Regulatory Guide 1.109: Difference between revisions

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


====s. REGULATORY ====
REGULATORY GUIDE 1.109                         "           "
GUIDE 1.109 " " CALCULATION  
                            CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE
OF ANNUAL DOSES.,'TO  
RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING COMPLIANCE WITH
MAN .fROM ROUTINE RELEASES OF REACTOR EFFLUENTS  
                                                  10 CFR PART SO, APPENDIX I
FOR THE PU.!RPOSE  
                                                                              7.?
OF EVALUATING  
                                        \'~       *%~
C 10 CFR PART SO, APPENDIX I 7.?OMPLIANCE
                                              5- I
WITH\'~ *%~5-I-~ ~USNRC REGULATORY  
                  -~     ~
GUIDES Comments should be sent to the Secretary of the Commission.
                      USNRC REGULATORY GUIDES                                       Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regultory Commission. Washingon D.C 20.                Attention. Doceing and Regulatory Guides are issued to describe and matte available to the publc          Service Section methods acceptable to the NRC still of implementing specific parts of the Commission's regulations, to delineate techntiques used by the sltff in evolu      The guides are issued in the foffowing tIn broad divisions sating specific problems or postulated accidents. or to provide guidance to eppli cants. RFegulatory Guides are not substitute% for regulatlons. end compliance      1. Power Reactors                      S. Products with them is not required. Methods end solution* different from those sot out in    2. Research and Test Roesctors          7 Transportation the guides will be acceptable It they provide a basis for the findings requistse to 3. Fuels and Materials facilitlee      a Occupational Health the issuance or continuance of a permit or license by the Commission                4. Environmental and Siting            2 Antitrust Review Comments and suggestions for improvements in these guides are encouraged            S. Meterials and Plant Protection      10 General at ail times, and guides will be revised. as appropriate, to accommodate corn mints and to reflect now information or aspetrience. However. cuminvets nn          Copies of published guiides msa be obteined by written request indicating the this guidea. f received within about Iwo months alter its Issuance will h. por      divisions desired to the U.S. Nuclear Regulatory Commrsrsun Washington. O.C
  ticularly useful in evaluating the need for an early revision                      206. Attention: Director. Office of Standards Development


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


Washingon D.C 20. Attention.
==A. INTRODUCTION==
......................................................................                                        1.109-7


Doceing and methods acceptable to the NRC still of implementing specific parts of the Service Section Commission's regulations, to delineate techntiques used by the sltff in evolu The guides are issued in the foffowing tIn broad divisions sating specific problems or postulated accidents.
==B. DISCUSSION==
........................................................................                                        1.109-7


or to provide guidance to eppli cants. RFegulatory Guides are not substitute%
==C. REGULATORY POSITION==
for regulatlons.
...............................................................                                      1.109-8
    1.  Radiation Doses from Liquid Effluent Pathways.                                                ..........................109-8 a.      Potable Water ...........................................................                                    1.109-8
          6.      Aquatic Foods ...........................................................                                    1.109-8 c.      Shoreline Deposits ....... ... ...........................................                                    1.109-8 d.      Irrigated Foods .........................................................                                    1.109-8
    2.  Gamma and Beta Doses from Gaseous Effluents ..................................                                        1.109-10
          a.      Gamma Air Dose Rates for Elevated Releases ..............................                                    1.109-10
          b.      Ganma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases                                          ........................... 1.109-11 c.      Total Body Dose Rates from Elevated Releases ............................                                    1.109-11 d.      Skin Dose Rate from Elevated Releases ...................................                                    1.109-12 e.      Total Body Dose Rates from Ground-Level Releases ........................                                    :.109-12 f.      Skin Dose Rates from Ground-Level Releases ..............................                                    1 109-12
    3.  Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere...                                        1.109-12 a.      External Irradiation from Activity Deposited onto the Ground Surface .... 1.109-13 b.      Inhalation ...............................................................                                    1.109-13 c.      Ingestion.                    .................................................. 1.109-13
    4.  Integrated Doses to the Population ...........................................                                      l.lO9-l1
    5.  Summary of Staff Position..........................................1.109-14


end compliance
==D. IMPLEMENTATION==
1. Power Reactors S. Products with them is not required.
....................................................................                                      1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO
THE AQUATIC ENVIRONMENT ................................................................                                        1.109-17
    1.  Equation for Calculating Radiation Dose via Liquid Pathways ..................                                        1.109-17 a.      Concentration in Environmental Media (Cip) ..............................                                    1.109-17 b.      Usage (Uap) .............................................................                                    1.109-17 C.      Dose Factor (Dp"p ) .....................................................                                    1.109-20
    2.  Equation for Liquid Pathways ................................................                                        l.l09-20
          a.      Potable Water                        ...............................................                          1.109-20
          b.      Aquatic Foods..                                                        ............................          1.109-20
          c.      Dose from Shoreline Deposits ............................................                                    1.109-30
          d.      Dose from Foods Grown on Land Irrigated by Contaminated Water ...........                                    1.109-33 REFERENCES FOR APPENDIX A..............................................................                                        1.109-36 APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE
ATMOSPHERE ............................................................................                                        1.109-39
                                                                              1.109-3


Methods end solution*
TABLE OF CONTENTS (Continued)
different from those sot out in 2. Research and Test Roesctors
                                                                                                  Page
7 Transportation the guides will be acceptable It they provide a basis for the findings requistse to 3. Fuels and Materials facilitlee a Occupational Health the issuance or continuance of a permit or license by the Commission
    1.  Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................        1.109-39
4. Environmental and Siting 2 Antitrust Review Comments and suggestions for improvements in these guides are encouraged S. Meterials and Plant Protection
    2.   Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose ..............................................................      1 .109-40
10 General at ail times, and guides will be revised. as appropriate, to accommodate corn mints and to reflect now information or aspetrience.
    3.  Annual Dose to Tissue from Noble Gas Effluents ..............................        1.109-40
          a.        Elevated Releases .......................................................  1.109-40
          b.        Ground-Level Releases ...................................................    1.109-42 REFERENCES FOR APPENDIX B..............................................................        1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ...................................        1.109-45
    1.  Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane .................................................................        1.109-45
    2.  Annual Dose from Inhalation of Radionuclides in Air ..........................        1.109-46
    3.   Concentrations of Airborne Radionuclides in Foods ............................        1.109-46 a.        Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .............................................                1.109-55 b.       Parameters for Calculating Nuclide Concentrations in Milk............        1.109-55
    4.


However. cuminvets nn Copies of published guiides msa be obteined by written request indicating the this guidea. f received within about Iwo months alter its Issuance will h. por divisions desired to the U.S. Nuclear Regulatory Commrsrsun Washington.
c.       Parameters for Calculating Nuclide Concentration in Meat ................
          Annual Dose from Atmospherically Released Radionuclides in Foods .............
                                                                                                1.109-59
                                                                                                1.109-59 I
REFERENCES FOR APPENDIX C..............................................................        1.109-60
APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
EFFLUENTS...............................................................................        1 .109-63
      1.  General Expressions for Pý.pulation Dose ......................................      1.109-63
    2.  Use of the Models .............................................................      1.109-67 a.        Population-Integrated Doses from Liquid Effluents .......................    1.109-67 b.        Population-Integrated Doses from Airborne Effluents .....................  1.109-68 REFERENCE FOR APPENDIX D...............................................................         1.109-69
                                                                                        1.109-4


O.C ticularly useful in evaluating the need for an early revision 206. Attention:
TABLE OF CONTENTS (Continued)
Director.
                                                                                                                          Page
    1.  Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................                                1.109-39
    2.  Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose ..............................................................                              1.109-40
    3.  Annual Dose to Tissue from Noble Gas Effluents ..............................                                1.109-40
          a..    Elevated Releases .......................................................                            1.109-40
          b.      Ground-Level Releases ...................................................                            1.109-42 REFERENCES FOR APPENDIX B..............................................................                                1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ...................................                                1.109-45
    1.  Annual External Dose from birect Exposure to Activity Deposited on the Ground Plane .................................................................                              1.109-45
    2.  Annual Dose from Inhalation of Radionuclides in Air ..........................                                1.109-46
    3.  Concentrations of Airborne Radionuclides in Foods ............................                                1.109-46 a.      Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .........................................................                            1 .109-55 b.      Parameters for Calculating Nuclide Concentrations in Milk ...............                            1.109-55 c.      Parameters for Calculating Nuclide Concentration in Meat ................                            1.109-59
    4.  Annual Dose from Atmospherically Released Radionuclides in Foods .............                              1.109-59 REFERENCES FOR APPENDIX C ..............................................................                              1.109-60
APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
EFFLUENTS... ...........................................................................                                1.109-63
    1.  GeneralExpressions for P p,,jlation Dose ......................................                              1.109-63
    2.  Use of the Models ...................................                              ........................ 1.109-67 a.      Population-Integrated Doses from Liquid Effluents .......................                            1.109-67 b.      Population-Integrated Doses from Airborne Effluents .....................                            1.109-68 REFERENCE FOR APPENDIX D...............................................................                                1.109-69 E
                                                                                      1.109-4


Office of Standards Development TABLE OF CONTENTS Page  
LIST OF TABLES
Table                                                                                                                      Page
  1  Summary of Staff Position - Methods of Evaluating Compliance with Appendix i ..................................................................                                  1 .109-15 A-I  Definition of Points at Which Concentrations in Environmental Media (Clp)
        Should be Calculated ........................................................                                  1.109-18 A-2  Recommended Values for Uap to be Used for the Maximum Exposed Individual in.Lieu of Site-Specific Data ...............................................                                  1.109-19 A-3  Adult Ingestion Dose Factors ..................................................                                  1.109-21 A-4  Teenager Ingestion Dose Factors ...............................................                                  1.109-25 A-5  Child Ingesticn Dose Factors ..................................................                                  1 .109-26 A-6  Infant Ingestion Dose Factors .................................................                                    1.109-27 A-7  External Dose Factors for Standing on Contaminated Ground .....................                                  1.109-28 A-8  Bioaccumulation Factors .......................................................                                  1 .109-31 A-9  Shore Width Factors for Use in Equations (A-5) and (A-6) ......................                                  1.109-34 A-10  Animal Consumption Rates ......................................................                                    1.109-34 B-i  Dose Factors for Noble Gases and Daughters                                            ..............................
                                                                                                                        1.109-41 C-1  Adult Inhalation Dose Factors .................................................                                  1.109-47 C-2  Teenager Inhalation Dose Factors ..............................................                                  1.109-51 C-3  Child Inhalation Dose Factors .................................................                                    1.109-52 C-4  Infant Inhalation Dose Factors ................................................                                    1.109-53 C-5  Stable Element Transfer Data ..................................................                                  1.109-56 C-6  Nuclide Transfer Parameters for Goat's Milk ...................................                                  1.109-57
0-1  Recommended Values to be Used for the Average Individual in Lieu of Site-Specific Data ..........................................................                                    1.109-64
0-2  Recommended Values for the Transport Times in the Food Distribution System ......................................................................                                  1 .109-66
                                                                                    1.109-5


==A. INTRODUCTION==
==A. INTRODUCTION==
......................................................................
Section 20.106, "Radioactivity in Effluents to Unrestricted Areas," of the Nuclear Regulatory Commission's regulations in 10 CFR Part 20, "Standards for Protection Against Radiation," estab- lishes limits on concentrations of radioactive material in effluents to unrestricted areas.
1.109-7
 
Paragraph (c) of 5 20.1, "Purpose," of 10 CFR Part 20 states that licensees s;hould, in addition to complying with the limits set forth in that part, make every reasonable effort to maintain releases of radioactive materials in effluents to unrestricted areas as far below the limits specified as is reasonably achievable.
 
Sections 50.34a, "Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents -- Nuclear Power Reactors," and 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"
set forth design objectives and technical specifications to control releases of radioactive efflu- ents from light-water-cooled nuclear power reactors.     Section 50.36a of 10 CFR Fart 50 further provides that, in order to keep power reactor effluent releases as low as is reasonably achiev- able, each operating license will include technical specifications that (a) require compliance with the provisions of § 20.106 dealing with effluent discharge limits, (b) require that operating procedures for the control of effluents be established and followed and that eqi ipment installed in the radioactive waste system be maintained and used, and (c) establish re( :,-ements for reporting measured releases of radionuclides to the environment.
 
Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light- Water-Cooled Nuclear Power Reactor Effluents," to 10 CFR Part 50 provides numerical guidance for radioactive effluent design objectives and technical specification requirements for limiting conditions of operation for light-water-cooled nuclear power plants.
 
To implement Appendix I, the NRC staff has developed a series of guides that provide methods acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man.   This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.
 
The methods used herein are general approaches that the NRC staff has developed for application in lieu of specific parameters for individual sites. The use of site-specific values by the applicant is encouraged.   However, the assumptions and methods used to obtain these parameters should be fully described and dncumented.
 
The procedures and models provided in this guide will be subject to continuing review by the-staff with the aim of providing greater flexibility to the applicant in meeting the require- ments of Appendix I. As a result of such reviews, it is expected that alternative acceptable methods for calculation will be made available to applicants and that calculational procedures found to be unnecessary will be eliminated.
 
This guide supersedes portions of Regulatory Guide 1.42, Revision 1, "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors," which is being withdrawn.


==B. DISCUSSION==
==B. DISCUSSION==
........................................................................  
Appendix I to 10 CFR Part SO provides guidance on the levels of exposure of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable.   This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses.     These estimates can be used to implement Appendix I in lieu of site-specific phenomena actually affecting the estimation of radiation exposure.
1.109-7 C. REGULATORY
 
POSITION ...............................................................  
In this guide, the term "dose," when applied to individuals,  is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU).
1.109-8 1. Radiation Doses from Liquid Effluent Pathways.
                                                1.109-7
 
Appendix A of this guide describes suggested methods for calculating the estimated doses to man from discharges to the hydrosphere. Appendix B of this guide describes suggested models and assumptions for calculatinr        submersion doses from radionuclides discharged to the atmosphere, and Appendix C gives equations for estimating doses from radioiodines and other radionuclides released to the atmosphere. Appendix D describes the models and assumptions for calculating population dose (man-rem and man-thyroid-rem) from radionuclide releases to the atmosphere and hydrosphere.
 
The models and assumptions described in Appendices A, B, C, and D of this guide are accept- able to the NRC staff for calculating doses to individuals and populations.           If other models are selected, they should include the same exposure pathways and physical mechanisms as are used in the models described in this guide.
 
As discussed in Section III.A.2 of Appendix I to 10 CFR Part 50, the applicant may take into account any real phenomena or actual exposure conditions that affect or modify the estimate of radiation exposure. Such conditions should include actual values for agricultural productiv- ity, residence times, dose attenuation by structures, measured environmental transport factors (suchas bioaccumulation factors), or similar values actually determined at a specific site.
 
The applicant should provide e-ough information on the measurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.


..........................
==C. REGULATORY POSITION==
109-8 a. Potable Water ...........................................................
1.   Radiation Doses from Liquid Effluent Pathways The NRC staff will calculate radiation doses from potable water, aquatic food, shoreline deposits, and irrigated food pathways by using the following equations from Appendix A of this guide.
1.109-8 6. Aquatic Foods ...........................................................
1.109-8 c. Shoreline Deposits ....... ... ...........................................
1.109-8 d. Irrigated Foods .........................................................
1.109-8 2. Gamma and Beta Doses from Gaseous Effluents
..................................
1.109-10 a. Gamma Air Dose Rates for Elevated Releases ..............................
1.109-10 b. Ganma Air Dose Rates from Ground-Level Releases;
Beta Air Dose Rates from Elevated and Ground-Level Releases ...........................
1.109-11 c. Total Body Dose Rates from Elevated Releases ............................
1.109-11 d. Skin Dose Rate from Elevated Releases ...................................
1.109-12 e. Total Body Dose Rates from Ground-Level Releases ........................
:.109-12 f. Skin Dose Rates from Ground-Level Releases ..............................
1 109-12 3. Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere...
1.109-12 a. External Irradiation from Activity Deposited onto the Ground Surface .... 1.109-13


====b. Inhalation ====
a.    Potable Water MU1100
...............................................................
                          M ,n R                        QiDaipjexp(-Xitp)                                      (1)
1.109-13 c. Ingestion.
      b.   Aquatic Foods Raj'1100 UapM pn*                  -At2 I
            Rapi    1100    F      QiBipoaipjexp(-Aitp)                                    (2)
      c.    Shoreline Deposits Wn 0
            Rapj = 110,000            I QiTiOai    [exp('Xitp)][l - exp(-'0t)]              (3)
      d.   Irrigated Foods For all radionuclides except tritium:
              ap      p veg  n  dIexp( At )D      . [r[l - exp(-AEite)]    Biv[l - exp(-xitb)]]
            Rapj    Uap        i I        ih alpj    L      YvEi          *J
                        Uanimal n            {QFd exp(Xith)    r[ - exp(-Eite)]
                        + Uap      SiA aipj                          YvxEi BivDl - ep-lb]
                    +            pexp(-itb)]    + CIAwQAw}                                  (4)
            For tritium:
            Rp        vegC D          animal                                                  (5)
                                            Dapj LA"(w +QAw)
                  -
              api = ap v apj + Uap
                                                      1.109-8
                                                                                                          4


..................................................
where Bip    is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentratio., in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/lizer), in liters/kg;
1.109-13 4. Integrated Doses to the Population
        Biv    is the concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;
...........................................
      CiAw    is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter);
l.lO9-l1 5. Summary of Staff Position..........................................1.109-14
        Ciw    is the radionuclide concentration in water, in pCi/liter;
      Daipi    is the dose factor, specific to a given radionuclide i, pathway p, organ j, and individual's age a, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in water, expressed as a ratio of the dose rate (in mrem/hr) and the radionuclide concentration in water (in pCi/liter);
        di    is the deposition rate of nuclide i, in pCi/m2 per hr;
          F  is the flow rate of the liquid effluent, in ft 3 /sec;
          k  is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle);
        Mp    is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food) as described in Table A-1 (in Appendix A of this guide),
              dimensionless;
          n  is the number of radionuclides that are to be considered;
          P  is the effective "surface density" for soil, in kg(dry soil)/m 2 . Assuming a uniform mixing of all radionuclides in a plow layer of 15 cm (6 in.) depth, P has a value of approximately 240 kg/mi2 ;
        QAw    is the consumption rate of contaminated water by an animal,  in liters/day;
        QF    is the consumption rate of contaminated feed or forage by an animal,  in kg/day (net weight);
          Qi  is the release rate of nuclide i,  in Ci/yr;
          r  is the fraction of deposited activity retained on crops (which is 0.25 for sprinkler irrigation, 0.2 for particulates, and 1.0 for airborne deposition of radionuclides), dimensionless;
      R    .i is the total annual dose to organ j of individuals of age a from all of the RaPj  nuclides I in pathway p, in mrem/yr;
        Si    is the transfer coefficient for radionuclide i which relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product)
              per pCi/day;
          t  is the period of time for which sediment is exposed to the contaminated water, nominally taken to be the mid-point of the operating lifetime of the facility, in hours;
        tb    is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours;
        te    Is the time period that crops are exposed to contamination during the growing season, in hours;
                                        1.109-9
 
th      is a holdup time that represents the time interval between harvest and consumption of the food, in hours;
              T      is the radioactive half life of nuclide i, in days;
              tp      is the average transit time required for nuclides to reach the point of exposure. For internal dose, t is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;
              Ua      is a usage factor that specifies the exposure time or intake rate for an Uap    individual of age a associated with pathway p, in hr/yr or kg/yr (as appro- priate);
                w    is the water intake rate via fresh forage (28 liters/day for beef cattle and
                      38 liters/day for dairy cattle);
                W    is the shoreline width factor, dimensionless;
              Yv    is the agricultural productivity (yield), in kg(wet weight)/m2 AEi    is the effective removal rate constant for radionuclide i from crops, in hr"
                      provided that AEN : Ai + Awl where Ai is the radioactive decay constant, in (hr)-I, and Aw is the removal rate constant for physical loss by weathering (Xw = 0.0021 hr- 1 , which corresponds to a removal half-life of 14 days);
              Ai    is the radioactive decay constant of nuclide i,    in hr  ,
              AM    is the water elimination rate constant (0.32/day for beef cattle and 0.28/day for dairy cattle);
            1100      is the factor to convert from (Ci/yr)/(ft 3 /sec)  to pCi/liter; and
        110,000      is the factor to convert from (Ci/yr)/(ft 3 /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.
 
These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose com*,itments to the total body or any organ of an individual from the sum of the exposure path- ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.
 
2.   Gamma and Beta Doses from Gaseous Effluents The NRC staff will calculate radiation doses from gaseous effluents using the following equations from Appendix B of this guide. The definitions of elevated and ground-level releases are found in Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors," and Appendix B to this guide.
 
a.   Gamma Air Dose Rates for Elevated Releases
                        260                                            IDA
                          -7(o n~~ un  ns    I(Ek)IE(H,u,s,oz,Ek          ik                (6)
where Aki      is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration;
        DY(r,o)      is the annual total gamma air dose at a distance r in the sector at angle 0,
                      in mrad/yr;
              Ek    is the energy of the kth photon energy group, in MeV/photon;
                                                1.109-10
 
fns      is the fraction of the time that stability class s and wind speed n occur for sector 0, dimensionless;
I(H,utsoz,Ek)          Is the result of the numerical integration accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and.
 
atmospheric stability (s)which in part determine the effective stack height (H)and the vertical plume standard deviation (o). In addition, I is a function of the photon energy E,1and is T = 1 4 kT2 as formulated in Slade (see Reference I fi:    Appendix B of this guide);
                'D
              Qn1      is the the releaser rate distance    under ofwind radionuclide i, corrected fnr decay during transit to speed un, in Ci/yr;
                  r    is the distance from the release point to the receptor, in meters;
                un      is the me;'n wind speed of wind speed class n, in m/sec;
                AO      is the sector width over which atmospheric conditions are averaged, in radians;
                      and ua(Ek)      is the air energy absorption coefficient for the kth photon energy group, in m1 .
      b.     Gamma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases Dy(r,o) or DO(r,0) = 3.17 x 1O4o3 QI[/Q '/    )D  r
                                                            ](r,o)(OFi  or DF')
                                                                      ( or                  (7)
where
                  8 DF'Y OF        are the gar,.na and beta air dose factors for radionuclide I,
                                  3 in mrad per yr/
          I' I        pCi per n ;
    Dy(r,O) or are the annual gamma and beta air doses at the distance r in the sector at D'(r,o)
                      angle 0 from the discharge point, in mrad/yr;
                Qi    is the release rate of the radionuclide I, in Ci/yr;
  [x/Q']O(r,e)        is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors," for methods to estimate x/Q'); and
    3.17 x lO4        is the number of pCi per Ci divided by the number of seconds per year.
 
c.     Total Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t]                                        (8)
where oT(r,e)      is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr;
        DY(r,o)      is the annual gamma air dose associated with the kth photon energy group at k          the distance r in the sector at angle 0 from the discharge point, in mrad/yr;
                                                    1.109-11
 
SF      is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless;
                  t      is the product of tissue density and depth used to determine a "whole-body"
                        exposure. This depth is 5 cm, which is equivalent to t = 5 g/cm2 ;
            T(Ek)        is the tissue energy absorption coefficient, in cm2 /g; and k)
            1.11        is the average ratio of tissue to air energy absorption coefficients.
 
d.     Skin Dose Rate from Elevated Releases oS(r,O) = l.1ISFOY(r,O) + 3.17 x 10 ' F Qi[x/QJ]D(rO)DFS                      (9)
where DFSi        is the beta skin dose factor for the radionuclide i which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr. This attenuation is for 70 micrometers or 7 mg/cm2 .f tissue; and DS(r,0)        is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/yr.
 
All other parameters are as defined in preceding sections.
 
e.     Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF
* xi(r,o)DFBi                                              (l0)
where DFBi      is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in Appendix B of this guide);
                                                                                                      4 DT(r,)        is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e)        is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 .
All other parameters are as defined above.
 
f.     Skin Dose Rates from Ground-Level Releases D5 (r,0) = 1.11 SF *xi(r,e)DF    +  xi(rO)OFSi                            (1i)
where D5 (r,O)        is the annual skin dose due to immersion in a semi-infinite cloud at the distance  r in the sector at angle 0 from the discharge point, in mrem/yr.
 
All other parameters are as defined above.
 
3.   Doses from Radioiodines and Other Radionuclides Released to the Atmosphere The NRC staff will calculate radiation doses from radioiodines and other radlonuclides released to the atmosphere using the following equations from Appendix C of this guide.
 
i
                                                  1.109-12
 
a.     External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF      cG(r,o)DFG..
                                      G                                                      (12)
where CG    is the ground plane concentration of radionuclide i, in pCi/m 2 ;
                  Ci DFGij      is the open field ground plane dose conversion factor for organ J from radio- nuclide i, in mrem-m 2 /pCi-hr;
          DG(r,O)        is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr;
                  SF    is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless;
                        and
              8760      is the number of hours in a year.
 
b.     Inhalation DA (r,o)    R    xi(r,o)DFAi                                                  (13)
where O (rO)          is the annual dose to organ      j of an individual in the age group a at location
                *      CrO) due to inhalation of all radionuclides, in mrem/yr;
            DFA. ijaa    is  the inhalation dose factor for radionuclide i, organ j, and age group a, in mrem/pCi;
                                                                                                3 Ra    is the annual air intake for individuals in the age group a, in m /yr; and
                                                                                                      3 xi(r,o)        is the concentration of radionuclide i in air at location (r,o), in pCi/m .
      c.       Ingestion o    r    v            m          .FL            L    1)
                  a (ro=
                D. (ro)ja
                          2DFIi -[I a 9cV(r,+)
                                            i
                                                  + UaCim(r,o)
                                                      a
                                                                + U.i(r,o) + Uaf Ci(r, ai      +  az
                                                                                              (14)
                                                                                              (4 where
          ,CF(r,O),
C.(r,o), C.(r,O)        are  the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg. These variables are determined using Equation (C-7) from Appendix C of this guide;
            D3 (r,o)      is the annual dose to the organ j of an individual in age group a from inges- ja          tion of all radlonuclides at location (r,o), in mrem/yr;
              DFlija    is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi;
                  f ft  are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note: fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U      Uvn, Um, UF    are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a Ua'  a a    respectively, for individuals in the age group a, in kg/yr.
 
1.109-13
 
4.   Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1, 2, and 3. Because of the various conditions under which the equa- tions in Appendix D are used, they are not presented in this section.   It is recommended that Appendix D be read for a detailed discussion of the staff's models.
 
5.   Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I
is presented in Table 1.


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


==A. INTRODUCTION==
II
Section 20.106, "Radioactivity in Effluents to Unrestricted Areas," of the Nuclear Regulatory Commission's regulations in 10 CFR Part 20, "Standards for Protection Against Radiation," estab-lishes limits on concentrations of radioactive material in effluents to unrestricted areas.Paragraph (c) of 5 20.1, "Purpose," of 10 CFR Part 20 states that licensees s;hould, in addition to complying with the limits set forth in that part, make every reasonable effort to maintain releases of radioactive materials in effluents to unrestricted areas as far below the limits specified as is reasonably achievable.
                                                                                                  I
                                              1.109-14
 
TABLE 1 SUMMARY OF STAFF POSITION -
                        METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I
                            APPENDIX I                POINT OF DOSE              EQUATIONS
TYPE OF DOSE              DESIGN OBJECTIVE                EVALUATION            TO BE USED
Liquid Effluents Dose to total          3 mrem/yr per unit          Location of the highest    1, 2, 3,  4, &5 body from all                                        dose offsite*
  pathways                                              (see also Table A-I).
  Dose to any organ      10 mrem/yr per unit          Same as above.            1, 2, 3,  4, &5 from all pathways Gaseous Effluents**
  Gamma dose in air      10 mrad/yr per unit          Location of the            6 or 7, as highest dose offsite.***  appropriate Beta dose in air        20 mrad/yr per unit          Same as above.             7 Dose to total body      5 mrem/yr per unit          Location of the            8 or 10, as of an individual                                    highest dose offsite.*    appropriate Dose to skin of an      15 mrem/yr per unit          Same as above.            9 or 11, as individual                                                                      appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ      15 mrem/yr per unit          Location of the          12, 13, & 14 from all pathways                                    highest dose offsite.,'
    Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.
 
Calculated only for noble gases.
 
Evaluated at a location that could be occupied during the term of plant operation.
 
Doses due to carbon-14 and tritium intake from terrestrial food chains are included in this category.
 
tt Evaluated at a location where an exposure pathway actually exists at time of licensing. How- ever, if the applicant determines design objectives with respect to radioactive iodine on the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine: (l) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives; (2) whether changes in land and water usage and food pathways which would result in individual exposures greater than originally estimated have occurred; and (3) the content of radioactive iodine and foods involved in the changes, if and when they occur.
 
1.109-15
 
APPENDIX A
                          METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE
                                  DISCHARGES TO THE AQUATIC ENVIRONMENT
      The equations for estimating radiation exposure to man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.          The equations can be used to calculate the annual doses to various organs of a child, 0 - 11 years; a teen, 12 - 18 years;
and an adult, 18+ years.
 
1.  Equation for Calculating Radiation Dose via Liquid Pathways Equa*tion (A-l) is the fundamental equation for calculating the radiation dose to man via liquid effluent pathways.
 
aipj  C ip Uap aipj                                                        (A--)
where Cip    is the concentration of nuclide i in the media of pathway p,        in pCi/kg;
            Dai        is the dose factor which is specific to a given radionuclide. i, pathway p, organ j, and individual's age a.      It represents Lhe annual dose due to the intake of a radionuJide, in mrem/pCi, or from exposure to a given concen- tration of a radionuclide in water, in mrem per hr/pCi per liter;
            Raip        is the annual dose to organ j of an individual of age a from nuclide i via apip      pathway p, in mrem/yr; and Uap    is the exposure time or intake rate (usage) associated with pathway p for lap    .ge group a, in hr/yi or kg/yr (as appropriate).
      The three factors making up Equation (A-1) are discussed in the following sections, most of which were taken directly from the WASA-1258 report (Ref. 1).            (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the BNWL-1754 report (Ref. 2).)
      a.    Concentration in Environmental Media (Cip)
            The points at which concentrations in environmental media of interest should be evaluated are shown in Table A-1.        The concentrations can be estimated from the mixing ratio Mp , the bio- accui;ýulation factor Bip, the radionuclide release rate Qi,        and other terms presented in the path- way equations that appear later in this discussion.
 
b.    Usageý (Uap)
            The second term of Equation (A-l)      is the usage term Uap.    Usage is expressed as a consumption rate in kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the pathway p and age group a under consideration.
 
The NRC staff encourages the use of site-specific data, whenever possible, for param- eters such as those included in Table A-2. Such data should be documented.            In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Table A-2 are reconmnended.*
  In selecting usage values, not only the present land and water uses should be considered, but also changes in land and water uses made possible by such activities as chemical pollution abatement.    Radioactive material released into waterways may include long-lived radionuclides that have potential for accumulation in sediments and biota and may persist for many years --
  perhaps beyond the lifetime of the nuclear power station.
 
1.109-17
 
TABLE A-I
                                      DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip)
                                                                SHOULD BE CALCULATED
                                                                                                        SUBMERGED (single or multi- PATHWAY                  SURFACE - LOW VELOCITY              SURFACE - HIGH VELOCITY              port) - HIGH VELOCITY
  Fish (fresh and salt water)      Discharge canal              Edge of initial mixing zone*        Edge of initial mixing zone**
  Invertebrates                    Discharge canal              Edge of initial mixing zone*        Edge of initial mixing zone**
  Shoreline                        Discharge canal              Point of contact of diluted          Point of contact of diluted effluent with shoreline              effluent with shnreline CO
  Drinking water                    Nearest anticipated          Nearest anticipated downstream      Nearest anticipated downstream downstream supply***        supply,*                              supply***
  Irrigated crops                  Nearest anticipated          Nearest anticipated point of        Nearest anticipated point of point of withdrawal          withdrawal for irrigation +          withdrawal for irrigation- for irrigation t Point where effluent has undergone prompt dilution near the surface (about 5:1 for large receiving water bodies).
      Point where effluent has undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water).
      Fresh water sites only. The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections over the plant lifetime, is the closest point to the site where a drinking water supply exists or could exist.
 
AFresh water sites only. The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land use projections over the plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists or could exist.
 
____
 
TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U SED FOR THE MAXIMUM
                        EXPOSED INDIVIDUAL IN LIEU OF S]ITE-SPECIFIC DATA
          PATHWAY                        CHILD              TEEN      ADULT        UNITS
Fruits & vegetables & graina'b            520.0              630.0      520        kg/yr Leafy vegetablesa                          26.0              P?.0        64        kg/yr Milka,c                                  330.0              100.0      310        liters/yr Meat & poultrya                            41.0              65.0      110        kg/yr Fish (fresh or salt) d                      6.9
                                                              16.0        21        kg/yr Sea fooda                                    1.7                3.8          5      kg/yr Drinking waterc'e                        510.0              5510.0      730        liters/yr Shoreline recreation e                      14.0
                                                              67.0        12        hr/yr e
Boating                                    29.0              52.0        52        hr/yr
                                                                        73 0 0 f Inhalation                              2 7 00 . 0 e        51,O0.,e                m 3/yr
                                        190P.O(infant)g aconsumption rate obtained from Reference 3 for average individual and age-prorated and maximized using techniques contained in Reference 4.
 
bconsists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24? grain.
 
CAn additional category of maximum individual (1-yr old) should be added for these pathways.
 
Consumption rates are the same as the child's.
 
dConsumption rate for adult obtained by averaging data from References 4, 6-9 and age-prorating using techniques contained in Reference 4.
 
eData obtained directly from Reference 4.
 
fData obtained directly from Reference 15.
 
glnhalation rate for infant obtained by averaging data from References 10-14.
 
1.109-19
 
C.    Dose Factor (Daip.)
            Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref. 15) for body burden and ma):imur permissible concentration (r.IPC).  Effective absorbed energies for the radionuclides are calcu- lated from the ICRP model. Appendix D of Reference 16 was used as a basic source of age-dependent dose factors for ingestion. Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.
 
The dose factors for external exposure were based on the assumption that the con- taminated medium is large enough to be considered an "infinite volume" relative to the range of the emitted radiations. Under this assumption, the energy emitted per gram of medium is equiva- lent to the energy absorbed per gram of medium corrected for the differences in energy absorption between air or water and tissue and for the physical geometry of each specific exposure situation.
 
Material deposited from sedimentation in an aquatic systet, or from irrigation water onto the ground represents a fairly large, nearly uniform thin sheet of contamination. The factors for converting surface contamination given in pCi/m 2 to the annual gaisia dose at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 4, 5, and 17).    Dose factors for exposure to soil sediment have units of mnrern/hr per pCi/1n2 surface.
 
A set of dose factors for 45 radionuclides was originally calculated for the year 2000
model (Ref. 4). These factors have since been recalculated using recent decay scheme informia- tion (Ref. 18) and expanded to include additional radionuclides. The revised list is given in Tables A-3 through A-7; it contains several radionuclides for which the daughter is not listed separately (e.g., Ru-Rh-106, Cs-137-Ba-137m, and Ce-Pr-144).    In those instances, the daughter's decay energy has been included in the factor.
 
2.    Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel.    Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated.    The doses from the four pathways should be added to determine the total dose.
 
a.    Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below:
            Rapj = 1100    Uap  Qjexp(-x. .t )Daipj                                      (A-2)
                apF            1            p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.
 
The sunmation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected. The Q!/F termis in Equation (A-2) define the concentration of nuclide i in the effluent at the point of discharge. The expression (QMM /F)exp(-A t ) yields the concentration of nuclide i at the time the water is consumed.
 
I pconcentration This            i p is the term Cip in Equation (A-1). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system. The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake. Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 4.
 
It should be noted that, depending on the hydrological dispersion model employed, the mixing ratio, M'Ip,or dilution factor may not be explicitly defined. In those instances (e.g.,
buildup of activity in a cooling pond), the relative concentration in the mixed stream (compared to the effluent concentration) may be supplied as a function of the radiological decay constarnt.
 
with any potential effluent recycling taken into account. Suggested hydrological dispersion ,:odels will be contained in another regulatory guide now under preparation on the subject of methods for estimating aquatic dispersion of liquid effluents from routine reactor releases for the purpose uO
implementing Appendix I.
 
b.  Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations,
                                                  1.109-20
 
TABLE A-3 ADULT INGESTION DOSE FACTORS
                                              (mirem/pCi ingested)
    'JUCLIDE    BO.E      LTVER          TnTAL 81)Y        1,i 3lI-O1    KT)NEY          LUNG      GI-LL I
  I        3  0.0          1.34E-n7          1 .3UE-07                    I, S.
 
3 E-fl7    I .,OE-07    I. SiF-n7
  4BE    10    3.l18-06    4.91E-n7          7.o5EF-0      n n            3. 71E-n7    0.0          2.bMF-0'i bC      14  P.BUE-06    5.69E-07          ri.bqE-7      5, qF -07      5.69F-07      S.bqE-07    5.bQE -07
  7N      13  B.37E-09                                        *l3 7EF- 0 9 8. 37E-ng          $7F-09  6. 371F-09
                            9.37E-09          ý. 37E-09                                    '.
  QF      IS  b.2SF-07    1.0              b.93E-OR      n.n            0.0          0.0
IPJA    22    1.70F-05    I.74E-05        I .74E-05      I .711E-05      I . 74E-nc    I . 74E-05    I ASE-05 IlIA    24    21,2OF-Ob                                                                  >. ?6*E-..0  P. 26F-Uh
                            2.?bE-0b          2.2hE-rib      22.2SE-0b      22.?6F.-06
          32    1.Q3F-04    1. 21 E-05        7,* 7F.-t0h                    0.0          0.0          2.1I 7E -09
1 5P                                          2. olE-nS
20CA    ul    1.87E-0'J    0.0                              0.n            0.0              ,0.        I ..ýJF -0i7 I .OOF-0B                  5.21F -05
21SC    Ub.  5.SIF-OQ    I .nBE-08        3.11 E-OQ
                                                              1.S5QF-0*                    3. 53F-n9
24CP    51    o.0                            2.bbE-19                                                  1 . ttIE -07
254.4      a  n0            S.57E-o6        .8 73E-.07    0.0                36RIE-06  0.0
25mN    5b    0.0          I . I9E-07        2. 0SE-OR      n n            l,6bE-07      0.0          3.h7F-O6
                                                              0.0              0.0
2hFE    55    b.20E-0O    2.79F-oS          7.33E-06                                    1.23E-05    I . oW -05
2bFE    59    U.3UE-0b    1 .03E-09        3.9?E-06      0.0            0.n                        5.4OF-06
27Cf0    57    0.0            .7 5 -07        2.JI1E-07      n.0            0.0
                                              I .67E-1b      0.0            0.0                        1 .91F-05
27C0    5B    0.0          / . I,SE -{') 7                  0,0                          0.0
27C0    60    0.0          2. 15E-0b        U,72E-nb                      0.0          n0.      -nb    ,022F-OS
                                                              0.0
28,NI    59    9.77E-06    3. 35E-O0        I .b3E-06      ( n                          0.0          b790E-07
                                                                              0.0
28N1    63    1.30E-O0    9.02E-O0          4.36F-Ob                                        ,00
284I    b5    5,20E-07    b.B7E-ng          3.1 3E-08                      0.0                        7I1.i
                                                                                                            .t i O-06 B F- Oh
2qCU    b4    ).0          5.3'JE-06        3.92E-OR                      ? 1nF - n                  Q.70E-(6
30ZN    65    U.SE-06      1 .54F-05        6.97E-08                      1 03E-nS                  2.49F-05
30ZN    b94  1.70F-07    u .0, E-07        3.731E0'      0,0            ?. USE- n7    0*,0
                                                              0.0                          0,0
                                                                                            0. n
30ZN    b9    1.03E-08    1 9SE-08          I .37E-0O                      I ?O2F-OR                  2. 9b-09
                                                              0.0
34SE    79    0.0          2. 6I-06          M.dOE-07                      41, 5 6F. -n6 0,0          5, 38F-07
35RP    A?    n.0          0.0              2.?PhE-n6                      n00          0.00        2.54F-Ob
355P      93  0,0          0.0              4 . 2E-ný,                    0.0                          .,79F-OR
35.P      84  0.0          0.0              5.22E-O0                      0.0          n,0,00      u0nqF-13
                            0.0                                                            0.0
                                                                                            0,0
35BR    85    0.0                            2.1 4E-O9                      0.0                        0.0
37RB    0b    0.0          ?.11 F-05        9.8UE-0b      0.0            0.0          0.0
                                                                                            0.0          4, 1bE-Oh
37BR      87  0.0          I .?3E-OS        4.28E-4b                                    0.0          5. 7(E-07
37RB      48  0.0          6.06F-()8        3 . 21 E-04    0,0            0.0          n00
                                                                                            0.0          8.3bF-19
37RR      89  n.0          U.0 1IE-O8        2.93E-0.      0.n                          0.0          0.0
38SR      B9  3.09F-0'J    0.0              5.89F-06      0.0                                        MI,*4E-05
3BSR    QO    7.61F-03    0.0              I .86E-03      0.0            0.0          0.0          I.02E-nu
3RSR    91    5.82F-Ob    0.0              P.ShE-07      0.0            0.0                        2.Q3E-05
                                                              0,0                          0.0          4 , 2bf -05
38SR      92  2.IbE-Ob    0.0              9.31E-08      0.0
39Y      go    9.63F-09    0.0              2.5RE-10      0.0                                        1.02E-04
39Y      91M  9.10E-11    0.0              3.53E-I?      0.0            0.0          0.0)        2,b7L-1 0
39Y      91    1.alE-07    0.0              3,7RE-09                      0.0          0.0          77bE7-05 Note;    0.0 means insufficient data or that the dose factor is <].OE-20.
 
1.109-21
 
TABLE A-3 (Continued)
  NUCLIDE        BONE  LIVER          TOTAL BODv  TH)ROID    KIDN EY                  Gl-I.Ll
                        0.0          2.07E-1I    0.0      0.P
39Y    92  8.46F-10                                                    n.0
                                                    n.,      0.0          0,0      9
* SO F -6C'5
39Y    93  2.6E-09    0.0          7.40E-11
        93  4 . IqF-08 2.3uE-Oq      1.09E-09    0.0      8.99E-O9              2.U3f -Oh
4OZR
                        9.76E-09      6.61E-09      n.0      I .SUF-08  0.0
  0OZR  95  3.0UE-OR                                                      ,00    I O5E -na a0ZR    97  I.68F'-09  3.39F-10      1.56E-10    0.0      5 1 P.E - 10 0.0
                        S. 33E-09    2.05E-09    o0n      5,58E-09    (0,0      3,RU*-no
  14tN  q33  2.55E-08 n.n      3. U5 E-0q
41.JN    5  b,2sF-09  3.46RE-09    1.36E-nq                                      2.1 OE -05 L.e2E-12    0.0        I .5AE-1 I  0.0
QLNB    q7  5.23E-1 I  1.32E-1 I
                                                    010                    0.0
u2mO    q3  0.0        7.52E-nb    2.03E-07                                      I .b??F -n, U,31E-0b                  A.('                  0.0I
4240    9q  0.0                      8.20E-07
43TC    994 2.47F-10  6.98E-I0      9.9nE-Aq    n.0        I O0hF-AR  1 ,S2E-10    ,153F-n7 q9  I 2bE-07    1 .8hF-07    5.OUE-08    o.n      2,34E-nb              b.08F -('6
43TC                                                                      I .9SE-OP t.SiF-05
                                      3.60E-19    n.0      ().bOE-09                    7F-OR
43TC 101    2.54F- 10  3.67E-1 0                                                  U*
                        0.0          7.qgE-0R    0.0      7.07E-n7
44RIJ 103    1 .85E-07                                                                  1bF-05
40RU 105    I.S4E-08  0.0          6.ORE-Oq    0.0      1 .'9E-07    0.0
              2.75E-O0  0.0          3.48E-07    0,0      5.32E-0b                    7 6 -('74
                                                                                          7E
LILRU 106                                                                  *.0
        105  1.22E-07  8.86E-08      S.SIE-OR    0.0      3.76F-07
45RH                                                        1 .. 32E-06
46PD  107  0.0        1 .47E-07    9.UIE-Oq    0.0
                                      U.OOE-08    0.0      I .02E-O1
  6bPD 109  0.0        I .77E-07
        1104  1.6bOE'-07  2!.'JRE-07  4.80E-04    0.0      2. 91E-n7              b.  0Laf-it,
47AG                                                                        (1.0
                                      1.21E-0B    n.0      7.8SF-nA
L7AG  III  5.82E-0R  2.44LE-08
                                                    0.0      3.50F-nb    0.0
48CO  1134  0.0        3. 1qF-Db    1.02E-07                                      2.2bF-n5
              0.0        I .84E-0b    5.AgE-OR    0.0      I4.6F-06              7 . 7 a"E- r*S
48Co  1154                                                              0.0      1,07Et-O5
50SN  123  3.1 IF-05  5.16E-07      7,6OE-07    L.38F-07              0.0      b. 33E-05
                                                7            0.0          0,0
50SN  125  8. 3bE-06  1 .6AF-n7    3.79E-0      1.39E-07
                                      2.JIE-06    4,92E-07  0.0          0.0
50SN  126  8. U6E-05  1.68E-Ob                                                  2.'3E-0S
                                                    6.79E-09  0.0          2.1 8E-Ob SISB  124  2.81E-06  5.30E-00      I.IIE-0.b                                    7.95F-O5
                        2.4nF-08      4.J8E-07    1.9BF-09  0.0          2.33F-04 S1SB  125  2.23F-Ob                                                              I .97F-O0
              1. 15F-Oh  2,3'E-n8      U.ISE-07    7.0SE-09  0.0          7,05E-n7 SISH  12b                                                                          9.40F-05
                                      9,q2E-0M    3,IIE-09  0.0          I .53E-n7 SISB  127  2.5E-07    5.bhE-09                                                    S QO2E-nh- I . 09E-05  0.0
'52TE  1254  2.b8E-Ob  9.73E-07      3.59E-07    8.07E-07                        1,07E-05
                                                    1.73E-06  2.75E-05    0,0      ?.27f -15
52TE  127M  6.78E-06  2.37F-Ob      9.26E-07
                                      2.3AE-OR    8.16E-0B  LAI*,LRE-07  0.0}      8. b8F -Ph
52TE  127  I 1 IOE-07 3,95E-08                                          0.0
527E  12qM  1015E-05  4L,30E-06    1.82E-06    3.qSF-06  Li,.!lE-n5
                                                              1.3?E-n7    0.0      2. 37Fl-08
52TE  129  3. ISE-08  1. 19E-0FB  7.66E-09    2.IE-0B
                                      7.06E-07    1.34E-06  8.5E-06      0.0      9.4 &#xa3;0E-05
.52TE  1314  S1,74E-06 9, 47E-07
                          5.24E-09    b.22E-O9    1.62E-OR  R.b'E-nf
52TE  131  1.97E-08                                                    0.0
                          1.6LAF-0b    1.51E-06    I.BOE-06  1,58E-05              7.*71 F-05
52TE  132  2.53E-05
              4.63F-08  2.80E-08      4.06E-08    3.92E-03  2.57E-07              Li.  I7F -00
52TE  1334                                                              0.0
                        2, 13E.-08    1.3nE-0'    2.,3E-05  2.09E-n7
52TE  134  3.24F-08                                                    0.0
                        2.8lE-Oh      9.22E-0b    7.23E-03  60OSE-(b
531    129  3.27E-Ob                                                    0.0
                                                                          0.0
              7,57E-07  2.2*iE-06    8.R1E-07    2.85E-OIA 3.UIE-Oh              1    .92E-nt,
531    130                                                                0.0
              4, tl6E-06 S. 96E'-06    3.41E-06    1.95F-n3  I. O.E -05            I .57F-I~b
531    131
                        5.43E-07      1.93E-07    7.15E-05    , bhE'-07          1 . n2E-07
531    132  2.03E-07 I
                                            1.109-22
 
TABLE A-3 (Continued)
                BONE        LIVER      TOTAL RODY      THYROID  KIDNEY        LUNG        GI-LLI
  SUCLIDE
531    133    1.43F-06    2.USF-06      7.57E-07      4.77E-04  4. 33E-flb  0.0        2. 18EOb
              1 ObE-07    2.SRE-07      1.03E-n7      3. 74E-05 '.*5    E-907 0.0        2.51F-1 0
531    134 I . I 7E-06    (429E-n7      I .5jE-n0  1. 86E-.nh  0.0        1.31E-06
531    135  4.43F-07
            2.1 3E-09    'J' (IQE -0B  ?. 3nE-os    D.0      2. 4 E .. n  3.83E- 09  1.58E-08
55CS  13U  6.2?F-05      1I USE -04. 1.21E-OU        0.0      &#xa3;4. OE..0n            05 2.%9E-O0
5SCS  135  I q.F-05      I 80E-a5      8.OOE-06      0.(I                    2,OSE-(
                                                                                I .S9F- 06 4.. 21F-07
55CS  13b  b.51F-ob      2.57E-o5      I .85E-05    0.0        I,  3E..n5          06 2.92E-0b I ,23E- OS 2.10E-06
55CS  137  7.98E-05      I. .OE-0O    7. 1SE-05      0.()      3. 71E'.-)5
                                                        0.0      8.02E.-n8    1 .Q2F- 09  4.65E-13
55CS  135  5. 5F-08      I. OoF-o 7    S.. iE-ns
55CS  139  3.&#xa3;4 F-Os    5.08F-08      I .SE-08                4.07E-08    3.70E- 09  0.0
                                                        0.0      6.&#xa3;7E-- I    3.92E- 11  1.72E-07
569A  139  0 . 7 1 F-O0S 5.92E-I I    2,84E-09
                          2.55E-08      I .3E-06      0.0      R.6bE-09      I '46F- 08 &#xa3;*418E-05
5654  1a 0  2.03E-05
                          3.56E-i 1                    0.0      3.3tIF-I      2, 02E- 11 2,22E-17
5bBA  IUI  0.0                          1.59E-09                1.,SFE-II
                                                        0.0        I,.95E-1t    I .2UE- 11 0.0
Sb8A  IUP  P. 13E-08    2. 19E-1 I    I .3UE-09 I .26E-O9    3.30E-10      0.0      0.0          0.0        Q,25E-OS
S7LA    1UO  2.SOF-OQ
            3.19E-10      9.91E-1l      I .62E-1 I    0*.0      0.0          0.0
57LA  I U1
57LA  IL2  1.28E-10      5.82E-11      1 .&#xa3;4S5- 11  0I.0      0.0          0.0        4.25E-07
58CE  IU    q,3 IE-Oq    6, 3&#xa3;4E-09    7 .18E-10      0.0                                2,42E-05
5CE    143  I.%5E-09      I.22E-O0      1.3SE-10      0.0      5.3.E-10      0.0        4,S6E-05 I bSE-OS
58CE  tUQ  u.BQE-07      2,uE-07      2.bE-08        0.()
                                                        0.0        I .21E-07 S9Pq 143    9.21E-09      3 . 70aF.-O0  4,57E-10                2.1 3E-09                4,03E-05 I .25E'-11I                            7. 06E-1 2    0.0        4.33E-18
59PR 10I4    3.02E-1 I                  1.53E-12      0.0
            h.30E-oq                    4.35E-I0                              0.0        3.49E-05
6OND lU7                  7.28E-09                    0.0        I.25E-09
6IPM &#xb6;LI7                                                                      0.0        8.93E-06
61PM I aB7  7.55E-08      7.10 E -09 2.P7E-Oq          0.0        1I13UE-08
                                                        0 .0                    0.0        6. 7E-05
            3.07E-08      7.96E-09      b.OSE-09      0.0        1.2 1IF-O0S
                                        6.OOE-t0      0.0      2.25F-09      0.0        9.34F-05
6IPM  tuB  7, 1BF-09    I . I9E-09
            1 .52E-09    2. 1SE-I 0 S.7qE-1 I        0.0      4.O7-1 0      0.0        *,03E-05
61Pm 151                                                                        0.0
                  7F-I 0
                . l9      1.1 7E-1 0    5.92E-1 I      0.0      2 . 0 9 F -1            3,22E-n5
                          1.1I9E-0B                    0.0        1 . 33E-08  0.0        S *25E-Ob
62SM  151  6.91E-08                    2.BbE-09 b2SM  153  8.5RF-IO      7.16E-1 0    5.23E-1 I                2.3?F-10                2,55E-05 U1,L"JE-OB                  0.0l      2.775E-07    0.0
                                                                                0.0        2.56E-05
63EU  152  I .q5E-O7    7o.7E-08      3.9IE-O0                              0.0
                                                        0.0
                                                        0.0        3.621--07    0.0        5.48E-05
63EU  154  6. 1bE-07                  5.39E-08
                                                        0.0
                                                        0.0      5.,LIE-rib    0.0
                                                                                0.0        9,60E-O0
63EU  155    5.61E-08    1 .22F -n8    7.88E-0Q
                                                        0&deg;0      7.09E-09      0.0        7.26E-05 b3EU  156    I . 37F -08  I .ObE-0      I .71E-ng
            4.70E-08      0.0                          0.0        I.94E-08    0.0        4.33E-05
65TB  IbO                              5.FbE-09
                          13.44E-09                    0.0
                                                        0.0
                                                        0 .0      1.26E-07    0.0        0.0
b740    16bM 2.70E-07                    bAlE-08        0.0
                                                        (0.0
                                                        0.0      0.0          0.0          *.bSE-07
74M~  191  9.9?E-09      3.24E-09      3.46E-10
            40.bE-07                                            0,0          *00        1,56E-05
740 185                    I. 35E-07      1.4?E-08
                                                                  0.0          0.0        2,82E-05
744    187    I .03E-07    8.62E-08      3,02E-08                              0.0
52PH P O      I .53F-02    U.38E-03      5. &#xa3;E-Oa                  1.23E-n2                5,42E-05
8381 210    0.b2E-07      3.19F-Ob      3.97E-08                3. 84E-05                4.75E-05
84PO 210    3.57E-OU      7.57E-o0      8.60E-n5                2.52E-03                6,36E-05
                                                1.109-23
 
TABLE A-3 (Continued)
  NUCL IDE  BONE          LIVER        TOTAL BODY    THYROID    KIDNEY    .LUNC  G[-I.'.'
B8RA      4.q8E-03      7.bbE-Ob                              2.17F-04    0.0
      223                            9.95E-OU      0.0
88RA 224  1.b2E-03      3.90E-Ob                    0.0      1.11 E-oiU  0.0
                                      3.23E-04                                    3.2    E-Ou h.57E-03      7.79E-06      I .31E-01    0.0      2.21F-ou
8BRA 225                                                                    .0
          3.05F-01                    2.21E-01      0.0      1.b3E-04            S.,32E-Ou
88RA 226                5.75E-06                                          0.0
                        3.1?E-06      1.21E-01      0.0      8.84E-0s            5.64E-05 B8RA 228  1.12F-01                                                        0.0
B9AC 225                              2,QsE-07      0.0      6. 90F-6 7          4.07E-04
          4.    -1F-06 6,07F-06                                              ,0.
 
89AC 227  1.88E-03      2. *8E-OU    I I II E-0Q    0.0      R.03E-05            7.q'E-05
                                                                            0.0
          1.37E-05      2.4BE-07                    0.0      tl    IE-Ob        5.JOE-Ou
90TH 227                              3.96E-07                            0.0
90rH 229                              I.b8E-AS      0.0      4.67F-05            5.h3E-Ou
          4.96F-OU      3.41E-06                                              ,0.
 
90TH 229  R.ObE-03      1.21E-O04    3.95E-O0      0.0      5.80E-OU    0.0    5,12E-Oa
90TH 230  2.08E-03      1 I1 BE -O04  5.76E-05                5.b9E-04            6,O2E-OS
                                                      0.0                  0.0
                        I .OIE-04    .4,9?E-05              U.'3bE-ou    n010  I *?'E-On
90TH 232  l.SOE-03                                  0.0                  n100
90TH 23Q  .9.02F-08 4.*72F-09        2.32E-09      0.0      2.b7E-OR    0.0    1.13E-Oa
91PA 231  4.I4F-03      I.56E-0l      I .61E-Ou    0.0      1.0          0.0    b.?T7-Ou
91PA 233  5.26F-09      I .0bE-09    Q,2AE-In      0.0      3.99F-nq            I , 4F -0s
92UL 232  u.l4E-03      0.0          2.95E-04      0.0
                                                              4.47E-04    0.0    b. 72E-0&#xfd;
92U    233 8.7?E-0O      0.0          5.29E-05      0.0      2.0TE-OQ    0.0    b,27E-05
92U    234 8.37F-014 G00              5. 1RE-05      0.0                  0.0    b. 1UE-05 A.86E-05                I 40E -no    0,0    7,BIE-05
92U    235 8.02E-04      0.0                          0.0
                                      4.97E-05                I,75E-0U    0.0    5. 7bE-OS
92U    23b 8.02E-O4      0.0                          0.0      2.27E-07
92U 237    S.53F-08      0.0          I .47E-O0      0.0
                        0.0                          0.0
                                                                                              I
92U 238    7.67F-OU                    4.55E-05                I *7E-04    0.0
                                                                            0,0    t.bbE-O0
                                                      0.0
                                                      0.0                  0,0    7.94E-A5
93NP 237  l.38E-03      1.20E-O0      5.5qE-05                I .26E-n9          7qUE-05
                                                      000
                                                      0.0
93NP 235  1.37E-08      3i,6E-10      2.1 3E- 10              3.S5E-10    0 0
93NP 239                              6.4AE-1 1      0.0                  0.0    2.a0E-05
          1.20E-09      1.18E-1O                              7. 1* E-o0
9'PU 238                  . 31E-05    1 .67E-n5      0.0                  0.0    7.30E-05
          6.7SF-OU                                            ?.9bE-05
94PU 239  7,60F-04      I OMiE-OQ    I .88E-05      0.0                  0,0    h1b6F-05
9UPU 240  7.58E-04      1,04iE-04S    I.88E-05      0.0      7.96E-05    0.0    6.78E-05
9IJPU                    9.4l7E-07    3.33E-07                I .53E-nS    0.0    l.u0E-O0
      2U1 1.5bE-05                                  0.0
guPU                    990E-05      I .79E-05              7.SRE-n5    0.0
                                                                            0.0    6.5  SE-os
      242 7.22E-04                                  0.0                          q.,5SE-05
                                                                                  9,75SE-OS
9JPU 2L4L  9.60E-0O4    I I1BE-O4    2.13E-05      0.0      9.03E-05    0.0
95AM 241  8.IOE-04      2.79E-04i    5.26E-05      0.0      3.QbE-OU            7.02F-05
95AM 2Q2M  8.32E-0O      2.78F-00      5,47E-05      0.0        .. O8E-n4        9. 34E-09
95AM 2i3  8.12E-0O      2.7 3E-O0i    5.24E-05      0.0      3.95E-0O    0.0
                                                                            11.0  9. 73E-Oi
96CM 2U2  1.58E-05      I .64E-&#xfd;05    I.OUE-Ob      0.0      4o.7E-0b    0.0    7.92E-05
96CM 243  b.43E-0O      2.QIE-0OJ    3.77E-05      0.0      SI *7bE-0O  0,0    7.8IE-09
                                                              1. 3LE-04    0.0)  7.55E-05
96CM 244  4.851-04      2.07E-04      2.BRE-05      0.0                  0.0    7.0F-05
96CM 24S.  1.03F-03      2.B8E-O0      5.BIE-05      0.0      2.71E-04    0.0
                                                                            0.0
96CM 2U6  1.02F-03      2. 88E-04    5,BOE-05      0.0      2.7,1E-n4          6,9I1L-05
96CM 247  9.95E-04      2. B3E-O0    5.72E-05      0.0      2.67E-O0    0.0    q. 09E-05
9bCM 2'8  8.27E-03      2. 33E-03    4.71E-O4                2.20E-03            1.87E-O.3
98CF 252  1.96E-O4      0.0          4.95E-06                0.0                2.88E-04
                                              1.109-24
                                                                                              4
 
TABLE A-4 TEENAGER INGESTION DOSE FACTORS
                                          (mrenm/pCi ingested)
    NUCLIDE      BONE      LIVER      TOTAL  B:oY    TqYq!10    OC
                                                                    I -)NF Y          GI-LLI
    IH      3 0.0          I ObE-07      I.06F-A7      1.n0E-07            I .06F-07  1.0h-07
    6C    1'J  7.55E-07    7 .55E-07    7.SSF-07    7 . SSE-07          7.55F-n7  7.55F-07 IINA    22  2.36E-09    2. 35E-35    2. 3SE-05    2.35F-05            2. 35F-05 2.88-*-h
27C0    513    ,00      9.92F-67                    nO                  0.0        I .3JF -05
                                          2.26E-Ob
27C0    bO  0.0          2. 76F-nb    6. 30E-Ob                                      . 31E-05
38SR    B9                0.0          I . 3E-15    n o
                                                        0.0          (USE    n0        4.49F-n5
                                                                            0.0
38SR    9o  1 .OE-02    0.0          2.57E-03      0.0                            2.4?eo-O0
39Y      qo  3. 3OF-08                  A.87F-ln0    0~o
                                                                            3.75E-nS  1.O9F-O0
                                                                    ADULT
39Y      91  1 .9hE-07    0.0          5.?P3E-n9                          0.0      7.53E-05 unZR    95  3.72E-08    I .2'JE-08    8.6hE-nQ                          0.0      2.68E-05
41,NB    95  7.2JE-09      *.36E-0q    ?.u7E-OQ      0,0
 
===0. n                  T===
                                                                            0.0        I. 78E-05 DOSE'  0.0
44RU 103      2,37F-07    0.0          1 OhE-07                                    1 .6SEF-0s OULRU job    U OOE-Ob    0.0          5.03E-07                          0.0      I. IE-o0
505N  123    U . 3AF -05  7,22E-o7      1 .0E-Ob      5.37E-07    FACTOR) 0&deg;0      6. 31F-05 SPTE  1254  3.93E-06    I . 37E -0h  5.0AE-07      I5,13E-07            0.0      I ,07F-05
              1.51E-07    5.3?E-OM      3.23F-08      I .03E0O7                      I .22E-0O
52TE  127                                                                  0.0
52TE  129M  I bhF-05    5.15F-Ob      2.61E-nb      5,30E-06                      5.R0E-05
52 T E 13?    3.55F-O0    2,22E-Ob      2.1 nE-n6    235SE-6 5                      8,00E-05
531    129    L.bbF-O6    3.92F-O0      1 .31F-05                                    4.31E-07
531    131    5.57E-0h    7.87E-06      U.6qE-nh      2.27E-03            0.0      1.49E-06
531    13    2. 03E-Ob    3."UE-Oh      I OhE-Ob      b.?5F-0U            0.0      2,50E-06
95cS  134    8.05E-05    1 .9QE-01    9. OhE-05    0.0                  2.35E-05  2.24E-Oh
55CS  137    1 .07F-O0    I lUUE-0LJ    5.05E-05                          1.91F-05  1.q2F-06
                                                        0.0
5b0A  1U n  2.83E-05    3.u4E-os      I.fPE-06                          ?.33E-09  4.tUE-Oh
57LA  140.  3.43
                  *8F  -09  I .72E-09    4.59E-10                           0.0      Q.8F.-0O
5.1CE  I1i0  1 .2bE-08                                                    n.O      2.29L-05
5RCE  I1aQ  7.22E-07    ?.9bE-07      3,83E-O8                          0.0      1.70E-04 o.6 b3EU) 154    1 I5E-Ob    I .OnE-n7    R.7qE-ng      0).0                0.0      5.12E-05
92U    232    60.bE-03    0.0          n,2tE-0                            0.0      6.72E-05
92U    234    1,22F-0,3    0 0          7.UnE-05      0,0                  0.0      6,14E-05 gaPU  238    5,&#xa3;0E-0a    I I*1 E-O0    2.ORE-05      0.0                  0.0      7.30E-05
9UP I  23-    9.2bE-04    I . 29E -n4  2.2QE-05                            o.0    6bE6F-05 QUPU                                                  0.0                            b.bbE-05
        240    9,25F-04    I . 30F-oil  2.31E-05                          0.0
9'PU  2a!    u.03E-07    1.852E-o      1.02E-00      0.0                  0.0      1.28f.-07
95AM  241    9,q3E-04    (.1 7E-nU    6.66E-05                          0.0      7.17E-05
9bCM  ?42    2.26E-05    2,33E-05      I .50E-06    0.0                  0.0      7.80E-05
96CM  24U    b
* hL F-0 L 3. 33E-0O    U.n3E-05                          0.0      7.42E-05 Note:  0.0 means insufficient data or that the dose factor is <1.OE-20.
 
