Regulatory Guide 1.109: Difference between revisions

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
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Latest revision as of 02:05, 17 January 2025

Revision 1*

October 1977 U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1. 09 CALCULATION OF ANNUAL DOSES TO MAN- FROM ROUTINE

RELEASES OF REACTOR EFFLUENTS FOR TH

E. PURPOSE

OF EVALUATING COMPLIANCE WITH

10 CFR PART 50, APPENDIX I

' USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regu- Regulatoey Guides are issued to describe nd make available to th Public methods latory Commission. Washington, D.C.

20555. Attention:

Docketing and Service Branch.

acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specilic problems The guides are issued in the following ten broad divisions or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations. and compliance with them is not required.

1. Power Reactors

6. Products Methods and solutions different from those set out in the guides will be accept..

2. Research and Test Reactors

7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance

3. Fuels and Materials Facilities B. Occupational Health of a permit or license by the Conmission.

4. Environmental and Siting S. Antitrust Review

5. Materials and Plant Protection

10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproducedl or for place times, and. guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience.

This guide was revised as a result of divisions should be made in writing to the U.S. Nuclear Regulatory Commission.

substantive comments received from the -public and additional staff review.

Washington. D.C.

20555, Attention:

Director, Division of Document Control.

The substantial number of.changes in this revision has made it impractical to indicate the changes with lines in the margin.

7

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 Dose 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 D.

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 ......

1.109-1.1 a.

Radionuclide Concentration in Environmental Media (Ci ) .................

I..109-11 i

b.

Usage (U)

..........................................

1.109-11 ap c.

Dose Factor (Daipj)

. .....................................................

1.109-11

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 S

REFERENCES

FOR APPENDIX A......................................

...................

1.109-18 iii

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 Air Dose from All Noble Gas Releases .........................................

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

1. 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..............

ý

.

....................

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 D, 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

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

=. .

,4

,v

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-Speciiic Data .......

1.109-13 A-2 Shore-Width Factors for Use in Equations (A-5),

(A-6),

and (A-7) ..............

1.109-15 B-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases .............

1.109-21 D-l 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 ...................................

l.I09-38 E-3 Animal Consumption Rates .............................................

......

1.109-38 E-4- Recommended Values for U a To Be Usedfor the Average Individual in lieu of Site-Specific Data .....

.....................................................

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-l0

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 Dose 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 Hamawi-Written Computer Listing .

1,109-78 vi

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 Light- Water-Cooled Nuclear Power Reactor Effluents," to 10 CFR Part 50 provides numerical guidance for radioactive effluent design objectives and technical specification requirements for limiting conditions of operation for light-water-cooled nuclear power plants.

To implement Appendix I, the NRC staff has developed a series of guides that provide methods.

acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man.

This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.

The methods used herein are general approaches that the NRC staff has developed for application in lieu of specific parameters for individual sites.

The use of site-specific values by the applicant is encouraged.

However, the assumptions and methods used to obtain these parameters should be fully described and 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 atmos- phere, 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 is-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 general 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.

11.109-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.

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 dose factors 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 accept- able to the NRC staff for calculating doses to individuals and populations.

If other models are selected, they should include the same exposure pathways considered in the models described in 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 intoaccount 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 the NRC staff to evaluate their validity.

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 con- sidered 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.

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 R

. : 1100 UapMp Q 0ai pjexp(-Xitp)

(1)

apj F

1ap b.

Aquatic Foods R a

1100 UaFp Q.B. 0D

.exp(-it.)

.

(2)

a pj F

1 1 p aipi i p c.

Shoreline Deposits Rap

= 110,000

p QiTiD

[exp(-Xitp)][l

- exp(-t)

(3)

apj =

F

1aipi

1pib

1 J09-2

d.

Irrigated Foods For all radionuclides except tritium:

Frrr

-

xp-I

8

)

fBv~

- exp(-itb)]l R

= uveg diexp(-thDaipj

---

Yv Eite)] +

--'

P

i b

api

.

v

1r e

rp( "

b

+ Uanimal F ADaipj Qd p

exp(AEite)]

ap IA aipjIQ F iexp iX

h)YvX

+ fI Biv[

- exp(-Aitb)]

+Ciaw

(4)

For tritium:

R

.

vegC D

uanimalD

FA(CvQ

+ CQw)

(5)

apj ap v apj + ap api A VF

AwAw where B.

is the equilibrium bioaccumulation factor'for nuclide i in pathway p, expressed ip as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in liters/kg;

B.

is the concentration factor for uptake of radionuclide i from soil by edible v parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;

CiAw is the concentration of radionuclide.i in water consumed by animals, in pCi/liter;

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

Daipj 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 concentra- tion of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the areal radionuclide concentration (in pCi/m 2);

di is the deposition rate of nuclide i, in pCi/m2 per hr;

F

is the flow rate of the liquid effluent, in ft 3 /sec;.

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

FiA

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;

M

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;',

P

is the effective 'surface density" for-sbil,. in kg(dry soil)/m2 -;

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

QF ,' is the consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight);,

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

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

R

Rap 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

NU

tb is the period of time for which sediment or soil is exposed to the contaminated water, in hours;

te 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;

Ti is the radioactive half life of nuclide i, in days;

t is the average transit time required for nucli es to reach the point of exposure.

For internal dose, tp is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;

Uap is a usage factor that specifies the expos.,*oe time or intake rate for an individual of age group a associated with pathway p, in hr/yr, z/yr, or kg/yr;

W

is the shoreline width factor, dimer;sionless;

Y v is the agricultural productivity (yield), in kg(wet weight)/m2 AEi is the effective removal rate corn

.]t for radionuclide i from crops, in hr where X Ei= Xi + Xw , i is the rz-,)active decay constant, and Xw is the removal rate constant for physic,:

s by weathering (see Appendix E,

Table E-15);

is the radioactive decay constant -:.r iuclide i, in hr-

1100

is the factor to convert from (Ci/yr)i(ft 3/sec)

to pCi/liter; and

110,000

is the factor to convert from (Ci/yr)/(ft 3/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equ; ions yield the dose'rates to various organs of individuals from the exposure pathways mentio, ed 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 path- ways 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,

"Methods 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 High Dy(r,o)

26 r1

1n1 n

U (Ek Eki(H,u,S,az;Ek QniAki6 n n s k1 where A

ki is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration;

Dy(r,e)

is the annual gamma.air dose at a distance r (meters) in the sector at angle o, in mrad/yr;

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

1.109-4

fns is the joint frequency of occurrence of stability class s and wind speed class n for sector O,_dimensionless;

I(H,u,s,az,Ek)

is the dimensionless numerical integration constant accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (a z).ý

In addition, I is a function of the photon energyEk and is T

Il + k12 as formulated in Slade (Appendix B, Reference 1);

D

Dni is the release rate of radionuclide i, corrected for decay during transit to the distance r under wind speed un, in Ci/yr;

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

60

is the sector width over which atmospheric conditionsare averaged, in radians;

Pa(Ek)

is the a.ir energy absorption coefficient for the kth photon energy group, in m-1; and

260

is the conversion factor to obtain DY(r,e),

in mrad/yr, and has the units of mrad-radians-m3-disintegration/sec-MeV-Ci.

b. -Annual Gamma Air Dose from All Other Noble Gas Releases; Annual Beta Air Dose from All Noble Gas Releases DY(r,o) or DB(r,e) =.3.17 x 104- Qi[x/Q]D(r,o)(DFi or. DFý)

(7)

where DFý,

DFý

are the gamma.and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m 3/pCi-yr;

DY(r,o) or D'(r,O)

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;

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

[x/Q]D (r,O)

is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in sector 0 in sec/m3 (see Regulatory Guide 1.111,

"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," for methods to estimate x/Q); and-

3.17 x 104 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 T

yT

0 (r,o) = 1.11 SF

Dk(r,O)exp[-1Ja(Ek)td]

(8),

where DT (r,o)

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

DY(r,0)

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

SF

is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless;

td is the product of tissue density and depth used to determine a total body dose, in g/cm2;

VT(Ek)

is the tissue energy absorption coefficient, in cm2/g; and

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 Hig DS(rG)

1 ..11SFDY(r,G)

+ 3.17 x 104 4 Qi1 x/Q]D(r,e)DFSi

(9)

where DFSi is the beta skin dose factor for a semi-infinite cloud of radionuclide i, which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr; and DS(r,e)

is the annual skin dose at the distance r in sector e, in mrem/yr.

All other parameters are as defined in preceding paragraphs.

e.

Annual Total Body Dose from All Other Noble Gas Releases, DT(r,b) : SF

xi(r,e)DFBi

(10)

where DFBi is the total body dose factor for a semi-infinite cloud of the radionuclide i, which includes the attenuation of 5 g/cm2. of tissue, in mrem-m3 /pCi-yr;.

DT(r,o)'

is the annualtotal body dose due.to immersion in a semi-infinite cloud at.

the distance r in sector 0, in mrem/yr; and xi(r,e)

is.. the annual average ground-level concentration of.radionuclide i at'the distance r in sector e, in pCi/m3 All other parameters are as defined above.

f.

Annual Skin Dose from All Other Noble Gas Releases D5 (r,0) = 1.11 S

xi(r,O)DFI +

X1(r,e)DFS

(1 F1

1 where Ds(r,e)

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.

Doses 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

a.

Annual Organ Dose from External Irradiation from Radionuclides Deposited onto the Ground Surface DG(r,o)

8760 SF

G

C*(r,o)DFGi

(12)

where CG(r,e)

is the ground plane concentration of radionuclide i at distance r in sector e, in pCi/m2 DFG.

is the open field ground plane dose conversion factor for organ j from radio- nuclide i, in mrem-m2/pCi-hr;

DT(r,O)

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

SF

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 in Air DA(r,e)

= R

(3 a = xi(r,O)DFAija

(13)

ja a

j where A(re)

is the annual dose to organ j of an individual in the age group a at location jar'

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

DFA..

is the inhalation dose factor~for radionuclide i, organ j, and age group a, in mrem/pCi;

Ra is the annual air intake for individuals in the age group a, in m3/yr; and..

xi(r,e)

is the annual average concentration of radionuclide i in.air at location (r,e), in pCi/m 3.

c.-

Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food DD (r,e) =

DFIa f Cv(r,o) + UmCm(ro) + UFCF(rO) + ULf Ci(r,O

(14)

ja ij[a91a where Cv(r,D), CF(r,o),

CL(r,o), C.(r,)

are the concentrations of radionuclide i in produce (non-leafy-vegetables,

1.

1 fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg or pCi/z;

DD (r,o)

'is the annual dose to the organ j of an individual in age group a from ja ingestion of produce, milk, leafy vegetables, and meat at location (r,), in mrem/yr;

DFlija is the ingestion dose factor for radionuclide i, organ j, and age group a, in mrem/pCi;

f ,fz are the respective fractions of the ingestion rates of produce and leafy vegetables that are produced in the garden of interest; and v

Um F

L

Ua m

a'

Ua'

Ua are the annual intake (usage) of produce, milk, meat, and leafy vegetables, respectively, for individuals in the age group a, in kg/yr or i/yr (equivalent to Uap).

1.109-7

4.

Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.-l,

2, and 3.

Because of the various conditions under which the equa- tions in Appendix D are used, they are not presented in this section.

It is recommended that Appendix D be read for a detailed. discussion of the staff's models..

5.

Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with the numerical guides for design objectives of Appendix I is presented in 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

-*~-<~

w TABLE 1 SUMMARY OF STAFF POSITION -

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I

APPENDIX I*

RM-50-2 DESIGN OBJECTIVES

DESIGN OBJECTIVES*

0

'.

TYPE OF DOSE

Liquid Effluents Dose to total body from all pathways I

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

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

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

Location of the highest dose offsite.**

Same as above.

Location of the highest dose offsite.÷

Same as above.

Location of the highest dose offsite.**

Same as above.

EQUATIONS

TO BE USED

1, 2, 3, 4, & 5

6 or 7, as appropriate

7

8 or 10, as appropriate

9 or 11, as appropriate See footnotes at end of table, on following page.

___________________________________________

-v

--~*-.--~~ --

---

--

-

TABLE 1 (Continued)

SUMMARY OF STAFF POSITION*-

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I

APPENDIX I*

RM-50-2 POINT OF DOSE

EQUATIONS

TYPE OF DOSE

DESIGN.OBJECTIVES

DESIGN OBJECTIVES*

EVALUATION

TO BE USED

Radioiodines and Particulates Released tothe.Atmosphere Dose to any organ

15 mrem/yr per unit

15 mrem/yr per site Location of the

12, 13, & 14 from all pathways highest dose offsite...++

1-131 releases

1 Ci/yr per unit

-

Evaluated for a maximum individual, as described in Section B of this guide.

Evaluated at a location that is anticipated to be occupied during plantlifetime 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.

tEvaluated at a location that could be occupied during the term of plant operation.

t t Doses due to carbon-14 and tritium intake from ferrestrial food chains are included in this category.

tttEvaluated 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 iodineon 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.

APPENDIX A

METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS

The equations for estimating radiation exposureto man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline-deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.

1. Generalized Equation for Calculating Radiation Dose via Liquid Pathways.

Equation (A-l)

is the generalized equation for calculating the radiation dose to man via liquid effluent pathways.

Raipj Cip UapD aipj (A-1)

where C.

is the concentration of nuclide i in the media of pathway p, in pCi/x, pCi/kg, or pCi/m 2;

Daipj is the dose factor, specific to age group a, radionuclide i, pathway p, alp, 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 alp,]

via pathway p, in mrem/yr; and Ua is the exposure time or intake rate (usage) associated with pathway p for ap age group a, in hr/yr, Z/yr or kg/yr (as appropriate).

The three factors, making up Equation (A-l) 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 Concentrationin Environmental Media (Cip)

The concentrations in environmental media of interest can be estimated from the mixing ratio Mp, the discharge flow F, the radionuclide release rate Qi'

and other terms presented in.

the pathway equations that appear later in this discussion..

b.

Usage (U Y.

The second term of Equation.(A-l) is the usage term Ua.

Usage is expressed as a ap- consumption rate in 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 (D aipj 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/m2 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 units of mrem/hr per pCi/m2 and are presented in Appendix E, Table E-6.

1.109-11

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:

M Ua- Rapj = 1100

pF aP* Qia pjeXp(-,t p)

(A-2)

Symbols for this equation were defined earlier, in Section C.l of this guide.

The summation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected.

The expression (1100 QiM p/F)exp(-xit p) yields the concentration of nuclide i at the time the water is consumed, in pCi/X.

This concentration is the term Cip in Equation (A-l).

As a minimum, the transit time tp may be set equal to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 for radionuclide removal by water purification processes using techniques such as those outlined in Reference 3.

It should be noted that, depending on the.hydrological dispersion model employed, the- mixing ratio, Mpor. dilution factor may not be explicitly defined.

In those instances (e.g.:,

buildup of activitykin a cooling pond),

the relative concentration in the mixed stream (comparedc to the effluent co,6centration) may be supplied as a function of the radiological decay constant, with any potential' effl'uent recycling taken into account.

Suggested hydrological dispersion models are 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 Bip in Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose from consumption of.aquatic foods.

U M

R

apj =1100

F .

QiBipD ai pjexp(-itp)

.

(A-3)

Values of B

are given in Table A-l; the other. parameters have been previously defined.

The ip methodology presented in Reference 7 for the development of site-specific freshwater bioaccumula- tion factorsis considered to-be acceptable by the NRC staff.

The transit time tp may be set equal to 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s* 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 ofempirical 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

TABLE A-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA

(pCi/kg per pCi/liter)*

ELEMENT

H

C

NA

P

CR

MN

FE

CO

NI

CU

ZN

BR

RB

SR

Y

ZR

NB

MO

TC

RU

RH

TE**

I

CS

BA

LA

CE

PR

ND

W

NP

9.

4.

2.

4.

1.

5.

1.

5.

2.

4.

2.

3.

2.

3.

4.

1.

2.

1.

4.

1.

2.

4.

2.

1.

2.

1.

FRESHWATER

FISH

INVERTEBRATE

OE-01

9.OE-01

6E 03

9.1E 03 OE 02

2.OE 02 OE 05

2.OE 04 OE 02

2,OE 03 OE 02

9.OE 04 OE 02

3.2E 03 OE 01

2.OE 02 OE 02

1.OE 02 OE 01

4.OE 02 OE 03

"

.OE

04

2E 02

"\\ 3.3E 02 OE 03i

1.OE 03 OE 0i l.OE 02

5E 01 l.OE 03

3E 00

6.7E 00

OE. 04 l.OE 02 OE 01

1.OE 01

5E 01

5.OE 00

OE 01

3.OE 02 OE 01

3.OE 02 OE 02

6.1E 03

5E 01

5.OE 00.

OE 03 l.OE 03****

OE 00

2.OE 02

5E 01 l.OE 03 OE 00

1.OE 03

5E 01 l.OE 03

2E 03 l.OE 01 OE 01

4.OE 02 SALTWATER

FISH

INVERTEBRATE

9.OE-OI

9.3E-C;

1.8E 03

1.4- 03

6.7E-02

1 9E-O1

2.9E 04

3.OE .04

4.OE 02

2.OE 03

5.5E 02

4.OE 02

3.OE 03

2.OE 04 l.OE 02

1.OE 03 l.OE 02

2.5E 02

6.7E 02

1.7E 03

2.OE 03

5.OF,01

1.5E-02

3.1E 00

8.3E 00

1.7E 01

2.OE 00

2.OE 01

2.5E 01

1.OE 03

2.OE 02

8.OE 01

3.OE 04 l.OE 02 l.OE 01

1.OE 01 l.OE 01

5.OE 01

3.OE 00

1.OE 03 l.OE 01

2.OE 03

1.OE 01 l.OE 02 l.OE 01

5.OE 01,

4.OE 01

2.5E 01 l.OE 01

1.OE 02

2.5E 01.

l.OE 03 l.OE 01

6.OE 02

2.5E 01

1.OE 03

2.5E 01

3. OE 01 I. OE 01

1 .OE

3. OE

1 . OE

03

01

01 Values in Table Data taken from Data taken from A-1 are taken from Reference 6 unless otherwise indicated.

Reference 8.

