.316-05 1.38E-05 

!<UIC5 9.88F-11 ,NC DATA 3.89C-U NO DATA 1.276-lC 1 . J7E-06 6.02E-06 

RU106 8.64E-C6 NO CATA 1.0JC-06 NO DATA 1.676-05 1.176-03 1.146-04 

AGUOK 1.35E-C6 1.25c-06 7.43C-07 NU DATA 2.46E-06 5.796-04 3.786-05 

TC125M 4.27E-07 1.9.6-07 5.846-08 1.31E-07 1.55e-06 3.92E-C5 8.83E-06 

TE127>» 1.586-06 7.215-07 1.966-07 4..116-07 5.726-06 1.206-04 I. ,376-05 

TE127 1.75C-10 8.0.,:-U 3.876-11 1.326-10 6.376-10 8.146-07 7.1'C-06 

1.129* 1.226-06 5.b4.-07 1.966-07 4.306-07 4.576-06 1.456-04 4.79.-05 

TE129 6.226-12 2.19L-12 1.5.E-12 4.376-12 2.346-11 2.42E-C7 1.96F-08 

TE131M B.746-09 5.455-09 3.63F-09 6.386-09 .. 366-08 1.826-05 6.956-05 

T F131 1.396-12 7.*AC^I 3 4.49E-13 1.176-12 5.466-12 1.745-07 2.306-09 

TE132 3.25U-08 2.696-08 2.026-08 2.37E-08 1.826-07 3.606-05 6.37F-05 

I 130 5.726-07 1.685-06 6.6C.C-07 1.42E-C4 2.616-06 NO DATA 9.616-07 

I 131 3.156-06 4.47.-06 2.56C-06 1.49E-C3 7.666-06 NO CATA 7.85F-C7 

I 132 1.4. E-07 4.07li-07 1.4.E-07 1.43E-C5 6.486-07 NO DATA 5.08F-08 

I 131 1.08E-C6 1.85.-06 5.6.6-07 2.696-C4 3.236-06 NO DATA 1.116-06 

I 134 B.056-08 2.16C-07 7.696-08 3.736-06 3.446-07 NO OATA 1.266-10 

I 135 3..5E-C7 8.73E-07 3.21E-07 5.606-0. 1.39E-06 NO OATA 6.566-07 

CS134 4.666-C5 1.066-04 9.10F-05 NO DATA 3.59E-C5 1.226-05 1.306-06 

CS136 4.886-C6 1.636-05. 1.316-05 NO CATA 1.C7E-P5 1.506-C6 1.466-06 

CS137 5.986-05 7.765-05 5.1JC-05 NO OATA 2.786-15 9.406-06 1.056-06 

CS13M 4.146-08 7.76.-08 4.0>6-08 NO OATJ 6.006-C? 6.076-09 2.33E-13 

HA139 1.176-10 fl...2.-14 3.42I-12 NO OATA 7.78E-14 4.706-07. 1.126-07 

1.109-45 
P.52 

TABL. E-7 , CONT'D 

PAGE 3 OF 3 

IMHALATION 

(MREM 

DCS 6 

PC!. ! 

FACTORS FOR 

CI INHALEO) 

ADULTS 

.UCLIUE 

HA140 

nAl4l 

HA142 

LA140 

LA142 

CE141 

06143 

C6144 

PR143 

?R144 

MD147 

* 187 

80NE 

4.886-06 

1.25E-11 

3.296-12 

4.30E-C8 

8.54E-U 

2.49E-06 

2.336-Cfl 

4.29E-04 

1.176^-06 

3..76E-12 

6.596-07 

1.06i*-09 

I IVER 

6. 136-09 

9.416-15 

3.38 .-15 

2.175-08 

3.886-11 

1.695-06 

1.726-03 

1.79E-04 

4.69G-07 

1.566-12 

7.62C-07 

3.d5_-l0 

T.6UCY 

3. 71 E-0 7 

4.2C6-13 

2.076-13 

5.73C-09 

9.656-12 

1.9U-07 

1.91E-09 

2.306-0 5 

5.806-08 

1.91E-13 

4.56E-08 

3.10E-10 

THYROID 

NO 

NO 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

OATA 

OATA 

DATA 

CATA 

DATA 

DATA 

DATA 

OATA 

DATA 

OATA 

KIDNEY 

2.09E-09 

8.75E-I5 

2.S6E-15 

NO- OATA 

NG DATA 

7.836-07 

7.60E-09 

1.06E-04 

2.70E-07 

8.81E-13 

4.45E-07 

NO DATA 

LUNG 

1.59F-04 

2.426-07 

1.49E-07 

1.70E-05 

7.916-07 

4.52E-05 

9.97E-06 

9.72E-04 

3.51E-05 

1.276-07 

2.76E-05 

3.63E-06 

GI-LLI 

2.73F-05 

1.45E-17 

1.96E-26 

5.736-05 

2.64E-07 

1.50E-05 

2.83E-05 

1.026-04 

2.50E-05 

2.69E-18 

2.16E-05 

1.94E-05 

NP239 2.87E-08 2.825-09 1.556-09 NO OATA 8.756-09 4.706-06 1.49E-05 

1.109-46 
P.53 

TABLE C-8 

PAG6 I OF 3 

INHALATION DOSE FACTORS FOR TEENAG6R 

(MREH P6R PCI INHAL60) 

NUCLIC E 

H U •J A 

P 

CR 

f»N 

f.N 

FE 

FE 

CO 

CU 

MI 

XI 

CU 

ZN 

?N 

HR 

UR 

^.R 

•*B 

R? 

RB 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

3 

14 

24 

32 

51 

54 

56 

55 

5 9 

50 

60 

63 

65 

64 

60 

69 

8 3 

84 

85 

86 

83 

89 

89 

90 

91 

92 

90 

91f 

91 

92 

NO 

3. 

1. 

2. 

NO 

NO 

NO 

4. 

1. 

NO 

NO 

7. 

2. 

NO 

4. 

6. 

NO 

NO 

NO 

NO 

NO 

NO 

5. 

1. 

1. 

1. 

3. 

4. 

8. 

1. 

BONE 

OATA 

256-06 

72E-06 

36E-04 

DATA 

CATA 

OATA 

18E-06 

996-06 

DATA 

DATA 

25E-05 

736-10 

OATA 

C2E-06 

046-12 

DATA 

OATA 

DATA 

OATA 

OATA 

OATA 

43E-05 

35E-02 

106-08 

19E-C9 

736-07 

63E-11 

26E-05 

84E-09 

1. 

6. 

1. 

1. 

NO 

6. 

2. 

2. 

4. 

2. 

1. 

5. 

3. 

2. 

1. 

1. 

NO 

NU 

NO 

2. 

6. 

4. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NU 

LIVER 

595-07 

C9E-07 

72.-06 

37.-0. 

DATA 

39F-06 

I2i£-10 

986-06 

626-06 

596-07 

896-C6 

436-06 

o6F-H 

546-10 

076-05 

15F-U 

DATA 

OATA 

OATA 

386-05 

826-08 

403-08 

DATA 

OATA 

CATA 

CATA 

OATA 

OATA 

OATA 

DATA 

T.BOCY 

1 

6. 

1. 

8 

I 

I 

3. 

6 

I 

3 

2 

2 

1 

1 

7 

8 

4 

5 

2 

1 

3 

2 

1 

8 

4 

5 

1 

1 

2 

5 

596-

096-

726-

.956-

.696-

.0.6-

156-

.936-

796-

.476-

.486-

.476-

.596-

.066-

.80E-

.076-

30C-

.416-

.296-

.05E-

.40E-

.91E-

.56E-

.356-

.39E-

.08E-

.OOE 

.776 

.21E 

. 36E 

-0 7 

-0 7 

-0 6 

-0 6 

-0 8 

-06 

-11 

-0 7 

-06 

-0 7 

-06 

-06 

-11 

-10 

-0 6 

-13 

-0 8 

-0 8 

r09 

-0 5 

-0 8 

-0 8 

-0 6 

-04 

-10 

-11 

-0 8 

-12 

-06 

-11 

THYROID 

1.596-07 

6.09E-07 

1.726-06 

NO DATA 

9.37E-09 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

DATA 

OATA 

OATA 

DATA 

DATA 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

DATA 

DATA 

DATA 

OATA 

KIDNEY 

1. 

6.( 

59F-07 

•»9E-07 

1.72E-06 

NC 

3. 

1. 

2.. 

NO 

NO 

NO 

NG 

NO 

NO 

8. 

1. 

7. 

NO 

NC 

NO 

NO 

NO 

NO 

NC 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

346-09 

S9E-06 

.46-10 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

316-10 

386-05 

53E-12 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

DATA 

OATA 

I. 

6. 

1. 

NC 

2. 

2. 

1. 

1. 

1. 

1. 

1. 

3. 

1. 

1. 

1. 

1. 

LUNG 

596-

09E72E-

•07 

•07 

•06 

) DATA 

62E48E906-

556-

916-

686-

096-

84E17E39E55E986-

•06 

-04 

-06 

-05 

-04 

-04 

-03 

•05 

-06 

-06 

-04 

-07 

NO OATA 

NC 

NC 

) DATA 

) DATA 

NO DATA 

NO DATA 

NO OATA 

3. 

2. 

7. 

3, 

3. 

4. 

3. 

3. 

02E06E59E43E66EOOE67E35E-

-04 

-03 

-06 

-06 

-05 

-07 

-04 

-06 

GI-LLI 

1. 

6. 

1. 

1. 

3. 

8. 

7. 

7. 

2. 

1. 

3 

1 

4 

7 

5 

3 

59E096-

726-

16F75E356-

186-

996-

23E-

.196-

.246-

.77E-

.596-

.686-

.836-

.566-

LT E-

-07 

-07 

-06 

-05 

-07 

-06 

-06 

-07 

-05 

-05 

-05 

-06 

-06 

-06 

-06 

-08 

.4 

LT E-24 

LT E-, 

2 

3. 

4. 

4. 

9 

3 

I 

6 

3 

5 

2 

216-

65E-

.22E-

,6s6-

.56E246-

.496-

.99E-

• 77E 

. HE 

.06E 

.4 

-06 

-15 

-17 

-05 

-05 

-05 

-05 

-05 

-09 

-05 

-05 

1.109-47 
" ' p 

!i 

"lUGLICE 

Y 93 

ZR 95 

ZR 97 

N3' 95 

MO 99 

TC 99W 

TClOl 

KU103 

<U105 

SU106 

AG LI OP 

TE125P 

TE12 7": 

TE127 

TE129H 

TF129 

lEUl*-

T6131 

TC132 

1 13C 

I 131 

I 132 

I 133 

I 134 

I 135 

CSI 34 

C.Sl 36 

CS137 

CS|138 

•3A139 

BCN6 

1.696-08 

1.826-05 

I. 726-08 

2.32C-06 

..0 DATA 

1.736-13 

7.406-15 

2.636-07 

1.406-lC 

1.23F-05 

1.7 36-06 

6.10E-07 

2.256-06 

2.516-10 

1.746-06 

8.876-12 

1.236-08 

1.97E-12 

4.50£-0e 

7.80E-07 

4.43E-06 

1.996-07 

1.526-06 

l.UE-07 

4.626-07 

6.285-0. 

6.446-06 

8.38E-05 

5.82E-08T 

1.67.-10 

TABLL EPAGE 8, CONT'D 

2 OF 3 

INHALATION DOSE FACTORS TCR 

( 

LIVF'. 

NO DATA 

5.735-06 

3.406-09 

1.295-06 

2.115-08 

4.B3E-1 J 

1.056-14 

NO CATA 

NO OATA 

NO OATA 

1.645-06 

2.806-07 

1.026-06 

1.14F-10 

8..3E-07 

4.225-12 

7.515-09 

1.045-12 

3.6.E-08 

2.245-06 

6.14F-06 

5.475-07 

2..66-06 

2.905-07 

1.10E-06 

1.41E-04 

2. -.25-05 

1.066-04 

1.076-07 

1.186-13 

» 

TEFNAGFR 

"RE* PtR PCI INHALED) 

T.I.OOY 

4.65E-1C 

3.946-06 

1.576-09 

7.086-07 

4.036-09 

6.246-12 

1.036-13 

1.12c-07 

5.426-11 

1.555-06 

9.99E-0-7 

8.34E-08 

2.73E-07 

5.52C-1 I 

2.816-0 7 

2.20E-12 

5.03E-09 

6.30E-13 

2.74E-08 

8.9e6-07 

3.30E-06 

1.97E-07 

7.78E-07 

1.056-07 

4.366-07 

6.e66-05 

1.716-05 

3.896-0 5 

5.586-08 

4.876-12 

THYROIO 

NO DATA 

NO DATA 

NO DATA 

NU DATA 

NO CATA 

NO OATA 

NO OATA 

NO UATA 

NO OATA 

NO DATA 

NU DATA 

1.756-07 

5.4eE-07 

1.776-10 

5.72E-07 

6.486-12 

9.066-09 

1.556-12 

3.076-08 

1.866-04 

1.836-03 

1.896-05 

3.656-04 

4.94E-06 

7.766-05 

NO DATA 

NO DATA 

NO DATA 

NO OATA 

NO DATA 

1.109-48 

KIDNEY 

NO DATA 

e.426-06 

.5.15E-09 

1.25E-06 

5.146-08 

7.206-12 

1.906-13 

9.29E-C7 

1.76E-10 

2.386-05 

3.136-06 

NO DATA 

8.176-06 

9.10E-10 

6.496-06 

3.32E-U 

5.496-08 

7.72E-12 

2.446-07 

3.44E-06 

1.05E-05 

8.65E-07 

4.496-06 

4.586-07 

1.866-06 

4.696-05 

1.386-05 

3.806-05 

8.286-08 

l.HE-13 

LUNG 

1.046-05 

3.366-04 

1.626-05 

9.39E-C5 

1.92E-05 

1.446-07 

8.34E-08 

9.796-05 

2.276-06 

2.016-03 

8.446-04 

6.706-05 

2.07E-04 

I.406-06 

2.476-04 

4.12E-07 

2.97E-05 

2.926-07 

5.616-05 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO DATA 

NO OATA 

1.836-05 

2.226-06 

1.516-05 

9.84E-09 

8.086-07 

. N • *• 

GI-LLI 

7.24E-05 

1.866-05 

7.886-05 

1.21E-05 

3.366-05 

7.66E-07 

1.096-16 

1.36P-05 

1.136-05 

1.206-04 

3.41F-05 

9.38E-06 

1.99E-05 

1.016-05 N 

5.06E-05 J 

2.02E-07 

7.76E-05 

1.89E-09 

5.79F-05 

1.146-P6 

8.11F-07 

1.59E-07 

1.296-06 

2.55C-09 

8.69E-07 

1.226-06 

I. 366-06 

1.066-06 

3.386-11 

8.066-07 
TAULE E-8 , CUNT'C 

PAGE 3 OF 3 

INHALATION OUSE FACTORS FCR TEENAGER 

.MREM PER PCI INHALED) 

P.55 

NUCLID E 

.A 14 0 

•5 A 14 I 

»'A142 

LA14 0 

LA14 ? 