1.109-25
 
TABLE A-5 CHILD INGESTION DOSE FACTORS
                                        (mrem/pCi ingested)
    NUCLIOE    BONE      LIVER      TOTAL B.11Y    TH~YRODI  K I)NEY    LUNr        G;I - LL I
  IH      3  0.0        2.03E-07      2,03E-07      2.03E-07            P . 0 3E - 07 2.0 3E-07
  6C          2.26E-06    2.26F-06    2.26E-06      2.26E-06 I INA  22    5. 89E-05                S.8QE-05      5.R~9E-05S                PQE-06S
                          5,89F-05                                                      2. S7k-Ob
27C0    58    0.0        I .8SE-nb    5.58E-flb                          0.0
27CO    bO    0.0        5.17E-06      1 .55E-05 0.0                                  JS.iSF-OS
38SR    89    1.*38F-03  0.0                                      (USE
                                        3.95E-05      0.0                                &#x17d;.2.8b -051 qO    1.*72E-02  0.0          41.36E-0 3 o.0                    0.0
39Y    90    4,1. E-08  0.0          I
* I3E-oq                ADULT  0.0
39Y,    91    5.65E-07    o,0          I .56E08)                          0.11          7. 77E-05
        95    1 .04F-07  2,012E-08    2.?OE-OA      0.0                  ,).0          2.50F-05 (J1NB  95    1 .95E-08 8.32E-09 6. IIE-09 0.0                    DOSE    0.0          1 .J44E -05
44 RU 103    6,78E.-07  0.0          2.71jE-07    0.0                  0.0l          I
* ThF -n03
44LRU lob    I*1.19E-05  0.0          I USJE-06    0.0                  0.0          I . k5F-va SO SN 123    1 .31E-0(1  1 .641E-06  3.22E-0b      I .73E-06 S2TE 1 25H    t I 1'JF-05                            3.20E-06    FACTOR) 0.0          1 , I OF -OS.
 
3.09E-flb    I .S2E-0b
52TE 127      4A.50F-07  t .20E-07    9.65E-06      3. 1 OE-07          (.0          1 .'0?f-fl
                          1 .38E-05                  1.58E-O5                          S5.96EF-05
52TE 129M
              41.95SO5                7.65E-06                          0.0
        132    I.02F-O5    UI.5OE -06 5.'I2E-Ob      b.62E -05b          0.0          7 .89F-O5
531
531
        129
        131
        133
55c S 137
              1 739-E -05
              1 .63E-05
              5,98E-06
                          8.S(1F-06
                          1 .67E-DS
                          7.38E-06
              2,24JE-041 3.77E-fl'
                                        3.81EF-05 I 426E-05
                                                      2.79E-02
                                                      5,USE-03
                                        2,90E-06~ 1 .7F-0_
                                        8. 02E-05    0.0
                                                                          0.0
                                                                          0n0
                                                                          u.19F-05 LI *  9L .f7
                                                                                        1 .43E-06
                                                                                        ?.Q9E-oh
                                                                                          2.04FI-0(,
                                                                                                        4 SscS          3. 12E-04  3.02E-04I 41.50F-05                            3.54E-05      1.8ar-06
56BA 110      8.26E-05    7.2SE-n8    &#xa3;1.SSE-0b    0.0                  u.32E-08      0.*21 E-0b
57LA 1 a1    I .01E-08  3.52E-09 1 . IQE-09                            0.0          1.noQE-011
58CE Ia 1    3.76E-OR    I BR8E-08 2.80E-09 0.00                        1.0          2.36E-05 SOCE          2,14'E-06  6. 70E-017    I.14(E -07                        0.0          I .711F-0'J
b3EU 154      2.58E-0b    2.08F-07    2.03E-07 0.0h 0.0                  0.0          ai. /Ok -05
                          0.0                        0.0
92U    232    1 .77E-02                1 .26E-03                        0.0          b.91L-OS
9?U 234      3,57E-03 0.0            2.2 1 E-04J                        0.0          6. 3eF-0'3
911PU 238    I .21F-03  1 .52E-04I 3.09E-OS        0.0                  0.0          7 . 50EF -V5
94iPU 239    1 .32E-03 1 .62E-04i 3.27E-05                              0.0          6
* PSE -0
                                                      0.0
94PU 2a0      1.32F-03    I .63E-noL 13flnE-05 Im 0.0                    0.0          6 1SL -05
                                                      0.00
94 U 2at      7. 12E-07                1 .81E-08    0.0                  0.0          I .32F -0 7
95AM 201                                            0.0
              1.4&#xa3;2E-03  b.211E-n4    9,9&E-05      n, n
                                                      0.0                  0.0          7 . 37 F - f'5
96CM 242      6,74E-05    5.28E-nS    '1.41hE-06    n,                                8.03E-05
96CM ?' 11    1. 12E-03  5.L f -0 1 6.99E-95                            0.0          7 . bUjE -OS
Note:  0.0 means insufficient data or that the dose factor is <I.OE-20.O
                                              1.109-26 I
 
TABLE A-6 INFANT INGESTION DOSE FACTORS
                                              (mrem/pCi ingested)
    NIJCLTr)E      qti'*E    LIVER        TflTAL ~VlDy        T H4Y 4 110 K 1 3N F Y    LONG      GJ-LLI
            .3    0.0        3.0 7F-o7      3. 07E-07        3. 07E-07              3. 07F-07    3.07E-07 bC      14    U.81F-Ob    4.*81 F-ob      U.BI E-06        a0,4B I-n0b                6 1 E-Ob A 22      1.OnF-OLI  I *00E-nd      I OO0E-04        I.o0F -04                  OO.0F-04~ 2
* 45E-Oh aJ Sa    0.0        3.78E-06      9.26E-06          0.0                    0 .09.79E-                b5
  27C'0 60n      0.0        1 .07 E- 05    2.56E-05          0.0                    n0.0        2bF          5
  38S1 R C        2,q3F-03    0.0            A.U2E-05          0.0            (USE    0.0          5."l8E-05u R 90      2.91F-02    0.0            6.U0E-03          6.0                    0.0          2      F-04
  385
            40    BQIE-08    0.0            2.41E-!&#xfd;9        0.n          ADUL.T      .01.29              0
  39y QI    I.2S9F -0h  0.0            3.33E-OR            .0                  (.0
                                                                                      0            8.27E-05 R. 5      ? .IIF -07  5.32E-nR      3.78E-08          n.n                    0 .0          ?.38E-05 Q P95    I.g9E-nR    I.75E-1)8      1.03E - 1        0.0          DOSF      0.0          1.LJE-Oc5
  4 1P(
        J 103    1.OilE-0    0 ,0          U.BSE-07          n .0                    1.0        1.7F0
        J 1.06    2.5"&E-05  0.0            3.12E-16          0,0                    0.0          19E0 5
50S~N 123        2.7'9E-0Li  Q.33F-oh      h.96E-lb          4.33E-(16    FACTOR)  0.0          b.41E-055
52TI E1254      2.'J3F-0'S  5.19E-nb      3,20E-flh        R.OnE-OS              0.0          1.17E-05
52TE 127        9.58F-07    3. 1 9F-n7    2. 06E-n7        7.75E-0 7              .. 0          2.?27E-05
52TE I?9M        1.05F-04    3.61F-05      1 .60E-05        3.q9E-05              0.0          6. 33E-05
521E 132        2.t3F-05    I n05E-05      0* 76E-Oh        I *99E-'n5            n,0          A, 08F.---05
531      129    2.95F-09    2. IbE-OS      7 .76E-05        h.*79 F-02            0.0          4.46JE-07
531      131    3.U2E-OS    401 0F-05      2.3RE-05          I .31E-62              0.0          1 .53E-06
                                                                                      ,0o0
531      133    1,2bF-05    1 BUE -05      S.'BE-06'        u.*35E-0 S                          3.*27E - 06
55CS 130        U.SAE-04    9~.2 4E-0 4    6.97E-05          0.0                    9.42E-05
55CS 13          6.53F-O0    7 . 31 -4      0. *20E-05        0).0                  R.81E-05
56BA 1'&0      1,74E-00      '75-n7
                                1            8 qqF-0b          0.0*                    I .07E-07
57LA 100        2.12E-08    5. 17E-ng      2
* I E-fO)      0.0*
                                                              0 5
                                                                                      0.0          I. OuF-04
                                            5.75E-IQ                                0.0
S8'E 141I        S.OOE-08    4:91F.08                        0.0                                  2. 39E-05
58CE    lU4    0.49E-0b    1 .7 7E -0 h  2.0?E-n7                                O.0          I.85E-04 O .RUE-n7                        0l,0                                4.*7bE -05
63EU 154        4.30F-06                  3.29E-07                                0.0
92U      232    3.66F-02    0.0            2.68E-03                                0.0          7.*34E -05
920J    234    7.u00F-n3  0.0            4.71EC-04        0.0                    0.0          6. 72F-05 qAPO P38      1.71F-03    2.1 BE-a04    0  .25E-q5                              0.0          7.98E -05
9'IPU ?39        1.70E-03    2. 2bF-q0      0
* I  E-1)5    0.0                    0l.0          7.*29F -09 qqpU ?'40        1.78E-03    22 8F?E- fl    0 .45E-05        0.0                    0).0          7.28E-05
  94PU P.01      11OhE-0b    I .37F-D7      2.70E-OP          0.0                    0.0          I .40OF-07
  95AM 241        1.93F-03                                                            n0.0
                              I .01F-n3      1 . IIE-nu      0.0                    0.0          7.8'4E-O5
96CM 2U2        1.43E-nu    I UOOE-04                        0.0                                  13.b,3r-05
                                            9 .Q9F-nb                                (0.0
96CM    244    1.bdE-03        7E -00                      0.0                                  8. 12E-05
                              1.6            1 .04E-04 Note:    0.0 means insufficient data or that the dose factor is <1.OE-20.
 
1.109-27
 
TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND*
                                              tmrem/hr per ptl/'.)
                  TOTAL BODY        SKIN                                          TOTAL BODY        sKirt iH      3    0'.0          0,n                            UOZR      93    6.0            3.0
      4BE    10    0.0            0.0                              4OZR    95    5.00F-09        s . G010
      bC                          0 0                            4OZR      97
                                                                                    5. SOE -()q
      74            7 60kE-0q      5.80E-09                          41N8    93*4      o0.
 
9F      18    b.    0FO-09  8. OOE-09                                95    5. 1OF -A9      5. O0)E -A9
              22      I ,66E-08    I. OE-08                                  97    4A*bOE-0q      i,4nE-Oq I TMA-
    11  NA          2.50E-0B      2.90E-08                                        2.29E-I I
    1P        32    0,0)          0.0                              42MO    99      1 .qUF-0O          *20F-09
    20CA      U1      . nO -O
                    03.'JlE-09 U.01E-n9                        LJ3TC    9q4    Q.*,,E-10        I* OE-OQ
    21 SC Ub          I*30F-08    1 .50E- -B                      43TC      04    0.0
    214CR                          2.b0E-1 0                      'i3TC            2.7WF-0O        I.OOF-Oq
              51
                                                                    44RU 101
                      2.20E-I0
    .25MN 50        9.60E-09
                      1 *BOE-ORq                                            103      S.bOE-OO      4 .20F-o9
                                                                            105      4.5UF-Oq
    25MN    5b                    I IOE.-08                                                        5. 101-O
                    0.0                                              LARU          I .50F-09      I    jAnF-0q
    26FE      55                    0.0                            U &#xa3;4P D
                                                                    LA9RH
    2bFE      59                  9,4OE-O9                                105      b.6OE-10        7.7nE-10
    27C0      57    9. OE-t0        I.OOE-OQ                                        0.0                S.0
    27C0      58    7.OOE-09      R.20E-0Q                          46PD  109      3.50E-I I      14.001-I11
    27CO      6n      1, 70F-08    2. 00E-O0                        47AG            I ,80F-08      '.  tOE-08 I
              5q                                                    47AG    1 nb I I~  I .80E-10      2. tOE-Io
    28NI                          0.0
    28NI      63                  0.0                                              2.3nF-12        2.60F-12
                      3. 70E-09                                    4A C r)
    28NI      65                    1 .70E-09                              111      0,0            0.0
    29CU      ba      I .50E-09                                                      0.0            b,* bE-qR
                                    I,70E-Oq                                123
    30ZN b5        UQ,00F-09                                              i07
                                                                            125      5. 7OF-t0      b.bOE-10
    3nzN 694                                                                                        I DO0E-nm
                    2.90E-09      3.0OE-09                                t 246    Q.DOF-09
    3'JZN 69        0.0            0.0                              5""s             1.30E-08      1 .50F-09
    34SE      79    0.0            0.0                              52TE
                                                                    5128    125      3. IOE-09      3.50E-09
    35BR      82      I
                      6 .90E-AA
                        . 9O0E - I 2.20F-ro8                        52TE I?b
                                                                    515R                *
                                                                                        .9OF  -') 9 I .OOE-O8 b.UOE-t 1                                                        5. 7OF-09      b.hOF-*9
              83                  9. 30E- II                              127
    358R                              .40E-08                                                        U*.AOE-1 I
                      I .20F-08                                    52TE            3.50F-12        1. 0E- II
    35BR      85    0.0            0.0                              51TE
                                                                    52TE    12741
    37RB          6.30E-1O        7.20F-10                        52TE    127      I OOF-I I      I .IOF-1 I
    37RB                                                                                            P *OOE-It0
              87                  0.0                              5?TE    122'4    7.70F-10        g.uOE-I0
    37RB 88        3.50E-09        4.OOE-09                        52TE    129
                                                                            12b      7. IOE-10
    37R8      5Aq  I .50E-08      1.80E-08                        52TE    t31M      S.,U OF -09  4.90E-09
    38SR      59    5.60F-1 3      b.5OE-13                        52TE    131      2,20F-09        2,b0E-Ob
    -38SR 90        0.0            0.0                              521E
                                                                    52TE    13 2      I . 70F-0Q    2.00F-09
    38SR            7.o I OE-Oq      . 3 0E-09                                        1.50E-08      I .70F-OA
    3ASR                                                                    I 3M
              92    9.OOE-09      I .OOE-08                                          I .OOF-09      1.20E-09
    34Y      90    2.20E-12      2,60E-12                        531    129      4 .SOE-1 0      7,50F-I 0
    39Y      914  3.80E-0q      4.40 E-09                                130      I *U0E-08      1 .70E1-ri
              91                                                                                      1 7 0E - n9
                                                                                                    5.40FO-DQ
    39Y            2. 4 OF- II    2.70E-i I                        531    131      2.80F-09
    39Y      q2    I .6bOF-09    17.90F-n                        531    13 2    I .7nE-0O      2. O0E -08
    39Y      93    5.70E-I0      7 .80E-1 0                              133      3.7UE-09        U.5AE-09
*The same factors apply for adult, teen, child.
 
Note:    0.0 means insufficient data or that the dose factor is <l.OE-20.
 
1.109-28 E
 
TABLE A-7 (Continued)
            TOTAL BODY        SKIN                                TOTAL BODY        SKIN
53!    13u    I.bOF-0      l.90t-o0i                    8RRA    2?3  1.50F-09    I.ROF-09
531    13      1 .20EE-08  1uOE-O8                      8SRA    22u  3.9nE-0q    1.OOE-08
                                                          88PA  P25  ;. 11F - I t I. 2()F -1A
55CS  134'1  b.P0E-10    7.Y0E-10
55CS  134    1 .2F-08    IQOE-0p                      88AA    22b  b.41JF-oq    7.40E-O0
55CS  135    0.0          D.0                            R.RA  228  I,?f'F-0    t.4OF-n8
                                                                                    1
55CS  t36    1.5OF-'4    '.70E-08                    89AC    P2?  IrNF-OQ      1.80E-oQ
55CS 137      4 .2OF      QJ90E-0Q
                            -.                          9A9C    227  2.OOE-09      2.40F-59
55CS 13A      2,tOE-05    2.uOE-OR                    90TH    227  5.10F-10      b.30F-t0
55CS t39      b.30E-ng    7.20F- nq                    90TH    22?  ,.QOF-0Q      t.00E-0A
5b65  139    2.uOE-0Q    2.70E-0Q                      90TH    229  2.20F-0 0    2.70E-09
5hBA 140      2.lOE-0q    2,unE-09                    90TH    230  h.S0E-nq      7.SOE-nq
56BA 1UI      U.IOF-o9    qt90F-0Q                      Q0TH    ?32  S.OOF-OQ    U.nOE-Oq
5b6A 1u2      7.9*E-09    9.00E-DO                      qOTH    23u  1.1OE-10    1.30F-10
57LA lU0      1.50E-0R    1.70E-08                      91PA  231  2.20F-0Q      &#xfd;.70E-09
57LA 141      2.5vE-10    2.5nE-t0                      qtPA  233  1.30F-09      1.50F-99
57LA IQ2      1.50E-OR    t.ROE-05                    92U    P32  2.5qF-12      2.b9E-11
58CE ]at      5.50E-10    b.20E-t0                      92U    233  2.30E-09      2.rtOF-o9
58CE 143      2.20E-0q    2.50E-0Q                      92U    234  b.32F-13      1,59E-10
58CE    Uaa    3.20F-10    3.70F- 10                    q2U    235  i.20F-Oq      4.OOF-ng
59PR 143      0.0        0.0                          92L    P3b  2. IF-I      I .80E-11
59PR IOU      2.OOF-10    '.3nF-10                      92U    237  t.00F-09      1.30E-0q bOND 147      1.00E-0q    1.20E-09                      92U    238  1.10F-10      1.50E-10
blPM    I7    0.0        0.0                          13NP  2;7  1.40F-09      1.bOE-Pq tIPM    4RM4  1.UtF-.F0  5 6.-01-                      93NP  238  2.8nF-09      3.20E-oq bIP4 10B      u*hOF-09    5.3f5--*9                    93NP  23q  9.50F-10      1.10E-0q bIPM 14Q      2.50E-11    2.QoE-il                      Q9PUJ  238  1.30E-12      1.80F-11 biPH  151    2.2'F-OQ    2.30E-o9                      9LPU    P39  7.90F-13      7.70E-12
                                                        94PU    240  1.30F-12    t.80E-11 b25    151    u.80E-11    2.10F-10
b2SM    53    2.70F-In    3.0OE-10                      9LPU  241  4.h0E-12      b.80E-12
13EU  152    7.37E-09    3.53E-0O                      QUPU  242  1.10F-12      1.60F-11
63EU  15u    7.BUE-09    4.00F-19                      9qPki  2441  8.95E-10      1.62E-10
b3EU  195    I.RIE-10    U.33E-10                      9SAM  241  1.801E-10    2.60F-10
b3EU  156    7.80F-09    3.70E-Mg                    95AM.4??4    2.h6F-11      1.80E-1l
65TB  160    A.6(0E-A9    1.00E-0A                    95AM  24.3  1.30E-09      1.50E-09
67H40  I664    5.90F-00    1.OOE-nS                    96CM  2U2  5.50E-12      2.30E-11
7UA    181    2*10F-12    2,ROE-12                    96CM  243  2.30F-Oq      2.90E-0Q
7Ui    185    n 0      .0  a                            96CM  2ila  2.qnE-12      1.8OE-11
74"    187    3.1'E-AQ    3.bOE-09                    96CM  245  9,50E-10      1,20E-09
82PH  210    1.30E-11    1.70E-11                    96CM  246  1.00E-12      1S50E-11
  381B 213    0.0          0.0                          96CH  ?P7  2,20E-0Q      2.bOE-09 RaPO  210    5,10E-'1    b.2OE-tu                      9bCM  2a8  6.8IE-0q      5.23E-09
                                                        98CF  252  b6b0F-0R      7.20E-08
                                          1.109-29
 
called bioaccumulation factors in this guide, can be found in the literature (Pnf. 19). The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose for consumption of aquatic foods.
 
Rap    = 1100 Uap      Q.B. D *exp(-Aitp                                      (A-3)
                                  i    aipj
                                        ,          p Values of Bip are given in Table A-8; the other parameters have been previously defined.
 
The transit time tp may be set equal to 24 hours to allow for radionuclide decay during transit through the food chain, as well as during food preparation.
 
c.  Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with suspended and deposited materials. One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21). Based on these references, an estimate of the radio- nuclide concentration in shoreline sediments can be obtained from the following expressions:
          C.s    Kc Ciw[l
                      1w  - exp(-.it)]
                              i                                                          (A-4)
                  isc where Cis      is the concentration of nuclide i in sediment, in pCi/kg;
              CiW      is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter;
              Kc      is an assumed transfer constant from water to sediment,  in liters/kg per day;
                t      is the length of time the sediment is exposed to the contaminated water, nominally 15 years (approximate midpoint of facility operating life), in hours; and Ai      is the decay constant* of nuclide i, in hours-l. In the original evaluation of the equation, Xi was chosen to be the radiological decay constant, but the true value should include an "environmental" removal constant.
 
The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period of several years in the Columbia River between Richiand, Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 22 and 23). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters nn*wmeter above the sediment, an effective surface contamina- tion was estimated. This surface contamination was assumed to be contained within the top 2.5 cm (I in.) of sediment.** The dose contribution from the radionuclides at depths below 2.5 cri was ignored. The resulting equation is Si      1 iCi WDl MOT        -  exp(-Ait)]                                              (A-5)
where Si      is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations;
  If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).
  With a mass of 40 kg/m 2 of surface.
 
1.109-30
 
TABLE A-8 BIOACCUMULATION FACTORS
                            CpCilkg per pCi/liter)
            FRESHNATER                              SALTMA17ER
ELEMENT FISH    INVERTF3RATE      PLANT          PIS'    TIVERTE3RATE        PLANT
H        9,0E-Ol    q.oE-01        9.OE-01      9.OE-ni        4.3E-01    9.3E-01 HE      1.0E 00      1.0f 00        10Elf      1.0ffO0        1.fOE 00  t.OE no LI      5,0E-Ol      C.oE: 01      3.0E 00      5.OE-01        50fE-Ol    3.0E 00
BE      2.OE 00      InE 01        2.0E 01    ',OE    02      e.OE 02    1.OE 03 B        2.2E-01    5.OE 01        2.2E 00      2.2E-Ot        QO.E-01    2.2E oA
C      U.    03
              0E    Q        03    4.bF 03    t.5F Os        1.14E 03  1.8E 03 N        1.5ES 05    1.;E 05        1.3f3E 04  h. E 04        1T7E "04  1 .0f p0
0      9.2E-O      9.?fE-01      9.2E-0l      9.bF-01        9.bE-01    Q.bE-O0
F        1.0E 01      1 .oE 02      2.0E 00      3.bF 00        3.6f on    1 .4E 00
NE      I.OE O0      I.nE 00      1.r E 00    1.0E 00        1.0OE 00  1.OF 00
NA      I.OE 02    2.oE. 02      5.OE 02      b.7E-02        1.QE-01    9.SE-O1 MG      5.OE 01      1.oE 02        1.0OE 02    7.7Ff-01        7.7fE -01  7.7E -0 1 AL      ioE0f 01    6.;E 01        U.2E 02      1.0OF n1        b.OE O0    6.OE 02 SI      2.5E 00      2.';E 01      1.3E    02  1.0f    01      3.3E    01 6.7P  01 F      1.0oE 05    2.oE. OU      5.0E 0';    2.fE n4        3.0E O4    3.0E 03 T      7.5E 02      I.oE. 02      1.0E 02      1.7E 00        4,UE-01    U.4E-01 CL      5.0E 01        .ofE 02    5.OE 01      1.3E-02        I.QE-02    7.6E-02 AR      I.OE 00    1.nE 00        1,OE 00      1.0ffno        I.OE 00    1.OE 00
K        I.OE 03    8.lE 02        6.7E 02      1.IE 01          .6fE 00  2.6E 01 CA      4,OE 01      3,3E 02        1.3E 02      5.0E-Ol        1.3E 01    5.OE 00
SC      2.0f 00      1.fE' 03      t0OE 0Oi    2.0fE 00        1.fOE 0 Q  I.0 E 05 TI      t.OE 03      3.OE. 03      5.OE 02      1.OE o3        1.OE 03    2.0E 03 V      1.OE 01      3.E 03        1.0E 02      1.0E Ol        5.OE O    i.OE 02 CR      2.0E 02      2.nE 03 .      ",OE 03      4.0E 02        2.0E 03    2.0E 03 m,,40OE        02    9.oE 04        1.0fE 04    5.5E 02 *        4.OE 02  5.5E 03 FE      10OE 02    3.pE 03        1.0E 03      3.0E 03        2.OE O4    7.3E 02 c0      5fOE 01      2.nE 02        2,0E 02        .0OE 02      I.0E 03    I.OE 03 NI      1.OE 02      1.OE. 02      5.0E 01      I.OE 02        2.5E 02    2.5E 02 CU      5.OE 01      'i.nE,02      2.0E 03        .7ffE02      1.7f 03    1.0E 03 ZN      2.0E 03      i.nE 04      2.0E 04      2.0E 03        5.0E OU    1.0E 03 GA        .3E 02    6.7E 02        1.7fE 03    3.3fE 02        b.7E 02    1.7fE 03 GE      3.3E 03      3.fE- 01      3.3E 01      3.3E 03        1.7fE OU  3.3E 02 AS      1.OE 02      i.nE. 01      3.0E 03      3.3E 0R        3.3E 02    1.7E 03 SE      1.7E 02      1.7E 02      1.0E 03      4.0E 03        1.0E 03    1.0E 03 BR      4.2E 02    3.iE 02        5.OE 01      1.5E-02        3.1E 00    1.5E 00
KR      1.0E 00      1.nE:00        102 0:0      Ij0E 0        .    f0E 00  .0fE 00
RB      2.0E 03      i.nE, 03      t.0E 03      8.3E 00        1.7E 01    1.7E 01 SR      3.0E 01      l.nE 02        5.0E 02      2.0E 00        20OF 01    I.OE 01 Y      2.5E 01      1.0E 03        5,OE 03      2.5E 01          .0OE 03  5.OE 03 ZR      3.3E 00      6.7fE 00      1.0E 03      2.OE 02            OE n1  I.OE 03 NB      3.0E Oi      l.nE u2        8.OE 02      3.0E n4        I.OE 02    5.0E 02 Mo      1.0fE 01    1.nE' 01      I.OE 03          f0
                                                    OE          1.0fE 0t  1.0fE 01 TC      I.5E 01      5.Off 00      U.0f1        1.0f    1O    5.0fE 01  4,OE 03 RU      10OE 01    3.0E 02        2.0E 03        .0OE 00      1.0E 03    2.OE 03 RH      1.fOE 01    3onE:02        2.OE 02      1.OE 01        2.0OE 03  2.0E 03 PD      1.0E 01      3.0E 02        2.OE 02      I.OE Ot        2.0E 03    2.0E 03 AG      2.3E 00      7.7Ef 02      2.OE 02      3.3E 03        3,3E 03    2.0E 02 CO      2.0E 02      2.nE. 03      1.0E 03      3.0E 03        2.5E 05    1.0E 03 IN      I.OE 05      l.nE 05        1.0E 05      1.0E 05        I.OE 05    I.OEf 05 SN      3.OE 03      1.0E 03      1.OE 02      3.0E 0          1.0fE 03  t.OE 02 sB      1.OE00      1..ff,01      1.5E 03 1JQ,OE 01            S.0IE 00  1.5E 03 TE      4.OE 02*      1.0E. 05      I.OE 02*    I.OE 01**      I.OE 05    i.OE 03**
1        1.5E Ot    5.0E 00        4.OE Ol    I1.0E 01          5.0F O0    I.OE 03
                                  1.109-31
 
TABLE A-8 (Continued)
                      FRESHWATER                            SALTWAE;&#xfd;
      ELEMENT    FISH    INVERYF3PATE      PLANT          TrIH    T1JVEITE3RATE      PLA'NT
      XE          I .0E  00  I . nE 00    I .OE 00    1 0OE 00      I.O0E 00            00
      CS                  03                                    oft                I
 
===5. nE Dl===
                    2,OE        I PoE 02      5.OE 02    0i 0OE        2.5f 01 BA           
* 0E 00  2.0E 02      5.OE 02    1 0OE 0!        1 . 0OE 02 5.OE 02 LA          2.SE  01    I .nE 03    S.E 03      2. 5E 01        I if E 03          03 CE          1.OE  00    1.nE 03      4*OE 03 t I.OE O          b.6OE 02    b.OE 02'
      PR          2.5E  01    I.OE 03      5.OE 03    2.5E O        I.OE 03    5.OE 03 ND          2.5E  01  I.nE, 03      S.OE 01    2.5E 01        1.OE 03    5.6c 03 PM          2.5E  01  IoE' 03      5.OE 03    2.5E 01        1.0E 03    5.OE 03 Sm          2.5E  01  I.OE 03      5.OE 03    2.5E 01        1.OE 03    S.nE 03 EU          2.5E  01  1.nE 03      S.OE 03    2.SE n1        1.0E 03    S.OE 03 GD          2.5E  01    10oE. 03    5.hE 03    2.5E 01        1,OE 03      5.OE 03 TB          2.5E  o0  1.oE 03      5.OE 03    ?.SE 01        1.0E 03      5.0F 0.3 DY          2,SE  01  I.oE 03      5,OE 03    2.SE 01        I.OE 01    5.OE 03 HO          2.5E  01  1.OE 03      5.OE 03    2.SE o0        I.oE 03    5.Or n3 ER          2.5E  01    I.oE 03      5.OE n3    2,5E 01        I.OE 03    5.OE 03 TM          2.5E  o0    1.hE 03      S.hE 03    2.SE 01        t.OE 03    S.OE 03 YB          2.5E  01  1.oE 03      S.OE 03    2.5E o1        I.OE 03      5.OE 03 LU          2.5E  01    1.nE 03      5.OE 03    2.SE O0        1.OE 03    5.OF 03 HF          3.3F  00  6,7E. 00      I.OE 03    2.OE 02        2.OE 01    2.OE 03 TA          3.OE  04  b.7E-02      8,OE 02    3.OE Ol        1.7E 04      I.OE 03 W            1o2E  03    1.oE 01      1.2E 03    3.0E 01        3.OE 01      3.OE 01 RE          1.2E  02  6.nE 01      2.UE 02    U.E 00        b.OF 01      2.uE 02
      0S          1.OE  01  3.0E 02      2.OE 02    1.OE 01        2.OE 03      2.OE 03 rR          I.OE  01  3.E'    02    2.OE 02    1.OE (1        2.OE 03    2.E 03 PT          1.OE  02  3.nE 02      2.OE 02    1.OE 02        2.OE 03      2.0E 03 AU          3,3E  01  5oE 01        3.3E 01    3.3E 01        3.3E 01      3.3E 01 HG
      TL
      PB
      B
                    I.OE
                    1,OE
                    1.OE
                    t.SE
                          03
                          04
                          02 o0
                                1.oE 05
                                1.;E 04
                                1.nE 02 I.OE 03 I.OE 05
                                              2.OE 02
                                2.aE 01"**2.E 01***tS
                                                          1.7E 01
                                                          1.0E 04
                                                          3.OE 02
                                                          1.5E 01
                                                                        3,3E 34
                                                                        1,5E 04
                                                                        1,E 03
                                                                        2.UE 01"**
                                                                                      t.OE 03 I1.E 05
                                                                                    5.OE 03
                                                                                      2. a F**0 1 i
      PD          5.OE  02  2.nE Ou      2.OE 03    3.OE 02        51OE 03      2.OE 03 AT          1,5E  01  5,E'    00      .. OE 01  1.OE                        4.0;7 03 RN          1.OE  00    I.oE 00      t.OE 00    1,OE 00        1,OE 00    I.OE 00
      FR          4.OE  02  1,oE 02      8.OE 01    3,OE 01        2.OE 01      2.OE 0l RA          5.OE  01  2,'E 02      2.5E 03    S.OE 01        1,OE 02      I.OE 02 AC.          2.5E  01    1.oE 03      SOE 03      2.5E 01        I.OE 03      5.OE 0O
      TH          3.OE  01  5.nE 02      1.5E 03    t.OE 01        2,OE 03      3.OE 03 PA          1.IE  01      .iEE 02    1.IE 03    I.OE 01        I.OE 01    6.OE 00
      U            2.OE  00  6,OE: O0      S.OE-0      1.OE 01.      !.OF 01      b.6E 01 NP          I.OE  01    4.nE. 02    3.OE 02    I.OE o1        1.OE 01      i. OE 00
      PU          3,5E  00    I.oE 02      3.5F 02    3.OE 00        2.OE 02      I.OE 03 AM          2.5E  01    1.0E 03      5.OE 03    2.SE 01        1.OE 03      5.OE 03 CM          2.5E  01  1.nE. 03      S.OE 03    2.5E 01        1.OE 03      5.0E 03 BK          2.5E  01    I.nE; 03    5.0E f3    ?.SE 01        1.OE 03      5.OE 03 CF          2.5E  01    I.oE'03      5.OE 03    2.SE 01        1.OE 03      5.OE 03 ES          I.OE  01  1.oE, 02      I.OE 03    I.OF 01        I.OE O0    b.OE 01 I.OE  01    1.E 02      I.OE 03    I.OE 01        I.OE 01    bOE 01
  *ORNL - Private Communication
**Freke, A.M., "A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol. 13, p. 749, 1967.
 
***Derived from data in Bowen, H.J.M., Trace Elements in Biochemistry, New York, Academic Press (1966).
                                              1.109-32
 
Ti        is the radiological half-life of nuclide i,              in days; and W        is a shore-width factor that describes the geometry of the exposure.
 
Shore-width factors were derived from experimental data (Ref. 24) and are sunanarized in Tdble A-9.        They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.
 
The combination of Equations (A-4) and (A-5) into the general Equation (A-i) leads to
    ,*uation  (A-6) below for calculation of radiation dose from exposure to shoreline sediments.
 
Rapj      U
                            ap    S*D
                                  i aipj U W
                                                    100Iap      Ciw Ti Daij [  - exp(-- t)]                  (A-6)
                                    U III W
                          110,000      --
                                        F  '--.
                                                      lli Dipj.[exp(-."\t QiT                iP )][l - exp(-:i1t)]                (A-7)
        d.    Dose from Foods Grown on Land Irrigated by Contaminated Water The equations in the following paragiaphs can be used to calculate doses from radio- nuclides in irrihjated crops.                Separate expressions are presented for tritium because of its unique environmental behavior.
 
(1)      Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The rmodel used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 4).
                        The equation for the model (for radionuclides except tritium) is presented below in slightly modified form.              The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility. Thus for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg,                is given by:
                                                                                                              (A-8 )
                iv      i"      - exp(- '"U t e)]v      Biv[I - ex 1(-'P 'itb)1]exp(-..it )
  The de;,osition rate, di,          from irrigated water is defined by the relation d'i = Ciw      (water deposition)                                                        (A-9)
I where Ciw          is the concentration of radionuclide i in water used for irrigation,                in pCi/liter, and I        is the irrigation rate, in liters/m2 /hr; i.e., volume of water (liters)
                              sprinkled on unit area of field in 1 hour.
 
For tritium, the equation for estimating Civ is (see Ref.                25):
                              Cv M Ctl                                                                      (A-10)
                        For a cow grazing on fresh forage,              te in Equation (A--8)  is set equal to 720 hours
  (30 days),    the typical time for a cow to return to a particular portion of the grazing site.
 
1.109-33
 
TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6)
      EXPOSURE SITUATION                      SHORE-WIDTH FACTOR, W
    Discharge canal bank                                  0.1 River shoreline                                      0.2 Lake shore                                          0.3 Nominal ocean site                                  0.5 Tidal basin                                          1.0
                                TABLE A-10
                        ANIMAL CONSUMPTION RATES
                                                                    I
                              FEED ORQFFORAGE            QAw WATER
                            (kg/day [wet weight])
    ANIMAL                                              (;./day)
    Milk cow              50 (pasture grass)                60
    Beef cattle          50 (stored feed grain)            5o From Reference 4, Tables 111-B and -10.
 
1.10g-34 P
 
(2)    Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water.        The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref. 4) is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w):
          CiA = F iAECiFQF + CiAwQAw]                                                                                (A-li)
                  The second set of terms in the brackets in Equation (A-1l)                            can be omitted if the animal does not drink contaminated water. Values for QF and QAw are presented in-Table A-i1.
 
Values for Biv and FiA are given in Table C-5 (see Appendix C).*
                  The total dose Rapj from irrigated foods (excluding tritium) is given by:
          Ra          veg    CiD          + Uanimal ap            Y
                                                              *  iA Daipj                                            (A-12)
            apj        ap        iv aipj If values for Civ from Equation (A-3) and CiA from Equation (A-11)                            are substituted in Equation (A-12):
                                            veg i[)Da [            -  exp(- Ei te)]        Biv[l - exp(-'it )]*
                                                                      v,                    iv      Xi        Lb apj R      ve ap    dix(,          ipJai hi                      YvEi
                                                                                    - -r[lexp( '1Ei te)]
                              U panima ap            iA ai pj OFui                    /  ~v Y- Ei (A-13)
                          +    +PN- exp(-,.,itb)]
                            Biv[l        i          )]+ CiAwQAwj It should be noted that the two components of Equation (A-12) imply that contribu- tions from the individual vegetable and animal products have already been summed.                                  In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)).
                  For tritium, the concentration in animal products is given by the following equation (adapted from Reference 25):
                  kWCv +QAwCAw                                                                                        (A-14)
            CA -          +kQCA
                      m            in Since by Equation (A-IO) Cv = Cw,                  and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows:
                    kC
            CA = 3        (w + QAw)                                                                                    (A-15)
                    in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):
            Rapj : U
            Ra.          ve Cvapj"
                        u~gvap D      + Uap        Aaj(-6 animal CAD    apj                                                            (A-16)
                                  Uve v,,animal Da            (w+    QAw)                                            (A-17)
                    V uea      apjs + Uap Daa                  apj-inab          Q(C--.
          fr FA appear as Fin and Ff in Table C-5.
 
Valus
                                                                  1.109-35
 
REFERENCES FOR APPENDIX A
1. "Final Environmental Statement Concerning Proposed Rule Making Action: Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents,"
    USAEC Report WASH-1258, Washington, D.C., July 1973.
 
2. J. K. Soldat et al, "Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.
 
3. "Food Consumption, Prices, and Expenditures," AER-138, U.S.  Department of Agriculture, Washington, D.C., December 1974.
 
4. J. F. Fletcher and W. L. Dotson (compilers), "HERMES - A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Peport HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.
 
5. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (;.Ci/m2),' Itemi 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.
 
6. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-,41638, General Electric Co., Richland, W'ash., February 1956.
 
7. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption -
    Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA,
    Seattle, Wash., June 1971.
 
8. "The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.
 
9. "Draft Environmental Statement - Waste Management Operations, Hanford Reservation,  Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September 1974.
 
10. "Radiological  Health Handbook," USPHS,  Rockville, Md., January 1970.
 
11. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1311 Dose to the Thyroid," IRS-W-5, Institute for Reactor Safety, Cologne, Germiany, April 1973.
 
12. P. S. Rohwer and S. V. Kaye, "Age-Dependent Models for Estimating Internal Dose in Feasibility Evaluations of Plowshare Events," ORNL-TM-2220, Oak Ridge, Tenn., April 1968.
 
13. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I
    and 137Cs to the Atmosphere," Health Physics, Vol.  17, pp. 51-57, July 1969.
 
14. W. S. Snyder, "Dosimetry of Internal Emitters for Population Exposure," in Population E&#xfd;x  ures, CONF-741018, Proceedings of the Eighth Midyear Topical Symposium of the Health Physics Society, Knoxville, Tenn., October 1974.
 
15. "Report of ICRP Committee II on Permissible Dose for Internal Radiation, International Commission on Radiological Protection," ICRP Publication 2, Pergamon Press, 1959.
 
16. J. K. Soldat, "Modeling of Environmental Pathways and Radiation Doses from fluclear Facilities," USAEC Report BNWL-SA-3939, Pacific Northwest Laboratory, 1971.
 
17. C. M. Lederer et al,  Table of Isotopes,  6th Ed., John Wiley and Sons,  Inc., 1967.
 
18. S. E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, Lawrence Radiation Laboratory, October 1972.
 
1.109-36
                                                                                                  1
 
19. J. K. Soldat, "A Statistical Study of the Habits of Fishermen Utilizing the Columbia River Below Hanford," Chapter 35 in Environmental Surveillance in the Vicinity of Nuclear Facilities, W. C. Reinig (ed.), Charles C. Thomas Publishers, 1970.
 
20. J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.
 
21. J. L. Nelson, "Distribution of Sediments and Associated Radionuc:lides in the Columbia River below Hanford," p. 3.80 in "Hanford Radiological Sciences Research and Development Annual Report for 1964," D. W. Pearce and J. K. Green (eds.), USAEC Report BNWL-36, Pacific Northwest Laboratories, 1965.
 
22. G. L. Toombs and P. B. Cutler (compilers), "Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 - July 31, 1967," Oregon State Board of Health, Div. of Sanitation and Engineering, 1968.
 
23. "Handbook of Radiological Protection, Part I: Data," prepared by a panel of the Radio- activity Advisory Committee (H. J. Dunster, Chairman), Dept. of Employment, Dept. of Health and Social Security, Ministry of Health and Social Services, Northern Ireland, Nlumber SNB 11 360079 8, Her Majesty's Stationery Office, London, England, 1971.
 
24. L. R.. Anspaugh et al, "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.),
    CONF-710809, 1973.
 
1.109-37
 
APPENDIX B
                                    MODELS FOR CALCULATING DOSES FROM
                                NOBLE GASES DISCHARGED TO THE ATMOSPHERE
      The following analytical models are used for calculating doses from exposure to gaseous effluents. Separate models are given for air and tissue doses due to gamma and beta rays.
 
Except for the case of noble gas doses resulting from elevated releases, all models assume submersion in an infinite cloud at the exposure point.
 
1.    Annual Gamma Air Dose    from Elevated    Releases of Noble Gases Slade (Ref. 1) describes the derivation of the equations for estimating annual air doses from photon emitters dispersed in the atmosphere. The following expression can be used for calculating annual doses:
                      D 260
                              n un s      I                      )1    Dik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.
 
The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient. Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki      I [AmEmpa(Em)]/[Ekwa(Ek)]                                            (B-2)
                    m where A      is the fraction of the disintegrations of nuclide i yielding photons m    of energy E
                Em      is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em)      is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined. The summation is carried out over all photons within energy group k. Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2. For radionuclides not contained in Reference 2, data were obtained from Reference 3.
 
Decay during travel from the point of release to the receptor is QD = Q* exp(-Xir/un)                                                          (B-3)
  The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays. Annihilation and bremsstrahlung photon radiations are possible contributors to this compunent of the air dose.
 
Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures. (See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors.")
                                                1.109-30
 
where Qi    is the initial release rate of nuclide i, in Ci/yr, and
                                                                  1 Ai    is the decay constant of nuclide i, in sec"
      All other parameters are as previously defined.
 
2.    Annual Gamma Air Dose from Ground-Level    Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents. The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.
 
The annual average ground-level concentration of gaseous effluent species i at location (r,o)
from the release point is determined from xi(ra) = 3.17 x 104 Q*[x//Q' 1D(r,o)                                      (6-4)
where xi(r,e)    is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 , and
    [/Q')1D(r,o)    is the annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle e at the distance r from the release point,.
                    in sec/mi3 The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year. All other parameters are as previously defined.
 
The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then                                                                          I
          DY(r,e) or DO(r,e) =    xi(re)(OF* or DFO)                                  (B-a)
where the terms are as defined in Regulatory Position C.2.b.
 
Table B-1 presents a tabulation of the dose factors for the noble gases and daughters of interest.
 
3.    Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas. The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue.
 
a.  Elevated Releases The annual total body dose is computed as follows:
          DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t]                                  (B-6)
  Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed. (See Regulatory Guide 1.111.)
  The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.
 
I
                                                1.109-40
 
TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
Nuci ide      a-air* (DFB)                        y-Air* (DFB'') y-Body    (DFBi)
Kr-83m      2.88E-04                                1.93t-05          7.56E-08 Kr-85m      I . 97E-03          1 .46E-03          1.23-03          1 17E-03 Kr-85      1 .95E-03            I.34E-03            1. 72E-05        1.61E-05 Kr-87      1 . 03E-02          9.73E-03            6. 17E-03        5 92E-03 Kr-88      2. 93E-03            2. 37E-03          1.52E-02          1 .47E-02 Kr-89      1.06E-02            1. 01 E-02          1.73E-02          1 .66E-02 Kr-90      7. 83E-03            7. 29E-03          1.63E-02          1 56E-02 Xe-1 31m    1.11 E-03          4. 76E-04            1.56E-04          9. 5E-05 Xe-1 33m    I .48E-03          9. 94E-04            3. 27E-04        2.51 E-04 Xe-i133    i .05E-03          3. 06E-04            3.53E-04          2.94E-04 Xe-i 35m    7. 39E-04          7.11 E-04            3. 36E-03        3.12E-03 Xe-1 35    2: 46E-03            1.86E-03            1.92 E-0:3        1.81E-03 Xe-1 37    1.27E-02            1. 22E-02          1.51 E-0:3        1 .42E-03 Xe-138      4. 75E-03          4.1 3E-03            9.21 E-03        8.83E-03 Ar-41      3.28E-03            2. 69E-03            9.30E-03          8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr
**'2.88E-04 = 2.88 x  I0"4
                                          1.109-41
 
Symbols for this equation were defined earlier in Regulatory Position C.2.c of this guide. The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.
 
The skin dose has two components,  the ganmia and beta contributions. The skin dose rate is computed by DS(r,o)    1.11 x SFD Y(r,o) + 3.17 x 1041    Qi(x/Q']D (r,o)DFSi            (8-7)
                                                        1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.
 
The skin beta dose factors OFS were determined using the decay scheme source docu- ments cited above and the methods used in References 4, 5, and 6.
 
b.    Ground-Level Releases The annual total body dose is computed as follows:
            DT(r,o) = 1.11 x SF &#xfd;xi(rO)DFBi                                              (B-8)
            Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.
 
The annual skin dose is computed as follows:
            Ds(r,o) - 1.11 x SFFZxi(r'e)DFi +    xii(ro)DFSi                            (8-9)
where D5 (r,e)    is the annual skin dose due to immersion in a semi-infinite cloud in I1 the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra)      is the airborne concentration of radionuclide i at point (r,6),  in pCi/m 3 .
                                                1.109-42 I
 
REFERENCES FOR APPENU.X B
I. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.),  USAEC Report TID-24190, 1968.
 
2. M. J. Martin, "Radioactive Atoms,  Supplement I," USAEC Report ORNL-4923,  November 1973.
 
3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-
  12037, 1970.
 
4. R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell,    eds.), Academic Press, New York, 1956.
 
5. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR
  73-107, 1973.
 
6. M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material    Immersed in a Radioactive Cloud," Health Physics,  Vol. 26, pp. 1-12, January 1974.
 
1.109-43
 
APPENDIX C
                                MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
                                      FROM RADIOIODINES AND OTHER RADIONUCLIDES
                                              DISCHARGED TO THE ATMOSPHERE
I.      Annual External Dose from Direct Exposure to Activitv Deposited on the Ground Plane The ground plane concentration of radionuclide          i at the location (r,o) with respect to the release point may be determined by
                          1.1 x  10,      (rc~  Q!                                        (C&#xfd;-l)
              Ci(r'c)                              1 1-exp(-Xit)j
;'-here C    .        is the ground plane concentration of the radionuclide i in the sector at angle - at the distance r from the release point,      in pCi/m2;
                    Qi    is the annual release rate of nuclide i to the atmosphere,          J'i/yr;
                  t      is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life).      This is a simplified method of approximating the average deposition over the operating lifetime of the facility;
                          is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport,      in mn-2 ; and is the radiological decay constant for nuclide i,      in yr-1 .
        The annual    dose from nuclide i resulting from direct exposure to the contaminated ground plant is then D  (r ,)      8760 SFCG(r,r.)DFG                                              (C-2)
where D.j(r,*)
                          is the annual dose to organ j from the ground plane concentration of nuclide ii i at the location (r,r,), in mrem/yr;
and other terms are as defined previously in Regulatory Position C.3.a of this guide.
 
The annual    dose to organ j is therefore D (r,o) = 8760 S        C9(r,o)DFGi                                          (C-3)
                      i          F    I1 Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7. The annual dose to all other organs is taken to be equivalent to the total body dose.
 
Does not include noble gases or their shurt-lived daughters; see Appendix B.
 
1.109-45
 
2.    Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide i at the location (r,t!)    -ith res- pect to the release point may be determined as Xi(r,o)    3.17 x 104QQ[X/Q'] D(r,)                                              (C-4)
where is the release rate of nuclide i to the atmosphere,    in Ci/yr;
          xi(r,O)      is the annual average ground-level concentration of nuclide i in air in the sector at angle 6 at distance r from the, release point, in pCi/m 3 ;
    [./Q']D(r,o)      is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111).    This includes depletion (for radiolodines and particulates)
                      and radioactive decay of the plume; and
                4
      3.17 x 10      is the product of the number of pCi/Ci and sec/yr.
 
The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then iiaa= xi(ro)RaDFAiija DDA (rO)                                                                      (C-5)
      Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.


Sections 50.34a, "Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents
The annual dose to organ j in age group a from all nuclides in the effluent is:                  4 DA                                        (ra=R(C-6)
-- Nuclear Power Reactors," and 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities," set forth design objectives and technical specifications to control releases of radioactive efflu-ents from light-water-cooled nuclear power reactors.
            Dja(r,o)    Ra zxi(re)DFAija
3.    Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is six:ilar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.


Section 50.36a of 10 CFR Fart 50 further provides that, in order to keep power reactor effluent releases as low as is reasonably achiev-able, each operating license will include technical specifications that (a) require compliance with the provisions of &sect; 20.106 dealing with effluent discharge limits, (b) require that operating procedures for the control of effluents be established and followed and that eqi ipment installed in the radioactive waste system be maintained and used, and (c) establish re( :,-ements for reporting measured releases of radionuclides to the environment.
For all radioiodines and particulate radionuclides, except tritium and carbon-14, the con- centrition of nuclide i in and on vegetation at the location (r,Q) is estimated using CV(rO)     di(r,o)  r[l  - exp('AEite)]    Biv[l - exp(-Ytb)]] exp(-1ith)
                        '          '    Ax        +        PXti                        (C-7)
      See Regulatory Position C.l of tnis guide for definitions of terms.


Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion
Carbon-14 is assumed to be in oxide form (CO and C02 ). The concentration of carbon-14 in vegetation is calculated by assuming that its ratio to the natural carbon in the vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 1 and 2).
'As Low As Is Reasonably Achievable'
                                                                                                        I
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.
                                                  1.109-46


However, the assumptions and methods used to obtain these parameters should be fully described and dncumented.
TABLE C-1 ADULT INHALATION DOSE FACTORS
                                          (mreni/pCi inhaled)
    NUCLIDE      A0IE    LIVER    TfTAL 9')Y                  KI)NEY                  GI-LLI
  I        3  0.0          1.3QE-07    t.34E-07        1 .34E-07  S.3LIE-07 1 I 34E-07    1 3LiE-0 7 UBE    10                                                      0.0
                I .qSE-OU  3.OhE-05    U.QbE-Oh                            ?.23E-Ou      1 .b7E-05 bE      I*l                                          u.L?7E-07            u.27F-07    Li.*27E-07
                2.28E-O0    4.27E-07    u.27E-17                  4.27E-07
  7N      13  6.27F-Oq    b.27E-09    h.27E-01      8.27E-09  6.27F-OQ  6 *27E-O9        *.27F-09 QF      14  4.71E-07    0.0        S.20E-oS        0.0        0.0        n.0          9.24E-09
11NA    22    1. 30F-05  1.30E-n5    1.30E-05        I 30E-05  1I 30E-05    I,1 E-n5    1 , 30E -09
1 1 NA  2a    1 .b9E-O6  t.69E-Ob    1.69E-0b        I .69E-Ob 1 ,bqE-06  1 69F-Ob      1 .bqE-Ob ISP      32    I .b5E-0O4  9.65E-Ob    6.27E-Oh        0.1        0.0        0.0          1
* 08E-05
20CA    4L    3.83E-05    0.0        U.II3E-Ob      0.0        0.0        0=0          2.AbE-07
                3.51E-05    1.07E-04    3.11E-05        0.0        I .OOE-0O              3.23E-05
215C    Ub                                                                  S. OE-06
24CR    51    0.0        0.0          1.25E-0R      7.u"UE-09  ?. 5SE-09  1 .75E-06    uL I 5 E-07
25MIN    54    0.0        +/-.95E-0b    7.A7E-07        0.0        I I23F-06              9.b7E-Ob
25 'N    5b    0.0        1.55E-10    2.29E-11        0.0        I.b3E-10  1 .18E-06    2.53E-06
                7.b2E-06    3,43E-05    9.O0E-0B                  0.0                    "7.SuF-Ob
26FE    55                                            0*.0                  ;o.RE-05
?6FE    59    I .a7E-Ob  3.47E-03    1.32E-06        0.0        0.0        1 .27F-04    2. 3SE-05
?7CO    57    0.0        5.bSE-08    B.39E-0O        0.0        0.0)      *.62F-05    3.93E-06
27C0    98    A 0        I.QBE-07    2.SQE-07                              1 .16bF-04i  I I ;3L-05
27CO    bo    0.0        1.u4E-nb    1.8SF-Ob
                                                        0.0
                                                                              7,L7E-04    3I. ,*,3E-OS
                                                                                                  .':6, -05
                                                        0o0        00
28NI    59    ",0OE-0b    1.4bE-O    b.77F-07        0.0        0.0        A,21E-06    b. 1 IE-07
28-1    65    5.40E-05    3.92E-nh    1.PtE-06        0.0        0.0        ?.23E-05      1 .67F-06
                1 .92F-I0  ?.62E-11    I.IaE-tl        0.0                  7.01E-n7      I , 5E -0O
                0.0        1.83F-10    7.b9E-1I                  5,7 8 F-10  *.L1E-07  h. 12E-06
29CU    b6                                            0.0
30ZN    65    L.0  hE-Oh 1.29E-05    S.PE-,)h        0.0        8.b2E-0b  I .OE-04    b.bBF-06
30ZN    694  1 .02F-09  2.L5E-nq    2.2LE-I0        0.0        I. Q48E-09 2,39E-Ob      I .71E-05
30  N  59    4.23F-12    0.13E-12    5.61;E-13                  5.27E-12  1.15E-07    2,0* E-09
                                                        0.0
3uSE    79    0.0        3.83E-n7    6.0QE-O0                  5.bQE-07  Li. LiE-OS
                                                                                          3.33E-Ob
359R    S2    0.0        3.0        1.6hE-06        0.0        0.0        n100          I . 30F-0b
35HR    93    0.0                                    0.0}      0.0        0.O          2.qOE-08
                            3.0        3.O0E-OR                              0.0
353P    84    0.0        0.0        3.91E-08        0.0}      0.0                    2.05E-1 3
353R    85                0.0        !.hAE-09        0.0        0.0        0.0          0.0
                0.0                                    0).0
374B    5h    0.0        1.6QE-O5    7.3RE-Ob                  0,0        0.0
                                                                              0.0          2.08E-O0
37RB    87                                            0.0                                2.88E-07
                0.0        ;.87E-Ob    3.?IE-0h                              0.0
37RR    58                3.85E-B8    P.4iE-08        0.0        0.0                    4,i11E-1I
                0.0
37BR    Bq                3.21E-OB    2.12E-O0        0.,0      0.0        0.0          0,0
3BSR          3.8OE-05                                0.0n                              4**37E-05
3ASR
          89
          90
                            0.0        1.09E-Ob                              I .75E-04 I .2"E-02  0*0        7.6?E-111      0.0
                                                        0.0A      6,0        I .20E-03  9.02E-05
38SP    91    7.9"E-09    0.0        3.,qE-10        0.0        0.0        u.92F-Ob    2,59E-05
3ASR    Q2  8. 4 1E-1O  0.0        3.64E-11        0.0        0.0        2.06E-Ob    5.3RE-Ob
39Y      90
          qO1  2,b6E-07    0.0        7.01E-09        0.0
                                                        0.0        0.0        2.12E-05    6.3PE-05
34Y
3QY      9 1U  3.?2 E- II  0.0        1.27E-12        0.0        0.0                    1 .6bE-I 0
                                                                              2.L1E-07
39Y      91  5.78E-05    0.0        1.55E-06                  0.0        2.1 3E-0 4  4.81E-OS
Note:  0.0 means insufficient data or that the dose factor is <].OE-20.