Reference 7.

1 .109-13 Iiiii I

suspended and deposited materials.

One method of approaching this problem was presented in 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.s = Kc Ciw[l - exp(-Aitb)]

(A-4)

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

Ciw is the concentration of nuclide i in water adjacent to the sediment, in pCi/liter;

K

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

tb 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 A.

is the decay constant* of nuclide i, in hours-l.

In the original evaluation of the equation, xi was chosen to be the radiological-decay constant.

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

The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period-of several years.in the Columbia River between 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 to facilitate estimates of the exposure rate from gamma.iemitters one meter above the sediment, an effective surface contamina- tion was estimated.

This surface contamination was assumed to be contained within the top 2.5 cm (1 in.) of sediment (with a mass of 40 kg/m 2 of surface).

The dose contribution from the radionuclides at depths below 2.5 cm was ignored.

The resulting equation is Si = lOOTiCiwW[l

- exp(-xitb)]

(A-5)

where Si is the "effective" surface contamination, in.pCi/m2 , that is used in subsequent calculations;

Ti 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 [Kc (/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-l) leads to Equation (A-6) below for calculation of radiation dose from exposure to shoreline sediments.

Rapj = Uap i.D

aipj = 100 UapW

C Ti D aipj[l - exp(-xitb)]

(A-6)

As in the development of Equation (A-2),

the expression (1100 Qi M p/F)exp(-it p) may be substituted for C .

This results in the following relationship:

Rap

= 110,000

ap p QiTiDipj[exp(-xitp)]El - exp(_xitb)]

(A-7)

apj F

1

1aip tb)p 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-51.

1.109-14

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 radio- nuclides released in liquid effluents but appearing in crops or animal products.

Separate expressions are presented for tritium because of its unique environmental behavior.

(1)

Vegetation The concentration of radioactive material in vegetation results frol 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 Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg,"is given by:.

Civ d

d [r[l -

exp(-xEite)] +f I

ibv[I

Cexp(-x i Y

ex (_

(A-8)

ci v

dX

_

ith

-

L

YvAEi P1 J

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

Appendix E, Table E-15, presents suggested values-for the parameters r, Yv'

te' P, and th.

Values for Biv are in Table E-l.

The deposition rate, di, from irrigated water is defined by the relation di = Ciw I (water deposition).

(A-9)

where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I

is the average irrigation rate, in liters/m2 /hr, during the growing season.

For a cow grazing on fresh forage, te in Equation (A-8)

is set equal to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months

(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 Civ is (see Ref. 13):

Cv = Cw (A-10)

1.109-15

Jull

(2)

Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water.

The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg is proportional to the animal's intake of the radionuclide in feed or forage (sub- script F) and in water (subscript w):

CiA = F iA[CiFQF +

Q

(A-ll)

The second set of terms in the brackets in Equation (A-1l)

can be omitted if the animal does not drink contaminated water.

Values for QF and QAw are presented in Appendix E,

Table E-3.

Values for Biv and FiA are given in Appendix E, Table E-l.*

(3)

Total Dose from Food Grown on Land The total dose R apj from irrigated foods and animal products (excluding tritium)

is given by:

R UY~g C D

U animal D

Rapj =

p u~

iv aipj ap

!

iA aipj (A-12)

If values for Civ from Equation (A-8) and CiA from Equation (A-11)

are substituted in Equation (A-12):

uveg dFril

- exp(-Ei te)]

flB[iv[

- exp(-Aitb)]1 Rapi ap d exp(ith)Daipj Yv XEi

+

PXi

.

+ u animal FQ

d rp -

Lxp-Ei e)

+

ap

! FiADaipj Fd iexp(-ith YvXEi f B [1

-exo(-x t )

(A-13)

+ I iv

i b CAAW

f PXi[

-

x{*t)_CiAwQAwj where the terms are defined in Section C, "Regulatory Position."

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

In actual.

use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-16)).

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

is given by the following equation:

CA = Fa(CvQF + CAwQAw)

(A-14)

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

Since by Equation (A-la) Cv = C , and since for all practical purposes CAw = CW,

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

CA = FAC w(QF +QAw)

(A-15)

S i

i Values for F. appear as F and Ff in Table E-l.

iA

m f

1.109-16 IiIi

Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):

R

=vegCD

+ uanimalc D

(A-16)

apj ap v apj ap A apj

1.109-17

Numerical Guides Criterion 'As Low ictor Effluents,"

REFERENCES FOR APPENDIX A

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

for Design Objectives and Limiting Conditions for Operation to Meet the As Practicable' for Radioactive Material in Light-Water-Cooled Power Rea 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.

4.

J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (iJCi/m 2 ),"

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 in Freshwater Biota,"

ORNL-5002, Oak Ridge, Tenn.,

November 1975.

8.

G. G' Kilaugh and L. R. McKay,

"A Methodology for Calculating Radiation Doses from Radio-*

activity Released to the Environment," ORNL-4992, Oak Ridge National Laboratory, Oak Ridge, Tenn., 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 panelof 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 ti 1/4..

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 Hih:

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:

i!

~260

D

DY(r,e) = 2--0

U-

fns

1*a(Ek)Ekl(HusozEk)

QniA

(B-l)

n n s k

nk Symbols for this equation were defined earlier, in Regulatory Position C.2.a of 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, Aki, is determined to be Aki = X [AmEma(Em)]/[Ekla(Ek)]

(B-2)

m where A

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

.of energy Em;

Em is the energy of the mth photon within the kth energy group, in MeV; and Wa (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 Qni Q

Qi exp(-xir/un)

(B-3)

., The term "gamma.air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays.

Annihilation and bremsstrahlung photon radiations are possible contributors to this component of the air dose.

1.109-19

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

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

-I

Xi is the decay constant of nuclide i, in 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)

is. determined from xi(r,e) = 3.17 x 104 Q[x/Q] D(r,e)

(8-4)

where x.(r,e)

is the annual average ground-level concentration of nuclide i at the3 distance r in the sector at angie e from the release point, in pCi/mi

, and

[x/Q]D(r,e)

is the annual average gaseous dispersion factor (corrected'for radioactive decay) in the sector at angle ,3 it the distance r from the release point, in sec/m3 .

(See Regulatory Guide 1,111 for atmospheric dispersion models.)

All other parameters are as previously defined.

The associated annual gamma or beta air dose is then D'(r,e) or D6 (r,e) =

xi(re)(DFi or DF)

(B-5)

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

Table B-1 presents a tabulation of the dose factors for the noble gases 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 and the skin dose at a depth of 7 mg/cm2 of tissue (Ref. 4).**

a.

Releases from Free-Standing Stacks More Than 80 Meters High The annual total body dose is computed as follows:

DT(r,e)

= 1.11 x SF I DY(r,O)exp[-T(Ek)td1 (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.,

o+, B-,

and conversion electrons.

See discussion in Appendix E, Section 3.

1.109-20

TABLE B-I

EXPOSURE TO A SEMI-INFINITE

CLOUD OF

DOSE FACTORS FOR

NOBLE GASES

Nucl ide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90

Xe-1 31m Xe-1 33m Xe-1 33 Xe-1 35m Xe-i 35.

Xe-i 37 Xe-i 38 Ar-41 B-air*(DF )

2. 88E-04

1. 97E-03

1 .95E-03

1 .03E-02

2. 93E-03

1 .06E-02

7.83E-03

1 .11 E-03

1 . 48E-03

1 . 05E-03

7. 39E-04

2. 46E-03

1 . 27E-02

4. 75E-03

3. 28E-53 B-Ski n* * (DFSi)

1 46E-03

1 34E-03

9. 73E-03

2. 37E-03

1 .OIE-02

7. 29E-03

4. 76E-04.

9. 94E-04

3. 06E-04

7.11 E-04

1 86E-03

1 22E-02

4. 13E-03

2. 69E-03 y-Air*(DFW)

1 93E-05 I 23E-03

1 72E-05

6. 1 7E-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 51 E-03

9.21 E -03

9. 30E-03 y-Body**(DFBi)

7. 56E-08

1.1 7E-03

1.61 E-05

5.. 92E-03

1 .47E-02

1. 66E-02

1 .56E-02

9.1 5E-05

2.551 E-04

2.94E-04

3.12E-03

1 .81E-03

1 .42E-03

8.83E-03

8.84E-03

3 mrad-m pCi-yr

3 mrem-m pCi-yr

2.88E-04 = 2.88 x 1O0

I .109-21

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

The factor SF 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,e) : 1.11 x SFDY(ro) + 3.17.x 1 1 Qi[x/Q]D(rG)DFSi (B-7)

.i Symbols 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-i.

b.

All Other Releases The annual total body dose is computed as follows:

D(r,e) : SF ! xi(r,e)DFBi (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:

D0(r,e)

1.11 x SF

x xi(r,O)DFW + ! xi(r,e)DFSi (B-9)

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

1.109-22

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," NEDO- 12037, 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 in a Radioactive Cloud," Health Physics, Vol.

26, pp. 1-12, January 1974.

al*

'::i k!

1.109-23

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 CG(r,O) = [1.0 x 1012.1

[6i(re) Qi]

1

-

1

[1 - exp(_xitb)].

(C-l)

where CG(r,e)

is the ground plane concentration of the radionuclide i in the sector at I

angle 0 at the distancer from the release point, in pCi/m2 Q.

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;

6i(r,e)

is the annual average relative deposition of effluent species i at location (r,e), considering depletion of the plume during transport, in m-2;

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

1.0 x 1012 is the number of pCi per Ci.

The annual dose resulting from direct exposure to the contaminated ground plane, from all radionuclides, is then DG(r,e) = 8760 SF

CG(r,e)DFGi (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 SF is assumed to have a value of 0.7, dimensionless.

Does not include noble gases.

1.109-24

K, i,,

2.

Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide iat the location (r,e) with res- pect to the release point may be determined as xi(r,e) = 3.17 x 104 Qi[x/Q] D(r,e)

(C-3)

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

Xi(r,e)

is the annual average ground-level concentration, of nuclide i in air in sector e at distance r, in pCi/m3;

[x/Q]D(r,o)

3.17 x l04

3 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 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

0.A

(r,e) = R Zx.(r,e)DFA.

ja a I

ja (C-4)

Values for DFAija are given in Appendix E, Tables E-7 through E-l0; values for Ra are given 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 Cv(r,e) =di (r,e) tr[l - exp(-AEi te)]+

Biv [ - exp(-xitb)]

_2 P X i exp (- i th )

(c-5)

See Regulatory Position C.1 of this guide for definitions of terms.

Values for the parameters r, te, Yv'

P, and th are provided in Appendix E, Table E-15.

For the parameters te, Yv and th' 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 in forage consumed as stored feed by dairy cows, beef cattle, or goats.

1.109-25

The deposition rate from the plume is defined by di(r,e) = 1.1 x 1086i(r,e)Qi (C-6)

where d.(r,e)

is the deposition rate of radionuclide i onto ground at location (r,e), in pCi/m 2-hr;

6i(r,e)

is th6 relative deposition of radionuclide i, considering depletion and

1

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

1.1 x 1O8 is the number of pCi per Ci (10 2) divided by the number of hours per year

(8760).

For radioiodines, the model considers only the elemental fraction of the effluent.

The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine.

Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Ref.

1).

With this consideration included, Equation (C-6) for radioiodine becomes di(r,e) = 5.5 x 1076i(r,e)Qi

6.(C-7)

where 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 non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).

For particulates, the deposition model considers both wet and dry deposition.

There is also a retention factor (r of Equation (C-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.

Carbon-14 is assumed to be released in oxide form (CO or C02 ).

The concentration4of 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,e) = 3.17 x 107pQl 4 [x/Q](r,e) 0.11/0.16

= 2.2 x 107 pQ1 4[X/Q)(r,e)

(C-8)

where C 4 (r,e)

is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;

Q14 is the annual release rate of carbon-14, in Ci/yr;

p is the fractional equilibrium ratio, dimensionless;

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

1. 109-26

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 lO1 2 pci/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).

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

Using the method described in Reference 10, the NRC staff derived the following equation:

c'(r,).

3.17 x 107 QT[x/Q(rKe)(0.75)(0.5/H)

= 1.2 x 107 QT[x/Q](r,e)/H

(C-9)

where C (r,e)

is the concentration of tritium in vegetation grown at location (r,e), in pCi/kg;

H

is the absolute humidity of the atmosphere at location (r,e), in g/m3 QT

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

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 feedconsumed by the animal.

The radionuclide concentration in milk is estimated as C'(re) =

vC(r,)Q exp(-xitf)

(C-10)

where Cm(r,e)

is the concentration in milk of nuclide i, in pCi/liter;

Cv(r, e)

is the concentration of radionuclide i in the animal's feed, in pCi/kg;

Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Appendix E, Tables E-l and E-2 for cow and goat data, respectively; for nuclides not listed in Table E-2, use the values in Table E-l);

is the amount of feed consumed by the animal per day, in kg/day;

tf 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 i.

is the radiological decay constant of nuclide i, in days--1 The concentration of radionuclide i in the animal's~feed is estimated as C.(r,e) = fpfsC.(r,e) + (l - f )C*(r,e) + fp(l fs)CS(r,e)

(C-11)

p s ip i

p'

(C-ll where C (r,e)

is the concentration of radionucl.ide i on pasture grass (calculated using Equation (C-5) with th=O),

in pCi/kg;

CS(r,e)

is the concentration of radionuclide i in stored feeds (calculated using Equation (C-5) with th=90 days), in pCi/kg;

1.109-27

fp is the fraction of the year that animals graze on pasture; and f s is the fraction of daily feed that is pasture grass when the animal grazes on pasture.

The values of the parameters tho te, Yv , and tf 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 concentra- tion in meat is estimated as F(r,e)

FfCi(r,e)QF exp(-xits)

(C-12)

where CF(r,e)

is the concentration of nuclide i in animal flesh, in pCi/kg;

Ff is the fraction of the animal's daily intake of nuclide i which appears in each kilogram of flesh, in days/kg (see Appendix E, Table E-l for values); and ts 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 i a vf v FF

c(Lo Lai

]

(-3 DP (r,e)

DFI~

ij[UafgC.(r,e)+ UmC¶(,e) + U CFF(re) + UL f C(re)]

(C-13)

agi a

a aaXI

where D a(r,-O)

is the annual dose to organ j of an individual in age group a from dietary intake of atmospherically released radionuclides, in mrem/yr;

DFI..

is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables E-ll through E-14 of Appendix E of this guide); and U

aV

U ,

UF,

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

a 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 fk 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.

i

1.109-28

REFERENCES FOR APPENDIX 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 ID0-12065, December 1968.

4.

F. 0. Hoffman, "Environmental Variables Involved with the Estimation of.the Amount of 1311

-in Milk and the Subsequent Dose to the Thyroid," Institute fUr Reaktorsicherheit, Cologne, West Germany, IRS-W-6, June 1973.

5.

F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1311 from Air to Milk,'" Institute fur Reaktorsicherheit, IRS-W-13, April-1975.

6.

C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs 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 of Cow's Milk as Critical Pathways for 1 37 Cs,

54Mn and 144Ce-144Pr 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 Radionuclide

s. 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

APPENDIX D

MODELS FOR CALCULATING POPULATION DOSES FROM

NUCLEAR POWER PLANT EFFLUENTS

Calculation of the annual population-integrated total body and thyroid doses* should be performed for the three effluent types identified in this guide.

These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D,Section II

of-Appendix I to 10 CFR Part 50.

For the purpose of calculating the annual population-integrated dose, the 50-mile region should be divided into a number of subregions consistent with the nature of the region.

These subregions may represent, for example, the reaches of a river or land areas over which the appro- priate dispersion factor is averaged.

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

1. General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con- sidered to be exposed to the average radionuclide concentrations estimated for the subregion,

,the annual population-integrated dose is calculated as follows:

D~j = O.Ol d*Pd Z Djdafda (D-l)-

d a

where Djda is the annual dose to organ j (total body or.thyroid) of an average individual of age group a in subregion d, in mrem/yr;

SP

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

in man-rems or thyroid man-rems;

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

P d is the population associated with subregion d; and

0.001 is the conversion factor from 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 population- integrated 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 contri- bution to the total population dose from all pathways.

In this context, a significant contribu- tion 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 concentra- tion is used in calculating the population doses.

The 50-mile average concentration of.nuclide in food p is computed as ip = (1/Vp) exp(-x itp)

P

Cdipvdp (D-2)

The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.

-1.109-30

where 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);

C ip is the 50-mile average concentration of nuclide iin pathway p, in

ip pCi/kg or pCi/liter;

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

in days (Table D-1 presents estimates of the transport times that may be used in lieu of site-specific data);

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

V

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

i is the radiological decay constant for nuclide i, in days- The population served by all the food produced within 50 miles of the site is estimated as Pp = V /I U f (D-3)

p .a ap a r

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

a P

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

likely to be produced within 50 miles of the site;

Ua is the use or consumption factor of food medium p for the average individual Uap in age group a, in kg/yr or liters/yr (taken from Table E-4); and V

is the annual mass or volume of food medium p likely to be produced within P

a 50-mile radius about the site, in kg or liters.