CE14 1 

C614 3 

CE144 

P9143 

IVR144 

MC147 

W 187 

00N6 

6.84E-06 

1.786-11 

4.62E-12 

5.996-08 

1.20C-10 

3.556-06 

3.325-08 

6.UE-04 

1.676-06 

5.37E-12 

9.83E-C7 

1.50E-09 

LlVL? 

8.i8F-09 

1.J26-14 

4.636-15 

2.955-08 

5.31E-U 

2.37C-06 

2.42E-08 

2.536-04 

6.64E-C7 

2.206-12 

1.67E-06 

1.22C-C9 

T.3CCY 

4.406-07 

5.91C-13 

2.846-13 

7.82C-09 

1.326-1 1 

2.716-07 

2.706-09 

3.23E-05 

J.2SE-08 

2.726-13 

6.416-0 8 

4.29E-IC 

THYP.OIC 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

DATA 

CATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

KIDN6Y 

2.856-09 

1.236-14 

3.92E-15 

NO OATA 

NC DATA 

1 .11.-06 

l.oec-08 

1.516-04 

3.866-07 

1.26E-12 

6.286-07 

NC OATA 

LUNG 

2.546-04 

4.116-07 

2.396-07 

2.686-05 

1.276-06 

7.676-05 

1.636-05 

1.67E-03 

6.04E-05 

2.196-07 

4.656-05 

5.92E-06 

GI-LLI 

2.86E-05 

9.336-14 

5.99E-20 

6.09E-05 

1.50E-06 

1.58E-05 

3.19E-05 

1.08E-04 

2.676-05 

2.94E-L4 

2.28F-05 

2.21F-05 

JP239 4.236-0 8 3.995-0 9 2.215-0 9 NU OATA 1.256-0 8 8.116-0 6 1.656-0 5 

1.109-49 
P.56 

TABL6 E-9 

PAG6 I UF 3 

INHALATION OCSE FACTORS FCR CHILD 

(MREM P5R PCI INHAL6D) 

NUCLICt 

H . 

C 

NA 

P 

CR 

MN 

MN 

F6 

3 

14 

24 

32 

51 

54 

56 

55 

F6| 59 

CO 

CO 

NI 

JI 

OU 

Z.N 

ZN 

. R. 

JR 

« • * 

KO 

KD 

KB 

SR 

SR 

SP. 

SR 

Y 

Y 

Y 

Y 

53 

60 

63 

65 

64 

65 

69 

8 3 

84 

85 

86 

88 

89 

89 

90 

91 

92 

90 

91M 

91 

92 

NO 

9. 

4. 

7. 

NO 

NO 

NO 

I. 

5. 

NO 

NO 

80N6 

DATA 

70E-06 

35E-06 

046-04 

DATA 

DATA 

DATA 

28E-05 

59E-06 

OATA 

OATA 

2.226-04 

8. 

NU 

1. 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

I. 

2. 

3. 

3. 

1. 

1. 

2. 

5. 

C8E-10 

DATA 

15E-05 

816-11 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

62E-04 

73E-02 

286-08 

.45-09 

116-06 

376-10 

476-04 

506-09 

3. 

1. 

4. 

3. 

NO 

I. 

4. 

6. 

9. 

4. 

3. 

1. 

7. 

5. 

3. 

2. 

NO 

NU 

NO 

5. 

1. 

9. 

NO 

NU 

NO 

NO 

NO 

NC 

NO 

NO 

LIVER 

C45-07 

825-06 

355-06 

095-05 

OATA 

165-05 

485-10 

006-06 

C46-06 

796-07 

556-06 

256-05 

996-11 

396-10 

066-05 

616-11 

OATA 

OATA 

OATA 

366-05 

526-07 

335-08 

DATA 

DATA 

CATA 

OATA 

DATA 

DATA 

DATA 

DATA 

T.rtOCY 

3. 

1. 

4. 

2. 

4 

2 

8. 

?.. 

4. 

8. 

6 

7 

4 

2 

1 

2-

1 

1 

6 

3 

9 

7 

4 

I 

1 

I 

2 

4 

6 

1 

046-

826-

356-

676-

17E576-

436-

106-

516-

556-

126-

566-

44E-

.90C-

.90C4 U-

.286-

486-

346-

.096-

.906-

,8J 6 

.666-

.746-

.246 

.426-

.996 

.936-

.596 

.57E 

-0 I 

-06 

-0 6 

-0 5 

-0 8 

-0 6 

-1 t 

-06 

-06 

-0 7 

-06 

-0 6 

-11 

-10 

-0 5 

-12 

-0 7 

-0 7 

-0 9 

-0 5 

-08 

-0 8 

-06 

-0 3 

-09 

-10 

-0 8 

-12 

-06 

-10 

THYROID 

3.046-07 

1.826-06 

4.356-06 

NO OATA 

2.31F-08 

NO 

NO 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

OATA 

OATA 

CATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

DATA 

OATA 

OATA 

DATA 

KIDN6Y 

3.046-07 

1.826-06 

4. 

NC 

J5E-C6 

OATA 

6.576-09 

2. •16-06 

4.526-10 

NO 

NO 

NO 

NO 

NO 

Nti 

DATA 

DATA 

OATA 

DATA 

UATA 

DATA 

1.636-09 

I. 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NC 

NO 

NO 

NO 

NO 

NO 

NO 

536-05 

586-11 

DATA 

DATA 

OATA 

OATA 

DAT* 

DATA 

DATA 

OATA 

DATA 

OATA 

DATA 

DATA 

OATA 

DATA 

3. 

1. 

4. 

LUNG 

04E826-

356-

•07 

•06 

-06 

NO DATA 

4. 

4. 

3. 

3. 

3. 

2. 

1. 

7. 

2. 

2. 

?. 

3. 

596-

26E55EOOE43C99E91E43E21E59E696-

846-

•06 

-04 

•06 

•05 

-04 

•04 

-03 

-05 

-06 

-06 

: 04 

-07 

NO OATA 

NO OATA 

NO DATA 

NO DATA 

NO CATA 

NO OATA 

5. 

3. 

1. 

6. 

7, 

7. 

7. 

6 

83E99E44E49C07E60F10E466-

-04 

-03 

-05 

-06 

-05 

-07 

-04 

-C6 

GI-LLI 

3. 

1. 

4. 

1. 

2. 

6. 

3. 

7. 

L. 

04E82E356-

146-

936-

196-

33C75E91E9.29E2 .60E1.71E2 

9 

4 

2 

.27E-

.926-

.416-

.756-

LT E-

-07 

-06 

-06 

-05 

-07 

-06 

-05 

-07 

-05 

-06 

-05 

-06 

-05 

-06 

-06 

-06 

.4 

LT E-24 

LT E2 .166-

4.666-

5 

4 

9 

4 

6 

7 

4 

4 

6 

.116-

.526-

.28E-

.70 .-

.556-

.246 

.646 

.976-

.466 

?4 

-06 

-09 

-10 

-05 

-05 

-05 

-05 

-05 

-07 

-05 

-05 

1.109-50 
P.57 

TAflLL 6-9 , CONT'D 

PAG6 2 OF 3 

INHALATION OLS6 FACTORS FOR CHILO 

("REM P6R PCI INHAL60) 

tUCLlDE BUN6 LIV.R T.iiODY THYRUID KION6Y LUNG Gl-LLI 

Y 93 5.046-08 .NO OATA 1.386-09 NO DATA NO DATA 2.01E-05 1.05E-04 

ZR 95 5.13E-05 1.135-05 l.OOE-05 NO OATA 1.616-05 6.036-04 1.65E-05 

ZR 97 5.076-08 7.346-09 4.326-09 NO OATA 1.05E-08 3.066-05 9.49E-05 

NH 9. 6.356-06 2.48E-06 1.776-06 NO OATA 2.33E-06 1.666-04 1.00E-05 

MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA I.C6E-07 3.666-05 3.42E-05 

TC 99f 4.816-13 9.41C-13 1.566-11 NO DATA 1.37C-U 2.57E-C7 1.30E-06 

TClOi 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.926-13 1.586-07 4.41F-09 

RU103 7.556-07 NO OATA 2.906-07 NO OATA 1.906-06 1.796-04 1.216-C5 

RU105 4.136-10 NU DATA 1.506-10 NO DATA 3.63E-10 4.30E-06 2.696-05 

RU106 3.686-05 NO DATA 4.576-06 NO DATA 4.97E-05 3.87E-03 1.166-04 

AGIIOM 4.56E-06 3.086-06 2.476-06 NO OATA 5.74L-06 1.486-03 2.71E-05 

TEL25M 1.82E-06 6.295-07 2.47E-07 5.20.-07 NC DATA 1.296-04 9.136-06 

TE127M 6.726-06 2.31E-06 8.loE-07 1.64E-06 1.72E-05 4.006-04 1.936-05 

TE127 7.496-10 2.576-10 1.656-10 5.306-10 1.916-09 2.716-06 1.526-05 

1E129M 5.19E-C6 1.856-06 8.226-07 1.716-06 1.366-05 4.766-04 4.916-05 

T6129 2.646-U 9.456-12 6.44C-12 1.936-11 6.94E-U 7.936-07 6.896-06 

T6131M 3.636-C8 1.606-08 1.37E-08 2.64E-08 1.086-07 5.5*6-05 8.326-05 

T5131 5.87E-12 2.28E-12 1.78C-12 4.596-12 1.59E-U 5.556-07 3.606-07 

TF132 1.306-07 7.366-08 7.126-08 8.586-08 4.796-07 1.026-04 3.726-05 

I 130 2.216-06 4.435-06 2.286-06 4.996-04 6.616-06 NO DATA 1.386-06 

I 131 1.306-05 1.306-05 7.376-06 4.396-03 2.l3e-05 NO DATA 7.636-07 

I 132 5.726-07 1.105-06 5.076-07 5.236-05 1.696-06 NO OATA 8.656-07 

I 133 4.48C-06 5.495-06 2.086-06 1.046-03 9.136-06 NO DATA 1.48E-06 

I 134 3.17E-07 5.845-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 

I 135 1.336-06 2.366-06 1.126-06 2.14C-04 3.626-06 NO DATA 1.20E-06 

CS134 1.766-04 2.746-04 6.076-05 NO OATA 8.936-05 3.276-05 1.04E-06 

CS136 1.766-05 4.626-05 3.14E-05 NO DATA 2.586-05 3.936-06 1.136-06 

CS137 2.456-04 2.235-04 3.476-05 NO OATA 7.63E-05 2.816-05 9.786-07 

CS138 1.716-07 2.276-07 1.506-07 NO DATA 1.686-07 1.84E-08 7.296-08 

BA139 4.98E-10 2.66F-13 1.45E-11 NO DATA 2.336-13 1.566-06 1.56E-05 

1.109-51 
P.58 

TABLE 6-9 , CONT'C 

PAGE 3 OF 3 

INHALATION DUS6 FACTORS FOR CHILO 

(MREM PER PCI INHALEO) 

NUCL IIUE 

I3A140 

BA141 

e.A14 2 

LA140 

LA142 

CE141 

CE143 

CE144 

PR143 

PR144 

NUL47 

W 187 

BUNE 

2.00E-05 

5.296-11 

1.356-11 

1.74E-07 

3.50E-10 

1.06E-05 

9.89E-08 

1.836-03 

4.996-06 

1.61E-11 

2.92E-06 

4.*.16-09 

LIV6R 

1.756-08 

2.956-14 

9.73C-15 

6.086-08 

I.116-10 

5.286-06 

5.376-08 

5.72E-04 

1.506-06 

4.996-12 

2.366-06 

2.61C-09 

T.BODY 

1.17E-06 

1.726-12 

7..4E-13 

2.04E-0 8 

3.49E-1 I 

7.83E-07 

7.77E-09 

9.776-05 

2.476-07 

8.106-13 

1.84F-0 7 

1.17F-09 

THYROIC 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

DATA 

CATA 

OATA 

OATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

KIDNEY 

5.716-09 

2.566-14 

7.376-15 

NO OATA 

NO OATA 

2.31E-06 

2.266-08 

3.176-04 

8.11t-07 

2.646-12 

1.30E-06 

NC DATA 

LUNG 

4.71E-04 

7.896-07 

4.446-07 

4.94E-05 

2.356-06 

1.47E-04 

3.12E-05 

3.23C-03 

L.17E-04 

4.23E-07 

8.876-05 

1.L1E-05 

GI-LLI 

2.75E-05 

7.44E-08 

7.41F-10 

6.10E-05 

2.05E-05 

1.53E-05 

3.44E-05 

1.05E-04 

2.63E-05 

5.32E-08 

2.22F-05 

2.466-05 

NP239 1.266-07 9.04 c

- 0 9 6.356-09 NO OATA 2.636-08 1.576-05 1.736-05 

1.109-52 
P.59 

TABLE E-10 

PAGE 1 OF 3 

INHALATION DOSE FACTORS FOR INFANT 

(MREM PER PCI INHAL6D) 

NUC 

H 

c • 

NA 

i» 

CR 

MN 

MN 

F6 

FE 

CO 

CO 

NI 

Nl 

CU 

ZN 

ZN 

BR 

HR 

RR 

RB 

'<B 

RB 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

:LIDE 

3 

14 

24 

32 

51 

54 

56 

55 

59 

58 

60 

6 3 

65 

64 

65 

69 

83 

84 

8a 

86 

88 

89 

89 

90 

91 

92 

90 

9li* 

91 

92 

NO 

I. 