The procedures and models provided in this guide will be subject to continuing review by the-staff with the aim of providing greater flexibility to the applicant in meeting the require-ments of Appendix I. As a result of such reviews, it is expected that alternative acceptable methods for calculation will be made available to applicants and that calculational procedures found to be unnecessary will be eliminated.
1.109-47


This guide supersedes portions of Regulatory Guide 1.42, Revision 1, "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors," which is being withdrawn.
TABLE C-1 (Continued)
NUCLIDE        BONE    LIVER        TOTAL BODY    THYROID    KIDNEY          lltlN;      .I-i.LI
39Y      92  1.2qE-09  0.0          3.77E-11      0,0        0.0        1.bE-0h    QIqE-ob
39Y      93  1.19E-08  0.0          3.26E-10      n00        n.0        b.n7E-nh  5.,7f.-05
40ZR    q3  5,22E-05  292E-o06    1,37E-O      0,0            .llF-0-5 '113E-05  I1.5F-06 UDZR    95  t.34F-05    4,30E-06    2.91E-0h      m.0        b.77E-0h    2.22F-ou  1.4L-0c)
40ZR    97  1.21E-OB  2.U5E-09    I.13E-nQ      0,0        3.71E-09    4.SE-0b    b.5UF-05
41NB      3
        934 3.lOE-05  1.0IF-n5    2.AqE-n6      A.0        1.IE -0S    3.1IF-n    2,;BEE-0b.


==B. DISCUSSION==
UINB    95  1,7kF-0    *.77E-n7    5.2hE-07      0.0        9.b7E-n7    b.12F-05    I.30E-65
Appendix I to 10 CFR Part SO provides guidance on the levels of exposure of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable.
  41N8  97  2.783E-11  7.03E-12    P.56E-I?      0.0        5. 1E-12      .oOF-07      1.2F-0H
u24n    93  0.0        1.17F-nb    3.17E-1;      q.n            .S55E-07 5.11E-05    1.7qF--t U2MD    Q9  0.0        1.51E-0B    2.87E-19      0,n          ;.&deg;UE-nB  1,1 AE-05  i.10-05
431C    994 0.n        3.64E-13    4 .h3E-1P    0.0        5.52E-12    P.SbE-n9  S.20F-n/
437C    9q  0.0        U.64F-0R    I.37E-04      0.0        5.95E-07    l.nIE-04  7.SuEE-0b Q3TC  101  0.0        7.52E-15    7.38E-14      n0.0        1.35F-13  U.9qE-ns  0.0
44RU  tn3  l.91E-07  0.0.        9.23E-fl      0.0        7.2qCE-07  6.32E-05  1.S        -o..
4uRU  105  9,ASF-11  0.0          3.RqE-l1      0.0          1.27E-10  1.3AE-0b  b.0?E-flb
'JLRU  106  8.64E-0b  0.0          I.0qE-06      0.0          1.67E-05  1.16E-03    1.i 1 E-oll
45RH  105  q.24F-10  b.73F-10    4.43E-10      n.0        2.hE-nQ    2.'41E-ntb  1.01)E-05
46PD  107  0.0        q,27F-08    5,87E-09      0.0        b.57E-07    Q.ugE-Ob    7.OhE-(,7
46PD  109  0.0        4.b3F-10    1.16E-itf    n.0        ?.35E-og    1.85E-Ob    1.52i-fS
47AG  1I104 1.335E-06  I.25E-06    7.a3E-07      n.(        2.3bF6-06  5.OE-04    3..763 -05
47AG  I1I    ,425E-08 I ./BE-08i  A.8TE-Oq      o,0        5. 7uE-P h  2. 34E-n)5 P.l79F-np      I
URCO  113M  n.0        1.54E-0O    '.q7E-06      0.0          1.71E-n4  2.06F-0U    1.99E-n5
48CO  115M  0.0        2.ab4-05    7.qSE-01      0.n          1.9RE-05  1.7bE-Ou      .8OE-05
50SN  123  3.02E-05  6.66E-07    9.P2E-07      5.6bE-07    0.o        P.89E-00  3 .92 -n5i
50SN  125  1.IhF-0b  3.13E-08    7.03E-06      2.59E-03    0.0        7,u2E-05      .MIE-05
50SN  12b  1.58E-04    J.I BE-06  6.OOE-06      1,P3E-0b    0.n          I17E-n 3  1.59L-0P
SISB  124  3.QOF-06    7.3bE-08    155E-06      9.44E-09    0.0        3.1OF-0u  9.0OBF-nl9
51S5  125  8.2bE-06  B.91E-OR    I6bbE-06      7.34F-09    P.0        ?.75F-04    I.?bhf-05
51SB  t2b    .O50F-07 9.13E-09    1.62E-07      2.75E-0    n0.0        1.5RF-n5  b. OIE-0q
515    127  3.30E-08  7.22E-i0    1.?7E-09      3.q7E-10    0.0        ?.nSE-05  3.771F-05
52TE  12591 4.27E-07    I.98E-n7    S.84E-0A      I.31E-07    1.55F-nb  3.92F-05  8.MSF-Ob
52TE  i274  1.58E-06  7.02E-07    1.9hE-07      4.11F-07    5.72E-Ob  1.?OF-OQ  1. 7F-O0
52TE  127  1.75E-10  -. 03E-.11  3,87E-11      1.3.E-10     h.17F-j0  *.15E-07  7.17E-oh
52TE  129M  1.22F-0b  5.64E-o7    1.9RE-77      4.30E-07    : .S7,-0b
                                                                  5E6      11SE-Oa u.7qE -01
52TE  129  b.22F-12  2.99E-12    t.5SE-12      4.87E-12    2.3L3E-11    .a2F-07  t.9bF-0 8
52TE  1314  B.74E-09  5.SE-0q      3,63E-09      BBF-01      3. bE-1A  1.82F--05  b, .9SF-0
52TE  131  1t39E-12  7.44E-13    u .'J9E-13    1.17E-1F    5.ubE-12  1.7 F-07  2. 4uE-0q
52TE  132  3.25F-07  2.b9E-Of    2.0?E-08      ?.37E-0      I.S3E-n7  3,60F-05  6 .3 7E-f5
52TE  1I33M 7,24E-12  5.b0E-12    7.14E-12      6,27E-12    3.7TF-I1  5.51E-07  3.u5F-AQ
527E  134  3.84E-12  3.22E-12    1.57E-12      3.t)U E-12  2.1BE-11    Z.3UE-07  3.b9Emog
531    129  2.'49E-0b  2.1IE-O6    6.91E-O      5.55F-01    14.514E-0b o.l        2.2E-07 S31    130  5.73E-07  1.68E-Ob    6..hF-07      2.18F-04    2.blE-m6  0.0        q.hlF-07
531    131  3.ISE-O6    4.47E-06    2.56F-0b      1.0J9E-03    7.b7F-Oh  0.0        7.8hF-O7
531    132  1.45E-07  U.07E-07    1.45E-07      5.JBE-05    b.UqF-07    0.n        5.18F-0R
                                                                                                      E
                                            1.109-48


This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses. These estimates can be used to implement Appendix I in lieu of site-specific phenomena actually affecting the estimation of radiation exposure.In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU).1.109-7 Appendix A of this guide describes suggested methods for calculating the estimated doses to man from discharges to the hydrosphere.
TABLE C-i (Continued)
  NUCLIDE        BONE        LI VER      TOTAL BODY      THYROID        KInNEY          LUNG          GI-LLI
                            I 56'F-Ob                                    3,*25E-O6
531    133  I .0BE-O0                    5.h7E-07        3.hbE-OLA    3.2UE-07            0.0      I.09E-06
531    134  5.ObE-08      2. 16E-07      7.70E- n        2.97E-05                    0.0
                                                          I . 17 F -OU    .   1 F-Ob  0.0          bSbF-U7
531    135  3.30E-07      R. ?&#xa3;E-M7      3.?2E-07
55CS        I *bOE-OR    S.20E-D8        I .72E-0A      0.0                          ?.94F-OQ      7.,2E-o9 U.hlF-05      1.06E-On      9.11IE-35                                      I.22E-05    I.30E-Otf
55CS                                                      0.0
55CS  135  1 ,UbF-05    I .29E-o5      6.AOE-lh                      I .07E-05      1.57E-06    2.11F-07
55CS    j36  4.8QE-06      I .83F-nS      1 .3 F-05                    2.'1IF-05
                                                          0.0
55CS  137  5.08F-05      7. 77F-05      5. 36E-05                                    9. UE-Ob      I.05b-0h L4. IIE-0b    7. 77E.-08      U. OE-31        0.0          h.Olr-nR      S.07F-09      2.33F-15
55CS                                                                    3705F-05
            2.50F-08      3.53F-n8                                                        ,;).9E-09  0.0
      139                                                0.0
                                                          0.


Appendix B of this guide describes suggested models and assumptions for calculatinr submersion doses from radionuclides discharged to the atmosphere, and Appendix C gives equations for estimating doses from radioiodines and other radionuclides released to the atmosphere.
9. 32F -I a    3.LE-t      2                7. li3F-Ili    u.70E-07      1.12E-07
5695  139  1.17F-I 0
S6BA I40                                  3.21F-07                      2.0QE-nq        1.5QE-nu    2.73L-05
            4.,86.F-0B          IE
                                  15FO
5*A                        9,LIE-i5      !1.2nE-I 3                                    ?.112E-07    I.115F-17
                          63 38E- 15    A. 7E-1 3        0.0          2. 7E-IS
SbBA                                                      0).0                        l.UqF-07      0.0
            9  I  F25
                      - 11                                              0l.0          1.70E-)5      5,.73E-nE
57LA                      2. 1 7E-OA    5S.71E-LnQ        o.n
        12                                                              0.0            1.SSE-Ob    7.31E-0e
57LA  1Ul  5 . 3 UF- 10  1 bhF    -In  2.7 1E-1 1
57LA                        ,.88E-1 I    9.bSE-1 2                      0.0            7.02F-07      2.ULF-07 I ,bQE-Ob                      0.0
                                                          0,.0                        u.52F-n5      1.SoE-05 SRCE        2.49F-02                      1 .QIE-07
      1UO                                                              7 .*          9.LRF-=Ob    2.USE-05
5FCE        2.3 5F -083  1 .72E-n9      I I*E-IQ                      7 .0 E-1A9
58CE        U32E -Ou      1.79F-04I 2.30F-05                                          4.73F-Au      1.02F-0O1
                                                          0. 0
                                                          0,0                          i.51F-3S      2.50F-05
5QPP        I I.7E-06    4.6QE-07      5. 7c)E-OR                      .570F-07 IL                                                                              1.27F-07      2.b6)-18
51PR I    7 3. 7bF- 1?    S.S96E-1 2    I .I E-1 3      0,0                R.55F-l 3 bO lO        6.59E-07      7.b2E-07      Li.S6E-ag        0.0
                                                            o~t                        2.76F-05      ?.IhE-09
            8.37F-05      7.87E-nb                                      1 .5AQE-0S    5.blE-n5      5.S4E-06 blPm 149                                  1I. * ~QfE-Oh IAE -0 L6
            9.82gE-Ob    2.5UE-16                        0.0                          2.l tjF - nUi M. 18 F- 0
b61P.                                                      0.0          3. 5F -0
            3.84E-07      S. 37E-o8      3.2nE-na        0(.0
                                                          0,0          I . f6E-17    3.Q1E-05      5.8OE-05 blPM        3. 17F-O      U.87E-09        I .'99F-00        ,0O        9. IQE-O5      7.?2E-Ob      2.50E-05
      151    ,5* F-0q    I.42F-09      7.21E-10        0.0          ?. 55F-nQ      3.Q4E-Ob      2.OOE-05 b2SH  151                                                                                J.LbE-n5    3.25E-06
      153    .759F-05    1 U.RE-05      1.SSE-Ob        0.0          I .56E-05 bSM          I.70E-08      1. iF-08        I O4E-09                    '4.* 9E-n9      u.1SE-Ob .      .58F-0S
b*EU  15?                5.UOE-05                                                    3.u3E-n4      1,59k-os
      151  2. 3b8F-0d                      .1E7h-05 0l,0              3. 35E-04
                                                                                                      3,'IOE-05 b3EU        7 IJOE-0U                                                  La. 3bE-~IL    5.P.5E-0L
      155                9. IOE-O5      6. LRE-OS
63EU        I *OIF-05    I u3SF-nS      9,21E-Oh                      5. 59E-05      1.47F-05      5.95F-n6 b3EU 15h                                                  0.0
                                                          0.0
      Tk-T  I .79E-Ob    I uSE-nb      2.UOE-n7                      9.95F-07      9.57E-05      L.SOE-05
6ST9  160                                2. 75E-1b        0.0              ,I E-Oh    1.Q2E-04      2.68E-05
            ?. 21F-OS    0.0
b7 1O        3. 3IE-05
            6.2  7E -O0Q I .OSE-n0i    q.00F-05                      t,57E-ou      3.q      -OL  1.59F-05
7LJ,                      2o0TE-ng      ?.1 7E-t 0                    n,0            1.72F-06      2.53E-07
      155                                                    h,0
7iU          I.9SF-07      6. U7E-08      6.81E-09                      0.0            5.57E-05      1.07F-05
        917              3,B5E-10      3.1 OE-lO0                    0,0
            I , ObF-OQ                                                                3.b3E-Ob      1.94E-O5
      210                                                0.0                          ;.63E-02      3.b6E-O5
82PR 210                  6.72E-03      8A.7E-Ou        0.0          2., 1 2E-02 R391        n.0          I .59F-O0      I .3?E-07      0.0          1 92F-05      1.11F-03      2,qSE-05 BiPo 210    3.97F-O0      9.bOE-01      Q.58E-05                      2.-75E-03      3,s1E-n2      4.19E-05
                                                    1.109-49


Appendix D describes the models and assumptions for calculating population dose (man-rem and man-thyroid-rem)  
TABLE C-1 (Continued)
from radionuclide releases to the atmosphere and hydrosphere.
  NUCLIDE    BONE      LIVER      TOTAL BODY    THYROID    KIDNEY                    GI-I.1.1
88RA 223  I .80F-0O  2.77E-07    3.bOE-05    n.0      7.8SE-nb      2.5SE-02    2.B4E-O0
88RA 224  1.98F-O5    4.7BE-08    3.96E-06    0.0      1.35E-Ob      q,78-03      3.0 E-Ou
68RA 225  3,00E-0O    3.56F-07    9.13E-02    0,0      I .OIE-05    2.92E-02    2.71E-Oa
88RA  22b  1.25E-01    2.39E-06                040      6.77E-05      1 .17E-01  2.94E-0O
8BRA  22A  4,41E-02    1.23E-Ob    4.76E-02    0.0      3.QSE-0O      1. 61E-01I  5.00&#xa3;-05
89AC  225  4.23E-0a    5.82E-nO    2. 8OE-O5 b . 3&#xa3; -05    2,21E-02    2.52E-04 BqAC  227  2.30F 00    3.05E-0l    1 .36E-01    0.0      9,9 2E-02      2.q F-0I    O.92E-05
9QTH  227  2. 17F-0O  3.92E-06    6.25E-06              2.22E-05      3. 78E-02    3. 3uE.-Oo
90TH  228  2.00F-Ol    3.39E-03    6.77E-03    0.0      I. 89E-02    1.DIO E (in  3.17E-04
90TH  229  8.88E 00    I .33E-01  4.36E-O0    0.0      b .52E-    I- 3.50E 00    3.1 7E-OU
90TH                                            0.0      6. (10E-0 1
      230  2,2QE 00    1.31E-01    6.36E-2?                            b.22E-01    3. 73E-05
90TH  232  I .99E 00  1.12E-01    5.43E-O2    0.0      5.*17E -01    5.31E-01    7.9'jF-05
90TH  234  I .63E-Ob  9.56E-08    4.70E-08              5 *, L1 E-0 7  I.89E&#xa3;-O    7.03F-05
                                                0.0                                  7
* 0 3-OSi
91PA  231  S.n08    00 I .91E-01  I.9SE-OI    0.0      0.0            5.75E-OP
91PA  233  1.21F-06    2.4 2E-07  2.09E-07    0.0      9 . 1SE -07    3.52E-05    1.02&#xa3;-05
92U  232  5. I 0E-02  0.0        3.66E-03    0.0      5.56E-03      2..23E-01    0*lbE-05
92U  233  I .09&#xa3;-02  0.0        6.5QE-Ou    nO,      2.5E-03        5.33E-02    3.89E-05
          1. O* E-02  0.0                              2 ,. -E -03    S.?2E-02    S.lf-05
92U  23U                          6,06E-Ou    0.0
920  235  I. OOF -02  0.0        6.07E-Ou    0.0      2. 3E-n3        .QOF-02    0
* 80&#xa3;-05 q2U  236  1.OOE-02    0.0        6.20E-00    0.0      2, 3Sq-03      5.01E-02    3.57E-05
                                                        1.51&#xa3;-fl?
                                                                                                  I
92U  237  3.67&#xa3;E-08  0.0        9.77E-09    0.0                    t.02F-0S    I, 2OE -nr
92U  238  9.58E-03    0.0        5.67E-O0    0.0      2. 1AF-03      0.5FF-02    I .ASE-O0
934P  237  1.69E 00    1,47E-01    b.87E-OP    0.0      5. 10E-O1      5.22F-02    4.92E-O5
93NP  23B  2.96E-07    7.99E-09    1.61E-n9    0.0      2. 7?&#xa3;-09      1 .0E-05    2.13F-05
93NP  239                                                8. 75E -flQ    u. 71F-Ob
          2.87E-O0    2.82E-09    1.55E-09              2,*,5E-01                  0 . 52&#xa3;F -OIi Q9PU  238  ?.69E 00    3.73E-01    6.6hE-&#xa3;O0    0.0
                                                0).0                    I .76F-01    0.52F-Os
94PU  239  3,05E 00    4,19&#xa3;-nl                0.0
                                                0.0      3.?0F-01      I .b7E-0
                                  7,53E-0?
94PU  240  3.04E 00    4. 19E-01  7.53E-0?    0.0      3. 20&#xa3;-0 I    I h7F-01        .20F -05
9PIJ  2ul  6.0SF-02                            0.0      5.93E-03      I .52F-O0    8. SE-07
                      3.28E-03    1.29E-03
94tPU 242                                      0,0      3,OSE-nt                      .o
                                                                                      *05-OS
          2.89&#xa3; 00                7,1 7E--2                            I sq9E-01
94PU  240              4.76E-01                0.0      3.64E-01      I .89F-01    t.03E -05
          3.45E 00                B,5'4E-02
95AM  201  9.93E-O0    3.46F-01    b6,7E-02    0.0                    5.86F-02      .6bOE-09
95AM  2424 1.02F n0    3.46E-01    B.73E-02    0.0      5. OIE-OI      2.45E-02    5. 7qE-05
95AM  243  9.qUE-01    3.40E-O0    hf.uE-n2    0.0      O.BbE-01      5.bSE-n2    b.03E.-05
                                                0.0.                    3.74E-02    4.64E-05
96CM  P42  I , I UF-02 I . 18F-02  7.50E-04              3.SOE-03
96CM  203  7.8SE-Ol    2.97E-O0    4.61E-02    0.0      2.15E-01      6.32F-02
          5.QOE-O1                            0.0      1,64E-01      6.07F-02    '4 *.6E -05
96CM 24,              2.5IE-01    3.51E-0?
9bCM  205  1.?bE 00    3.59E-01    7.1 &#xa3;E-f2    0.0      3.33E-ni      5.86&#xa3;-n?    0. 36F-05
                                                0.0      3.33E-01      5.97E-02    0.291-O',
9bCM  246  1.25E 00    3,59QE-O                                                    5.b E-OS
                                                0.0
96CM  247  1.22E 00    3.53E-at    7.03E-a?              3.28E-01      5.86E-02    S. 091-O0
96CM  208  I.01E 01    2.91E 00                0.0      2.70E 00      0.83E-al
                                  5.7qE-01
98CF  252  7.33E-01    0.0        i .83E-02            0.0            1.56E-0l    I . 78&#xa3; -00
                                        1.109-50
                                                                                                  4


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.
TABLE C-2 TEENAGER INHALATION DOSE FACTORS
                                            (mrem/pCi inhaled)
      NUCL IDE      A ONE    LIVER      TOlTAL 8B1)Y    THYROID  K I3NEY    LUNG      U 1-LI. I
    IH        3  0.0        1.06E-07      1.OhE-07    I .06F-01          1 .O06F-07  I.ObE -07 bC      14l  5.66E-07    5.66E-07      S.bbE-07    5.bbE-07            S.b6E-07    5.06eE-07
  11!INA  22    I*7bF-OS    1.76E-05      1.76E-05    i .7bE-05          I .76F-05    I .'J LE-Oh
  27C0 55        0.0        2.20E-08 2.93E-OR          A,(                I .71E-OLI  1.1I F-05 bO    0).0                                  0.0
  27CO                        1.55E-07 2.OhE-07                              I .07F-03    2.Q4lE-0'5
  38Sp B9        4,.84E-06  a3.0          1 .39E-07    0.0        (USE    3.13E-0LJ    4.4L2E -05
  38SR      90    I *.48E-03  0.0          9.01JE-05    0.0                ?.n7F-03
                                                        0.n                            9.* bF-05
  3c9Y      90    I .41E-.08  0.0          3.79E-10    0.0                0.0          h. 79L-0'5
  39Y      01    b. 72E06b  0 .0          1.80E-07                PMULT  3.57E-04I    LI* 7F -05
  'jOZR    95    1.*3bE -Ob  !J.5LLE-07 3.17E-07        0,0                3.*20E-04I  I .6bE -05 JJINB 95        I . 70E-07  1.03E-07    9.7AIE-09      S.*
                                                        0.0 0                9.96E-05    1.1IOE -05 U'JRU 103      2.04OLE-08  0.0          Q.ISF-flQ    0.0        DOSE    4.'I9E-05    I . IRF-05
  44RJ;U 106      I .05F-0b  0.0          1.3?E-07                        ?.05E-nS    1. 16L-04I
  S0SN' 123                  7.6RE-08      I.1ISE-n7    6.1 5E-OA          LI 693E-0LI  3.91E-05
  52TE 1254      5.09E-08    2.32F-D8 b.QIE-09          1 USE-OB    FACTOR) 6.70E-05    8.95E-06
  52TE 127        I b62E- II 7.30E-12      4I.02E-12    1.34E-1 1          I .33E-06    I . 01IE-09
  52TE t294      I .49E-07  7.05F-08    2.40OE-08    i.FBE-05            21.5LF-0LI  LI.80E-05
  52TE 132        3. 75F -09  3.-OOE-09    2.2QE-09      2.54E-09            5.6b7E-05  b.b lE-OS
  531      129    3.53E-06    2.9UE.06    9.81E-06      7.32E-03            0.0        2. 16F-07
  531      131    4I.21IE-06  5.90E-0b    3.SRE-06      I .7E-03            0).0        7.45FE-07
  531      133    I 54~E-06  2.58E-06 7.93E-n7          4.79E-04            0.0          1 .25E-06
  55CS 13Ll      6
* LE-05  1.38F-04I    6.80E-05      0.0                I.ROE-05    I . 12E-06 SSCS t37        8.02E-05    1.03F-04I    3.79E-fl9    0.0
                                                                            1 .47F-05  9.bOE-07
  56BA 1Ji0      6,62E-07    6.06E-10    LI.?7E-ng    0.0                P. 53F-OLI
  57LA ILJO      I .79E-09  4,.72E-10    l.b7E-10      0.0                2. 70E-05  5.981E-05
  5ACE 1'J1      2.84IE-07  1.90E-07    2.1RE-DA      0.0                7. 29E05    I .4I2E-05
  58CE I1U    U  5. 2uF-05  2,17E-05    2,80E-06      0.0                I . 72E-03  1 . OSE-04*
  b3EUI ISLI      9.195E-05  I.02E-o5    &#xfd;.07E-06      0.0                9.29E-04    3.UIE-05 QU      232    6. lL4E-03  0.0          LJ.37E-OLI                        3.84IE-01    4,. IbE-OS
  9?U    234I    I .25F-03  0.0          Z.72E-nS      0.0                9.00OE-02  3.F81E-05
  9UPU 234~      3.22F-01    3.4I3E-02    7.9FLE-03    0,0                            's.52E-05
                                                                            3.1ILI-01 QLIPU 239      3.67E-01I 5.OOF-02      9.06E-03      0.0                2.98E-01    '4. 13E-05
  9Lipu 2U0      3.66,E-0 1 5.OLIF-n2 Q.13E-03                              3.01E-01    4,.13E-05
  9LJPU 24I1      I .29E-04I I.BLIE-0S    3.26E-Oh      0,0                I Q92E-04I  7.94LE-08
  95AM 24J1      I .20E-01  4l.11F-02    7.79E-01                          I .0 1E -01 LI.LJLE-05
  96CM 24I2      I .35E-03  1.40OE-03    8,97E-0';    0o0                6.LI7E02
    9CM 244L    b.99E-02    2.99E-02    4I.16E-03                        1 OSE-01    LI.60E-05 N4ote:    0.0 means insufficient data or that the dose factor is <1.OE-20.


If other models are selected, they should include the same exposure pathways and physical mechanisms as are used in the models described in this guide.As discussed in Section III.A.2 of Appendix I to 10 CFR Part 50, the applicant may take into account any real phenomena or actual exposure conditions that affect or modify the estimate of radiation exposure.
1.109-51


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


For internal dose, t is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;Ua is a usage factor that specifies the exposure time or intake rate for an Uap individual of age a associated with pathway p, in hr/yr or kg/yr (as appro-priate);w is the water intake rate via fresh forage (28 liters/day for beef cattle and 38 liters/day for dairy cattle);W is the shoreline width factor, dimensionless;
(mrem/pCi inhaled)
Yv is the agricultural productivity (yield), in kg(wet weight)/m2 A Ei is the effective removal rate constant for radionuclide i from crops, in hr" provided that AEN : Ai + Awl where Ai is the radioactive decay constant, in (hr)-I, and Aw is the removal rate constant for physical loss by weathering (Xw = 0.0021 hr-1 , which corresponds to a removal half-life of 14 days);Ai is the radioactive decay constant of nuclide i, in hr , AM is the water elimination rate constant (0.32/day for beef cattle and 0.28/day for dairy cattle);1100 is the factor to convert from (Ci/yr)/(ft
    NUCLIDE      BONE      LIVER    TOTAL BODY      T-4YR310    KI )NFY        LJN.G        GI-LLI
3/sec) to pCi/liter;  
  IH      3  0.0        2.03E-07    2.03E-n7      ?.03E-07                  2.03E-07      2. 03R -07
and 110,000 is the factor to convert from (Ci/yr)/(ft
  6C    i1    1 .69E-06  1.69E-06    1.69E-06      I ,69E-06                I b69E-06      I .bqE-06 IINA ?2      4,42F-05    4.42E-05    4u2E-05      a. a2E-05                ", '2E-05
3/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose to the total body or any organ of an individual from the sum of the exposure path-ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.
27C0 5a                  0.t1F-n8    7.?3E-08      0.0                      3.,O*E-OLi    9. 1,* -0o
27C0    60    0.0        2.qOF-07    5.07E-n7      0.0          (USE        1.67E-03      2.H3F-0%
3ASR    89    I..45E-05  0.0        4.16E-07      0.0                _____  .  0E-Oa    I.56F -05
38SR    qO    4.A3F-03    0.0        2.70E-14      0.0                          *.OOE-n3 Q1    1
                                                                                                  ,EF-Ob
39Y    90    9.87E-08    0.0        2.65E-OQ        0.      ADULT        7.26E-05
                                                                                6190E-OI          .. 23E-OS
39Y    QI    2.01E-05    0.0        5.36E-07                                              LI.*    _-O
4OZR    95    3.8IE-06    9.86E-A7    8.05E-07                                5. 72F-O0
LINR    q5  06,0E-07    1.96E-07
                                                    000
                                      t.dLE-07      0.0
                                                    0.0        DOSE          I 5AE-0*
44RU 103    5.AUE-08    0.0        2.36E-OB      0.0                      1.71E-04i          .IS2E -05
  44RU lOb    3.12F-O0    0.0        3.89E-07                                3.93F-03
503N 123      I OUE-OS    1.74E-07    3.'3E-n7      I .9RE-07  FACTOR)       9.46E-04      lI. 1 I- -05
52TE 125m    I .52E-07  5.25E-08    2.0hE-08      4.35E-05                  I . 30F- 04        .10 3E-06
52TE 127    4.83E-I I    1.bSF-11    1.20E-11      U.,IE-l 1                2.5E-Ob
52TE 12QM    a.t4UE-07                              1 .4bE-07                a.T7F-OU      7. 53F
                                                                                              I.    137-07-05
                          1.58E-07    7.03E-08
              1..08E-08                                                                      b.52(- -05
52TE 132                  6.08E-0
                              .*        .91E-09    7.24E-04                  I .03E-O0
531
531
531
      129
      131
      133
55CS 134
55CS 137 I, 05E -05 I .?3E-05
              4.53E-Ob
              1.68E-O0
              2.34E-O4
                          5.4OE-Ob
                          1&deg;25E-05
                          5,S3E-06
                          2.b9E-O0
                          2.16E-o'
                                      2.86E-fS
                                      Q.a7E-0h
                                      2T17E-06
                                      6,02E-05
                                      3.38E-05
                                                    2.14E-02 u.t6E-03 I
* 36F -03
                                                    0.0
                                                        &deg;00
                                                                              .1.0
                                                                              0.0
                                                                                    0
                                                                              3.21E-n5
                                                                              2.71F-05 q.22E
                                                                                              2.168-07 I .54E-O0
                                                                                              I7. .08E-Ob
                                                                                                        -OS)
                                                                                                    I 7E-05
                                                                                                  , 22E-')7
                                                                                                              6 SbBA iaO      1 ,93E-Ob  I,26E-nq    1.laE-07      0.0                      0.69QE-0      2..28E-01
57LA I4O    5.20F-09    9.63E-10    L.3uE-In      0.0                      U*Q2E-05 S8CE 14l    8.47E-07      .24E-n7  6.30E-08      0.0                      I.39E-n4        I.flE-05
58CE 144      1.57E-0U    'I,9tE-oS  8,37E-06      0.0                      3. 32F-n3      I .07E-OP
b3EU IS1    2.87E-04    2.IPE-05    2.OqE-n5      0.0                      I .67F-03      3.71F -05
92U  232    1 .83F-02  0.0        1.31E-n3      0.n
                                                    0.0                      7,"J3E-nl
92U  234    3.73E'03    0.0        2.31E-04      0.0                       I .70F-01
                                                                                              /J. V2E-is a.    57F -05 qiPU 238    9,62E-0I    I.OOE-01    2.38E-02      0.0                      5.87E-01
94PU 239      I.IOE 00    1.13E-01    2.71E-0?                                5.5bF-0I
94PU 20                                            0.0)                                     Li,  &#x17d;LE -05
              1 .09E 00  I.I'4E-O.  2,73E-0?                                5.61E-ni
94PU 241                    .16E-n5  9.73E-06
                                                    0.0r                      3.6lE-0OJ      8. 1bE-OF
              3.84E-o0
95AM 241                                                                      I.QSF-OI      *J.S7F-05
              3.57E-01    9.31E-02    2.33E-02
96CM 242    4.,05F-03    3,17E-03    2.bRE-0O,                                .2? E_-n_1-_
                                                                              ?,02E-01      a. 73r-05
96CM 244    2. 09E-0I    b.77E-02    1.24E-02      0,0
Note:  0.0 means insufficient data or that the dose factor is <1.0E-20.


2. Gamma and Beta Doses from Gaseous Effluents The NRC staff will calculate radiation doses from gaseous effluents using the following equations from Appendix B of this guide. The definitions of elevated and ground-level releases are found in Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors," and Appendix B to this guide.a. Gamma Air Dose Rates for Elevated Releases 260 I DA-7(o n~~ un ns I(Ek)IE(H,u,s,oz,Ek ik (6)where Aki is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration;
1.109-52
DY(r,o) is the annual total gamma air dose at a distance r in the sector at angle 0, in mrad/yr;Ek is the energy of the kth photon energy group, in MeV/photon;
1.109-10
fns is the fraction of the time that stability class s and wind speed n occur for sector 0, dimensionless;
I(H,utsoz,Ek)
Is the result of the numerical integration accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and.atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (o). In addition, I is a function of the photon energy E,1 and is T = 1 4 kT 2 as formulated in Slade (see Reference I fi: Appendix B of this guide);'D Qn 1 is the release rate of radionuclide i, corrected fnr decay during transit to the distance r under wind speed un, in Ci/yr;r is the distance from the release point to the receptor, in meters;un is the me;'n wind speed of wind speed class n, in m/sec;AO is the sector width over which atmospheric conditions are averaged, in radians;and ua(Ek) is the air energy absorption coefficient for the kth photon energy group, in m 1.b. Gamma Air Dose Rates from Ground-Level Releases;
Beta Air Dose Rates from Elevated and Ground-Level Releases o3 Q '/ )D r ( or DF')Dy(r,o) or DO(r,0) = 3.17 x 1O4 I[/Q ](r,o)(OFi or (7)where DF'Y OF 8 I' I Dy(r,O) or D'(r,o)Qi[x/Q']O(r,e)
3.17 x lO4 c. Total are the gar,.na and beta air dose factors for radionuclide I, in mrad per yr/pCi per n 3;are the annual gamma and beta air doses at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;is the release rate of the radionuclide I, in Ci/yr;is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," for methods to estimate x/Q'); and is the number of pCi per Ci divided by the number of seconds per year.Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t]
(8)where oT(r,e)DY(r,o)k is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr;is the annual gamma air dose associated with the kth photon energy group at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;1.109-11 SF is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures
(0.7), dimensionless;
t is the product of tissue density and depth used to determine a "whole-body" exposure.


This depth is 5 cm, which is equivalent to t = 5 g/cm 2;T(Ek) is the tissue energy absorption coefficient, in cm 2/g; and k)1.11 is the average ratio of tissue to air energy absorption coefficients.
TABLE C-4 INFANT INHALATION DOSE FACTORS
                                            (irirem/pCi inhaled)
    NUCLIDE      S O:N F  LIVER        TDIAL 3J)Y                    KI  NE Y  LU NC        GI-LLI
                0.0          3. 07E -n7    3.07E-07                            3.07E-07      3.07F-n7
                                                            3.07E-07 bC      1"                              3.bOE-06        3.SAE-06            3.bOE-Ob      3.OF-Oh
                3.6OE-O0      3.6OF-06
                                                                    0
                                            7.53E-05        7.53E- 5            7.S3F-05        1 .22L-06 IINA    22  7.53E-05      7.53E-05
                0.0          8. 39E-OR    I .2nE-07      0.0                  h.28F-O0      8.67F-06
27C0      58
                0.0          !. OOE-07      8.38E-07                    (USE    3.QRE-03      2. *3E-('0
27C0      b0                                                                                  4.6bE-
38SQ        Q. 3.01E-05                    5,89E-07                            I .h5F-n3
                            0.0
38SR      QO  9.4FE-03                    5.7hE-0A        0.0                  I .09E-02 AU. Q8E-04    9.89F-    *
39Y        00  2.lOF-07    0.0            5.65E-09        0.0
          91  UL27E-05    0,0            191 LE-OB      0.0          ADULT'      , 88E-03  5. 12E -05
39Y
4nZR      05  7.7uE-O6    1 .9SE-06      1.*3QE-*6      0.0                  I .2QE-03      I .01E-05
4INB      05  9. I6E-07    4. 11E-07      2.ULiE-07      0.0*                                8. b7E-Ob
                                                          0.0          DOSE    3.JiF-OU      11.I SE-05
4JRUi  103    I .21E-07  0.0            4 . ! 9E - n                        D. OE -04
44RU    106    6.b5E-O6    0.0            8.16E-07      0,0
                                                            0 .O E-                            1.2bE-04 I .07E-02 U.6IE-n7      7.30E-07      LA. IlE-07                          4.28F-05
50SN 123      2.22E-05                                                        2.SBF-A3 I .39E-07      u.UOE-08        1 .09F-0 7                          9.71F-Oh
52TE 1254      3.2uE-07                                                FACTOR) 3.54E-O4      I .87E-05
52TE i27      1.03E-I0    w.31E-t II 2.56E-1 I          I .OOE-10            7. 03F-00b Q ,UuF-07    4i 1 UE-07    1.47E-07        3. 63F -0 7                        5.23F-05
52TE 1294                  I. I2E-08                                          I .31E-03
                2,25E-08                    I .*hE-nR      I .70E-05                          6. b8E-05 S2TE 132                                                                        2.Q8E-04 I .b2E-05      5.A2E-05      5.21E-02                            2M2E-07
531    129    2.23E-05                                                        0.0
                2.59F-05                    I .70E-35      I .OIE-02                          7b6hE-07
531    131                3.n5E-05                                            0.0
                9.5hE-06    I .38E-05                    3. 33E-03                            I .S3E-0b
53!    133                                LA.IQE-Oh                            0.0
                                                                                                9.80E-07
                3. 43E-OL    5.8QE-O0      5.23E-05      0.0
55CS 13u7                                                0.0
                                                                                7.22E-05
                                                                                                9.45E-07
55CS 13        ".90E-04    5.22E-04      3.15E-n5                            5.7%E-05
5b8.    !LAO      .0 77E-06    S05E-09    2.11IE-07      0.0                                  2.77E-06
                                                          0.0                    ,I 17E-03    6.43F-05
                1 .09E-08    2.29E-3q      7.* E-1 0
57LA 1LO                                                  n.0                  1 .21E-04l 1 .4l F-05
5BCE 1l1      i .80E-Ob    1. IIE-0b      1.2QE-17                            3.7AE-O0
                3. 3IF-O4    I 30E-04      I .7AE-05      0.0                                  I 15E-OLA
58CE IlUq                                                                      9.06E-03
                            4.95E-n5      3.72E-05      0.0                                  3.73E-05 b3EU  154    5.99E-0O                                                        3.99E-03
                            0.0            2.71E-03      0.0                                  L.SSE-05
92U    P32    3.q1E-02                                  0.0                  2.02E      00
                                                                                                A. 16E-05
92U    234    7.94qE-03    0.0            0.91E-14                              *.7LE-fl S.OSE-92                            I .51E    00  4.qbE-05 quPU  238    2.05E 00    2.66E-01                      0.0                              00
                                                                                I .43E        U.51L-05
9gPU  239    2.33E 00    3.O0E-01      5.77E-02
                                                          0.0                                  A.51E-05 gapu    PLao  2.33E 00    3.02E-01      5.81E-0?                            I .45E      00
                            I. I OE--04    2.07E-05      0.0                                  8,.bE-08
94PU  2U1    5. IBE--04                                                      q.9OE-nf L.96E-02                                            U.86E-05
95AM  241    7.61E-01    2.47E-l1                                            S.32E-01
                9,62E-03    8.40E-03      5.71 F- 14                                          5.29E-05
96CM 2u2                                                  0.n                  3,UIF-01
                4.L45E-0 1   I. 70F-01                                                          5.03E-05 obC4 2U4                                  2.65E-02      0.0                  5.51E-01 Note:  0.0 means insufficient data or that the dose factor is <1.OE-20.


d. Skin Dose Rate from Elevated Releases oS(r,O) = l.1ISFOY(r,O)
1 109-53
+ 3.17 x 10 ' Qi[x/QJ]D(rO)DFS
                                                      .
(9)F where DFSi is the beta skin dose factor for the radionuclide i which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr.


This attenuation is for 70 micrometers or 7 mg/cm 2 .f tissue; and DS(r,0) is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/yr.All other parameters are as defined in preceding sections.e. Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF xi(r,o)DFBi (l0)where DFBi is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn 2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in 4 Appendix B of this guide);DT(r,) is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3.All other parameters are as defined above.f. Skin Dose Rates from Ground-Level Releases D 5 (r,0) = 1.11 SF
This yields CV 4 (ro)    =  3.17 x 107 Q74 [x/Q'](r,) 0.11/0.16                                          U
+ xi(rO)OFSi
                          = 2.2 x 107 Qi4 [x/Q'J(r,O)                                           (C-8)
(1i)where D 5 (r,O) is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr.All other parameters are as defined above.3. Doses from Radioiodines and Other Radionuclides Released to the Atmosphere The NRC staff will calculate radiation doses from radioiodines and other radlonuclides released to the atmosphere using the following equations from Appendix C of this guide.i 1.109-12 a. External Irradiation from Activity Deposited onto the Ground Surface D&#xfd;(r,0) = 8760 SF G cG(r,o)DFG..
where Cv 4 (r,O)         is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;
(12)where CG is the ground plane concentration of radionuclide i, in pCi/m 2;Ci DFGij is the open field ground plane dose conversion factor for organ J from radio-nuclide i, in mrem-m 2/pCi-hr;DG(r,O) is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr;SF is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless;
                  !Q14      is the annual release rate of carbon-14, in Ci/yr;
and 8760 is the number of hours in a year.b. Inhalation DA (r,o) R R xi(r,o)DFAi
              0.11          is the fraction of total plant mass that is natural carbon, dimensionless;
(13)where O (rO) is the annual dose to organ j of an individual in the age group a at location* CrO) due to inhalation of all radionuclides, in mrem/yr;DFA. a is the inhalation dose factor for radionuclide i, organ j, and age group a, ija in mrem/pCi;3 Ra is the annual air intake for individuals in the age group a, in m /yr; and xi(r,o) is the concentration of radionuclide i in air at location (r,o), in pCi/m 3.c. Ingestion o r v m .FL L 1)a (ro= 2DFIi -cV(r,+) + UaCim(r,o)
              0.16          is equal to the concentration of natural carbon in the atmosphere,     in g/M 3 and
+ U.i(r,o) + Uaf Ci(r, (14)D. (ro)ja [I a 9 i a ai + a z (4 where ,CF(r,O), C.(r,o), C.(r,O) are the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg. These variables are determined using Equation (C-7) from Appendix C of this guide;D3 (r,o) is the annual dose to the organ j of an individual in age group a from inges-ja tion of all radlonuclides at location (r,o), in mrem/yr;DFlija is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi;f ft are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note: fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U Uvn, Um , UF are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a Ua' a a respectively, for individuals in the age group a, in kg/yr.1.109-13
      3.17 x 107            is equal to (1.0 x 1012 pCi/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).
4. Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1, 2, and 3. Because of the various conditions under which the equa-tions in Appendix D are used, they are not presented in this section. It is recommended that Appendix D be read for a detailed discussion of the staff's models.5. Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I is presented in Table 1.
      The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.          Using the method described in Reference 3, the NRC staff derived the following equation:
            CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H)
                        = 1.2 x 10 7 Qi[X/Q'](re)/H                                            (c-9)
where Cv(r,o)           is the concentration of tritium in vegetation grown at location (r,e), pCi/kg;
                  H        is the absolute humidity of the atmosphere at location (r,o) in g/m3 Q&#xfd;         is the annual release rate of tritium, Ci/yr;
                0.5        is the ratio of tritium concentration in atmospheric water to tritium con--
                            centration in plant water, dimensionless; and
              0.75          is the fraction of total plant mass that is water, dimensionless.


==D. IMPLEMENTATION==
The deposition rate from the plume is defined by:
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.
            dC(r.o) = 1.1 x 108ai(r,e)Qj                                                        (C-10)
where
        6 1 (r,O)          is the relative deposition of nuclide i,    considering depletion and decay in transit to location (r,O),    in m"2 (see Regulatory Guide 1.111) and
      1.1 x 108            is the number of pCi per Ci (1012)  divided by the number of hours per year
                            (8760).
      For radioiodines the model considers only the elemental fraction of the effluent. The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Reference 4).            With this consideration included, Equation  (C-l0)      for radioiodine  becumes:
                                                                                                            I
                                                        1.109-54


Therefore, except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as a result of suggestions from the public or additional staff review.II I 1.109-14 TABLE 1 SUMMARY OF STAFF POSITION -TYPE OF DOSE Liquid Effluents Dose to total body from all pathways Dose to any organ from all pathways Gaseous Effluents**
15.5          x    Si(r,6)Q.107                                              (C-1l)
Gamma dose in air Beta dose in air Dose to total body of an individual Dose to skin of an individual METHODS OF EVALUATING
and Q! is the total (elemental and nonelemental)     radioiodine emission rate.   The retention      ictor r for elemental radioiodine on vegetation should be taken as unity, since the experimental mea- surement (References 5, 6, and 7) techniques used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (References 8, 9, and 10).
APPENDIX I DESIGN OBJECTIVE 3 mrem/yr per unit 10 mrem/yr per unit POINT OF DOSE EVALUATION
      For radioiodines, the deposition model is based only on the dry deposition process.         Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).
COMPLIANCE
      For particulates, the deposition model considers both wet and dry deposition.        There is also a retention factor (r of Equation (C-7)) that accounts for the interception and capture of the deposited activity by the vegetative cover.       A value of 0.2 is taken for this factor (References
WITH APPENDIX I EQUATIONS TO BE USED Location of the highest dose offsite*(see also Table A-I).Same as above.1, 2, 3, 4, & 5 1, 2, 3, 4, & 5 10 mrad/yr per unit 20 mrad/yr per unit 5 mrem/yr per unit 15 mrem/yr per unit Location of the highest dose offsite.***
11 and 12).    All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.
6 or 7, as appropriate Same as above.7 Location of the highest dose offsite.*Same as above.8 or 10, as appropriate
9 or 11, as appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ from all pathways 15 mrem/yr per unit Location of the highest dose offsite.,'
12, 13, & 14 Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.


Calculated only for noble gases.Evaluated at a location that could be occupied during the term of plant operation.
a.  Parameters for Calculating Nuclides Concentrations in Veqetation Consumed by Man When the radionuclide concentration in vegetation directly ingested by man is estimated using Equation (C-7), the following parameters are used:
                        Parameter                                Value
                                                                      2 Yv    (vegetation yield)                        2.0 kg/mi te    (exposure time to plume)                  60 days th    (holdup after harvest)                    1  day for garden-fresh leafy vegetables
                                                            60 days for stored vegetables tb    (soil exposure time)                      15 years (midpoint of reactor operating lifetime)
          All other parameters in this equation are given in Regulatory Position C of this guide.


Doses due to carbon-14 and tritium intake from terrestrial food chains are included in this category.tt Evaluated at a location where an exposure pathway actually exists at time of licensing.
b.  Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal.      The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q    exp(-xit)                                              (C-12)
where C'(r,a)        is the concentration in milk of nuclide i,    in pCi/liter;
        CY(r,O)        is the concentration of radionuclide i in the animal's feed,    in pCi/kg;
              Fm      is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively; for nuclides not listed in Table C-6, use the values in Table C-5);
                                                    1.109-55


How-ever, if the applicant determines design objectives with respect to radioactive iodine on the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine: (l) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives;  
TABLE C-5 STABLE ELEMENT TRANSFER DATA
(2) whether changes in land and water usage and food pathways which would result in individual exposures greater than originally estimated have occurred;  
            Biv        Fm(Cow)            Ff                      8.av    Fm(Cow)          Ff VES/S3IL  41LK (1/L)    MEATT(D/KG)
and (3) the content of radioactive iodine and foods involved in the changes, if and when they occur.1.109-15 APPENDIX A METHODS FOR CALCULATING
ELEM    VEG/SOIL  MILK(CD/L        MEAT(D/XG)          ELEM
DOSES TO MAN FROM RADIONUCLIDE
                                                            SB  I.IE-02    I oSE-03      POE-03 H      4,BE O0    I ,OE02** 2.2E-02
DISCHARGES
                    2,0E-O;                               TE  I'3E 00    I.0E-03        7, 7E-02 HE      5.OE-02                      2,nE-02
TO THE AQUATIC ENVIRONMENT
        8,3E-OG    5,0E-O.                                I  2,OE-02    b. OE-3l3      I2&#xfd;9E-03 Ll                                                                        2.OE-02        2. E-02 BE      4, 2E-o4    I,0E-Oa          i.oE-n3              VE  IOE 01 CS  I OE-02    I
The equations for estimating radiation exposure to man from four principal exposure path-ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide. The equations can be used to calculate the annual doses to various organs of a child, 0 -11 years; a teen, 12 -18 years;and an adult, 18+ years.1. Equation for Calculating Radiation Dose via Liquid Pathways(A-l) is the fundamental equation for calculating the radiation dose to man via liquid effluent pathways.aipj C ip Uap aipj (A--)where Cip is the concentration of nuclide i in the media of pathway p, in pCi/kg;D ai is the dose factor which is specific to a given radionuclide.
* 2E-02"     
* OE-03 B      1.2E-01    2,7E-0"
                                                                b,OE-03                  3.2E-03 C      5*5E" O0    1,2E-02          3.1IF-n2                              . GOE-O1***
N      7.5E 00    2,2E*O.              .OE-02            LA  2,SE-03                  2.OE-04 B.OE-n2              CE                            1.2E-03
0      1.bE GO    2. OE*O2          I .6F-02                2*5E-03    5OE-Oh PR                            4,7E-03 F      6.5E-4O    1.,E-02                                    2,SE-03    SOE-Ob NE                  2. OE-O?                              ,jD                          3.3E-03 iE-ol                        2. OF-n2                2 5E-03    S.OE-Ob NA      5.2E-02    4 .OE-02*4**      I3.OE-02 SF-ot            PM                              4.8E-03 S4  2,SE-, 3  5.OE-Gb        S. E-03
4G      1.3E-ol    IOE-02            SIOE-03                2.E-03 EU            5.0E-Ob        4.BE-03 AL      I .BE-04    5,OE-Ou            I ,E-o3                2.SE0 3    S.OE-O6        3, bE-03 al      1.5E-OM    I1OE-Oa                                GD  2,bE-03 TB            5.OE-Gb        ~4,(E-03 P      1.IE nO    2,5E-OP            u.bFE-2                            SOE-Gb Dy  2.bE-03
                                                                2,SE-03                  S.3E-03 S      S19E-0!    IBE-02            I a.E-nI
                                      Q.OF-03                  2,#E-03                  U,*E-03 CL.    S.OE 00    5,OE-02            8.nE-o2                            5.OE-Ob
                                                                2. SE-03                    .uOE-03 AR      6oOE-01    2.0E-02            'J.6 -n2            ER            SOE-Gb K                  IOE'O*.                                T  2, 5E-03
        3,7E-oi    8 , OE-03***      1.2E-02                            S.OE-Ob        u.OE-03
        .,,6E"O,?                                          YB  2, SE-o33 CA                  5.0E'06**                                            SoOE-06        4.OE-03 sc      I . IE-03  5,OE-06              a.bE-02          LO  2 bvE-03  5IOE-06 TI                                                        NF                              ,CiE-O1 So"E-OS    S. GE-Ge,          3,IE-02                1,7E-OP
V                  lOE-03                                TA                            I.bE O0
        i 3E-03                                                6,3E-03    2.5E-02 CR
MN
FE
CO
        2.SEOu0
        2.9E-io2
        6,6E-Oq
        9,a4E-03
                    2,2E*03
                    2,SE-Ou
                    1?2E-03 I.OE-03
                                        2a3E-n3
                                          1.4E-03
                                        4.OE-04
                                        4.OE-n2 w
                                                            RE
                                                            OS
                                                            IR  1. SE Ot S,OE-Ou
                                                                          2*5E-02
                                                                          5.OE-03
                                                                                          1.3E-03
                                                                                            .,E-03 uOE-OI
                                                                                          1,SE-03 II
                    6,7E-01            1.3E-02            PT  5,3E-01    5,OE-03          4.OE-03 NJ      1,9E-O2                                                                            .OE-03 CU                  I# 4E-02                                  2.SE-03    S.OE'03
        1.2E-01                        8. DE-03            AU            3.BE-02        2.bE-G1 ZN      (S.OE-OI                      3OBE-62
                                                                3 @3E-0I
                                                            TL  2.5E-01    2,2E-02        u.OE-O?
GA      2.SE-0O    5,0E-05            I &#xfd;3F on S. OE04                                    b, SE-02  b.2E-O04        2,9E-04 GE      i OE-ol                        ?.fE 01            PB
                    6,OE"03                                81  I9SE-01    S5OE-O0        I SE-02 A5      I.OE-02                        2.OE-03 S,3E-03
                    ',SE-02                                P3  2oSE-01    3,0E-O0        I 2E-02"
SE      1.3E O0                                                2, SE-Ol                      GOE O0
BR      7#bE-01                        1.5E-n3            AT            S.OE-02 S.OE"O2                                              2.oE-02        2,OE-02 KR      3,OE O0    2, EOE.02                              RN  3,SE 00
Re                  3#OE-O2            2.OE-n2            FR  I, E-O2    5GOE-02        2.OE-02
        1,3E-01    B OE-O4***        3a IE -0'          PA  3, IE-OQ    .80"03** 3,UE-02 SR      1.7E-02                                                                          beOE-02 I I OE-05                            AC  2.5E-03    5.GE-O6 Y      2.bE"03                        Is.6 E-03 S OE-06                                TH  Q,2E-03    S.GE-Oh        2. GE -04I
ZR      16.7E-04                      3,OIE.02                                            B.OE 02 NB                  2#5E"03                                PA  2,SE-03    SOEGOb
        9.4LE,-03                      2., BE -01          U  2,SEmO3    S.OEGOU        3,4E-O4-
        1.2E-01l    7,5E-03            5,OE-o3
                    2.SE-02                                NP  2, SE,,03  5,GOE-b        2,0E-04
        2,5E-01                        4.GE-ot                            2,OE-Oh RU                  IOE"O6                                PU  2, SE"-0                   1.UE-05*.**
        5.OOZ02
        9.OE"01      I.OE-02                                  2, SE"04  5.GE-Gb        2,OE-Oci RN      1,3E 01 t,;5E-Gt    I,OEOG.           t.SE-03            A4 Po      3,  OE-O00
                  I                                            2, SE,03  S.0E-Oh        2.OE-O *i-
        5,OE'      5,0E'02 AG      2,SE-01                        I .7E-02            9K  2,SEo.03  S.OE-Gb
        2.5E-01    5aOEw02                                              5,0E-06        2,OE-G04- CD                  162E-Ou                              CF  2 , SE"03  5,OE-Ob ES  2,SE-03    S.,OE-Gb        2,0E-O*
IN                  I.OE-0O          8.OE-n3                                            20GE-OU f
        2,5E'03    2.5E-03                                F-  2, SE-O3  5,.OE - Oh SN                                    R.MfE-02 t
    Ref. 1.                  Refs. 7, 8, 9, 10, 14, 15, 16, 17.


i, pathway p, organ j, and individual's age a. It represents Lhe annual dose due to the intake of a radionuJide, in mrem/pCi, or from exposure to a given concen-tration of a radionuclide in water, in mrem per hr/pCi per liter;Raip is the annual dose to organ j of an individual of age a from nuclide i via apip pathway p, in mrem/yr; and U ap is the exposure time or intake rate (usage) associated with pathway p for lap .ge group a, in hr/yi or kg/yr (as appropriate).
Ref. 3.               +t Ref. 18.
The three factors making up Equation (A-1) are discussed in the following sections, most of which were taken directly from the WASA-1258 report (Ref. 1). (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the BNWL-1754 report (Ref. 2).)a. Concentration in Environmental Media (Cip)The points at which concentrations in environmental media of interest should be evaluated are shown in Table A-1. The concentrations can be estimated from the mixing ratio M p , the bio-accui;&#xfd;ulation factor Bip, the radionuclide release rate Qi, and other terms presented in the path-way equations that appear later in this discussion.


b. Usage&#xfd; (Uap)The second term of Equation (A-l) is the usage term U ap. Usage is expressed as a consumption rate in kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the pathway p and age group a under consideration.
Ref. 13.


The NRC staff encourages the use of site-specific data, whenever possible, for param-eters such as those included in Table A-2. Such data should be documented.
1.109-56 E1


In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Table A-2 are reconmnended.*
TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK
In selecting usage values, not only the present land and water uses should be considered, but also changes in land and water uses made possible by such activities as chemical pollution abatement.
              ELEMENT                                  Fm (days/liter)
                H                                          0.17 B                                          0.012 C                                          0.10
                Mg                                        0.042 P.                                        0.25"
                Cl                                        0.5 K                                          0.057 Ca                                        0.47
                                                                  *
                Fe                                        1.3E-04 Cu                                        0.013 Sr                                        0.014 I                                          0.06 Cs                                        0.30
                Po                                        0.0018 Computed from the data of Refs.  I and 19.


Radioactive material released into waterways may include long-lived radionuclides that have potential for accumulation in sediments and biota and may persist for many years --perhaps beyond the lifetime of the nuclear power station.1.109-17 TABLE A-I DEFINITION
**
OF POINTS AT WHICH CONCENTRATIONS
  Ref. 13.
IN ENVIRONMENTAL
MEDIA (C ip)SHOULD BE CALCULATED
SUBMERGED (single or multi-PATHWAY SURFACE -LOW VELOCITY SURFACE -HIGH VELOCITY port) -HIGH VELOCITY Fish (fresh and salt water)Invertebrates Shoreline Drinking water CO Discharge canal Discharge canal Discharge canal Nearest anticipated downstream supply***Nearest anticipated point of withdrawal for irrigation t Edge of initial mixing zone*Edge of initial mixing zone*Point of contact of diluted effluent with shoreline Nearest anticipated downstream supply,*Nearest anticipated point of withdrawal for irrigation
+Edge of initial mixing zone**Edge of initial mixing zone**Point of contact of diluted effluent with shnreline Nearest anticipated downstream supply***Nearest anticipated point of withdrawal for irrigation- Irrigated crops Point where effluent has Point where effluent has Fresh water sites only.over the plant lifetime, AFresh water sites only.use projections over the or could exist.undergone prompt dilution near the surface (about 5:1 for large receiving water bodies).undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water).The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections is the closest point to the site where a drinking water supply exists or could exist.The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists____
PATHWAY Fruits & vegetables Leafy vegetablesa Milka,c Meat & poultrya Fish (fresh or salt)Sea fooda Drinking waterc'e Shoreline recreation e Boating Inhalation TABLE A-2 RECOMMENDED
VALUES FOR Uap TO BE U EXPOSED INDIVIDUAL
IN LIEU OF S]CHILD& graina'b 520.0 26.0 330.0 41.0 d 6.9 1.7 510.0 5 e 14.0 29.0 2 7 0 0.0 e 51 190P.O(infant)g SED FOR THE MAXIMUM ITE-SPECIFIC
DATA TEEN ADULT 630.0 520 P?.0 64 100.0 310 65.0 110 16.0 21 3.8 5 510.0 730 67.0 12 52.0 52 ,O0.,e 7 3 0 0 f UNITS kg/yr kg/yr liters/yr kg/yr kg/yr kg/yr liters/yr hr/yr hr/yr m 3/yr aconsumption rate obtained from Reference
3 for average individual and age-prorated and maximized using techniques contained in Reference
4.bconsists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24? grain.CAn additional category of maximum individual
(1-yr old) should be added for these pathways.Consumption rates are the same as the child's.dConsumption rate for adult obtained by averaging data from References
4, 6-9 and age-prorating using techniques contained in Reference
4.eData obtained directly from Reference
4.fData obtained directly from Reference
15.glnhalation rate for infant obtained by averaging data from References
10-14.1.109-19 C. Dose Factor (D aip.)Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref.


15) for body burden and ma):imur permissible concentration (r.IPC). Effective absorbed energies for the radionuclides are calcu-lated from the ICRP model. Appendix D of Reference
1.109-57
16 was used as a basic source of age-dependent dose factors for ingestion.


Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.The dose factors for external exposure were based on the assumption that the con-taminated medium is large enough to be considered an "infinite volume" relative to the range of the emitted radiations.
QF      is the amount of feed consumed by the animal per day,       in kg/day;
              t      is the average transport time of the activity from the feed into the mil:
                      and to the receptor (a value of 2 days is assumed); and Ni      is the radiological decay constant of nuclide i,      in days- Milk-producing animals are assumed to be on open pasture for the following grazing periods:
                        Reg i Uon                          Pasture Period Southern U.S.                      Whole year (fp    1)
                      Northern U.S.                      May - Sept.  (fp = 1/2)
where fp      is the fraction of the year that animals graze on pasture.


Under this assumption, the energy emitted per gram of medium is equiva-lent to the energy absorbed per gram of medium corrected for the differences in energy absorption between air or water and tissue and for the physical geometry of each specific exposure situation.
These data may be supplemented by information on site-specific dairy practices.      The concentration of radionuclide i in the animal's feed is then cv(r, a)  f fCP(e)+ (I1 f )C5 (r,)        +f(1                                  (-3
              ,        pfC(ro          -      i ,.p +      -  5  C~
                                                                    I                      (-
where P
        Ci(ra)      is the concentration of radionuclide i on pasture grass, in pCi/kg;
          I(ro)      is the concentration of radionuclide i in stored feeds, in pCi/kg; and fs      is the fraction of daily feed that is pasture grass when the animal grazes on pasture.


Material deposited from sedimentation in an aquatic systet, or from irrigation water onto the ground represents a fairly large, nearly uniform thin sheet of contamination.
The following parameters will be employed in evaluating the milk pathway, unless site-specific data is supplied.