The annual population-integrated dose is then calculated as D 0.001 Y' P

p f

aC.i U

apDF ai(D-4)

Sp a

where

P p if P*p

< P 5 p

50

Pp .,

P5 if Pp > P5"

50]

50*

and DFai is the ingestion dose factor for age group a and nuclide i, in mrem/pCi (taken from Appendix E, Tables E-ll to E-14);

1.109-31

TABLE D-1 RECOMMENDED VALUESFOR THE TRANSPORT TIMES IN THE FOOD

DISTRIBUTION SYST-...

FOOD MEDIUM

Fruits, grains, and vegetables Milk Meat and poultry Sport fish Con*nercial 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

0)

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

!*

in man-rem/yr or thyroid man-rem/yr;

Pp is the population consuming food medium p; and P50

is the total populationwithin 50 miles.

All other factors are as defined above.

Note that the above formulation limits theevaluation 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 liq- uid effluents should be evaluated for the following principal pathways:

potable' water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri- gated with water that has received the liquid effluent.

(1)

Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump- tion are evaluated for all subregions that have water intakes existing or designated-at the time of the license application.

The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose.

The formulation expressed in Equation (D-1)

may be used.

The total body and thyroid dose of the individuals should be evaluated using

-Equation (A-2)

in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1 The dilution from the discharge point to the usage point'should be evaluated using appropriate hydrological models for the various subregions.

If the population served by a particular water supply. system is not known, it can be estimated by the following:

Pw e v/c (D-5)

where c

is the average daily usage of individuals on the system, in gal/day per person;

Pw is the estimated population served by the water system; and v

is the average daily intake of the water supply system, in gal/day.

If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation (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 via drinking water should be included in the 50-mile population dose evaluation.

1.109-33

(2)

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

The mixing ratio (or dilution) should be evaluated for each subregion using an appropriate hydrological model.

For sport harvests, the entire edible harvest is a'ssumed to be ingested by the population within 50 miles.

The formulation expressed by Equation.

(D-4) should be used with-the population Pp.given by the results of Equation (D-3).

The age- specific ingestion rates of Table E-4 may be used in lieu of site-specific data.

For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest.

Equation (D-2) should be used to compute the average concentration, with V as the total estimated U.S. commercial harvest of the aquatic food p

medium p.

The annual population--integrated dose is then computed using Equation (D-4) with Pp = P50.

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 summiing the product of the individual doses in each subregion and the population exposed therein.

All subregions within the 50-mile radius should be considered.where existing or designated recreational facili- ties exist.

If available, actual recreational usage in the vicinity of each facility should be used.

The formulation of Equation (D-l) 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-l may be used in lieu of site-specific data in the evaluation of Equation (D-4).

b.

Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should-be evaluated for the following principal exposure pathways:

noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and produce), and external irradiation from activity deposited on the ground.

Available state or county agricultural pro- duction 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 age- specific inhalation rates of Table E-4 may be used with the data of Tables E-7 to E-l0.

1.109-34

(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-l, 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-l).

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

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 staDle element transfer coefficients:

a.

Biv 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.

Fm for the estimation of cow milk activity from that in feed (pCi/i in milk per pCi/

day ingested by the animal); and c.

Ff 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/cm2 .

These tissue depths are indicated by Reference 12, where it is suggested that, for

1.109-36

TABLE E-1 STABLE ELEMENT TRANSFER DATA*

Element H**

C**

Na P

Cr Mn Fe Co Ni Cu Zn Rb Sr

'Y

Zr Nb Mo Tc Ru Rh Ag Te I

Cs Ba, La Ce Pr Nd W

Np Biv Veg/Soil

4.8E 00

5.5E 00

5.2E-02 l.IE 00

2.5E-04

2.9E-02

6.6E-04

9.4E-03

1 .9E-02

1 .2E-01

4.OE-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 l.3E 01 I .5E-01 l.3E 00

2.OE-02

1 .OE-02

5.OE-03

2.5E-03

2.4E-03

1 .8E-02

2.5E-03 F (Cow)

m Milk (d/z)

1 .OE-02

1.2E-02

4.0E-02***

2.5E-02

2.2E-03

2.5E-04

1 .2E-03 I .OE-03

6.7E-03

1 .4E-02

3.9E-02

3.OE-02

8.0E-04***

1.OE-05

5.OE-06

2.5E-03

7.5E-03

2.5E-02

1 .OE-06

1.OE-02

5.OE-02

1 .OE-03

6.OE-03t

1 .2E-02***

.4.0E-04"***

5.OE-06 l.OE-04***

5.OE-06

5.OE-04

5.OE-06 Ff Meat (d/kg)

1.2E-02

3.1E-02

3.OE-02

4.6E-02

2.4E-03

8.OE-04

4.OE-02

1.3E-02

5.3E-02

8.OE-03

3.0E-02

3.1E-02

6.OE-04

4.6E-03

3.4E-02

2.8E-01

8.OE-03

4.OE-01

4.6E-01

1.5E-03

1.7E-02

7.7E-02

2.9E-03

4.OE-03

3.2E-03

2. OE-04

1 2E-03

4.7E-03

3. 3E-03

1 .3E-03

2.OE-041t

'I'

N,

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.

tSee text.

ttFroim Reference 13.

1.109-37

TABLE E-2 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK*

Element H

C

P

Fe Cu Sr I

Cs Fm (days/liter)

0.17

0.10

0.25

1.3E-04

0.014"*

0.06&*

-0.30**

Values in this table are from References 1 and 14 unless otherwise indicated.

From Reference 15.

TABLE E-3 ANIMAL CONSUMPTION RATES

Animal Milk cow Beef cattle Goats Feed or Forage (kg/day [wet weight])

50 (Ref.

10)

50 (Ref. 10)

6 (Ref. 17)

QAw Water

(

R./day)

60 (Ref. 16)

50 (Ref.

16)

8 (Ref . 18)

IL

1.109-38

TABLE E-4 RECOMMENDED VALUES FOR U

TO BE USED FOR THE AVERAGE INDIVIDUAL

ap IN LIEU OF SITE-SPECIFIC DATA

Pathway Child Teen Adult Fruits, vegetables, &

grain (kg/yr)*

200

240

190

Milk (z/yr)*

170

200

110

Meat & poultry (kg/yr)*

37

59

95 Fish (kg/yr)*

2.2

5.2

6.9 Seafood (kg/yr)*

0.33

0.75

1.0

Drinking water (L/yr)**

260

370

Shoreline recreation (hr/yr)**

9.5

47

8.3 Inhalation (m3 /yr)

3700***

8000***

8000t 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 in Reference 20.

tData obtained directly from Reference 20.

1.109-39

TABLE E-5 RECOMMENDED VALUES FOR Uap TO BE USED FOR THE MAXIMUM EXPOSED

-

INfJVIDUAL IN LIEU OF SITE-SPECIFIC DATA

Pathway Fruits, vegetables &

grain (kg/yr)*,**

Leafy vegetables

(kg/yr)*

Milk (k/yr)*

Meat & poultry (kg/yr)*

Fish (fresh or salt)

(kg/yr)***

Other seafood (kg/yr)*

Drinkingwater (Z/yr)t Shoreline recreation (hr/yr)t Inhalation (m 3/yr)

Infant Child Teen Adult

520

26

330

630

520

330

42

64

400

310

65

110

16

21

41

6.9

1.7

510

3.8

5

330

510

730

14

3700ttt

67

8000tt-t

1400tt

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.

tData obtained directly from Reference 10.

.Data obtained directly from Reference 20.

tttiInhalation rate derived from data provided in Reference 20.

1.109-40

TABLE E-6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND

(mrem/hr per pCi/m2)

Element Total Body Skin

-H-3

0.0

C-14

0.0

NA-24

2.50E-08

2.90E-08 P-32

0.0

Cr-51

2.20E-10

2.60E-10

Mn-54

5.80E-09

6.80E-09 Mn-56 l.1OE-08

1.30E-08 Fe-55

0.0

.Fe-59

8.OOE-09

9.40E-09 Co-58

7.OOE-09

8.20E-09 Co-60

1.70E-08

2.OOE-08 Ni-63

0.0

Nr-65

3.70E-09

4.30E-09 Cu-64

1.51E-09

1.70E-09 Zn-65

4.OOE-09

4.60E-09 Zn-69

0.0

Br-83

6.40E-11

9.30E-11 Br-84

1.20E-08

1.40E-08 Br-85

0.0

Rb-86

6.30E-10

7.20E-10

Rb-B8

3.50E-09

4.O0E-09 Rb-89

1.50E-08

1.80E-08 Sr-89

5.60E-13

6.50E-13 Sr-91

7.10E-09

8 30E-09 Sr-92

.9.00E-09 IOOE-08 Y-90

2.20E-12

2.60E-12 Y-91M

3.80E-09

4.40E-09 Y-91

2.40E-ll

2.70E-11 Y-92

1.60E-09

1.90E-09 Y-93

5.70E-1O

7.80E-10

Zr-95

5.ODE-09

5-80E-09 Zr-97

5.50E-09

6.40E-09

Nb-95

5.10E-09

6.OOE-09 Mo-99

1.90E-09

2.20E-09 Tc-99M

9.60E-10

1.1OE-09 Tc-ll

2.70E-09

3.OOE-09 Ru-103

3.60E-09

4.2DE-09 Ru-105

4.50E-09

5.1DE-09 Ru-106

1.50E-09

1.80E-09 Ag-liOM

1.80E-08

2.10E-08 Te-125M

.3.50E-l1

4.80E-l1

.Te-127M

1.1OE-12

1.30E-12 Te-127

1.OOE-l1

1.1OE-11 Te-129M

7.70E-10

9.O0E-10

Te-129

7.10E-10

8.40E-10

Te-131M

8.40E-09

9.90E-09- Te-131

2.20E-09

2.60E-06 Te-132

1.70E-09

2.00E-09

1-130

1.40E-08

1.70E-08

1-131

2.80E-09

3.40E-09

1-132

1.70E-08

2.OOE-08

1-133

3.70E-09

4.50E-09

1-134

1.60E-08

1.90E-08

1-135

1.20E-08

1.40E-08

1.109-41

TABLE E-6 (Continued)

Element Cs.-134 Cs-136 Cs-1 37 Cs-138 Ba-139 Ba-1 40

Ba-141 Ba-142 La-I 40

La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 Total Body

1.20E-08

1.50E-08

4.20E-09

2. 1OE-08

2.40E-09

2. lOE-09

4.30E-09

7.90E-09

1.50E-08

5.50E-10

2.20E-09

3.20E-10

0.0

2.00E-10

1. OOE-09

3.10E-09

9.50E-10

Skin

1. 40E-08

1 .70E-08

4.90E-09

2.40E-08

2.70E-09

2.40E-09

4.90E-09

9.00E-09

1. 70E-08 I. 80E-08

6.20E-10

2.50E-09

3.70E-10

0.0

2.30E-10

1.20E-09

3.60E-09

1 .10E-09

1.109-42

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-l0 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 cal- culational 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 path- way.

Table E-15 has been organized to note these complications.

Values of the parameter SF,

a structural shielding and occupancy factor, are given in Table E-15 as 0.7 (for maximum individuals) and 0.5 (for the generalpopulation).

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

TABLE E-7 PASE

I OF

3 INHALATION DOSE FACTORS FOR AnULTS

(UREM

PER

PCI INHALED)

NUCLIDE

HONE

LIVER

T.ROCY

THYROID

KIDNEY

LUNG

GI-LLI

H

3 NO DATA

1.58E-07

1.58F-07

1.58E-C7 l.58E-07 1.58E-07

1.58E-07

1.4

2.27E-06

4.26E-07

4.26L-07

4.26E-07

4.26E-07 AA 24

1.28E-06

1.2RE-06

1.28E-06 p

32

1.65E-04

9.64E-06

6.26[-06 NO DATA

NC DATA

NO DATA

1.08E-05 CR 51 NO DATA

NO DATA

1.25E-08

7.44E-Oq

2.85E-09

1.80E-06

4.15F-07 MN 54 NO DATA

4.95E-0b

7.8rE-07 NO DATA

1.23L-06

1.75E-04 q.67E-06 MN 56 NO DATA

1.55E-10

2.29E-11

'0 DATA

1.63E-1O

1.18E-06

2.53E-06 FE 55

3.07E-06

2.12C-06

4.93E-07 NO DATA

NO DATA

9.C1E-06

7.54E-07 FE 59

1.47E-06

3.47E-0b

1.32E-06 NO DATA

NO DATA

1.27E-04

2.35E-05 CO 58 ND DATA

1.98E-07

2.59E-07 NO DATA

NC DATA

1.16E-04

1.13E-05, CO 60

NO DATA

1.44E-06

1.85E-36 NO DATA

NO DATA

7.4bE-04

3.56E-05 NJ1 63

5.40E-05

3.13E-06

1.81E-06 NO DATA

NO DATA

2.23E-05

1.67E-06

4l 65 I.92E-10

2.o2C-II

1.14F-11 NO DATA

NC DATA

7.0OE-07

1.54E-06 CU 64 NO DATA

1.93E-10

7.63F-11 NO

DATA

5.78E-1O

8.48E-07

6.12E-06 ZN 65

4.05E-06

1.29F-05

5.82E-06 NO DATA

R.62E-06

1.08E-04

6.68E-06 ZN 69

4.23E-12

8.14ý-12

5.65E-13 NO DATA

5.27L-12

1.15.E-07

2.04E-C9

ýAR 83 NO DATA

40 DATA

3.01E-08 NO DATA

NO DATA

2.90F-08

,R 84 NO DATA

NO DATA

3.91E-08 NO DATA

NO DATA

2.05E-13 diR 80

NO DATA

1.60E-09 NO DATA

NC DATA

NO DATA

LT E-24 RE!

8B

NO DATA

1.69E-D5

7.371E-06 NO DATA

NO DATA

2.08E-06 RB 88 NO DATA

.4.84E-08

2.41E-98 NO DATA

NO DATA

4.iB-I1 RB 89 NO DATA

3.20E-O8

2.12E-08 NO DATA

NO DATA

1.16F-21 SR

89

3.80E-05 NO DATA

1.09E-06 NO DATA

NO DATA

1.75E-04 4.37E-05 SR 90

1.24E-02 NO DATA

7.62E-04 NO DATA

NC DATA

1.20E-03

9.02E-05 SR 91

7.74E-Oq NO DATA

3.13E-1D

NO DATA

4.56E-06

2.39F-05 SR 92

8.43E-10

NO DATA

3.64E-11 NO DATA

NO DATA

2.06E-06

5.38E-06 Y

90

2.61E-07 NO DATA

7.01E-09 NO DATA

NO DATA

2.12E-05

6.32E-05 Y

9111

3.26E-11 NO DATA

1.27E-12 NO DATA

NC DATA

2.40E-07

1.66E-10

Y

91

5.78E-05 NO OArA

1.55E-06 NO

DATA

NO DATA

2.13E-04

4.81E-05 Y

92

1.29E-09 NO DATA

3.77E-11 NO DATA

NO DATA

I.q6E-06

9.19E-06

1.109-44

TABLF E-7, CONT'D

PASF

2 OF 3 INHALATION

DOCSE

FACTORS

FOR ADULTS

,(REM PFR PCI

INHALED)

.NUCL I ;L

BONE

LIVFR

T.-BODY

THYROID

KIDNEY

LUNG

GJ-LLI

'y

93

1.18E-Or NO DATA

3.26E-10

NO

DATA

NC

DAT.A

0.06E-06

5.27E-05 I

ZR

95

1.34E-05

4.3CE-06

2.91E-06 NO

DAT4

6.77E-06

2.21E-04

1.38E-05 ZR 97

1.2IF-O8

2.45E-09

1.13E-09 NO

DATA

3.71E-09

9.84E-C3

6.54E-05 NB 95

1.76E-06

9.77L-07

5.26E-07 NO DATA

9.67E-07

6.31E-05

1.30F-05 MO 99.

AJO DATA

1.I5-1

8

2.87E-09 NO DATA

3.64E-OB

1.14E-05

3.10E-05 TC

99M,'

1.29E-13

3.64F-13

4.63E-12 NO DATA

5.52E-12

9.55E-08

5.20E-07 TC101

5."'2E-15

7.52E-15

1.36E-14 NO DATA

-1.35E-13

4.99E-08

1.36F-21 RU*03

1.91E-07 NO DATA

8.23E-08 NO DATA '7.29E-07

6.31E-05

1.38E-05 RUIC5

9.88E-11 NO DATA

3.89E-1i NO

DATA

1.27E-10

1.37E-06 6.02E-06 RUI06

8.64E-C6 NO

DATA

l.O)E-06 NO DATA

1.67E-05

1.17E-03

1.14E-04 AG110

1.35C-,6

1..25.-06

7.43,--07 NO

DATA

2.46E-06

5.790-04

3.78E-05 TC125M1

4.27E-07

1.Q9E-O7

5.84E-08

1.31E-07

1.5

5 E-06

3.92E-C5

8.83E-06 TE127r'

1.58F-06

7.21C-07

1.96E-07

4..1iE-07

5.72E-06

1.20E-04

1.87E-05 TE127

1.75[-10

8.OC'3-Il

3.87E-11

1.32E-10

6.37E-10

8.14E-07

7.1.7-06 IE129P

1.22E-06

5.84's-07

1.96E-O7

4.30E-07

4.57E-06 l.45E-O4

,.79-05 TE129

6.220-12

2."9L-12

1.5'.)E-12

4.87E-12

2.34E-11

2.42E-07 I.96F-08 TEI3lM

8.14E-09

5.45E-09

3.63F-09

6.88E-09

3.86E-08

1.82E-05

6.95E-05 TF131

1.39E-12

7.44E-13 4.49E-13

1.17T-12

5.46E-12

1.74=-07

2.30E-09

1E132

3.25L-08

2.69E-08

2.0O?-08

2.37E-08

1.82E-07

3.60E-05

6.37F-05

1 1.30

5.72E-07 I.o8E-O6

6.6;C-07

1.42E-04

2.61E-06 NO DATA

9.61E-07

1 131

3.15E-06

4.47E-io

2.56E-06

1.49E-03

7.66E-06 NO [ATA

7.85F-07

1 132

1.45E-07

4.07E-07

1.45E-07

1.43E-05

6.48E-07 NO DATA

5.08F-08

1 133

1.08E-06

1.85E-06

5.65E-07

2.69E-04

3.23E-06 NO DATA

1.11F-06 I

134

,.05-08

2.160-07

7.69E-08

3.73E-06

3.44E-07 NO DATA

1.26E-1O

I

135

3.35E-C7

8.73E-07

3.21E-07

5.bOE-C5

1.39E-06 NO DATA

6.56E-07 CS134

4.66E-05

1.06E-04

9.10-05 NO DATA

3.59E-C5

1.22E-05

1.30E-06 CS136

4.88E-C6

1.F3Z0-05

1.3 3q-05

'40 DATA

I.,07E-05

1.50E-06

1.46E-06

--S137

5.98E-05

7.760-05

5.35[-05 NO

DATA

2.78E-q5

9.40E-06

1.052-06 CS13'i

4.14E-08

7.767-08

4.0jE-38 NO

,ATA

6.OE-09

6.07E-09

2.33E-13 a139

1.17-.-10

-14

3.42-12 NO

DATA

7.78E-14

4.70E-07

1.120-07

1.109-45 A!!