7. 

L. 

NO 

NO 

NO 

1. 

9. 

NO 

NO 

2. 

1. 

NO 

I. 

3. 

NO 

NO 

NO 

NO 

NO 

NO 

2. 

2. 

6. 

7. 

2. 

2. 

4. 

1. 

B0N6 

DATA 

896-05 

546-06 

45E-03 

UATA 

OATA 

OATA 

41E-05 

69E-C6 

OATA 

OATA 

426-04 

71E-09 

DATA 

386-05 

ese-u 

OATA 

OATA 

OATA 

DATA 

UATA 

OATA 

84E-04 

92E-02 

836-08 

50E-09 

35E-06 

916-10 

206-04 

176-08 

4. 

3. 

7. 

8. 

NO 

1. 

1. 

8. 

1. 

8. 

5. 

1. 

2. 

1. 

4. 

6. 

NO 

NO 

NO 

1. 

3. 

2. 

NO 

NU 

NO 

NC 

NO 

NG 

NO 

NO 

LIV6R 

626-07 

79E-06 

54E-06 

036-05 

DATA 

816-05 

106-09 

39L-06 

685-05 

716-07 

736-06 

466-05 

03C-10 

346-09 

WF-0 5 

91E- U 

OATA 

UATA 

DATA 

36C-04 

986-07 

296-07 

DATA 

OATA 

OATA 

OATA 

DATA 

DATA 

DATA 

OATA 

T.BOCY 

4. 

3. 

7. 

5. 

6. 

3. 

1. 

2. 

6. 

1. 

8. 

8 

8. 

5 

2 

5 

2. 

2. 

1 

6. 

2 

1. 

8. 

1. 

2 

2 

6 

9 

I 

3 

626-

79E54E53E39E56C506-

386-

776-

306-

416-

296-

79E-

.536-

.226-

13E726-

866-

466-

306-

.OaE476-

15C856-

.476-

.796-

.306-

.906 

.126-

.29E 

-07 

-06 

-0 6 

-05 

-08 

-06 

-10 

-06 

-06 

-06 

-06 

-0 6 

-11 

-10 

-0 5 

-12 

-0 7 

-0 7 

-0 8 

-0 5 

-0 7 

-0 7 

-06 

-0 3 

-09 

-10 

-08 

-12 

-05 

-10 

THYROID 

4.62F-07 

3.796-06 

7.! 

NO 

4. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NQ 

NO 

546-06 

OATA 

116-08 

DATA 

OATA 

DATA 

OATA 

OATA 

DATA 

OATA 

OATA 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

DATA 

OATA 

OATA 

KIDN6Y 

4.626-07 

3. 

7.' 

NG 

9.' 

3.' 

7.1 

NO 

NO 

NO 

NO 

NO 

NO 

2. 

2. 

2 . 

NC 

NO 

NC 

NO 

NO 

NO 

NO 

NC 

NO 

NO 

NO 

NO 

NC 

NO 

79E-06 

54E-06 

OATA 

^56-09 

566-06 

366-10 

OATA 

DATA 

OATA 

OATA 

DATA 

OATA 

346-09 

326-05 

176-11 

DATA 

DATA 

DATA 

OATA 

DATA 

DATA 

DATA 

OATA 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

4. 

3. 

7. 

LUNG 

626-

796-

546-

-07 

-06 

-06 

NO DATA 

9. 

7. 

fl. 

6. 

7. 

5. 

3. 

1. 

5. 

6. 

4. 

1. 

176-

146-

95E-

-06 

-04 

-06 

21E-05 

256-

556-

-04 

•04 

22E-03 

496-

80E64E62E056-

-04 

-06 

-06 

-04 

-06 

NO OATA 

NO DATA 

NO DATA 

NO DATA 

NO OATA 

NC 

1. 

8. 

3. 

1. 

1. 

1. 

L. 

1. 

) OATA 

456-03 

03E766-

70E926-

99E756-

75E-

•03 

-05 

-05 

-04 

-06 

-03 

-05 

GI-LLI 

4 

3 

7 

1 

2 

5 

5 

7 

L 

7 

2 

L 

3 

1 

3 

9 

.626-

.796-

.546-

.L5E-

.556-

.04E-

.1?E-

.826-

.776-

.95E-

.286-

.736 

.58E-

.076-

.676-

.446-

LT 6-

LT E--

L

1 

2 

? 

4 

4 

9 

5 

1 

7 

1 

5 

9 

r 6-

. 17E-

.42E-

.87E-

.57E-

.366-

.246-

.006 

.436-

.686-

.02E-

.04E-

-07 

-06 

-06 

-05 

-07 

-06 

-05 

-07 

-05 

-06 

-05 

-06 

-05 

-05 

-05 

-06 

.4 

24 

24 

-06 

-07 

-08 

-05 

-05 

-05 

-04 

-05 

-06 

-05 

-05 

1.109-53 
TABLE E-10, CONT'D 

PAGE 2 OF 3 

INHALATION DCSE FACTORS FOR INFANT 

(MREM PER PCI INHALED) 

NUCLIDE BONE LIVER T.BOUY THYROID KIONEY LUNG GI-LLI 

Y 93 1.07E-07 NO OATA 2.9LE-09 NO DATA NO OATA 5.46E-05 1.19E-04 

ZR 95 8.24E-05 1.99E-05 L.45E-05 NO OATA 2.226-05 1.25E-03 1.55E-05 

ZR 97 L.07E-07 1.83E-08 8.36E-09 NO OATA 1.85E-08 7.88E-05 l.OOE-04 

NB 95 1.12E-05 4.596-06 2.70E-06 NO OATA 3.37E-06 3.42E-04 9.0SE-06 

MO 99 NO OATA 1.186-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 

TC 99M 9.98E-L3 2.06E-12 2.666-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 

TCLOL 4.656-14 5.88E-L4 5.80E-L3 NO OATA 6.99E-L3 4.17E-07 6.03E-07 

RU103 L.44E-06 NO OATA 4.85E-07 NO OATA 3.03E-06 3.94E-04 1.15E-05 

RU105 8.74E-10 NO OATA 2.93E-L0 NO DATA 6.42E-10 1.L2E-05 3.46E-05 

RU106 6.20E-05 NO OATA 7.77E-06 NO OATA 7.61E-05 8.26E-03 1.176-04 

AGIIOM 7.136-06 5.166-06 3.57E-06 NO OATA 7.80E-06 2.62E-03 2.366-05 

TEL25M 3.40E-06 1.42E-06 4.70E-07 L.16E-06 NO OATA 3.19E-04 9.22E-06 

TE127M 1.19E-05 4.93E-06 1.486-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 

TE12J7 1.59E-09 6.8LE-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 

TE12j?M 1.01E-05 4.35E-06 1.596-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 

TEL2|9 5.63E-U 2.48E-LL L.34E-LL 4.82E-11 1.25E-10 2.L4E-06 L.88E-05 

TE13!LM 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 L.42E-04 8.516-05 

TE131 L.24E-LL 5.87E-L2 3.57E-12 1.136-11 2.856-11 l.47E-r06 5.87E-06 

TE13I2 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 

1 130 4.54E-"06 9.9LE-06 3.986-06 1.146-03 L.09E-05 NO OATA 1.426-06 

I 13L 2.716-05 3.17E-05 L.40E-05 1.06E-02 3.706-05 NO OATA 7.56E-07 

I 132 1.21E-06 2.53E-06 8.99E-07 1.216-04 2.82E-06 NO OATA 1.36E-06 

I 133 9.46E-06 1.37E-05 4.00E-06 2.546-03 1.60E-05 NO OATA 1.54E-06 

I 134 6.58E-07 I.34E-06 4.756-07 3.18E-05 1.49E-06 NO OATA 9.21E-07 

I 135 2.76E-06 5.43E-06 1.986-06 4.97E-04 6.05E-06 NO OATA 1.31E-06 

CS134 2.83E-04 5.02E-04 5.32E-05 NO OATA 1.366-04 5.69E-05 9.53E-07 

CS136 3.45E-05 9.61E-05 3.78E-05 NO OATA 4.03E-05 8.40E-06 1.026-06 

CS137 3.92E-04 4.376-04 3.25E-05 NO OATA L.23E-04 5.09E-05 9.53E-07 

CSL3'8 3.6LE-07 5.58E-07 2.846-07 NO OATA 2.93E-07 4.67E-08 6.266-07 

BA139 1.06E-09 7.03E-L3 3.07E-LI NO OATA 4.23E-L3 4.25E-06 3.646-05 

1.109-54 
P.61 

TABLE E-LOt CONT'D 

PAGE 3 OF 3 

INHALATION DOSE FACTORS FOR INFANT 

(MREM PER PCI INHALED) 

NUCLIDE 

BAL40 

.A141 

HA142 

LA140 

LA142 

CE141 

CE143 

CE144 

PRL43 

PR 144 

ND147 

W 187 

BONE 

4.00E-05 

L.L2E-LO 

2.84E-LL 

3.61E-07 

7.36E-L0 

L.98E-05 

2.09E-07 

2.28E-03 

1.006-05 

3.42E-LI 

5.67E-06 

9.26E-09 

LIVER 

4.00E-08 

7.70E-14 

2.36E-14 

L.43E-07 

2.69E-10 

1.196-05 

1.386-07 

8.656-04 

3.746-06 

L.32E-L1 

5.8LF-06 

6.44E-09 

T.BOOY 

2.07E-06 

3.556-12 

1.406-12 

3.68E-08 

6.46E-U 

L.42E-06 

L.58E-08 

L.26E-04 

4.99E-07 

L.72E-12 

3.57E-07 

2.23E-09 

THYROID 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

KIONEY 

9.59E-09 

4.64E-L4 

1.36E-14 

NO OATA 

NO OATA 

3.756-06 

4.03E-08 

3.84E-04 

1.41E-06 

4.80E-12 

2.25E-06 

NO OATA 

LUNG 

1.14E-03 

2.126-06 

L.llE-06 

1.20E-04 

5.87E-06 

3.696-04 

8.30E-05 

7.03E-03 

3.09E-04 

1.L5E-06 

2.30E-04 

2.83E-05 

GI-LLI 

2.74E-05 

3.396-06 

4.95E-07 

6.06E-05 

4.25E-05 

1.54E-05 

3.55E-05 

L.06E-04 

2.66E-05 

3.066-06 

2.23E-05 

2.54E-05 

NP239 2.65E-5.0T 2.37E-08 1.34E-08 NO OATA 4.73E-08 4.25E-05 1.78E-05 

1.109-55 
TABLE E-ll 

PAGE 1 OF 3 

INGESTION OUSE FACTORS FOR ADULTS 

(MREM PER PCI INGESTED) 

NUCLICE 

H 

C 

NA 

P 

CR 

MN 

MN 

FE 

FE 

CO 

CO 

NI 

NI 

CU 

ZN 

ZN 

BR 

BR 

BR 

RB 

RB 

R8 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

3 

14 

24 

32 

5 1 I 

54 

56 

55 

59 

58 

60 

63 

65 

64 

65 

69 

83 

84 

85 

86 

88 

89 

89 

90 

91 

92 

90 

91M 

91 

92 

NO 

2. 

1. 

1. 

NO 

NO 

NO 

2. 

4. 

NO 

NO 

1. 

5. 

NO 

4. 

1. 

40 

NO 

NO 

NO 

NO 

NO 

3. 

.7. 

5. 

2. 

9. 

9. 

1. 

8. 

BONE 

DATA 

84E-06 

706-06 

93E-04 

DATA 

UATA 

OATA 

75E-06 

34E-06 

OATA 

OATA 

30E-C4 

28E-07 

OATA 

84E-06 

0 3E-08 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

08E-04 

58E-03 

67E-06 

ISE-06 

62E-09 

09E-LI 

41E-07 

45E-10 

I. 