The factors for converting surface contamination given in pCi/m 2 to the annual gaisia dose at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 4, 5, and 17). Dose factors for exposure to soil sediment have units of mnrern/hr per pCi/1n2 surface.A set of dose factors for 45 radionuclides was originally calculated for the year 2000 model (Ref. 4). These factors have since been recalculated using recent decay scheme informia-tion (Ref. 18) and expanded to include additional radionuclides.
Parameter                                  Value QF  (animal's daily feed)          50 kg/day (wet weight) for cattle
                                                      6 kg/day (wet weight) for goats th  (storage time of animal's food)                          0 for pasture
                                                      90 days for stored feed te  (crop exposure time)            30 days Yv  (crop yield)                    0.75 kg/m 2 (wet weight) for pasture
                                                      2.0 kg/m 2 (wet weight) for stored feed
                                                  1.109-58
                                                                                                    4


The revised list is given in Tables A-3 through A-7; it contains several radionuclides for which the daughter is not listed separately (e.g., Ru-Rh-106, Cs-137-Ba-137m, and Ce-Pr-144).
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
In those instances, the daughter's decay energy has been included in the factor.2. Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel. Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated.
                                                                                                        (C-14)
where C1&#xfd;(r~o)          is the concentration of nuclide i in animal flesh,         in pCi/kg;
                    Ff        is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t      is the average time from slaughter to consumption, which is assumed to be
                            20 days.


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


The Q!/F termis in Equation (A-2) define the concentration of nuclide i in the effluent at the point of discharge.
Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.


The expression (QMM /F)exp(-A
4.     Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by
t ) yields the concentration of nuclide i at the time the water is consumed.I p i p This concentration is the term Cip in Equation (A-1). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system. The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake. Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference
              0.
4.It should be noted that, depending on the hydrological dispersion model employed, the mixing ratio, M'Ip, or dilution factor may not be explicitly defined. In those instances (e.g., buildup of activity in a cooling pond), the relative concentration in the mixed stream (compared to the effluent concentration)
may be supplied as a function of the radiological decay constarnt.


with any potential effluent recycling taken into account. Suggested hydrological dispersion
ija (r,,,) = DFIi4a i [Uvf
,:odels will be contained in another regulatory guide now under preparation on the subject of methods for estimating aquatic dispersion of liquid effluents from routine reactor releases for the purpose uO implementing Appendix I.b. Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations, 1.109-20
                                        [aa gCv(r,.)
TABLE A-3 ADULT INGESTION
                                                i
DOSE FACTORS (mirem/pCi ingested)'JUCLIDE BO.E I 3 0.0 4BE 10 3.l18-06 bC 14 P.BUE-06 7N 13 B.37E-09 QF IS b.2SF-07 IPJA 22 1.70F-05 IlIA 24 21,2OF-Ob 1 5P 32 1.Q3F-04 20CA ul 1.87E-0'J 21SC Ub. 5.SIF-OQ 24CP 51 o.0 254.4 a n0 25mN 5b 0.0 2hFE 55 b.20E-0O 2bFE 59 U.3UE-0b 27Cf0 57 0.0 27C0 5B 0.0 27C0 60 0.0 28,NI 59 9.77E-06 28N1 63 1.30E-O0 284I b5 5,20E-07 2qCU b4 ).0 30ZN 65 U.SE-06 30ZN b94 1.70F-07 30ZN b9 1.03E-08 34SE 79 0.0 35RP A? n.0 355P 93 0,0 35.P 84 0.0 35BR 85 0.0 37RB 0b 0.0 37BR 87 0.0 37RB 48 0.0 37RR 89 n.0 38SR B9 3.09F-0'J 3BSR QO 7.61F-03 3RSR 91 5.82F-Ob 38SR 92 2.IbE-Ob 39Y go 9.63F-09 39Y 91M 9.10E-11 39Y 91 1.alE-07 LTVER 1.34E-n7 4.91E-n7 5.69E-07 9.37E-09 1.0 I .74E-05 2.?bE-0b 1. 21 E-05 0.0 I .nBE-08 S.57E-o6 I .I9E-07 2.79F-oS 1 .03E-09.7 5 -07/ .I, SE -{') 7 2. 15E-0b 3. 35E-O0 9.02E-O0 b.B7E-ng 5.3'JE-06 1 .54F-05 u .0, E-07 1 9SE-08 2. 6I-06 0.0 0.0 0.0 0.0?.11 F-05 I .?3E-OS 6.06F-()8 U.0 1IE-O8 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TnTAL 81)Y 1 .3UE-07 7.o5EF-0 ri.bqE-7&#xfd;. 37E-09 b.93E-OR I .74E-05 2.2hE-rib 7,
                                                        + UCr,)
* 7F.-t0h 2. olE-nS 3.11 E-OQ 2.bbE-19.8 73E-.07 2. 0SE-OR 7.33E-06 3.9?E-06 2.JI1E-07 I .67E-1b U,72E-nb I .b3E-06 4.36F-Ob 3.1 3E-08 3.92E-OR 6.97E-08 3.731E0'I .37E-0O M.dOE-07 2.?PhE-n6 4 .2E-n&#xfd;, 5.22E-O0 2.1 4E-O9 9.8UE-0b 4.28E-4b 3 .21 E-04 2.93E-0.5.89F-06 I .86E-03 P.ShE-07 9.31E-08 2.5RE-10 3.53E-I?3,7RE-09 1,i 3lI-O1 n n 5, qF -07*l 3 7EF-0 9 n.n I .711E-05 22.2SE-0b 0.n0.0 n n 0.0 0.0 n.0 0.0 0,0 0.0 ( n 0,0 0.0 0.0 0.0 0,0 0.n 0.0 0.0 0.0 0.0 0,0 0.0 0.0 KT)NEY I, S. 3 E-fl7 3. 71E-n7 5.69F-07 8. 37E-ng 0.0 I .74E-nc 22. ?6F.-06 0.0 0.0 I .OOF-0B 36RIE-06 l,6bE-07 0.0 0.n 0.0 0.0 0.0 0.0 0.0? 1 n F -n 1 03E-nS?. USE- n7 I ?O2F-OR 41, 5 6F. -n6 n00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 LUNG I .,OE-07 0.0 S.bqE-07'. $7F-09 0.0 I .74E-05>.  0.0 ,0.3. 53F-n9 0.0 0.0 1.23E-05-nb 0.0 ,00 n0.0.0 0,0 0 .n 0,0 0.00 ,00 0.0 0.0 0.0 n00 n,0 0,0 0.0 0.0 0.0 0.0 0.0 0.0)0.0 GI-LL I I .SiF-n7 2.bMF-0'i 5.bQE -07 6. 371F-09 I ASE-05 P. 26F-Uh 2.1I 7E -09 I ..&#xfd;JF -0i7 5.21F -05 1 .ttIE -07 3.h7F-O6 I .oW -05 5.4OF-06 1 .91F-05 ,022F-OS b790E-07 I1 .t i B F -O h 7 .i O-06 Q.70E-(6 2.49F-05 2. 9b-09 5, 38F-07 2.54F-Ob.,79F-OR u0nqF-13 0.0 4, 1bE-Oh 5. 7(E-07 8.3bF-19 0.0 MI,*4E-05 I .02E-nu 2.Q3E-05 4 , 2bf -05 1.02E-04 2,b7L-1 0 77bE7-05 Note; 0.0 means insufficient data or that the dose factor is <].OE-20.1.109-21 TABLE A-3 (Continued)
                                                          a i-     + U FC(,
NUCLIDE 39Y 92 39Y 93 4OZR 93 0OZR 95 a0ZR 97 14tN q33 41.J N 5 QLNB q7 u2mO q3 4240 9q 43TC 994 43TC q9 43TC 101 44RIJ 103 40RU 105 LILRU 106 45RH 105 46PD 107 6bPD 109 47AG 1104 L7AG III 48CO 1134 48Co 1154 50SN 123 50SN 125 50SN 126 SISB 124 S1SB 125 SISH 12b SISB 127'52TE 1254 52TE 127M 52TE 127 527E 12qM 52TE 129.52TE 1314 52TE 131 52TE 132 52TE 1334 52TE 134 531 129 531 130 531 131 531 132 BONE 8.46F-10 2.6E-09 4 .IqF-08 3.0UE-OR I.68F'-09 2.55E-08 b,2sF-09 5.23E-1 I 0.0 0.0 2.47F-10 I 2bE-07 2.54F- 10 1 .85E-07 I .S4E-08 2.75E-O0 1 .22E-07 0.0 0.0 1.6bOE'-07
                                                                      Ua i        + ULf a CL(r, U.       r e        (C-15)
5.82E-0R 0.0 0.0 3.1 IF-05 8. 3bE-06 8. U6E-05 2.81E-06 2.23F-Ob 1. 15F-Oh 2.5E-07 2.b8E-Ob 6.78E-06 I 1 IOE-07 1015E-05 3. ISE-08 S1,74E-06 1.97E-08 2.53E-05 4.63F-08 3.24F-08 3.27E-Ob 7,57E-07 4, tl6E-06 2.03E-07 LIVER 0.0 0.0 2.3uE-Oq 9.76E-09 3.39F-10 S. 33E-09 3.46RE-09 1.32E-1 I 7.52E-nb U,31E-0b 6.98E-I0 1 .8hF-07 3.67E-1 0 0.0 0.0 0.0 8.86E-08 1 .47E-07 I .77E-07 2!.'JRE-07
where DDija
2.44LE-08 3. 1qF-Db I .84E-0b 5.16E-07 1 .6AF-n7 1.68E-Ob 5.30E-00 2.4nF-08 2,3'E-n8 5.bhE-09 9.73E-07 2.37F-Ob 3,95E-08 4L,30E-06 1. 19E-0FB 9, 47E-07 5.24E-09 1.6LAF-0b 2.80E-08 2, 13E.-08 2.8lE-Oh S. 96E'-06 5.43E-07 TOTAL BODv TH)ROID 2.07E-1I 0.0 7.40E-11 n., 1.09E-09 0.0 6.61E-09 n.0 1.56E-10 0.0 2.05E-09 o0n 1.36E-nq n.n L.e2E-12 0.0 2.03E-07 010 8.20E-07 A.('9.9nE-Aq n.0 5.OUE-08 o.n 3.60E-19 n.0 7.qgE-0R 0.0 6.ORE-Oq 0.0 3.48E-07 0,0 S.SIE-OR 0.0 9.UIE-Oq 0.0 U.OOE-08 0.0 4.80E-04 0.0 1.21E-0B n.0 1.02E-07 0.0 5.AgE-OR 0.0 7,6OE-07 L.38F-07 3.79E-0 7  1.39E-07 2.JIE-06 4,92E-07 I.IIE-0.b
            . (r,e)         is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr;
6.79E-09 4.J8E-07 1.9BF-09 U.ISE-07 7.0SE-09 9,q2E-0M 3,IIE-09 3.59E-07 8.07E-07 9.26E-07 1.73E-06 2.3AE-OR 8.16E-0B 1.82E-06 3.qSF-06 7.66E-09 2.IE-0B 7.06E-07 1.34E-06 b.22E-O9 1.62E-OR 1.51E-06 I.BOE-06 4.06E-08 3.92E-03 1.3nE-0' 2.,3E-05 9.22E-0b 7.23E-03 8.R1E-07 2.85E-OIA 3.41E-06 1.95F-n3 1.93E-07 7.15E-05 KIDN EY 0.P 0.0 8.99E-O9 I .SUF-08 5 1 P .E -10 5,58E-09 3. U 5 E-0q I .5AE-1 I I O0hF-AR 2,34E-nb ().bOE-09 7.07E-n7 1 .'9E-07 5.32E-0b 3.76F-07 1 ..32E-06 I .02E-O1 2. 91E-n7 7.8SF-nA 3.50F-nb I4.6F-06 0.0 0.0 0.0 0.0 0.0 0.0 I .09E-05 2.75E-05 LAI*,LRE-07 Li,.!lE-n5
            DFIija          is the age      dosea, conversion group      in mrem/pCifactor (from for the ingestion Tables  A-3 throughof A-6 nuclide i, organA j, of Appendix    of and this guide); and v      m    F     L    are the ingestion rates of produce (non-leafy vegetables, fruit, and grains),
1.3?E-n7 8.5E-06 R.b'E-nf 1,58E-05 2.57E-07 2.09E-n7 60 OSE-(b 3.UIE-Oh I. O.E -05 , bhE'-07 n.0 0,0 0.0 ,00 0.0 (0,0 0.0 0.0 0.0I 1 ,S2E-10 I .9SE-OP 0.0 (1.0 0.0 0.0 0.0 0,0 0.0 2.1 8E-Ob 2.33F-04 7,05E-n7 I .53E-n7 0.0 0,0 0.0}0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Gl-I.Ll 9
  Ua , Ua, Ua, Ua milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide).
* SO F -6C'5 2.U3f -Oh I O5E -na 2.1 OE -05 t.SiF-05 U
All the other symbols are as previously defined.
* 7 F-OR I .b??F -n, ,153F-n7 b.08F -('6 1bF-05 7 6 7E -('74 1,07Et-O5 b. 0Laf-it, 2.2bF-n5 7 .7 a"E -r* S b. 33E-05 2.'3E-0S 7.95F-O5 I .97F-O0 9.40F-05 S QO2E-nh-1,07E-05?.27f -15 8. b8F -Ph 2. 37Fl-08 9.4 &#xa3;0E-05 7.*71 F-05 Li. I 7F -00 1 .92E-nt, I .57F-I~b 1 .n2E-07 I 1.109-22 TABLE A-3 (Continued)
SUCLIDE 531 133 531 134 531 135 55CS 13U 5SCS 135 55CS 13b 55CS 137 55CS 135 55CS 139 569A 139 5654 1 a 0 5bBA IUI Sb8A IUP S7LA 1UO 57LA I U1 57LA IL2 58CE I U 5CE 143 58CE tUQ S9Pq 143 59PR 10I4 6OND lU7 6IPM &#xb6;LI7 61PM I aB7 6IPM tuB 61Pm 151 62SM 151 b2SM 153 63EU 152 63EU 154 63EU 155 b3EU 156 65TB IbO b740 16bM 74M~ 191 740 185 744 187 52PH P O 8381 210 84PO 210 BONE 1.43F-06 1 ObE-07 4.43F-07 2.1 3E-09 6.2?F-05 I q.F-05 b.51F-ob 7.98E-05 5. 5F-08 3.&#xa3;4 F-Os 0 .7 1 F-O0S 2.03E-05 0.0 P. 13E-08 2.SOF-OQ 3.19E-10 1.28E-10 q,3 IE-Oq I.%5E-09 u.BQE-07 9.21E-09 3.02E-1 I h.30E-oq 7.55E-08 3.07E-08 7, 1BF-09 1 .52E-09.l9 7F-I 0 6.91E-08 8.5RF-IO I .q5E-O7 6. 1bE-07 5.61E-08 I .37F -08 4.70E-08 2.70E-07 9.9?E-09 40.bE-07 I .03E-07 I .53F-02 0.b2E-07 3.57E-OU LIVER 2.USF-06 2.SRE-07 I .I 7E-06'J' (IQE -0B 1I USE -04.I 80E-a5 2.57E-o5 I. .OE-0O I. OoF-o 7 5.08F-08 5.92E-I I 2.55E-08 3.56E-i 1 2. 19E-1 I I .26E-O9 9.91E-1l 5.82E-11 6, 3&#xa3;4E-09 I.22E-O0 2,uE-07 3 .70aF.-O0 I .25E'-11I 7.28E-09 7 .10 E -09 7.96E-09 I .I9E-09 2. 1SE-I 0 1.1 7E-1 0 1.1I9E-0B 7.16E-1 0 U1 ,L"JE-OB 7o.7E-08 1 .22F -n8 I .ObE-0 0.0 13.44E-09 3.24E-09 I. 35E-07 8.62E-08 U.38E-03 3.19F-Ob 7.57E-o0 TOTAL RODY THYROID KIDNEY 7.57E-07 1.03E-n7 (429E-n7?. 3nE-os 1.21E-OU 8.OOE-06 I .85E-05 7. 1SE-05 S.. iE-ns I .SE-08 2,84E-09 I .3E-06 1.59E-09 I .3UE-09 3.30E-10 I .62E-1 I 1 .&#xa3;4S5- 11 7 .18E-10 1.3SE-10 2.bE-08 4,57E-10 1.53E-12 4.35E-I0 2.P7E-Oq b.OSE-09 6.OOE-t0 S.7qE-1 I 5.92E-1 I 2.BbE-09 5.23E-1 I 3.9IE-O0 5.39E-08 7.88E-0Q I .71E-ng 5.FbE-09 bAlE-08 3.46E-10 1.4?E-08 3,02E-08 5. &#xa3;E-Oa 3.97E-08 8.60E-n5 4.77E-04 3. 74E-05 I .5jE-n0 D.0 0.0 0.(I 0.0 0.()0.0 0.0 0.0 0.0 0.0 0.0 0I.0 0.0 0.0 0.0 0.()0.0 0.0 0.0 0.0 0 .0 0.0 0.0 0.0 0.0 0.0 0.0 0&deg;0 0.0 0.0 (0.0 0 .0 0.0 0.0l 0.0 0.0 0.0 0.0 4. 33E-flb'.*5 E-9 07 1. 86E-.nh 2. 4 E .. n&#xa3;4. OE..0n I , 3E..n5 3. 71E'.-)5 8.02E.-n8 4.07E-08 6.&#xa3;7E-- I R.6bE-09 3.3tIF-I 1.,SFE-II I,.95E-1t 0.0 0.0 0.0 5.3.E-10 I .21E-07 2. 1 3E-09 7. 06E-1 2 I.25E-09 1I1 3UE-08 1 .2 1IF-O0S 2.25F-09 4.O7-1 0 2 .0 9 F -1 1 .33E-08 2.3?F-10 2.775E-07 3.621--07 5.,LIE-rib
7.09E-09 I.94E-08 1.26E-07 0.0 0,0 0.0 1.23E-n2 3. 84E-05 2.52E-03 LUNG 0.0 0.0 0.0 3.83E-2,OSE-(I .S9F-I ,23E-1 .Q2F-3.70E-3.92E-I '46F-2, 02E-I .2UE-0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 GI-LLI 2. 18EOb 2.51F-1 0 1.31E-06 09 1.58E-08 05 2.%9E-O0 06 4.. 21F-07 06 2.92E-0b OS 2.10E-06 09 4.65E-13 09 0.0 11 1.72E-07 08  11 2,22E-17 11 0.0 Q,25E-OS 4.25E-07 2,42E-05 4,S6E-05 I bSE-OS 4,03E-05 4.33E-18 3.49E-05 8.93E-06 6. 7E-05 9.34F-05 3,22E-n5 S *25E-Ob 2,55E-05 2.56E-05 5.48E-05 9,60E-O0 7.26E-05 4.33E-05 0.0*.bSE-07 1,56E-05 2,82E-05 5,42E-05 4.75E-05 6,36E-05 1.109-23 TABLE A-3 (Continued)
NUCL B8RA 88RA 8BRA 88RA B8RA B9AC 89AC 90TH 90rH 90TH 90TH 90TH 90TH 91PA 91PA 92UL 92U 92U 92U 92U 92U 92U 93NP 93NP 93NP 9'PU 94PU 9UPU 9IJPU guPU 9JPU 95AM 95AM 95AM 96CM 96CM 96CM 96CM 96CM 96CM 9bCM 98CF IDE BONE 223 4.q8E-03 224 1.b2E-03 225 h.57E-03 226 3.05F-01 228 1.12F-01 225 4. -1F-06 227 1.88E-03 227 1.37E-05 229 4.96F-OU 229 R.ObE-03 230 2.08E-03 232 l.SOE-03 23Q .9.02F-08 231 4.I4F-03 233 5.26F-09 232 u.l4E-03 233 8.7?E-0O 234 8.37F-014 235 8.02E-04 23b 8.02E-O4 237 S.53F-08 238 7.67F-OU 237 l.38E-03 235 1.37E-08 239 1.20E-09 238 6.7SF-OU 239 7,60F-04 240 7.58E-04 2U1 1.5bE-05 242 7.22E-04 2L4L 9.60E-0O4 241 8.IOE-04 2Q2M 8.32E-0O 2i3 8.12E-0O 2U2 1.58E-05 243 b.43E-0O 244 4.851-04 24S. 1.03F-03 2U6 1.02F-03 247 9.95E-04 2'8 8.27E-03 252 1.96E-O4 LIVER 7.bbE-Ob 3.90E-Ob 7.79E-06 5.75E-06 3.1?E-06 6,07F-06 2.  2.4BE-07 3.41E-06 1.21E-O04 1 I1 BE -O04 I .OIE-04 4.*72F-09 I.56E-0l I .0bE-09 0.0 0.0 G00 0.0 0.0 0.0 0.0 1.20E-O0 3i,6E-10 1.18E-1O.31E-05 I OMiE-OQ 1,04iE-04S
9.4l7E-07 990E-05 I I 1BE-O4 2.79E-04i 2.78F-00 2.7 3E-O0i I .64E-&#xfd;05 2.QIE-0OJ 2.07E-04 2.B8E-O0 2. 88E-04 2. B3E-O0 2. 33E-03 0.0 9.95E-OU 3.23E-04 I .31E-01 2.21E-01 1.21E-01 2,QsE-07 I I II E-0Q 3.96E-07 I.b8E-AS 3.95E-O0 5.76E-05.4,9?E-05 2.32E-09 I .61E-Ou Q,2AE-In 2.95E-04 5.29E-05 5. 1RE-05 A.86E-05 4.97E-05 I .47E-O0 4.55E-05 5.5qE-05 2.1 3E- 10 6.4AE-1 1 1 .67E-n5 I .88E-05 I.88E-05 3.33E-07 I .79E-05 2.13E-05 5.26E-05 5,47E-05 5.24E-05 I.OUE-Ob 3.77E-05 2.BRE-05 5.BIE-05 5,BOE-05 5.72E-05 4.71E-O4 4.95E-06 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 000 TOTAL BODY THYROID 2.17F-04 1.11 E-oiU 2.21F-ou 1.b3E-04 8.84E-0s 6. 90F-6 7 R.03E-05 tl IE-Ob 4.67F-05 5.80E-OU 5.b9E-04 U.'3bE-ou 2.b7E-OR 1.0 3.99F-nq 4.47E-04 2.0TE-OQ I 40E -no 2.27E-07 I,75E-0U I *7E-04 I .26E-n9 3.S5E-10 7. 1* E-o0?.9bE-05 7.96E-05 I .53E-nS 7.SRE-n5 9.03E-05 3.QbE-OU..O8E-n4 3.95E-0O 4o.7E-0b SI *7bE-0O 1. 3LE-04 2.71E-04 2.7,1E-n4 2.67E-O0 2.20E-03 0.0 KIDNEY .LUNC 0.0 0.0.0 0.0 0.0 ,0.0.0 0.0 ,0.0.0 0.0 n010 0.0 0.0 n100 0.0 0.0 0.0 0,0 0.0 0,0 0.0 0,0 0 0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 11.0 0.0 0.0)0.0 0.0 0.0 G[-I.'.'3.2 E-Ou S.,32E-Ou 5.64E-05 4.07E-04 7.q'E-05 5.JOE-Ou 5.h3E-Ou 5,12E-Oa 6,O2E-OS I *?'E-On 1.13E-Oa b.?T7-Ou I , 4F -0s b. 72E-0&#xfd;b,27E-05 b. 1 UE-05 7,BIE-05 5. 7bE-OS t.bbE-O0 7.94E-A5 7qUE-05 2.a0E-05 7.30E-05 h1b6F-05 6.78E-05 l.u0E-O0 6.5 SE-os q.,5SE-05 9,75SE-OS 7.02F-05 9. 34E-09 9. 73E-Oi 7.92E-05 7.8IE-09 7.55E-05 7.0F-05 6,9I1L-05 q. 09E-05 1.87E-O.3 2. 88E-04 I 4 1.109-24 TABLE A-4 TEENAGER INGESTION
DOSE FACTORS (mrenm/pCi ingested)NUCLIDE BONE LIVER TOTAL B:oY I H 3 6C 1'J IINA 22 27C0 513 27C0 bO 38SR B9 38SR 9o 39Y qo 39Y 91 unZR 95 41,NB 95 44RU 103 OULRU job 505N 123 SPTE 1254 52TE 127 52TE 129M 52 T E 13?531 129 531 131 531 13 95cS 134 55CS 137 5b0A 1U n 57LA 140.5.1CE I1i0 5RCE I1aQ b3EU) 154 92U 232 92U 234 gaPU 238 9UP I 23-QUPU 240 9'PU 2a!95AM 241 9bCM ?42 96CM 24U 0.0 7.55E-07 2.36E-09 ,00 0.0 1 .OE-02 3. 3OF-08 1 .9hE-07 3.72E-08 7.2JE-09 2,37F-07 U OOE-Ob U .3AF -05 3.93E-06 1.51E-07 I bhF-05 3.55F-O0 L.bbF-O6 5.57E-0h 2. 03E-Ob 8.05E-05 1 .07F-O0 2.83E-05 3.43 *8F -09 1 .2bE-08 7.22E-07 1 I5E-Ob 60.bE-03 1,22F-0,3 5,&#xa3;0E-0a 9.2bE-04 9,25F-04 u.03E-07 9,q3E-04 2.26E-05 b
* hL F-0 L I ObE-07 7 .55E-07 2. 35E-35 9.92F-67 2. 76F-nb 0.0 0.0 0.0 I .2'JE-08*.36E-0q 0.0 0.0 7,22E-o7 I .37E -0h 5.3?E-OM 5.15F-Ob 2,22E-Ob 3.92F-O0 7.87E-06 3."UE-Oh 1 .9QE-01 I lUUE-0LJ 3.u4E-os I .72E-09?.9bE-07 I .OnE-n7 0.0 0 0 I I* 1 E-O0 I .29E -n4 I .30F-oil 1.852E-o (.1 7E-nU 2,33E-05 3. 33E-0O I .06F-A7 7.SSF-07 2. 3SE-05 TqYq!10 1.n0E-07 7 .SSE-07 2.35F-05 2.26E-Ob 6. 30E-Ob I .3E-15 2.57E-03 A.87F-ln0 5.?P3E-n9 8.6hE-nQ?.u7E-OQ 1 OhE-07 5.03E-07 1 .0E-Ob 5.0AE-07 3.23F-08 2.61E-nb 2.1 nE-n6 1 .31F-05 U.6qE-nh I OhE-Ob nO 0.0 n o 0.0 0~o 0 .n 0,0 I5,13E-07 5.37E-07 I .03E0O7 5,30E-06 235SE-6 5 2.27E-03 b.?5F-0U 0.0 (USE n 0 0.0 ADULT 3.75E-nS 0.0 0.0 T 0.0 DOSE' 0.0 0.0 FACTOR) 0 &deg; 0 0.0 0.0 0.0 0.0 I .3JF -05.31E-05 4.49F-n5 2.4? eo-O0 1 .O9F-O0 7.53E-05 2.68E-05 I .78E-05 1 .6SEF-0s I .IE-o0 6. 31F-05 I ,07F-05 I .22E-0O 5.R0E-05 8,00E-05 4.31E-07 1.49E-06 2,50E-06 OC I -)NF Y I .06F-07 7.55F-n7 2. 35F-05 GI-LLI 1.0h-07 7.55F-07 9. OhE-05 5.05E-05 I.fPE-06 4.59E-10 3,83E-O8 R.7qE-ng n,2tE-0 7.UnE-05 2.ORE-05 2.2QE-05 2.31E-05 1.02E-00 6.66E-05 I .50E-06 U.n3E-05 0.0 0.0 o.6 0).0 0,0 0.0 0.0 0.0 0.0 2.35E-05 2.24E-Oh 1.91F-05 1.q2F-06?.33E-09 4.tUE-Oh 0.0 Q.8F.-0O n.O 2.29L-05 0.0 1.70E-04 0.0 5.12E-05 0.0 6.72E-05 0.0 6,14E-05 0.0 7.30E-05 o.0 6bE6F-05 0.0 b.bbE-05 0.0 1.28f.-07 0.0 7.17E-05 0.0 7.80E-05 0.0 7.42E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-25 TABLE A-5 CHILD INGESTION
DOSE FACTORS (mrem/pCi ingested)NUCLIOE BONE LIVER TOTAL B.11Y I H 6C I INA 27C0 27CO 38SR 39Y 39Y, (J1NB 44 RU 44LRU SO SN S2TE 52TE 52TE 531 531 55c S SscS 56BA 57LA 58CE SOCE b3EU 92U 9?U 911PU 94iPU 94PU 94 U 95AM 96CM 96CM 3 22 58 bO 89 qO 90 91 95 95 103 lob 123 1 25H 127 129M 132 129 131 133 137 110 1 a1 I a 1 154 232 234 238 239 2a0 2at 201 242?' 11 0.0 2.26E-06 5. 89E-05 0.0 0.0 1.* 38F-03 1.*72E-02 4,1. E-08 5.65E-07 1 .04F-07 1 .95E-08 6,78E.-07 I*1.19E-05
1 .31E-0(1 t I 1'JF-05 4A.50F-07 41.95SO5 I .02F-O5 1 739-E -05 1 .63E-05 5,98E-06 2,24JE-041
3. 12E-04 8.26E-05 I .01E-08 3.76E-OR 2,14'E-06 2.58E-0b 1 .77E-02 3,57E-03 I .21F-03 1 .32E-03 1 .32F-03 7. 12E-07 1.4&#xa3;2E-03 6,74E-05 1. 12E-03 2.03E-07 2.26F-06 5,89F-05 I .8SE-nb 5. 17E-06 0.0 0.0 0.0 o,0 2,012E-08 8. 32E-09 0.0 0.0 1 .641E-06 3.09E-flb t .20E-07 1 .38E-05 UI.5OE -06 8.S(1F-06 1 .67E-DS 7.38E-06 3.77E-fl'3.02E-04I 7.2SE-n8 3.52E-09 I BR8E-08 6. 70E-017 2.08F-07 0.0 0.0 1 .52E-04I 1 .62E-04i I .63E-noL b.211E-n4 5.28E-nS 5. L f -0 1 5.58E-flb 1 .55E-05 3.95E-05 41.36E-0 3 I
* I3E-oq I .56E08)2.?OE-OA 6. I IE-09 2.71jE-07 I USJE-06 3.22E-0b I .S2E-0b 9.65E-06 7.65E-06 5.'I2E-Ob 3.81EF-05 I 426E-05 2,90E-06~2,03E-07 2. 26E-06 S.8QE-05 TH~YRODI 2.03E-07 2.26E-06 5.R~9E-05S
K I )NEY 0.0 0.0 o.0 0.0 0.0 0.0 0.0 I .73E-06 3.20E-06 3. 1 OE-07 1.58E-O5 b.62E -05b 2.79E-02 5,USE-03 1 .7F-0_0.0 (USE 0.0 ADULT 0.0 0.11 ,).0 DOSE 0.0 0.0l 0.0 FACTOR) 0.0 (.0 0.0 0.0 0.0 0n0 JS. iSF-OS.2 .8b -051 7. 77E-05 2.50F-05 1 .J44E -05 I
* ThF -n03 I .k5F-va 1 , I OF -OS.1 .'0?f-fl S5.96EF-05
7 .89F-O5 LI
* 9L .f7 1 .43E-06?.Q9E-oh LUNr P .0 3E -07 PQE-06S G; I -LL I 2.0 3E-07 2. S7k-Ob 4 8. 02E-05 41.50F-05&#xa3;1.SSE-0b 1 .I QE-09 2.80E-09 I.14 (E -07 2.03E-07 1 .26E-03 2.2 1 E-04J 3.09E-OS 3.27E-05 13flnE-05 1 .81E-08 9,9&E-05'1.41hE-06
6.99E-95 0.0 0.0 0.00 0.0 0.0h 0.0 0.0 0.0 0.00 0.0 0.0 0.0 0.0 n , n n , u.19F-05 3.54E-05 u.32E-08 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2.04FI-0(, 1 .8ar-06 0. *21 E-0b 1.noQE-011
2 .36E-05 I .711F-0'J ai. /Ok -05 b.91L-OS 6. 3eF -0'3 7 .50EF -V5 6
* PSE -0 6 1SL -05 I .32F -0 7 7 .37 F -f'5 8.03E-05 7 .bUjE -OS Im Note: 0.0 means insufficient data or that the dose factor is <I.OE-20.O
I 1.109-26 TABLE A-6 INFANT INGESTION
DOSE FACTORS (mrem/pCi ingested)NI b C 27C'38S1 385 39y 4 1 P(50S~52TI JCLTr)E qti'*E.3 0.0 14 U.81F-Ob A 22 1.OnF-OLI LIVER TflTAL ~VlDy 3.0 7F-o7 4.*81 F-ob I *00E-nd 3. 07E-07 U.BI E-06 I OO0E-04 T H4 Y 4 110 3. 07E-07 a0, 4 B I-n0b I.o 0F -04 K 1 3N F Y LONG 3. 07F-07 6 1 E-Ob OO.0F-04~GJ-LLI 3.07E-07 2
* 45E-Oh aJ Sa 0.0 3.78E-06 9.26E-06 0.0 0 .09.79E-0 60n 0.0 1 .07 E- 05 2.56E-05 0.0 n0. 0 2bF R C 2,q3F-03 0.0 A.U2E-05 0.0 (USE 0.0 5."l8E-05 R 90 2.91F-02 0.0 6.U0E-03 6.0 0.0 2 F-04 40 BQIE-08 0.0 2.41E-!&#xfd;9
0 .n ADUL.T .01.29 0 Q I I. 2S9F -0h 0.0 3.33E-OR .0 0 (.0 8.27E-05 R .5 ? .IIF -07 5.32E-nR 3.78E-08 n .n 0 .0 ?.38E-05 Q P95 I.g9E-nR I. 75E-1)8 1 .0 3E -1 0.0 DOSF 0 .0 1 .LJE-Oc J 103 1.OilE-0 0 ,0 U.BSE-07 n .0 1.0 1.7F0 J 1.06 2.5"&E-05
0.0 3.12E-16 0,0 0.0 19E0 N 123 2.7'9E-0Li Q.33F-oh h.96E-lb 4.33E-(16 FACTOR) 0.0 b.41E-05 E1254 2.'J3F-0'S
5.19E-nb 3,20E-flh R.OnE-OS 0.0 1.17E-05 b 5 5 u 5 5 5 52TE 127 9.58F-07 52TE I?9M 1.05F-04 521E 132 2.t3F-05 531 129 2.95F-09 531 131 3.U2E-OS 531 133 1,2bF-05 55CS 130 U.SAE-04 55CS 13 6.53F-O0 56BA 1'&0 1,74E-00 57LA 100 2.12E-08 S8'E 141I S.OOE-08 58CE lU4 0.49E-0b 63EU 154 4.30F-06 92U 232 3.66F-02 920J 234 7.u00F-n3 qAPO P38 1.71F-03 9'IPU ?39 1.70E-03 qqpU ?'40 1.78E-03 94PU P.01 11OhE-0b 95AM 241 1.93F-03 96CM 2U2 1.43E-nu 96CM 244 1.bdE-03 3. 1 9F-n7 3.61F-05 I n05E-05 2. IbE-OS 401 0F-05 1 BUE -05 9~ .2 4E-0 4 7 .31 -4 1 '75-n7 5. 17E-ng 4:91F.08 1 .7 7E -0 h O .RUE-n7 0.0 0.0 2.1 BE-a04 2. 2bF-q0 22 8F? E- fl I .37F-D7 I .01F-n3 I UOOE-04 1.6 7E -00 2. 06E-n7 1 .60E-05 0* 76E-Oh 7 .76E-05 2.3RE-05 S.'BE-06'7.75E-0 7 3.q9E-05 I *99E-'n5 h.* 79 F-02 I .31E-62 u.*35E-0 S..0 0.0 n,0 0.0 0.0 ,0o0 2.?27E-05 6. 33E-05 A, 08F.---05 4.46JE-07 1 .53E-06 3.*27E -06 6.97E-05 0. *20E-05 8 qqF-0b 2
* I E-fO)5.75E-IQ 2.0?E-n7 3.29E-07 2.68E-03 4.71EC-04 0 .25E-q5 0
* I E-1)5 0 .45E-05 2.70E-OP 1 .IIE-nu 9 .Q9F-nb 1 .04E-04 0.0 0 5 0).00.0 0l,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9.42E-05 R.81E-05 I .07E-07 0.0 0.0 O.0 0.0 0.0 0.0 0.0 0l.0 0).0 0.0 0.0 (0.0 n0.0 I .OuF-04 2. 39E-05 I .85E-04 4.*7bE -05 7.*34E -05 6. 72F-05 7.98E -05 7.*29F -09 7.28E-05 I .40OF-07 7.8'4E-O5 13.b,3r-05
8. 12E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-27 TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED
GROUJND*tmrem/hr per ptl/'.)TOTAL BODY SKIN TOTAL BODY sKirt i H 4BE b C 74 9F I TMA-11 NA 1P 20CA 2 1 S C 214CR.25MN 25MN 26FE 2bFE 27C0 27C0 27CO 28NI 28NI 28NI 29CU 30ZN 3nzN 3'JZN 34SE 35BR 358R 35BR 37RB 37RB 37RB 37R8 38SR-38SR 38SR 3ASR 34Y 39Y 39Y 39Y 39Y 3 10 18 22 32 U 1 Ub 51 50 5b 55 59 57 58 6n 5q 63 65 ba b5 694 69 79 82 83 85 87 88 5Aq 59 90 92 90 914 91 q2 93 0'.0 0.0 7 60kE-0q b. 0FO-09 I ,66E-08 2.50E-0B 0,0)3.'JlE-09 0 .nO -O I *30F-08 2.20E-I0 9.60E-09 1 *BOE-ORq 0.0 9. OE-t0 7.OOE-09 1, 70F-08 3. 70E-09 I .50E-09 UQ,00F-09 2.90E-09 0.0 0.0 I .90E-AA 6 .9O0E -I b.UOE-t 1 I .20F-08 0.0 6.30E-1O 3.50E-09 I .50E-08 5.60F-1 3 0.0 7.o I OE-Oq 9.OOE-09 2.20E-12 3.80E-0q 2. 4 OF- II I .6bOF-09 5.70E-I0 0,n 0.0 0 0 5.80E-09 8. OOE-09 I .OE-08 2.90E-08 0.0 U.01E-n9 1 .50E- -B 2.b0E-1 0 I IOE.-08 0.0 9,4OE-O9 I.OOE-OQ R.20E-0Q 2. 00E-O0 0.0 0.0 1 .70E-09 I,70E-Oq 3.0OE-09 0.0 0.0 2.20F-ro8 9. 30E- II.40E-08 0.0 7.20F-10 0.0 4.OOE-09 1.80E-08 b.5OE-13 0.0.3 0E-09 I .OOE-08 2,60E-12 4.40 E-09 2.70E-i I 17.90F-n 7 .80E-1 0 UOZR 4OZR 4OZR 41N8 42MO LJ3TC 43TC'i3TC 44RU U &#xa3;4 P D LA RU LA 9RH 46PD 47AG 47AG 4 A C r)5""s 52TE 52TE 5128 515R 51TE 52TE 52TE 52TE 5?TE 52TE 521E 52TE 52TE 52TE 531 531 531 93 95 97 93*4 95 97 99 9q4 04 101 103 105 1 nb 105 i07 109 I I~111 123 125 12b t 246 125 I ?b 127 12741 127 12 2'4 129 t31M 131 13 2 I 3M 129 130 131 13 2 133 6.0 5.00F-09 5. SOE -()q o0.5. 1OF -A9 4A*bOE-0q 2.29E-I I 1 .qUF-0O Q. *,,E-10 0.0 2.7WF-0O S.bOE-OO 4.5UF-Oq I .50F-09 b.6OE-10 0.0 3.50E-I I I ,80F-08 I .80E-10 2.3nF-12 0,0 0.0 5. 7OF-t0 Q.DOF-09 1.30E-08 3. IOE-09* .9OF -') 9 5. 7OF-09 3.50F-12 I OOF-I I 7.70F-10 7. IOE-10 S., U OF -09 2,20F-09 I .70F-0Q 1 .50E-08 I .OOF-09 4 .SOE-1 0 I *U0E-08 2.80F-09 I .7nE-0O 3.7UE-09 3.0 s .G010 5. O0)E -A9 i,4nE-Oq*20F-09 I* OE-OQ I.OOF-Oq 4 .20F-o9 5. 101-O I jAnF-0q 7.7nE-10 S.0 14.001-I11
'. tOE-08 2. tOE-Io 2.60F-12 0.0 b,* bE-qR b.bOE-10 I DO0E-nm 1 .50F-09 3.50E-09 I .OOE-O8I 1. 0E- II I .IOF-1 I P *OOE-It0 g.uOE-I0 4.90E-09 2,b0E-Ob 2.00F-09 I .70F-OA 1.20E-09 7,50F-I 0 1 .70E1-ri 1 7 0E -n9 5.40FO-DQ 2. O0E -08 U.5AE-09 I*The same factors apply for adult, teen, child.Note: 0.0 means insufficient data or that the dose factor is <l.OE-20.E 1.109-28 TABLE A-7 (Continued)
TOTAL BODY SKIN 53! 13u I.bOF-0 l.90t-o0i 531 13 1 .20EE-08 1uOE-O8 55CS 134'1 b.P0E-10 7.Y0E-10 55CS 134 1 .2F-08 IQOE-0p 55CS 135 0.0 D.0 55CS t36 1.5OF-'4 '.70E-08 55CS 137 4 .2OF QJ -.90E-0Q 55CS 13A 2,tOE-05 2.uOE-OR 55CS t39 b.30E-ng 7.20F- nq 5b65 139 2.uOE-0Q 2.70E-0Q 5hBA 140 2.lOE-0q 2,unE-09 56BA 1UI U.IOF-o9 qt90F-0Q 5b6A 1u2 9.00E-DO 57LA lU0 1.50E-0R 1.70E-08 57LA 141 2.5vE-10 2.5nE-t0 57LA IQ2 1.50E-OR t.ROE-05 58CE ]at 5.50E-10 b.20E-t0 58CE 143 2.20E-0q 2.50E-0Q 58CE Ua a 3.20F-10 3.70F- 10 59PR 143 0.0 0.0 59PR IOU 2.OOF-10 '.3nF-10 bOND 147 1.00E-0q 1.20E-09 blPM I7 0.0 0.0 tIPM 4RM4 1.UtF-.F0
5 6.-01-bIP4 10B  bIPM 14Q 2.50E-11 2.QoE-il biPH 151 2.2'F-OQ 2.30E-o9 b25 151 u.80E-11 2.10F-10 b2SM 53 2.70F-In 3.0OE-10 13EU 152 7.37E-09 3.53E-0O 63EU 15u 7.BUE-09 4.00F-19 b3EU 195 I.RIE-10 U.33E-10 b3EU 156 7.80F-09 3.70E-Mg 65TB 160 A.6(0E-A9
1.00E-0A 67H40 I664 5.90F-00 1.OOE-nS 7UA 181 2,ROE-12 7Ui 185 n 0 .0 a 74" 187 3.1'E-AQ 3.bOE-09 82PH 210 1.30E-11 1.70E-11 381B 213 0.0 0.0 RaPO 210 5,10E-'1 b.2OE-tu TOTAL BODY SKIN 8RRA 2?3 1.50F-09 I.ROF-09 8SRA 22u 3.9nE-0q 1.OOE-08 88PA P25 ;. 11F -t I I. 2()F -1A 88AA 22b b.41JF-oq
7.40E-O0 R.RA 228 I,?f'F-0 1 t.4OF-n8 89AC P2? IrNF-OQ 1.80E-oQ 9A9C 227 2.OOE-09 2.40F-59 90TH 227 5.10F-10 b.30F-t0 90TH 22? ,.QOF-0Q t.00E-0A 90TH 229 2.20F-0 0 2.70E-09 90TH 230 h.S0E-nq 7.SOE-nq Q0TH ?32 S.OOF-OQ U.nOE-Oq qOTH 23u 1.1OE-10 1.30F-10 91PA 231 2.20F-0Q &#xfd;.70E-09 qtPA 233 1.30F-09 1.50F-99 92U P32 2.5qF-12 2.b9E-11 92U 233 2.30E-09 2.rtOF-o9 92U 234 b.32F-13 1,59E-10 q2U 235 i.20F-Oq 4.OOF-ng 92L P3b 2. IF-I I .80E-11 92U 237 t.00F-09 1.30E-0q 92U 238 1.10F-10 1.50E-10 13NP 2;7 1.40F-09 1.bOE-Pq 93NP 238 2.8nF-09 3.20E-oq 93NP 23q 9.50F-10 1.10E-0q Q9PUJ 238 1.30E-12 1.80F-11 9LPU P39 7.90F-13 7.70E-12 94PU 240 1.30F-12 t.80E-11 9LPU 241 4.h0E-12 b.80E-12 QUPU 242 1.10F-12 1.60F-11 9qPki 2441 8.95E-10 1.62E-10 9SAM 241 1.801E-10
2.60F-10 95AM .4??4 2.h6F-11 1.80E-1l 95AM 24.3 1.30E-09 1.50E-09 96CM 2U2 5.50E-12 2.30E-11 96CM 243 2.30F-Oq 2.90E-0Q 96CM 2ila 2.qnE-12 1.8OE-11 96CM 245 9,50E-10 1,20E-09 96CM 246 1.00E-12 1S50E-11 96CH ?P7 2,20E-0Q 2.bOE-09 9bCM 2a8 6.8IE-0q 5.23E-09 98CF 252 b6b0F-0R 7.20E-08 1.109-29 called bioaccumulation factors in this guide, can be found in the literature (Pnf. 19). The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose for consumption of aquatic foods.Rap = 1100 Uap Q.B. D (A-3)i aipj , p Values of Bip are given in Table A-8; the other parameters have been previously defined.The transit time tp may be set equal to 24 hours to allow for radionuclide decay during transit through the food chain, as well as during food preparation.


c. Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with suspended and deposited materials.
The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD =      DF      .rvf          +  m          +  F F          L      L                (C-16)
                ja          ija    a g 1          a i          a i          a k I
                                                          1.l0-59


One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21). Based on these references, an estimate of the radio-nuclide concentration in shoreline sediments can be obtained from the following expressions:
REFERENCES FOR APPENDIX C
Ciw[l -exp(-.it)]
I. Y. C. Ng et a), "Prediction of the Maximum Dosage to Man fro;m the rallout cif ucclar Devices, IV Handbook for Estimating the Maxi'ium Internal Dose tro,m RPdio!;uclide:;             :d-,
C.s Kc 1w i (A-4)is c where Cis is the concentration of nuclide i in sediment, in pCi/kg;CiW is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter;
                                                                                                  &#x17d;,Pc to the Biosphere," USAEC Report UCRL-5D163, Part IV, 1968.
Kc is an assumed transfer constant from water to sediment, in liters/kg per day;t is the length of time the sediment is exposed to the contaminated water, nominally
15 years (approximate midpoint of facility operating life), in hours; and Ai is the decay constant*
of nuclide i, in hours-l. In the original evaluation of the equation, Xi was chosen to be the radiological decay constant, but the true value should include an "environmental" removal constant.The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period of several years in the Columbia River between Richiand, Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 22 and 23). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters meter above the sediment, an effective surface contamina- tion was estimated.


This surface contamination was assumed to be contained within the top 2.5 cm (I in.) of sediment.**
2. R. C. Weast (ed.),  "Handbook of Chemistry and Physics," CRC Press, Cle,',eland,       Ohio, 1D70.
The dose contribution from the radionuclides at depths below 2.5 cri was ignored. The resulting equation is Si MOT 1 iCi WDl -exp(-Ait)] (A-5)where Si is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations;
If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).With a mass of 40 kg/m 2 of surface.1.109-30
TABLE A-8 BIOACCUMULATION
FACTORS CpCilkg per pCi/liter)
FRESHNATER
SALTMA17ER
ELEMENT FISH INVERTF3RATE
PLANT PIS' TIVERTE3RATE
PLANT H 9,0E-Ol q.oE-01 9.OE-01 9.OE-ni 4.3E-01 9.3E-01 HE 1.0E 00 1.0f 00 10Elf 1.0ff O0 1.fOE 00 t.OE no LI 5,0E-Ol C.oE: 01 3.0E 00 5.OE-01 50fE-Ol 3.0E 00 BE 2.OE 00 InE 01 2.0E 01 ',OE 02 e.OE 02 1.OE 03 B 2.2E-01 5.OE 01 2.2E 00 2.2E-Ot QO.E-01 2.2E oA C U. 0E 03 Q 03 4.bF 03 t.5F Os 1.14E 03 1.8E 03 N 1.5ES 05 1.;E 05 1.3f3E 04 h. E 04 1T7E "04 1 .0f p 0 0 9.2E-O 9.?fE-01 9.2E-0l 9.bF-01 9.bE-01 Q.bE-O0 F 1.0E 01 1 .oE 02 2.0E 00 3.bF 00 3.6f on 1 .4E 00 NE I.OE O0 I.nE 00 1. r E 00 1.0E 00 1.0OE 00 1.OF 00 NA I.OE 02 2.oE. 02 5.OE 02 b.7E-02 1.QE-01 9.SE-O1 MG 5.OE 01 1.oE 02 1.0OE 02 7.7Ff-01 7.7fE -01 7.7E -0 1 AL ioE0f 01 6.;E 01 U.2E 02 1.0OF n1 b.OE O0 6.OE 02 SI 2.5E 00 2.';E 01 1.3E 02 1.0f 01 3.3E 01 6.7P 01 F 1.0oE 05 2.oE. OU 5.0E 0'; 2.fE n4 3.0E O4 3.0E 03 T 7.5E 02 I.oE. 02 1.0E 02 1.7E 00 4,UE-01 U.4E-01 CL 5.0E 01 .ofE 02 5.OE 01 1.3E-02 I.QE-02 7.6E-02 AR I.OE 00 1.nE 00 1,OE 00 1.0ffno I.OE 00 1.OE 00 K I.OE 03 8.lE 02 6.7E 02 1.IE 01 .6fE 00 2.6E 01 CA 4,OE 01 3,3E 02 1.3E 02 5.0E-Ol 1.3E 01 5.OE 00 SC 2.0f 00 1.fE' 03 t0OE 0 Oi 2.0fE 00 1.fOE 0 Q I.0 E 05 TI t.OE 03 3.OE. 03 5.OE 02 1.OE o3 1.OE 03 2.0E 03 V 1.OE 01 3.E 03 1.0E 02 1.0E Ol 5.OE O i.OE 02 CR 2.0E 02 2.nE 03 .",OE 03 4.0E 02 2.0E 03 2.0E 03 m, ,40OE 02 9.oE 04 1.0fE 04 5.5E 02
* 4.OE 02 5.5E 03 FE 10OE 02 3.pE 03 1.0E 03 3.0E 03 2.OE O4 7.3E 02 c0 5fOE 01 2.nE 02 2,0E 02 .0OE 02 I.0E 03 I.OE 03 NI 1.OE 02 1.OE. 02 5.0E 01 I.OE 02 2.5E 02 2.5E 02 CU 5.OE 01 'i.nE, 02 2.0E 03 .7ffE 02 1.7f 03 1.0E 03 ZN 2.0E 03 i.nE 04 2.0E 04 2.0E 03 5.0E OU 1.0E 03 GA .3E 02 6.7E 02 1.7fE 03 3.3fE 02 b.7E 02 1.7fE 03 GE 3.3E 03 3.fE- 01 3.3E 01 3.3E 03 1.7fE OU 3.3E 02 AS 1.OE 02 i.nE. 01 3.0E 03 3.3E 0R 3.3E 02 1.7E 03 SE 1.7E 02 1.7E 02 1.0E 03 4.0E 03 1.0E 03 1.0E 03 BR 4.2E 02 3.iE 02 5.OE 01 1.5E-02 3.1E 00 1.5E 00 KR 1.0E 00 1.nE:00 102 0:0 Ij 0E 0 .f0E 00 .0fE 00 RB 2.0E 03 i.nE, 03 t.0E 03 8.3E 00 1.7E 01 1.7E 01 SR 3.0E 01 l.nE 02 5.0E 02 2.0E 00 20OF 01 I.OE 01 Y 2.5E 01 1.0E 03 5,OE 03 2.5E 01 .0OE 03 5.OE 03 ZR 3.3E 00 6.7fE 00 1.0E 03 2.OE 02 OE n1 I.OE 03 NB 3.0E Oi l.nE u2 8.OE 02 3.0E n4 I.OE 02 5.0E 02 Mo 1.0fE 01 1.nE' 01 I.OE 03 OE f0 1.0fE 0t 1.0fE 01 TC I.5E 01 5.Off 00 U.0f1 1.0f 1O 5.0fE 01 4,OE 03 RU 10OE 01 3.0E 02 2.0E 03 .0OE 00 1.0E 03 2.OE 03 RH 1.fOE 01 3onE:02 2.OE 02 1.OE 01 2.0OE 03 2.0E 03 PD 1.0E 01 3.0E 02 2.OE 02 I.OE Ot 2.0E 03 2.0E 03 AG 2.3E 00 7.7Ef 02 2.OE 02 3.3E 03 3,3E 03 2.0E 02 CO 2.0E 02 2.nE. 03 1.0E 03 3.0E 03 2.5E 05 1.0E 03 IN I.OE 05 l.nE 05 1.0E 05 1.0E 05 I.OE 05 I.OEf 05 SN 3.OE 03 1.0E 03 1.OE 02 3.0E 0 1.0fE 03 t.OE 02 sB 1.OE 00 1..ff,01 1.5E 03 1JQ,OE 01 S.0IE 00 1.5E 03 TE 4.OE 02* 1.0E. 05 I.OE 02* I.OE 01** I.OE 05 i.OE 03**1 1.5E Ot 5.0E 00 4.OE Ol I1.0E 01 5.0F O0 I.OE 03 1.109-31 TABLE A-8 (Continued)
FRESHWATER
ELEMENT XE CS BA LA FISH I .0E 2,OE* 0E 2.SE INVERYF3PATE
SALTWAE;&#xfd;TrIH T1JVEITE3RATE
PLA'NT 00 03 00 01 I .nE I PoE 2.0E I .nE 00 02 02 03 PLANT I .OE 00 5.OE 02 5.OE 02 S.E 03 1 0 OE 0i 0OE 1 0 OE 2. 5E 00 oft 0!01 I .O0E 2.5f 1 .0OE I if E 00 01 02 03 I5. nE 5. OE 00 Dl 02 03 CE 1.OE 00 1.nE 03 4*OE 03 t I.OE O b.6OE 02 b.OE 02'PR 2.5E 01 I.OE 03 5.OE 03 2.5E O I.OE 03 5.OE 03 ND 2.5E 01 I.nE, 03 S.OE 01 2.5E 01 1.OE 03 5.6c 03 PM 2.5E 01 IoE' 03 5.OE 03 2.5E 01 1.0E 03 5.OE 03 Sm 2.5E 01 I.OE 03 5.OE 03 2.5E 01 1.OE 03 S.nE 03 EU 2.5E 01 1.nE 03 S.OE 03 2.SE n1 1.0E 03 S.OE 03 GD 2.5E 01 10oE. 03 5.hE 03 2.5E 01 1,OE 03 5.OE 03 TB 2.5E o0 1.oE 03 5.OE 03 ?.SE 01 1.0E 03 5.0F 0.3 DY 2,SE 01 I.oE 03 5,OE 03 2.SE 01 I.OE 01 5.OE 03 HO 2.5E 01 1.OE 03 5.OE 03 2.SE o0 I.oE 03 5.Or n3 ER 2.5E 01 I.oE 03 5.OE n3 2,5E 01 I.OE 03 5.OE 03 TM 2.5E o0 1.hE 03 S.hE 03 2.SE 01 t.OE 03 S.OE 03 YB 2.5E 01 1.oE 03 S.OE 03 2.5E o1 I.OE 03 5.OE 03 LU 2.5E 01 1.nE 03 5.OE 03 2.SE O0 1.OE 03 5.OF 03 HF 3.3F 00 6,7E. 00 I.OE 03 2.OE 02 2.OE 01 2.OE 03 TA 3.OE 04 b.7E-02 8,OE 02 3.OE Ol 1.7E 04 I.OE 03 W 1o2E 03 1.oE 01 1.2E 03 3.0E 01 3.OE 01 3.OE 01 RE 1.2E 02 6.nE 01 2.UE 02 U.E 00 b.OF 01 2.uE 02 0S 1.OE 01 3.0E 02 2.OE 02 1.OE 01 2.OE 03 2.OE 03 rR I.OE 01 3.E' 02 2.OE 02 1.OE (1 2.OE 03 2.E 03 PT 1.OE 02 3.nE 02 2.OE 02 1.OE 02 2.OE 03 2.0E 03 AU 3,3E 01 5oE 01 3.3E 01 3.3E 01 3.3E 01 3.3E 01 HG I.OE 03 1.oE 05 I.OE 03 1.7E 01 3,3E 34 t.OE 03 TL 1,OE 04 1.;E 04 I.OE 05 1.0E 04 1,5E 04 I1.E 05 PB 1.OE 02 1.nE 02 2.OE 02 3.OE 02 1,E 03 5.OE 03 B t.SE o0 2.aE 01"**2.E 01***tS 1.5E 01 2.UE 01"** 2. a 0 1 F**PD 5.OE 02 2.nE Ou 2.OE 03 3.OE 02 51OE 03 2.OE 03 AT 1,5E 01 5,E' 00 ..OE 01 1.OE 4.0;7 03 RN 1.OE 00 I.oE 00 t.OE 00 1,OE 00 1,OE 00 I.OE 00 FR 4.OE 02 1,oE 02 8.OE 01 3,OE 01 2.OE 01 2.OE 0l RA 5.OE 01 2,'E 02 2.5E 03 S.OE 01 1,OE 02 I.OE 02 AC. 2.5E 01 1.oE 03 SOE 03 2.5E 01 I.OE 03 5.OE 0O TH 3.OE 01 5.nE 02 1.5E 03 t.OE 01 2,OE 03 3.OE 03 PA 1.IE 01 .iEE 02 1.IE 03 I.OE 01 I.OE 01 6.OE 00 U 2.OE 00 6,OE: O0 S.OE-0 1.OE 01. !.OF 01 b.6E 01 NP I.OE 01 4.nE. 02 3.OE 02 I.OE o1 1.OE 01 i. OE 00 PU 3,5E 00 I.oE 02 3.5F 02 3.OE 00 2.OE 02 I.OE 03 AM 2.5E 01 1.0E 03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 CM 2.5E 01 1.nE. 03 S.OE 03 2.5E 01 1.OE 03 5.0E 03 BK 2.5E 01 I.nE; 03 5.0E f3 ?.SE 01 1.OE 03 5.OE 03 CF 2.5E 01 I.oE'03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 ES I.OE 01 1.oE, 02 I.OE 03 I.OF 01 I.OE O0 b.OE 01 i I.OE 01 1.E 02 I.OE 03 I.OE 01 I.OE 01 bOE 01*ORNL -Private Communication
**Freke, A.M., "A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol. 13, p. 749, 1967.***Derived from data in Bowen, H.J.M., Trace Elements in Biochemistry, New York, Academic Press (1966).1.109-32 Ti is the radiological half-life of nuclide i, in days; and W is a shore-width factor that describes the geometry of the exposure.Shore-width factors were derived from experimental data (Ref. 24) and are sunanarized in Tdble A-9. They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.


The combination of Equations (A-4) and (A-5) into the general Equation (A-i) leads to(A-6) below for calculation of radiation dose from exposure to shoreline sediments.
3. L. R. Anspaugh et al, "The Dose to Man via the Fooo-Chain Transfer EResultinq fro!:m Exposure to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1i,1972.


Rapj U S*D 100 U W C T D [ -exp(-- t)] (A-6)ap i aipj Iap iw i aij U III W 110,000 --'--. QiT D .[exp(-."\t
4. B. H. Weiss et al, "Detailed Measurement of 1-13' in Air, Veqetation and 'i1[' ;.-ound Three Operating Reactor Sites," NUREG-75/021, U.S. N~uclear Regulatory Commission, Washington, D.C., March 1975.
)][l -exp(-:i t)] (A-7)F lli ipj iP 1 d. Dose from Foods Grown on Land Irrigated by Contaminated Water The equations in the following paragiaphs can be used to calculate doses from radio-nuclides in irrihjated crops. Separate expressions are presented for tritium because of its unique environmental behavior.(1) Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The rmodel used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 4).The equation for the model (for radionuclides except tritium) is presented below in slightly modified form. The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility.