TABLL E-7, CONT'D

PAGE

3 OF

3 INHALATION DUSE FACTORS' FOR ADULTS

(MREM PER PCI

INHALED)

NUCLICE

BONE

LIVER

T.BcY

THYROID

KIDNEY

LUNG

GI-LLI

sA140,

4.F8E-O6 b.13F-09

1.21E-07 NO DATA

2.O9E-09

1.59E-04

2.73F-05

-AI41

1.25E-11

9.41tz-15

4.2CE'-13 NO DATA

8.75E-15

2.42E-07

1.45E-17 RAI42

3.29E-12

3.38E-15

2.07E-1I

NO DATA

2.96E-15 I.49E-O

1.96E-26 LA140

4.30E-C8

2.171-08

5.73E-09 NU DATA

NO DATA

.1.70E-0.5

5.73E-05 LA142

8.54E-1i

3.88E-11

9.65E-12 NO DATA

NO DATA

7.91F-07

2.64E-07 CE4I1

2.49E-O0

1.69;--06

1.91E-07 NO DATA

7.83E-07

4.52E-05

1.50E-05

E143

2.33E-08

1.72E-o0

1.91E-O9 NO DATA

7.60E-0

9 .97E-06

2.83E-05

-E144

4.29E-04

1.79E-04

2.30E-05 NO DATA

1.ObE-04

9.72E-04

1.02E-04 PR143

1.17E-06

4.69E-07

5.80E-O8 NO DATA

2.70E-07

3.51E-05

2.50E-05 PR144

3.76E-12

1.56E-12

1.91E-13 NO

DATA

8.RIE-13

1.27E-07

2.69E-18 OD147

6.59E-07 7.62E-07

4.56E-08 NO DATA

4.45E-07

2.76E-05

2.16E-05 w 187 I.06E-09 B.85E-10

3.10E-IO

NO

DATA

NO DATA

3.63E-06

1.q4E-05 NP239

-2.87E-O8

2.S2E-09

1.55E-09 NO DATA

8.75E-09

4.70E-06

1.49E-05

1.109-46

77

$

TABLE E-8 PAGE

1 OF 3 INHALATION DOSE FACTORS FOR

TEENAGER

(NREM

PER PCI

INHALED)

14UCLICE

BONE

LIVER

T.BODY

THYROID

KIDNEY

LUNG

GI-LLI

H

3 NO DATA

1.59E-07

1.59F-07

1.59E-07

1.59E-07 C

14

3.25E-06

6.C9E-07

6.09E-07

1A 24

1.72E-06

1.72[-06

1.72E-06

1.72E-06 P- "32

2.36E-04

1.

37E-05

8.95E-06 NO DATA

NC DATA

NO DATA

1.16F-05 CR 51 NO DATA

NO DATA

1..69E-08

9.37E-09

3.842-09

2.62E-06

3,75E-07 M N 54 NO DATA

6.39F-06

1.OE-O6 NO DATA

1.59E-06

2.48E-04

8.35E-06 MN 56- NO DATA

2.1 2 E-1O 3.15E-11 NO DATA

2.24E-10

1.90E-06

7.18E-06 FE-55

4.18E-06

2.98E-06

6.93E-07 NO DATA

NO DATA

1.55E-05

7.99E-07 FE 53

1.99E-06

4.62E-0.6

1.79E-06.

NO DATA

L.91F-04 2.23E-05 CO 58.

NO DATA

2.59E-07

3.47E-07 NO DATA

NO DATA

1.68E-04

1.19E-05 CO 60

NO DATA

L.89E-06

2.48E-06

-NO DATA

NO DATA

1.09E-03

3.24E-.05 NI 63

7.25E-05

5.43E-06

2.47E-06 NO DATA

NO DATA

3.84E-05

1.77E-06

'I 6ý5

2.73E-10

3.uo6-1l

1.59E-11 NO DATA

NO

DATA

1.17E-06

4.59E-06 CU 64 NO DATA

2.54E-10

1.06E-10

NO DATA

8.01E-10

1392E-06 7.68E-06 LN 65

4.82E-06

1.67E-05

7.80E-06 NO DATA

1.08E-05

1.55E-04

5.83E-06

N 69

6.04E-12

1.15F-11

8.07E-13 NO DATA

7.53E-12 I.q8E-07

3.56F-08 HR 83 NO DATA

NO DATA

4.30E-00

NO DATA

NO

DATA

NO DATA

LT E-24 L3R 84 NO DATA

NO DATA

5.41E-08 NO DATA

NO

DATA

NO DATA

LT E-24 riR 85 NO DATA

NO DATA

2.29E-09

-NO DATA

NO DATA

LT E-24 RB 86 NO DATA

2.38E-05

1.05E-05- NO DATA

NO DATA

2.21E-06 R

8'3 NO DATA

6.82E-08

3.40E-08 NO DATA

NO DATA

3.65E-15 RB 89 NO DATA

4.402-08

2.9.1E-08 NO DATA

NO DATA

4.22E-17 SR 89

5.43E-05 NO DATA

1.56E-06 NO DATA

NO DATA

3.02E-04

4.64E-05 SR q3

1.35E-02 NO DATA

8.35E-04 NO DATA

NO DATA

2.06E-03

9.56E-05 SR 91

1.10E-08 NO DATA

4.39E-10

NO DATA

7.59E-06

3.24E-05 SR 92

1.19E-09 NO DATA

5.08EI-

NO DATA

3.43E-06

1.49E-05 Y

90

3.73E-07 NO DATA

1.OE-08 NO DATA

NO DATA

3.66E-05

6.99E-05 Y

91M

4.63E-11 NO DATA

1.77E-12 NO DATA

NO DATA

4.0OE-07

3.77E-09 Y

91

8.26E-05 NO DATA

2.21E-06 NO DATA

NO DATA

3.67E-04

5.11E-05 Y

92

1.84E-0q NO DATA

5.36E-11 NO DATA

NO DATA

3.35E-06

2.06E-05

1.109-47

TABLE E-8, CONTID

PAGE 2 OF

3 lNHALtCTIOA DOSE

FACTORS FOR TEFNAGFR

(MREM

PER PCI

INHALED)

IRJCLIDE

BONE

LIVFR

T.AODY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

1.69E-08 NO DATA

4.65E-10

NO DATA

1.04E-05

7.24E-05

!R 95

1.82E-05

5.73c-O

3.94E-06 NO DATA

8.42E-06

3.36E-04

1.86E-05 ZR 97

1.72E-08

3.40E-09

1.57E-09 NO DATA

5.15E-09

1.62E-05

7.88E-05 iDl 95

2.32E-06

1.29E--b

7.08E-07 NO DATA

1.25E-06

9.39E-05

1.21E-05 MO 99 AJ0 DATA

2.l1E-08

4.03E-09

40 CATA

5.14E-08

1.92E-05

3.36E-05 IC

99M

1.73E-13

4.83E-13 b.24E-12 NO DATA

7.20E-12

.1.44E-01

7.66E-07 TCIOI

7.40E-15

1.OE-14

1.03E-13 NO DATA

1.90E-13 F.34E-0O

1.09E-16 RU103

2.63E-07 NO CATA

1.12C-07 NO DATA

9.29E-07

9.79E-05

1.36F-05 RU1O5

1.40E-10

NO DATA

5.42E-11 NO DATA

1.76E-0O

2.27E-06

1.13E-05 RULOb

1.23F-05 NO DATA

1.55E-06 NO DATA

2.38E-05

2.01E-03

1.20E-04 AGtlOM

1.73E-06

1.64E-Ob

9.99E-0-7 NO DATA

3.13E-06 B.44E-04

3.41F-05 TE12SM

6.lOE-07

2.80E-07

8.34E-08

1.75E-07 NO DATA

6.70E-05

9.38E-06 TE127M

2.?5E-06

1.CF-0O

2.73E-07

5.48E-07

8.17E-06

2.07E-04

1.99E-05 TE127

2.51E-10

1.14F-1O

5.52E-11

1.77E-10

9.1OE-1O

1.40F-06

1.OIE-05 rE129m

1.74E-06

8.

2 3E-07

2.81E-07

5.72E-07

6.49E-06 2.47E-04

5.06E-05 TF129

8.87E-12

4.22E-12

2.29E-12

6.4RE-12

3.32E-11

4.12E-07

2.02E-07 rEl31

1.23E-08

7.51E-09

5.03E-09

'.3/406E-09

5.49E-08

2.97E-05

7.76E-05 TEl31

1.97E-12

1.04E-12

6.30E-13 I..55E-12

7.72E-12

2.92E-07

1.89E-09 TE132

4.50E-08

3.63E-08

2.74E-08

3.07E-08

2.44E-07

5.61E-05

5.79F-05 I 130

7.80E-07

2.247-06

8.9oE-07

1.86E-04

3.44E-06 NO DATA

1.14E-06

1 131

4.43E-06

6.14F-06

3.30E-06 I.83E-03

1.05E-05 NO DATA

8.11F-07 I

132

1.99E-07

5.47E-07 l.q7E-07

1.89E-05

8.65E-07 NO DATA

1.59E-07

1 133

1.52F-06

2.,bE-Cb

7.78E-97

3.b5E-04

4.49E-06 NO DATA

1.29E-06 I 134

1.1IE-07

2.90E-07

1.05E-07

4.94E-06

4.58E-07 NO DATA

2.55E-09

1 135

4.62E-07

1.18E-Ob

4.36E-07

7.76E-05

1.86E-06 NO DATA

9.69E-07 CS134

6.28E-05

1.41E-O

b.8oE-05 NO DATA

4.69E-05

1.83E-05

1.22E-06 CS136

6.44E-06

2.42C-05

1.71E-05 NO DATA

1.38E-05

2.22E-06

1.36E-06 CS137

8.38E-05

1.06E-04

3.89E-O5 NO DATA

3.80E-05

1.51F-05

1.06E-06 CS138

5.82E-08

1.07E-07

5.59E-08 NO DATA

8.28E-08

9.84E-09

3.38E-1l BA[39

1.67E-10

1.IE-13

4.87E-12 NO DATA

I.IIE-13

8.08E-07

8.06E-07

1.109-48

'TAtLiLE

E-8, CONT'IC

PAGE 3 OF

3 INHALATION

00[SE F.ACTORS FOR

TEENAGER

(MREM

PER PCT

INHALED)

NULO

DOE

LIL

T.3CCY

THYOC

KIDNEY

LUNG

GI-L

,3&140O

6.84E-06 A. 58F-09

4.40E-07 NIO DATA

2.85E-n9

2.54E-04

2.86E-05

1dA41

1.78E-11 l..12F-1[4

5.93[-13 NO

DATA

1.23E-14

4.11E-07

9.33E-14

!AA2

4.62E-12

4.63E-15) 2.84F-13 NO DATA,

3.92E-15

2.39E-07

5.99E-20

LA140

5.99E-08

2.951E-08

7.82--09 NO UATA

NO DATA

2.68E-05

6.09E-05 LA142

1.200-10

5.31E-11

1.32E-11 NO DATA

N' DATA

1.27E-06 1.50[-06 CE141

3.55E-06

2.37ý-Oh

2.71E-07 NO DAT4

1.11L-06 7.67E-05

1.58E-05 CE143

3.32E-08

2.4/2E-08

2.70E-09 NO DATA

I.08 R-08

1.63E-0'5

3.19E-05 CE144

6.11E-04

2.53E-04

3.23E-05 NO DATA

1.51E-04

1.67E-03

1.08E-04

.

PR143

1.67E-06

6.64E-07

3.2SE-O8 NO DATA

3.86E-07

6.04E-05

2.67E-05 PI,144

5.37E-12

2.20E-12

2.72E-13-- N'O DATA

1.26E-12

.2.19E-C7 2.94E-14 NIC4

147

9.83E-07

1.07E-Ob

6.41E-08 NO DATA

b.2qE-07

4.65E-05

2.28F-05 W 187

1.50E-09

1.22c-O9 4.29E-IC

NO DATA

5.q2E-06

2.21F-05

.. P239

4.23E-08

3.99E-09

2.21E-09 NU

DATA

1.25E-08

8.11E-06

1.65E-05 i4 4

1.109-49 O -.

TABLE E-9 PAGE

1 OF 3

-

INHALATION DCSE FACTORS FOR CHILD

(MREM

PER

PCI

INHALED)

NUCLIUE

BONE

LIVER

T.BOCY

THYROID

KIDNEY

LUNG

GI-LLI

11

3 NO DATA

3.04E-97

3.04E-07

3.04E-07 C

14

9.70E-06

1.82E-06

1.82E-06 NA.24

4..35E-06

4.35:-06

4.35E-06

4.35E-C6

4.35E-06

4.35E-06 P

32.

7.04E-04

3.CgE-05

2.671-05 NO DATA

NO DATA

Nn DATA

1.14E-05 CR 51.

NO DATA

4.17E-08

2.31F-O8

6.57E-09

4.59E-06.,

2.93E-07 MN 54

'4O DATA

1.16:-05

2.57E-Ob NO DATA

2.71E-06

4.26F-04

6.19F-06 MN 56 NO DATA

4.48E-10

8.43E-11 NO DATA

4.52E-10

3.55E-06

3.33E-05 FE 55

1.28E-05

6.D0E-0o

2.10E-06 NO DATA

NO DATA

3.OOE-05

7.75E-07 FE 59

5.59E-06

9.C4E-06

4.51E-06 NO DATA

NO DATA

3.43E-04

1.91E-05 CO 58 NO DATA

4.79E-O7

8.55E-07 NO DATA

NO DATA

2.99E-04

9.29E-06 CO 60

NO DATA

3.55E-06

6.12E-06 Nil DATA

NO DATA

1.91E-03

2.60E-05 NI 63

2.22E-04

1.25E-05

7.56E-06 NO DATA

NO DATA

7.43E-05 I.71E-06

4I 65

8.08E-10

7.99E-11

4.44E-11 Nfl DATA

NU DATA

2.21E-06

2.27E-05 CU 64 NO DATA

5.39E-10

2.90E-10

NO DATA

1.63E-09

2.59E-06 q.92E-06 ZN 65

1.15E-05

3.06E-05

1.90E-05 NO DATA

1.93E-05

2.69E-04

4.41E-06 ZN 69

1.81E-[1

2.61E-11

2.41E-12 NO DATA

1.58E-11

3.84E-07

2.75F-06 MR 83 NO DATA

NO DATA

1.28E-07 NO DATA

NO DATA

LT E-24 aR 84 NO DATA

NO DATA

1.48E-07 NO DATA

NO DATA

LT E-24

!R 85 NO DATA

NO DATA

6.84E-09 NO DATA.

NO DATA

LT E-24 R( 86 NO DATA

5.36E-05

3.09E-O5 NO DATA

NO DATA

2.16E-06 RE' 88 NO DATA

1.52E-0T

9.90E-08 NO DATA

NO DATA

NO

DATA

4.66E-09 RB 89 NO DATA

9.33E-08

7.8.E-O8 NO DATA

NO DATA-

NO

DATA

5.11E-1O

SR 89

1.62E-04 NO DATA

4.66E-06 NO DATA

NO DATA

5.83E-04

4.52E-05 SR 9O

2.73E-02 NO DATA

1.74E-03 NO DATA

NO DATA

3.99E-03

9.28E-05 SR 9L

3.28E-08 NO DATA

1.24E-09 NO DATA

NO DATA

1.44E-05

4.701-05 SR 92

3.54E-09 NO DATA

1.42E-10

NO DATA

6.49[-06

6.55E-05 Y

90

1.1IE-06 NO DATA

2.99E-08 NO DATA

NO DATA

7.07E-05

7.24E-05 Y

91P

1.37E-1O

NO DATA

4.98E-12.