5. 

1. 

1. 

NO 

4. 

1. 

1. 

1. 

7. 

2. 

9. 

6. 

8. 

1. 

1. 

NO 

NO 

NO 

2. 

6. 

4. 

NO 

NO 

NO 

NO 

NU 

NG 

NG 

NO 

LIVER 

05E-07 

68E-07 

70E-06 

20E-05 

CATA 

576-06 

15C-07 

90E-06 

02E-05 

45t_-07 

14F-06 

016-06 

86E-08 

33E-08 

545-05 

97E-08 

OATA 

OATA 

OATA 

115-05 

055-08 

016-08 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

CATA 

T.BODY 

1. 

5. 

1. 

7. 

2. 

8. 

2. 

4. 

3. 

1. 

4. 

4. 

3. 

3. 

6. 

1. 

4. 

5. 

2 

9 

3. 

2 

8 

1 

2. 

9 

2 

3 

3 

2 

05E686-

-0 7 

-0 7 

70E-06 

466-

6&E72E04E41E91E67E72C366-

136-

91E96E37F026-

216 

146 

.83E-

.216-

.826 

.846-

.866-

.296-

. 30E-

.586 

.52E 

.77E 

.476 

-06 

-09 

-0 7 

-0 8 

-0 7 

-06 

-06 

-06 

-06 

-0 8 

-08 

-06 

-09 

-08 

-08 

-09 

-06 

-08 

-08 

-06 

-0 3 

-0 7 

-08 

-10 

-12 

-09 

-IL 

THYROIO 

1.05E-07 

5.68E-07 

1. 

NO 

r0E-06 

OATA 

1.59E-09 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

OATA 

OATA 

OATA 

UATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

UATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

CATA 

OATA 

OATA 

KIDNEY 

l.l D5E-07 

5.68E-07 

1. 

NC 

5.1 

I. 

.OE-06 

OATA 

J6E-10 

366-06 

1.466-07 

NO 

NO 

NO 

NO 

NO 

NO 

2. 

L. 

I.. 

NO 

NO 

NC 

NO 

NO 

NO 

NO 

NO 

NC 

NC 

NG 

NO 

NO 

NO 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

106-07 

33E-05 

?8E-08 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

CATA 

DATA 

OATA 

OATA 

OATA 

LUNG 

1.05E-07 

5.68E-07 

1.70E-06 

NO OATA 

3.53E-09 

NO 

NO 

OATA 

OATA 

1.06E-06 

2.85E-06 

NO 

NO 

NO 

NO 

OATA 

OATA 

OATA 

OATA 

ND DATA 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

GI-LLI 

1. 

5. 

L 

2 

6 

L. 

3 

L 

3 

I 

4 

1 

I 

7 

9 

2 

5 

4 

.056-

.686-

• 70E-

.17E-

.69E-

.40E-

.67F-

.09E-

.40E-

.51E-

.026-

.88E-

.74E-

.10E-

.706-

.96E-

.796-

•0 

•0 

-0 

•0! 

-o-, 

•01 

-06 

-06 

-05 

-05 

-05 

-06 

-06 

-06 

-06 

-09 

-08 

.09E-13 

LT E-24 

4 

8 

2 

4 

2 

2 

4 

L 

2 

7 

L 

.166-

.366-

.33E-

.94E-

.19E-

.70E-

.26E-

.02E-

.67E-

.76E-

.486-

-06 

-19 

-21 

-05 

-04 

-05 

-05 

-04 

-10 

-05 

-05 

1.109-56 
P.63 

TABLE 6-ll t CONT'D 

PAGE 2 OT 3 

INGESTION DOSE FACTORS FCR ADULTS 

(MREM PhR PCI INGESTED) 

NUCLIDE 

Y 93 

ZR 95 

ZR 97 

NH 95 

MO 99 

TC 99M 

TCIOL 

1U103 

RU105 

RU106 

AGIIOM 

T6L25M 

TEL27M 

TE127 

TE129M 

T6129 

TE131M 

TE 13 L 

T 6132 

I 130 

I 131 

I 132 

1 133 

I 134 

I 135 

CS134 

CS136 

CS137 

CS138 

BA139 

BONE 

2.68E-C9 

3.04E-08 

1.68E-09 

6.22E-C9 

NO OATA 

2.476-10 

2.54E-10 

1.85E-07 

1.54E-08 

2^756-06 

1.606-07 

2.6.E-06 

6.77E-06 

1.106-07 

1.156-05 

3.146-08 

1.73E-06 

1.976-08 

2.526-06 

7.566-07 

4.165-06 

2.036-07 

1.426-06 

1.06C-07 

4.436-07 

6.226-05 

6.51E-06 

7.976-05 

5.526-08 

9.706-08 

LIVER 

NO OATA 

9.75E-C9 

3.395-10 

3.466-09 

4.316-06 

6.985-10 

3.666-10 

NO UATA 

NU CATA 

NO OATA 

1.48F-07 

9.716-07 

2.42C-06 

3.956-03 

4.?9C-C6 

1. 18E-08 

8.465-C7 

3.235-09 

1.63E-06 

2.2 35-06 

5.955-06 

5.43F-0? 

2.<t7E-06 

2.88C-07 

1. 165-06 

1.485-04 

2.575-05 

I.C9E-04 

1.C9E-07 

6.915-H 

T.BOCY 

7.40E-1 I 

6.606-09 

1.55E-10 

1.86E-0 9 

8.20E-07 

8.89E-09 

3.59E-09 

7.975-08 

6.036-09 

3.436-07 

8.796-0 8 

3.59C-07 

8.25C-07 

2.3H6-08 

1.826-06 

7.6.6-09 

7.056-07 

6.226-09 

1.5.6-06 

8.806-07 

3.41E-06 

1.90E-0 7 

7.536-0 7 

1.036-0 7 

4.23C-07 

1.21E-04 

1.856-05 

7.146-05 

5.406-08 

2.846-09 

THYR01C 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

8. 

1. 

8. 

3. 

2. 

1. 

1. 

1. 

1. 

1. 

1. 

3. 

4. 

7. 

NO 

NU 

NO 

NO 

NO 

OATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

DATA 

DATA 

DATA 

06F-07 

73E-06 

156-08 

95E-06 

41E-08 

346-06 

626-08 

8CE-C6 

89F-04 

956-C3 

90E-05 

636-04 

995-06 

65E-05 

OATA 

OATA 

OATA 

DATA 

OATA 

KIONEY 

NO DATA 

1.53E-08 

5.12E-10 

3.42E-C9 

9.766-06 

1.06E-08 

6.596-09 

7.066-07 

1.99E-07 

5.31E-06 

2.916-07 

1.096-05 

2.756-05 

4.486-07 

4.806-05 . 

1.32E-07 

8.576-06 

3.6 36-08 

1.576-05 

3.485-06 

1.02.-^5 

8.65.-07 

4.316-06 

4.586-07 

1.366-C6 

4.79t-05 

1.436-05 

3.70t-05 

8.01t-08 

6.466-U 

LUNG 

NO 

NO 

NO 

DATA 

CATA 

DATA 

NO OATA 

NO OATA 

3.426-10 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

1. 

1. 

1. 

7. 

3. 

37E-10 

DATA 

DATA 

DATA 

DATA 

CATA 

DATA 

OATA 

OATA 

CATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

595-05 

966-06 

236-05 

91E-09 

92E-U 

GI-LLI 

8.506-05 

3.096-05 

1.05E-04 

2.10E-05 

9.99E-06 

4.13E-07 

1.10E-21 

2.16E-05 

9.42E-06 

1.78E-04 

6.04E-05 

1.07F-05 

2.27E-C5 

8.68E-06 

5.79E-05 

2.37E-08 

8.40E-05 

2.79E-C9 

7.71E-05 

1.92E-06 

1.57E-06 

1.026-07 

2.226-06 

2.516-10 

1.316-06 

2.596-06 

2.92E-06 

2.UE-06 

4.65E-13 

1.72E-07 

1.109-57 
P.64 

TA..LF E-ll, CONT'D 

PAGE 3 OF 3 

INGESTION DnSE FACTORS FOR ADULTS 

(MR£K PLR PCI INGESTED) 

NUCLIl'E 

•I AL4 0 

r. A 14 I 

HA14 2 

LA14 0 

LA14 2 

_E14L 

-E14 3 

CE14 4 

PR 14 J 

PRI4 4 

N014 7 . 

V. 137 

BONE 

2.03C-C5 

4.71E-08 

2.13E-C8 

2.50C-09 

1.28E-10 

9.36E-09 

1.65E-09 

4.88E-07 

9.206-09 

3.015-11 

6.295-09 

1.036-07 

L IV6R 

2.555-08 

3. .65-11 

2.196-11 

1.265-09 

5.825-U 

6..35-09 

1.225-06 

2.C45-07 

3.695-09 

1.25.-11 

7._76-C. 

8.615-08 

T.ailDY 

1.336-06 

1.596-09 

1.346-09 

3.335-10 

1.456-11 

7.18E-IC 

1.356-10 

2.625-08 

4.566-»0 

1.5.6-12 

4.356-10 

3.01E-08 

THYROID 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

OATA 

OATA 

OATA 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

OATA 

KIONEY 

8.676-09 

3.316-11 

1.356-11 

NO DATA 

NC- DATA 

2.94E-09 

5.37E-10 

1.216-07 

2.136-09 

7.056-12 

4.256-09 

NO DATA 

LUNG 

1.466-08 

2.02E-U 

1.24E-U 

NO DATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

GI-LLI 

4.18E-05 

2.22E-17 

3.00E-26 

9.25E-05 

4.25E-07 

2.42E-05 

4.56E-05 

1.65E-04 

4.03E-05 

4.33E-18 

3.49E-05 

2.82E-05 

,.P239 1.19E-09 1.17C-10 6.45E-11 NO OATA 3.656-10 NO OATA 2.40E-05 

1.109-58 
P.65 

TABL6 6-12 

PAGE I OF 3 

INGESTION OOSE FACTORS FCR TEENAGER 

(MREM PER PCI INGESTED) 

NUCLID E 

II 

C 

MA 

r> 

CR 

."N 

MN 

F6 

FE 

CO 

CO 

JI 

Hi 

cu 

/N 

ZN 

f.9 

•_R 

»* 

i<8 

*8 

HB 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

I 

.3 

14 

24 

32 

51 

54 

56 

55 

59 

58 

60 

6 3 

65 

64 

65 

69 

83 

84 

85 

86 

83 

89 

89 

90 

91 

92 

90 

91M 

91 

92 

NO 

4. 

2. 

2. 

NU 

NO 

NO 

3. 

5. 

NO 

NO 

1. 

7. 

NO 

5. 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

4. 

8. 

8. 

3. 

1. 

1. 

2. 

1. 

BONE 

DATA 

06E-06 

30E-06 

76E-04 

OATA 

CATA 

UATA 

78E-06 

87E-06 

DATA 

DATA 

77E-04 

49E-07 

OATA 

76E-06 

47E-08 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

40E-04 

30E-03 

07E-06 

056-06 

376-08 

296-10 

016-07 

21E-09 

1. 

8. 

2. 

1. 

NO 

5. 

1. 

2. 

1. 

9. 

2. 

1. 

9. 

1. 

?. 

2. 

NO 

NO 

NO 

2. 

8. 

5. 

NO 

NO 

NO 

NO 

NO 

NO 

NU 

NO 

LIV6R 

065-07 

126-07 

306-06 

71C-05 

DATA 

905-06 

.8C-07 

68F-06 

J 76-05 

726-07 

61E-06 

25C-05 

576-08' 

156-07 

C0E-C5 

806-08 

OATA 

CATA 

OATA 

98E-05 

52E-08 

506-08 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

T.BOCY 

1. 

8. 

2. 

1. 

3. 

1. 

2. 

6. 

5 

2. 

6. 

6 

4. 

5. 

9. 

1 

5. 

7. 

3 

1 

4 

3 

I 

2 

3 

1 

3 

4 

5 

3 

06E-0 7 

126 

3CE076-

6Q6-

176-

816-

256-

296-

246-

336-

OOE36E 

416-

336-

966-

746 

226 

056 

.40E-

.54E89E 

.265 

.05E 

.216 

.306 

.696 

.936-

.396-

506 

-0 7 

-0 6 

-0 5 

-0 9 

-0 6 

-0 3 

-0 7 

-0 6 

-0 6 

-06 

-06 

-Ob 

-0 8 

-0 6 

-0 9 

-0 8 

-0 8 

-09 

-0 5 

-0 8 

-0 8 

-0 5 

-0 3 

-07 

-0 7 

-10 

-12 

-09 

-11 

THYROIU 

1.06C-07 

3. L2F-07 

2.306-06 

NO OATA 

2.006-09 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

OATA 

OATA 

DATA 

OATA 

OATA 

OATA 

DATA 

DATA 

DATA 

OATA 

DATA 

OATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

KIONEY 

1.06E-07 

3. 

2. 

NO 

L26-07 

306-06 

DATA 

7.396-10 

1. 766-06 

2.00E-07 

NG 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

UATA 

OATA 

OATA 

DATA 

2.916-07 

1.286-05 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NC 

NO 

NO 

ne-oa 

DATA 

DATA 

DATA 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

LUNG 

1.066-07 

8. 

2. 

NO 

5. 

NO 

NO 

1. 

4. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

MO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

L26-07 

30E-06 

OATA 

146-09 

DATA 

DATA 

70E-06 

32E-06 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

DATA 

DATA 

DATA 

CATA 

OATA 

DATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

GI-LLI 

1 

8. 

2. 

2. 

6. 

1. 

06E12F30E32E05E216-

1.046-

1.166-

3 .24E1.346-

3.66E1.99E5 .19E8.92E8.47E5 .16E-

-07 

-07 

-06 

-05 

-0 7 

-05 

-05 

-06 

-05 

-05 

-05 

-06 

-06 

-06 

-06 

-08 

LT E-24 

LT E-24 

LT E-24 

4 

7 

.416-

.306-

8.43F5 

2 

.246-

.336-

3.66E7 

1 

6 

77E-

. 13E-

.09E8.24E3.32E-

-06 

-15 

-17 

-05 

-04 

-05 

-05 

-04 

-09 

-05 

-05 

1.109-59 
TABLF E-12, CONT'D 

PAGE 2 OF 3 

INGESTIOiN OOSE FACTORS FOR TEENAGER 

(MREM PFR PCI INGESTEO) 

NUCL I 'JE 

Y 93 

ZK 95 

*R 97 

<. 95 

MO 99 

TC 99M 

TClOl 

RU103 

KU105 

RU106 

AGIIOM 

TE125<* 

TF127M 

TE127 

TE129M 

T6L29 

TElll" 

TF131 

IE132 

I 130 

I 131 

I 132 

I 13.3 

1 134 

I 135 

CSli4 

CS136 

CS137 

CS138 

3A139 

B0N6 

3.836-09 

4.126-08 

2.376-09 

3.22E-09 

NO DATA 

3.326-10 

3.60E-IC 

2.55E-07 

2.18E-08 

3.92E-06 

2.C5E-07 

3.33E-06 

9.67E-06 

1.58E-07 

1.636-05 

4.48E-03 

2.446-06 

2.796-08 

3.49E-06 

1.036-06 

5.856-06 

2.796-07 

2.016-06 

1.466-07 

6.106-07 

8.376-05 

8.596-06 

1.12E-04 

7.76E-08 

1.39E-07 

LIVER 

NO OATA 

1.30C-08 

4.695-10 

4.56.-09 

6.03E-06 

9.265-10 

5.125-10 

NU OATA 

NO UATA 

NO OATA 

1.946-07 

I.386-06 

3.4.E-06 

5.605-08 

6.056-06 

I.67F-08 

1.17C-06 

1.156-08 

2.21F-06 

2.986-06 

8.19C-06 

7.iCC-07 

3.416-06 

3.076-07 

1..7E-06 

1.976-04 

3..486-05 

1.49E-04 

1.496-07 

9.785-11 

T.BODY 

1.05E-10 

8.9«.6-09 

2.16E-10 

2.516-09 

1.15F-06 

1.206-08 

5.03E-09 

1.09E-0 7 

8.46E-09 

4.946-07 

1. 136-0 7 

5.12E-07 

1.15E-06 

3.40E-08 

2.58E-06 

1.09E-08 

9.76E-07 

3.72E-09 

2.06E-06 

1.19E-06 

4.40E-06 

2.62.E-0 7 

1.046-06 

1.396-07 

5.826-07 

9.146-05 

2.276-05 

5.19E-05 

7.45E-08 

4.05E-09 

THYROID 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

L. 

2. 

1. 

5. 

3. 

1. 

2. 

2. 

2. 

2. 

2. 

4. 

6. 

1. 

NO 

NO 

NO 

NO 

NO 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

0 76-06 

30E-06 

09F-07 

266-06 

20E-0S 

766-06 

15E-08 

33E-06 

4 3E-04 

39E-03 

466-05 

76E-04 

456-06 

016-04 

OATA 

OATA 

OATA 

OATA 

OATA 

KIDNEY 

NO DATA 

1.916-08 

7.UE-10 

4.42E-09 

1.38E-05 

I.386-08 

9.26E-09 

8.996-07 

2.75E-07 

7.56E-06 

3.70E-07 

NO DATA 

3.92E-05 

6.40E-07 

6.82E-05 

1.88.-07 

1.226-05 

1.226-07 

2.12E-05 

4.59E-06 

1.416-05 

1.156-06 

5.98E-06 

6.10E-07 

2.48E-06 

6.266-05 

1.846-05 

5.07E-05 

I.106-07 

9.226-11 

LUNG 

NO 

NO 

NO 

NO 

NO 

5. 

3. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

DATA 

OATA 

OATA 

DATA 

L4E-L0 

12E-10 

OATA 

OATA 

DATA. 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

NO OATA 

2.39E-05 

2.906-06 

L.< 

1.. 

6. 

J7E-05 

.8F-08 

74E-IL 

GI-LLI 

1.17E-04 

3.00E-05 

I.276-04 

1.95F-05 

1.08E-05 

6.08E-07 

. 8.75E-17 

2.13E-05 

L.76E-05 

1.88E-04 

5.45E-05 

I.L3E-05 

2.4LE-05 

L.22E-05 

6.12E-0S 

2.45F-07 

9.39E-05 

2.29C-09 

7.00E-05 

2.29E-06 

1.62E-06 

3.18E-07 

2.58E-06 

5.106-09 

1.74E-06 

2.45E-06 

2.72E-06 

2.12E-06 

6.76E-H 

I.24E-06 

1.109-60 
TABLE E-12, CONT'D 

PAGE 3 OF 3 

INGESTION OOSE FACTORS FOR TEFNAGFR 

(MREM PER PCI ING6STCD) 

P.67 

NUCLKC 

BA140 

BA14L 

.TA142 

LA140 

I.A142 

C6141 

CC143 

CF144 

PR143 

PR144 

N0147 

W 187 

BONE 

2.846-05 

6.71E-08 

2.99C-08 

3.485-09 

1.79C-10 

1.33E-08 

2.356-09 

6.966-07 

1.316-06 

4.306-11 

9.38C-09 

1.466-07 

LIVER 

3.485-03 

5.(!l5-ll 

2.996-11 

1.715-09 

7.956-11 

8.885-09 

1.715-06 

2.885-07 

5.235-09 

1.765-11 

1.02F-08 

1.195-07 

T.tJOCY 

1.8 36-0 6 

2.246-09 

1.846-09 

4.556-10 

1.98E-U 

1.026-09 

1.91E-10 

3.746-0 8 

6.52E-10 

2.18E-12 

6.11E-10 

4.17E-08 

THYROID 

NO 

NO 

JO 

NO 

NO 

NO 

NO 

NO 

NU 

NO 

NO 

NO 

OATA 

OATA 

DATA 

CATA 

OATA 

DATA 

UATA 

DATA 

DATA 

DATA 

OATA 

DATA 

KIDNEY 

1.186-08 

4.656-11 

2.53.-11 

NC OATA 

NO DATA 

4.186-09 

7.676-10 

1.726-07 

3.«4E-09 

1.01E-11 

5.991.-09 

NO OATA 

LU.NG 

2.346-08 

3.43E-11 

1.996-11 

NO DATA 

NO OATA 

NO DATA 

NO DATA 

NO OATA 

NO CATA 

NO OATA 

NO DATA 

NO CATA 

GI-LLI 

4.386-05 

1.436-13 

9.186-20 

9.826-05 

2.426-06 

2.546-05 

5.14E-05 

1.75F-04 

4.316-05 

4.74E-L4 

3.68E-05 

3.22E-05 

NP239 1.76E-09 I.665-10 9.226-11 *0 DATA 5.216-10 NO CATA 2.67E-05 

1.109-61 
P.68 

TABL5 6-13 

PAGE 1 OF 3 

INGESTION DOSE FACTORS FOR CHILD 

(MREM PER PCI INGESTED) 

NUCLIUE 

H 3 

C 14 

NA 24 

P 32 

CR 51 

MN 54 

BONF 

NO OATA 

1.21E-05 

5.80E-06 

8.25E-04 

NO OATA 

NO OATA 

LIVER 

2.036-07 

2.*2E-06 

5.806-06 

3.865-05 

NO CATA 

1.076-05 

T.BOUY 

2.036-07 

2.42E-06 

5.80E-06 

3.18E-05 

8.90E-09 

2.85E-06 

THYROIO 

2.03E-07 

2.42E-06 

5.806-06 

NO DATA 

4.94E-09 

NO OATA 

KIONEY 

2.03E-07 

2.42E-06 

5.806-06 

NO OA.TA 

1.35E-09 

3.00E-06 

LUNG 

2.03E-07 

2.42E-06 

5.80E-06 

NO DATA 

9.02E-09 

NO DATA 

GI-LLI 

2.03E-07 

2.42E-06 

5.80E-06 

2.28E-05 

4.726-07 

8.98E-06 

MN 56 

FE 55 

FE 59 

CO 

CO 

58 

60 

MI 63 

NI 

CU 

ZN 

ZN 

BR 

BR 

65 

64 

65 

69 

8 3 

84 

BR 8. 

KB 86 

RB 88 

NO OATA 

1.156-05 

1.656-05 

3.34E-07 

6.10E-06 

2.6 7E-05 

7.54E-08 

1.896-06 

1.33E-05 

NO DATA 

NO DATA 

NO OATA 

4.04E-07 

NO OATA 

NO DATA 

NO OATA 

3.45E-06 

7.74E-06 

4.846-05 

1.13E-06 

2.78E-05 

NO OATA 

NO DATA 

5.38E-C4 

1.80E-06 

5.29F-06 

2.886-05 

5.51E-0 6 

1.566-05 

1.83E-05 

NO OATA 

NO DATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO OATA 

NO DATA 

NO DATA 

2.22E-06 

NO OATA 

1.376-05 

2.09F-07 

2.456-07 

3.O56-05 

1.226-07 

1.48E-0 7 

2.27E-05 

NO DATA 

NO OATA 

NO DATA 

NO OATA 

5.92E-07 

2.30E-05 

NO OATA 

NO DATA 

NO OATA 

4.385-08 

NO OATA 

NO DATA 

6..3E-08 

NO OATA 

NO OATA 

5.85E-09 

1.71E-07 

1.986-07 

NO DATA 

NO DATA 

NO DATA 

3.84E-08 

NO DATA 

NO DATA 

NO DATA 

NO DATA 

NO OATA 

NO DATA 

NO OATA 

NO DATA 

NO DATA 

6.706-05 

1.90E-07 

9.12E-09 

4.12E-05 

1.32E-07 

NO DATA 

NO OATA 

NO DATA 

NO DATA 

NO DATA 

NO DATA 

NO DATA 

NO OATA 

NO OATA 

1.05E-05 

2.93E-05 

1.94E-06 

2.56E-05 

1.15E-05 

6.41E-06 

3.99E-06 

LT E-24 

LT E-24 

LT E-24 

4.31F-06 

9.32C-09 

RB 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

|89 

89 

90 

91 

92 

90 

9 IK 

91 

92 

NO DATA 

1. 

1. 

2 

9. 

4. 

3 

6 

3 

326-

70E40E036-

116-

82E02E60E-

-03 

-02 

-05 

-06 

-08 

-10 

-07 

-09 

1. 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

L76-07 

OATA 

UATA 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

1 

3 

4 

9 

3 

1 

1 

1 

1 

046-

.776-

.316-

066-

.626-

.106-

.39E-

.61F-

.03E-

-0 7 

-0 5 

-0 3 

-0 7 

-0 7 

-0 9 

-11 

-0 8 

-10 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

DATA 

OATA 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

DATA 

OATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

1 

5 

2 

5 

I 

1 

7 

8 

I 

026-

.UE-

.29E-

.30E-

.7LE-

. 17E-

.48E-

.02E-

.04E-

-09 

•05 

-04 

-05 

-04 

-04 

-07 

-05 

-04 

1.109-62 
P.69 

TABLE E-13, CONT'D 

PAGE 2 OF 3 

INGESTION OOS6 FACTORS FOR CHILD 

(MR6M Pfi. PCI INC6STED) 