Thus for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg, is given by: iv i" -exp(- '"U t e)]v Biv[I -ex 1(-'P 'itb)1]exp(-..it ) (A-8 )The de;,osition rate, di, from irrigated water is defined by the relation d'i = C iw (water deposition) (A-9)where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I is the irrigation rate, in liters/m 2/hr; i.e., volume of water (liters)sprinkled on unit area of field in 1 hour.For tritium, the equation for estimating Civ is (see Ref. 25): Cv M Ctl (A-10)For a cow grazing on fresh forage, te in Equation (A--8) is set equal to 720 hours (30 days), the typical time for a cow to return to a particular portion of the grazing site.I 1.109-33 TABLE A-9 SHORE-WIbTH
5. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!.,           To,"
FACTORS FOR USE IN EQUATIONS (A-5) and (A-6)EXPOSURE SITUATION
    USAEC Report ID0-12063, January 1968.
SHORE-WIDTH
FACTOR, W Discharge canal bank 0.1 River shoreline
0.2 Lake shore 0.3 Nominal ocean site 0.5 Tidal basin 1.0 TABLE A-10 ANIMAL CONSUMPTION
RATES I ANIMAL Milk cow Beef cattle QF FEED OR FORAGE (kg/day [wet weight])50 (pasture grass)50 (stored feed grain)QAw WATER (;./day)60 5o From Reference
4, Tables 111-B and -10.P 1 .10g-34
(2) Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water. The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref. 4) is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w): CiA = F iAECiFQF + CiAwQAw] (A-li)The second set of terms in the brackets in Equation (A-1l) can be omitted if the animal does not drink contaminated water. Values for QF and QAw are presented in-Table A-i1.Values for Biv and FiA are given in Table C-5 (see Appendix C).*The total dose Rapj from irrigated foods (excluding tritium) is given by: R a veg CiD + Uanimal Y D apj ap iv aipj ap iA aipj (A-12)If values for Civ from Equation (A-3) and CiA from Equation (A-11) are substituted in Equation (A-12): veg i[)Da [ -exp(- Ei te)] Biv[l -exp(-'it R ve dix(, hi ai iv , X Lb apj ap v ipJ YvEi i U panima -r[l -exp( '1Ei te)]ap iA ai pj OFui Y- / ~v Ei+ Biv[l -exp(-,.,itb)] (A-13)+PN i )]+ CiAwQAwj It should be noted that the two components of Equation (A-12) imply that contribu-tions from the individual vegetable and animal products have already been summed. In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)).For tritium, the concentration in animal products is given by the following equation (adapted from Reference
25): kWCv +QAwCAw (A-14)C A -+kQCA m in Since by Equation (A-IO) Cv = Cw, and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows: kC C A = 3 (w + QAw) (A-15)in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1): Ra. U ve C D animal CAD apj (A-16)Rapj : u~gvap vapj" + Uap Aaj(-6 Uve v ,,animal Da (w+ QAw) (A-17)V uea Daa apjs + Uap apj-inab Q(C--.Valus fr FA appear as Fin and Ff in Table C-5.1.109-35 REFERENCES
FOR APPENDIX A 1. "Final Environmental Statement Concerning Proposed Rule Making Action: Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion
'As Low As Practicable'
for Radioactive Material in Light-Water-Cooled Power Reactor Effluents," USAEC Report WASH-1258, Washington, D.C., July 1973.2. J. K. Soldat et al, "Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.3. "Food Consumption, Prices, and Expenditures," AER-138, U.S. Department of Agriculture, Washington, D.C., December 1974.4. J. F. Fletcher and W. L. Dotson (compilers), "HERMES -A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Peport HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.5. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration
(;.Ci/m2),'
Itemi 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.6. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-,41638, General Electric Co., Richland, W'ash., February 1956.7. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption
-Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA, Seattle, Wash., June 1971.8. "The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.9. "Draft Environmental Statement
-Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September
1974.10. "Radiological Health Handbook," USPHS, Rockville, Md., January 1970.11. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent
1311 Dose to the Thyroid," IRS-W-5, Institute for Reactor Safety, Cologne, Germiany, April 1973.12. P. S. Rohwer and S. V. Kaye, "Age-Dependent Models for Estimating Internal Dose in Feasibility Evaluations of Plowshare Events," ORNL-TM-2220, Oak Ridge, Tenn., April 1968.13. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I and 137Cs to the Atmosphere," Health Physics, Vol. 17, pp. 51-57, July 1969.14. W. S. Snyder, "Dosimetry of Internal Emitters for Population Exposure," in Population E&#xfd;x ures, CONF-741018, Proceedings of the Eighth Midyear Topical Symposium of the Health Physics Society, Knoxville, Tenn., October 1974.15. "Report of ICRP Committee II on Permissible Dose for Internal Radiation, International Commission on Radiological Protection," ICRP Publication
2, Pergamon Press, 1959.16. J. K. Soldat, "Modeling of Environmental Pathways and Radiation Doses from fluclear Facilities," USAEC Report BNWL-SA-3939, Pacific Northwest Laboratory, 1971.17. C. M. Lederer et al, Table of Isotopes, 6th Ed., John Wiley and Sons, Inc., 1967.18. S. E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, Lawrence Radiation Laboratory, October 1972.1 1. 109-36
19. J. K. Soldat, "A Statistical Study of the Habits of Fishermen Utilizing the Columbia River Below Hanford," Chapter 35 in Environmental Surveillance in the Vicinity of Nuclear Facilities, W. C. Reinig (ed.), Charles C. Thomas Publishers, 1970.20. J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.21. J. L. Nelson, "Distribution of Sediments and Associated Radionuc:lides in the Columbia River below Hanford," p. 3.80 in "Hanford Radiological Sciences Research and Development Annual Report for 1964," D. W. Pearce and J. K. Green (eds.), USAEC Report BNWL-36, Pacific Northwest Laboratories, 1965.22. G. L. Toombs and P. B. Cutler (compilers), "Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 -July 31, 1967," Oregon State Board of Health, Div. of Sanitation and Engineering, 1968.23. "Handbook of Radiological Protection, Part I: Data," prepared by a panel of the Radio-activity Advisory Committee (H. J. Dunster, Chairman), Dept. of Employment, Dept. of Health and Social Security, Ministry of Health and Social Services, Northern Ireland, Nlumber SNB 11 360079 8, Her Majesty's Stationery Office, London, England, 1971.24. L. R.. Anspaugh et al, "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.), CONF-710809, 1973.1.109-37 APPENDIX B MODELS FOR CALCULATING
DOSES FROM NOBLE GASES DISCHARGED
TO THE ATMOSPHERE
The following analytical models are used for calculating doses from exposure to gaseous effluents.


Separate models are given for air and tissue doses due to gamma and beta rays.Except for the case of noble gas doses resulting from elevated releases, all models assume submersion in an infinite cloud at the exposure point.1. Annual Gamma Air Dose from Elevated Releases of Noble Gases Slade (Ref. 1) describes the derivation of the equations for estimating annual air doses from photon emitters dispersed in the atmosphere.
6. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at             le National Reactor Testing Station, Progress Report Number Four," USAEC Report iO--126E.


The following expression can be used for calculating annual doses: D 260 D n un s I )1 ik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient.
December 1968.


Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki I [AmEmpa(Em)]/[Ekwa(Ek)] (B-2)m where A is the fraction of the disintegrations of nuclide i yielding photons m of energy E Em is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em) is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined. The summation is carried out over all photons within energy group k. Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference
7. B. H. Weiss et al, "Detailed Measurement of 1311 in Air, Vegetation and M.1ilk around Three Operating Reactor Sites," Environmental Surveillance around Nuclear Installatiorns. !nter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. 1: pp. 169-190, 1974.
2. For radionuclides not contained in Reference
2, data were obtained from Reference
3.Decay during travel from the point of release to the receptor is QD = exp(-Xir/un) (B-3)The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays. Annihilation and bremsstrahlung photon radiations are possible contributors to this compunent of the air dose.Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures. (See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors.")
1. 109-30
where Qi is the initial release rate of nuclide i, in Ci/yr, and Ai is the decay constant of nuclide i, in sec" 1 All other parameters are as previously defined.2. Annual Gamma Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents. The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.The annual average ground-level concentration of gaseous effluent species i at location (r,o)from the release point is determined from xi(ra) = 3.17 x 10 41 D(r,o) (6-4)where xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 , and[/Q')1D(r,o)
is the annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle e at the distance r from the release point,.3 in sec/mi The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year. All other parameters are as previously defined.The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then I DY(r,e) or DO(r,e) =
or DFO) (B-a)where the terms are as defined in Regulatory Position C.2.b.Table B-1 presents a tabulation of the dose factors for the noble gases and daughters of interest.3. Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas. The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue.a. Elevated Releases The annual total body dose is computed as follows: DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t] (B-6)Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed. (See Regulatory Guide 1.111.)The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.


I 1.109-40
8. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, Colo*ncno West Germany, IRS-W-6, June 1973.
TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Nuci ide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-1 31m Xe-1 33m Xe-i133 Xe-i 35m Xe-1 35 Xe-1 37 Xe-138 Ar-41 a-air* (DFB)2.88E-04 I .97E-03 1 .95E-03 1 .03E-02 2. 93E-03 1. 06E-02 7. 83E-03 1.11 E-03 I .48E-03 i .05E-03 7. 39E-04 2: 46E-03 1. 27E-02 4. 75E-03 3.28E-03 1 .46E-03 I .34E-03 9. 73E-03 2. 37E-03 1 .01 E-02 7. 29E-03 4. 76E-04 9. 94E-04 3. 06E-04 7.11 E-04 1.86E-03 1. 22E-02 4.1 3E-03 2. 69E-03 y-Air* (DFB'')1.93t-05 1.23-03 1. 72E-05 6. 17E-03 1.52E-02 1. 73E-02 1. 63E-02 1. 56E-04 3. 27E-04 3.53E-04 3. 36E-03 1. 92 E-0:3 1.51 E-0:3 9.21 E-03 9.30E-03 y-Body (DFBi)7.56E-08 1 17E-03 1.61E-05 5 92E-03 1 .47E-02 1 .66E-02 1 56E-02 9. 5E-05 2.51 E-04 2.94E-04 3.12E-03 1.81E-03 1 .42E-03 8.83E-03 8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr**'2.88E-04
= 2.88 x I0"4 1.109-41 Symbols for this equation were defined earlier in Regulatory Position C.2.c of this guide. The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.The skin dose has two components, the ganmia and beta contributions.


The skin dose rate is computed by DS(r,o) 1.11 x SFD Y(r,o) + 3.17 x 104 1 Qi(x/Q']D (r,o)DFSi
9. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 131i Doe to the Thyroid," Institute fur Reaktorsicherheit, IRS-W-5, April 1973.
(8-7)1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.The skin beta dose factors OFS were determined using the decay scheme source docu-ments cited above and the methods used in References
4, 5, and 6.b. Ground-Level Releases The annual total body dose is computed as follows: DT(r,o) = 1.11 x SF &#xfd;xi(rO)DFBi (B-8)Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.The annual skin dose is computed as follows: Ds(r,o) -1.11 x SFF Zxi(r'e)DFi
+ xii(ro)DFSi
(8-9)where D 5 (r,e) is the annual skin dose due to immersion in a semi-infinite cloud in the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra) is the airborne concentration of radionuclide i at point (r,6), in pCi/m 3.I1 I 1.109-42 REFERENCES
FOR APPENU.X B I. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-24190, 1968.2. M. J. Martin, "Radioactive Atoms, Supplement I," USAEC Report ORNL-4923, November 1973.3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-12037, 1970.4. R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.), Academic Press, New York, 1956.5. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR 73-107, 1973.6. M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol. 26, pp. 1-12, January 1974.1.109-43 APPENDIX C MODELS FOR CALCULATING
DOSES VIA ADDITIONAL
PATHWAYS FROM RADIOIODINES
AND OTHER RADIONUCLIDES
DISCHARGED
TO THE ATMOSPHERE
I. Annual External Dose from Direct Exposure to Activitv Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,o) with respect to the release point may be determined by 1.1 x 10, (rc~ Q!C i(r'c) 1 1-exp(-Xit)j (C&#xfd;-l);'-here C .is the ground plane concentration of the radionuclide i in the sector at angle -at the distance r from the release point, in pCi/m2;Qi is the annual release rate of nuclide i to the atmosphere, J'i/yr;t is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility;is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport, in mn-2; and The annual plant is then is the radiological decay constant for nuclide i, in yr-1.dose from nuclide i resulting from direct exposure to the contaminated ground D (r ,) 8760 SFCG(r,r.)DFG (C-2)where D. ii and other terms The annual is the annual dose to organ j from the ground plane concentration of nuclide i at the location (r,r,), in mrem/yr;are as defined previously in Regulatory Position C.3.a of this guide.dose to organ j is therefore D (r,o) = 8760 S C9(r,o)DFGi i F I 1 (C-3)Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7. The annual dose to all other organs is taken to be equivalent to the total body dose.Does not include noble gases or their shurt-lived daughters;
see Appendix B.1.109-45
2. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide i at the location (r,t!) -ith res-pect to the release point may be determined as Xi(r,o) 3.17 x 104QQ[X/Q']
D(r,) (C-4)where is the release rate of nuclide i to the atmosphere, in Ci/yr;xi(r,O) is the annual average ground-level concentration of nuclide i in air in the sector at angle 6 at distance r from the, release point, in pCi/m 3;[./Q']D(r,o)
is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111). This includes depletion (for radiolodines and particulates)
and radioactive decay of the plume; and 4 3.17 x 10 is the product of the number of pCi/Ci and sec/yr.The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then DDA (rO) = xi(ro)RaDFAi (C-5)iiaa ija Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.The annual dose to organ j in age group a from all nuclides in the effluent is: 4 DA (ra=R(C-6)
Dja(r,o) Ra zxi(re)DFAija
3. Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is six:ilar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.For all radioiodines and particulate radionuclides, except tritium and carbon-14, the con-centrition of nuclide i in and on vegetation at the location (r,Q) is estimated using CV(rO) di(r,o) r[l -exp('AEite)]
Biv[l -exp(-Y tb)]] exp(-1ith)
' ' + Ax PXti (C-7)See Regulatory Position C.l of tnis guide for definitions of terms.Carbon-14 is assumed to be in oxide form (CO and C0 2). The concentration of carbon-14 in vegetation is calculated by assuming that its ratio to the natural carbon in the vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 1 and 2).I 1.109-46 TABLE C-1 ADULT INHALATION
DOSE FACTORS (mreni/pCi inhaled)NUCLIDE I 3 UBE 10 bE  7N 13 QF 14 11NA 22 1 1 NA 2 a ISP 32 20CA 4L 215C U b 24CR 51 25MIN 54 25 'N 5b 26FE 55?6FE 59?7CO 57 27C0 98 27CO bo 28NI 59 28-1 65 29CU b6 30ZN 65 30ZN 694 30 N 59 3uSE 79 359R S2 35HR 93 353P 84 353R 85 374B 5h 37RB 87 37RR 58 37BR Bq 3BSR 89 3ASR 90 38SP 91 3ASR Q2 39Y 90 34Y qO1 3QY 9 1 U 39Y 91 A0IE 0.0 I .qSE-OU 2.28E-O0 6.27F-Oq 4.71E-07 1. 30F-05 1 .b9E-O6 I .b5E-0O4 3.83E-05 3.51E-05 0.0 0.0 0.0 7.b2E-06 I .a7E-Ob 0.0 A 0 0.0",0OE-0b 5.40E-05 1 .92F-I0 0.0 L.0 hE-Oh 1 .02F-09 4.23F-12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.8OE-05 I .2"E-02 7.9"E-09 8. 4 1E-1O 2,b6E-07 3.?2 E- II 5.78E-05 LIVER TfTAL 9')Y 1.3QE-07 t.34E-07 3.OhE-05 U.QbE-Oh 4.27E-07 u.27E-17 b.27E-09 h.27E-01 0.0 S.20E-oS 1.30E-n5 1.30E-05 t.69E-Ob 1.69E-0b 9.65E-Ob 6.27E-Oh 0.0 U.II3E-Ob 1.07E-04 3.11E-05 0.0 1.25E-0R+/-.95E-0b 7.A7E-07 1.55E-10 2.29E-11 3,43E-05 9.O0E-0B 3.47E-03 1.32E-06 5.bSE-08 B.39E-0O I.QBE-07 2.SQE-07 1.u4E-nb 1.8SF-Ob 1.4bE-O b.77F-07 3.92E-nh 1.PtE-06?.62E-11 I.IaE-tl 1.83F-10 7.b9E-1I 1.29E-05 S.PE-,)h 2.L5E-nq 2.2LE-I0 0.13E-12 5.61;E-13 3.83E-n7 6.0QE-O0 3.0 1.6hE-06 3.0 3.O0E-OR 0.0 3.91E-08 0.0 !.hAE-09 1.6QE-O5 7.3RE-Ob;.87E-Ob 3.?IE-0h 3.85E-B8 P.4iE-08 3.21E-OB 2.12E-O0 0.0 1.09E-Ob7.6?E-111 0.0 3.,qE-10 0.0 3.64E-11 0.0 7.01E-09 0.0 1.27E-12 0.0 1.55E-06 1 .34E-07 u.L?7E-07 8.27E-09 0.0 I 30E-05 I .69E-Ob 0.1 0.0 0.0 7.u"UE-09 0.0 0.0 0.0 0.0 0.0 0o0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0}0.0}0.0 0).0 0.0 0.0 0.,0 0.0n 0.0 0.0 0.0 0.0 0.0 0.0A 0.0 KI)NEY S.3LIE-07 0.0 4.27E-07 6.27F-OQ 0.0 1I 30E-05 1 ,bqE-06 0.0 0.0 I .OOE-0O?. 5SE-09 I I23F-06 I .b3E-10 0.0 0.0 0.0)00 0.0 0.0 5,7 8 F-10 8.b2E-0b I .Q48E-09 5.27E-12 5.bQE-07 0.0 0.0 0.0 0.0 0,0 0.0 0.0 6,0 0.0 0.0 0.0 0.0 0.0 1 I 34E-07?.23E-Ou u.27F-07 6 *27E-O9 n.0 ,1 I E-n5 1 69F-Ob 0.0 0=0 S. OE-06 1 .75E-06 1 .18E-06;o.RE-05 1 .27F-04 1 .16bF-04i 7,L7E-04 A,21E-06?.23E-05 7.01E-n7*.L1E-07 I .OE-04 2,39E-Ob 1.15E-07 Li. LiE-OS n100 0.O 0.0 0.0 0.0 0.0 0.0 0.0 I .75E-04 I .20E-03 u.92F-Ob 2.06E-Ob 2.12E-05 2.L1E-07 2.1 3E-0 4 GI-LLI 1 3LiE-0 7 1 .b7E-05 Li.*27E-07
*.27F-09 9.24E-09 1 , 30E -09 1 .bqE-Ob 1
* 08E-05 2.AbE-07 3.23E-05 uL 5 I E-07 9.b7E-Ob 2.53E-06"7.SuF-Ob 2. 3SE-05 3.93E-06 I I ;3L-05 I. ,3E-OS 3 ,* .':6, -05 b. 1 IE-07 1 .67F-06 I , 5E -0O h. 12E-06 b.bBF-06 I .71E-05 2,0* E-09 3.33E-Ob I .30F-0b 2.qOE-08 2.05E-1 3 0.0 2.08E-O0 2.88E-07 4,i 11E-1I 0,0 9.02E-05 2,59E-05 5.3RE-Ob 6.3PE-05 1 .6bE-I 0 4.81E-OS Note: 0.0 means insufficient data or that the dose factor is <].OE-20.1.109-47 TABLE C-1 (Continued)
NUCLIDE BONE LIVER TOTAL BODY THYROID KIDNEY lltlN; .I-i.LI 39Y 92 1.2qE-09 0.0 3.77E-11 0,0 0.0 1.bE-0h QIqE-ob 39Y 93 1.19E-08 0.0 3.26E-10 n00 n.0 b.n7E-nh 5.,7f.-05 40ZR q3 5,22E-05 292E-o06 1,37E-O 0,0 .llF-0-5 '113E-05 I1.5F-06 UDZR 95 t.34F-05 4,30E-06 2.91E-0h m.0 b.77E-0h 2.22F-ou 1.4L-0c)40ZR 97 1.21E-OB 2.U5E-09 I.13E-nQ 0,0 3.71E-09 4.SE-0b b.5UF-05 41NB 934 3 3.lOE-05 1.0IF-n5 2.AqE-n6 A.0 1.IE -0S 3.1IF-n 2,;BEE-0b.


UINB 95 1,7kF-0 5.2hE-07 0.0 9.b7E-n7 b.12F-05 I.30E-65 41N8 97 2.783E-11
10. F. 0. Hoffman,   "A Reassessment of the Parameters Used To Predict the Environmental Trans*ort of 1311 from Air to Milk," Institute fur Reaktorsicherheit,         IRS-W-13,   April 1975.
7.03E-12 P.56E-I? 0.0 5. 1E-12 .oO F-07 1.2F-0H u24n 93 0.0 1.17F-nb 3.17E-1; q.n .S55E-07 5.11E-05 1.7qF--t U2MD Q9 0.0 1.51E-0B 2.87E-19 0,n ;.&deg;UE-nB 1,1 AE-05 i.10-05 431C 994 0.n 3.64E-13 4 .h3E-1P 0.0 5.52E-12 P.SbE-n9 S.20F-n/437C 9q 0.0 U.64F-0R I.37E-04 0.0 5.95E-07 l.nIE-04 7.SuEE-0b Q3TC 101 0.0 7.52E-15 7.38E-14 n0.0 1.35F-13 U.9qE-ns 0.0 44RU tn3 l.91E-07 0.0. 9.23E-fl 0.0 7.2qCE-07
6.32E-05 1.S -o..4uRU 105 9,ASF-11 0.0 3.RqE-l1 0.0 1.27E-10 1.3AE-0b b.0?E-flb'JLRU 106 8.64E-0b 0.0 I.0qE-06 0.0 1.67E-05 1.16E-03 1.i 1 E-oll 45RH 105 q.24F-10 b.73F-10 4.43E-10 n.0 2.hE-nQ 2.'41E-ntb
1.01)E-05 46PD 107 0.0 q,27F-08 5,87E-09 0.0 b.57E-07 Q.ugE-Ob 7.OhE-(,7 46PD 109 0.0 4.b3F-10 1.16E-itf n.0 ?.35E-og 1.85E-Ob 1.52i-fS 47AG 1I104 1.335E-06 I.25E-06 7.a3E-07 n.( 2.3bF6-06
5.OE-04 3..763 -05 47AG I1 I ,425E-08 I ./BE-08i A.8TE-Oq o,0 5. 7uE-P h 2. 34E-n)5 P.l79F-np I URCO 113M n.0 1.54E-0O '.q7E-06 0.0 1.71E-n4 2.06F-0U 1.99E-n5 48CO 115M 0.0 2.ab4-05 7.qSE-01 0.n 1.9RE-05 1.7bE-Ou .8OE-05 50SN 123 3.02E-05 6.66E-07 9.P2E-07 5.6bE-07 0.o P.89E-00 3 .92 -n5i 50SN 125 1 .IhF-0b 3.13E-08 7.03E-06 2.59E-03 0.0 7,u2E-05 .MIE-05 50SN 12b 1.58E-04 J.I BE-06 6.OOE-06 1,P3E-0b 0.n I 17E-n 3 1.59L-0P SISB 124 3.QOF-06 7.3bE-08 155E-06 9.44E-09 0.0 3.1OF-0u 9.0OBF-nl9
51S5 125 8.2bE-06 B.91E-OR I6bbE-06 7.34F-09 P.0 ?.75F-04 I.?bhf-05 51SB t2b .O50F-07 9.13E-09 1.62E-07 2.75E-0 n 0.0 1.5RF-n5 b. OIE-0q 515 127 3.30E-08 7.22E-i0 1.?7E-09 3.q7E-10 0.0 ?.nSE-05 3.771F-05 52TE 12591 4.27E-07 I.98E-n7 S.84E-0A I.31E-07 1.55F-nb 3.92F-05 8.MSF-Ob 52TE i274 1.58E-06 7.02E-07 1.9hE-07 4.11F-07 5.72E-Ob 1.?OF-OQ 1. 7F-O0 52TE 127 1.75E-10 -.03E-.11 3,87E-11 1.3.E-10 h.17F-j0 7.17E-oh 52TE 129M 1.22F-0b 5.64E-o7 1.9RE-77 4.30E-07 : .S7,-0b 5E6 11SE-Oa u.7qE -01 52TE 129 b.22F-12 2.99E-12 t.5SE-12 4.87E-12 2.3L3E-11 .a2F-07 t.9bF-0 8 52TE 1314 B .74E-09 5.SE-0q 3,63E-09 BBF-01 3. bE-1A 1.82F--05 b, .9SF-0 52TE 131 1t39E-12 7.44E-13 u .'J9E-13 1.17E-1F 5.ubE-12 1.7 F-07 2. 4uE-0q 52TE 132 3.25F-07 2.b9E-Of 2.0?E-08 ?.37E-0 I.S3E-n7 3,60F-05 6 .3 7E-f5 52TE 1I33M 7,24E-12 5.b0E-12 7.14E-12 6,27E-12 3.7TF-I1 5.51E-07 3.u5F-AQ 527E 134 3.84E-12 3.22E-12 1.57E-12 3.t)U E-12 2.1BE-11 Z.3UE-07 3.b9Emog 531 129 2.'49E-0b
2.1IE-O6 6.91E-O 5.55F-01 14.514E-0b o.l 2.2E-07 S31 130 5.73E-07 1.68E-Ob 6..hF-07 2.18F-04 2.blE-m6 0.0 q.hlF-07 531 131 3.ISE-O6 4.47E-06 2.56F-0b 1.0J9E-03
7.b7F-Oh 0.0 7.8hF-O7 531 132 1.45E-07 U.07E-07 1.45E-07 5.JBE-05 b.UqF-07 0.n 5.18F-0R E 1.109-48 TABLE C-i (Continued)
NUCLIDE 531 531 531 55CS 55CS 55CS 55CS 55CS 55CS 5695 S6BA SbBA 57LA 57LA 57LA SRCE 5FCE 58CE 5QPP 51PR bO lO blPm b61 P.blPM b2SH bSM b3EU 63EU b3EU 6ST9 b7 1O 7LJ, 7iU 82PR R391 BiPo 133 134 135 135 j36 137 139 139 I40 1Ul 1 2 1UO IL I 7 149 151 151 153 15?151 155 15h 160 Tk-T 155 917 210 210 210 BONE I .0BE-O0 5.ObE-08 3.30E-07 I
* bOE-OR U .hlF-05 1 ,UbF-05 4.8QE-06 5.08F-05 L4. IIE-0b 2.50F-08 1.17F-I 0 4.,86.F-0B
5 .3 UF- 10 9 I F25 -11 2.49F-02 2. 3 5F -083 U3 2E -Ou I I.7E-06 3. 7bF- 1?6.59E-07 8.37F-05 9.82gE-Ob 3.84E-07 3. 17F-O ,5* F-0q.759F-05 I .70E-08 2. 3b8F-0d 7 IJOE-0U I *OIF-05 I .79E-Ob?. 21F-OS 3 .3 7E -O0Q 6.2 IE-05 I .9SF-07 I , ObF-OQ n.0 3.97F-O0 LI VER I 56'F-Ob 2. 16E-07 R. ?&#xa3;E-M7 S.20E-D8 1 .06E-On I .29E-o5 I .83F-nS 7. 77F-05 7. 77E.-08 3.53F-n8 9. 32F -I a I E 15FO 63 3 8E- 15 9,LIE-i5 2. 1 7E-OA 1 bhF -In ,.88E-1 I I ,bQE-Ob 1 .72E-n9 1.79F-04I 4.6QE-07 S.S96E-1 2 7.b2E-07 7.87E-nb 2.5UE-16 S. 37E-o8 U.87E-09 I.42F-09 1 U.RE-05 1. iF-08 5.UOE-05 9. IOE-O5 I u3SF-nS I uSE-nb 0.0 I .OSE-n0i 2o0TE-ng 6. U7E-08 3,B5E-10 6.72E-03 I .59F-O0 9.bOE-01 5.h7E-07 7.70E- n 3.?2E-07 I .72E-0A 9.11IE-35 6.AOE-lh 1 .3 F-05 5. 36E-05 U .OE-31 3.LE-t 2 3.21F-07!1.2nE-I 3 A. 7E-1 3 5S. 71E-LnQ 2.7 1E-1 1 9.bSE-1 2 1 .QIE-07 I I* E-IQ 2.30F-05 5. 7c)E-OR I .I E-1 3 Li.S6E-ag 1 * ~ I AE -0 L6 I. QfE-Oh 3.2nE-na I .'99F-00 7.21E-10 1.SSE-Ob I O4E-09.1E7h-05 6. LRE-OS 9,21E-Oh 2.UOE-n7 2. 75E-1b q.00F-05?.1 7E-t 0 6.81E-09 3.1 OE-lO0 8A.7E-Ou I .3?E-07 Q.58E-05 TOTAL BODY THYROID 3.hbE-OLA 2.97E-05 I .1 7 F -OU 0.0 0.0 0.0 0.0 0.0 0.0.0 0).0 o.n 0.0 0,.0 0,0 0,0 0 .0 o~t 0.0 0.0 0,0 0.0 0(.0 ,0O 0.0 0.0 0l,0 0.0 0.0 0.0 h,0 0.0 0.0 0.0 KInNEY 3,*25E-O6 3.2UE-07.1 F-Ob I .07E-05 2.'1IF-05 h.Olr-nR 3705F-05 7. li3F-Ili 2.0QE-nq 2. 7E-IS 0l.0 0.0 0.0 7 .*7 .0 E-1A9.570F-07 R.55F-l 3 1 .5AQE-0S 3. 5F -0 I .f6E-17 9. IQE-O5?. 55F-nQ I .56E-05'4.* 9E-n9 3. 35E-04 La .3bE-~IL 5. 59E-05 9. 95F-07 ,I E-Oh t,57E-ou n,0 0.0 0,0 2., 1 2E-02 1 92F-05 2.-75E-03 LUNG GI-LLI 0.0 I.09E-06 0.0 0.0 bSbF-U7?.94F-OQ 7.,2E-o9 I.22E-05 I.30E-Otf 1.57E-06 2.11F-07 9. UE-Ob I.05b-0h S.07F-09 2.33F-15 ,;).9 E-09 0.0 u.70E-07 1.12E-07 1.5QE-nu 2.73L-05?.112E-07 I.115F-17 l.UqF-07 0.0 1.70E-)5 5,.73E-nE 1.SSE-Ob 7.31E-0e 7.02F-07 2.ULF-07 u.52F-n5 1.SoE-05 9.LRF-=Ob
2.USE-05 4.73F-Au 1.02F-0O1 i.51F-3S 2.50F-05 1.27F-07 2.b6)-18 2.76F-05 ?.IhE-09 5.blE-n5 5.S4E-06 2.l tjF -nU i M. 18 F- 0 3.Q1E-05 5.8OE-05 7.?2E-Ob 2.50E-05 3.Q4E-Ob 2.OOE-05 J.LbE-n5 3.25E-06 u.1SE-Ob ..58F-0S 3.u3E-n4 1,59k-os 5.P.5E-0L
3,'IOE-05 1.47F-05 5.95F-n6 9.57E-05 L.SOE-05 1.Q2E-04 2.68E-05 3.q -OL 1.59F-05 1.72F-06 2.53E-07 5.57E-05 1.07F-05 3.b3E-Ob 1.94E-O5;.63E-02 3.b6E-O5 1.11F-03 2,qSE-05 3,s1E-n2 4.19E-05 1.109-49 TABLE C-1 (Continued)
NUCLIDE 88RA 223 88RA 224 68RA 225 88RA 22b 8BRA 22A 89AC 225 BqAC 227 9QTH 227 90TH 228 90TH 229 90TH 230 90TH 232 90TH 234 91PA 231 91PA 233 92U 232 92U 233 92U 23U 920 235 q2U 236 92U 237 92U 238 934P 237 93NP 23B 93NP 239 Q9PU 238 94PU 239 94PU 240 9PIJ 2ul 94tPU 242 94PU 240 95AM 201 95AM 2424 95AM 243 96CM P42 96CM 203 96CM 24, 9bCM 205 9bCM 246 96CM 247 96CM 208 98CF 252 BONE I .80F-0O 1.98F-O5 3,00E-0O 1.25E-01 4,41E-02 4.23E-0a 2.30F 00 2. 1 7F-0O 2.00F-Ol 8.88E 00 2,2QE 00 I .99E 00 I .63E-Ob S.n08 00 1.21F-06 5. I 0E-02 I .09&#xa3;-02 1. O* E-02 I. OOF -02 1 .OOE-02 3.67&#xa3;E-08 9.58E-03 1.69E 00 2.96E-07 2.87E-O0?.69E 00 3,05E 00 3.04E 00 6.0SF-02 2.89&#xa3; 00 3.45E 00 9.93E-O0 1.02F n0 9.qUE-01 I , I UF-02 7.8SE-Ol 5.QOE-O1 1.?bE 00 1.25E 00 1.22E 00 I.01E 01 7.33E-01 LIVER 2.77E-07 4.7BE-08 3.56F-07 2.39E-06 1.23E-Ob 5.82E-nO 3.05E-0l 3.92E-06 3.39E-03 I .33E-01 1.31E-01 1.12E-01 9.56E-08 I .91E-01 2.4 2E-07 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,47E-01 7.99E-09 2.82E-09 3.73E-01 4,19&#xa3;-nl 4. 19E-01 3.28E-03 4.76E-01 3.46F-01 3.46E-01 3.40E-O0 I .18F-02 2.97E-O0 2.5IE-01 3.59E-01 3,59QE-O 3.53E-at 2.91E 00 0.0 TOTAL BODY 3.bOE-05 3.96E-06 9.13E-02 4.76E-02 2. 8OE-O5 1 .36E-01 6.25E-06 6.77E-03 4.36E-O0 6.36E-2?5.43E-O2 4.70E-08 I.9SE-OI 2.09E-07 3.66E-03 6.5QE-Ou 6,06E-Ou 6.07E-Ou 6.20E-00 9.77E-09 5.67E-O0 b.87E-OP 1.61E-n9 1.55E-09 6.6hE-&#xa3;O0 7,53E-0?7.53E-0?1.29E-03 7,1 7E--2 B,5'4E-02 b6,7E-02 B.73E-02 hf.uE-n2 7.50E-04 4.61E-02 3.51E-0?7.1 &#xa3;E-f2 7.03E-a?5.7qE-01 i .83E-02 THYROID n.0 0.0 0,0 040 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 nO, 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.0 0.0 0).0 0.0 KIDNEY 7.8SE-nb 1.35E-Ob I .OIE-05 6.77E-05 3.QSE-0O b .3&#xa3; -05 9,9 2E-02 2.22E-05 I. 89E-02 b .52E- I-6. (10E-0 1 5. *17E -01 5 *, L 1 E-0 7 0.0 9 .1 SE -07 5.56E-03 2.5E-03 2 ,. -E -03 2. 3E-n3 2, 3Sq-03 1.51&#xa3;-fl?2. 1AF-03 5. 10E-O1 2. 7?&#xa3;-09 8. 75E -flQ 3.?0F-01 3. 20&#xa3;-0 I 5.93E-03 3,OSE-nt 3.64E-01 5. OIE-OI O.BbE-01 3.SOE-03 2.15E-01 1,64E-01 3.33E-ni 3.33E-01 3.28E-01 2.70E 00 0.0 2.5SE-02 q,78-03 2.92E-02 1 .17E-01 1. 61E-01I 2,21E-02 2.q F-0I 3. 78E-02 1.DIO E (in 3.50E 00 b.22E-01 5.31E-01 I.89E&#xa3;-O 5.75E-OP 3.52E-05 2..23E-01 5.33E-02 S.?2E-02.QOF-02 5.01E-02 t.02F-0S 0.5FF-02 5.22F-02 1 .0E-05 u. 71F-Ob I .76F-01 I .b7E-0 I h7F-01 I .52F-O0 I sq9E-01 I .89F-01 5.86F-02 2.45E-02 5.bSE-n2 3.74E-02 6.32F-02 6.07F-02 5.86&#xa3;-n?5.97E-02 5.86E-02 0.83E-al 1.56E-0l GI-I.1.1 2.B4E-O0 3.0 E-Ou 2.71E-Oa 2.94E-0O 5.00&#xa3;-05 2.52E-04 O.92E-05 3. 3uE.-Oo 3.17E-04 3. 1 7E-OU 3. 73E-05 7.9'jF-05 7.03F-05 7
* 0 3-OSi 1.02&#xa3;-05 0*lbE-05 3.89E-05 S.lf-05 0
* 80&#xa3;-05 3.57E-05 I, 2OE -nr I .ASE-O0 4.92E-O5 2.13F-05 0 .52&#xa3;F -OIi 0.52F-Os.20F -05 8. SE-07.o *05-OS t.03E -05.6bOE-09 5. 7qE-05 b.03E.-05 4.64E-05'4 *. 6E -05 0. 36F-05 0.291-O', 5.b E-OS S. 091-O0 I .78&#xa3; -00 I 4 1.109-50
TABLE C-2 TEENAGER INHALATION
DOSE FACTORS (mrem/pCi inhaled)NUCL IDE I H 3 bC 14l 11!INA 22 27C0 55 27CO bO 38Sp B9 38SR 90 3c9Y 90 39Y 01'jOZR 95 JJINB 95 U'JRU 103 44RJ;U 106 S0SN' 123 52TE 1254 52TE 127 52TE t294 52TE 132 531 129 531 131 531 133 55CS 13Ll SSCS t37 56BA 1Ji0 57LA ILJO 5ACE 1'J1 58CE I1U U b3EUI ISLI QU 232 9?U 234I 9UPU 234~QLIPU 239 9Lipu 2U0 9LJPU 24I1 95AM 24J1 96CM 24I2 9CM 244L A ONE 0.0 5.66E-07 I *7bF-OS 0.0 0).0 4,.84E-06 I *.48E-03 I .41E-.08 b. 72E06b 1.*3bE -Ob I .70E-07 2.04OLE-08 I .05F-0b 5.09E-08 I b62E- II I .49E-07 3. 75F -09 3.53E-06 4I.21IE-06 I 54~E-06 6
* LE-05 8. 02E-05 6,62E-07 I .79E-09 2.84IE-07 5. 2uF-05 9.195E-05 6. lL4E-03 I .25F-03 3.22F-01 3.67E-01I 3.66,E-0 1 I .29E-04I I .20E-01 I .35E-03 b.99E-02 LIVER TOlTAL 8B1)Y 1.06E-07 1.OhE-07 5.66E-07 S.bbE-07 1.76E-05 1.76E-05 2.20E-08 2.93E-OR 1.55E-07 2.OhE-07 a3.0 1 .39E-07 0.0 9.01JE-05 0.0 3.79E-10 0 .0 1.80E-07!J.5LLE-07
3.17E-07 1.03E-07 9.7AIE-09 0.0 Q.ISF-flQ 0.0 1.3?E-07 7.6RE-08 I.1ISE-n7 2.32F-D8 b.QIE-09 7.30E-12 4I.02E-12 7.05F-08 2.40OE-08 3.-OOE-09
2.2QE-09 2.9UE.06 9.81E-06 5.90E-0b 3.SRE-06 2.58E-06 7.93E-n7 1.38F-04I
6.80E-05 1.03F-04I
3.79E-fl9 6.06E-10 LI.?7E-ng 4,.72E-10
l.b7E-10 1.90E-07 2.1RE-DA 2,17E-05 2,80E-06 I.02E-o5 &#xfd;.07E-06 0.0 LJ.37E-OLI
0.0 Z.72E-nS 3.4I3E-02
7.9FLE-03 5.OOF-02 9.06E-03 5.OLIF-n2 Q.13E-03 I.BLIE-0S
3.26E-Oh 4l.11F-02
7.79E-01 1.40OE-03
8,97E-0';2.99E-02 4I.16E-03 THYROID I .06F-01 5.bbE-07 i .7bE-05 A,(0.0 0.0 0.0 0.n 0.0 0,0 0.0 S.* 0 0.0 6.1 5E-OA 1 USE-OB 1.34E-1 1 i.FBE-05 2.54E-09 7.32E-03 I .7E-03 4.79E-04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0,0 0o0 K I 3NEY LUNG 1 .O06F-07 S.b6E-07 I .76F-05 I .71E-OLI I .07F-03 (USE 3.13E-0LJ?.n7F-03 0.0 PMULT 3.57E-04I 3.*20E-04I
9.96E-05 DOSE 4.'I9E-05?.05E-nS LI 693E-0LI FACTOR) 6.70E-05 I .33E-06 21.5LF-0LI
5.6b7E-05 0.0 0).0 0.0 I .ROE-05 1 .47F-05 P. 53F-OLI 2. 70E-05 7. 29E05 I .72E-03 9.29E-04 3.84IE-01 9.00OE-02 3.1ILI-01 2.98E-01 3.01E-01 I Q92E-04I I .0 1E -0 1 6.LI7E02 1 OSE-01 U 1-LI. I I .ObE -07 5.06eE-07 I .'J LE-Oh 1.1 I F-05 2.Q4lE-0'5
4.4 L2E -05 9.* bF-05 h. 79L-0'5 LI
* 7F -05 I .6bE -05 1.1 IOE -05 I .IRF-05 1. 16L-04I 3.91E-05 8.95E-06 I .01IE-09 LI.80E-05 b.b lE-OS 2. 16F-07 7.45FE-07 1 .25E-06 I .12E-06 9.bOE-07 5.981E-05 I .4I2E-05 1 .OSE-04*3.UIE-05 4,. IbE-OS 3.F81E-05's.52E-05'4. 13E-05 4,. 13E-05 7.94LE-08 LI.LJLE-05 LI.60E-05 N4ote: 0.0 means insufficient data or that the dose factor is <1.OE-20.1.109-51 TABLE C-3 CHILD INHALATION
DOSE FACTORS.(mrem/pCi inhaled)NUCLIDE IH 3 6C i1 IINA ?2 27C0 5a 27C0 60 3ASR 89 38SR qO 39Y 90 39Y QI 4OZR 95 LINR q 5 44RU 103 44RU lOb 503N 123 52TE 125m 52TE 127 52TE 12QM 52TE 132 531 129 531 131 531 133 55CS 134 55CS 137 SbBA iaO 57LA I4O S8CE 14l 58CE 144 b3EU IS1 92U 232 92U 234 qiPU 238 94PU 239 94PU 20 94PU 241 95AM 241 96CM 242 96CM 244 BONE 0.0 1 .69E-06 4,42F-05 0.0 I..45E-05 4.A3F-03 9.87E-08 2.01E-05 3.8IE-06 06,0E-07 5.AUE-08 3.12F-O0 I OUE-OS I .52E-07 4.83E-I I a.t4UE-07 1.. 08E-08 I, 05E -05 I .?3E-05 4.53E-Ob 1.68E-O0 2.34E-O4 1 ,93E-Ob 5.20F-09 8.47E-07 1.57E-0U 2.87E-04 1 .83F-02 3.73E'03 9,62E-0I I.IOE 00 1 .09E 00 3.84E-o0 3.57E-01 4.,05F-03 2. 09E-0I LIVER TOTAL BODY 2.03E-07 2.03E-n7 1.69E-06 1.69E-06 4.42E-05 4u2E-05 0.t1F-n8 7.?3E-08 2.qOF-07 5.07E-n7 0.0 4.16E-07 0.0 2.70E-14 0.0 2.65E-OQ 0.0 5.36E-07 9.86E-A7 8.05E-07 1.96E-07 t.dLE-07 0.0 2.36E-OB 0.0 3.89E-07 1.74E-07 3.'3E-n7 5.25E-08 2.0hE-08 1.bSF-11 1.20E-11 1.58E-07 7.03E-08 6.08E-0 .91E-09 5.4OE-Ob 2.86E-fS 1&deg;25E-05 Q.a7E-0h 5,S3E-06 2T17E-06 2.b9E-O0 6,02E-05 2.16E-o' 3.38E-05 I,26E-nq 1.laE-07 9.63E-10 L.3uE-In.24E-n7 6.30E-08'I,9tE-oS
8,37E-06 2.IPE-05 2.OqE-n5 0.0 1.31E-n3 0.0 2.31E-04 I.OOE-01 2.38E-02 1.13E-01 2.71E-0?I.I'4E-O.


2,73E-0?.16E-n5 9.73E-06 9.31E-02 2.33E-02 3,17E-03 2.bRE-0O, b.77E-02 1.24E-02 T-4YR310?.03E-07 I ,69E-06 a. a2E-05 0.0 0.0 0.0 0.0 0.000 0.0 0.0 0.0 I .9RE-07 4.35E-05 U.,IE-l 1 1 .4bE-07 7.24E-04 2.14E-02 u.t6E-03 I
11. C. A. Pelletier and P. G. Voilleque,   "The Behavior of 137Cs and Other Fallout RadiontucI'det.
* 36F -03 0.0&deg;00 0.0 0.0 0.0 0.0 0.0 0.n 0.0)0.0r 0.0 0.0 0.0 K I )NFY LJN.G 2.03E-07 I b69E-06", '2E-05 (USE 1.67E-03_____ .0E-Oa*.OOE-n3 7.26E-05 ADULT 6190E-OI 5. 72F-O0 DOSE I 1.71E-04i 3.93F-03 FACTOR) 9.46E-04 I .30F- 04 2.5E-Ob a.T7F-OU I .03E-O0 0.1.0 0.0 3.21E-n5 2.71F-05 0.69QE-0 U*Q2E-05 I. 39E-n4 3. 32F-n3 I .67F-03 7,"J3E-nl I .70F-01 5.87E-01 5.5bF-0I 5.61E-ni 3.6lE-0OJ I .QSF-OI.2 ? E_- n_1-_?,02E-01 GI-LLI 2. 03R -07 I .bqE-06 9. -0o 2.H3F-0%I.56F -05 Q1 1 ,EF-Ob..23E-OS LI .* _-O.I S2E -05 lI. 1 I- -05 7. 13 7-07.10 3E-06 I. 53F -05 q.22E -OS)b.52(- -05 2.168-07 7. I 7E-05 I .54E-O0 I .08E-Ob , 22E-')7 2.. 28E-01 I.flE-05 I .07E-OP/J. 57F -05 3.71F -05 a. V2E-is Li, LE -05 8. 1bE-OF a. 73r-05 6 0,0 Note: 0.0 means insufficient data or that the dose factor is <1.0E-20.1.109-52 TABLE C-4 INFANT INHALATION
DOSE FACTORS (irirem/pCi inhaled)NUCLIDE bC 1" IINA 22 27C0 58 27C0 b0 38SQ Q.38SR QO 39Y 00 39Y 91 4nZR 05 4INB 05 4JRUi 103 44RU 106 50SN 123 52TE 1254 52TE i27 52TE 1294 S2TE 132 531 129 531 131 53! 133 55CS 13u 55CS 13 7 5b8. !LAO 57LA 1LO 5BCE 1l1 58CE IlUq b3EU 154 92U P32 92U 234 quPU 238 9gPU 239 gapu PLao 94PU 2U1 95AM 241 96CM 2u2 obC4 2U4 S O:N F 0.0 3.6OE-O0 7.53E-05 0.0 0.0 3.01E-05 9.4FE-03 2.lOF-07 UL27E-05 7.7uE-O6 9. I6E-07 I .21E-07 6.b5E-O6 2.22E-05 3.2uE-07 1.03E-I0 Q ,UuF-07 2,25E-08 2.23E-05 2.59F-05 9.5hE-06 3. 43E-OL".90E-04.0 7 7E-06 1 .09E-08 i .80E-Ob 3. 3IF-O4 5.99E-0O 3.q1E-02 7.94qE-03 2.05E 00 2.33E 00 2.33E 00 5. IBE--04 7.61E-01 9,62E-03 4.L45E-0 1 LIVER 3. 07E -n7 3.6OF-06 7.53E-05 8. 39E-OR!. OOE-07 0.0 0.0 0,0 1 .9SE-06 4. 11E-07 0.0 0.0 U.6IE-n7 I .39E-07 w. 31E-t II 4i 1 UE-07 I. I2E-08 I .b2E-05 3.n5E-05 I .38E-05 5.8QE-O0 5.22E-04 S05E-09 2.29E-3q 1. IIE-0b I 30E-04 4.95E-n5 0.0 0.0 2.66E-01 3.O0E-01 3.02E-01 I. I OE--04 2.47E-l1 8.40E-03 I. 70F-01 TDIAL 3J)Y 3.07E-07 3.bOE-06 7.53E-05 I .2nE-07 8.38E-07 5,89E-07 5.7hE-0A 5.65E-09 191 LE-OB 2.ULiE-07 4 .! 9E -n 8.16E-07 7.30E-07 u.UOE-08 2.56E-1 I 1.47E-07 I  5.A2E-05 I .70E-35 LA. I QE-Oh 5.23E-05 3.15E-n5 2.11IE-07E-1 0 1.2QE-17 I .7AE-05 3.72E-05 2.71E-03 0.91E-14 S.OSE-92 5.77E-02 5.81E-0?2.07E-05 L.96E-02 5.71 F- 14 3.07E-07 3.SAE-06 7.53E-0 5 0.0 0.0 0.0 0.0 0.00.0 0,0 LA. IlE-07 0 .O E-1 .0 9F-0 7 I .OOE-10 3. 63F -0 7 I .70E-05 5.21E-02 I .OIE-02 3. 33E-03 0.0 0.0 0.0 0.0 n.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 K I NE Y LU N C 3.07E-07 3.bOE-Ob 7.S3F-05 h.28F-O0 (USE 3.QRE-03 I .h5F-n3 I .09E-02 AU. Q8E-04 ADULT' , 88E-03 I .2QE-03 DOSE 3.JiF-OU D. OE -04 I .07E-02 2.SBF-A3 FACTOR) 3.54E-O4 7. 03F-00b I .31E-03 2.Q8E-04 0.0 0.0 0.0 7.22E-05 5.7%E-05 ,I 17E-03 1 .21E-04l 3.7AE-O0 9.06E-03 3. 99E-03 2.02E 00*.7LE-fl I .51E 00 I .43E 00 I .45E 00 q.9OE-nf S.32E-01 3,UIF-01 5.51E-01 GI-LLI 3.07F-n7 3.OF-Oh 1 .22L-06 8.67F-06 2.  4.6bE-9.89F- *5. 1 2E -05 I .01E-05 8. b7E-Ob 11. I SE-05 1.2bE-04 4.28F-05 9.71F-Oh I .87E-05 5.23F-05 6. b8E-05 2M2E-07 7b6hE-07 I .S3E-0b 9.80E-07 9.45E-07 2.77E-06 6.43F-05 1 .4l F-05 I 15E-OLA 3.73E-05 L.SSE-05 A. 16E-05 4.qbE-05 U.51L-05 A.51E-05 8,.bE-08 U.86E-05 5.29E-05 5.03E-05 0.n 2.65E-02 0.0 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.1 .109-53 This yields C V 4 (ro) = 3.17 x 107 Q7 4[x/Q'](r,)
0.11/0.16 U= 2.2 x 107 Qi 4[x/Q'J(r,O) (C-8)where C v 4 (r,O) is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;!Q14 is the annual release rate of carbon-14, in Ci/yr;0.11 is the fraction of total plant mass that is natural carbon, dimensionless;
0.16 is equal to the concentration of natural carbon in the atmosphere, in g/M 3 and 3.17 x 107 is equal to (1.0 x 1012 pCi/Ci)(l.0
x 103 g/kg)/(3.15 x 107 sec/yr).The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.


Using the method described in Reference
on a Michigan Dairy Farm," Health Phys.,   Vol. 21, p. 777,   1971.
3, the NRC staff derived the following equation: CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H)
= 1.2 x 10 7 Qi[X/Q'](re)/H (c-9)where Cv(r,o) is the concentration of tritium in vegetation grown at location (r,e), pCi/kg;H is the absolute humidity of the atmosphere at location (r,o) in g/m3 Q&#xfd; is the annual release rate of tritium, Ci/yr;0.5 is the ratio of tritium concentration in atmospheric water to tritium con--centration in plant water, dimensionless;
and 0.75 is the fraction of total plant mass that is water, dimensionless.


The deposition rate from the plume is defined by: dC(r.o) = 1.1 x 10 8 ai(r,e)Qj (C-10)where 6 1 (r,O) is the relative deposition of nuclide i, considering depletion and decay in transit to location (r,O), in m" 2 (see Regulatory Guide 1.111) and 1.1 x 108 is the number of pCi per Ci (1012) divided by the number of hours per year (8760).For radioiodines the model considers only the elemental fraction of the effluent.
12. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption
                                                                14 4    14 4 of Cow's Milk as Critical Pathways for 1 3 7 Cs, 5 4 Mn and       Ce-      Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.


The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Reference
13. R. J. Garner, "Transfer of Radioactive Materials from the "i,T,'restrial Environ;nent to Animals and Man," CRC Press, Cleveland, Ohio, 1972.
4). With this consideration included, Equation (C-l0) for radioiodine becumes: I 1.109-54
15.5 x 107 Si(r,6)Q.(C-1l)and Q! is the total (elemental and nonelemental)
radioiodine emission rate. The retention ictor r for elemental radioiodine on vegetation should be taken as unity, since the experimental mea-surement (References
5, 6, and 7) techniques used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (References
8, 9, and 10).For radioiodines, the deposition model is based only on the dry deposition process. Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con-sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).For particulates, the deposition model considers both wet and dry deposition.


There is also a retention factor (r of Equation (C-7)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (References
14. F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol. 17, pp. 565-9, 1969.
11 and 12). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.


a. Parameters for Calculating Nuclides Concentrations in Veqetation Consumed by Man When the radionuclide concentration in vegetation directly ingested by man is estimated using Equation (C-7), the following parameters are used: Parameter Value Yv (vegetation yield) 2.0 kg/mi 2 te (exposure time to plume) 60 days th (holdup after harvest) 1 day for garden-fresh leafy vegetables
15. R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.),
60 days for stored vegetables tb (soil exposure time) 15 years (midpoint of reactor operating lifetime)All other parameters in this equation are given in Regulatory Position C of this guide.b. Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q
    Pergamon Press, Oxford, England, 1966.
exp(-xit) (C-12)where C'(r,a) is the concentration in milk of nuclide i, in pCi/liter;
CY(r,O) is the concentration of radionuclide i in the animal's feed, in pCi/kg;Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively;
for nuclides not listed in Table C-6, use the values in Table C-5);1.109-55 TABLE C-5 STABLE ELEMENT TRANSFER DATA ELEM H HE Ll BE B C N 0 F NE N A 4G AL al P S CL.AR K CA sc TI V CR MN FE CO NJ CU ZN GA GE A5 SE BR KR Re SR Y ZR NB RU RN Po AG CD IN SN Biv VEG/SOIL 4,BE O0 5.OE-02 8,3E-OG 4, 2E-o4 1.2E-01 5*5E" O0 7.5E 00 1.bE GO 6.5E-4O iE-ol 5.2E-02 1.3E-ol I .BE-04 1.5E-OM 1.IE nO S19E-0!S.OE 00 6oOE-01 3,7E-oi.,,6E"O,?I .IE-03 So"E-OS i 3E-03 2.SEOu0 2.9E-io2 6,6E-Oq 9,a4E-03 1,9E-O2 1.2E-01 (S.OE-OI 2.SE-0O i OE-ol I.OE-02 1.3E O0 7#bE-01 3,OE O0 1,3E-01 1.7E-02 2.bE"03 16.7E-04 9.4LE,-03 1.2E-01l 2,5E-01 5.OOZ02 1,3E 01 5,OE' 00 9.OE"01 t,;5E-Gt 2.5E-01 3, OE-O I 2,SE-01 2,5E'03 F m(Cow)MILK(CD/L I ,OE02**2,0E-O;5,0E-O.I,0E-Oa 2,7E-0" 1,2E-022.  1.,E-02 2. OE-O?4 .OE-02*4**
IOE-02 5,OE-Ou I1OE-Oa 2,5E-OP IBE-02 5,OE-02 2.0E-028 , OE-03***5.0E'06**5,OE-06 S. GE-Ge, lOE-03 2,2E*03 2,SE-Ou 1?2E-03 I.OE-03 6,7E-01 I# 4E-02 5,0E-05 S. OE04 6,OE"03',SE-02 S.OE"O2 2, EOE.02 3#OE-O2 B OE-O4***I I OE-05 S OE-06 2#5E"03 7,5E-03 2.SE-02 IOE"O6 I.OE-02 I,OEOG.5,0E'02 5aOEw02 162E-Ou I.OE-0O 2.5E-03 Ff MEAT(D/XG)
2.2E-02 2,nE-02 i.oE-n3 B.OE-n2 3. 1IF-n2.OE-02 I .6F-02 I SF-ot 2. OF-n2 3.OE-02 SIOE-03 I ,E-o3 Q.OF-03 u.bFE-2'J.6 -n2 I a.E-nI 8. nE-o2 1.2E-02 a.bE-02 3,IE-02 2a3E-n3 1.4E-03 4.OE-04 4.OE-n2 1.3E-02 S,3E-03 8. DE-03 3OBE-62 I &#xfd;3F on?.fE 01 2.OE-03 1.5E-n3 2.OE-n2 3 a I E -0'Is.6 E-03 3,OIE.02 2. , BE -01 5,OE-o3 4. G E-ot t.SE-03 I .7E-02 8.OE-n3 R.MfE-02 ELEM SB TE I VE CS LA CE PR ,jD PM S4 EU GD TB Dy ER T YB LO NF TA w RE OS I R PT A U TL PB 81 P3 AT RN FR PA A C TH PA U NP PU A 4 9K CF ES F -8.av VES/S3IL I.IE-02 I'3E 00 2,OE-02 IOE 01 I OE-02 b,OE-03 2,SE-03 2*5E-03 2,SE-03 2 5E-03 2,SE-, 3 2.E-03 2.SE0 3 2,bE-03 2.bE-03 2,SE-03 2,#E-03 2. SE-03 2, 5E-03 2, SE-o33 2 bvE-03 1,7E-OP 6,3E-03 1. SE Ot 5,3E-01 2.SE-03 3 @3E-0I 2.5E-01 b, SE-02 I9SE-01 2oSE-01 2, SE-Ol 3,SE 00 I, E-O2 3, IE-OQ 2.5E-03 Q,2E-03 2,SE-03 2,SEmO3 2, SE,,03 2, SE"-0 2, SE"04 2, SE,03 2,SEo.03 2 , SE"03 2,SE-03 2, SE-O3 Fm(Cow)41 LK (1/L)I oSE-03 I .0E-03 b. OE-3l3 2.OE-02 I
* 2E-02".GOE-O1***5OE-Oh SOE-Ob S.OE-Ob 5.OE-Gb 5.0E-Ob S.OE-O6 5.OE-Gb SOE-Gb 5.OE-Ob SOE-Gb S.OE-Ob SoOE-06 5IOE-06 2.5E-02 S,OE-Ou 2*5E-02 5.OE-03 5,OE-03 S.OE'03 3.BE-02 2,2E-02 b.2E-O04 S5OE-O0 3,0E-O0 S.OE-02 2.oE-02 5GOE-02.80"03**5. GE-O6 S. GE-Oh SOEGOb S.OEGOU 5,GOE-b 2,OE-Oh 5.GE-Gb S.0E-Oh S.OE-Gb 5,0E-06 5,OE-Ob S.,OE-Gb 5,.OE -Oh Ff MEATT(D/KG)
POE-03 7, 7E-02 I2&#xfd;9E-03 2. E-02* OE-03 3.2E-03 2.OE-04 1.2E-03 4,7E-03 3.3E-03 4.8E-03 S. E-03 4.BE-03 3, bE-03~4, (E-03 S.3E-03 U,*E-03.uOE-03 u.OE-03 4.OE-03 ,Ci E-O1 I.bE O0 1.3E-03.,E-03 uOE-OI 1,SE-03 4.OE-03.OE-03 2.bE-G1 u.OE-O?2,9E-04 I SE-02 I 2E-02" GOE O0 2,OE-02 2.OE-02 3,UE-02 be OE-02 2. GE -04I B.OE 02 3,4E-O4-2,0E-04
2,OE-Oci 2. OE-O *i-2,OE-G04-2,0E-O*20GE-OU f II Ref. 1.Ref. 3.Ref. 13.t Refs. 7, 8, 9, 10, 14, 15, 16, 17.+t Ref. 18.E1 1.109-56 TABLE C-6 NUCLIDE TRANSFER PARAMETERS
FOR GOAT'S MILK ELEMENT Fm (days/liter)
H 0.17 B 0.012 C 0.10 Mg 0.042 P. 0.25" Cl 0.5 K 0.057 Ca 0.47*Fe 1.3E-04 Cu 0.013 Sr 0.014 I 0.06 Cs 0.30 Po 0.0018 Computed from the data of Refs. I and 19.**Ref. 13.1.109-57 QF is the amount of feed consumed by the animal per day, in kg/day;t is the average transport time of the activity from the feed into the mil: and to the receptor (a value of 2 days is assumed);
and Ni is the radiological decay constant of nuclide i, in days-Milk-producing animals are assumed to be on open pasture for the following grazing periods: Reg i Uon Southern U.S.Northern U.S.Pasture Period Whole year (fp 1)May -Sept. (fp = 1/2)where fp is the fraction of the year that animals graze on pasture.These data may be supplemented by information on site-specific dairy practices.