NO DATA

7.60F-O0

4.64E-07 Y

91

2.47E-04 NO DATA

6.59E-06 NO DATA

NO DATA

7.10E-04

4.97E-05 Y

92

5.50E-09 NO DATA

1.57E-1O

NO DATA

6.46E-C6

6.46E-05

1.109-50

TABLL

E-9, CONTOD

PASE 2 OF 3 INHALATION

DLSE FACTORS FOR CHILD

(MREýM PER PCI INHALED)

I DUCLIE BU.E

LIVER

T. LsOGY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

5.04E-08 NO DATA

1.38E-09 NO DATA

NO DATA

2.0IE-05

1.05E-04 ZaR 95

5.13E-05

1.13E-05

1.OOE-05 NO DATA

1.61E-05

6.03E-04

1.65E-05 IR 97

5.07E-08

7.34E-09

4.32E-09 NO DATA

1.05E-08

3.06E-05

9.49E-05

"NA 95

6.35E-06

2.48E-06

1.77E-06 NO DATA

2.33E-06

1.66E-04 l.OOE-05 IMO 99 NO DATA

4.66E-08

1.15E-08 NO DATA

1.06E-07

3.66E-05

3.42E-05 TC 99'

4.81E-13

9.41E-.13

1.56E-11 NO DATA

1.37E-11

2.57E-C7

1..0E-06 TC10

2.19E-14

2.30E-14t

2.91E-13 NO DATA

3.92E-13

1.5RE-07

4.41F-09 PU103

7.55E-07 NO DATA

2.90E-07 NO DATA

1.90E-06

1.79E-04

1.21E-05 RUIO5

4.13E-1O

NO DATA

1.5OE-10

NO DATA

3.63E-10

4.30E-06

2.69E-05 RU106

3.68E-05 NO DATA

4.57E-06 NO DATA

4.97E-05

3.87E-03

1.16E-04 AGILOM 4.56E-06

3.08E-06

2.47E-06 NO DATA

5.74[-06

1.48E-03

2.TIE-05 TEI25M

1.82E-06

6.29E-07

2.47E-07

5.20E-07 NO DATA

1.29E-04 9.13E-06 TE127M

6.72E-06

2.31E-06

8.loE-07

1.64E-06

1.72E-05

4.OOE-04

1.93E-05 TE127

7.49E-10

2.57E-10

1.65E-10

5.30E-iO

1.91E-09

2.71F-06

1.52E-05

1E129M

5.19E-C6

1.85E-06

8.22E-07 t.71E-06 1.36E-05

4.76E-04

4.91E-05 TE129

2.b4E-11

9.45E-12

6.44[-12

1.93E-11

6.94L-1i

7.94E-07

6.89E-06 TE131m

3.63E-08

1.60E-08

1.37E-08

2.64E-08

1.08E-07

5.56E-05

8.32F-05 rE131

5.87E-12

2.28E-12

1.78E-12

4.59E-12

1.59s-Il

5.55E-07

3.60E-07 TE132

1.30E-07

7.36E-08

7.12E-08

8.58E-08

4.79E-07

1.02E-04 3.72E-05

1 .1.30

2.21E-06

4.43E-06

2.28E-06

4.99E-04

6.61L-06 NO DATA

1.38E-06

1 131

1.30E-05

7.37F-Ob

4.39E-03

2.13E-05 NO DATA

7.68E-07

1 132

5.72E-07

1.10E-06

5.01E-07

5.23E-05

1.69E-06 NO DATA

8.65E-07

1 133

4.48E-06

5.497-06

2-.08E-06

1.04E-03

9.13E-06 NO DATA

1.48E-06

1 134

3.17E-07

5.84E-07

2.69E-07

1.37E-05

8.92E-07 NO DATA

2.58E-07

[35

1.33E-06

2.36E-06

1.12E-06

2.14[-04

3.62E-06 NO DATA

1.20E-06 CS14

1. 76E-04

2.742-04

6.07E-05 AD DATA

8.93E-05

3.27E-05

1.04E-06 CS136

1.76E-05

4.62E-05

3.14E-05 NO DATA

2.58E-05

3.93E-06

1.13E-06 CS137

2.45E-04

2.23E-04

3.47F-05 NO DATA

7.63E-05

2.81E-05

9.78E-07 CS138

1.71E-07

2.27E-07

1.50E-07 NO DATA

1.68E-07

1.84E-08

7.29E-08

, A139

4.98E-10

2.66F-13

1.45E-1i NO DATA

2.33E-13

1.56E-06

1.56E-05 l0a,

TABLE E-9, CONTIC

PAGE 3 OF 3 INHALATION DOSE FACTORS

FOR CHILD

(MREM

PER PCI INHALED)

NUCLIDE

BONE

LIVER

T.RODY

THYROID

KIDNEY

LUNG

GI-LLI

GA140

2.00E-05

1.75E-08 I.I7E-06 NO DATA

5.T7E-09

4.71E-O4

2.75E-05 BA[41

5.291E-11

2.95E-14

1.72F-12 NO DATA

2.56E-14

7.89E-07

7.44E-08 BA142

1.35E-11

9.73E-15

7.54E-13 NO DATA

7.87E-15

4.44E-07

7.41F-10

LAI40

I.74E-07

6.OBF-08

2.04E-08 NO DATA

NO DATA

4.94E-05

6.IOE-05 LAI42

3.50E-10

1.I1E-IO

3.49E-LI

Nfl DATA

NO DATA

2.35F-06

2.05E-05 CEI14

1.06E-05

5.28E-06

7.83E-07 NO DATA

2.31E-06

1.47E-04

1.53E-05 CE143

9.89E-o8 5.37L-08

7.77E-09 NO DATA

2.26E-OB

3.I2E-05

3.44E-05 CE144 I.B3E-03

5.72E-04

9.77E-05 NO DATA

3.17E-04

3.23E-03

1.05E-04 PR143

4.99E-06

1.50E-06

2.47E-0.7 NO DATA

8.1IE-07

1.17E-04

2.63E-05 PR144

1.b6E-11

4.99E-12

8.10E-13 NO DATA

2.64E-12

4.23E-07

5.32E-08 ND147

2.q211-06

2.36E-06

1.84F-07 NO DATA

1.30E-06

8.87L-05

2.22F-05 W 187

4.*dE-09

2.61[-09

1.17F-09 NO DATA

NC DATA

1.1LF-05 2.46E-05 NP239

1.26E-07

9.04-09 6.35E-09 NO DATA

2.63E-OB

1.5TE-05

1.73E-05

1 .109-52

TA13LE E-10

PAGE

1 OF 3 INHALATION DOSE FACTORS FOR

INFANT

(MREM

PER PCI

INHALED)

NUCLIDE

BONE

LIVER

T.3ODY

THYROID

KIDNEY

LUNG

GI-LLI

H

3 NO DATA

4.62E-07

4.62F-67 4.62E-07

4.62E-07

4.62E-07 C

14

1.89E-05

3.79C-06

3.79E-06

3.79P-06

3.79E-06

3.79E-06 NA 24

7.54E-06

7.54E-06 P

32

1.45E-03

8.03E-05

5.53E-05 NO DATA

NO DATA

1.15E-05 CR 51 NO DATA

NO DATA

6.31E-08

4.11E-08

9.45E-09

9.17E-06

2.55E-07 MN 54 NO DATA

1.81E-05 3.56[-06 NO DATA

3.56E-06

7.14E-04

5.04E-06 MN 56 NO DATA

1.10E-09

1.58E-10

NO DATA

7.86E-10

P.95E-06

5.12E-05 FE 55

1.41E-05

8.39L-Ob

2.38E-06 NO DATA

NO DATA

' 6.21E-05

7.82E-07 FE 59

9.69E-06

1.b6E-05

6.77E-06 NO DATA

NO DATA

7.25E-04

1.77E-05 CO 58 NO DATA

8.71E-07

1.30E-06 NO DATA

NO DATA

5.55E-04

7.95F-06 CO 60

NO DATA

5.73E-06

8.41E-06 NO DATA

NO DATA

3.22E-03

2.28E-05 NI 61

2.42E-04

1.46E-05

8.29E-06 NO DATA-

NO DATA

1.49E-04

1.73E-06 NI 65

1.71E-09 2.303-10

8.79E-11 NO DATA

NO DATA

5.80E-06

3.58E-05 CU-64 NO DATA

1.34E-09

5.53E-10

NO DATA

2.84E-09

6.64E-06

1.07E-05 ZN 65

1.38E-05

4.,,7F-05

2.22E-05 NO DATA

2..32E-05

4.62E-04

3.67E-05

(01

7N 69

3.P5E-11

6.91g-ll

5.13E-12 NO DATA

2.87E-I1

1.05E-06

9.44E-06 RR 83'

NO DATA

2.72E-07 NO DATA

NO DATA

LT F-24 HR 84 NO DATA

NO DATA

2.86E-07 NO DATA

NO DATA

LT E-24 RR 8>

ýNO DATA

NO

DATA

1.46E-08 NO DATA

NC DATA

NO DATA

LT E-24 IB 8b NO DATA

1.36E-04

6.30E-05 NO DATA

NO DATA

- 2.17E-06

'ýB 88 N(l UATA

3.98F-07

2.0DE-O7 NO DATA

NO DATA

2.42E-07 RB 89 NO DATA

2.29E-07

1.47E-07 NO DATA

NO DATA

4.87E-08 SR 89

2.84E-04 NO DATA

8.15E-06 NO DATA

NO DATA

1.45E-03

4.57E-05 SR 90

2.92E-02 NO DATA

1.85F-03 NO DATA

NC DATA

8.03E-03

9.3b6-05 SR 91

6.83E-O

NO DATA

2.47E-09 NO DATA

NO DATA

3.76E-05

5.24E-05 SR 92

7.50E-09 NO

DATA

2.79E-10

NO DATA

1.70E-05

1.00E-04 Y

90

2.15L-06 NO

DATA

6.30E-08 NO DATA

NO DATA

1.92F-04

7.43E-05

Y

91,

2.AIE-10

NO

DATA

,

9.qOE-12 NO DATA

NO DATA

1.99E-06

1.68E-06 Y

91

'.?OE-04 NO DATA

1.12E-05 NO DATA

NO DATA

1.75E-03

5.02E-05 Y

92

1.L7E-08 NO

DATA

3.29E-10

NO DATA

1.75E-05

9.04E-05

1.109-53

TABLE E-1Ot CONTID

PAGE 2 OF 3 INHALATION DOSE FACTORS FOR INFANT

(MREM

PER PCI INHALED)

NUCLIDE

BONE

LIVER

T.BODY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

1.07E-07 NO DATA

2.91E-09 NO DATA

NO DATA

5.46E-05

1.19E-04 ZR 95

8.24E-05

1.99E-05

1.45E-05 NO DATA

2.22E-05

1.25E-03

1.55E-05 ZR 97

1.07E-07

1.83E-08

8.36E-09 NO DATA

1.85E-08 7.88E-05

1.0OE-04ý

NB 95

1.12E--05 4.59E-06

2.70E-06 NO DATA

3.37E-06

3.42E-04

9.05E-06 Mo 99 NO DATA

1.18-07

2.31E-08 NO DATA

I1R9E-07

9.63E-05

3.48E-05 TC 99M

9.98E-13

2.06E-12

2.66E-11 NO DATA

2.22E-11

5.79E-07

1.45E-06 TCIOI

4.65E-14

.5.98E-14

5.80E-13 NO DATA

6.99E-13

4.17E-07

6.03E-07

'RUI03

1.44E-06 NO DATA

4.85E-07 NO DATA

3.03E-06

3.94E-04

1.15E-05 RUI05

8.74E-10

NO'DATA

'2.93E-10

NO DATA

6.42E-10

1.12E-05 3.46E-05 RU106

6.20E-05 NO DATA

7.7.7E-06 NO DATA

7.61E-05

8.26E-03

1.17E-04 AGLIOM

7.13E-06. 5.16E-06

3.57E-06 NO DATA

7.80E-06' 2.62E-03

2.36E-05 TE125M

3.40E-06

1.42E-06

4.70E-07

1.16E-06 NO DATA

3.19E-04

9.22E-06 TE127M

1.19E-05

4.93E-06 I1.4BE-D6

3.48E-06

2.68E-05

9.37E-04

1.95E-05 TE12T

1.59E-09

6.81E-10

3.49E-10

1.32E-09

3.47E-09

7.39E-06

1.74E-05 TE129M

I.OIE-05

4.35E-06

1.59E-06

3.91E-06

2.27E-05

1.20E-03

4.93E-05 TE129

5.63E-11

2.48E-1I

1.34E-11

4.82E-11

1.25E-10

2.14E-06

1.88E-05 TE131M

7.62E-08

3.93E-08

2.59E-08

6.38E-08

1.89E-07

1.42E-04

8.51E-05 TE131

1.24E-11

5.87E-12

3.57E-12

1.13E-l

2.85E-11

1.47E-06

5.87E-06 TE132

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

9.91E-06

3.98E-06

1.14E-03

1.09E-05 NO DATA

1.42E-06

.1 131

2.71E-05

3.17E-05

1.40E-05

1.06E-02 3.70E-05 NO DATA

7.56E-07

1 132

1.21E-06

2.53E-06

8.99E-07

1.21E-04

2.82E-06 NO DATA

1.36E-06

1 133

9.46E-06

1.37E-05

4.OE-06

2.54E-03

1.60E-05 NO DATA

1.54E-06

1 134

6.58E-07

1.34E-06

4.75E-07

3.18E-05

1.49E-06 NO DATA

9.21E-07 I 135

2.76E-06

5.43E-06

1.98E-06

4.97E-04

6.05E-06 NO DATA

1.31E-06 CS134

2.83E-04

5.02E-04

5.32E-05 NO DATA

1.36E-04

5.69E-05

9.53E-07 CS136

3.45E-05

9.61E-05

3.7BE-05 NO DATA

4.03E-05

8.40E-06

1.02E-06 CS137

3.92E-04

4.37F-04

3.25E-05 NO DATA

1.23E-04

5.09E-05

9,.53E-07 CS138

3.61E-07

5.58E-07

12.84E-OT

NO DATA

2.93E-07

4.67E-08

6.26E-07'

BA139

1.06E-09 7.03E-13

3.07E-11 NO DATA

4.23E-13

4.25E-06

3.64E-05

1.109-54

TABLE E-1O,

CONT'D

PAGE

3 OF

3 INHALATION

DOSE

FACTORS FOR

INFANT

(MREM

PER PCI INHALED)

NuCLIOE

BONE

LIVER

F.BODY

THYROID

KIDNEY

LUNG

GI-LLI

BA140

4.OOE-05

4.OOE-08

2.07E-06 NO DATA

9.59E-09

1.14E-03

2.74E-05 BAl4L

L.12E-1O

7.70r-14

3.55E-12 NO DATA

4.64E-14

2.12E-06

3.39E-06 BA142

2.84E-11

2.36E-14

1.40E-12 NO DATA

1.36E-14

1.I1E-06

4.95E-07 LAI40

3.61E-07

1.43E-07

3.68E-08 NO DATA

NO DATA

1.20E-04

6.06E-05 LA142

7.36E-10

2.69E-1O

6.46E-II

NO DATA

5.87E-06

4.25E-05 CE141

1.98E-05

1.19E-05

1.42E-06 NO DATA

3.75E-06

3.69E-04

1.54E-05 CE143

2.09E-07 I.18E-07 I.58E-08 NO DATA

4.03E-08

8.30E-05

3.55E-05 CE144

2.28E-03

8.05E-04

1.26E-04 NO DATA

3.84E-04

7.03E-03

1.06E-04 PR143

1.OOE-05

3.74E-06

4.99E-07 NO DATA

1.41E-06

3.09E-04

2.66E-05 PR144

3.42E-1I

1.32E-11

1.72E-12 NO DATA

4.80E-12

1.15E-06 3.06E-06 NDI47

5.b7E-O6

5.81F-06

3.57E-07 NO DATA

2.25E-06

2.30E-04

2.23E-05 W 187

9.26E-Og

6.44E-09

2.23E-09 NO DATA

NO DATA

2.83E-05

2.54E-05 NP2.39

2.65E-07

2.37E-08

1.34E-08 NO DATA

4.73E-08

4.25E-05

1.78E-05

1 .109-55

TABLE E-1i PAGE 1 OF 3 INGESTION

DOUSE

FACTORS FOR ADULTS

( MREM PER PCI

INGESTED)

NUCLILE

BONE

LIVER

T.BOGY

THYROID

KIDNEY

LUNG

GI-LLI

-11

3 NO DATA

I.05E-07 I.05E-07

1.05E-07

1.05E-0

C

14

2.84E-06

5.68E-07

5.68E-0

NA

24

1.70E-06

1.70E-06 l.TOE-06

1.70E-06

1.70E-O

P

32

.1.93E-04

1.20E-05

7.46E-06 NO DATA

NC DATA

NO DATA

2.17E-0!

CR

51 NO DATA

NO DATA

2.6bE-09

1.59E-09

5.86E-I0

3.53E-09. 6.69E-0

.