NUCLICE BONE LIVER T.30UY THYROID KIDNEY LUNG GI-LLI 

Y 93 1.14C-C8 NO OATA 3.13C-10 NO OATA NO DATA NO OATA 1.70E-04 

ZR 95 1.166-07 2..5E-08 2.276-08 NO OATA 3.65E-08 NO DATA 2.666-05 

ZR 97 6.996-09 1.01E-09 5.966-10 NO UATA 1.45E-09 NO OATA 1.53E-04 

NR 95 2.25E-08 8.76E-09 6.26E-09 NO OATA 8.236-09 NO OATA 1.62E-05 

MO 99 NO DATA 1.336-05 3.296-06 NO OATA 2.846-05 NO OATA 1.10E-05 

TC 99M 9.23E-10 1.81E-09 3.006-08 NO DATA 2.636-08 9.196-10 1.036-06 

TClOl 1.076-09 1.126-09 1.425-08 NO DATA 1.9U-08 5.92E-10 3.566-09 

RU103 7.316-07 NO DATA 2.816-07 NO OATA 1.846-06 NO DATA 1.89E-05 

f.UlOS 6.45E-08 NO DATA 2.34E-08 NO OATA 5.676-07 NO OATA 4.21E-05 

KUL06 1.17E-.05 NO DATA 1.466-06 NO DATA 1.586-05 NO DATA 1.82E-04 

AGIIOM 5.396-07 3.64C-07 2.91E-07 NO OATA 6.786-07 NO OATA 4.33E-05 

TF125M I.146-05 3.09E-06 1.52E-06 3.20E-06 NO OATA NO OATA I.106-05 

TE127M 2.896-05 7.786-06 3.43E-06 6.916-06 8.246-05 NO OATA 2.34E-05 

TF127 4.71E-07 1.27F-07 1.01E-07 3.26E-07 1.346-06 NO DATA 1.84E-05 

TE129" 4.876-05 1.366-05 7.566-06 1.576-05 1.436-04 NO OATA 5.94E-05-

TE129 1.346-07 3.74E-08 3.186-08 9.566-08 3.926-07 NO DATA 8.346-06 

T6131H 7.206-06 2.496-06 2.656-06 5.126-06 2.41E-05 NO CATA 1.01E-04 

TE1.31 8.30E-08 2.536-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 

T6132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 

I 130 2.92E-06 5.90E-06 3.046-06 6.506-04 8.826-06 NO OATA 2.766-06 

I 131 1.726-05 1.73E-05 9.836-06 5.72E-03 2.846-05 NO OATA 1.546-06 

I 132 8.00E-07 I.475-06 6.76E-07 6.82E-05 2.256-06 NO DATA 1.736-06 

I 133 5.926-06 7.326-06 2.776-06 1.366-03 1.22E-05 NO DATA 2.956-06 

I 134 4.196-07 7.786-07 3.586-07 1.796-05 1.196-06 NO DATA 5.166-07 

I 135 1.756-06 3.15E-06 1.49E-06 2.79E-04 4.836-06 NO DATA 2.406-06 

CS134 2.346-04 3.84C-04 8.10E-05 NO DATA 1.19E-04 4.276-05 2.07E-06 

CS136 2.35E-05 6.466-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 

CS137 3.27E-04 3.13C-04 4.62E-05 NO OATA 1.026-C4 3.67E-05 1.96E-06 

CS138 2.28E-07 3.17E-07 2.01E-07 NO OATA 2.236-07 2.40E-08 1.46E-07 

3A139 4.14E-07 2.21E-10 1.20E-08 NO OATA 1.936-10 1.30E-10 2.39E-05 

1.109-63 
TA6LC E-13, C0N1'0 

P4G6 3 OF 3 

INGESTION DOSE FACTORS FOR CHILD 

(MREM PER PCI INGESTED) 

P.70 

NUCLI HE 

RA.140 

_A14_ 

0A142 

LA 140 

LA142 

CE141 

CE143 

CE144 

PR143 

PR144 

N0147 

W 187 

BONE 

8.J1E-05 

2.00E-07 

8.746-08 

1.01E-08 

5.24E-10 

3.97E-08 

6.99C-09 

2.08E-06 

3.93E-08 

1.29C-10 

2.79E-08 

4.29E-07 

LIVER 

7.285-08 

1.125-10 

6.29E-U 

.3. 53E-09 

1.67F-10 

1.985-08 

3.79E-06 

6.525-07 

1. 18C-08 

3.996-11 

2.266-08 

2.545-07 

T.dODY 

4.856-06 

6.516-09 

4.88E-09 

1.19E-09 

5.23E-11 

2.945-09 

5.49E-10 

l.UE-07 

1.95E-09 

6.496-12 

1.75E-09 

1.14E-07 

THYROID 

NO 

NO 

NO 

•JO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NU 

DATA 

OATA 

OATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

DATA 

KIDNEY 

2.37L-08 

9.696-11 

5.09E-U 

NC DATA 

NO DATA 

8.68E-09 

1.596-09 

3.616-07 

6.396-09 

2.116-11 

1.246-08 

NO DATA 

LUNG 

4.346-08 

6.586-10 

3.705-11 

NO OATA 

NO DATA 

NO OATA 

NO DATA 

NO OATA 

NO DATA 

NO DATA 

NO DATA 

NO DATA 

GI-LLI 

4.216-05 

1.146-07 

1.146-09 

9.846-05 

3.316-05 

2.476-05 

5.55C-05 

1.706-04 

4.246-05 

8.596-08 

3.58E-05 

3.57E-05 

NP239 5.256-09 3.776-10 2.656-10 NO DATA 1.096-09 NO DATA 2.796-05 

1.109-64 
P.71 

TABLE E-14 

PAGE 1 OF 3 

INGESTION OOSE FACTORS FOR INFANT 

(MREM PER PCI INGESTED) 

NUCLIDE 

H 

C 

NA 

P 

CR 

MN 

MN 

FE 

FF 

CO 

CO 

NI 

NI 

CU 

ZN 

ZN 

UR 

bR 

BR 

RB 

KB 

RC 

SR 

SR 

SR 

SR 

Y 

Y 

Y 

Y 

3 

14 

24 

32 

51 

54 

56 

55 

59 

58 

60 

63 

65 

64 

65 

69 

83 

84 

85 

86 

88 

89 

89 

90 

9L 

92 

90 

9LM 

91 

92 

NO 

2. 

1. 

1. 

NO 

NO 

NO 

I. 

3. 

NO 

NO 

6. 

4. 

NO 

1. 

9. 

NO 

NO 

NO 

NO 

NO 

NO 

2. 

1. 

5. 

1. 

8. 

8. 

1. 

7. 

BONE 

OATA 

37E-05 

01E-05 

70E-03 

OATA 

OATA 

OATA 

39E-05 

08E-05 

DATA 

OATA 

34E-04 

70E-06 

OATA 

34E-05 

33E-08 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

5LE-03 

05E-02 

00E-C5 

92C-05 

69E-08 

10E-1C 

13E-06 

65E-09 

3. 

5. 

1. 

1. 

NO 

1. 

8. 

8. 

5. 

3. 

1. 

3. 

5. 

6. 

6. 

1. 

MO 

NO 

NO 

I. 

4. 

2. 

NO 

NU 

NU 

NO 

NU 

NO 

NO 

NO 

LIVER 

086-07 

06E-06 

01C-05 

00E-04 

OATA 

99E-05 

18E-07 

98E-06 

386-05 

60E-06 

086-05 

926-05 

32E-07 

096-07 

316-05 

686-07 

OATA 

DATA 

DATA 

705-04 

986-07 

866-07 

OATA 

DATA 

DATA 

OATA 

DATA 

DATA 

OATA 

OATA 

3 

5 

1 

6. 

1. 

4. 

1. 

2. 

2. 

8. 

2. 

2. 

2 

2 

2. 

1 

3 

3 

1 

8. 

2 

1 

7 

4 

1 

7 

2 

2 

3 

2 

T.BOUY 

.086-

.066-

.OlE-

.59E-

.41E-

.51E41E-

.4CE-

.12E93E55E-

.20E-

.426-

.82E-

.91E-

.25E-

.63E-

.82E-

.94E-

.40E-

.73E-

.97E-

.20E-

.71E-

.81E-

.136-

.3JE-

. 76E-

.OlE-

. 15E-

-0 7 

-06 

-0 5 

-0 5 

-0 8 

-06 

-0 7 

-06 

-0 5 

-06 

-0 5 

-0 5 

-0 7 

-0 7 

-0 5 

-0 8 

-0 7 

-0 7 

-0 8 

-0 5 

-0 7 

-0 7 

-0 5 

-0 3 

-06 

-0 7 

-09 

-11 

-08 

-10 

THYROID 

3.08E-07 

5.06E-06 

L.01E-05 

NO OATA 

9.20E-09 

NO 

NU 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

UATA 

OATA 

OATA 

DATA 

OATA 

OATA 

DATA 

DATA 

DATA 

DATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

KIONEY 

3. 

5.1 

l.l 

NO 

2.1 

386-07 

366-06 

31E-05 

OATA 

3LE-09 

4.41E-06 

7.1 

NO 

NO 

NO 

NC 

NO 

NO 

l.l 

3.1 

6.' 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

3 36-07 

DATA 

OATA 

DATA 

OATA 

DATA 

OATA 

33E-06 

36E-05 

J8E-08 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

1 

3.1 

LUNG 

38E-07 

5.06F-06 

l.OLE-05 

NO OATA 

1.79E-08 

NO 

NO 

4. 

1.' 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

CATA 

OATA 

39E-06 

59E-05 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

DATA 

DATA 

OATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

GI-LLI 

3 

5. 

1. 

2. 

4. 

7 

7, 

I 

2 

8. 

2. 

L 

4 

1 

5 

I 

.08E-

.06E-

.01E-

.30E-

.HE-

.31E-

.43E-

.14E-

.576-

.97E-

.57E-

.95E-

.05E-

.25E-

.33E-

.37FLT E-. 

-07 

-06 

-05 

-05 

-07 

-06 

-05 

-06 

-05 

-06 

-05 

-06 

-05 

-05 

-05 

-05 

24 

LT E-24 

LT E-. 

4 

4 

9 

5 

2 

5 

2 

I 

2 

8 

I 

.35E-

.85F-

.74E-

.166-

.31E-

.92E-

.07E-

.20E-

.706-

.106-

.466-

24 

-06 

-07 

-08 

-05 

-04 

-05 

-04 

-04 

-06 

-05 

-04 

1.109-65 
• > • 

TABLE 6-14 , CONT'O 

PAGE 2 OF 3 

ING6STION UOSE FACTORS FOR INFANT 

(MREM PER PCI INGESTED) 

NUCLIDE 

Y 9 3 

ZR 95 

ZR 97 

.B 95 

MO 99 

TC 99M 

TClOl 

RU103 

RU105 

RU106 

AGIIOM 

TE125M 

TE127M 

TE127 

TE129M 

TE129 

TE131M 

TE131 

TE132 

I 130 

I 131 

I 132 

I 133 

I 134 

I 135 

CS134 

CS136 

CS137 

CSI 38 

BA139 

BONE 

2.43E-08 

2.06E-07 

1.48E-08 

4.20E-08 

NO OATA 

1.926-09 

2.27E-09 

1.48E-06 

1.36E-07 

2.41E-05 

9.96E-07 

2.33E-05 

5.85E-05 

l.OOE-06 

1.00E-04 

2.84E-07 

1.52E-05 

1.76E-07 

2.08E-05 

6.006-06 

3.59E-05 

1.666-06 

1.256-05 

8.69E-07 

3.64E-06 

3.77E-04 

4.59E-05 

5.22E-04 

4.816-07 

8.81E-07 

LIVER 

NO DATA 

5.02E-08 

2.54E-09 

1.73E-08 

3.405-05 

3.965-09 

2.86E-09 

NO UATA 

NO OATA 

NO DATA 

7.275-07 

7.79C-06 

1.946-05 

3.35E-07 

3.435-05 

9.79E-08 

6.12E-06 

6.50E-08 

1.03E-05 

1.32E-05 

4.236-05 

3.37E-06 

1.825-05 

1.785-06 

7.245-06 

7.035-04 

1.356-04 

6.116-04 

7.826-07 

5.84E-10 

T.OOOY 

6.62E-10 

3.56E-08 

1.16E-09 

1.00E-08 

6.636-06 

5.106-08 

2.8 36-0 8 

4.95E-07 

4.58E-08 

3.016-06 

4.81E-07 

3.15E-06 

7.08E-06 

2.15E-07 

1.54E-05 

6.63E-08 

5.05E-06 

4.94E-0 8 

9.61E-06 

5.30E-06 

1.866-05 

1.20E-06 

5.33E-06 

6.33E-07 

2.64E-06 

7.10E-05 

5.04E-05 

4.336-05 

3.79E-07 

2. 556-08 

THYROIO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

7. 

1. 

8. 

3. 

2. 

1. 

1. 

1. 

1. 

1. 

1. 

3. 

4. 

6. 

NO 

NO 

NO 

NO 

NO 

OATA 

OATA 

OATA 

OATA 

DATA 

OATA 

DATA 

DATA 

OATA 

OATA 

OATA 

84E-06 

69E-05 

14E-07 

84E-05 

386-07 

246-05 

576-07 

526-05 

48E-03 

396-02 

58E-04 

316-03 

155-05 

496-04 

OATA 

UATA 

DATA 

OATA 

OATA 

KIONEY 

NO OATA 

5.41E-08 

2.56E-09 

I.246-08 

5.08E-05 

4.26E-08 

3.40E-08 

3.08E-06 

l.OOE-06 

2.85E-05 

1.04E-06 

NO DATA 

1.44E-04 

2.446-06 

2.506-04 

7.076-07 

4.216-05 

4.506-07 

6.44E-05 

1.456-05 

4.94E-05 

3.76E-06 

2.14E-05 

1.99E-06 

3.07E-06 

1.81E-04 

5.38E-05 

1.64E-04 

3.90E-07 

3.51E-10 

LUNG 

NO 

NO 

NO 

OATA 

OATA 

OATA 

NO OATA 

NO OATA 

2.07E-09 

1.! 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

7.' 

6. 

6. 

3. 