The concentration of radionuclide i in the animal's feed is then cv(r, a) f fCP(e)+ (I1 f )C 5 (r,) +f(1 (-3 , pfC(ro -,.p i + -I 5 C~ (-where P Ci(ra) is the concentration of radionuclide i on pasture grass, in pCi/kg;I(ro) is the concentration of radionuclide i in stored feeds, in pCi/kg; and f s is the fraction of daily feed that is pasture grass when the animal grazes on pasture.following parameters will be employed in evaluating the milk pathway, unless data is supplied.The site-specific Parameter QF (animal's daily feed)th (storage time of animal's food)te (crop exposure time)Yv (crop yield)Value 50 kg/day (wet weight) for cattle 6 kg/day (wet weight) for goats 0 for pasture 90 days for stored feed 30 days 0.75 kg/m 2 (wet weight) for pasture 2.0 kg/m 2 (wet weight) for stored feed 4 1.109-58 c. Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentra- tion in meat is estimated as F (C-14)where C 1&#xfd;(r~o)is the concentration of nuclide i in animal flesh, in pCi/kg;Ff is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t is the average time from slaughter to consumption, which is assumed to be 20 days.All the other symbols are as previously defined.Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.4. Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by 0 .(r,,,) = DFIi4a [Uvf Cv(r,.) + UCr,) + U FC(, + ULf CL(r, e ija i [a a g i a i -Ua i a U. r (C-15)where D .(r,e)Dija is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr;DFIija is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables A-3 through A-6 of Appendix A of this guide); and v m F L Ua , Ua, Ua, Ua are the ingestion rates of produce (non-leafy vegetables, fruit, and grains), milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide).All the other symbols are as previously defined.The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD = DF .rvf + m + F F L L ja ija a g 1 a i a i a k I (C-16)1.l0-59 REFERENCES
16. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of
FOR APPENDIX C I. Y. C. Ng et a), "Prediction of the Maximum Dosage to Man fro;m the rallout cif ucclar Devices, IV Handbook for Estimating the Maxi'ium Internal Dose tro, m RPdio!;uclide:;
    1311 and 13 7 Cs to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.
,Pc :d-, to the Biosphere," USAEC Report UCRL-5D163, Part IV, 1968.2. R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, Cle,',eland, Ohio, 1D70.3. L. R. Anspaugh et al, "The Dose to Man via the Fooo-Chain Transfer EResultinq fro!:m Exposure to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1i, 1972.4. B. H. Weiss et al, "Detailed Measurement of 1-13' in Air, Veqetation and 'i1[' ;.-ound Three Operating Reactor Sites," NUREG-75/021, U.S. N~uclear Regulatory Commission, Washington, D.C., March 1975.5. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!., To," USAEC Report ID0-12063, January 1968.6. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at le National Reactor Testing Station, Progress Report Number Four," USAEC Report iO--126E.December 1968.7. B. H. Weiss et al, "Detailed Measurement of 1311 in Air, Vegetation and M.1ilk around Three Operating Reactor Sites," Environmental Surveillance around Nuclear Installatiorns.


!nter-national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. 1: pp. 169-190, 1974.8. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit,  West Germany, IRS-W-6, June 1973.9. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent
E
131i Doe to the Thyroid," Institute fur Reaktorsicherheit, IRS-W-5, April 1973.10. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental  of 1311 from Air to Milk," Institute fur Reaktorsicherheit, IRS-W-13, April 1975.11. C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout RadiontucI'det.
                                                I.109-60


on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971.12. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption of Cow's Milk as Critical Pathways for 1 3 7 Cs, 5 4 Mn and 1 4 4 Ce-1 4 4 Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.13. R. J. Garner, "Transfer of Radioactive Materials from the "i,T,'restrial Environ;nent to Animals and Man," CRC Press, Cleveland, Ohio, 1972.14. F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol. 17, pp. 565-9, 1969.15. R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.), Pergamon Press, Oxford, England, 1966.16. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1311 and 1 3 7 Cs to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.E I.109-60
REFERENCES (Continued)
REFERENCES (Continued)
17. J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report 100-12067, p. 36, 1968.18. R. S. Booth et al, "A Systems Analysis Methodology for Predicting Dose to Man from a Radioactivity Contaminated Terrestrial Environment," Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501, Oak Ridge, Tenn., pp. 877-893, 1971.19. D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.1.109-61 APPENDIX D MODELS FOR CALCULATING  
17. J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report
POPULATION  
    100-12067, p. 36, 1968.
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.
 
18. R. S. Booth et al, "A Systems Analysis Methodology for Predicting Dose to Man from a Radioactivity Contaminated Terrestrial Environment," Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501, Oak Ridge, Tenn., pp. 877-893, 1971.
 
19. D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.
 
1.109-61
 
APPENDIX D
                              MODELS FOR CALCULATING POPULATION DOSES FROM
                                      NUCLEAR POWER PLANT EFFLUENTS
      Calculation of the annual population-integrated total body and thyroid doses should be performed for the three effluent types identified in this guide. These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D, Section II
of Appendix I to 10 CFR Part 50.
 
For the purpose of calculating the annual population-integrated dose, the 50-mile region should be divided into a number of subregions consistent with the nature of the region.       These subregions may represent, for example, the reaches of a river or land areas over which the appro- priate dispersion factor is averaged.      Dispersion factors, population data, and other information describing existing or planned uses of the subregions should be developed.
 
1.    General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con- sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows:
            D Dd0.001 Z Pd    Yd jad Djdafda f                                                    (D-l)
where Djda      is the annual dose to organ j (total body or thyroid) of an average individual of age group a in subregion d, in mrem/yr;
              D      is the annual population-integrated dose to organ j (total body or thyroid),
                i      in man-rems or thyroid man-rems;
            fda      is the fraction of the population in subregion d that is in age group a;
              Pd      is the population associated with subregion d; and
          0.001      is the conversion factor from millirems to rems.
 
The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide. The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.
 
For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption.      For all the food that is produced within the
50-mile radius, the radioactivity concentrations are averaged over the entire area by weiqhting the concentrations in each subregion by the amount produced in each subregion. This average concentration is used in calculating the population doses.      The 50-mile average concentration of nuclide i in food p is computed as C    =  (/V  ) exp(-Ait ) C v                                                (0-2)
                  ip  p        1 p d dip dp The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.
 
1.109-63
 
TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL
                                IN LIEU OF SITE-SPECIFIC DATA
                                                PER CAPITA USAGE FACTORS (IUap)
            PATHWlAY                      CHILD        TEEN        ADULT      JNITS
      Fruits & Vegetables
      & grain                            200.00      240.00        190.0      kg/yr Milk                              170.00      200.00        110.0        1/yr Meat & Poultry                      37.00        59.00        95.0      kg/yr Fish                                2.20        5.20          6.9      kg/yr Seafood                              0.33        0.75          1.0      kg/yr Drinking water                    260.00      260.00        370.0        1/yr Shoreline recreation                9.50        47.00          8.3      hr/yr Inhalation                        2700.00      5100.00      7300.0      m3/yr External Exposure from Deposited Airborne Radio- active Materials                  8760.00      8760.00      8760.0      hr/yr Consumption rate obtained from Reference 3 of Appendix A and age-prorated using techniques in Reference 4 of Appendix A.
 
Data obtained directly from Reference 4 of Appendix A.
 
Data obtained directly from Reference 15 of Appendix A.
 
1.109-64 i
 
where Cd                                                                                    pathway p, is the average concentration over subregion d of the nuclide iforin models Cdip        in pCi/kg or pCi/liter (see Appendices A and C of this guide and equations for calculation of pathway concentrations);
              C ip        is the 50-mile average concentration of nuclide i in pathway p,    in Cip        pCi/kg or pCi/liter;
                t          is the transport time of the food medium p through the distribution system, p        in days (Tahle D-2 presents estimates of the transport times that may be used in lieu of site-specific data);
              vd          is the annual mass or volume of food medium p produced in subregion d, Vdp        in kg or liters;
                V          is the mass or volume of the food medium p produced annually with the p'      50-mile radius about the site, in kg or liters; 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 = Vp/X Uapfa                                                                      (0-3)
where fa        is the fraction of the population within the age group a;
                P          is the estimated population that can be served by the quantity of food p p        likely to be produced within 50 miles of the site;
              Ua          is the use or consumption factor of food medium p for the average Uap        individual in age group a, in kg/yr or liters/yr (taken from Table 0-1);
                          and V          is the annual mass or volume of food medium p likely to be produced within a 50-mile radius about the site, in kg or liters.
 
The annual population-integrated dose is then calculated as
          ?~O~
                  DiP= .Ol Z p
                    0.001      P  1 *.*fa&#xfd;CipUapDai(-4
                                          8 *U  ODF.                                          (0-4)
where P    if  Pp < P5 Pp                  p P50 if    Pp > Ps and DFai          is the dose factor for age group a and nuclide i,  in mrem/pCi (taken from Tables A-3 to A-7 and C-1 to C-4);
                                                      1.109-65
 
TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD
                              DISTRIBUTION SYSTEMT
      FOOD MEDIUM                              DISTRIBUTION TRANSPORT TIME (in days)
Fruits, grains,  and vegetables                              14 Milk                                                            4 Meat and poultry                                              20
Sport fish                                                      7 Commercial  fish                                              10
                                                                IO
Drinking water To be used in lieu of site-specific data on food distribution.
 
1.109-66
                                                                                      4
 
D.Dj    is  the annual population-integrated in man-rem/yr  or thyroid man-rem/yr; dose to organ j (total body or thyroid),
                Pp      is the population consuming food medium p; and P5 0      is the total population within 50 miles.
 
All other factors are as defined above.
 
Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I
to 10 CFR Part 50.      In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D).          Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.
 
2.    Use of the Models a.  Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq- uid effluents should be evaluated for the following principal pathways: potable water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri- gated with water that has received the liquid effluent.        In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant* contribution to the annual dose received by an exposed population group.
 
(1) Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump- tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application.        The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose. The formulation expressed in Equation (D-1) may be used.
 
The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1.        The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.
 
If the population served by a particular water supply system is not known,      it can be estimated by the following:
            Pw = v/c                                                                          (D-5)
where c      is the average daily usage of individuals on the system,    in gal/day per person;
                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.


Dispersion factors, population data, and other information describing existing or planned uses of the subregions should be developed.
If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation
(0-5).
  For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here. Any pathway so identified should then be evaluated by a model similar to that used above.


1. General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con-sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows: D 0.001 Z Pd f Djdafda (D-l)Dd Yd jad where Djda is the annual dose to organ j (total body or thyroid) of an average individual of age group a in subregion d, in mrem/yr;D is the annual population-integrated dose to organ j (total body or thyroid), i in man-rems or thyroid man-rems;fda is the fraction of the population in subregion d that is in age group a;P d is the population associated with subregion d; and 0.001 is the conversion factor from millirems to rems.The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide. The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.
1.109-67


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


For all the food that is produced within the 50-mile radius, the radioactivity concentrations are averaged over the entire area by weiqhting the concentrations in each subregion by the amount produced in each subregion.
Such exposed population should be included in the 50-mile population dose evaluation.


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


4 1.109-66 D. is the annual population-integrated dose to organ j (total body or thyroid), Dj in man-rem/yr or thyroid man-rem/yr;
For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with Vp as the total estimated U.S. commercial harvest of the aquatic food medium p. The annual population-integrated dose is then computed using Equation (D-4) with Pp = PSO" The age-specific factors of Table 0-1 may be used in lieu of site-specific data.
Pp is the population consuming food medium p; and P 5 0  is the total population within 50 miles.All other factors are as defined above.Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50. In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D). Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.2. Use of the Models a. Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq-uid effluents should be evaluated for the following principal pathways:
potable water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri-gated with water that has received the liquid effluent.


In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant*
(3) Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by sunmming the product of the individual doses in each subregion and the population exposed therein. All subregions within the 50-mile radius should be considered where existing or designated recreational facili- ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The formulation of Equation (D-1) is appropriate.
contribution to the annual dose received by an exposed population group.(1) Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump-tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application.


The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose. The formulation expressed in Equation (D-1) may be used.The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1. The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.
(4)  Doses from Consumption of Terrestrial Food Products Irrigated by Waters Receiving the Liquid Effluent The annual population-integrated total body and thyroid doses from consumption of food irrigated with water from the body receiving the liquid effluent are evaluated following the procedures outlined in the development of Equation (0-4).    Note that the term Vp of Equations
(0-2) and (D-3) denotes the total production of food medium p within 50 miles, not just the total production of irrigated food medium p. The consumption rate data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4).
      b.  Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and vegetation), and external irradiation from activity deposited on the ground.    In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant contribution to the annual dose received by an exposed population group. (See Regulatory Position C.1 of this guide.)
          For the evaluation of exposures from atmospheric releases, the 50-mile region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE, etc.)
and annuli at distances of 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 miles from the center of the facility. The atmospheric dispersion factors (x/Q') or similar factors should be evaluated at the radial midpoint for each of the subregions using appropriate atmospheric dispersion models such as those described in Regulatory Guide 1.111.


If the population served by a particular water supply system is not known, it can be estimated by the following:
(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 E
Pw = v/c (D-5)where c is the average daily usage of individuals on the system, in gal/day per person;P w is the estimated population served by the water system; and v is the average'daily intake of the water supply system, in gal/day.If the industrial usage from the water supply system is known, it can be sub-tracted from the average daily intake of the system before this value is entered into Equation (0-5).For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here. Any pathway so identified should then be evaluated by a model similar to that used above.1.109-67 The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle. This population may be pro-rated to include only the population within the 50-mile radius. Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius.Such exposed population should be included in the 50-mile population dose evaluation.
not differentiate between age groups. A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.


(2) Doses from Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions.
1.109-68


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


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


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


Equation (D-1) may be used. For external exposure, the model does not differentiate between age groups. A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.E 1.109-68
For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-1, D-2, and A-l to calculate population doses.
(2) Doses due to Inhalation of Radlolodines and Particulates The annual population-integrated total body and thyroid doses from inhalation of airborne effluents should be evaluated by summing the products of the individual doses received in each subregion and the population in each subregion.


Equation (D-1) may be used.The age-specific inhalation rates of Table D-1 may be used with the data of Tables C-l to C-4.(3) Doses due to Ingestion of Terrestrial Food Products The annual population-integrated total body and thyroid doses from ingestion of terrestrial food products should be evaluated using the production data for each subregion.
(4) Doses due to External Irradiation from Activity Deposited o' the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A
household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-7.


For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-1, D-2, and A-l to calculate population doses.(4) Doses due to External Irradiation from Activity Deposited o' the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-
REFERENCE FOR APPENDIX D
"Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Commerce,
1975.


===7. REFERENCE ===
1.109-69}}
FOR APPENDIX D"Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Commerce, 1975.1.109-69}}


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Calculation of Annual Does to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1.
ML13350A285
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Site: WM-00011
Issue date: 03/31/1976
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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION March 1976 REGULATORY GUIDE 

 OFFICE. OF STANDARDS DEVELOPMENT
                                                                                                                                      4,s.

REGULATORY GUIDE 1.109 " " 

                            CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE

RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING COMPLIANCE WITH 

                                                  10 CFR PART SO, APPENDIX I
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                                             5- I
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                      USNRC REGULATORY GUIDES                                        Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regultory Commission. Washingon D.C 20.                Attention. Doceing and Regulatory Guides are issued to describe and matte available to the publc           Service Section methods acceptable to the NRC still of implementing specific parts of the Commission's regulations, to delineate techntiques used by the sltff in evolu       The guides are issued in the foffowing tIn broad divisions sating specific problems or postulated accidents. or to provide guidance to eppli cants. RFegulatory Guides are not substitute% for regulatlons. end compliance       1. Power Reactors                       S. Products with them is not required. Methods end solution* different from those sot out in    2. Research and Test Roesctors          7 Transportation the guides will be acceptable It they provide a basis for the findings requistse to 3. Fuels and Materials facilitlee       a Occupational Health the issuance or continuance of a permit or license by the Commission                4. Environmental and Siting             2 Antitrust Review Comments and suggestions for improvements in these guides are encouraged            S. Meterials and Plant Protection      10 General at ail times, and guides will be revised. as appropriate, to accommodate corn mints and to reflect now information or aspetrience. However. cuminvets nn           Copies of published guiides msa be obteined by written request indicating the this guidea. f received within about Iwo months alter its Issuance will h. por       divisions desired to the U.S. Nuclear Regulatory Commrsrsun Washington. O.C
 ticularly useful in evaluating the need for an early revision                       206. Attention: Director. Office of Standards Development

TABLE OF CONTENTS 

                                                                                                                                  Page

A. INTRODUCTION

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

B. DISCUSSION

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

C. REGULATORY POSITION

............................................................... 1.109-8 

    1.   Radiation Doses from Liquid Effluent Pathways.                                                 ..........................109-8 a.      Potable Water ...........................................................                                     1.109-8
         6.      Aquatic Foods ...........................................................                                     1.109-8 c.      Shoreline Deposits ....... ... ...........................................                                    1.109-8 d.      Irrigated Foods .........................................................                                     1.109-8
    2.   Gamma and Beta Doses from Gaseous Effluents ..................................                                        1.109-10
         a.      Gamma Air Dose Rates for Elevated Releases ..............................                                    1.109-10
         b.      Ganma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases                                          ........................... 1.109-11 c.      Total Body Dose Rates from Elevated Releases ............................                                     1.109-11 d.      Skin Dose Rate from Elevated Releases ...................................                                     1.109-12 e.      Total Body Dose Rates from Ground-Level Releases ........................                                     :.109-12 f.      Skin Dose Rates from Ground-Level Releases ..............................                                    1 109-12
    3.   Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere...                                         1.109-12 a.      External Irradiation from Activity Deposited onto the Ground Surface .... 1.109-13 b.      Inhalation ...............................................................                                    1.109-13 c.      Ingestion.                    .................................................. 1.109-13
    4.   Integrated Doses to the Population ...........................................                                       l.lO9-l1
    5.   Summary of Staff Position..........................................1.109-14

D. IMPLEMENTATION

.................................................................... 1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO THE AQUATIC ENVIRONMENT ................................................................ 1.109-17 

    1.   Equation for Calculating Radiation Dose via Liquid Pathways ..................                                        1.109-17 a.      Concentration in Environmental Media (Cip) ..............................                                     1.109-17 b.      Usage (Uap) .............................................................                                     1.109-17 C.      Dose Factor (Dp"p ) .....................................................                                    1.109-20
    2.   Equation for Liquid Pathways ................................................                                         l.l09-20
         a.      Potable Water                        ...............................................                          1.109-20
         b.      Aquatic Foods..                                                         ............................          1.109-20
         c.      Dose from Shoreline Deposits ............................................                                     1.109-30
         d.      Dose from Foods Grown on Land Irrigated by Contaminated Water ...........                                     1.109-33 REFERENCES FOR APPENDIX A..............................................................                                         1.109-36 APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE

ATMOSPHERE ............................................................................ 1.109-39 

                                                                              1.109-3

TABLE OF CONTENTS (Continued) 

                                                                                                  Page
    1.   Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................        1.109-39
    2.   Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose ..............................................................       1 .109-40
    3.   Annual Dose to Tissue from Noble Gas Effluents ..............................         1.109-40
         a.        Elevated Releases .......................................................   1.109-40
         b.        Ground-Level Releases ...................................................    1.109-42 REFERENCES FOR APPENDIX B..............................................................         1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES

AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 

    1.   Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane .................................................................         1.109-45
    2.   Annual Dose from Inhalation of Radionuclides in Air ..........................        1.109-46
    3.   Concentrations of Airborne Radionuclides in Foods ............................         1.109-46 a.        Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .............................................                1.109-55 b.        Parameters for Calculating Nuclide Concentrations in Milk............        1.109-55
    4.

c. Parameters for Calculating Nuclide Concentration in Meat ................ 

         Annual Dose from Atmospherically Released Radionuclides in Foods .............
                                                                                                1.109-59
                                                                                                1.109-59 I

REFERENCES FOR APPENDIX C.............................................................. 1.109-60 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS............................................................................... 1 .109-63 

     1.  General Expressions for Pý.pulation Dose ......................................       1.109-63
    2.   Use of the Models .............................................................       1.109-67 a.        Population-Integrated Doses from Liquid Effluents .......................    1.109-67 b.        Population-Integrated Doses from Airborne Effluents .....................   1.109-68 REFERENCE FOR APPENDIX D...............................................................         1.109-69
                                                                                       1.109-4

TABLE OF CONTENTS (Continued) 

                                                                                                                         Page
    1.   Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................                                1.109-39
    2.   Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose ..............................................................                              1.109-40
    3.   Annual Dose to Tissue from Noble Gas Effluents ..............................                                1.109-40
         a..     Elevated Releases .......................................................                            1.109-40
         b.      Ground-Level Releases ...................................................                             1.109-42 REFERENCES FOR APPENDIX B..............................................................                                1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES

AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 

    1.   Annual External Dose from birect Exposure to Activity Deposited on the Ground Plane .................................................................                               1.109-45
    2.   Annual Dose from Inhalation of Radionuclides in Air ..........................                                1.109-46
    3.   Concentrations of Airborne Radionuclides in Foods ............................                                1.109-46 a.      Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .........................................................                            1 .109-55 b.      Parameters for Calculating Nuclide Concentrations in Milk ...............                             1.109-55 c.      Parameters for Calculating Nuclide Concentration in Meat ................                             1.109-59
    4.   Annual Dose from Atmospherically Released Radionuclides in Foods .............                               1.109-59 REFERENCES FOR APPENDIX C ..............................................................                               1.109-60

APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS... ........................................................................... 1.109-63 

    1.   GeneralExpressions for P p,,jlation Dose ......................................                               1.109-63
    2.   Use of the Models ...................................                               ........................ 1.109-67 a.      Population-Integrated Doses from Liquid Effluents .......................                             1.109-67 b.      Population-Integrated Doses from Airborne Effluents .....................                             1.109-68 REFERENCE FOR APPENDIX D...............................................................                                 1.109-69 E
                                                                                     1.109-4

LIST OF TABLES Table Page 

  1  Summary of Staff Position - Methods of Evaluating Compliance with Appendix i ..................................................................                                   1 .109-15 A-I   Definition of Points at Which Concentrations in Environmental Media (Clp)
       Should be Calculated ........................................................                                   1.109-18 A-2   Recommended Values for Uap to be Used for the Maximum Exposed Individual in.Lieu of Site-Specific Data ...............................................                                   1.109-19 A-3   Adult Ingestion Dose Factors ..................................................                                   1.109-21 A-4   Teenager Ingestion Dose Factors ...............................................                                   1.109-25 A-5   Child Ingesticn Dose Factors ..................................................                                   1 .109-26 A-6   Infant Ingestion Dose Factors .................................................                                    1.109-27 A-7   External Dose Factors for Standing on Contaminated Ground .....................                                   1.109-28 A-8   Bioaccumulation Factors .......................................................                                   1 .109-31 A-9   Shore Width Factors for Use in Equations (A-5) and (A-6) ......................                                   1.109-34 A-10  Animal Consumption Rates ......................................................                                    1.109-34 B-i   Dose Factors for Noble Gases and Daughters                                            ..............................
                                                                                                                        1.109-41 C-1   Adult Inhalation Dose Factors .................................................                                   1.109-47 C-2   Teenager Inhalation Dose Factors ..............................................                                   1.109-51 C-3   Child Inhalation Dose Factors .................................................                                    1.109-52 C-4   Infant Inhalation Dose Factors ................................................                                    1.109-53 C-5   Stable Element Transfer Data ..................................................                                   1.109-56 C-6   Nuclide Transfer Parameters for Goat's Milk ...................................                                   1.109-57

0-1 Recommended Values to be Used for the Average Individual in Lieu of Site-Specific Data .......................................................... 1.109-64 0-2 Recommended Values for the Transport Times in the Food Distribution System ...................................................................... 1 .109-66 

                                                                                   1.109-5

A. INTRODUCTION

Section 20.106, "Radioactivity in Effluents to Unrestricted Areas," of the Nuclear Regulatory Commission's regulations in 10 CFR Part 20, "Standards for Protection Against Radiation," estab- lishes limits on concentrations of radioactive material in effluents to unrestricted areas.

Paragraph (c) of 5 20.1, "Purpose," of 10 CFR Part 20 states that licensees s;hould, in addition to complying with the limits set forth in that part, make every reasonable effort to maintain releases of radioactive materials in effluents to unrestricted areas as far below the limits specified as is reasonably achievable.

Sections 50.34a, "Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents -- Nuclear Power Reactors," and 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities," set forth design objectives and technical specifications to control releases of radioactive efflu- ents from light-water-cooled nuclear power reactors. Section 50.36a of 10 CFR Fart 50 further provides that, in order to keep power reactor effluent releases as low as is reasonably achiev- able, each operating license will include technical specifications that (a) require compliance with the provisions of § 20.106 dealing with effluent discharge limits, (b) require that operating procedures for the control of effluents be established and followed and that eqi ipment installed in the radioactive waste system be maintained and used, and (c) establish re( :,-ements for reporting measured releases of radionuclides to the environment.

Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light- Water-Cooled Nuclear Power Reactor Effluents," to 10 CFR Part 50 provides numerical guidance for radioactive effluent design objectives and technical specification requirements for limiting conditions of operation for light-water-cooled nuclear power plants.

To implement Appendix I, the NRC staff has developed a series of guides that provide methods acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man. This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.

The methods used herein are general approaches that the NRC staff has developed for application in lieu of specific parameters for individual sites. The use of site-specific values by the applicant is encouraged. However, the assumptions and methods used to obtain these parameters should be fully described and dncumented.

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

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

B. DISCUSSION

Appendix I to 10 CFR Part SO provides guidance on the levels of exposure of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable. This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses. These estimates can be used to implement Appendix I in lieu of site-specific phenomena actually affecting the estimation of radiation exposure.

In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). 

                                                1.109-7

Appendix A of this guide describes suggested methods for calculating the estimated doses to man from discharges to the hydrosphere. Appendix B of this guide describes suggested models and assumptions for calculatinr submersion doses from radionuclides discharged to the atmosphere, and Appendix C gives equations for estimating doses from radioiodines and other radionuclides released to the atmosphere. Appendix D describes the models and assumptions for calculating population dose (man-rem and man-thyroid-rem) from radionuclide releases to the atmosphere and hydrosphere.

The models and assumptions described in Appendices A, B, C, and D of this guide are accept- able to the NRC staff for calculating doses to individuals and populations. If other models are selected, they should include the same exposure pathways and physical mechanisms as are used in the models described in this guide.

As discussed in Section III.A.2 of Appendix I to 10 CFR Part 50, the applicant may take into account any real phenomena or actual exposure conditions that affect or modify the estimate of radiation exposure. Such conditions should include actual values for agricultural productiv- ity, residence times, dose attenuation by structures, measured environmental transport factors (suchas bioaccumulation factors), or similar values actually determined at a specific site.

The applicant should provide e-ough information on the measurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.

C. REGULATORY POSITION

1. Radiation Doses from Liquid Effluent Pathways The NRC staff will calculate radiation doses from potable water, aquatic food, shoreline deposits, and irrigated food pathways by using the following equations from Appendix A of this guide.

a. Potable Water MU1100 

                          M ,n R                         QiDaipjexp(-Xitp)                                       (1)
     b.    Aquatic Foods Raj'1100 UapM pn*                   -At2 I
           Rapi     1100     F      QiBipoaipjexp(-Aitp)                                     (2)
     c.    Shoreline Deposits Wn 0
           Rapj = 110,000             I QiTiOai    [exp('Xitp)][l - exp(-'0t)]               (3)
     d.    Irrigated Foods For all radionuclides except tritium:
              ap       p veg   n  dIexp( At )D       .  [r[l - exp(-AEite)]     Biv[l - exp(-xitb)]]
           Rapj     Uap        i I        ih alpj    L       YvEi          *J
                       Uanimal n             {QFd exp(Xith)    r[ - exp(-Eite)]
                        + Uap      SiA aipj                          YvxEi BivDl - ep-lb]
                    +            pexp(-itb)]     + CIAwQAw}                                  (4)
           For tritium:
           Rp        vegC D          animal                                                  (5)
                                            Dapj LA"(w +QAw)
                  -
             api = ap v apj + Uap
                                                     1.109-8
                                                                                                         4

where Bip is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentratio., in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/lizer), in liters/kg; 

       Biv    is the concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;
      CiAw    is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter);
       Ciw    is the radionuclide concentration in water, in pCi/liter;
     Daipi    is the dose factor, specific to a given radionuclide i, pathway p, organ j, and individual's age a, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in water, expressed as a ratio of the dose rate (in mrem/hr) and the radionuclide concentration in water (in pCi/liter);
        di    is the deposition rate of nuclide i, in pCi/m2 per hr;
          F   is the flow rate of the liquid effluent, in ft 3 /sec;
          k   is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle);
        Mp    is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food) as described in Table A-1 (in Appendix A of this guide),
              dimensionless;
          n   is the number of radionuclides that are to be considered;
          P   is the effective "surface density" for soil, in kg(dry soil)/m 2 . Assuming a uniform mixing of all radionuclides in a plow layer of 15 cm (6 in.) depth, P has a value of approximately 240 kg/mi2 ;
       QAw    is the consumption rate of contaminated water by an animal,  in liters/day;
        QF    is the consumption rate of contaminated feed or forage by an animal,   in kg/day (net weight);
          Qi  is the release rate of nuclide i,  in Ci/yr;
          r   is the fraction of deposited activity retained on crops (which is 0.25 for sprinkler irrigation, 0.2 for particulates, and 1.0 for airborne deposition of radionuclides), dimensionless;
      R    .i is the total annual dose to organ j of individuals of age a from all of the RaPj   nuclides I in pathway p, in mrem/yr;
        Si    is the transfer coefficient for radionuclide i which relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product)
              per pCi/day;
          t   is the period of time for which sediment is exposed to the contaminated water, nominally taken to be the mid-point of the operating lifetime of the facility, in hours;
        tb    is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours;
        te    Is the time period that crops are exposed to contamination during the growing season, in hours;
                                        1.109-9

th is a holdup time that represents the time interval between harvest and consumption of the food, in hours; 

              T       is the radioactive half life of nuclide i, in days;
              tp      is the average transit time required for nuclides to reach the point of exposure. For internal dose, t is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;
             Ua       is a usage factor that specifies the exposure time or intake rate for an Uap     individual of age a associated with pathway p, in hr/yr or kg/yr (as appro- priate);
                w     is the water intake rate via fresh forage (28 liters/day for beef cattle and
                     38 liters/day for dairy cattle);
                W     is the shoreline width factor, dimensionless;
              Yv     is the agricultural productivity (yield), in kg(wet weight)/m2 AEi     is the effective removal rate constant for radionuclide i from crops, in hr"
                     provided that AEN : Ai + Awl where Ai is the radioactive decay constant, in (hr)-I, and Aw is the removal rate constant for physical loss by weathering (Xw = 0.0021 hr- 1 , which corresponds to a removal half-life of 14 days);
              Ai     is the radioactive decay constant of nuclide i,     in hr  ,
              AM     is the water elimination rate constant (0.32/day for beef cattle and 0.28/day for dairy cattle);
           1100      is the factor to convert from (Ci/yr)/(ft 3 /sec)   to pCi/liter; and
        110,000      is the factor to convert from (Ci/yr)/(ft 3 /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose com*,itments to the total body or any organ of an individual from the sum of the exposure path- ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.

2. Gamma and Beta Doses from Gaseous Effluents The NRC staff will calculate radiation doses from gaseous effluents using the following equations from Appendix B of this guide. The definitions of elevated and ground-level releases are found in Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors," and Appendix B to this guide.

a. Gamma Air Dose Rates for Elevated Releases 

                       260                                             IDA
                         -7(o n~~ un  ns    I(Ek)IE(H,u,s,oz,Ek           ik                 (6)

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

        DY(r,o)      is the annual total gamma air dose at a distance r in the sector at angle 0,
                     in mrad/yr;
              Ek     is the energy of the kth photon energy group, in MeV/photon;
                                                1.109-10

fns is the fraction of the time that stability class s and wind speed n occur for sector 0, dimensionless; I(H,utsoz,Ek) Is the result of the numerical integration accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and.

atmospheric stability (s)which in part determine the effective stack height (H)and the vertical plume standard deviation (o). In addition, I is a function of the photon energy E,1and is T = 1 4 kT2 as formulated in Slade (see Reference I fi: Appendix B of this guide); 

                'D
             Qn1       is the the releaser rate distance    under ofwind radionuclide i, corrected fnr decay during transit to speed un, in Ci/yr;
                 r     is the distance from the release point to the receptor, in meters;
               un      is the me;'n wind speed of wind speed class n, in m/sec;
               AO      is the sector width over which atmospheric conditions are averaged, in radians;
                      and ua(Ek)      is the air energy absorption coefficient for the kth photon energy group, in m1 .
     b.     Gamma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases Dy(r,o) or DO(r,0) = 3.17 x 1O4o3 QI[/Q '/    )D   r
                                                           ](r,o)(OFi  or DF')
                                                                     ( or                   (7)

where 

                 8 DF'Y OF        are the gar,.na and beta air dose factors for radionuclide I,
                                 3 in mrad per yr/
          I' I        pCi per n ;
    Dy(r,O) or are the annual gamma and beta air doses at the distance r in the sector at D'(r,o)
                      angle 0 from the discharge point, in mrad/yr;
               Qi     is the release rate of the radionuclide I, in Ci/yr;
  [x/Q']O(r,e)        is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors," for methods to estimate x/Q'); and
    3.17 x lO4        is the number of pCi per Ci divided by the number of seconds per year.

c. Total Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t] (8) where oT(r,e) is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr; 

        DY(r,o)       is the annual gamma air dose associated with the kth photon energy group at k           the distance r in the sector at angle 0 from the discharge point, in mrad/yr;
                                                    1.109-11

SF is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless; 

                 t      is the product of tissue density and depth used to determine a "whole-body"
                        exposure. This depth is 5 cm, which is equivalent to t = 5 g/cm2 ;
           T(Ek)        is the tissue energy absorption coefficient, in cm2 /g; and k)
            1.11        is the average ratio of tissue to air energy absorption coefficients.

d. Skin Dose Rate from Elevated Releases oS(r,O) = l.1ISFOY(r,O) + 3.17 x 10 ' F Qi[x/QJ]D(rO)DFS (9) where DFSi is the beta skin dose factor for the radionuclide i which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr. This attenuation is for 70 micrometers or 7 mg/cm2 .f tissue; and DS(r,0) is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/yr.

All other parameters are as defined in preceding sections.

e. Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF

  • xi(r,o)DFBi (l0)

where DFBi is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in Appendix B of this guide); 

                                                                                                     4 DT(r,)         is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e)        is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 .

All other parameters are as defined above.

f. Skin Dose Rates from Ground-Level Releases D5 (r,0) = 1.11 SF *xi(r,e)DF + xi(rO)OFSi (1i) where D5 (r,O) is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr.

All other parameters are as defined above.

3. Doses from Radioiodines and Other Radionuclides Released to the Atmosphere The NRC staff will calculate radiation doses from radioiodines and other radlonuclides released to the atmosphere using the following equations from Appendix C of this guide.

i 

                                                  1.109-12

a. External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF cG(r,o)DFG.. 

                                      G                                                      (12)

where CG is the ground plane concentration of radionuclide i, in pCi/m 2 ; 

                  Ci DFGij       is the open field ground plane dose conversion factor for organ J from radio- nuclide i, in mrem-m 2 /pCi-hr;
         DG(r,O)        is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr;
                 SF     is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless;
                        and
             8760       is the number of hours in a year.

b. Inhalation DA (r,o) R xi(r,o)DFAi (13) where O (rO) is the annual dose to organ j of an individual in the age group a at location 

                *       CrO) due to inhalation of all radionuclides, in mrem/yr;
           DFA. ijaa    is  the inhalation dose factor for radionuclide i, organ j, and age group a, in mrem/pCi;
                                                                                               3 Ra     is the annual air intake for individuals in the age group a, in m /yr; and
                                                                                                      3 xi(r,o)        is the concentration of radionuclide i in air at location (r,o), in pCi/m .
     c.       Ingestion o    r     v            m           .FL            L     1)
                 a (ro=
               D. (ro)ja
                          2DFIi -[I a 9cV(r,+)
                                           i
                                                  + UaCim(r,o)
                                                     a
                                                               + U.i(r,o) + Uaf Ci(r, ai       +  az
                                                                                              (14)
                                                                                              (4 where
          ,CF(r,O),

C.(r,o), C.(r,O) are the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg. These variables are determined using Equation (C-7) from Appendix C of this guide; 

           D3 (r,o)      is the annual dose to the organ j of an individual in age group a from inges- ja          tion of all radlonuclides at location (r,o), in mrem/yr;
             DFlija     is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi;
                 f ft   are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note: fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U      Uvn, Um, UF     are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a Ua'   a a     respectively, for individuals in the age group a, in kg/yr.

1.109-13

4. Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1, 2, and 3. Because of the various conditions under which the equa- tions in Appendix D are used, they are not presented in this section. It is recommended that Appendix D be read for a detailed discussion of the staff's models.

5. Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I is presented in Table 1.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.

This guide reflects current Nuclear Regulatory Commission practice. Therefore, except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as a result of suggestions from the public or additional staff review.

II 

                                                                                                 I
                                             1.109-14

TABLE 1 SUMMARY OF STAFF POSITION - 

                       METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I
                            APPENDIX I                POINT OF DOSE              EQUATIONS

TYPE OF DOSE DESIGN OBJECTIVE EVALUATION TO BE USED Liquid Effluents Dose to total 3 mrem/yr per unit Location of the highest 1, 2, 3, 4, &5 body from all dose offsite* 

 pathways                                              (see also Table A-I).
 Dose to any organ       10 mrem/yr per unit          Same as above.             1, 2, 3,  4, &5 from all pathways Gaseous Effluents**
 Gamma dose in air       10 mrad/yr per unit          Location of the            6 or 7, as highest dose offsite.***   appropriate Beta dose in air        20 mrad/yr per unit          Same as above.             7 Dose to total body      5 mrem/yr per unit           Location of the            8 or 10, as of an individual                                     highest dose offsite.*     appropriate Dose to skin of an      15 mrem/yr per unit          Same as above.             9 or 11, as individual                                                                      appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ       15 mrem/yr per unit           Location of the           12, 13, & 14 from all pathways                                     highest dose offsite.,'
   Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.

Calculated only for noble gases.

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

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

tt Evaluated at a location where an exposure pathway actually exists at time of licensing. How- ever, if the applicant determines design objectives with respect to radioactive iodine on the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine: (l) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives; (2) whether changes in land and water usage and food pathways which would result in individual exposures greater than originally estimated have occurred; and (3) the content of radioactive iodine and foods involved in the changes, if and when they occur.

1.109-15

APPENDIX A 

                         METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE
                                  DISCHARGES TO THE AQUATIC ENVIRONMENT
     The equations for estimating radiation exposure to man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.           The equations can be used to calculate the annual doses to various organs of a child, 0 - 11 years; a teen, 12 - 18 years;

and an adult, 18+ years.

1. Equation for Calculating Radiation Dose via Liquid Pathways Equa*tion (A-l) is the fundamental equation for calculating the radiation dose to man via liquid effluent pathways.

aipj C ip Uap aipj (A--) where Cip is the concentration of nuclide i in the media of pathway p, in pCi/kg; 

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

b. Usageý (Uap) 

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

The NRC staff encourages the use of site-specific data, whenever possible, for param- eters such as those included in Table A-2. Such data should be documented. In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Table A-2 are reconmnended.* 

 In selecting usage values, not only the present land and water uses should be considered, but also changes in land and water uses made possible by such activities as chemical pollution abatement.     Radioactive material released into waterways may include long-lived radionuclides that have potential for accumulation in sediments and biota and may persist for many years --
 perhaps beyond the lifetime of the nuclear power station.

1.109-17

TABLE A-I 

                                     DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip)
                                                               SHOULD BE CALCULATED
                                                                                                        SUBMERGED (single or multi- PATHWAY                  SURFACE - LOW VELOCITY              SURFACE - HIGH VELOCITY               port) - HIGH VELOCITY
  Fish (fresh and salt water)       Discharge canal              Edge of initial mixing zone*         Edge of initial mixing zone**
  Invertebrates                     Discharge canal              Edge of initial mixing zone*         Edge of initial mixing zone**
  Shoreline                         Discharge canal              Point of contact of diluted          Point of contact of diluted effluent with shoreline              effluent with shnreline CO
  Drinking water                    Nearest anticipated          Nearest anticipated downstream       Nearest anticipated downstream downstream supply***         supply,*                              supply***
  Irrigated crops                   Nearest anticipated          Nearest anticipated point of         Nearest anticipated point of point of withdrawal          withdrawal for irrigation +          withdrawal for irrigation- for irrigation t Point where effluent has undergone prompt dilution near the surface (about 5:1 for large receiving water bodies).
      Point where effluent has undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water).
      Fresh water sites only. The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections over the plant lifetime, is the closest point to the site where a drinking water supply exists or could exist.

AFresh water sites only. The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land use projections over the plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists or could exist.

____

TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U SED FOR THE MAXIMUM 

                       EXPOSED INDIVIDUAL IN LIEU OF S]ITE-SPECIFIC DATA
          PATHWAY                        CHILD               TEEN      ADULT        UNITS

Fruits & vegetables & graina'b 520.0 630.0 520 kg/yr Leafy vegetablesa 26.0 P?.0 64 kg/yr Milka,c 330.0 100.0 310 liters/yr Meat & poultrya 41.0 65.0 110 kg/yr Fish (fresh or salt) d 6.9 

                                                              16.0        21        kg/yr Sea fooda                                    1.7                3.8          5       kg/yr Drinking waterc'e                         510.0              5510.0       730        liters/yr Shoreline recreation e                      14.0
                                                              67.0        12        hr/yr e

Boating 29.0 52.0 52 hr/yr 

                                                                       73 0 0 f Inhalation                              2 7 00 . 0 e        51,O0.,e                 m 3/yr
                                       190P.O(infant)g aconsumption rate obtained from Reference 3 for average individual and age-prorated and maximized using techniques contained in Reference 4.

bconsists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24? grain.

CAn additional category of maximum individual (1-yr old) should be added for these pathways.

Consumption rates are the same as the child's.

dConsumption rate for adult obtained by averaging data from References 4, 6-9 and age-prorating using techniques contained in Reference 4.

eData obtained directly from Reference 4.

fData obtained directly from Reference 15.

glnhalation rate for infant obtained by averaging data from References 10-14.

1.109-19

C. Dose Factor (Daip.) 

           Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref. 15) for body burden and ma):imur permissible concentration (r.IPC).   Effective absorbed energies for the radionuclides are calcu- lated from the ICRP model. Appendix D of Reference 16 was used as a basic source of age-dependent dose factors for ingestion. Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.

The dose factors for external exposure were based on the assumption that the con- taminated medium is large enough to be considered an "infinite volume" relative to the range of the emitted radiations. Under this assumption, the energy emitted per gram of medium is equiva- lent to the energy absorbed per gram of medium corrected for the differences in energy absorption between air or water and tissue and for the physical geometry of each specific exposure situation.

Material deposited from sedimentation in an aquatic systet, or from irrigation water onto the ground represents a fairly large, nearly uniform thin sheet of contamination. The factors for converting surface contamination given in pCi/m 2 to the annual gaisia dose at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 4, 5, and 17). Dose factors for exposure to soil sediment have units of mnrern/hr per pCi/1n2 surface.

A set of dose factors for 45 radionuclides was originally calculated for the year 2000 model (Ref. 4). These factors have since been recalculated using recent decay scheme informia- tion (Ref. 18) and expanded to include additional radionuclides. The revised list is given in Tables A-3 through A-7; it contains several radionuclides for which the daughter is not listed separately (e.g., Ru-Rh-106, Cs-137-Ba-137m, and Ce-Pr-144). In those instances, the daughter's decay energy has been included in the factor.

2. Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel. Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated. The doses from the four pathways should be added to determine the total dose.

a. Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below: 

           Rapj = 1100    Uap   Qjexp(-x. .t )Daipj                                      (A-2)
               apF            1            p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.

The sunmation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected. The Q!/F termis in Equation (A-2) define the concentration of nuclide i in the effluent at the point of discharge. The expression (QMM /F)exp(-A t ) yields the concentration of nuclide i at the time the water is consumed.

I pconcentration This i p is the term Cip in Equation (A-1). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system. The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake. Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 4.

It should be noted that, depending on the hydrological dispersion model employed, the mixing ratio, M'Ip,or dilution factor may not be explicitly defined. In those instances (e.g., buildup of activity in a cooling pond), the relative concentration in the mixed stream (compared to the effluent concentration) may be supplied as a function of the radiological decay constarnt.

with any potential effluent recycling taken into account. Suggested hydrological dispersion ,:odels will be contained in another regulatory guide now under preparation on the subject of methods for estimating aquatic dispersion of liquid effluents from routine reactor releases for the purpose uO implementing Appendix I.

b. Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations, 

                                                 1.109-20

TABLE A-3 ADULT INGESTION DOSE FACTORS 

                                             (mirem/pCi ingested)
    'JUCLIDE     BO.E       LTVER           TnTAL 81)Y        1,i 3lI-O1     KT)NEY           LUNG       GI-LL I
  I        3   0.0           1.34E-n7          1 .3UE-07                     I, S.

3 E-fl7 I .,OE-07 I. SiF-n7 

  4BE     10    3.l18-06    4.91E-n7          7.o5EF-0       n n             3. 71E-n7     0.0           2.bMF-0'i bC      14   P.BUE-06     5.69E-07          ri.bqE-7       5, qF -07       5.69F-07      S.bqE-07     5.bQE -07
  7N      13   B.37E-09                                         *l3 7EF- 0 9 8. 37E-ng           $7F-09  6. 371F-09
                            9.37E-09          ý. 37E-09                                    '.
  QF      IS   b.2SF-07     1.0               b.93E-OR       n.n             0.0           0.0

IPJA 22 1.70F-05 I.74E-05 I .74E-05 I .711E-05 I . 74E-nc I . 74E-05 I ASE-05 IlIA 24 21,2OF-Ob >. ?6*E-..0 P. 26F-Uh 

                            2.?bE-0b          2.2hE-rib      22.2SE-0b       22.?6F.-06
          32    1.Q3F-04    1. 21 E-05        7,* 7F.-t0h                    0.0           0.0          2.1I 7E -09

1 5P 2. olE-nS 20CA ul 1.87E-0'J 0.0 0.n 0.0 ,0. I ..ýJF -0i7 I .OOF-0B 5.21F -05 21SC Ub. 5.SIF-OQ I .nBE-08 3.11 E-OQ 

                                                             1.S5QF-0*                     3. 53F-n9

24CP 51 o.0 2.bbE-19 1 . ttIE -07 254.4 a n0 S.57E-o6 .8 73E-.07 0.0 36RIE-06 0.0 25mN 5b 0.0 I . I9E-07 2. 0SE-OR n n l,6bE-07 0.0 3.h7F-O6 

                                                             0.0               0.0

2hFE 55 b.20E-0O 2.79F-oS 7.33E-06 1.23E-05 I . oW -05 2bFE 59 U.3UE-0b 1 .03E-09 3.9?E-06 0.0 0.n 5.4OF-06 27Cf0 57 0.0 .7 5 -07 2.JI1E-07 n.0 0.0 

                                              I .67E-1b      0.0             0.0                         1 .91F-05

27C0 5B 0.0 / . I,SE -{') 7 0,0 0.0 27C0 60 0.0 2. 15E-0b U,72E-nb 0.0 n0. -nb ,022F-OS 

                                                             0.0

28,NI 59 9.77E-06 3. 35E-O0 I .b3E-06 ( n 0.0 b790E-07 

                                                                             0.0

28N1 63 1.30E-O0 9.02E-O0 4.36F-Ob ,00 284I b5 5,20E-07 b.B7E-ng 3.1 3E-08 0.0 7I1.i 

                                                                                                            .t i O-06 B F- Oh

2qCU b4 ).0 5.3'JE-06 3.92E-OR  ? 1nF - n Q.70E-(6 30ZN 65 U.SE-06 1 .54F-05 6.97E-08 1 03E-nS 2.49F-05 30ZN b94 1.70F-07 u .0, E-07 3.731E0' 0,0  ?. USE- n7 0*,0 

                                                             0.0                           0,0
                                                                                           0. n

30ZN b9 1.03E-08 1 9SE-08 I .37E-0O I ?O2F-OR 2. 9b-09 

                                                             0.0

34SE 79 0.0 2. 6I-06 M.dOE-07 41, 5 6F. -n6 0,0 5, 38F-07 35RP A? n.0 0.0 2.?PhE-n6 n00 0.00 2.54F-Ob 355P 93 0,0 0.0 4 . 2E-ný, 0.0 .,79F-OR 35.P 84 0.0 0.0 5.22E-O0 0.0 n,0,00 u0nqF-13 

                            0.0                                                            0.0
                                                                                           0,0

35BR 85 0.0 2.1 4E-O9 0.0 0.0 37RB 0b 0.0  ?.11 F-05 9.8UE-0b 0.0 0.0 0.0 

                                                                                           0.0          4, 1bE-Oh

37BR 87 0.0 I .?3E-OS 4.28E-4b 0.0 5. 7(E-07 37RB 48 0.0 6.06F-()8 3 . 21 E-04 0,0 0.0 n00 

                                                                                           0.0          8.3bF-19

37RR 89 n.0 U.0 1IE-O8 2.93E-0. 0.n 0.0 0.0 38SR B9 3.09F-0'J 0.0 5.89F-06 0.0 MI,*4E-05 3BSR QO 7.61F-03 0.0 I .86E-03 0.0 0.0 0.0 I.02E-nu 3RSR 91 5.82F-Ob 0.0 P.ShE-07 0.0 0.0 2.Q3E-05 

                                                             0,0                           0.0          4 , 2bf -05

38SR 92 2.IbE-Ob 0.0 9.31E-08 0.0 39Y go 9.63F-09 0.0 2.5RE-10 0.0 1.02E-04 39Y 91M 9.10E-11 0.0 3.53E-I? 0.0 0.0 0.0) 2,b7L-1 0 39Y 91 1.alE-07 0.0 3,7RE-09 0.0 0.0 77bE7-05 Note; 0.0 means insufficient data or that the dose factor is <].OE-20.

1.109-21

TABLE A-3 (Continued) 

 NUCLIDE         BONE   LIVER          TOTAL BODv   TH)ROID    KIDN EY                   Gl-I.Ll
                        0.0           2.07E-1I     0.0       0.P

39Y 92 8.46F-10 n.0 

                                                   n.,       0.0          0,0       9
  • SO F -6C'5

39Y 93 2.6E-09 0.0 7.40E-11 

        93   4 . IqF-08 2.3uE-Oq      1.09E-09     0.0       8.99E-O9               2.U3f -Oh

4OZR 

                        9.76E-09      6.61E-09       n.0      I .SUF-08   0.0
  0OZR  95   3.0UE-OR                                                       ,00     I O5E -na a0ZR    97   I.68F'-09  3.39F-10      1.56E-10     0.0       5 1 P.E - 10 0.0
                        S. 33E-09     2.05E-09     o0n       5,58E-09     (0,0      3,RU*-no
  14tN  q33  2.55E-08 n.n       3. U5 E-0q

41.JN 5 b,2sF-09 3.46RE-09 1.36E-nq 2.1 OE -05 L.e2E-12 0.0 I .5AE-1 I 0.0 QLNB q7 5.23E-1 I 1.32E-1 I 

                                                   010                    0.0

u2mO q3 0.0 7.52E-nb 2.03E-07 I .b??F -n, U,31E-0b A.(' 0.0I 4240 9q 0.0 8.20E-07 43TC 994 2.47F-10 6.98E-I0 9.9nE-Aq n.0 I O0hF-AR 1 ,S2E-10 ,153F-n7 q9 I 2bE-07 1 .8hF-07 5.OUE-08 o.n 2,34E-nb b.08F -('6 43TC I .9SE-OP t.SiF-05 

                                      3.60E-19     n.0       ().bOE-09                     7F-OR

43TC 101 2.54F- 10 3.67E-1 0 U* 

                        0.0           7.qgE-0R     0.0       7.07E-n7

44RIJ 103 1 .85E-07 1bF-05 40RU 105 I.S4E-08 0.0 6.ORE-Oq 0.0 1 .'9E-07 0.0 

             2.75E-O0   0.0           3.48E-07     0,0       5.32E-0b                    7 6 -('74
                                                                                         7E

LILRU 106 *.0 

       105   1.22E-07   8.86E-08      S.SIE-OR     0.0       3.76F-07

45RH 1 .. 32E-06 46PD 107 0.0 1 .47E-07 9.UIE-Oq 0.0 

                                      U.OOE-08     0.0       I .02E-O1
  6bPD 109   0.0         I .77E-07
       1104  1.6bOE'-07  2!.'JRE-07   4.80E-04     0.0       2. 91E-n7              b.   0Laf-it,

47AG (1.0 

                                      1.21E-0B     n.0       7.8SF-nA

L7AG III 5.82E-0R 2.44LE-08 

                                                   0.0       3.50F-nb     0.0

48CO 1134 0.0 3. 1qF-Db 1.02E-07 2.2bF-n5 

             0.0         I .84E-0b    5.AgE-OR     0.0       I4.6F-06               7 . 7 a"E- r*S

48Co 1154 0.0 1,07Et-O5 50SN 123 3.1 IF-05 5.16E-07 7,6OE-07 L.38F-07 0.0 b. 33E-05 

                                               7             0.0          0,0

50SN 125 8. 3bE-06 1 .6AF-n7 3.79E-0 1.39E-07 

                                      2.JIE-06     4,92E-07  0.0          0.0

50SN 126 8. U6E-05 1.68E-Ob 2.'3E-0S 

                                                   6.79E-09  0.0          2.1 8E-Ob SISB   124   2.81E-06   5.30E-00      I.IIE-0.b                                     7.95F-O5
                        2.4nF-08      4.J8E-07     1.9BF-09  0.0          2.33F-04 S1SB   125   2.23F-Ob                                                               I .97F-O0
             1. 15F-Oh  2,3'E-n8      U.ISE-07     7.0SE-09  0.0          7,05E-n7 SISH   12b                                                                          9.40F-05
                                      9,q2E-0M     3,IIE-09  0.0          I .53E-n7 SISB   127   2.5E-07    5.bhE-09                                                    S QO2E-nh- I . 09E-05   0.0

'52TE 1254 2.b8E-Ob 9.73E-07 3.59E-07 8.07E-07 1,07E-05 

                                                   1.73E-06  2.75E-05     0,0       ?.27f -15

52TE 127M 6.78E-06 2.37F-Ob 9.26E-07 

                                      2.3AE-OR     8.16E-0B  LAI*,LRE-07  0.0}      8. b8F -Ph

52TE 127 I 1 IOE-07 3,95E-08 0.0 527E 12qM 1015E-05 4L,30E-06 1.82E-06 3.qSF-06 Li,.!lE-n5 

                                                              1.3?E-n7    0.0       2. 37Fl-08

52TE 129 3. ISE-08 1. 19E-0FB 7.66E-09 2.IE-0B 

                                      7.06E-07     1.34E-06  8.5E-06      0.0       9.4 £0E-05

.52TE 1314 S1,74E-06 9, 47E-07 

                         5.24E-09     b.22E-O9     1.62E-OR  R.b'E-nf

52TE 131 1.97E-08 0.0 

                         1.6LAF-0b    1.51E-06     I.BOE-06  1,58E-05               7.*71 F-05

52TE 132 2.53E-05 

             4.63F-08   2.80E-08      4.06E-08     3.92E-03  2.57E-07               Li.   I7F -00

52TE 1334 0.0 

                        2, 13E.-08    1.3nE-0'     2.,3E-05  2.09E-n7

52TE 134 3.24F-08 0.0 

                        2.8lE-Oh      9.22E-0b     7.23E-03  60OSE-(b

531 129 3.27E-Ob 0.0 

                                                                          0.0
             7,57E-07   2.2*iE-06     8.R1E-07     2.85E-OIA 3.UIE-Oh               1     .92E-nt,

531 130 0.0 

             4, tl6E-06 S. 96E'-06    3.41E-06     1.95F-n3   I. O.E -05            I .57F-I~b

531 131 

                        5.43E-07      1.93E-07     7.15E-05     , bhE'-07           1 . n2E-07

531 132 2.03E-07 I 

                                            1.109-22

TABLE A-3 (Continued) 

                BONE        LIVER       TOTAL RODY       THYROID   KIDNEY        LUNG        GI-LLI
 SUCLIDE

531 133 1.43F-06 2.USF-06 7.57E-07 4.77E-04 4. 33E-flb 0.0 2. 18EOb 

             1 ObE-07     2.SRE-07       1.03E-n7      3. 74E-05 '.*5    E-907 0.0        2.51F-1 0

531 134 I . I 7E-06 (429E-n7 I .5jE-n0 1. 86E-.nh 0.0 1.31E-06 531 135 4.43F-07 

            2.1 3E-09     'J' (IQE -0B   ?. 3nE-os     D.0       2. 4 E .. n   3.83E- 09  1.58E-08

55CS 13U 6.2?F-05 1I USE -04. 1.21E-OU 0.0 £4. OE..0n 05 2.%9E-O0 5SCS 135 I q.F-05 I 80E-a5 8.OOE-06 0.(I 2,OSE-( 

                                                                               I .S9F- 06 4.. 21F-07

55CS 13b b.51F-ob 2.57E-o5 I .85E-05 0.0 I, 3E..n5 06 2.92E-0b I ,23E- OS 2.10E-06 55CS 137 7.98E-05 I. .OE-0O 7. 1SE-05 0.() 3. 71E'.-)5 

                                                       0.0       8.02E.-n8     1 .Q2F- 09  4.65E-13

55CS 135 5. 5F-08 I. OoF-o 7 S.. iE-ns 55CS 139 3.£4 F-Os 5.08F-08 I .SE-08 4.07E-08 3.70E- 09 0.0 

                                                       0.0       6.£7E-- I     3.92E- 11  1.72E-07

569A 139 0 . 7 1 F-O0S 5.92E-I I 2,84E-09 

                          2.55E-08      I .3E-06       0.0       R.6bE-09      I '46F- 08 £*418E-05

5654 1a 0 2.03E-05 

                          3.56E-i 1                    0.0       3.3tIF-I      2, 02E- 11 2,22E-17

5bBA IUI 0.0 1.59E-09 1.,SFE-II 

                                                       0.0        I,.95E-1t    I .2UE- 11 0.0

Sb8A IUP P. 13E-08 2. 19E-1 I I .3UE-09 I .26E-O9 3.30E-10 0.0 0.0 0.0 Q,25E-OS S7LA 1UO 2.SOF-OQ 

            3.19E-10      9.91E-1l      I .62E-1 I     0*.0      0.0           0.0

57LA I U1 57LA IL2 1.28E-10 5.82E-11 1 .£4S5- 11 0I.0 0.0 0.0 4.25E-07 58CE IU q,3 IE-Oq 6, 3£4E-09 7 .18E-10 0.0 2,42E-05 5CE 143 I.%5E-09 I.22E-O0 1.3SE-10 0.0 5.3.E-10 0.0 4,S6E-05 I bSE-OS 58CE tUQ u.BQE-07 2,uE-07 2.bE-08 0.() 

                                                       0.0        I .21E-07 S9Pq 143     9.21E-09      3 . 70aF.-O0  4,57E-10                 2.1 3E-09                4,03E-05 I .25E'-11I                            7. 06E-1 2    0.0        4.33E-18

59PR 10I4 3.02E-1 I 1.53E-12 0.0 

            h.30E-oq                    4.35E-I0                               0.0        3.49E-05

6OND lU7 7.28E-09 0.0 I.25E-09 6IPM ¶LI7 0.0 8.93E-06 61PM I aB7 7.55E-08 7.10 E -09 2.P7E-Oq 0.0 1I13UE-08 

                                                       0 .0                    0.0        6. 7E-05
            3.07E-08      7.96E-09      b.OSE-09       0.0        1.2 1IF-O0S
                                        6.OOE-t0       0.0       2.25F-09      0.0        9.34F-05

6IPM tuB 7, 1BF-09 I . I9E-09 

            1 .52E-09     2. 1SE-I 0 S.7qE-1 I         0.0       4.O7-1 0      0.0        *,03E-05

61Pm 151 0.0 

                  7F-I 0
               . l9       1.1 7E-1 0    5.92E-1 I      0.0       2 . 0 9 F -1             3,22E-n5
                          1.1I9E-0B                    0.0        1 . 33E-08   0.0        S *25E-Ob

62SM 151 6.91E-08 2.BbE-09 b2SM 153 8.5RF-IO 7.16E-1 0 5.23E-1 I 2.3?F-10 2,55E-05 U1,L"JE-OB 0.0l 2.775E-07 0.0 

                                                                               0.0        2.56E-05

63EU 152 I .q5E-O7 7o.7E-08 3.9IE-O0 0.0 

                                                       0.0
                                                       0.0        3.621--07    0.0        5.48E-05

63EU 154 6. 1bE-07 5.39E-08 

                                                       0.0
                                                       0.0       5.,LIE-rib    0.0
                                                                               0.0        9,60E-O0

63EU 155 5.61E-08 1 .22F -n8 7.88E-0Q 

                                                       0°0       7.09E-09      0.0        7.26E-05 b3EU   156    I . 37F -08  I .ObE-0       I .71E-ng
            4.70E-08      0.0                          0.0        I.94E-08     0.0         4.33E-05

65TB IbO 5.FbE-09 

                          13.44E-09                    0.0
                                                       0.0
                                                       0 .0       1.26E-07     0.0        0.0

b740 16bM 2.70E-07 bAlE-08 0.0 

                                                       (0.0
                                                       0.0       0.0           0.0          *.bSE-07

74M~ 191 9.9?E-09 3.24E-09 3.46E-10 

            40.bE-07                                             0,0           *00        1,56E-05

740 185 I. 35E-07 1.4?E-08 

                                                                 0.0           0.0        2,82E-05

744 187 I .03E-07 8.62E-08 3,02E-08 0.0 52PH P O I .53F-02 U.38E-03 5. £E-Oa 1.23E-n2 5,42E-05 8381 210 0.b2E-07 3.19F-Ob 3.97E-08 3. 84E-05 4.75E-05 84PO 210 3.57E-OU 7.57E-o0 8.60E-n5 2.52E-03 6,36E-05 

                                                1.109-23

TABLE A-3 (Continued) 

 NUCL IDE   BONE          LIVER        TOTAL BODY     THYROID     KIDNEY    .LUNC   G[-I.'.'