MN 54 NO UATA

4.57E-06

8.72E-07 NO DATA

1.36E-06 NO DATA

1.40E-0

MN 56 NO DATA

1.15r-07

2.04E-08 NO DATA

1.46E-07 NO DATA

3.67F-06 FE 55

2.75E-06

1.90F-O0

4.43E-07 NO DATA

NO DATA

1.06E-06

1.09E-06 FE 59

4.34E-06

1.02E-05

3.91E-06 NO DATA

NO DATA

2.85E-06

3.40E-05 CC 58 NO DATA

7.45E-07 1.67E-06 NO DATA

NO DATA

i.51F-05 CC 60

NO DATA

2.14F-06

4'.72

-0 6 NO DATA

NO DATA

4.02E-05 ilI 63

1.30E-C4

9.OIE-Ob

4.36E-06 NO DATA

NO DATA

I.88E-06 NI 65

5.28E-07

6.86E-08

3.13E-08 NO DATA

NO DATA

1.7lE-06 CU 64 NO DATA

8.33E-08

3.91E-08 NO DATA

2.10E-07 NO DATA

7.10E-06 ZN 65

4.847E-06

1649-65 0.gE-06 NO DATA

1.03E-05 NO DATA

9.70E-06 ZN 69

1.03E-08

1.97E-08

1.37E-09 NO DATA

1.28E-08 NO DATA

2.96E-09 BR 83 NO DATA

NO DATA

4.02E-08 NO DATA

NO DATA

5.79E-08 BR 84 NO DATA

NO DATA

5.2IE-08 NO DATA

NO DATA

4.09E-13 BR 85 NO DATA

NO DATA

2.14E-09 NO DATA

NC DATA

NO DATA

LT E-24

'R8 86 NO DATA

2.1E-05 9.83E-06 NO DATA

NO DATA

4.16E-06 RB 88 NO DATA

6.05E-08

3.21E-08 NO DATA

NO DATA

8.36E-1.9 RB 89 NO DATA

4.01E-08

2.82E-08 NO DATA

NO DATA

2.33E-21 SR 89

3.08E-04 NO DATA

8.84E-06 NO DATA

NO DATA

4.94E-05 SR 90

7.58E-03 NO DATA

.1.8bE-03 NO DATA

NO DATA

2.19E-04 SR 91

5.6TE-06 NO DATA

2.29E-07 NO DATA

NC DATA

NO DATA

2.70E-05 SR 92

2.15E-06 NO DATA

9.30E-08 NO DATA

NO DATA

4.26E-05 Y

90

9.62E-09 NO DATA

2.58E-1O

NO DATA

1.02E-04 Y

91M

9.09E-11 NO DATA

3.52E-12 NO DATA

NO DATA

2.67E-IO

Y

91

1.41E-07 NO

DATA

3.77E-09 NO DATA

NO DATA

7.76E-05 Y

92

8.45E-10

NO DATA

2.47E-1I

NO DATA

1.48E-05

- - - - - - - - - - - - - -

- -

- - -

- - - -

- -

-

- - -

- - - -

- - -

--

.5:

1.109-56

TAB3LE E-11, C(JNT'D

PArE

2 or 3 INGESFION DOSE

FACTOOS

FOR ADULIS

(MREM

PER PCI

INGESTFD)

NUCLICE

BONE

LIVER

T.BODY

THYROIC

KIDNEY

LUNG

GI-LLI

Y

93

2.68E-C9 NO DATA

7.40E-11 NO DATA

NO DATA

8.50F-05 ZR 95

3.04E-OR

9.75E-09

6.60E-09 NO DATA

1.53E-08 NO DATA

3.09E-05 ZR 97

1.68E-09

3.39=-10

1.55E-10

NO DATA

5.12E-10

NO DATA

1.05E-04 N8 95

6.22E-09

3.46E-09

1.86E-09 NO DATA

3.42E-0q NO DATA

2.10E-05 MO 99 NO DATA

4.31E-06

8.20E-07 NO DATA

9.76E-06 NO DATA

9.99E-06 TC

99PI

2.47E-10

6.98=-10

8.89E-09 NO DATA

1.06E-08

3.42E-10

4.13E-07 TCioi

2.54E-10

3.66E-IC

3.59E-09 NO DATA

6.59E-09

1.87E-10

1.10E-21 RUIO3

1.85E-07 NO DATA

7.97E-08 NO DATA

7.06E-07 NO DATA

2.16E-05 RUIO!I

1.54E-08 NU DATA

6.03L-09 NO DATA

1.99E-07 NO DATA

9.42E-06 WU106

2.75F-06 NO DATA

3.48E-07 JO DATA

5.31E-06 NO DATA

1.78E-04 AG11OM

1.60E-07

1.48F-07

8.79E-08 NO DATA

2.91C-07 NO DATA

6.04E-05 T2125M

2.69E-06

9.712-07

3.59E-07

8.06F-07

1.09E-05 NO DATA

1.07E-05 TE127M

6.77E-06

2.42C-06

8.25[-07

1.73E-06 2.75E-05 NO DATA

2.27E-05 TE127

1.IE-07

3.95E-08

2.38E-O8

8.15E-06

4.48E-07 NO DATA

8.68E-06

1TE129M

1.15E-05

4.29c-0o

1.82E-06

3.95E-06

4.80E-05 NO DATA

5.792-05 rE129

3.14E-08 I.18E-O8

7.c*E-O9

2.41E-08

1.32E-07 NO DATA

2.37E-08 TE131t

1.73E-06

8.46'-07

7.05E-07

1.34E-06

8.57E-06 NO DATA

8.40E-05 T1131

1.97E-08

8.23E-09

6.22E-09

1.62E-08

.. 63L-08 NO

DATA

2.79E-C9

..

r2132

2.52E-06

1.b3E-O6i

1.5.-E-06

1.8E-C6 1.57E-05 NO DATA

T.7.12E-05

1 130

7.56E-07

2.23E-06 8.80E-07

1.89f:-04

3.48E-06 NO DATA

' 1.92E-06 I

131

4.16E-06

5.95c-06

3.41E-06

1.95F-C3

1.02E-05 NO DATA

1.57E-06

1 132

2.03E-07

5.43F-07

1.90E-07

1.90E-05

8.65L-07 NO DATA

1.02E-07

[ 133

1.42E-06

2.'t7E-06

7.53E-07

3.63E-04

4.31E-06 NO DATA

2.22E-06

1 134

1.06E-07

2.881-07

1.03E-07

4.99E-06

4.58E-07 NO DATA

2.51E-10

1 1-35

4.43E-07

1.16C-06 4.23C-07

7.65E-05

1.86E-C6 NO DATA

1.31E-06 CS134

6.22E-05

1.48E-04

1.21E-04 NO DATA

4.79L-05

1.59E-05

2.59E-06 v

CS136

6.51E-06

2.571-05

1.85E-05 NO DATA

1.43E-05

1.96E-06

2.92E-06 CS137

7.97E-05

1.G9E-04

7.14E-05 NO DATA

3.70L-05

1.23E-05

2.11E-06 CS138

5.52E-OR

1.C9E-07

5.40E-08 NO DATA

8.01E-08

7.91E-09

4.65E-13 BA139

9.70E-08

6.91E-I

2.84E-09 NO DATA

6.46E-11 i.92E-11

1.72E-07

1.109-57

IL

TABLF E-,I,

CONT'D

PACE

3 OF 3 INGESTION

DOSE

FACTORS

FOR

ADULTS

AMREM

PLR PCI

INGESTED)

NUCL I CE

BONE

LIVER

T. (3DY

THYROID

KIDNEY

LUNG

GI-LLI

-3A140

2.03[-05

2.55E-08 I.33E-06 NO

DATA

8.67E-09

1.46E-08

4.18E-05 r.A141

4.TIE-08

3.56E-1I

1.59E-09 NO DATA

3.31E-l1

2.02E-11

2.22E-17 OA142

2.13E-08

2.19E-11

1.34E-09

.40 DATA

1.35E-1I

1.24E-11

3.OOE-26 LA140

2.5OE-09

1.26>-09

3.33E-10

NO DATA

9.25E-05 LA142

1.28E-10

5.B2E--1

1.45E-l1 NO DATA

NC DATA

NO DATA

4.25E-07

0E141

9..36E-09

6.33E-09

7.1[E-lC

NO DATA

2.94E-09 NO DATA

2.42E-05

.E143

1.65E-09

1.22F-06

1.35E-1O

NO DATA

5.37E-10

NO DATA

4.56E-05

'CE144

4.A8E-07

2.04E-07

2.62E-08 NO DATA

1.21E-07 NO DATA

1.65E-04 PR143

9.20E-O

3.69-!09

4.56E-10

NO DATA

2.13E-09 NO DATA

4.03E-05 P1I44

3.OIE-11

1.25E-11

1.53E-12 NO DATA

7.05E-12 NO DATA

4.33E-18 N0147

6.29E-C9

7.Z7E-09

4.35E-I0

NO DATA

4.25E-09 NO DATA

3.49E-05 k 19.7

1.03E-07

8.61E-08

3.OE-08 NO DATA

NO DATA

Nn DATA

2.82E-05 NP239

1.19E-09

1.1,7E-1O

6.45E-1I

NO

DATA

3.65E-10

NO DATA

2.40E-05

1.109-58

TABLE E-12 PAGE

1 OF 3 INGESTION-DOSE

FACTORS FOR

TEENASER

(MREM

PER PCI INGESTED)

NUCLICE

BONE

LIVER

T.HnUY

THYROID

KIDNEY

LUNG

GI-LLI

II

3 NO DATA

1.06E-07

1.OE-07

1.06[-07

1.06E-07 L.06E-07

1.06E-O7 C

14

4.06E-06 e.12E-07

8.12E-O7

8.12F-07

8.12E-07 H.12E-07

8.12F-07 NA 24

2.30E-06

2.30E-06 P

32

2.76E-04

1.71E-05

1.07E-05 NO DATA

NO DATA

NO

DATA

2.32E-05 CR

51 NU DATA

NO

DATA

3.6OE-09

2.OOE-09

7.99E-10 5.14E-09

6.05E-07 MN 54 NO DATA

5.90E-Ob

1.17E-06 NO DATA

1.76E-06 NO

DATA

1.21E-05 MN 56 NO DATA

1.58E-07

2.8LE-08 NO DATA

2..OE-07- NO

DATA

1.04E-05 FE 55

3.7BE-06

2.68F-06

6.25E-07 NO

DATA

NO DATA

1.70E-06

1.16E-06 FE 59

5.87E-06

.iJE-05

5.29E-06 NO DATA

NO DATA

4.32E-06

3.24E-05

'O 58 NO DATA

9.72E-07

2.24E-06 ND DATA

NO DATA

NO

DATA

1.34E-05 CO 60

NO DATA

2.81E-06

6.33E-06 NO DATA

NO.DATA

NO

DATA

3.66E-05

ý4I 63

1.77E-04

1.25C-05 b.OOE-06 NO DATA

NO DATA

1.99E-06

14I 65

7.49E-07 .9.57E-08

4.36E-08 NO DATA

NO.DATA

NO DATA

5.19E-06 CU 64 NO DATA

1.15E-07

5.41E-08 NO DATA

2.91E-07 NO DATA

8.92E-06 ZN 65

5.76E-06

2.COE-C5.

9.33E-06 NO DATA

1.28E-05 NO DATA

8.47E-06 LN69

1.47E-08

2.6OE-08

1.96E-09 NO DATA

I.R3E-O8 NO DATA

5.16E-08

R

83 NO DATA

NO DATA

5.74E-08 NO DATA

NO DATA

LT E-24

.9R 84 NO DATA

N. DATA

7.22E-08 NO DAT3 NO

DATA

NO DATA

LT E-24 bR 85 NO DATA

NO DATA

3.05E-09 NO DATA

NO DATA

LT E-24 RB 86 NO

DATA

2.98E-05

1.40E-05 NO DATA

NO DATA

4.41E-06 RB 88 NO DATA

8.52E-08

4.54E-08 NO DATA

NO DATA

7.30E-15 RB 89 NO DATA

5.50E-08

3.89E-08 NO DATA

NO DATA

8.43F-17 SR 89

4.40E-04 NO DATA

1.26E-05 NO DATA

NO DATA

5.24E-O5 SR 90

8.30E-03 NO DATA

2.05E-03 NO DATA

NO DATA

2.33E-04 SR

---

8.-- E-O6 ND-DATA

3.21E-07 NO DATA

ND DATA

3.-6E-05 SR 92

3.05E-06 NO DATA

3.30E-07 NO DATA

NO DATA

7.77E-05 Y

90

1.37E-08 NO DATA

3.69E-1O

NO DATA

1.13E-04 Y

91M

1.29E-10

NO DATA

4.93E-12 NO DATA

NO DATA

6.09E-09 Y

91

2.0IE-07 NO DATA

5.31E-09 NO DATA

NO DATA

8.24E-05 Y

92

1.21E-09 NO DATA

3.50E-11 NO DATA

NO DATA

3.32E-05

1.109-59

TAtLF E-12, CONTDO

PASE 2 OF 3 INGESTION DOSE

FACTORS FOR TEENAGER

(MREM

PFR PCI INGESTED)

NUCLI'2E

BONE

LIVER

T.tODY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

3.83E-C9 NO DATA

1.05E-10

NO DATA

NC DATA

NO DATA

1.17E-04 ZR 95

4.12E-08

1.302-08

8.91+E-09 NO DATA

1.91E-08 NO DATA

3.OOE-05

7R 97

2.37E-09

4.69E-1O

2.16E-10

ND DATA

7.11E-10

NO DATA

1.27E-04

14 P 95

8.22E-09

4.5bE-09

2.51E-09 NO DATA

4.42E-Oq NO DATA

1.95F-05 MO 99 NO DATA

6.03E-06

1.15F-06 NO DATA

1.38E-05 NO DATA

1.08E-05 TC 99M

3.32E-10

9.26E-10

L.20E-08 NO DATA

1.38E-08

5.14E-1O

6.08E-07 TCIDI

3.60E-10

5.127-10

5.03E-09 NO DATA

q.26E-09

3.12E-10

8.75E-17 RU103

2.55E-07 NO DATA

1.09E-07 NO DATA

8.99E-07 NO DATA

2.13E-05 RU105

2.18E-08 NO UATA

8.46E-09

40 DATA

2.75E-07 NO DATA

1.76E-05 RI)0ob

3.92E-06 NO DATA

4.94E-07 NO DATA

7.56E-06 NO DATA

1.88E-04 AGIIOM

2.05E-07

1.94E-07

1.18E-O7 NO DATA

3.70E-07 NO DATA

5.45E-05 TE125m 3.33E-06

1.382-06

5.12E-07

1.07E-06 NO DATA

NO DATA

1.13E-05 TF127M

9.67E-06

3.4iE-Ob

1.15E-06 2.30E-06

3.92L-05 NO DATA

2.41E-05 FE127

1.58E-07

5.60E-08

3.40E-08

1.09F-O7

6.40E-07 NO

DATOS

1.2ZE-05 TE129M

1.63E-05

6.C5-O6

2.58E-06

5.2bE-06

6.82E-05 Nn DATA

6.12E-05

TEL29

4.48E-08

1.'b7F-08 I.,0)E-08

3.20E-08

1.88E-07 NO DATA

2.45F-07

!

TEl31m

2.44E-06

1.17E-Ob

9.76E-07

1.76E-06

1.22E-05 NO DATA

9.39E-05 TF131

2.79E-08 I.L52-08

8.72E-09

2.15E-08

1.22E-07 NO DATA

2.29[-09

2E132

3.49E-06

2.21F-06

2.08E-06

2.33E-06

2.12E-05 NO DATA

7.ODE-05

1 130

1.03E-06

2.98E-06

1.19E-06

2.43E-04

4.59E-06 NO DATA

Z.29E-06

1 131

5.85E-O

8.19C-06

4.40E-06

2.39E-03

1.41E-05 NO DATA

1.62E-06

1 132

2.79E-07

7.30E-07

2.62E-07

2.46E-05

1.15E-06 NO DATA

3.18E-07

133

2.01E-06

3.41L-06

1.04E-06

4.76E-04

5.98E-06 NO DATA

2.58E-06 I 134

1.46E-07

3.87E-07

1.39E-07

6.45E-06

6.10E-07 NO DATA

5.10E-09

1 135

6.10E-07

1.57E-06

5.82E-07

1.OIE-04

2.48E-06 NO DATA

1.74E-06 CS134

8.37E-05

1.97F-04

9.14E-05 NO DATA

6.26E-05

2.39E-05

2.45E-06 CS136

8.59E-06

3.38E-05

2.27E-05 NO DATA

1.84E-05

2.90E-06

2.72E-06 CS137

1.12E-04

1.49E-04

5.19E-05 NO DATA

5.07E-05

1.97E-05

2.12E-06 CS138

7.76E-08

1.49C-07

7.45E-08 NO DATA

I.IOE-07

1.28F-08

6.76E-11

3A139

1.39E-07

9.78L-11

4.05E-09 NO DATA

9.22E-1i

6.74E-11

1.24E-06

1.109-60

TABLE E-12, CONT'D

PAGE 3 OF 3 I:AGESTION DOSE

FACTORS

FOR TEFNAGER

(MREM

PER

PCT

INGESTED)

WUCLTLE

BONE

LIVER

T.60OY

THYROID

KIDNEY

LUNG

GI-LLI

64140

2.84E-05

3.48E-09

1.83E-06 NO DATA

1.18E-08

2.34E-08

4.38E-05 RAI41

6.71E.-OR

5.('1E-11

2.24E-09 NO

DATA

4.65E-11

3.43E-11

1.43E-13

'A142

2.99E-08

2.39E-11

1.84E-09

40 DATA

2.53E-11

1.9qE-11 9.18E-20

LA140

3.48E-09

1.71C-09 4.55E-10

NO DATA

NC DATA

NO DATA

9.82E-05 LA142

1.79E-10

7.95E-11

1.98E-11 NO DATA

NO DATA

2.42E-06 CE141

1.33E-O8

8.88'-09

1.02E-09 NO DATA

4.18E-09 NO

D4.TA

2.54E-05 CE143

2.35E-09

1.

7 1E-0

6

1.91E-1O

NO DATA

7.67E-10

NO DATA

.5.14E-05 CF144

6.96E-07

2.88E-07

3.74E-68 NO DATA

1.72E-07 NO DATA

1.755-04 PR143

1.31E-08

5.23C-09

6.52E-10

NO DATA

3.n4E-O9 NO DATA

4.31E-05 PR144

4.30E-11

1.762-11

2.18E-12 NO DATA

1.01E-11 NO DATA

4.74E-14

qU147

9.38E-09

1.02F-08

6.11E-10

NO DATA

5.q99L-Oq Nn DATA

3.68E-05

187

1.46E-07

1.19F-07

4.11E-38 NO DATA

NO DATA

NO

DATA

3.22E-05

'JP239

1.76E-Oq

1.66E-10

9.22E-11

,,n DATA

5.21L-10

NO DATA

2.67E-05

1 .109-61

TABLE E-13 PAGE

I OF

3 INGESTION DOSE

FACTORS

FOR CHILD

(MREM

PER PCI

INGESTED)

NUCLIDE

BONE

LIVER

T.oOUY

THYROID

KIDNEY

LUNG

GI-LL!