56E-09 

DATA 

DATA 

OATA 

OATA 

OATA 

DATA 

OATA 

DATA 

OATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

DATA 

DATA 

OATA 

V2E-05 

10E-05 

54E-05 

09E-08 

54E-10 

GI-LLI 

1.92E-04 

2.50F-05 

1.62E-04 

1.46E-05 

1.12E-05 

1.15E-06 

4.86E-07 

1.80E-05 

5.41E-05 

1.83F-04 

3.77E-05 

1.11E-05 

2.36E-05 

2.10ET0 5 

5.97E-05 

2.27E-05 

1.03E-04 

7.11E-06 

3.81E-05 

2.83E-06 

1.51E-06 

2.73E-06 

3.08E-06 

1.84E-06 

2.62E-06 

1.91E-06 

2.05E-06 

1.91E-06 

1.25E-06 

5.58E-05 

1.109-66 
TABLE 6-14, CONT'D 

PAG6 3 OF 3 

INGESTION OOSE FACTORS FOR INFANT 

(MR6M P6K PCI ING6ST6DI 

P.73 

NUCLILSE 

3A14U 

RA141 

BA142 

LA140 

LA142 

CE141 

C6143 

C6144 

PR 143 

PR 144 

MO 147 

V. 187 

BONE 

1.716-04. 

4.25E-07 

1.84E-07 

2.11E-08 

1.10E-09 

7.87E-08 

1.48E-08 

2.985-06 

8.13E-08 

2.74C-10 

5.536-08 

9.03E-07 

LIVER 

1.71E-07 

2.915-10 

1.536-10 

8.325-09 

4.046-10 

4.805-08 

9.82E-06 

1.226-06 

3.C4E-08 

1.066-10 

5.686-08 

6.286-07 

T..3C0Y 

8.816-06 

1.346-0 8 

9.066-09 

2.146-09 

9.6/6-11 

5.65E-09 

1.12E-09 

1.67E-07 

4. 0.3E-09 

1.386-11 

3.486-09 

2.176-07 

THYROID 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

NO 

DATA 

OATA 

DATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

OATA 

KIDN6Y 

4.066-08 

1.75E-10 

8.81E-11 

NO OATA 

NC DATA 

1.48E-08 

2.866-09 

4.93E-07 

1.136-08 

3.846-11 

2.196-08 

NO DATA 

LUNG 

1.056-07 

1.776-10 

9.266-11 

NO DATA 

NO OATA 

NO DATA 

NO DATA 

NO OATA 

NO OATA 

NO OATA 

NO DATA 

NO OATA 

GI-LLI 

4.20E-05 

5.19E-06 

7.596-07 

9.776-05 

6.866-05 

2.48E-05 

5.73E-05 

1.71E-04 

4.29E-05 

4.93E-06 

3.60E-05 

3.69E-05 

NP239 l.UE-08 9.936-10 5.616-10 NO DATA 1.98E-09 NO OATA 2.87E-05 

1.109-67 
1.109-68 

* 

Parameter 

Symbol 

fg 

ft 

p 

r 

SF 

S 

\ 

*f 

* 

Parameter 

TABLE E-15 

RECOMMENDED VALUES FOR OTHER 

Definition 

Fraction of produce Ingested grown in garden of interest 

Fraction of leafy vegetables grown In garden of Interest 

Effective surface density of soil (assumes a 15 cm plow 

layer, expressed In dry weight) 

Fraction of deposited activity retained on crops, leafy 

vegetables, or pasture grass 

Attenuation factor accounting for shielding provided by 

residential structures 

Period of long-term buildup for activity in sediment or 

soil (nominally 15 yr) 

Period of crop, leafy vegetable, or pasture grass 

exposure during growing season 

Transport time from animal feed-milk-man 

values given without references are based on staff judgments. 

'v. 

PARAMETERS^ 

Equation(s) 

Where Used 

14 & C-13 

14 & C-13 

4. A-8, A-13, & 

4, A-8, & A-13 

C-5 

C8, 9, 10, 11, 12, 

B-6, B-7, B-8, B-i 

& C-2 

3, 4, A-4, A-5, 

A-7, A-8, A-13, 

4, A-8, A-13, & 

C-10 

_-^ 

A-

& 

C-

-5 

), 

• 6 , 

C-5 

-5 

Values Referenced )* 

0.76 

1.0 

240 kg/m2 

0.25 

1.0 (for iodines) 

0.2 (for other 

particulates) 

0.7 (for maximum 

individual) 

0.5 (for general 

population) 

1.31 x IO5 hr 

720 hrs (30 days, 

for grass-cow-milkman pathway) 

1440 hrs (60 days, 

for crop/vegetationman pathway) 

2 days (for maximum 

individual) 

4 days (for general 

population) 

— 

— 

10 

27 

2. 4, 13, 

28-31 

26 

26 

— 

10 & 32 

— 

~ - " 

**» 
TABLE E-15 (Continued) 

o 

IO Ol 

ID 

Parameter 

Symbol Definition 

Time delay between harvest of vegetation or crops and 

ingestion 

i) For ingestion of forage by animals 

ii) For ingestion of crops by man 

Environmental transit time, release to receptor 

(add time from release to exposure point to 

minimums shown for distribution) 

Average time from slaughter of meat animal to 

consumption 

Agricultural productivity by unit area (measured 

in wet weight) 

Rate constant for removal of activity on plant or leaf 

surfaces by weathering (corresponds to a 14-day half-life) 

Equation(s) 

Where Used 

4, A-8, A-13, & C-5 

4, A-8, A-13, & C-5 

1 & A-2 

2 & A-J 

3 & A-7 

C-12 

4, A-8, A-13, & C-5 

Values Reference(s)' 

Zero (for pasture 

grass) 

2160 hr (90 days for 

stored feed) 

24 hr (1 day, for 

leafy vegetables & 

maximum individual) 

1440 hr (60 days, for 

produce & maximum 

individual) 

336 hr (14 days, for 

general population) 

12 hr (for maximum 

individual) 

24 hr (for general 

population) 

24 hr (for maximum 

individual) 

168 hr (7 days for 

population sport 

fish doses) 

240 hr (10 days for 

population commercial fish doses 

Zero 

20 days 

0.7 kg/m (for grasscow-milk-man pathway) 

o 

2.0 kg/m (for produce 

or leafy vegetables , 

ingested by man) 

0.0021 hr"1 

33 

34 

Parameter values given without references are based on staff judgments. 
• . • . * 

REFERENCES FOR APPENDIX E 

1. Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear 

Devices, Handbook for Estimating the Maximum Internal Dose from Radionuclides Released 

to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968. 

2. B. H. Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk around Three 

Operating Reactor Sites," Environmental Surveillance Around Nuclear Installations, International Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. I: pp. 169-190, 1974. 

3. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1-131 

in Milk and the Subsequent Dose to the Thyroid," Institute fiir Reaktorsicherheit, Cologne, 

West Germany, IRS-W-6, June 1973. 

4. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1-131 Dose 

to the Thyroid," Institute fiir Reaktorsicherheit, Cologne, West Germany, IRS-W-5, April 

1973. 

5. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport 

of 1-131 from Air to M1lk," Institute fiir Reaktorsicherheit, Cologne, West Germany, IRS-W-13, 

April 1975. 

6. 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. 

7. R. J., Garner and R. S..Russel, Radioactivity and Human Diet, R. Scott Russel (ed.), Pergamon 

Press^ Oxford, England, 1966. 

8. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1-131 

and Cs-137 to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969. 

9. J. D. Zimbrick and P. G. Voilleque (eds.), "1967 CERT Progress Report," USAEC Report 

100-12067, p. 36, 1968. 

10. J. F. Fletcher and W. L. Dotson (compilers), "HERMES - A Digital Computer Code for Estimating 

Regional Radiological Effects from the Nuclear Power Industry," USAEC Report HEDL-TME-71-168, 

Hanford Engineering Development Laboratory, 1971. 

11. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (pCi/m ),"" Item 04.3.4 

in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, 

Hanford Laboratories, 1962. 

12. "Permissible Dose from External Sources of Ionizing Radiation," Handbook 59, U.S. Dept. of 

Commerce, 1954. 

13. 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 C0NF-710501, Oak Ridge, Tenn., pp. 877-893, 1971. 

14. D. S. Altman and P. L. Altman (eds.), "Metabolism," Federation of American Societies for 

Experimental Biology, Bethesda, Md., 1968. 

15. R. J!. Garner, "Transfer of Radioactive Materials from the Terrestrial Environment to Animals 

and Man," CRC Press, Cleveland, Ohio, 1972. 

16. J. K. Soldat et al., "Models and Computer Codes for Evaluating Radiation Doses," USAEC 

Report BNWL-1754, Pacific Northwest Laboratories, February 1974. 

17. A. L. Rogers, "Goat Keeping in the United States," International Dairy Goat Conference, 

London, July 1964. 

18. R. G. Bond and C. P. Straub (eds.), Handbook of Environmental Control, Vol. Ill, "Water 

Supply and Treatment," CRC Press, Cleveland, Ohio, 1975. 

1.109-70 
P.77 

r .-

19. "Food Consumption, Prices, and Expenditures," AER-138, U.S. Department of Agriculture, 

Washington, D.C , December 1974. 

20. "Report of the Task Group on Reference Man," ICRP Publication 23, Pergamon Press, Oxford, 

England, 1975. 

21. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for 

Radiological Calculations," HW-41638, General Electric Co., Richland, Wash., February 1956. 

22. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption -

Some Preliminary Findings of the 1969 Consumer Panel Survey," NMFS Circular 361, USDC/NOAA, 

Seattle, Wash., June 1971. 

23. "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. 

24. "Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, 

Washington," USAEC Report WASH-1528, Washington, D.C , September 1974. 

25. G. R. Hoenes and J. K. Soldat, "Age-Specific Radiation Dose Commitment Factors for a One 

Year Chronic Intake," USNRC Report NUREG-0172, to be issued in 1977. A draft is available 

in the Public Document Room. 

26. Z. G. Burson and A. E. Profio, "Structural Shielding from Cloud and Fallout Gamma Ray Sources 

for Assessing the Consequences of Reactor Accidents," EG&G-l183-1670, Las Vegas, Nev., 1975. 

27. D. A. Baker et al., "FOOD - Arx Interactive Code to Calculate Internal Radiation Doses from 

Contaminated Food Products," BNWL-SA-5523, February 1976. 

28. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two," 

USAEC Report IDO-12063, January 1968. 

29. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the' 

National Reactor Testing Station, Progress Report Number Four," USAEC Report IDO-12065, 

December 1968. 

30. C. A. Pelletier and P. G. Voilleque, "The Behavior of Cs-137 and Other Fallout Radionuclides 

on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971. 

31. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consumption 

of Cow's Milk as Critical Pathways for Cs-137, Mn-54 and Pr-144 Released to the Atmosphere," 

Health Phys., Vol. 27, p. 189, 1974. 

32. J. J. Koranda, "Agricultural Factors Affecting'the Daily Intake of Fresh Fallout by Dairy 

Cows," USAEC Report UCRL-12479, 1965. 

33. M. E. Heath et al., Forages, the Iowa State University Press, Ames, Iowa, 1973. 

34. "Statistical Abstract of the United States," U.S. Bureau of the Census, 93rd-Edition, 1972. 

1.109-71 
v ••. ^ 

APPENDIX F 

METHODS FOR EVALUATING THE I FUNCTION 

The NRC staff calculates ground-level gamma radiation doses from elevated noble gas releases 

using Equation (6) in Regulatory Position C.2.a of this guide. Equation (6) is based on the 

model presented in Slade (Ref. 1), which can be characterized as a vertically finite sectoraveraged Gaussian plume model. Use of the model involves volume integration over a distributed 

source,J)resulting in certain integrals that define the I function, denoted by IT in Reference 1. 

1. Derivation of the I Function 

The derivation of the I function presented below is taken directly from Reference 1, which 

should be consulted for further details. 

The sector-average airborne radionuclide concentration resulting from a continuous release 

is. given by the Gaussian plume model as (see Equation 7.60 of Ref. 1): 

where 

x(R,z) 

/27 o uRe 

<exp j^M-v1

. 

(F-l) 

R 

H 

x"(R,z) 

z 

e 

Is the effective release height, in meters; 

is the effective release rate, considering decay in transit, 1n C1/sec; 

Is the downwind distance, in meters; 

is the average wind speed, in m/sec; 

is the sector-average concentration at location (R,z), in Ci/m ; 

is the vertical distance above the ground plane, in meters; 

is the sector width, in radians; and 

is the vertical plume spread, in meters. 

Equation (F-l) may be restated, for simplicity, as: 

x(R,z) = 

where 

/US" o Ji Re 

G(z) = exp 

(z - h)' 

— w — 

2af 

+ exp xt 

where the terms are as defined above. 

(F-2) 

(F-3) 

1.109-72 
P.79 

» 

' 4 

The garnna dose rate to air at a distance of r meters from a point source of q curies is 

expressed by (see Equation 7.33 of Ref. 1): 

ya(3.7xl010)E(1.6xlO"6)B(u,u .rjexpt-ur) 

D

1 = -2 5 2 (F.4) 

4*^(1293) (100) 

where 

B(w,._,r) is the buildup factor, dimensionless; 

a 

D' is the dose rate to air, in rad/sec; 

E is the gamma ray energy per disintegration, in MeV; 

q is the point source strength, in curies; 

r is the distance, in meters; 

w is the attenuation coefficient for air, in m" ; 

y, is the energy absorption coefficient for air, in m" ; 

100 is the number of ergs per gram-rad; 

1293 is the density of air at standard temperature and pressure, in 

g/m ; 

1.6 x 10" is the number of ergs per MeV; and 

3.7 x 10 is the number of disintegrations, per Ci-sec. 