B8RA 4.q8E-03 7.bbE-Ob 2.17F-04 0.0 

      223                             9.95E-OU       0.0

88RA 224 1.b2E-03 3.90E-Ob 0.0 1.11 E-oiU 0.0 

                                      3.23E-04                                    3.2    E-Ou h.57E-03      7.79E-06       I .31E-01     0.0      2.21F-ou

8BRA 225 .0 

          3.05F-01                    2.21E-01       0.0      1.b3E-04            S.,32E-Ou

88RA 226 5.75E-06 0.0 

                        3.1?E-06      1.21E-01       0.0      8.84E-0s            5.64E-05 B8RA 228   1.12F-01                                                         0.0

B9AC 225 2,QsE-07 0.0 6. 90F-6 7 4.07E-04 

          4.     -1F-06 6,07F-06                                              ,0.

89AC 227 1.88E-03 2. *8E-OU I I II E-0Q 0.0 R.03E-05 7.q'E-05 

                                                                           0.0
          1.37E-05      2.4BE-07                     0.0      tl     IE-Ob        5.JOE-Ou

90TH 227 3.96E-07 0.0 90rH 229 I.b8E-AS 0.0 4.67F-05 5.h3E-Ou 

          4.96F-OU      3.41E-06                                              ,0.

90TH 229 R.ObE-03 1.21E-O04 3.95E-O0 0.0 5.80E-OU 0.0 5,12E-Oa 90TH 230 2.08E-03 1 I1 BE -O04 5.76E-05 5.b9E-04 6,O2E-OS 

                                                     0.0                   0.0
                        I .OIE-04     .4,9?E-05               U.'3bE-ou    n010   I *?'E-On

90TH 232 l.SOE-03 0.0 n100 90TH 23Q .9.02F-08 4.*72F-09 2.32E-09 0.0 2.b7E-OR 0.0 1.13E-Oa 91PA 231 4.I4F-03 I.56E-0l I .61E-Ou 0.0 1.0 0.0 b.?T7-Ou 91PA 233 5.26F-09 I .0bE-09 Q,2AE-In 0.0 3.99F-nq I , 4F -0s 92UL 232 u.l4E-03 0.0 2.95E-04 0.0 

                                                              4.47E-04     0.0    b. 72E-0ý

92U 233 8.7?E-0O 0.0 5.29E-05 0.0 2.0TE-OQ 0.0 b,27E-05 92U 234 8.37F-014 G00 5. 1RE-05 0.0 0.0 b. 1UE-05 A.86E-05 I 40E -no 0,0 7,BIE-05 92U 235 8.02E-04 0.0 0.0 

                                      4.97E-05                I,75E-0U     0.0    5. 7bE-OS

92U 23b 8.02E-O4 0.0 0.0 2.27E-07 92U 237 S.53F-08 0.0 I .47E-O0 0.0 

                        0.0                          0.0
                                                                                              I

92U 238 7.67F-OU 4.55E-05 I *7E-04 0.0 

                                                                           0,0    t.bbE-O0
                                                     0.0
                                                     0.0                   0,0    7.94E-A5

93NP 237 l.38E-03 1.20E-O0 5.5qE-05 I .26E-n9 7qUE-05 

                                                     000
                                                     0.0

93NP 235 1.37E-08 3i,6E-10 2.1 3E- 10 3.S5E-10 0 0 93NP 239 6.4AE-1 1 0.0 0.0 2.a0E-05 

          1.20E-09      1.18E-1O                              7. 1* E-o0

9'PU 238 . 31E-05 1 .67E-n5 0.0 0.0 7.30E-05 

          6.7SF-OU                                            ?.9bE-05

94PU 239 7,60F-04 I OMiE-OQ I .88E-05 0.0 0,0 h1b6F-05 9UPU 240 7.58E-04 1,04iE-04S I.88E-05 0.0 7.96E-05 0.0 6.78E-05 9IJPU 9.4l7E-07 3.33E-07 I .53E-nS 0.0 l.u0E-O0 

      2U1 1.5bE-05                                   0.0

guPU 990E-05 I .79E-05 7.SRE-n5 0.0 

                                                                           0.0    6.5  SE-os
      242 7.22E-04                                   0.0                          q.,5SE-05
                                                                                  9,75SE-OS

9JPU 2L4L 9.60E-0O4 I I1BE-O4 2.13E-05 0.0 9.03E-05 0.0 95AM 241 8.IOE-04 2.79E-04i 5.26E-05 0.0 3.QbE-OU 7.02F-05 95AM 2Q2M 8.32E-0O 2.78F-00 5,47E-05 0.0 .. O8E-n4 9. 34E-09 95AM 2i3 8.12E-0O 2.7 3E-O0i 5.24E-05 0.0 3.95E-0O 0.0 

                                                                           11.0   9. 73E-Oi

96CM 2U2 1.58E-05 I .64E-ý05 I.OUE-Ob 0.0 4o.7E-0b 0.0 7.92E-05 96CM 243 b.43E-0O 2.QIE-0OJ 3.77E-05 0.0 SI *7bE-0O 0,0 7.8IE-09 

                                                              1. 3LE-04    0.0)   7.55E-05

96CM 244 4.851-04 2.07E-04 2.BRE-05 0.0 0.0 7.0F-05 96CM 24S. 1.03F-03 2.B8E-O0 5.BIE-05 0.0 2.71E-04 0.0 

                                                                           0.0

96CM 2U6 1.02F-03 2. 88E-04 5,BOE-05 0.0 2.7,1E-n4 6,9I1L-05 96CM 247 9.95E-04 2. B3E-O0 5.72E-05 0.0 2.67E-O0 0.0 q. 09E-05 9bCM 2'8 8.27E-03 2. 33E-03 4.71E-O4 2.20E-03 1.87E-O.3 98CF 252 1.96E-O4 0.0 4.95E-06 0.0 2.88E-04 

                                              1.109-24
                                                                                              4

TABLE A-4 TEENAGER INGESTION DOSE FACTORS 

                                         (mrenm/pCi ingested)
    NUCLIDE      BONE      LIVER       TOTAL   B:oY    TqYq!10    OC
                                                                   I -)NF Y           GI-LLI
   IH       3 0.0           I ObE-07      I.06F-A7      1.n0E-07            I .06F-07  1.0h-07
   6C     1'J  7.55E-07     7 .55E-07     7.SSF-07     7 . SSE-07           7.55F-n7   7.55F-07 IINA    22   2.36E-09     2. 35E-35     2. 3SE-05     2.35F-05             2. 35F-05 2.88-*-h

27C0 513 ,00 9.92F-67 nO 0.0 I .3JF -05 

                                         2.26E-Ob

27C0 bO 0.0 2. 76F-nb 6. 30E-Ob . 31E-05 38SR B9 0.0 I . 3E-15 n o 

                                                       0.0          (USE    n0        4.49F-n5
                                                                            0.0

38SR 9o 1 .OE-02 0.0 2.57E-03 0.0 2.4?eo-O0 39Y qo 3. 3OF-08 A.87F-ln0 0~o 

                                                                            3.75E-nS   1.O9F-O0
                                                                    ADULT

39Y 91 1 .9hE-07 0.0 5.?P3E-n9 0.0 7.53E-05 unZR 95 3.72E-08 I .2'JE-08 8.6hE-nQ 0.0 2.68E-05 41,NB 95 7.2JE-09 *.36E-0q  ?.u7E-OQ 0,0

0. n T

                                                                            0.0        I. 78E-05 DOSE'   0.0

44RU 103 2,37F-07 0.0 1 OhE-07 1 .6SEF-0s OULRU job U OOE-Ob 0.0 5.03E-07 0.0 I. IE-o0 505N 123 U . 3AF -05 7,22E-o7 1 .0E-Ob 5.37E-07 FACTOR) 0°0 6. 31F-05 SPTE 1254 3.93E-06 I . 37E -0h 5.0AE-07 I5,13E-07 0.0 I ,07F-05 

              1.51E-07     5.3?E-OM      3.23F-08      I .03E0O7                      I .22E-0O

52TE 127 0.0 52TE 129M I bhF-05 5.15F-Ob 2.61E-nb 5,30E-06 5.R0E-05 52 T E 13? 3.55F-O0 2,22E-Ob 2.1 nE-n6 235SE-6 5 8,00E-05 531 129 L.bbF-O6 3.92F-O0 1 .31F-05 4.31E-07 531 131 5.57E-0h 7.87E-06 U.6qE-nh 2.27E-03 0.0 1.49E-06 531 13 2. 03E-Ob 3."UE-Oh I OhE-Ob b.?5F-0U 0.0 2,50E-06 95cS 134 8.05E-05 1 .9QE-01 9. OhE-05 0.0 2.35E-05 2.24E-Oh 55CS 137 1 .07F-O0 I lUUE-0LJ 5.05E-05 1.91F-05 1.q2F-06 

                                                       0.0

5b0A 1U n 2.83E-05 3.u4E-os I.fPE-06  ?.33E-09 4.tUE-Oh 57LA 140. 3.43 

                 *8F  -09  I .72E-09     4.59E-10                           0.0       Q.8F.-0O

5.1CE I1i0 1 .2bE-08 n.O 2.29L-05 5RCE I1aQ 7.22E-07  ?.9bE-07 3,83E-O8 0.0 1.70E-04 o.6 b3EU) 154 1 I5E-Ob I .OnE-n7 R.7qE-ng 0).0 0.0 5.12E-05 92U 232 60.bE-03 0.0 n,2tE-0 0.0 6.72E-05 92U 234 1,22F-0,3 0 0 7.UnE-05 0,0 0.0 6,14E-05 gaPU 238 5,£0E-0a I I*1 E-O0 2.ORE-05 0.0 0.0 7.30E-05 9UP I 23- 9.2bE-04 I . 29E -n4 2.2QE-05 o.0 6bE6F-05 QUPU 0.0 b.bbE-05 

       240    9,25F-04     I . 30F-oil   2.31E-05                           0.0

9'PU 2a! u.03E-07 1.852E-o 1.02E-00 0.0 0.0 1.28f.-07 95AM 241 9,q3E-04 (.1 7E-nU 6.66E-05 0.0 7.17E-05 9bCM ?42 2.26E-05 2,33E-05 I .50E-06 0.0 0.0 7.80E-05 96CM 24U b

  • hL F-0 L 3. 33E-0O U.n3E-05 0.0 7.42E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-25

TABLE A-5 CHILD INGESTION DOSE FACTORS 

                                        (mrem/pCi ingested)
    NUCLIOE     BONE      LIVER      TOTAL B.11Y     TH~YRODI   K I)NEY     LUNr        G;I - LL I
  IH      3   0.0         2.03E-07      2,03E-07      2.03E-07            P . 0 3E - 07 2.0 3E-07
  6C          2.26E-06    2.26F-06     2.26E-06      2.26E-06 I INA   22    5. 89E-05                S.8QE-05      5.R~9E-05S                PQE-06S
                          5,89F-05                                                      2. S7k-Ob

27C0 58 0.0 I .8SE-nb 5.58E-flb 0.0 27CO bO 0.0 5.17E-06 1 .55E-05 0.0 JS.iSF-OS 38SR 89 1.*38F-03 0.0 (USE 

                                       3.95E-05      0.0                                Ž.2.8b -051 qO    1.*72E-02   0.0          41.36E-0 3 o.0                     0.0

39Y 90 4,1. E-08 0.0 I

  • I3E-oq ADULT 0.0

39Y, 91 5.65E-07 o,0 I .56E08) 0.11 7. 77E-05 

        95    1 .04F-07   2,012E-08    2.?OE-OA      0.0                  ,).0          2.50F-05 (J1NB   95    1 .95E-08 8.32E-09 6. IIE-09 0.0                    DOSE    0.0           1 .J44E -05

44 RU 103 6,78E.-07 0.0 2.71jE-07 0.0 0.0l I

  • ThF -n03

44LRU lob I*1.19E-05 0.0 I USJE-06 0.0 0.0 I . k5F-va SO SN 123 1 .31E-0(1 1 .641E-06 3.22E-0b I .73E-06 S2TE 1 25H t I 1'JF-05 3.20E-06 FACTOR) 0.0 1 , I OF -OS.

3.09E-flb I .S2E-0b 52TE 127 4A.50F-07 t .20E-07 9.65E-06 3. 1 OE-07 (.0 1 .'0?f-fl 

                          1 .38E-05                  1.58E-O5                           S5.96EF-05

52TE 129M 

              41.95SO5                 7.65E-06                           0.0
       132    I.02F-O5    UI.5OE -06 5.'I2E-Ob       b.62E -05b           0.0           7 .89F-O5

531 531 

       129
       131
       133

55c S 137 

              1 739-E -05
              1 .63E-05
              5,98E-06
                          8.S(1F-06
                          1 .67E-DS
                          7.38E-06
              2,24JE-041 3.77E-fl'
                                       3.81EF-05 I 426E-05
                                                     2.79E-02
                                                     5,USE-03
                                       2,90E-06~ 1 .7F-0_
                                       8. 02E-05     0.0
                                                                          0.0
                                                                          0n0
                                                                          u.19F-05 LI *  9L .f7
                                                                                        1 .43E-06
                                                                                        ?.Q9E-oh
                                                                                         2.04FI-0(,
                                                                                                       4 SscS          3. 12E-04   3.02E-04I 41.50F-05                             3.54E-05      1.8ar-06

56BA 110 8.26E-05 7.2SE-n8 £1.SSE-0b 0.0 u.32E-08 0.*21 E-0b 57LA 1 a1 I .01E-08 3.52E-09 1 . IQE-09 0.0 1.noQE-011 58CE Ia 1 3.76E-OR I BR8E-08 2.80E-09 0.00 1.0 2.36E-05 SOCE 2,14'E-06 6. 70E-017 I.14(E -07 0.0 I .711F-0'J b3EU 154 2.58E-0b 2.08F-07 2.03E-07 0.0h 0.0 0.0 ai. /Ok -05 

                          0.0                        0.0

92U 232 1 .77E-02 1 .26E-03 0.0 b.91L-OS 9?U 234 3,57E-03 0.0 2.2 1 E-04J 0.0 6. 3eF-0'3 911PU 238 I .21F-03 1 .52E-04I 3.09E-OS 0.0 0.0 7 . 50EF -V5 94iPU 239 1 .32E-03 1 .62E-04i 3.27E-05 0.0 6

  • PSE -0
                                                     0.0

94PU 2a0 1.32F-03 I .63E-noL 13flnE-05 Im 0.0 0.0 6 1SL -05 

                                                     0.00

94 U 2at 7. 12E-07 1 .81E-08 0.0 0.0 I .32F -0 7 95AM 201 0.0 

              1.4£2E-03   b.211E-n4    9,9&E-05      n, n
                                                     0.0                  0.0           7 . 37 F - f'5

96CM 242 6,74E-05 5.28E-nS '1.41hE-06 n, 8.03E-05 96CM ?' 11 1. 12E-03 5.L f -0 1 6.99E-95 0.0 7 . bUjE -OS Note: 0.0 means insufficient data or that the dose factor is <I.OE-20.O 

                                              1.109-26 I

TABLE A-6 INFANT INGESTION DOSE FACTORS 

                                             (mrem/pCi ingested)
    NIJCLTr)E      qti'*E    LIVER        TflTAL ~VlDy        T H4Y 4 110 K 1 3N F Y    LONG       GJ-LLI
           .3    0.0         3.0 7F-o7       3. 07E-07        3. 07E-07               3. 07F-07    3.07E-07 bC      14    U.81F-Ob    4.*81 F-ob      U.BI E-06        a0,4B I-n0b                6 1 E-Ob A 22      1.OnF-OLI   I *00E-nd       I OO0E-04        I.o0F -04                  OO.0F-04~ 2
  • 45E-Oh aJ Sa 0.0 3.78E-06 9.26E-06 0.0 0 .09.79E- b5
 27C'0 60n       0.0         1 .07 E- 05    2.56E-05          0.0                     n0.0         2bF           5
 38S1 R C        2,q3F-03    0.0            A.U2E-05          0.0            (USE     0.0          5."l8E-05u R 90      2.91F-02    0.0            6.U0E-03          6.0                    0.0           2      F-04
 385
           40    BQIE-08     0.0            2.41E-!ý9         0.n           ADUL.T      .01.29               0
 39y QI    I.2S9F -0h  0.0            3.33E-OR            .0                   (.0
                                                                                     0             8.27E-05 R. 5      ? .IIF -07  5.32E-nR       3.78E-08          n.n                    0 .0          ?.38E-05 Q P95     I.g9E-nR    I.75E-1)8       1.03E - 1        0.0           DOSF      0.0          1.LJE-Oc5
 4 1P(
       J 103     1.OilE-0    0 ,0           U.BSE-07          n .0                     1.0         1.7F0
       J 1.06    2.5"&E-05   0.0            3.12E-16          0,0                    0.0           19E0 5

50S~N 123 2.7'9E-0Li Q.33F-oh h.96E-lb 4.33E-(16 FACTOR) 0.0 b.41E-055 52TI E1254 2.'J3F-0'S 5.19E-nb 3,20E-flh R.OnE-OS 0.0 1.17E-05 52TE 127 9.58F-07 3. 1 9F-n7 2. 06E-n7 7.75E-0 7 .. 0 2.?27E-05 52TE I?9M 1.05F-04 3.61F-05 1 .60E-05 3.q9E-05 0.0 6. 33E-05 521E 132 2.t3F-05 I n05E-05 0* 76E-Oh I *99E-'n5 n,0 A, 08F.---05 531 129 2.95F-09 2. IbE-OS 7 .76E-05 h.*79 F-02 0.0 4.46JE-07 531 131 3.U2E-OS 401 0F-05 2.3RE-05 I .31E-62 0.0 1 .53E-06 

                                                                                     ,0o0

531 133 1,2bF-05 1 BUE -05 S.'BE-06' u.*35E-0 S 3.*27E - 06 55CS 130 U.SAE-04 9~.2 4E-0 4 6.97E-05 0.0 9.42E-05 55CS 13 6.53F-O0 7 . 31 -4 0. *20E-05 0).0 R.81E-05 56BA 1'&0 1,74E-00 '75-n7 

                               1            8 qqF-0b          0.0*                    I .07E-07

57LA 100 2.12E-08 5. 17E-ng 2

  • I E-fO) 0.0*
                                                              0 5
                                                                                     0.0           I. OuF-04
                                            5.75E-IQ                                 0.0

S8'E 141I S.OOE-08 4:91F.08 0.0 2. 39E-05 58CE lU4 0.49E-0b 1 .7 7E -0 h 2.0?E-n7 O.0 I.85E-04 O .RUE-n7 0l,0 4.*7bE -05 63EU 154 4.30F-06 3.29E-07 0.0 92U 232 3.66F-02 0.0 2.68E-03 0.0 7.*34E -05 920J 234 7.u00F-n3 0.0 4.71EC-04 0.0 0.0 6. 72F-05 qAPO P38 1.71F-03 2.1 BE-a04 0 .25E-q5 0.0 7.98E -05 9'IPU ?39 1.70E-03 2. 2bF-q0 0

  • I E-1)5 0.0 0l.0 7.*29F -09 qqpU ?'40 1.78E-03 22 8F?E- fl 0 .45E-05 0.0 0).0 7.28E-05
 94PU P.01       11OhE-0b    I .37F-D7      2.70E-OP          0.0                    0.0           I .40OF-07
 95AM 241        1.93F-03                                                            n0.0
                             I .01F-n3       1 . IIE-nu       0.0                    0.0           7.8'4E-O5

96CM 2U2 1.43E-nu I UOOE-04 0.0 13.b,3r-05 

                                            9 .Q9F-nb                                (0.0

96CM 244 1.bdE-03 7E -00 0.0 8. 12E-05 

                             1.6            1 .04E-04 Note:     0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-27

TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND* 

                                              tmrem/hr per ptl/'.)
                 TOTAL BODY        SKIN                                           TOTAL BODY        sKirt iH       3    0'.0           0,n                             UOZR      93     6.0             3.0
      4BE     10    0.0            0.0                              4OZR     95     5.00F-09        s . G010
      bC                           0 0                             4OZR      97
                                                                                    5. SOE -()q
      74            7 60kE-0q      5.80E-09                          41N8    93*4       o0.

9F 18 b. 0FO-09 8. OOE-09 95 5. 1OF -A9 5. O0)E -A9 

             22      I ,66E-08     I. OE-08                                  97     4A*bOE-0q       i,4nE-Oq I TMA-
    11  NA          2.50E-0B       2.90E-08                                         2.29E-I I
    1P        32    0,0)           0.0                              42MO     99      1 .qUF-0O          *20F-09
    20CA      U1       . nO -O
                    03.'JlE-09 U.01E-n9                        LJ3TC     9q4    Q.*,,E-10        I* OE-OQ
    21 SC Ub          I*30F-08     1 .50E- -B                      43TC      04     0.0
    214CR                          2.b0E-1 0                       'i3TC            2.7WF-0O        I.OOF-Oq
             51
                                                                   44RU 101
                     2.20E-I0
   .25MN 50        9.60E-09
                     1 *BOE-ORq                                            103       S.bOE-OO       4 .20F-o9
                                                                           105      4.5UF-Oq
    25MN     5b                    I IOE.-08                                                        5. 101-O
                   0.0                                               LARU           I .50F-09       I    jAnF-0q
   26FE      55                    0.0                             U £4P D
                                                                   LA9RH
   2bFE      59                   9,4OE-O9                                 105      b.6OE-10        7.7nE-10
   27C0      57    9. OE-t0        I.OOE-OQ                                         0.0                S.0
   27C0      58    7.OOE-09       R.20E-0Q                          46PD   109      3.50E-I I       14.001-I11
   27CO      6n      1, 70F-08    2. 00E-O0                        47AG             I ,80F-08       '.   tOE-08 I
             5q                                                    47AG    1 nb I I~   I .80E-10       2. tOE-Io
   28NI                           0.0
   28NI      63                   0.0                                               2.3nF-12        2.60F-12
                     3. 70E-09                                     4A C r)
   28NI      65                    1 .70E-09                               111      0,0             0.0
   29CU      ba      I .50E-09                                                      0.0             b,* bE-qR
                                   I,70E-Oq                                123
    30ZN b5        UQ,00F-09                                               i07
                                                                           125      5. 7OF-t0       b.bOE-10
   3nzN 694                                                                                         I DO0E-nm
                   2.90E-09       3.0OE-09                                 t 246    Q.DOF-09
   3'JZN 69        0.0            0.0                              5""s              1.30E-08       1 .50F-09
   34SE      79    0.0            0.0                              52TE
                                                                   5128    125      3. IOE-09       3.50E-09
   35BR      82      I
                     6 .90E-AA
                       . 9O0E - I 2.20F-ro8                        52TE I?b
                                                                   515R                *
                                                                                       .9OF   -') 9 I .OOE-O8 b.UOE-t 1                                                        5. 7OF-09       b.hOF-*9
             83                   9. 30E- II                               127
   358R                              .40E-08                                                        U*.AOE-1 I
                     I .20F-08                                     52TE             3.50F-12        1. 0E- II
   35BR      85    0.0            0.0                              51TE
                                                                   52TE    12741
    37RB           6.30E-1O        7.20F-10                        52TE    127       I OOF-I I      I .IOF-1 I
   37RB                                                                                             P *OOE-It0
             87                   0.0                              5?TE    122'4    7.70F-10        g.uOE-I0
   37RB 88         3.50E-09        4.OOE-09                        52TE    129
                                                                           12b      7. IOE-10
   37R8      5Aq   I .50E-08      1.80E-08                         52TE    t31M       S.,U OF -09   4.90E-09
   38SR      59    5.60F-1 3      b.5OE-13                         52TE    131      2,20F-09        2,b0E-Ob
   -38SR 90        0.0            0.0                              521E
                                                                   52TE    13 2      I . 70F-0Q     2.00F-09
   38SR            7.o I OE-Oq      . 3 0E-09                                        1.50E-08       I .70F-OA
   3ASR                                                                    I 3M
             92    9.OOE-09       I .OOE-08                                          I .OOF-09      1.20E-09
   34Y       90    2.20E-12       2,60E-12                         531     129      4 .SOE-1 0      7,50F-I 0
   39Y       914   3.80E-0q       4.40 E-09                                130       I *U0E-08      1 .70E1-ri
             91                                                                                       1 7 0E - n9
                                                                                                    5.40FO-DQ
   39Y             2. 4 OF- II    2.70E-i I                        531     131      2.80F-09
   39Y       q2    I .6bOF-09     17.90F-n                         531     13 2     I .7nE-0O       2. O0E -08
   39Y       93    5.70E-I0       7 .80E-1 0                               133      3.7UE-09        U.5AE-09
  • The same factors apply for adult, teen, child.

Note: 0.0 means insufficient data or that the dose factor is <l.OE-20.

1.109-28 E

TABLE A-7 (Continued) 

            TOTAL BODY         SKIN                                 TOTAL BODY        SKIN

53! 13u I.bOF-0 l.90t-o0i 8RRA 2?3 1.50F-09 I.ROF-09 531 13 1 .20EE-08 1uOE-O8 8SRA 22u 3.9nE-0q 1.OOE-08 

                                                         88PA   P25   ;. 11F - I t I. 2()F -1A

55CS 134'1 b.P0E-10 7.Y0E-10 55CS 134 1 .2F-08 IQOE-0p 88AA 22b b.41JF-oq 7.40E-O0 55CS 135 0.0 D.0 R.RA 228 I,?f'F-0 t.4OF-n8 

                                                                                   1

55CS t36 1.5OF-'4 '.70E-08 89AC P2? IrNF-OQ 1.80E-oQ 55CS 137 4 .2OF QJ90E-0Q 

                           -.                           9A9C    227  2.OOE-09      2.40F-59

55CS 13A 2,tOE-05 2.uOE-OR 90TH 227 5.10F-10 b.30F-t0 55CS t39 b.30E-ng 7.20F- nq 90TH 22? ,.QOF-0Q t.00E-0A 5b65 139 2.uOE-0Q 2.70E-0Q 90TH 229 2.20F-0 0 2.70E-09 5hBA 140 2.lOE-0q 2,unE-09 90TH 230 h.S0E-nq 7.SOE-nq 56BA 1UI U.IOF-o9 qt90F-0Q Q0TH ?32 S.OOF-OQ U.nOE-Oq 5b6A 1u2 7.9*E-09 9.00E-DO qOTH 23u 1.1OE-10 1.30F-10 57LA lU0 1.50E-0R 1.70E-08 91PA 231 2.20F-0Q ý.70E-09 57LA 141 2.5vE-10 2.5nE-t0 qtPA 233 1.30F-09 1.50F-99 57LA IQ2 1.50E-OR t.ROE-05 92U P32 2.5qF-12 2.b9E-11 58CE ]at 5.50E-10 b.20E-t0 92U 233 2.30E-09 2.rtOF-o9 58CE 143 2.20E-0q 2.50E-0Q 92U 234 b.32F-13 1,59E-10 58CE Uaa 3.20F-10 3.70F- 10 q2U 235 i.20F-Oq 4.OOF-ng 59PR 143 0.0 0.0 92L P3b 2. IF-I I .80E-11 59PR IOU 2.OOF-10 '.3nF-10 92U 237 t.00F-09 1.30E-0q bOND 147 1.00E-0q 1.20E-09 92U 238 1.10F-10 1.50E-10 blPM I7 0.0 0.0 13NP 2;7 1.40F-09 1.bOE-Pq tIPM 4RM4 1.UtF-.F0 5 6.-01- 93NP 238 2.8nF-09 3.20E-oq bIP4 10B u*hOF-09 5.3f5--*9 93NP 23q 9.50F-10 1.10E-0q bIPM 14Q 2.50E-11 2.QoE-il Q9PUJ 238 1.30E-12 1.80F-11 biPH 151 2.2'F-OQ 2.30E-o9 9LPU P39 7.90F-13 7.70E-12 

                                                        94PU    240   1.30F-12     t.80E-11 b25    151     u.80E-11    2.10F-10

b2SM 53 2.70F-In 3.0OE-10 9LPU 241 4.h0E-12 b.80E-12 13EU 152 7.37E-09 3.53E-0O QUPU 242 1.10F-12 1.60F-11 63EU 15u 7.BUE-09 4.00F-19 9qPki 2441 8.95E-10 1.62E-10 b3EU 195 I.RIE-10 U.33E-10 9SAM 241 1.801E-10 2.60F-10 b3EU 156 7.80F-09 3.70E-Mg 95AM.4??4 2.h6F-11 1.80E-1l 65TB 160 A.6(0E-A9 1.00E-0A 95AM 24.3 1.30E-09 1.50E-09 67H40 I664 5.90F-00 1.OOE-nS 96CM 2U2 5.50E-12 2.30E-11 7UA 181 2*10F-12 2,ROE-12 96CM 243 2.30F-Oq 2.90E-0Q 7Ui 185 n 0 .0 a 96CM 2ila 2.qnE-12 1.8OE-11 74" 187 3.1'E-AQ 3.bOE-09 96CM 245 9,50E-10 1,20E-09 82PH 210 1.30E-11 1.70E-11 96CM 246 1.00E-12 1S50E-11 

 381B 213     0.0          0.0                          96CH   ?P7   2,20E-0Q      2.bOE-09 RaPO   210     5,10E-'1    b.2OE-tu                      9bCM   2a8   6.8IE-0q      5.23E-09
                                                        98CF   252   b6b0F-0R      7.20E-08
                                          1.109-29

called bioaccumulation factors in this guide, can be found in the literature (Pnf. 19). The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose for consumption of aquatic foods.

Rap = 1100 Uap Q.B. D *exp(-Aitp (A-3) 

                                  i    aipj
                                        ,          p Values of Bip are given in Table A-8; the other parameters have been previously defined.

The transit time tp may be set equal to 24 hours to allow for radionuclide decay during transit through the food chain, as well as during food preparation.

c. Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with suspended and deposited materials. One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21). Based on these references, an estimate of the radio- nuclide concentration in shoreline sediments can be obtained from the following expressions: 

          C.s     Kc Ciw[l
                      1w   - exp(-.it)]
                             i                                                           (A-4)
                 isc where Cis      is the concentration of nuclide i in sediment, in pCi/kg;
             CiW      is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter;
              Kc      is an assumed transfer constant from water to sediment,  in liters/kg per day;
               t      is the length of time the sediment is exposed to the contaminated water, nominally 15 years (approximate midpoint of facility operating life), in hours; and Ai      is the decay constant* of nuclide i, in hours-l. In the original evaluation of the equation, Xi was chosen to be the radiological decay constant, but the true value should include an "environmental" removal constant.

The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period of several years in the Columbia River between Richiand, Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 22 and 23). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters nn*wmeter above the sediment, an effective surface contamina- tion was estimated. This surface contamination was assumed to be contained within the top 2.5 cm (I in.) of sediment.** The dose contribution from the radionuclides at depths below 2.5 cri was ignored. The resulting equation is Si 1 iCi WDl MOT - exp(-Ait)] (A-5) where Si is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations; 

  If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).
 With a mass of 40 kg/m 2 of surface.

1.109-30

TABLE A-8 BIOACCUMULATION FACTORS 

                           CpCilkg per pCi/liter)
           FRESHNATER                               SALTMA17ER

ELEMENT FISH INVERTF3RATE PLANT PIS' TIVERTE3RATE PLANT H 9,0E-Ol q.oE-01 9.OE-01 9.OE-ni 4.3E-01 9.3E-01 HE 1.0E 00 1.0f 00 10Elf 1.0ffO0 1.fOE 00 t.OE no LI 5,0E-Ol C.oE: 01 3.0E 00 5.OE-01 50fE-Ol 3.0E 00 BE 2.OE 00 InE 01 2.0E 01 ',OE 02 e.OE 02 1.OE 03 B 2.2E-01 5.OE 01 2.2E 00 2.2E-Ot QO.E-01 2.2E oA C U. 03 

              0E    Q        03     4.bF 03     t.5F Os         1.14E 03   1.8E 03 N        1.5ES 05     1.;E 05        1.3f3E 04   h. E 04         1T7E "04   1 .0f p0

0 9.2E-O 9.?fE-01 9.2E-0l 9.bF-01 9.bE-01 Q.bE-O0 F 1.0E 01 1 .oE 02 2.0E 00 3.bF 00 3.6f on 1 .4E 00 NE I.OE O0 I.nE 00 1.r E 00 1.0E 00 1.0OE 00 1.OF 00 NA I.OE 02 2.oE. 02 5.OE 02 b.7E-02 1.QE-01 9.SE-O1 MG 5.OE 01 1.oE 02 1.0OE 02 7.7Ff-01 7.7fE -01 7.7E -0 1 AL ioE0f 01 6.;E 01 U.2E 02 1.0OF n1 b.OE O0 6.OE 02 SI 2.5E 00 2.';E 01 1.3E 02 1.0f 01 3.3E 01 6.7P 01 F 1.0oE 05 2.oE. OU 5.0E 0'; 2.fE n4 3.0E O4 3.0E 03 T 7.5E 02 I.oE. 02 1.0E 02 1.7E 00 4,UE-01 U.4E-01 CL 5.0E 01 .ofE 02 5.OE 01 1.3E-02 I.QE-02 7.6E-02 AR I.OE 00 1.nE 00 1,OE 00 1.0ffno I.OE 00 1.OE 00 K I.OE 03 8.lE 02 6.7E 02 1.IE 01 .6fE 00 2.6E 01 CA 4,OE 01 3,3E 02 1.3E 02 5.0E-Ol 1.3E 01 5.OE 00 SC 2.0f 00 1.fE' 03 t0OE 0Oi 2.0fE 00 1.fOE 0 Q I.0 E 05 TI t.OE 03 3.OE. 03 5.OE 02 1.OE o3 1.OE 03 2.0E 03 V 1.OE 01 3.E 03 1.0E 02 1.0E Ol 5.OE O i.OE 02 CR 2.0E 02 2.nE 03 . ",OE 03 4.0E 02 2.0E 03 2.0E 03 m,,40OE 02 9.oE 04 1.0fE 04 5.5E 02 * 4.OE 02 5.5E 03 FE 10OE 02 3.pE 03 1.0E 03 3.0E 03 2.OE O4 7.3E 02 c0 5fOE 01 2.nE 02 2,0E 02 .0OE 02 I.0E 03 I.OE 03 NI 1.OE 02 1.OE. 02 5.0E 01 I.OE 02 2.5E 02 2.5E 02 CU 5.OE 01 'i.nE,02 2.0E 03 .7ffE02 1.7f 03 1.0E 03 ZN 2.0E 03 i.nE 04 2.0E 04 2.0E 03 5.0E OU 1.0E 03 GA .3E 02 6.7E 02 1.7fE 03 3.3fE 02 b.7E 02 1.7fE 03 GE 3.3E 03 3.fE- 01 3.3E 01 3.3E 03 1.7fE OU 3.3E 02 AS 1.OE 02 i.nE. 01 3.0E 03 3.3E 0R 3.3E 02 1.7E 03 SE 1.7E 02 1.7E 02 1.0E 03 4.0E 03 1.0E 03 1.0E 03 BR 4.2E 02 3.iE 02 5.OE 01 1.5E-02 3.1E 00 1.5E 00 KR 1.0E 00 1.nE:00 102 0:0 Ij0E 0 . f0E 00 .0fE 00 RB 2.0E 03 i.nE, 03 t.0E 03 8.3E 00 1.7E 01 1.7E 01 SR 3.0E 01 l.nE 02 5.0E 02 2.0E 00 20OF 01 I.OE 01 Y 2.5E 01 1.0E 03 5,OE 03 2.5E 01 .0OE 03 5.OE 03 ZR 3.3E 00 6.7fE 00 1.0E 03 2.OE 02 OE n1 I.OE 03 NB 3.0E Oi l.nE u2 8.OE 02 3.0E n4 I.OE 02 5.0E 02 Mo 1.0fE 01 1.nE' 01 I.OE 03 f0 

                                                    OE          1.0fE 0t   1.0fE 01 TC      I.5E 01      5.Off 00       U.0f1        1.0f     1O     5.0fE 01   4,OE 03 RU       10OE 01     3.0E 02        2.0E 03        .0OE 00       1.0E 03    2.OE 03 RH      1.fOE 01     3onE:02        2.OE 02      1.OE 01         2.0OE 03   2.0E 03 PD      1.0E 01      3.0E 02        2.OE 02      I.OE Ot         2.0E 03    2.0E 03 AG      2.3E 00      7.7Ef 02       2.OE 02      3.3E 03         3,3E 03    2.0E 02 CO      2.0E 02      2.nE. 03       1.0E 03      3.0E 03         2.5E 05    1.0E 03 IN      I.OE 05      l.nE 05        1.0E 05      1.0E 05         I.OE 05    I.OEf 05 SN      3.OE 03       1.0E 03       1.OE 02      3.0E 0          1.0fE 03   t.OE 02 sB      1.OE00       1..ff,01       1.5E 03 1JQ,OE 01            S.0IE 00   1.5E 03 TE      4.OE 02*      1.0E. 05      I.OE 02*     I.OE 01**       I.OE 05    i.OE 03**

1 1.5E Ot 5.0E 00 4.OE Ol I1.0E 01 5.0F O0 I.OE 03 

                                  1.109-31

TABLE A-8 (Continued) 

                      FRESHWATER                            SALTWAE;ý
      ELEMENT     FISH     INVERYF3PATE      PLANT          TrIH     T1JVEITE3RATE      PLA'NT
      XE           I .0E  00   I . nE 00     I .OE 00    1 0OE 00       I.O0E 00             00
      CS                  03                                     oft                 I

5. nE Dl

                   2,OE        I PoE 02      5.OE 02     0i 0OE         2.5f 01 BA
  • 0E 00 2.0E 02 5.OE 02 1 0OE 0! 1 . 0OE 02 5.OE 02 LA 2.SE 01 I .nE 03 S.E 03 2. 5E 01 I if E 03 03 CE 1.OE 00 1.nE 03 4*OE 03 t I.OE O b.6OE 02 b.OE 02'
      PR           2.5E   01    I.OE 03      5.OE 03     2.5E O         I.OE 03     5.OE 03 ND           2.5E   01   I.nE, 03      S.OE 01     2.5E 01        1.OE 03     5.6c 03 PM           2.5E   01   IoE' 03       5.OE 03     2.5E 01        1.0E 03     5.OE 03 Sm           2.5E   01   I.OE 03       5.OE 03     2.5E 01        1.OE 03     S.nE 03 EU           2.5E   01   1.nE 03       S.OE 03     2.SE n1        1.0E 03     S.OE 03 GD           2.5E   01    10oE. 03     5.hE 03     2.5E 01        1,OE 03      5.OE 03 TB           2.5E   o0   1.oE 03       5.OE 03     ?.SE 01        1.0E 03      5.0F 0.3 DY           2,SE   01   I.oE 03       5,OE 03     2.SE 01        I.OE 01     5.OE 03 HO           2.5E   01   1.OE 03       5.OE 03     2.SE o0        I.oE 03     5.Or n3 ER           2.5E   01    I.oE 03      5.OE n3     2,5E 01        I.OE 03     5.OE 03 TM           2.5E   o0    1.hE 03      S.hE 03     2.SE 01        t.OE 03     S.OE 03 YB           2.5E   01   1.oE 03       S.OE 03     2.5E o1        I.OE 03      5.OE 03 LU           2.5E   01    1.nE 03      5.OE 03     2.SE O0        1.OE 03     5.OF 03 HF           3.3F   00   6,7E. 00      I.OE 03     2.OE 02        2.OE 01     2.OE 03 TA           3.OE   04   b.7E-02       8,OE 02     3.OE Ol        1.7E 04      I.OE 03 W            1o2E   03    1.oE 01      1.2E 03     3.0E 01        3.OE 01      3.OE 01 RE           1.2E   02   6.nE 01       2.UE 02     U.E 00         b.OF 01      2.uE 02
      0S           1.OE   01   3.0E 02       2.OE 02     1.OE 01        2.OE 03      2.OE 03 rR          I.OE   01   3.E'    02    2.OE 02     1.OE (1        2.OE 03     2.E 03 PT           1.OE   02   3.nE 02       2.OE 02     1.OE 02        2.OE 03      2.0E 03 AU           3,3E   01   5oE 01        3.3E 01     3.3E 01        3.3E 01      3.3E 01 HG
      TL
      PB
      B
                   I.OE
                   1,OE
                   1.OE
                   t.SE
                          03
                          04
                          02 o0
                               1.oE 05
                               1.;E 04
                                1.nE 02 I.OE 03 I.OE 05
                                             2.OE 02
                               2.aE 01"**2.E 01***tS
                                                         1.7E 01
                                                         1.0E 04
                                                         3.OE 02
                                                         1.5E 01
                                                                        3,3E 34
                                                                        1,5E 04
                                                                        1,E 03
                                                                        2.UE 01"**
                                                                                     t.OE 03 I1.E 05
                                                                                    5.OE 03
                                                                                     2. a F**0 1 i
      PD           5.OE   02   2.nE Ou       2.OE 03     3.OE 02        51OE 03      2.OE 03 AT           1,5E   01   5,E'    00      .. OE 01  1.OE                        4.0;7 03 RN           1.OE   00    I.oE 00      t.OE 00     1,OE 00         1,OE 00     I.OE 00
      FR           4.OE   02   1,oE 02       8.OE 01     3,OE 01        2.OE 01      2.OE 0l RA           5.OE   01   2,'E 02       2.5E 03     S.OE 01        1,OE 02      I.OE 02 AC.          2.5E   01    1.oE 03      SOE 03      2.5E 01        I.OE 03      5.OE 0O
      TH           3.OE   01   5.nE 02       1.5E 03     t.OE 01        2,OE 03      3.OE 03 PA           1.IE   01      .iEE 02    1.IE 03     I.OE 01        I.OE 01     6.OE 00
      U            2.OE   00   6,OE: O0      S.OE-0      1.OE 01.       !.OF 01      b.6E 01 NP           I.OE   01    4.nE. 02     3.OE 02     I.OE o1        1.OE 01      i. OE 00
      PU           3,5E   00    I.oE 02      3.5F 02     3.OE 00        2.OE 02      I.OE 03 AM           2.5E   01    1.0E 03      5.OE 03     2.SE 01        1.OE 03      5.OE 03 CM           2.5E   01   1.nE. 03      S.OE 03     2.5E 01        1.OE 03      5.0E 03 BK           2.5E   01    I.nE; 03     5.0E f3     ?.SE 01        1.OE 03      5.OE 03 CF           2.5E   01    I.oE'03      5.OE 03     2.SE 01        1.OE 03      5.OE 03 ES           I.OE   01   1.oE, 02      I.OE 03     I.OF 01         I.OE O0    b.OE 01 I.OE   01    1.E 02       I.OE 03     I.OE 01         I.OE 01     bOE 01
 *ORNL - Private Communication
    • Freke, A.M., "A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol. 13, p. 749, 1967.
      • Derived from data in Bowen, H.J.M., Trace Elements in Biochemistry, New York, Academic Press (1966).
                                             1.109-32

Ti is the radiological half-life of nuclide i, in days; and W is a shore-width factor that describes the geometry of the exposure.

Shore-width factors were derived from experimental data (Ref. 24) and are sunanarized in Tdble A-9. They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.

The combination of Equations (A-4) and (A-5) into the general Equation (A-i) leads to 

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

Rapj U 

                           ap     S*D
                                 i aipj U W
                                                   100Iap       Ciw Ti Daij [  - exp(-- t)]                  (A-6)
                                    U III W
                         110,000       --
                                       F  '--.
                                                     lli Dipj.[exp(-."\t QiT                 iP )][l - exp(-:i1t)]                (A-7)
        d.    Dose from Foods Grown on Land Irrigated by Contaminated Water The equations in the following paragiaphs can be used to calculate doses from radio- nuclides in irrihjated crops.                 Separate expressions are presented for tritium because of its unique environmental behavior.

(1) Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The rmodel used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 4). 

                       The equation for the model (for radionuclides except tritium) is presented below in slightly modified form.              The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility. Thus for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg,                 is given by:
                                                                                                             (A-8 )
                iv       i"       - exp(- '"U t e)]v       Biv[I - ex 1(-'P 'itb)1]exp(-..it )
 The de;,osition rate, di,          from irrigated water is defined by the relation d'i = Ciw      (water deposition)                                                         (A-9)

I where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I is the irrigation rate, in liters/m2 /hr; i.e., volume of water (liters) 

                              sprinkled on unit area of field in 1 hour.

For tritium, the equation for estimating Civ is (see Ref. 25): 

                              Cv M Ctl                                                                      (A-10)
                       For a cow grazing on fresh forage,               te in Equation (A--8)  is set equal to 720 hours
  (30 days),    the typical time for a cow to return to a particular portion of the grazing site.

1.109-33

TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6) 

     EXPOSURE SITUATION                      SHORE-WIDTH FACTOR, W
   Discharge canal bank                                  0.1 River shoreline                                       0.2 Lake shore                                           0.3 Nominal ocean site                                   0.5 Tidal basin                                           1.0
                                TABLE A-10
                        ANIMAL CONSUMPTION RATES
                                                                   I
                             FEED ORQFFORAGE             QAw WATER
                            (kg/day [wet weight])
   ANIMAL                                              (;./day)
   Milk cow              50 (pasture grass)                60
   Beef cattle           50 (stored feed grain)            5o From Reference 4, Tables 111-B and -10.

1.10g-34 P

(2) Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water. The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref. 4) is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w): 

          CiA = F iAECiFQF + CiAwQAw]                                                                                (A-li)
                 The second set of terms in the brackets in Equation (A-1l)                             can be omitted if the animal does not drink contaminated water. Values for QF and QAw are presented in-Table A-i1.

Values for Biv and FiA are given in Table C-5 (see Appendix C).* 

                 The total dose Rapj from irrigated foods (excluding tritium) is given by:
          Ra           veg    CiD          + Uanimal ap            Y
                                                             *   iA Daipj                                            (A-12)
            apj        ap        iv aipj If values for Civ from Equation (A-3) and CiA from Equation (A-11)                             are substituted in Equation (A-12):
                                            veg i[)Da [            -  exp(- Ei te)]        Biv[l - exp(-'it )]*
                                                                      v,                    iv      Xi        Lb apj R      ve ap     dix(,           ipJai hi                      YvEi
                                                                                    - -r[lexp( '1Ei te)]
                             U panima ap             iA ai pj OFui                     /  ~v Y- Ei (A-13)
                          +    +PN- exp(-,.,itb)]
                            Biv[l        i           )]+ CiAwQAwj It should be noted that the two components of Equation (A-12) imply that contribu- tions from the individual vegetable and animal products have already been summed.                                  In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)).
                  For tritium, the concentration in animal products is given by the following equation (adapted from Reference 25):
                  kWCv +QAwCAw                                                                                        (A-14)
           CA -           +kQCA
                      m            in Since by Equation (A-IO) Cv = Cw,                   and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows:
                   kC
           CA = 3        (w + QAw)                                                                                    (A-15)
                    in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):
            Rapj : U
           Ra.          ve Cvapj"
                       u~gvap D       + Uap        Aaj(-6 animal CAD    apj                                                            (A-16)
                                  Uve v,,animal Da             (w+     QAw)                                            (A-17)
                   V uea       apjs + Uap Daa                   apj-inab           Q(C--.
         fr FA appear as Fin and Ff in Table C-5.

Valus 

                                                                 1.109-35

REFERENCES FOR APPENDIX A 1. "Final Environmental Statement Concerning Proposed Rule Making Action: Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents," 

   USAEC Report WASH-1258, Washington, D.C., July 1973.

2. J. K. Soldat et al, "Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.

3. "Food Consumption, Prices, and Expenditures," AER-138, U.S. Department of Agriculture, Washington, D.C., December 1974.

4. J. F. Fletcher and W. L. Dotson (compilers), "HERMES - A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Peport HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.

5. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (;.Ci/m2),' Itemi 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.

6. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-,41638, General Electric Co., Richland, W'ash., February 1956.

7. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption - 

   Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA,
   Seattle, Wash., June 1971.

8. "The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.

9. "Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September 1974.

10. "Radiological Health Handbook," USPHS, Rockville, Md., January 1970.

11. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1311 Dose to the Thyroid," IRS-W-5, Institute for Reactor Safety, Cologne, Germiany, April 1973.

12. P. S. Rohwer and S. V. Kaye, "Age-Dependent Models for Estimating Internal Dose in Feasibility Evaluations of Plowshare Events," ORNL-TM-2220, Oak Ridge, Tenn., April 1968.

13. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I 

   and 137Cs to the Atmosphere," Health Physics, Vol.   17, pp. 51-57, July 1969.

14. W. S. Snyder, "Dosimetry of Internal Emitters for Population Exposure," in Population Eýx ures, CONF-741018, Proceedings of the Eighth Midyear Topical Symposium of the Health Physics Society, Knoxville, Tenn., October 1974.

15. "Report of ICRP Committee II on Permissible Dose for Internal Radiation, International Commission on Radiological Protection," ICRP Publication 2, Pergamon Press, 1959.

16. J. K. Soldat, "Modeling of Environmental Pathways and Radiation Doses from fluclear Facilities," USAEC Report BNWL-SA-3939, Pacific Northwest Laboratory, 1971.

17. C. M. Lederer et al, Table of Isotopes, 6th Ed., John Wiley and Sons, Inc., 1967.

18. S. E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, Lawrence Radiation Laboratory, October 1972.

1.109-36 

                                                                                                  1

19. J. K. Soldat, "A Statistical Study of the Habits of Fishermen Utilizing the Columbia River Below Hanford," Chapter 35 in Environmental Surveillance in the Vicinity of Nuclear Facilities, W. C. Reinig (ed.), Charles C. Thomas Publishers, 1970.

20. J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.

21. J. L. Nelson, "Distribution of Sediments and Associated Radionuc:lides in the Columbia River below Hanford," p. 3.80 in "Hanford Radiological Sciences Research and Development Annual Report for 1964," D. W. Pearce and J. K. Green (eds.), USAEC Report BNWL-36, Pacific Northwest Laboratories, 1965.

22. G. L. Toombs and P. B. Cutler (compilers), "Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5, 1961 - July 31, 1967," Oregon State Board of Health, Div. of Sanitation and Engineering, 1968.

23. "Handbook of Radiological Protection, Part I: Data," prepared by a panel of the Radio- activity Advisory Committee (H. J. Dunster, Chairman), Dept. of Employment, Dept. of Health and Social Security, Ministry of Health and Social Services, Northern Ireland, Nlumber SNB 11 360079 8, Her Majesty's Stationery Office, London, England, 1971.

24. L. R.. Anspaugh et al, "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.), 

   CONF-710809, 1973.

1.109-37

APPENDIX B 

                                   MODELS FOR CALCULATING DOSES FROM
                               NOBLE GASES DISCHARGED TO THE ATMOSPHERE
     The following analytical models are used for calculating doses from exposure to gaseous effluents. Separate models are given for air and tissue doses due to gamma and beta rays.

Except for the case of noble gas doses resulting from elevated releases, all models assume submersion in an infinite cloud at the exposure point.

1. Annual Gamma Air Dose from Elevated Releases of Noble Gases Slade (Ref. 1) describes the derivation of the equations for estimating annual air doses from photon emitters dispersed in the atmosphere. The following expression can be used for calculating annual doses: 

                     D 260
                             n un s      I                      )1    Dik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.

The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient. Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki I [AmEmpa(Em)]/[Ekwa(Ek)] (B-2) 

                   m where A       is the fraction of the disintegrations of nuclide i yielding photons m     of energy E
               Em      is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em)       is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined. The summation is carried out over all photons within energy group k. Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2. For radionuclides not contained in Reference 2, data were obtained from Reference 3.

Decay during travel from the point of release to the receptor is QD = Q* exp(-Xir/un) (B-3) 

 The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays. Annihilation and bremsstrahlung photon radiations are possible contributors to this compunent of the air dose.

Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures. (See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors.") 

                                                1.109-30

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

                                                                  1 Ai     is the decay constant of nuclide i, in sec"
     All other parameters are as previously defined.

2. Annual Gamma Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents. The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.

The annual average ground-level concentration of gaseous effluent species i at location (r,o) from the release point is determined from xi(ra) = 3.17 x 104 Q*[x//Q' 1D(r,o) (6-4) where xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 , and 

    [/Q')1D(r,o)    is the annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle e at the distance r from the release point,.
                    in sec/mi3 The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year. All other parameters are as previously defined.

The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then I 

          DY(r,e) or DO(r,e) =    xi(re)(OF* or DFO)                                  (B-a)

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

Table B-1 presents a tabulation of the dose factors for the noble gases and daughters of interest.

3. Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas. The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue.

a. Elevated Releases The annual total body dose is computed as follows: 

          DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t]                                   (B-6)
  Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed. (See Regulatory Guide 1.111.)
  The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.

I 

                                               1.109-40

TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Nuci ide a-air* (DFB) y-Air* (DFB) y-Body (DFBi) Kr-83m 2.88E-04 1.93t-05 7.56E-08 Kr-85m I . 97E-03 1 .46E-03 1.23-03 1 17E-03 Kr-85 1 .95E-03 I.34E-03 1. 72E-05 1.61E-05 Kr-87 1 . 03E-02 9.73E-03 6. 17E-03 5 92E-03 Kr-88 2. 93E-03 2. 37E-03 1.52E-02 1 .47E-02 Kr-89 1.06E-02 1. 01 E-02 1.73E-02 1 .66E-02 Kr-90 7. 83E-03 7. 29E-03 1.63E-02 1 56E-02 Xe-1 31m 1.11 E-03 4. 76E-04 1.56E-04 9. 5E-05 Xe-1 33m I .48E-03 9. 94E-04 3. 27E-04 2.51 E-04 Xe-i133 i .05E-03 3. 06E-04 3.53E-04 2.94E-04 Xe-i 35m 7. 39E-04 7.11 E-04 3. 36E-03 3.12E-03 Xe-1 35 2: 46E-03 1.86E-03 1.92 E-0:3 1.81E-03 Xe-1 37 1.27E-02 1. 22E-02 1.51 E-0:3 1 .42E-03 Xe-138 4. 75E-03 4.1 3E-03 9.21 E-03 8.83E-03 Ar-41 3.28E-03 2. 69E-03 9.30E-03 8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr

    • '2.88E-04 = 2.88 x I0"4
                                         1.109-41

Symbols for this equation were defined earlier in Regulatory Position C.2.c of this guide. The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.

The skin dose has two components, the ganmia and beta contributions. The skin dose rate is computed by DS(r,o) 1.11 x SFD Y(r,o) + 3.17 x 1041 Qi(x/Q']D (r,o)DFSi (8-7) 

                                                       1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.

The skin beta dose factors OFS were determined using the decay scheme source docu- ments cited above and the methods used in References 4, 5, and 6.

b. Ground-Level Releases The annual total body dose is computed as follows: 

           DT(r,o) = 1.11 x SF ýxi(rO)DFBi                                               (B-8)
           Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.

The annual skin dose is computed as follows: 

           Ds(r,o) - 1.11 x SFFZxi(r'e)DFi +     xii(ro)DFSi                            (8-9)

where D5 (r,e) is the annual skin dose due to immersion in a semi-infinite cloud in I1 the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra) is the airborne concentration of radionuclide i at point (r,6), in pCi/m 3 . 

                                               1.109-42 I

REFERENCES FOR APPENU.X B I. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-24190, 1968.

2. M. J. Martin, "Radioactive Atoms, Supplement I," USAEC Report ORNL-4923, November 1973.

3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO- 

  12037, 1970.

4. R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.), Academic Press, New York, 1956.

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

  73-107, 1973.

6. M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol. 26, pp. 1-12, January 1974.

1.109-43

APPENDIX C 

                               MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
                                     FROM RADIOIODINES AND OTHER RADIONUCLIDES
                                             DISCHARGED TO THE ATMOSPHERE

I. Annual External Dose from Direct Exposure to Activitv Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,o) with respect to the release point may be determined by 

                          1.1 x  10,       (rc~  Q!                                         (Cý-l)
             Ci(r'c)                               1 1-exp(-Xit)j
'-here C . is the ground plane concentration of the radionuclide i in the sector at angle - at the distance r from the release point, in pCi/m2;
                   Qi     is the annual release rate of nuclide i to the atmosphere,           J'i/yr;
                  t       is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life).      This is a simplified method of approximating the average deposition over the operating lifetime of the facility;
                          is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport,       in mn-2 ; and is the radiological decay constant for nuclide i,      in yr-1 .
       The annual    dose from nuclide i resulting from direct exposure to the contaminated ground plant is then D   (r ,)      8760 SFCG(r,r.)DFG                                              (C-2)

where D.j(r,*) 

                          is the annual dose to organ j from the ground plane concentration of nuclide ii i at the location (r,r,), in mrem/yr;

and other terms are as defined previously in Regulatory Position C.3.a of this guide.

The annual dose to organ j is therefore D (r,o) = 8760 S C9(r,o)DFGi (C-3) 

                      i          F     I1 Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7. The annual dose to all other organs is taken to be equivalent to the total body dose.

Does not include noble gases or their shurt-lived daughters; see Appendix B.

1.109-45

2. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide i at the location (r,t!) -ith res- pect to the release point may be determined as Xi(r,o) 3.17 x 104QQ[X/Q'] D(r,) (C-4) where is the release rate of nuclide i to the atmosphere, in Ci/yr; 

         xi(r,O)      is the annual average ground-level concentration of nuclide i in air in the sector at angle 6 at distance r from the, release point, in pCi/m 3 ;
   [./Q']D(r,o)       is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111).    This includes depletion (for radiolodines and particulates)
                      and radioactive decay of the plume; and
               4
      3.17 x 10       is the product of the number of pCi/Ci and sec/yr.

The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then iiaa= xi(ro)RaDFAiija DDA (rO) (C-5) 

      Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.

The annual dose to organ j in age group a from all nuclides in the effluent is: 4 DA (ra=R(C-6) 

           Dja(r,o)    Ra zxi(re)DFAija

3. Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is six:ilar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.

For all radioiodines and particulate radionuclides, except tritium and carbon-14, the con- centrition of nuclide i in and on vegetation at the location (r,Q) is estimated using CV(rO) di(r,o) r[l - exp('AEite)] Biv[l - exp(-Ytb)]] exp(-1ith) 

                        '          '     Ax         +        PXti                         (C-7)
      See Regulatory Position C.l of tnis guide for definitions of terms.

Carbon-14 is assumed to be in oxide form (CO and C02 ). The concentration of carbon-14 in vegetation is calculated by assuming that its ratio to the natural carbon in the vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 1 and 2). 