II

3 NO DATA

2.03E-O7

2.01E-07

2.03E-07

2.03E-OT

2.03E-07

2.03E-07 C

14

1.21E-05

2.42E-06

2.42E-06 NA 24

5.80E-06

5.BOE-06

5.80E-06

5.80E-06 P

32

8.25E-04

3.86C-05

3.IE--O5

40 DATA

NO DATA

2.28E-0.5 CR 51 NO DATA

NO DATA

8.90E-09 4.94E-09

1.35E-09

9.02E-09

4.72E-07

4 MN 54 NO DATA

1.07E-05 2.85E-06 NO DATA

3.OD0-06 NO DATA

8.98E-06 MN 56 NO DATA

3.34E-OT

7.54E.-08 NO DATA

4.04E-O7 NO DATA

4.84E-05 I!

FE-55

1.1SE-05

6.IOE-06

1.89E-06 NO DATA

NO DATA

3.45E-06

1.13E-06 FE 59

1.65E-05

2.67E-05

1.33E-05 NO DATA

NO DATA

7.74E-06

2.78E-05 CO 58 NO DATA

1.8OE-06

5.51E-06 NO DATA

NO.DATA

NO DATA

1.05E-05 CO 60

NO DATA

5.29E-06

1.56E-05 NO DATA

NO DATA

NO .DATA

2.93E-05 NI 63

5.38E-C4

2.88E-05

1.83E-05 NO DATA

NO DATA

1.94[-06 NI 65

2.22E-06

2.09F-07

1.22E-07 NO DATA

NO DATA

2.56E-05 CU 64 NO DATA

2.45E-07

1.48E-07 NO DATA

5.92E-07 NO DATA

1.15E-05 ZN 65

1.37E-05

3.o5E-0

2.27E-05 NO DATA

2.30E-05 NO DATA

6.41E-06 ZN 69

4.38E-O8

6.13E-08

5.85E-09 NO DATA

3.84E-08 NO DATA

3.99E-06 BR 83 NO DATA

NO DATA

1.71E-07 NO DATA

NO DATA

LT E-24

...

BR 84 NO DATA

NO

DATA

1.97E-07 NO DATA

NO DATA

LT E-24

-

--

R 8- NO DATA

NO DATA

-1-E-07 NO DATA

NO DATA

NO- DATA

LT E-24

,i!RR

85 NO

DATA

NO DATA

9.12E-09 NO DATA

NO

DATA

NO. DATA

LT E-24 RB Bb"

NO DATA

6.70E-05

4.12E-05 NO DATA

NO DATA

4.31F-06 RB 88 NO DATA

1.90E-07

1.32E-07 NO DATA

NO DATA

9.32E-09 RB 89 NO DATA

1.17E-07

1.04E-07 NO

DATA

NO DATA

1.02E-09 SR.89

.1.32E-03 NO DATA

3.77E-05 NO DATA

NO DATA

5.11E-05 SR 90

1.70E-02 NO DATA

4.31E-03 NO DATA

NO DATA

NO

DATA

2.29E-04 SR 91

2.40E-05 NO DATA

9.06E-OT

NO DATA

5.30E-05 SR 92

9.03E-06 NO DATA

3.62E-07 NO DATA

NO DATA

1.TIE-04 Y

90

4.11E-08 NO DATA

I.IOE-09 NO DATA

NO DATA

1.17E-04 Y

91M

3.82E-10

NO DATA

1.39E-1I

NO DATA

7.48E-07 Y

91

6.02E-07 NO DATA

1.61F-08 NO DATA

NO DATA

8.02E-05 Y

92

3.60E-09 NO DATA

1.03E-1O

NO DATA

1.04E-04

1.109-62

TABLE E-13, CONr'D

PAGE 2 OF 3 INGESTION DOSE

FACTORS FOR CHILO

(MREM

PR PC[ INGESTED)

NUCLIDE

BONE

LIVER

T.3OOY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

1.14C-CO

NO DATA

3.13E-1O

NO DATA

1.70E-04 ZR 95

1.1bE-07

2.,5E-08

2.27E-08 NO DATA

'3.65E-O8 NO DATA

2.66E-05 ZR 97

6.99E-09 I.CIE-09

5.96E-1O

NO DATA

1.45E-09 NO DATA

1.53E-04 NR 95

2.25E-D8

8.76E-09

6.26E-09 NO DATA

8.23E-09 NO DATA

1.62E-05 mO 99 NO DATA

I.33F-05

3.29E-06 NO DATA

2.84E-05.

NO DATA

I.OE-O5 TC 99M

9.23E-1O

1.81E-09

3.00E-08 NO DATA

2.63E-08

°.19E-10

1.03E-06 rClO1

1.07E-09

1.12E-09

1.42E-08 NO DATA

1.91E-08

5.92E-1O

3.56E-09 RUI03

7.31E-07 NO DATA

2.81E-07 NO DATA

1.84E-06.

NO DATA

1.89E-05

!'U1O5

6.45E-08 NO DATA

2.34E-08 NO DATA

5.67E-07 NO DATA

4.21E-05 RU106

1.17E-05 NO DATA

1.46E-06 NO DATA

1.58E-05 NO DATA

1.82E-04 AGIIOH

5.39E-07

3.64E-07

2.91E-07 NO DATA

6.78E-07 NO DATA

4.33E-05 TF125M

1.14E-05

3.09E-06

1.52E-06

3.20E-06 NO DATA

NO DATA

1.10F-05 FE127M 2.89E-05

7.78F-06

3.43E-06

6.91E-06

8.24E-05 NO DATA

2.34E-05 TF127

4.71E-07

1.27F-07

1.01E-07

3.26E-07

1.34E-06 NO DATA

1.84E-05 rE1291A

4.87E-05

1.36E-05

7.56E-06

1.57E-05

1.43E-04 NO DATA

5.94E-05

1E129

1.34E-07

3.74E-08

3.18E-08

9.56E-08

3.92E-07 NO DATA

8.34E-06 TE131M 7.20E-06

2.49E-06

2.65E-06

5.12E-06

2.41E-05 NO DATA

1.01E-04 TE131

8.30E-08

2.53E-08

2.47E-08

6.35E-08

2.51E-07 NO DATA

4.36E-07 tE132

1.01E-05 4.47E-0o

5.40E-06

6.51E-06

4.15E-05 NO DATA

4.50E-05

1 130

2.92E-06

5.90E-06

3.04E-06

6.50E-04

8.82E-06 NO DATA

2.76E-06 I

131

1.72E-05

1.73C-05

9.83E-06

5.72E-03

2.84E-05 NO DATA

1.54E-06

1 132

8.00E-07

1.47E-06

6.76E-07

6.82E-05

2.25E-06 NO DATA

1.73E-06

1 133

5.92E-06

7.32E-06

2.77E-06

1.36E-03

1.22E-05 NO DATA

2.95E-06

1 134

4.19E-07

7.78E-07

3.58E-07

1.79E-05

1.19E-06 NO DATA

5.16E-07

1 135

1.75E-06

3.15E-06

1.49E-06

2.79E-04

4.83E-06 NO DATA

.2.40E-06 CS134

2.34E-04

3.84E-04

8.10E-0S

NO DATA

1.19E-04

4.27E-05

2.07E-06 CS136

2.35E-05

6.46E-05

4.18E-05 NO DATA

3.44E-05

5.13E-06

2.27E-06 CS137.

3.27E-04

3.13E-04

4.62E-05 NO DATA

1.02E-04 3.67E-05

1.96E-06 CS138

2.28E-07

3.17E-07

2.01E-07 NO DATA

2.23E-07

2.40E-08

1.46E-07

3A1,39

4.14E-07

2.21E-10

1.20E-08 NO DATA

1.93E-10

1.30E-10

2.39E-05

1.109-63

TABLE E-13, CONT'D

PASE 3 OF .3 INGESTION DOSE

FACTORS FOR CHILD

(MREP PER PCI

INGESTED)

NUCLIUE

BONE

LIVER

T.BODY

THYROID

KIDNEY

LUNG

GI-LLI

RA140

8.31E-05

7.28E-08

4.85E-06 NO DATA

2.37L-08

4.34E-O8

4.21E-05

ýA!41

2.OOE-07

1.12C-1O 6.51E-09 NO DATA

9.69E-11

6.58E-1O

1.14E-O7

0A142

8.74E-08

6.29E-1i

4.88F-09 NO. DATA

5.09E-11

3.70E-11

1.14E-09 LA140

I.OIE-O8

3.53E-09

1.19E-09 AO.DATA

NO DATA

9.84E-05 LA142

5.24E-I0

1.67T-1O

5.23E-11 NO DATA

NO DATA

3.31E-05 CEI41

3.97E-08

1.98[-08

2.94E-09 NO DATA

8.68E-O0

NO DATA

2.47E-05 CE143

6.99E-09

3.79E-06

5.49E-1O

NO DATA

1.59E-09 NO DATA

5.55E-05 CE144

2.08E-06

6.52E-O

I.IIE-07 NO DATA

3.61E-07 NO DATA

1.70E-04 PR143

3.93E-08

1.18E-O8

1.95E-09 NO DATA

6.39E-09 NO DATA

4.24E-05 PR144

1.29E-10

3.99E-I1

6.49E-12 NO DATA

2.1lE-11 NO DATA

8.59E-08 N0147

2.79E-OR

2.26E-08 I.75E-09 'Nn DATA

1.24E-08 NO DATA

3.58E-05 W 187

4.29E-07

2.54F-07

1.14E-07 NO DATA

NO DATA

.:NO

DATA

3.57E-05 NP239

5.25E-09

3.77E-10

2.65E-10

NO DATA

1.09E-09 NO DATA

2.79E-05

1.109-64

TABLE E-14 PAGE I OF 3 INGESTION DOSE

FACTORS FOR INFANT

(MREM

PER -PCI INGESTED)

NUCLIDE

BONE

LIVER

T.BODY

THYROID

KIDNEY

LUNG

GI-LLI

H

3 NO DATA

3.08E-07

3.08E-O7

3.0RE-07

3.08E-07

3.OBE-O7 3.08E-07 C

14

2.37E-05

5.06E-06

5.06F-06

5.06E-06 NA 24

1.O1E-05 1.OIE-05

1.01E-05 I.OIE-05 I.OIE-05 I.OIE-O5

1.O1E-05 P

32

1.70E-03

1.OOE-04

6.59E-05 NO DATA

NO DATA

2.30E-05 CR 51 NO DATA

NO DATA

1.41E-08

9.20E-09

2.OIE-09

1.79E-08

4.l1E-07 MN 54 NO DATA

1.99E-05

4.51E-06 NO DATA

4.41E-06 NO DATA

7.31E-06 MN 56 NO DATA

8.18E-07

1.41E-O7 ND DATA

7.03E-07 NO DATA

7.43E-05 FE 55

1.39E-05

8.98E-06

2.40E-06 NO DATA

NO DATA

4.39E-06

1.14E-06 FE 59

3.08E-05

5.38E-05

2.12E-05 NO DATA

NO DATA

1.59E-05

2.57E-05 CO 58 NO DATA

3.60E-06

8.93E-06 NO DATA

NO DATA

8.97E-06 CC 60

NO DATA

1.08E-05 2.55E-05 NO DATA

NO DATA

2.57E-05 NI 63

6.34E-04

3.92E-05

2.20E-05 NO DATA

NO DATA

1.95E-06 NI 65

4.70E-06

5.32E-07

2.42E-07 NO DATA

NO DATA

4.05E-05 CU 64 NO DATA

6.09E-07

2.82E-07 NO DATA

1.03E-06 NO DATA

1.25E-05 ZN 65

1.34E-05

6.31E-05

2.91E-05 NO DATA

3.06E-05 NO DATA

5.33E-05 ZN 69

9.33E-08

1.b8E-07

1.25E-08 NO DATA

6.98E-08 NO DATA

1.37F-05 BR 83 NO DATA

NO DATA

3.63E-07 NO DATA

NO DATA

LT E-24 bR 84 NO DATA

NO DATA

3.82E-07 NO DATA

NO DATA

LT E-24 OR 85 NO DATA

NO DATA

1.94E-08 NO DATA

NO DATA

LT E-24 RB B6 NO DATA

1.70,E-04

8.40E-05 NO DATA

NO DATA

4.35E-06 RB 88 NO DATA

4.98E-O7

2.73E-07 NO DATA

NO DATA

4.85F-07 RD 89 NO DATA

2.86E-07

1.97E-07 NO DATA

NO DATA

9.74E-08 SR

89

2.51E-03 NO DATA

7.20E-05 NO DATA

NO DATA

5.16E-05 SR 90

1.85E-02 NO DATA

4.71E-03 NO

DATA

NO DATA

2.31E-04.

SR 91

5.OOE-05 NO DATA

1.81E-06 NO DATA

NO DATA

5.92E-05 SR 92

1.92C-05 NO DATA

7.13E-07 NO DATA

NO DATA

2.07E-04 Y

90

8.69E-08 NO DATA

2.3iE-09 NO DATA

NO DATA

1.20E-04 Y

91M

8.10E-I1 NO DATA

2.76E-11 NO DATA

NO DATA

2.70E-06 Y

91

1.13E-06 NO DATA

3.01E-08 NO DATA

NO DATA

8.10E-05 Y

92

7.65E-09 NO DATA

2.15E-10

NO DATA

1.46E-04

1.109-65

TABLE E-14, CONI'D

PAGE 2 OF 3 INGESTION DOSE

FACTORS FOR INFANT

(MREM

PER PCI INGESTED)

NUCLIDE*

BONE

LIVER

T.DODY

THYROID

KIDNEY

LUNG

GI-LLI

Y

93

2.43E-08 NO DATA

6.62E-10

NO DATA

1.92E-04 ZR 95

2.06E-07

5.02E-08

3.56E-08 NO DATA

5.41E-O8 NO DATA

2.50E-05 IR 97

1.48E-08

2.54E-09

1.1&E-09 NO DATA

2.56E-09 NO DATA

1.62E-04 N8 95

4.20E-08

1.73E-08 I.ODE-08 NO DATA

1.74E-08 NO DATA

1.46E-05 MO 99 NO DATA

1.4CE-O5

6.63E-06 NO DATA

5.08E-05 NO DATA

1.12E-05 TC 99M

1.92E-09

3.96b-09

5.10E-08 NO DATA

4.26E-08

2.07E-09

1.15E-06 TC1O0

2.27E-09

2.86E-09

2.83E-08

-NO DATA

3.40E-08

1.56E-09

4.86E-07 RUED3

1.48E-06 NO DATA

4.95E-07

'4O DATA

3.08E-06 NO

DATA

1.80E-05 RUI05

1.36E-07 NO DATA

4.58E-08 NO DATA

1.O0E-06 Nfl DATA

5.41E-05 RU106

2.41E-05 NO DATA

3.DIE-06 NO DATA

2.85E-05 NO

DATA

- 1.83E-04 AGIOM

9.96E-07

7.27E-07. 4.81E-07 NO DATA

1.04E-06 NO

DATA

3.77E-05 TE125M

2.33E-05

7.79C-06

3.15E-O0

7.84E-06 NO DATA

NO

DATA,

1.1lE-05 TEI27M

5.85E-05

1.94E-05

7.08E-06

1.69E-05

1.44E-04 NO

DATA

2.36E-05 TE127

1.00E-06 3.35E-07

2.15E-07

8.14E-07

2.44E-06 NO DATA

2.10E-05 TE129M

1.OOE-04

3.43E-05

1.54E-05

3.84E-05

2.50E-04 NO

DATA

5.97E-05 TE129

2.84E-07

9.79OE-08

.63E-08

2.382-07

7.07E-07 NO DATA

2.27E-05 TEI131

1.52E-05

6.12E-06

5.05E-06

1.24E-05

4.21E-05 NO DATA

1.03E-04 TE131

1.76E-07

6.502E-08

4.94E-08 1.7E-07

4.50E-07 NO DATA

7.11E-06 TE132

2.08E-05

1.03E-05

9.612E-06

1.52E-05

6.44E-05 NO DATA

3.81E-05 I

130

6.OOE-06 1.32E-05

5.30E-06

1.48E-03

1 45E-05 NO DATA

2.83E-06

1 131

3.59E-05

4.23E-05

1.86E-05

1.39E-02

4.94E-05 NO DATA

1.51E-06

1132

1.66E-06

3.37E-06

1.20E-06

1.58E-04

3.76E-06 NO DATA

2.73E-06 I 133

1.25E-05

1.82[-05

5.33E-06

3.31E-03

2.14E-05 NO DATA

3.08E-06

1134

8.69E-P7

1.78E-06 6.33E-07

4.15E-05

1..99E-06 NO DATA

1.84E-06

1 135

3.64E-06

7.24E-06

2.64E-06

6.49E-04

9.07E-06 NO DATA

2.62E-06 CS134

3.77E-04

7.03E-04

7.10E-05 NO DATA

1.81E-04

7.42E-05

1.91E-06 CS136

4.59E-05

1.35E-04

5.04E-05 NO DATA

5.38L-05

1.10E-05 2.05E-06 CS137

5.22E.-04 b.IIE-04

4.33E-05 NO DATA

1.64E-04

6.64E-05

1.91E-06 CS138

4.81E-07

7.82E-07

3.79E-07 NO DATA

3.90E-07

6.09E-08

1.25E-06 BA139

8.81E-07.