Equation (F-4) may be simplified as follows: 

Ku qEB(p,u ,r)exp(-ur) 

D. = __ a (F.5) 

4irr* 

where 

,10.,, _ - in-6 11 7 x 10'")(1.6 x 10'") ..., ,c ,» 

(1293)(l06)

 = °-46 (F"6) 

The next step is to incorporate Equation (F-2) into Equation (F-5) to arrive at an 

expression for the differential dose rate dD' from the differential volume dV containing the 

radionuclide concentration x(R.z)- Consider a volume element of the plume located z meters above 

the ground and at a horizontal distance L meters from receptor location (R, 0) (see Figure 7.20 

of Ref. 1). All such volume elements located at the horizontal distance L are included in the 

ring-shaped differential volume 2irLdLdz. If R is sufficiently_large that the concentration 

averaged over all such volume elements can be approximated by x(R.z), the contribution of the ring-shaped differential volume dV to the air dose rate at location (R,0) is given as 

Ku EB(p,y .r)exp(-pr) _ /F 7v 

dD1 = —^ K x(R,2)dV

 (F"7' 

4irr* 

1.109-73 
< ,1 « 

where q has been replaced by x(R,z)dV. Substituting (L + z2 )

1 ' '2 for r and 2irLdLdz for dV 1n 

Equation !(F-7), and integrating, the following expression is obtained: 

D' = 

Ku.EQ" 

2 JTv xiRo e 

oo ao 

Si [p.p., (L2 • z2 )

1/2 ] G(z) exp [-y(L2 + z2) 

/2 

L

2 + z2 

The I function, denoted by I_ in Reference 1,' is defined as 

B [t i,.a ,(L2 . z2 )

1/2 ]G(z)exp[-t j(L2 . z2 )1 /2 ] 

I = i

3 ^ I! L

2

 + z2 

LdLdz 

LdLdz 

(F-8) 

(F-9) 

which, when substituted into Equation (F-8), yields 

Ku.EQD 

D' = -^ I 

ir ufce 

(F-10) 

The constant K, equal to 0.46, when divided by H yields the factor 0.260, which Is the 

same as the factor of 260 in Equation (6) of Regulatory Position C2.a, after multiplying by the 

number of mrad per rad. 

The buildup factor given in Reference 1 is of the form 

i 

B(M.y,,r) = 1 + kyr 

where 

k « 

(F-ll) 

(F-12) 

Substituting the above expression for the buildup factor Into Equation (F-9), the I function 

is then given as 

I = I* + kl2 (F-13) 

where the I, and I2 integrals can be written for this form of the build.p factor as 

h -

ao 

-3727 G(z)El(yz)d2 (F-14) 

and I- = 2 " p7I 

00 

z)exp(-pz)dz (F-15) 

where E.(IJZ) is the exponential integral defined by 

¥ pz) . i exfii^ri d(pr) (F-16) 

1.109-74 
P.81 

•/' 4 . 

2. Evaluation of the I Function 

In Reference 1 the I, and I., integrals have been evaluated and the results presented 

graphically. Extraction of the data from these six-cycle log-log multicurve plots is a formidable 

task. A more satisfactory approach is to prepare a tabulation of the Integrals as evaluated 

using numerical methods. These data can then be interpolated in implementing Equation (6) of 

Regulatory Position C2.a. 

« 

The NRC staff has developed a computer routine that evaluates the I function as formulated 

in Equation (F-9). The I function as expressed in Equation (F-9) is Independent of the buildup 

factor form. A listing of this routine is provided in Figure F-l. Communication with the 

routine is through the COMMON statement, which also communicates with the function subprogram 

BULDUP, which defines the dose buildup factor B(p,u,r) desired by the user. 

a 

Also, Yankee Atomic Electric Company has supplied a routine written by Dr. John N. Hamawi 

of that company (Ref. 2) . This routine evaluates the I.. and I- integrals as formulated in 

Equations (Ff 14) and (F-15), respectively. A li.stlng of the routine is providea in Figure F-2 

(reproduced with the permission of Yankee Atomic Electric Company). With the exceptions of 

changes in the title, the addition of the COMMON statement, the computing of I from I, and I-, 

and comment cards as to its authorship, the routine is reproduced as written by Dr. Hamawi. The 

staff has compared the two routines and found their results to be in excellent agreement. The 

routine supplied by the Yankee Atomic Electric Company was found to be considerably faster than 

the staff's routine. 

1.109-75 
P.82 

i 0 * A 

c [I 

C ' 

C , 

c : 

c 

c 

c 

C >: 

C 

C ' 

c 

c 

c 

c 

c 

c** 

0.1612223560, 

0.4086864819, 

0.6288673967, 

0.8070662040, 

0.9313866907, 

0.9935301722, 

0.2247637903, 

0.4669029047, 

0.6778723796, 

0.8435882616, 

0.9529877031, 

0.9987710072/ 

SUBROUTINE DINT 

COMMON/DATAIT/GMU,ZK,HS,3IGMZ,EBAR,01,M 

OOSE INTEGRAL SUBROUTINE -K.F. ECKERMAN U-24-74 

SUBROUTINE EVALUATES THE OOSE INTEGRAL 'IT' AS DEFINED BY EQN 7.61 

IN MET _ AE-1968. THE TWO DIMENSIONAL INTEGRATION IS EVALUATED 

USING GAUSSIAN-LEGENDRE QUADRATURE OF ORDER 48. 

COMMON INFO 

GMU-MA33 ATTENUATION COEFFICIENT C1/METER8) 

ZK-BUILDUP FACTOR (MU-MUAJ/MUA IF USED 

HS-RELEASE POINT HEITH 

RELEASE POINT HEIGHT (METERS) 

3IGMZ-8TANOARO DEVIATION OF PLUME (METERS) 

E8AR-GAMMA RAY ENERGY (MEV) 

DI-DOSE INTEGRAL 

M.ENERGY QROUP INDEX IF NEEDEO 

NOTE-ZK,EBAR,& M ARE USED BY 8UL0UP 

DIMENSION X(24),W(24) 

DATA NN/48/,A/2.828427125/ 

DATA X/ 

10.0323801709, 0.0970046992, 

20.2873624873, 0.3487558862, 

30.5231609747, 0.5772247260, 

40.7240341309, 0.7671590325, 

50.8765720202, 0.9058791367, 

60.9705915925, 0.9841245837, 

DATA M/ 

10.0647376968, 0.0644661644, 

20.0620394231, 0.0607044391, 

30.0551995036, 0.0528901894, 

40.0446745608, 0.0415450829, 

50.0311672278, 0.0274265097, 

60.0155793157, 0.0114-772345, 

3UM«o. 

B*0.5/(3IGMZ*SIGMZ) 

ZLB>HS-4.*SIGMZ 

ZUB«HS«4.*SIGMZ 

IF(ZLB.LT.O.)ZLB»0 . 

YUB«15./GMU 

C»0.5*(ZUB-ZLB ) 

G»0.5*(ZUB*ZLB ) 

E»0,5*YUB 

DO 70 II«1»NN 

I«II-II/ 2 

F«l . 

EX«0. 

IF(MOD(II,2).EO.O)F«-1 . 

ZZ«F*X(I)*C* G 

ARGU«B*(ZZ-HS)*(ZZ-H3 ) 

IF(ARGU.GT.20.)GO TO 55 

EX«EXP(-ARGU) 

55 ARGU«B*(ZZ*HS)*(ZZ+HS) 

IF(ARGU.GT.20.)GO TO 58 

EX«EX>EXP(-ARGU) 

58 IF(EX.EO.0.)G O TO 70 

DO 60 KK«1,NN 

KsKK-KK/2 

IF(MQD(KK#2).EQ.0)FB-1 . 

0.0639242385 , 0.0631141922 , 

0.0591148396 , 0.0572772921 , 

0.0503590355 , 0.0476166584 , 

0.0382413510 , 0.0347772225 , 

0.0235707608 , 0.0196161604 , 

0.0073275539 , 0.0031533460 / 

Figure F-l . Staff-Written Computer Listing 

1.109-76 
P.83 

YY»F.X(K)*E*E 

D1«YY*YY*ZZ*ZZ 

ARGUaGMU*SORT(Dl) 

IF(ARGU.GT.20.)GO TO 60 

EX1«EX*EXP(-ARGU)*BULDUP(ARGU)*YY/01 

3UM»SUM+H(I)*H(K)*EX1 

60 CONTINUE 

70 CONTINUE 

DI«3UM*C*E/(A*3IGMZ) 

RETURN 

END 

Figure F-l (continued) 

1.109-77 
P.84 

SUBROUTINE DINT 

REAL MU 

COMMON/DATAIT/MU,ZK,H,3IGZ,DI,L 

C** 

C DOSE INTEGRAL ROUTINE WRITTEN BY 

C DR. JOHN N. HAMAWI 

JC YANKEE ATOMIC ELECTRIC COMPANY 

C NUCLEAR SERVICES DIVISION 

C ,' 20 TURNPIKE ROAD 

C ME3TBOROUGH, MASSACHUSETTS 01581 

c YAEC REPORT NO. nos 

c 

C COMMON INFO 

C MU-MASS ATTENUATION COEFFICIENT (1/METER8) 

C ZK-BUILDUP FACTOR (MU-MUA./MUA 

C SIGZ-STANDARD DEVIATION OF PLUME (METERS) 

C OI-DOSE INTEGRAL -I TOTAL 

C L- DETERMINES NUMBER OF INTERVALS USED IN INTEGRATION 

C** 

DIMENSION CDATA(5),E(49),B(49),P(49) 

DATA M/9/,CDATA/5.00*3,1.0D+4,2.00*4,5.00*4,1.00*5/ 

OATA A0,A1,A2,A3,A4,A5/ -0.57721566, 0.99999193, - 0.24991055, 

C 0.05519968,-0.00976004, 0.00107857/ 

DATA 80,81,82,83/ 0.2677737343, 8.6347608925, 18.0590169730, 

C 8.5733287401/ 

DATA 00,01,02,03/ 3.9584969228, 21.0996530827, 25.6329561486, 

C 9.5733223454/ 

DATA 0,01*02,03,04,05,06,07,08,09/ 

C 3543.75,989.,5888.,-928.,10496.,-4540.,10496.,-928.,5888.,989./ 

C**** COMPUTE LIMITS OF INTEGRATION ZMlN AND ZMAX, ANO INTERVAL WIDTH 

IF(L.LT.2.0R.L.GT.6)" L • 6 

C a COATA(L-l) \ 

N a L*(M-1 ) • 1 . 

3IGZ2 a SIGZ*SIGZ S 

ALFA • H - HU*SIGZ2 

BETA a 3IGZ* SORT(2.0*ALOG(C)) 

IF(ALFA.GT.O.O) GO TO 150 

ZMIN a 0.0 

ZMAX a ALFA • SORT(ALFA*ALFA t BETA*BETA) 

GO TO 200 

150 ZMIN a ALFA - BETA 

IF(ZMIN.LT.O.O) ZMIN a 0.0 

ZMAX a ALFA • BETA 

200 OZ a (ZMAX-ZMIN)/(N-i) 

C**** COMPUTE EXPONENTIAL INTEGRAL TERMS Ed ) (SPECIAL PROCEO. FOR E(l)) 

E(l) a 2.18907-ALOG(MU*OZ) 

DO 250 I a i, N 

Z a ZMIN • (I-l)*OZ 

X a HU*Z 

IF(X.LE.O.O) GO TO 2S0 

X2 a x*X 

X3 a x*X2 

X4 a x*X3 

X5 a x*X4 

IF(X.LE.l.O) Ed ) a -ALOG(X) • AO* Al *X*A2*X2 + A3*X3*A4*X4*A5»X5 

IF(X.GT.l.O) Ed ) a (B0*B1*X*B2*X2*B3*X3->X4) / 

C (C0*C1*X*C2*X2*C3*X3*X4)/(X* EXP(X)) 

250 CONTINUE 

t**** COMPUTE INTEGRAND TERMS B(I) AND Pd ) 

DO 300 I a i, N 

Z • ZMIN • (I-l)*OZ 

Figure F-2. Hamawi-Written Computer Listing 

1.109-78 
P.85 

300 

C**** 

Ga EXP(-(Z*H)*(Z+H)/(2.0*SIGZ2)) • EXP (-(Z-H)*(Z-H)/(2.0*SIGZ2) ) 

8(1) a 6*E(I) 

P(I ) a 6* EXP(-MU*Z) 

PERFORM NUMERICAL INTEGRATION USING 9-POINT NEWTON-COTES FORMULA 

3UMB a 

3UMP a 

MM a M 

KM a N 

DO 350 

8UMB a 

0.0 

0.0 

- 1 

. M 

K « 

SUMB 

350 

* 1 

1,KM,MM 

* Dl*B(K)+02*B(K*l)+03*B(K<.2)+D4*B(K*3)+O5*B(K+4) 

+D6*B(K+5)+07*B(K-.6)+D8*B(K*7)+D9*B(K + 8) 

SUMP a SUMP • D1*P(K)*D2*P(K*1)*D3*P(K*2)*D4*P(K*3)*05*P(K*4) 

J •06*P(K*5)*07*P(K*6)*08*P(K*7)t09*P(K*8 ) 

CONTINUE 

0iabz*(8UMB+3UMP*ZK)/(0*2.828427*3IGZ) 

RETURN 

END 

Figure F-2 (continued) 

1.109-79 
P.86 

REFERENCES FOR APPENDIX F 

1. \"Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-241090, 1968. 

2. N. Hamawi, "A Method for Computing the Gamma-Dose Integrals T, and T- for the FlniteCloud Sector-Average Model," Yankee Atomic Electric Company Report YAEC-1105, 1976. 

1.109-80