                                                                                                       I
                                                 1.109-46

TABLE C-1 ADULT INHALATION DOSE FACTORS 

                                         (mreni/pCi inhaled)
    NUCLIDE       A0IE     LIVER     TfTAL 9')Y                   KI)NEY                  GI-LLI
  I         3  0.0          1.3QE-07    t.34E-07        1 .34E-07  S.3LIE-07 1 I 34E-07    1 3LiE-0 7 UBE     10                                                      0.0
                I .qSE-OU  3.OhE-05     U.QbE-Oh                             ?.23E-Ou      1 .b7E-05 bE      I*l                                          u.L?7E-07             u.27F-07     Li.*27E-07
               2.28E-O0    4.27E-07    u.27E-17                   4.27E-07
  7N      13   6.27F-Oq    b.27E-09     h.27E-01       8.27E-09   6.27F-OQ   6 *27E-O9        *.27F-09 QF      14   4.71E-07    0.0         S.20E-oS        0.0        0.0        n.0          9.24E-09

11NA 22 1. 30F-05 1.30E-n5 1.30E-05 I 30E-05 1I 30E-05 I,1 E-n5 1 , 30E -09 1 1 NA 2a 1 .b9E-O6 t.69E-Ob 1.69E-0b I .69E-Ob 1 ,bqE-06 1 69F-Ob 1 .bqE-Ob ISP 32 I .b5E-0O4 9.65E-Ob 6.27E-Oh 0.1 0.0 0.0 1

  • 08E-05

20CA 4L 3.83E-05 0.0 U.II3E-Ob 0.0 0.0 0=0 2.AbE-07 

               3.51E-05    1.07E-04    3.11E-05        0.0        I .OOE-0O               3.23E-05

215C Ub S. OE-06 24CR 51 0.0 0.0 1.25E-0R 7.u"UE-09  ?. 5SE-09 1 .75E-06 uL I 5 E-07 25MIN 54 0.0 +/-.95E-0b 7.A7E-07 0.0 I I23F-06 9.b7E-Ob 25 'N 5b 0.0 1.55E-10 2.29E-11 0.0 I.b3E-10 1 .18E-06 2.53E-06 

               7.b2E-06    3,43E-05    9.O0E-0B                   0.0                    "7.SuF-Ob

26FE 55 0*.0 ;o.RE-05 

?6FE     59    I .a7E-Ob   3.47E-03    1.32E-06        0.0        0.0        1 .27F-04    2. 3SE-05
?7CO     57    0.0         5.bSE-08    B.39E-0O        0.0        0.0)       *.62F-05     3.93E-06

27C0 98 A 0 I.QBE-07 2.SQE-07 1 .16bF-04i I I ;3L-05 27CO bo 0.0 1.u4E-nb 1.8SF-Ob 

                                                       0.0
                                                                             7,L7E-04     3I. ,*,3E-OS
                                                                                                 .':6, -05
                                                       0o0        00

28NI 59 ",0OE-0b 1.4bE-O b.77F-07 0.0 0.0 A,21E-06 b. 1 IE-07 28-1 65 5.40E-05 3.92E-nh 1.PtE-06 0.0 0.0  ?.23E-05 1 .67F-06 

               1 .92F-I0   ?.62E-11    I.IaE-tl        0.0                   7.01E-n7      I , 5E -0O
               0.0         1.83F-10    7.b9E-1I                   5,7 8 F-10   *.L1E-07   h. 12E-06

29CU b6 0.0 30ZN 65 L.0 hE-Oh 1.29E-05 S.PE-,)h 0.0 8.b2E-0b I .OE-04 b.bBF-06 30ZN 694 1 .02F-09 2.L5E-nq 2.2LE-I0 0.0 I. Q48E-09 2,39E-Ob I .71E-05 30 N 59 4.23F-12 0.13E-12 5.61;E-13 5.27E-12 1.15E-07 2,0* E-09 

                                                       0.0

3uSE 79 0.0 3.83E-n7 6.0QE-O0 5.bQE-07 Li. LiE-OS 

                                                                                          3.33E-Ob

359R S2 0.0 3.0 1.6hE-06 0.0 0.0 n100 I . 30F-0b 35HR 93 0.0 0.0} 0.0 0.O 2.qOE-08 

                           3.0         3.O0E-OR                              0.0

353P 84 0.0 0.0 3.91E-08 0.0} 0.0 2.05E-1 3 353R 85 0.0  !.hAE-09 0.0 0.0 0.0 0.0 

               0.0                                     0).0

374B 5h 0.0 1.6QE-O5 7.3RE-Ob 0,0 0.0 

                                                                             0.0          2.08E-O0

37RB 87 0.0 2.88E-07 

               0.0         ;.87E-Ob    3.?IE-0h                              0.0

37RR 58 3.85E-B8 P.4iE-08 0.0 0.0 4,i11E-1I 

               0.0

37BR Bq 3.21E-OB 2.12E-O0 0.,0 0.0 0.0 0,0 3BSR 3.8OE-05 0.0n 4**37E-05 3ASR 

         89
         90
                           0.0         1.09E-Ob                              I .75E-04 I .2"E-02   0*0         7.6?E-111       0.0
                                                       0.0A       6,0        I .20E-03   9.02E-05

38SP 91 7.9"E-09 0.0 3.,qE-10 0.0 0.0 u.92F-Ob 2,59E-05 3ASR Q2 8. 4 1E-1O 0.0 3.64E-11 0.0 0.0 2.06E-Ob 5.3RE-Ob 39Y 90 

         qO1  2,b6E-07     0.0         7.01E-09        0.0
                                                       0.0        0.0        2.12E-05    6.3PE-05

34Y 3QY 9 1U 3.?2 E- II 0.0 1.27E-12 0.0 0.0 1 .6bE-I 0 

                                                                             2.L1E-07

39Y 91 5.78E-05 0.0 1.55E-06 0.0 2.1 3E-0 4 4.81E-OS Note: 0.0 means insufficient data or that the dose factor is <].OE-20.

1.109-47

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

        934 3.lOE-05   1.0IF-n5     2.AqE-n6      A.0         1.IE -0S    3.1IF-n    2,;BEE-0b.

UINB 95 1,7kF-0 *.77E-n7 5.2hE-07 0.0 9.b7E-n7 b.12F-05 I.30E-65 

 41N8   97  2.783E-11  7.03E-12     P.56E-I?      0.0         5. 1E-12      .oOF-07       1.2F-0H

u24n 93 0.0 1.17F-nb 3.17E-1; q.n .S55E-07 5.11E-05 1.7qF--t U2MD Q9 0.0 1.51E-0B 2.87E-19 0,n  ;.°UE-nB 1,1 AE-05 i.10-05 431C 994 0.n 3.64E-13 4 .h3E-1P 0.0 5.52E-12 P.SbE-n9 S.20F-n/ 437C 9q 0.0 U.64F-0R I.37E-04 0.0 5.95E-07 l.nIE-04 7.SuEE-0b Q3TC 101 0.0 7.52E-15 7.38E-14 n0.0 1.35F-13 U.9qE-ns 0.0 44RU tn3 l.91E-07 0.0. 9.23E-fl 0.0 7.2qCE-07 6.32E-05 1.S -o.. 4uRU 105 9,ASF-11 0.0 3.RqE-l1 0.0 1.27E-10 1.3AE-0b b.0?E-flb 'JLRU 106 8.64E-0b 0.0 I.0qE-06 0.0 1.67E-05 1.16E-03 1.i 1 E-oll 45RH 105 q.24F-10 b.73F-10 4.43E-10 n.0 2.hE-nQ 2.'41E-ntb 1.01)E-05 46PD 107 0.0 q,27F-08 5,87E-09 0.0 b.57E-07 Q.ugE-Ob 7.OhE-(,7 46PD 109 0.0 4.b3F-10 1.16E-itf n.0  ?.35E-og 1.85E-Ob 1.52i-fS 47AG 1I104 1.335E-06 I.25E-06 7.a3E-07 n.( 2.3bF6-06 5.OE-04 3..763 -05 47AG I1I ,425E-08 I ./BE-08i A.8TE-Oq o,0 5. 7uE-P h 2. 34E-n)5 P.l79F-np I URCO 113M n.0 1.54E-0O '.q7E-06 0.0 1.71E-n4 2.06F-0U 1.99E-n5 48CO 115M 0.0 2.ab4-05 7.qSE-01 0.n 1.9RE-05 1.7bE-Ou .8OE-05 50SN 123 3.02E-05 6.66E-07 9.P2E-07 5.6bE-07 0.o P.89E-00 3 .92 -n5i 50SN 125 1.IhF-0b 3.13E-08 7.03E-06 2.59E-03 0.0 7,u2E-05 .MIE-05 50SN 12b 1.58E-04 J.I BE-06 6.OOE-06 1,P3E-0b 0.n I17E-n 3 1.59L-0P SISB 124 3.QOF-06 7.3bE-08 155E-06 9.44E-09 0.0 3.1OF-0u 9.0OBF-nl9 51S5 125 8.2bE-06 B.91E-OR I6bbE-06 7.34F-09 P.0  ?.75F-04 I.?bhf-05 51SB t2b .O50F-07 9.13E-09 1.62E-07 2.75E-0 n0.0 1.5RF-n5 b. OIE-0q 515 127 3.30E-08 7.22E-i0 1.?7E-09 3.q7E-10 0.0  ?.nSE-05 3.771F-05 52TE 12591 4.27E-07 I.98E-n7 S.84E-0A I.31E-07 1.55F-nb 3.92F-05 8.MSF-Ob 52TE i274 1.58E-06 7.02E-07 1.9hE-07 4.11F-07 5.72E-Ob 1.?OF-OQ 1. 7F-O0 52TE 127 1.75E-10 -. 03E-.11 3,87E-11 1.3.E-10 h.17F-j0 *.15E-07 7.17E-oh 52TE 129M 1.22F-0b 5.64E-o7 1.9RE-77 4.30E-07  : .S7,-0b 

                                                                  5E6       11SE-Oa u.7qE -01

52TE 129 b.22F-12 2.99E-12 t.5SE-12 4.87E-12 2.3L3E-11 .a2F-07 t.9bF-0 8 52TE 1314 B.74E-09 5.SE-0q 3,63E-09 BBF-01 3. bE-1A 1.82F--05 b, .9SF-0 52TE 131 1t39E-12 7.44E-13 u .'J9E-13 1.17E-1F 5.ubE-12 1.7 F-07 2. 4uE-0q 52TE 132 3.25F-07 2.b9E-Of 2.0?E-08  ?.37E-0 I.S3E-n7 3,60F-05 6 .3 7E-f5 52TE 1I33M 7,24E-12 5.b0E-12 7.14E-12 6,27E-12 3.7TF-I1 5.51E-07 3.u5F-AQ 527E 134 3.84E-12 3.22E-12 1.57E-12 3.t)U E-12 2.1BE-11 Z.3UE-07 3.b9Emog 531 129 2.'49E-0b 2.1IE-O6 6.91E-O 5.55F-01 14.514E-0b o.l 2.2E-07 S31 130 5.73E-07 1.68E-Ob 6..hF-07 2.18F-04 2.blE-m6 0.0 q.hlF-07 531 131 3.ISE-O6 4.47E-06 2.56F-0b 1.0J9E-03 7.b7F-Oh 0.0 7.8hF-O7 531 132 1.45E-07 U.07E-07 1.45E-07 5.JBE-05 b.UqF-07 0.n 5.18F-0R 

                                                                                                     E
                                           1.109-48

TABLE C-i (Continued) 

 NUCLIDE        BONE         LI VER       TOTAL BODY      THYROID        KInNEY          LUNG           GI-LLI
                           I 56'F-Ob                                    3,*25E-O6

531 133 I .0BE-O0 5.h7E-07 3.hbE-OLA 3.2UE-07 0.0 I.09E-06 531 134 5.ObE-08 2. 16E-07 7.70E- n 2.97E-05 0.0 

                                                          I . 17 F -OU     .   1 F-Ob  0.0           bSbF-U7

531 135 3.30E-07 R. ?£E-M7 3.?2E-07 55CS I *bOE-OR S.20E-D8 I .72E-0A 0.0  ?.94F-OQ 7.,2E-o9 U.hlF-05 1.06E-On 9.11IE-35 I.22E-05 I.30E-Otf 55CS 0.0 55CS 135 1 ,UbF-05 I .29E-o5 6.AOE-lh I .07E-05 1.57E-06 2.11F-07 55CS j36 4.8QE-06 I .83F-nS 1 .3 F-05 2.'1IF-05 

                                                          0.0

55CS 137 5.08F-05 7. 77F-05 5. 36E-05 9. UE-Ob I.05b-0h L4. IIE-0b 7. 77E.-08 U. OE-31 0.0 h.Olr-nR S.07F-09 2.33F-15 55CS 3705F-05 

            2.50F-08      3.53F-n8                                                        ,;).9E-09  0.0
      139                                                 0.0
                                                          0.

9. 32F -I a 3.LE-t 2 7. li3F-Ili u.70E-07 1.12E-07 5695 139 1.17F-I 0 S6BA I40 3.21F-07 2.0QE-nq 1.5QE-nu 2.73L-05 

            4.,86.F-0B           IE
                                  15FO

5*A 9,LIE-i5 !1.2nE-I 3  ?.112E-07 I.115F-17 

                          63 38E- 15     A. 7E-1 3        0.0           2. 7E-IS

SbBA 0).0 l.UqF-07 0.0 

            9   I  F25
                     - 11                                               0l.0           1.70E-)5      5,.73E-nE

57LA 2. 1 7E-OA 5S.71E-LnQ o.n 

        12                                                              0.0             1.SSE-Ob     7.31E-0e

57LA 1Ul 5 . 3 UF- 10 1 bhF -In 2.7 1E-1 1 57LA ,.88E-1 I 9.bSE-1 2 0.0 7.02F-07 2.ULF-07 I ,bQE-Ob 0.0 

                                                          0,.0                         u.52F-n5       1.SoE-05 SRCE         2.49F-02                      1 .QIE-07
      1UO                                                               7 .*           9.LRF-=Ob     2.USE-05

5FCE 2.3 5F -083 1 .72E-n9 I I*E-IQ 7 .0 E-1A9 58CE U32E -Ou 1.79F-04I 2.30F-05 4.73F-Au 1.02F-0O1 

                                                          0. 0
                                                          0,0                          i.51F-3S      2.50F-05

5QPP I I.7E-06 4.6QE-07 5. 7c)E-OR .570F-07 IL 1.27F-07 2.b6)-18 51PR I 7 3. 7bF- 1? S.S96E-1 2 I .I E-1 3 0,0 R.55F-l 3 bO lO 6.59E-07 7.b2E-07 Li.S6E-ag 0.0 

                                                            o~t                        2.76F-05      ?.IhE-09
            8.37F-05      7.87E-nb                                      1 .5AQE-0S     5.blE-n5      5.S4E-06 blPm 149                                  1I. * ~QfE-Oh IAE -0 L6
            9.82gE-Ob     2.5UE-16                        0.0                          2.l tjF - nUi M. 18 F- 0

b61P. 0.0 3. 5F -0 

            3.84E-07      S. 37E-o8      3.2nE-na         0(.0
                                                          0,0           I . f6E-17     3.Q1E-05      5.8OE-05 blPM         3. 17F-O      U.87E-09        I .'99F-00        ,0O         9. IQE-O5      7.?2E-Ob      2.50E-05
      151     ,5* F-0q    I.42F-09       7.21E-10         0.0          ?. 55F-nQ       3.Q4E-Ob      2.OOE-05 b2SH   151                                                                                J.LbE-n5    3.25E-06
      153     .759F-05    1 U.RE-05       1.SSE-Ob        0.0           I .56E-05 bSM          I.70E-08      1. iF-08        I O4E-09                     '4.* 9E-n9      u.1SE-Ob .      .58F-0S

b*EU 15? 5.UOE-05 3.u3E-n4 1,59k-os 

      151   2. 3b8F-0d                       .1E7h-05 0l,0              3. 35E-04
                                                                                                     3,'IOE-05 b3EU         7 IJOE-0U                                                  La. 3bE-~IL     5.P.5E-0L
      155                 9. IOE-O5      6. LRE-OS

63EU I *OIF-05 I u3SF-nS 9,21E-Oh 5. 59E-05 1.47F-05 5.95F-n6 b3EU 15h 0.0 

                                                          0.0
      Tk-T  I .79E-Ob     I uSE-nb       2.UOE-n7                       9.95F-07       9.57E-05      L.SOE-05

6ST9 160 2. 75E-1b 0.0 ,I E-Oh 1.Q2E-04 2.68E-05 

            ?. 21F-OS     0.0

b7 1O 3. 3IE-05 

            6.2   7E -O0Q I .OSE-n0i     q.00F-05                       t,57E-ou       3.q      -OL   1.59F-05

7LJ, 2o0TE-ng  ?.1 7E-t 0 n,0 1.72F-06 2.53E-07 

      155                                                     h,0

7iU I.9SF-07 6. U7E-08 6.81E-09 0.0 5.57E-05 1.07F-05 

        917               3,B5E-10       3.1 OE-lO0                    0,0
            I , ObF-OQ                                                                 3.b3E-Ob       1.94E-O5
      210                                                 0.0                          ;.63E-02      3.b6E-O5

82PR 210 6.72E-03 8A.7E-Ou 0.0 2., 1 2E-02 R391 n.0 I .59F-O0 I .3?E-07 0.0 1 92F-05 1.11F-03 2,qSE-05 BiPo 210 3.97F-O0 9.bOE-01 Q.58E-05 2.-75E-03 3,s1E-n2 4.19E-05 

                                                   1.109-49

TABLE C-1 (Continued) 

 NUCLIDE     BONE      LIVER      TOTAL BODY    THYROID     KIDNEY                     GI-I.1.1

88RA 223 I .80F-0O 2.77E-07 3.bOE-05 n.0 7.8SE-nb 2.5SE-02 2.B4E-O0 88RA 224 1.98F-O5 4.7BE-08 3.96E-06 0.0 1.35E-Ob q,78-03 3.0 E-Ou 68RA 225 3,00E-0O 3.56F-07 9.13E-02 0,0 I .OIE-05 2.92E-02 2.71E-Oa 88RA 22b 1.25E-01 2.39E-06 040 6.77E-05 1 .17E-01 2.94E-0O 8BRA 22A 4,41E-02 1.23E-Ob 4.76E-02 0.0 3.QSE-0O 1. 61E-01I 5.00£-05 89AC 225 4.23E-0a 5.82E-nO 2. 8OE-O5 b . 3£ -05 2,21E-02 2.52E-04 BqAC 227 2.30F 00 3.05E-0l 1 .36E-01 0.0 9,9 2E-02 2.q F-0I O.92E-05 9QTH 227 2. 17F-0O 3.92E-06 6.25E-06 2.22E-05 3. 78E-02 3. 3uE.-Oo 90TH 228 2.00F-Ol 3.39E-03 6.77E-03 0.0 I. 89E-02 1.DIO E (in 3.17E-04 90TH 229 8.88E 00 I .33E-01 4.36E-O0 0.0 b .52E- I- 3.50E 00 3.1 7E-OU 90TH 0.0 6. (10E-0 1 

     230  2,2QE 00    1.31E-01    6.36E-2?                             b.22E-01     3. 73E-05

90TH 232 I .99E 00 1.12E-01 5.43E-O2 0.0 5.*17E -01 5.31E-01 7.9'jF-05 90TH 234 I .63E-Ob 9.56E-08 4.70E-08 5 *, L1 E-0 7 I.89E£-O 7.03F-05 

                                               0.0                                  7
  • 0 3-OSi

91PA 231 S.n08 00 I .91E-01 I.9SE-OI 0.0 0.0 5.75E-OP 91PA 233 1.21F-06 2.4 2E-07 2.09E-07 0.0 9 . 1SE -07 3.52E-05 1.02£-05 92U 232 5. I 0E-02 0.0 3.66E-03 0.0 5.56E-03 2..23E-01 0*lbE-05 92U 233 I .09£-02 0.0 6.5QE-Ou nO, 2.5E-03 5.33E-02 3.89E-05 

          1. O* E-02  0.0                               2 ,. -E -03    S.?2E-02     S.lf-05

92U 23U 6,06E-Ou 0.0 920 235 I. OOF -02 0.0 6.07E-Ou 0.0 2. 3E-n3 .QOF-02 0

  • 80£-05 q2U 236 1.OOE-02 0.0 6.20E-00 0.0 2, 3Sq-03 5.01E-02 3.57E-05
                                                        1.51£-fl?
                                                                                                  I

92U 237 3.67£E-08 0.0 9.77E-09 0.0 t.02F-0S I, 2OE -nr 92U 238 9.58E-03 0.0 5.67E-O0 0.0 2. 1AF-03 0.5FF-02 I .ASE-O0 934P 237 1.69E 00 1,47E-01 b.87E-OP 0.0 5. 10E-O1 5.22F-02 4.92E-O5 93NP 23B 2.96E-07 7.99E-09 1.61E-n9 0.0 2. 7?£-09 1 .0E-05 2.13F-05 93NP 239 8. 75E -flQ u. 71F-Ob 

          2.87E-O0    2.82E-09    1.55E-09              2,*,5E-01                   0 . 52£F -OIi Q9PU  238  ?.69E 00    3.73E-01    6.6hE-£O0    0.0
                                               0).0                    I .76F-01    0.52F-Os

94PU 239 3,05E 00 4,19£-nl 0.0 

                                               0.0      3.?0F-01       I .b7E-0
                                  7,53E-0?

94PU 240 3.04E 00 4. 19E-01 7.53E-0? 0.0 3. 20£-0 I I h7F-01 .20F -05 9PIJ 2ul 6.0SF-02 0.0 5.93E-03 I .52F-O0 8. SE-07 

                      3.28E-03    1.29E-03

94tPU 242 0,0 3,OSE-nt .o 

                                                                                      *05-OS
          2.89£ 00                7,1 7E--2                            I sq9E-01

94PU 240 4.76E-01 0.0 3.64E-01 I .89F-01 t.03E -05 

          3.45E 00                B,5'4E-02

95AM 201 9.93E-O0 3.46F-01 b6,7E-02 0.0 5.86F-02 .6bOE-09 95AM 2424 1.02F n0 3.46E-01 B.73E-02 0.0 5. OIE-OI 2.45E-02 5. 7qE-05 95AM 243 9.qUE-01 3.40E-O0 hf.uE-n2 0.0 O.BbE-01 5.bSE-n2 b.03E.-05 

                                               0.0.                    3.74E-02     4.64E-05

96CM P42 I , I UF-02 I . 18F-02 7.50E-04 3.SOE-03 96CM 203 7.8SE-Ol 2.97E-O0 4.61E-02 0.0 2.15E-01 6.32F-02 

          5.QOE-O1                             0.0      1,64E-01       6.07F-02    '4 *.6E -05

96CM 24, 2.5IE-01 3.51E-0? 9bCM 205 1.?bE 00 3.59E-01 7.1 £E-f2 0.0 3.33E-ni 5.86£-n? 0. 36F-05 

                                               0.0      3.33E-01       5.97E-02     0.291-O',

9bCM 246 1.25E 00 3,59QE-O 5.b E-OS 

                                               0.0

96CM 247 1.22E 00 3.53E-at 7.03E-a? 3.28E-01 5.86E-02 S. 091-O0 96CM 208 I.01E 01 2.91E 00 0.0 2.70E 00 0.83E-al 

                                  5.7qE-01

98CF 252 7.33E-01 0.0 i .83E-02 0.0 1.56E-0l I . 78£ -00 

                                        1.109-50
                                                                                                  4

TABLE C-2 TEENAGER INHALATION DOSE FACTORS 

                                           (mrem/pCi inhaled)
     NUCL IDE      A ONE     LIVER      TOlTAL 8B1)Y    THYROID   K I3NEY     LUNG       U 1-LI. I
   IH        3   0.0         1.06E-07      1.OhE-07     I .06F-01           1 .O06F-07   I.ObE -07 bC      14l   5.66E-07    5.66E-07      S.bbE-07     5.bbE-07            S.b6E-07     5.06eE-07
  11!INA   22    I*7bF-OS    1.76E-05      1.76E-05     i .7bE-05           I .76F-05    I .'J LE-Oh
 27C0 55         0.0         2.20E-08 2.93E-OR          A,(                 I .71E-OLI   1.1I F-05 bO    0).0                                   0.0
 27CO                        1.55E-07 2.OhE-07                              I .07F-03    2.Q4lE-0'5
 38Sp B9         4,.84E-06   a3.0          1 .39E-07    0.0         (USE    3.13E-0LJ    4.4L2E -05
 38SR      90    I *.48E-03  0.0           9.01JE-05    0.0                 ?.n7F-03
                                                        0.n                             9.* bF-05
 3c9Y      90    I .41E-.08  0.0           3.79E-10     0.0                 0.0          h. 79L-0'5
 39Y       01    b. 72E06b   0 .0          1.80E-07                 PMULT   3.57E-04I    LI* 7F -05
 'jOZR     95    1.*3bE -Ob  !J.5LLE-07 3.17E-07        0,0                 3.*20E-04I   I .6bE -05 JJINB 95        I . 70E-07  1.03E-07     9.7AIE-09      S.*
                                                        0.0 0                9.96E-05    1.1IOE -05 U'JRU 103       2.04OLE-08  0.0          Q.ISF-flQ     0.0         DOSE    4.'I9E-05    I . IRF-05
 44RJ;U 106      I .05F-0b   0.0           1.3?E-07                         ?.05E-nS     1. 16L-04I
 S0SN' 123                   7.6RE-08      I.1ISE-n7    6.1 5E-OA           LI 693E-0LI  3.91E-05
 52TE 1254      5.09E-08     2.32F-D8 b.QIE-09          1 USE-OB    FACTOR) 6.70E-05    8.95E-06
 52TE 127        I b62E- II 7.30E-12      4I.02E-12     1.34E-1 1           I .33E-06    I . 01IE-09
 52TE t294       I .49E-07   7.05F-08     2.40OE-08     i.FBE-05            21.5LF-0LI  LI.80E-05
 52TE 132        3. 75F -09  3.-OOE-09    2.2QE-09      2.54E-09            5.6b7E-05   b.b lE-OS
 531      129    3.53E-06    2.9UE.06     9.81E-06      7.32E-03            0.0         2. 16F-07
 531      131    4I.21IE-06  5.90E-0b     3.SRE-06      I .7E-03            0).0        7.45FE-07
 531      133    I 54~E-06   2.58E-06 7.93E-n7          4.79E-04            0.0          1 .25E-06
 55CS 13Ll       6
  • LE-05 1.38F-04I 6.80E-05 0.0 I.ROE-05 I . 12E-06 SSCS t37 8.02E-05 1.03F-04I 3.79E-fl9 0.0
                                                                            1 .47F-05   9.bOE-07
 56BA 1Ji0       6,62E-07    6.06E-10     LI.?7E-ng     0.0                 P. 53F-OLI
 57LA ILJO       I .79E-09   4,.72E-10    l.b7E-10      0.0                 2. 70E-05   5.981E-05
 5ACE 1'J1       2.84IE-07   1.90E-07     2.1RE-DA      0.0                 7. 29E05     I .4I2E-05
 58CE I1U    U   5. 2uF-05   2,17E-05     2,80E-06      0.0                 I . 72E-03   1 . OSE-04*
 b3EUI ISLI      9.195E-05   I.02E-o5     ý.07E-06      0.0                 9.29E-04    3.UIE-05 QU      232     6. lL4E-03  0.0          LJ.37E-OLI                        3.84IE-01    4,. IbE-OS
 9?U     234I    I .25F-03   0.0          Z.72E-nS      0.0                 9.00OE-02   3.F81E-05
 9UPU 234~       3.22F-01    3.4I3E-02    7.9FLE-03     0,0                             's.52E-05
                                                                            3.1ILI-01 QLIPU 239       3.67E-01I 5.OOF-02       9.06E-03      0.0                 2.98E-01    '4. 13E-05
 9Lipu 2U0       3.66,E-0 1 5.OLIF-n2 Q.13E-03                              3.01E-01     4,.13E-05
 9LJPU 24I1      I .29E-04I I.BLIE-0S     3.26E-Oh      0,0                 I Q92E-04I  7.94LE-08
 95AM 24J1       I .20E-01   4l.11F-02    7.79E-01                          I .0 1E -01 LI.LJLE-05
 96CM 24I2       I .35E-03   1.40OE-03    8,97E-0';     0o0                 6.LI7E02
   9CM 244L     b.99E-02     2.99E-02     4I.16E-03                         1 OSE-01    LI.60E-05 N4ote:    0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-51

TABLE C-3 CHILD INHALATION DOSE FACTORS.

(mrem/pCi inhaled) 

   NUCLIDE      BONE      LIVER     TOTAL BODY      T-4YR310    KI )NFY         LJN.G        GI-LLI
  IH      3   0.0         2.03E-07    2.03E-n7      ?.03E-07                  2.03E-07       2. 03R -07
  6C    i1    1 .69E-06   1.69E-06    1.69E-06       I ,69E-06                I b69E-06      I .bqE-06 IINA ?2       4,42F-05    4.42E-05    4u2E-05       a. a2E-05                 ", '2E-05

27C0 5a 0.t1F-n8 7.?3E-08 0.0 3.,O*E-OLi 9. 1,* -0o 27C0 60 0.0 2.qOF-07 5.07E-n7 0.0 (USE 1.67E-03 2.H3F-0% 3ASR 89 I..45E-05 0.0 4.16E-07 0.0 _____ . 0E-Oa I.56F -05 38SR qO 4.A3F-03 0.0 2.70E-14 0.0 *.OOE-n3 Q1 1 

                                                                                                 ,EF-Ob

39Y 90 9.87E-08 0.0 2.65E-OQ 0. ADULT 7.26E-05 

                                                                               6190E-OI          .. 23E-OS

39Y QI 2.01E-05 0.0 5.36E-07 LI.* _-O 4OZR 95 3.8IE-06 9.86E-A7 8.05E-07 5. 72F-O0 LINR q5 06,0E-07 1.96E-07 

                                                    000
                                      t.dLE-07      0.0
                                                    0.0         DOSE          I 5AE-0*

44RU 103 5.AUE-08 0.0 2.36E-OB 0.0 1.71E-04i .IS2E -05 

 44RU lOb     3.12F-O0    0.0         3.89E-07                                3.93F-03

503N 123 I OUE-OS 1.74E-07 3.'3E-n7 I .9RE-07 FACTOR) 9.46E-04 lI. 1 I- -05 52TE 125m I .52E-07 5.25E-08 2.0hE-08 4.35E-05 I . 30F- 04 .10 3E-06 52TE 127 4.83E-I I 1.bSF-11 1.20E-11 U.,IE-l 1 2.5E-Ob 52TE 12QM a.t4UE-07 1 .4bE-07 a.T7F-OU 7. 53F 

                                                                                             I.    137-07-05
                          1.58E-07    7.03E-08
              1..08E-08                                                                      b.52(- -05

52TE 132 6.08E-0 

                              .*        .91E-09     7.24E-04                  I .03E-O0

531 531 531 

      129
      131
      133

55CS 134 55CS 137 I, 05E -05 I .?3E-05 

              4.53E-Ob
              1.68E-O0
             2.34E-O4
                          5.4OE-Ob
                          1°25E-05
                          5,S3E-06
                          2.b9E-O0
                          2.16E-o'
                                      2.86E-fS
                                      Q.a7E-0h
                                      2T17E-06
                                      6,02E-05
                                      3.38E-05
                                                    2.14E-02 u.t6E-03 I
  • 36F -03
                                                    0.0
                                                       °00
                                                                              .1.0
                                                                              0.0
                                                                                   0
                                                                              3.21E-n5
                                                                              2.71F-05 q.22E
                                                                                             2.168-07 I .54E-O0
                                                                                             I7. .08E-Ob
                                                                                                        -OS)
                                                                                                   I 7E-05
                                                                                                 , 22E-')7
                                                                                                             6 SbBA iaO      1 ,93E-Ob   I,26E-nq    1.laE-07      0.0                       0.69QE-0       2..28E-01

57LA I4O 5.20F-09 9.63E-10 L.3uE-In 0.0 U*Q2E-05 S8CE 14l 8.47E-07 .24E-n7 6.30E-08 0.0 I.39E-n4 I.flE-05 58CE 144 1.57E-0U 'I,9tE-oS 8,37E-06 0.0 3. 32F-n3 I .07E-OP b3EU IS1 2.87E-04 2.IPE-05 2.OqE-n5 0.0 I .67F-03 3.71F -05 92U 232 1 .83F-02 0.0 1.31E-n3 0.n 

                                                    0.0                       7,"J3E-nl

92U 234 3.73E'03 0.0 2.31E-04 0.0 I .70F-01 

                                                                                              /J. V2E-is a.    57F -05 qiPU 238     9,62E-0I     I.OOE-01    2.38E-02      0.0                       5.87E-01

94PU 239 I.IOE 00 1.13E-01 2.71E-0? 5.5bF-0I 94PU 20 0.0) Li, ŽLE -05 

              1 .09E 00   I.I'4E-O.   2,73E-0?                                5.61E-ni

94PU 241 .16E-n5 9.73E-06 

                                                    0.0r                      3.6lE-0OJ      8. 1bE-OF
             3.84E-o0

95AM 241 I.QSF-OI *J.S7F-05 

             3.57E-01     9.31E-02    2.33E-02

96CM 242 4.,05F-03 3,17E-03 2.bRE-0O, .2? E_-n_1-_ 

                                                                              ?,02E-01       a. 73r-05

96CM 244 2. 09E-0I b.77E-02 1.24E-02 0,0 Note: 0.0 means insufficient data or that the dose factor is <1.0E-20.

1.109-52

TABLE C-4 INFANT INHALATION DOSE FACTORS 

                                           (irirem/pCi inhaled)
    NUCLIDE       S O:N F   LIVER        TDIAL 3J)Y                    KI  NE Y   LU NC        GI-LLI
               0.0           3. 07E -n7    3.07E-07                             3.07E-07       3.07F-n7
                                                           3.07E-07 bC      1"                              3.bOE-06        3.SAE-06             3.bOE-Ob       3.OF-Oh
               3.6OE-O0      3.6OF-06
                                                                    0
                                           7.53E-05        7.53E- 5             7.S3F-05        1 .22L-06 IINA     22   7.53E-05      7.53E-05
               0.0           8. 39E-OR     I .2nE-07       0.0                  h.28F-O0       8.67F-06

27C0 58 

               0.0          !. OOE-07      8.38E-07                     (USE    3.QRE-03       2. *3E-('0

27C0 b0 4.6bE- 38SQ Q. 3.01E-05 5,89E-07 I .h5F-n3 

                            0.0

38SR QO 9.4FE-03 5.7hE-0A 0.0 I .09E-02 AU. Q8E-04 9.89F- * 39Y 00 2.lOF-07 0.0 5.65E-09 0.0 

          91   UL27E-05     0,0            191 LE-OB      0.0          ADULT'       , 88E-03   5. 12E -05

39Y 4nZR 05 7.7uE-O6 1 .9SE-06 1.*3QE-*6 0.0 I .2QE-03 I .01E-05 4INB 05 9. I6E-07 4. 11E-07 2.ULiE-07 0.0* 8. b7E-Ob 

                                                          0.0           DOSE    3.JiF-OU       11.I SE-05

4JRUi 103 I .21E-07 0.0 4 . ! 9E - n D. OE -04 44RU 106 6.b5E-O6 0.0 8.16E-07 0,0 

                                                           0 .O E-                             1.2bE-04 I .07E-02 U.6IE-n7       7.30E-07       LA. IlE-07                           4.28F-05

50SN 123 2.22E-05 2.SBF-A3 I .39E-07 u.UOE-08 1 .09F-0 7 9.71F-Oh 52TE 1254 3.2uE-07 FACTOR) 3.54E-O4 I .87E-05 52TE i27 1.03E-I0 w.31E-t II 2.56E-1 I I .OOE-10 7. 03F-00b Q ,UuF-07 4i 1 UE-07 1.47E-07 3. 63F -0 7 5.23F-05 52TE 1294 I. I2E-08 I .31E-03 

               2,25E-08                    I .*hE-nR       I .70E-05                           6. b8E-05 S2TE 132                                                                        2.Q8E-04 I .b2E-05      5.A2E-05       5.21E-02                             2M2E-07

531 129 2.23E-05 0.0 

               2.59F-05                    I .70E-35       I .OIE-02                           7b6hE-07

531 131 3.n5E-05 0.0 

               9.5hE-06     I .38E-05                     3. 33E-03                            I .S3E-0b

53! 133 LA.IQE-Oh 0.0 

                                                                                               9.80E-07
               3. 43E-OL    5.8QE-O0       5.23E-05       0.0

55CS 13u7 0.0 

                                                                                7.22E-05
                                                                                               9.45E-07

55CS 13 ".90E-04 5.22E-04 3.15E-n5 5.7%E-05 5b8. !LAO .0 77E-06 S05E-09 2.11IE-07 0.0 2.77E-06 

                                                          0.0                     ,I 17E-03    6.43F-05
               1 .09E-08    2.29E-3q       7.* E-1 0

57LA 1LO n.0 1 .21E-04l 1 .4l F-05 5BCE 1l1 i .80E-Ob 1. IIE-0b 1.2QE-17 3.7AE-O0 

               3. 3IF-O4    I 30E-04       I .7AE-05      0.0                                  I 15E-OLA

58CE IlUq 9.06E-03 

                            4.95E-n5       3.72E-05       0.0                                  3.73E-05 b3EU   154     5.99E-0O                                                         3.99E-03
                            0.0            2.71E-03       0.0                                  L.SSE-05

92U P32 3.q1E-02 0.0 2.02E 00 

                                                                                               A. 16E-05

92U 234 7.94qE-03 0.0 0.91E-14 *.7LE-fl S.OSE-92 I .51E 00 4.qbE-05 quPU 238 2.05E 00 2.66E-01 0.0 00 

                                                                                I .43E         U.51L-05

9gPU 239 2.33E 00 3.O0E-01 5.77E-02 

                                                          0.0                                  A.51E-05 gapu     PLao  2.33E 00     3.02E-01       5.81E-0?                             I .45E      00
                            I. I OE--04    2.07E-05       0.0                                  8,.bE-08

94PU 2U1 5. IBE--04 q.9OE-nf L.96E-02 U.86E-05 95AM 241 7.61E-01 2.47E-l1 S.32E-01 

               9,62E-03     8.40E-03       5.71 F- 14                                          5.29E-05

96CM 2u2 0.n 3,UIF-01 

               4.L45E-0 1   I. 70F-01                                                          5.03E-05 obC4 2U4                                   2.65E-02       0.0                   5.51E-01 Note:   0.0 means insufficient data or that the dose factor is <1.OE-20.

1 109-53 

                                                     .

This yields CV 4 (ro) = 3.17 x 107 Q74 [x/Q'](r,) 0.11/0.16 U 

                          = 2.2 x 107 Qi4 [x/Q'J(r,O)                                           (C-8)

where Cv 4 (r,O) is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg; 

                 !Q14      is the annual release rate of carbon-14, in Ci/yr;
             0.11          is the fraction of total plant mass that is natural carbon, dimensionless;
             0.16          is equal to the concentration of natural carbon in the atmosphere,     in g/M 3 and
     3.17 x 107            is equal to (1.0 x 1012 pCi/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).
     The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.           Using the method described in Reference 3, the NRC staff derived the following equation:
           CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H)
                        = 1.2 x 10 7 Qi[X/Q'](re)/H                                             (c-9)

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

                  H        is the absolute humidity of the atmosphere at location (r,o) in g/m3 Qý         is the annual release rate of tritium, Ci/yr;
               0.5         is the ratio of tritium concentration in atmospheric water to tritium con--
                           centration in plant water, dimensionless; and
             0.75          is the fraction of total plant mass that is water, dimensionless.

The deposition rate from the plume is defined by: 

           dC(r.o) = 1.1 x 108ai(r,e)Qj                                                         (C-10)

where 

        6 1 (r,O)          is the relative deposition of nuclide i,    considering depletion and decay in transit to location (r,O),    in m"2 (see Regulatory Guide 1.111) and
      1.1 x 108            is the number of pCi per Ci (1012)   divided by the number of hours per year
                           (8760).
     For radioiodines the model considers only the elemental fraction of the effluent. The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Reference 4).             With this consideration included, Equation   (C-l0)      for  radioiodine  becumes:
                                                                                                           I
                                                       1.109-54

15.5 x Si(r,6)Q.107 (C-1l) and Q! is the total (elemental and nonelemental) radioiodine emission rate. The retention ictor r for elemental radioiodine on vegetation should be taken as unity, since the experimental mea- surement (References 5, 6, and 7) techniques used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (References 8, 9, and 10). 

     For radioiodines, the deposition model is based only on the dry deposition process.         Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).
     For particulates, the deposition model considers both wet and dry deposition.        There is also a retention factor (r of Equation (C-7)) that accounts for the interception and capture of the deposited activity by the vegetative cover.       A value of 0.2 is taken for this factor (References

11 and 12). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.

a. Parameters for Calculating Nuclides Concentrations in Veqetation Consumed by Man When the radionuclide concentration in vegetation directly ingested by man is estimated using Equation (C-7), the following parameters are used: 

                       Parameter                                Value
                                                                      2 Yv     (vegetation yield)                         2.0 kg/mi te     (exposure time to plume)                   60 days th     (holdup after harvest)                     1  day for garden-fresh leafy vegetables
                                                            60 days for stored vegetables tb     (soil exposure time)                       15 years (midpoint of reactor operating lifetime)
          All other parameters in this equation are given in Regulatory Position C of this guide.

b. Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q exp(-xit) (C-12) where C'(r,a) is the concentration in milk of nuclide i, in pCi/liter; 

        CY(r,O)        is the concentration of radionuclide i in the animal's feed,    in pCi/kg;
              Fm       is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively; for nuclides not listed in Table C-6, use the values in Table C-5);
                                                   1.109-55

TABLE C-5 STABLE ELEMENT TRANSFER DATA 

            Biv        Fm(Cow)            Ff                       8.av     Fm(Cow)          Ff VES/S3IL  41LK (1/L)     MEATT(D/KG)

ELEM VEG/SOIL MILK(CD/L MEAT(D/XG) ELEM 

                                                           SB  I.IE-02    I oSE-03       POE-03 H       4,BE O0     I ,OE02** 2.2E-02
                    2,0E-O;                                TE  I'3E 00    I.0E-03        7, 7E-02 HE      5.OE-02                       2,nE-02
        8,3E-OG     5,0E-O.                                I   2,OE-02    b. OE-3l3      I2ý9E-03 Ll                                                                        2.OE-02        2. E-02 BE      4, 2E-o4    I,0E-Oa           i.oE-n3              VE  IOE 01 CS  I OE-02    I
  • 2E-02"
  • OE-03 B 1.2E-01 2,7E-0"
                                                               b,OE-03                   3.2E-03 C       5*5E" O0    1,2E-02           3.1IF-n2                              . GOE-O1***

N 7.5E 00 2,2E*O. .OE-02 LA 2,SE-03 2.OE-04 B.OE-n2 CE 1.2E-03 0 1.bE GO 2. OE*O2 I .6F-02 2*5E-03 5OE-Oh PR 4,7E-03 F 6.5E-4O 1.,E-02 2,SE-03 SOE-Ob NE 2. OE-O? ,jD 3.3E-03 iE-ol 2. OF-n2 2 5E-03 S.OE-Ob NA 5.2E-02 4 .OE-02*4** I3.OE-02 SF-ot PM 4.8E-03 S4 2,SE-, 3 5.OE-Gb S. E-03 4G 1.3E-ol IOE-02 SIOE-03 2.E-03 EU 5.0E-Ob 4.BE-03 AL I .BE-04 5,OE-Ou I ,E-o3 2.SE0 3 S.OE-O6 3, bE-03 al 1.5E-OM I1OE-Oa GD 2,bE-03 TB 5.OE-Gb ~4,(E-03 P 1.IE nO 2,5E-OP u.bFE-2 SOE-Gb Dy 2.bE-03 

                                                               2,SE-03                   S.3E-03 S       S19E-0!     IBE-02             I a.E-nI
                                      Q.OF-03                  2,#E-03                   U,*E-03 CL.     S.OE 00     5,OE-02            8.nE-o2                            5.OE-Ob
                                                               2. SE-03                     .uOE-03 AR      6oOE-01     2.0E-02            'J.6 -n2            ER             SOE-Gb K                   IOE'O*.                                T   2, 5E-03
        3,7E-oi     8 , OE-03***       1.2E-02                            S.OE-Ob        u.OE-03
        .,,6E"O,?                                          YB  2, SE-o33 CA                  5.0E'06**                                             SoOE-06         4.OE-03 sc      I . IE-03   5,OE-06              a.bE-02           LO  2 bvE-03   5IOE-06 TI                                                         NF                               ,CiE-O1 So"E-OS     S. GE-Ge,          3,IE-02                 1,7E-OP

V lOE-03 TA I.bE O0 

        i 3E-03                                                6,3E-03    2.5E-02 CR

MN FE CO 

        2.SEOu0
        2.9E-io2
        6,6E-Oq
        9,a4E-03
                    2,2E*03
                    2,SE-Ou
                    1?2E-03 I.OE-03
                                       2a3E-n3
                                         1.4E-03
                                       4.OE-04
                                       4.OE-n2 w
                                                           RE
                                                           OS
                                                           IR  1. SE Ot S,OE-Ou
                                                                          2*5E-02
                                                                          5.OE-03
                                                                                         1.3E-03
                                                                                           .,E-03 uOE-OI
                                                                                          1,SE-03 II
                    6,7E-01            1.3E-02             PT  5,3E-01    5,OE-03          4.OE-03 NJ      1,9E-O2                                                                             .OE-03 CU                   I# 4E-02                                  2.SE-03    S.OE'03
        1.2E-01                        8. DE-03            AU             3.BE-02         2.bE-G1 ZN      (S.OE-OI                       3OBE-62
                                                               3 @3E-0I
                                                           TL  2.5E-01    2,2E-02         u.OE-O?

GA 2.SE-0O 5,0E-05 I ý3F on S. OE04 b, SE-02 b.2E-O04 2,9E-04 GE i OE-ol  ?.fE 01 PB 

                    6,OE"03                                81  I9SE-01    S5OE-O0         I SE-02 A5      I.OE-02                        2.OE-03 S,3E-03
                    ',SE-02                                P3  2oSE-01    3,0E-O0         I 2E-02"

SE 1.3E O0 2, SE-Ol GOE O0 BR 7#bE-01 1.5E-n3 AT S.OE-02 S.OE"O2 2.oE-02 2,OE-02 KR 3,OE O0 2, EOE.02 RN 3,SE 00 Re 3#OE-O2 2.OE-n2 FR I, E-O2 5GOE-02 2.OE-02 

        1,3E-01     B OE-O4***         3a IE -0'           PA  3, IE-OQ     .80"03** 3,UE-02 SR      1.7E-02                                                                           beOE-02 I I OE-05                             AC  2.5E-03    5.GE-O6 Y       2.bE"03                        Is.6 E-03 S OE-06                                TH  Q,2E-03    S.GE-Oh        2. GE -04I

ZR 16.7E-04 3,OIE.02 B.OE 02 NB 2#5E"03 PA 2,SE-03 SOEGOb 

        9.4LE,-03                      2., BE -01          U   2,SEmO3    S.OEGOU         3,4E-O4-
        1.2E-01l    7,5E-03            5,OE-o3
                    2.SE-02                                NP  2, SE,,03  5,GOE-b         2,0E-04
        2,5E-01                        4.GE-ot                            2,OE-Oh RU                   IOE"O6                                PU  2, SE"-0                   1.UE-05*.**
        5.OOZ02
        9.OE"01      I.OE-02                                   2, SE"04   5.GE-Gb         2,OE-Oci RN      1,3E 01 t,;5E-Gt     I,OEOG.           t.SE-03             A4 Po      3,  OE-O00
                 I                                             2, SE,03   S.0E-Oh         2.OE-O *i-
        5,OE'       5,0E'02 AG      2,SE-01                        I .7E-02            9K  2,SEo.03   S.OE-Gb
        2.5E-01     5aOEw02                                               5,0E-06         2,OE-G04- CD                   162E-Ou                               CF  2 , SE"03  5,OE-Ob ES  2,SE-03    S.,OE-Gb        2,0E-O*

IN I.OE-0O 8.OE-n3 20GE-OU f 

        2,5E'03     2.5E-03                                F-  2, SE-O3   5,.OE - Oh SN                                     R.MfE-02 t
    Ref. 1.                   Refs. 7, 8, 9, 10, 14, 15, 16, 17.

Ref. 3. +t Ref. 18.

Ref. 13.

1.109-56 E1

TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK 

             ELEMENT                                  Fm (days/liter)
               H                                          0.17 B                                          0.012 C                                          0.10
               Mg                                         0.042 P.                                         0.25"
               Cl                                         0.5 K                                          0.057 Ca                                         0.47
                                                                  *
               Fe                                         1.3E-04 Cu                                         0.013 Sr                                         0.014 I                                          0.06 Cs                                         0.30
               Po                                         0.0018 Computed from the data of Refs.  I and 19.

  Ref. 13.

1.109-57

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

              t      is the average transport time of the activity from the feed into the mil:
                     and to the receptor (a value of 2 days is assumed); and Ni      is the radiological decay constant of nuclide i,      in days- Milk-producing animals are assumed to be on open pasture for the following grazing periods:
                        Reg i Uon                          Pasture Period Southern U.S.                      Whole year (fp     1)
                     Northern U.S.                      May - Sept.   (fp = 1/2)

where fp is the fraction of the year that animals graze on pasture.

These data may be supplemented by information on site-specific dairy practices. The concentration of radionuclide i in the animal's feed is then cv(r, a) f fCP(e)+ (I1 f )C5 (r,) +f(1 (-3 

              ,        pfC(ro          -       i ,.p +       -  5   C~
                                                                    I                       (-

where P 

        Ci(ra)       is the concentration of radionuclide i on pasture grass, in pCi/kg;
         I(ro)       is the concentration of radionuclide i in stored feeds, in pCi/kg; and fs      is the fraction of daily feed that is pasture grass when the animal grazes on pasture.

The following parameters will be employed in evaluating the milk pathway, unless site-specific data is supplied.

Parameter Value QF (animal's daily feed) 50 kg/day (wet weight) for cattle 

                                                     6 kg/day (wet weight) for goats th   (storage time of animal's food)                          0 for pasture
                                                     90 days for stored feed te   (crop exposure time)            30 days Yv  (crop yield)                     0.75 kg/m 2 (wet weight) for pasture
                                                     2.0 kg/m 2 (wet weight) for stored feed
                                                 1.109-58
                                                                                                    4

c. Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentra- tion in meat is estimated as F 

                                                                                                        (C-14)

where C1ý(r~o) is the concentration of nuclide i in animal flesh, in pCi/kg; 

                   Ff        is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t       is the average time from slaughter to consumption, which is assumed to be
                            20 days.

All the other symbols are as previously defined.

Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.

4. Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by 

              0.

ija (r,,,) = DFIi4a i [Uvf 

                                       [aa gCv(r,.)
                                               i
                                                       + UCr,)
                                                          a i-      + U FC(,
                                                                      Ua i        + ULf a CL(r, U.       r e        (C-15)

where DDija 

           . (r,e)          is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr;
            DFIija          is the age      dosea, conversion group       in mrem/pCifactor (from for the ingestion Tables  A-3 throughof A-6 nuclide i, organA j, of Appendix    of and this guide); and v      m    F      L     are the ingestion rates of produce (non-leafy vegetables, fruit, and grains),
  Ua , Ua, Ua, Ua milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide).

All the other symbols are as previously defined.

The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD = DF .rvf + m + F F L L (C-16) 

               ja           ija     a g 1           a i           a i          a k I
                                                          1.l0-59

REFERENCES FOR APPENDIX C I. Y. C. Ng et a), "Prediction of the Maximum Dosage to Man fro;m the rallout cif ucclar Devices, IV Handbook for Estimating the Maxi'ium Internal Dose tro,m RPdio!;uclide:; :d-, 

                                                                                                  Ž,Pc to the Biosphere," USAEC Report UCRL-5D163, Part IV, 1968.

2. R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, Cle,',eland, Ohio, 1D70.

3. L. R. Anspaugh et al, "The Dose to Man via the Fooo-Chain Transfer EResultinq fro!:m Exposure to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1i,1972.

4. B. H. Weiss et al, "Detailed Measurement of 1-13' in Air, Veqetation and 'i1[' ;.-ound Three Operating Reactor Sites," NUREG-75/021, U.S. N~uclear Regulatory Commission, Washington, D.C., March 1975.

5. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!., To," 

   USAEC Report ID0-12063, January 1968.

6. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at le National Reactor Testing Station, Progress Report Number Four," USAEC Report iO--126E.

December 1968.

7. B. H. Weiss et al, "Detailed Measurement of 1311 in Air, Vegetation and M.1ilk around Three Operating Reactor Sites," Environmental Surveillance around Nuclear Installatiorns. !nter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. 1: pp. 169-190, 1974.

8. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1311 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, Colo*ncno West Germany, IRS-W-6, June 1973.

9. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 131i Doe to the Thyroid," Institute fur Reaktorsicherheit, IRS-W-5, April 1973.

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

11. C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout RadiontucI'det.

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

12. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption 

                                                                14 4     14 4 of Cow's Milk as Critical Pathways for 1 3 7 Cs, 5 4 Mn and       Ce-      Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.

13. R. J. Garner, "Transfer of Radioactive Materials from the "i,T,'restrial Environ;nent to Animals and Man," CRC Press, Cleveland, Ohio, 1972.

14. F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol. 17, pp. 565-9, 1969.

15. R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.), 

   Pergamon Press, Oxford, England, 1966.

16. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 

   1311 and 13 7 Cs to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.

E 

                                               I.109-60

REFERENCES (Continued) 17. J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report 

   100-12067, p. 36, 1968.

18. R. S. Booth et al, "A Systems Analysis Methodology for Predicting Dose to Man from a Radioactivity Contaminated Terrestrial Environment," Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501, Oak Ridge, Tenn., pp. 877-893, 1971.

19. D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.

1.109-61

APPENDIX D 

                             MODELS FOR CALCULATING POPULATION DOSES FROM
                                     NUCLEAR POWER PLANT EFFLUENTS
     Calculation of the annual population-integrated total body and thyroid doses should be performed for the three effluent types identified in this guide. These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D, Section II

of Appendix I to 10 CFR Part 50.

For the purpose of calculating the annual population-integrated dose, the 50-mile region should be divided into a number of subregions consistent with the nature of the region. These subregions may represent, for example, the reaches of a river or land areas over which the appro- priate dispersion factor is averaged. Dispersion factors, population data, and other information describing existing or planned uses of the subregions should be developed.

1. General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con- sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows: 

           D Dd0.001 Z Pd    Yd jad Djdafda f                                                    (D-l)

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

              D       is the annual population-integrated dose to organ j (total body or thyroid),
               i      in man-rems or thyroid man-rems;
            fda       is the fraction of the population in subregion d that is in age group a;
              Pd      is the population associated with subregion d; and
          0.001       is the conversion factor from millirems to rems.

The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide. The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.

For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption. For all the food that is produced within the 50-mile radius, the radioactivity concentrations are averaged over the entire area by weiqhting the concentrations in each subregion by the amount produced in each subregion. This average concentration is used in calculating the population doses. The 50-mile average concentration of nuclide i in food p is computed as C = (/V ) exp(-Ait ) C v (0-2) 

                 ip   p         1 p d dip dp The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.

1.109-63

TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL 

                               IN LIEU OF SITE-SPECIFIC DATA
                                                PER CAPITA USAGE FACTORS (IUap)
           PATHWlAY                       CHILD         TEEN        ADULT       JNITS
      Fruits & Vegetables
      & grain                            200.00       240.00        190.0       kg/yr Milk                               170.00       200.00        110.0        1/yr Meat & Poultry                      37.00        59.00         95.0       kg/yr Fish                                 2.20         5.20          6.9       kg/yr Seafood                              0.33         0.75          1.0       kg/yr Drinking water                     260.00       260.00        370.0        1/yr Shoreline recreation                 9.50        47.00          8.3       hr/yr Inhalation                        2700.00      5100.00       7300.0       m3/yr External Exposure from Deposited Airborne Radio- active Materials                  8760.00      8760.00       8760.0       hr/yr Consumption rate obtained from Reference 3 of Appendix A and age-prorated using techniques in Reference 4 of Appendix A.

Data obtained directly from Reference 4 of Appendix A.

Data obtained directly from Reference 15 of Appendix A.

1.109-64 i

where Cd pathway p, is the average concentration over subregion d of the nuclide iforin models Cdip in pCi/kg or pCi/liter (see Appendices A and C of this guide and equations for calculation of pathway concentrations); 

             C ip         is the 50-mile average concentration of nuclide i in pathway p,    in Cip        pCi/kg or pCi/liter;
               t          is the transport time of the food medium p through the distribution system, p        in days (Tahle D-2 presents estimates of the transport times that may be used in lieu of site-specific data);
             vd           is the annual mass or volume of food medium p produced in subregion d, Vdp        in kg or liters;
               V          is the mass or volume of the food medium p produced annually with the p'       50-mile radius about the site, in kg or liters; 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 = Vp/X Uapfa                                                                      (0-3)

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

               P          is the estimated population that can be served by the quantity of food p p        likely to be produced within 50 miles of the site;
             Ua           is the use or consumption factor of food medium p for the average Uap        individual in age group a, in kg/yr or liters/yr (taken from Table 0-1);
                          and V          is the annual mass or volume of food medium p likely to be produced within a 50-mile radius about the site, in kg or liters.

The annual population-integrated dose is then calculated as 

          ?~O~
                 DiP= .Ol Z p
                   0.001      P  1 *.*faýCipUapDai(-4
                                          8 *U   ODF.                                           (0-4)

where P if Pp < P5 Pp p P50 if Pp > Ps and DFai is the dose factor for age group a and nuclide i, in mrem/pCi (taken from Tables A-3 to A-7 and C-1 to C-4); 

                                                      1.109-65

TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD 

                             DISTRIBUTION SYSTEMT
     FOOD MEDIUM                               DISTRIBUTION TRANSPORT TIME (in days)

Fruits, grains, and vegetables 14 Milk 4 Meat and poultry 20 Sport fish 7 Commercial fish 10 

                                                               IO

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

1.109-66 

                                                                                     4

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

               Pp       is the population consuming food medium p; and P5 0      is the total population within 50 miles.

All other factors are as defined above.

Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50. In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D). Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.

2. Use of the Models a. Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq- uid effluents should be evaluated for the following principal pathways: potable water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri- gated with water that has received the liquid effluent. In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant* contribution to the annual dose received by an exposed population group.

(1) Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump- tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application. The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose. The formulation expressed in Equation (D-1) may be used.

The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1. The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.

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

           Pw = v/c                                                                          (D-5)

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

               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 (0-5). 

 For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here. Any pathway so identified should then be evaluated by a model similar to that used above.

1.109-67

The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle. This population may be pro-rated to include only the population within the 50-mile radius. Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius.

Such exposed population should be included in the 50-mile population dose evaluation.

(2) Doses from Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions. The mixing ratio (or dilution) should be evaluated for each sub- region using an appropriate hydrological model. For sport harvests, the entire edible harvest is assumed to be ingested by the population within 50 miles. The formulation expressed by Equation (D-4) should be used with the population Pp given by the results of Equation (D-3). The age-specific ingestion factors of Table D-I may be used in lieu of site-specific data.

For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with Vp as the total estimated U.S. commercial harvest of the aquatic food medium p. The annual population-integrated dose is then computed using Equation (D-4) with Pp = PSO" The age-specific factors of Table 0-1 may be used in lieu of site-specific data.

(3) Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by sunmming the product of the individual doses in each subregion and the population exposed therein. All subregions within the 50-mile radius should be considered where existing or designated recreational facili- ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The formulation of Equation (D-1) is appropriate.

(4) Doses from Consumption of Terrestrial Food Products Irrigated by Waters Receiving the Liquid Effluent The annual population-integrated total body and thyroid doses from consumption of food irrigated with water from the body receiving the liquid effluent are evaluated following the procedures outlined in the development of Equation (0-4). Note that the term Vp of Equations (0-2) and (D-3) denotes the total production of food medium p within 50 miles, not just the total production of irrigated food medium p. The consumption rate data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4). 

     b.   Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and vegetation), and external irradiation from activity deposited on the ground.    In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant contribution to the annual dose received by an exposed population group. (See Regulatory Position C.1 of this guide.)
          For the evaluation of exposures from atmospheric releases, the 50-mile region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE, etc.)

and annuli at distances of 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 miles from the center of the facility. The atmospheric dispersion factors (x/Q') or similar factors should be evaluated at the radial midpoint for each of the subregions using appropriate atmospheric dispersion models such as those described in Regulatory Guide 1.111.

(1) Doses due to Exposure to Noble Gases The annual population-integrated total body dose due to noble gas effluents should be evaluated by summing the products of the individual doses in each subregion and the population in each subregion. Equation (D-1) may be used. For external exposure, the model does E not differentiate between age groups. A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.

1.109-68

(2) Doses due to Inhalation of Radlolodines and Particulates The annual population-integrated total body and thyroid doses from inhalation of airborne effluents should be evaluated by summing the products of the individual doses received in each subregion and the population in each subregion. Equation (D-1) may be used.

The age-specific inhalation rates of Table D-1 may be used with the data of Tables C-l to C-4.

(3) Doses due to Ingestion of Terrestrial Food Products The annual population-integrated total body and thyroid doses from ingestion of terrestrial food products should be evaluated using the production data for each subregion.

For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-1, D-2, and A-l to calculate population doses.

(4) Doses due to External Irradiation from Activity Deposited o' the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-7.

REFERENCE FOR APPENDIX D "Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Commerce, 1975.

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