5.84E-10

2.55E-08 NO DATA

3.51E-1O

3.54E-10

.5.58E-05

1.109-66 m

TAt6LE E-14, CONT'D

PA:,E 3 OF 3 INGESTION

DOSE FACTORS FOR INFANT

(MREM PER

PCI INGESTED)

NUCLIL;E

BONE

LIVER

T.3ODY

THYROID

KIDNEY

LUNG

GI-LLI

BA14u

1.7LE-04

1.71E-07

8.81E-06 NO DATA

4.06E-08

1.05E-07 4.20E-05 P,.A141

4.25E-O7

2.91E-1O

1.34E-08 NO DATA

1.75E-10

1.7TTE-O

5.19E-06 BA142 I.B4E-07

1.53E-1O

9.06E-09 NO DATA

8.8IE-11

9.26E-11 T.59E-07 LA140

2.11E-O8

8.32E-09

2.14E-09 NO DATA

NO DATA

9.77E-05 LA142

1.1OE-09

4.04E-10

9.61F-Il NO DATA

NC DATA

NO DATA

6.86F-05 CEI4I

7.87E-08

4.8OE-08

5.65E-09 NO DATA

1.48E-08 NO DATA

2.48E-05 CE143

1.48E-08

9.82E-06

1.1?E-09 NO DATA

2.86E-09 NO DATA

5.73E-05 CE144

2.98E-06 1.22E-06

1.67E-07 NO DATA

4.93E-07 NO DATA

1.71E-04 PR143

8.13E-08

3.04E-08

4.03E-09 NO DATA

1.13E-08 NO DATA

4.29E-05 PR144

2.74L-I0

I.ObE-l0

1.38E-1I

NO DATA

3.84E-11 NO DATA

4.93E-06 ND147

5.53E-08

5.68E-08

3.48E-09 NO DATA

2.19E-O8 NO DATA

3.60E-05 w 187

9.03E-07 6.28E-07

2.17E-01 NO DATA

NO DATA

3.69E-05 NP239

1.1IE-08

9.93E-10

5.61E-16 NO DATA

1.98E-09 NO

DATA

2.87E-05

1.109-67

-

~

TABLE E-15 RECOMMENDED VALUES FOR OTHER PARAMETERS

Parameter Symbol Definition fg ft p

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 Equation(s)

Where Used

14 & C-13

4, A-8, A-13, & C-5 Values

0.76

1.0

240 kg/mi

2 Reference(s)*

10

4, A-8, & A-13 C-5

00

Io

0QO

SF

tb te

8, 9,

10, 11, 12, B-6, B-7, B-8, B-9,

& C-2

3, 4, A-4, A-5, A-6, A-7, A-8, A-13,

& C-5

4, A-8, A-13, & C-5

0.25

1.0 (for iodines)

0.2 (for other particulates)

0.7 (for maximum individual)

0.5 (for general population)

1.31 x 105 hr

720 hrs (30 days,.

for grass-cow-milk- man pathway)

1440 hrs (60 days, for crop/vegetation- man pathway)

2 days (for maximum individual)

4 days (for general population)

27

2, 4, 13,

28-31

26

10 & 32 tf Transport time from animal feed-milk-man C-10

Parameter values given without references are based on staff judgments.

TABLE E-15 (Continued)

Parameter Symbol th Equation(s)'

Where Used 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 Values Reference(s)*

4, A-8, A-13, & C-5

4, A-8, A-13, & C-5 t p Environmental transit time, release to receptor (add time from release to exposure point to minimums shown for distribution)

1 & A-2 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 com- mercial fish doses Zero

0

2 & A-3

3 & A-7 tS

YV

Average time from slaughter of meat animal to consumption Agricultural productivity by unit area (measured in wet weight)

C-12

20 days

4, A-8, A-13,

& C-5

0.7 kg/mi2 (for grass- cow-milk-man pathway)

2.0 kg/m 2 (for produce or leafy vegetables ingested by man)

0.0021 hr-1

33

34 w

Rate constant for removal of activity on plant or leaf surfaces by weathering (corresponds to a 14-day half-life)

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, Inter- national 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 fur 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 fir 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 Milk," Institute fur 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 IDO-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 (liCi/m 2 )," 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 CONF-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.

III, "Water

40

Supply and Treatment," CRC Press, Cleveland, Ohio, 1975.

1.109-70

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 apd 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-1183-1670,

Las Vegas, Nev.,

1975.

27.

D. A. Baker et al.,

"FOOD - An 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

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 Posifion 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 sector- averaged Gaussian plume model.

Use of the model involves volume integration over a distributed source, resulting in certain integrals that define the I function, denoted by TT 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):

(Rz) Q

exp

2(z

- h

+ exp (F-i)

2V~

0 zURe

22L

2oL

v~Taz uez where h

is the effective release height, in meters;

QD

is the effective release rate, considering decay in transit, in Ci/sec;

(7 R

is the downwind distance, in meters;

u is the average wind speed, in m/sec;

x(R,z)

is the sector-average concentration at location (R,z), in Ci/m3 z

is the vertical distance above the ground plane, in meters;

e is the sector width, in radians; and a

o is the vertical plume spread, in meters.

Equation (F-l) maybe restated, for simplicity, as:

7(R,z)

=

'DG(z)

(F-2)

zRe where G(z)=

expF-

iz h)2

+ exp (F-3)

L

2a j

L 2a J

zp z where the terms are as defined above.

6.

1.109-72 M

-77- ME ý"

,

E ý - ,

The gamma 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):

Pa q(3.7xlOl10)E(l.6xlo -6)B(p,jia r)exp(-or)

41r 2 (1293)(100)

(F-4)

Where B(,va ,r)

is the buildup factor, dimensionless;

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;

P

is the attenuation coefficient for air, in m-1l la is the energy absorption coefficient for air, in m-I

100

is the number of ergs per gram-rad;

1293 is the density of air at standard temperature and pressure, in g/m3

1.6 x 10-6 is the number of ergs per MeV; and

3.7 x 1010

is the number of disintegrations, per Ci-sec.

Equation (F-4) may be simplified as follows:

S KiaqEB(P,'a,r)exp(-pr)

41Tr (F-5)

M~

were K

(3.7 x 10101(.6 x I0- 6

0.46

(1293)(100)=04 (F-6)

The next step is to incorporate Equation (F-2) into Equation (F-5) to arrive at an ression for the differential dose rate dD' from the differential volume dV containing the e...

nuclide concentration X(R,z).

Consider a volume element of the plume located z meters above r ga...d and at a horizontal distance L meters from-receptor location (R, 0) (see Figure 7.20

0the All such volume elements located at the horizontal distance L are included in the

7,

,g91shaped differential volume 21TLdLdz.

If R is sufficiently large that the concentration r0aged over all such volume elements can be approximated by -(R,z), the contribution of the Vershaped differential volume dV to the air dose rate at location (R,0) is given as K ia EB(

p' va'r)exp(- tr) *(~

~ V(F-7)

dD'

=

F7

4r

2 (Rz)dV

1.109-73

1

1 I

where q has been replaced by x(R,z)dV.

Substituting (L2 + z2)I/2 for r and 2wLdLdz for dV in Equation (F-7),

and integrating, the following expression is obtained:

Ku Ia EQ D

B [vi'vaý (L

2+ zI)j1 G(z) exp LuI(L 2+Z2 jLdd

2 ,/2'R7 L2 + z 2

0 0

(F-8)

The I function, denoted by TT in Reference l, is defined as B_1__(_2_

Z2)l1/2]1 G(z)exp [w(L 2 + z2)1/2]

37-~ J B )g;(2

2 L

2

- LdLdz (F-9)

O00

L

which, when substituted into Equation (F-8), yields Kv aEQD

D'=

I

(F-10)

The constant K, equal to 0.46, when divided by /F yields the factor 0.260, which is the same as the factor of 260 in Equation (6) of Regulatory Position C.2.a, after multiplying by the number of mrad per rad.

The buildup factor given in Reference I is of the form B(p,var) : 1 + kpr (F-11)

where k

"a (F-12)

Ila Substituting the above expression for the buildup factor into Equation (F-9), the I function is then given as I = '1 + k12 (F-13)

where the Il and 12 integrals can be written for this form of the buildup factor as I

23/2zi G(z)El(ljz)dz (F-14)

0

and

1 G(z)exp(-Pz)dz (F-15)

an.

2 a

z

0

where El(z) is the exponential integral defined by El(GZ) =

f exp(-r)r d(pr)

(F-16)

prz

1.109-74

2.

Evaluation of the I Function In Reference 1 the I and 12 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 C.2.a.

The .NRC staff has developed a computer routine that evaluates the I function as formulated in Equation (F-g).

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-1.

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,p ar)

desired by the user.

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 12 integrals as formulated in Equations (F-14) and (F-15), respectively.

A li.sting of the routine is provided 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 IlI

and 12V

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

C**

C

C,

C .

C

C.

C

Cw SUBROUTINE DINT

COMMONDATAIT/GMUZKHSSIGMZEBARDIM

DOSE INTEGRAL SUBROUTINE -K.F.

ECKERMAN 11-24-74 SUBROUTINE EVALUATES THE DOSE

INTEGRAL

'IT' AS DEFINED BY EON 7.61 IN MET & AE-1968.

THE TWO DIMENSIONAL INTEGRATION

IS

EVALUATED

USING GAUSSIAN-LEGENDRE

QUADRATURE OF ORDER 48.

COMMON

INFO

GMU-MASS ATTENUATION COEFFICIENT

(I/METERS)

ZK-BUILDUP FACTOR

((U-MUA5/MUA

IF

USED

HS-RELEASE POINT HEITH

RELEASE POINT HEIGHT

(METERS)

SIGmZ-STANDARD DEVIATION OF PLUME

(METERS)

EBAR-GAMMA

RAY ENERGY

(MEV)

DI-DOSE INTEGRAL

M-ENERGY GROUP INDEX

IF

NEEDED

NOTE-ZKoEBAR,& M ARE USED BY BULDUP

r~r, DIMENSION X(245),(24)

DATA NN/48/,A/2.828427125/

DATA X/

10.0323801709,

0.0970046992o

20.2873624873,

0.3487558862,

30.5231609747,

0.5772247260,

40.7240341309# 0.7671590325,

50.8765720202,

0.9058791367,

60.9705915925,

0.9841245837, DATA W/

10.0647376968o 0,0644661644#

20,0620394231,

0.0607044391,

30.0551995036,

0.0528901894,

40.0446745608p 0.0415450829#

50,0311672278,

0.0274265097,

60.0155793157,

0.0114772345, SUMUO.

Buo.5/(SIGMZ*SIGMZ)

ZLB3HS-4.*SIGMZ

ZUBBHS+4.*SIGMZ

IFCZLB.LT.0.)ZLBuO.

YUBUIS./GMU

CZ0.5*(ZUB-ZLB)

GcO.S*(ZUB+ZLB)

E8O.5*YUB

DO 7o II21PNN

III-II1/2 Ful.

EX=O.

IF(MOD(II,2).EQ.0)Fu-1.

ZZUF*X(I)*C÷G

ARGUxB*(ZZ-HS),(ZZ-HS)

IF(ARGU.GT.20.)GO TO 55 EXUEXP(-ARGU)

55 ARGU=B*(ZZ÷HS)*(ZZeHS)

IF(ARGU.GT.20.)GO TO 58 EXEEX+EXPC-ARGU)

58 IFCEX.E..0.)GO TO 70

DO 60 KK8I1NN

KzKK-KK/2 Fpa.

IF(MOD(KK,2).EQ.0)Fu-I.

0.1612223560,

0,4086864819,

0.6288673967,

0.8070662040,

0.9313866907,

0,9935301722v

0.0639242385,

0.0591148396,

0.0503590355,

0.0382413510,

0.0235707608,

0.0073275539,

0.2247637903,

0.4669029047,

0.6778723796,

0.8435882616,

0.9529877031,

0.9987710072/

0.0631141922,

0.0572772921,

0,0076166584,

0,0347772225,

010196161604,

0.0031533460/

Figure F-I. Staff-Written Computer Listing

/

1.109-76

YYzF*XCK)*E+E

DI=YY*Yy÷ZZ*ZZ

ARGUUGMU*SQRT(Dl)

IF(ARGU.GT.2o.,)GO

TO 60

EXIEEX*EXP(-ARGU)*BULDUPCARGU)*YY/DI

SUM-SUM÷W( I*W(K)*EXI

60 CONTINUE

70 CONTINUE

DIxSUM*C*E/(A*SIGMZ)

RETURN

END

Figure F-I (continued)

1 .109-77

SUBROUTINE DINT

REAL MU

COMMON/DATAIT/MUZK*HoSIGZDIL

C

DOSE INTEGRAL ROUTINE WRITTEN

BY

C

DR,

JOHN N.

HAMAWI

C

YANKEE ATOMIC ELECTRIC COMPANY

C

NUCLEARSERVICES DIVISION

C

20 TURNPIKE ROAD

C

WESTBOROUGH#

MASSACHUSE-TTS 01581 C

YAEC REPORT No.

1105 C

C

COMMON

INFO

C

MU-MASS

ATTENUATION COEFFICIENT

(1/METERS)

C

ZK-BUILDUP FACTOR

(MU-MUA)/MUA

C

SIGZ-STANDARD DEVIATION OF PLUME (METERS)

C

DI-DOSE INTEGRAL

-I

TOTAL

C

L-

DETERMINES NUMBER OF INTERVALS

USED IN INTEGRATION

C**

DIMENSION CDATA(S),E(L9),B(49),P(9).

DATA M/9/,CDATA/5.OD+3

1.OD+4o,2.0D+4#,5.0D+÷,1.OD÷S/5 DATA AOA1,A2,A3,A4,AS/

-0.57721566,

0.99999193,

-

0,249910.55, C

0.05519968,-0.00976004,

0.00107857/

DATA BO,BI,B2,B3/0.26777373M3,

8.6347608925,

18.0590169730,

C

8.5733287401/

DATA CO,CIPC2,C3/

3.9584969228,

21.0996530827,

25.6329561486, C

9,5733223454/

DATA DDID2oD3,DD4,D5,D6oD7,D8,D9/

C

3543.75,989.,5888.,-928.,10496.,-4540.,1049b.,-928.,5888.,

9 8 9./

C****

COMPUTE LIMITS OF

INTEGRATION ZMIN

AND ZMAXs AND

INTERVAL

WIDTH

IF(L.LT.2.OR.L.GT.6)

L*

6 C S CDATA(L-I)

N U L*(M-1)

+ 1 SIGZ2 S

SI.GZ*SIGZ

ALFA

m H -

MU*SIGZ2 BETA = SIGZ*

SQRT(2.0*ALOG(C))

IF(ALFA.GT.O.0)

GO TO 150

ZMIN a 0.0

ZMAX x ALFA +

SQRT(ALFA*ALFA

+ BETA*BETA)

GO.TO 200

150 ZMIN 9 ALFA -

BETA

IF(ZMIN.LT.O.0)

ZMIN a

0.0

ZMAX.8 ALFA + BETA

2M DZ 2 (ZMAX-ZMIN)/(N-1)

C****

COMPUTE EXPONENTIAL

INTEGRAL

TERMS EUl) (SPECIAL

PROCED.

FOR E(1))

E(I)

2 2.1B907-ALOG(MU*DZ)

DO 2s0 I 8 1, N

Z 2 ZMIN + (I-i)*DZ

X a MU*Z

.IF(X.LE.0O) GO TO 250

X2 9 X*X

X3 *

X*X2 X4 2 X*X3 X5 z X*X4 IF(X.LE.I.0) E(I)

z -ALOG(X)

+ AO÷AI*X+A2*X2+A3*X3+A4*X4+AS*X5 IF4X.GT.10O) E(VI)

a (BO+BI*X+B2*X2÷B3*X3÷X4)/

C

(oCOI.C*X4C2*X2+C3*X3,X4)/(X*

EXP(X))

250 CONTINUE

C****

COMPUTE INTEGRAND

TERMS B(I1 AND P(I)

DO 309 I

p1 N

Z

ZMIN + (I-1)*DZ

Figure F-2. Hamawi-Written Computer Listing

1.109-78

Gu EXP(-(Z+H)*(Z+÷H/C2.0*SIGZ2))

+

EXP (-(Z-Hi*(Z-H)/C2.0*SIGZ2))

B(I) a G*E(I)

300 PCI)

a G* EXP(-MU*Z)

C**** PERFORM NUMERICAL INTEGRATION USING 9-POINT NEWTON-COTES

FORMULA

SUMB v 0.0

SUMP

u

0.0

MM

5 M -

I

KM x N -

M + I

DO 350 K 9 IpKMPMM

8UMB x SUMB + DI*B(K)+D2*B(K÷I)÷D3*B(K÷2)e+D*BCK÷3)÷n5*B(K+S)

C

+D6*B(K+5)+D7*B(K4bý+D8*B(K+7)+D

9 *BCK+8)

SUMP a SUMP + DI*P(K)+D2*P(K+I)+D3*P(K+2ý÷D1*P(K+3)+DS*P(K+4)

C

+Db*P(K+S)+D7*P(K*bj+DS*P(K+7)+D9*PCK+8)

350 CONTINUE

DOmDZ*(SUMB+SUMP*ZK)/(D*2.828427*SIGZ)

RETURN

END

Figure F-2 (continued)

1.109-79

REFERENCES FOR APPENDIX F

1. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.),

USAEC Report TID-241090,

1968.,

2.

J. N. Hamawi,

"A Method for Computing- the Gamma-Dose Integrals

1 and T2 for the Finite- Cloud Sector-Average Model," Yankee Atomic Electric Company Report YAEC-I105, 1976.

A

1.109-80

U. S. GOVERNM~ENT PRINTING OFFICE. 1988-202-292:80014

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555 FIRST CLASS MAIL

POSTAGE &t FEES PAID

USNRC

PERMIT No. G-67 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

S

Regulatory Guide 1.109: Difference between revisions

Latest revision as of 02:05, 17 January 2025

E. PURPOSE

1. Power Reactors

s. Released

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